ML18066A421
| ML18066A421 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/23/1999 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18066A420 | List: |
| References | |
| NUDOCS 9903300283 | |
| Download: ML18066A421 (191) | |
Text
{{#Wiki_filter:** ENCLOSURE CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 1998 ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT 189 Pages
. PALISADES NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY - DECEMBER 1998 This report provides information relating to radioactive effluent releases and solid radioactive waste shipments at the Palisades Nuclear Plant during the period of January 1, 1998 through December 31, 1998. The report is required by 10 CFR 50.36a(a)(2) and Plant Technical Specification 6.6.3. The report format is detailed in the Offsite Dose Calculation Manual (ODCM) Appendix A Plant Operating History Palisades went off line on February 6th to add oil to P-50C, repack P-10A and repair steam leak on M0-0510. Plant returned to service on February 9th. The Plant was taken off line at 24:00 on April 24th for refueling. The Plant was returned to service following the refueling outage on June 7th. The Plant was taken off line on June 9th for additional turbine balancing, and returned to service on June 10th. On July 21st the Plant was manually tripped off line due to a loss of "A" feedpump, and returned to service July 22nd. On December 13th Plant taken off line to repair leak on pump P-50D oil system and CRD-2. Upon startup P-50A seal failed and Plant remained out of service for the remainder of 1998 .
- Supplemental Information A Batch Releases Information relating to batch release of gaseous and liquid effluents is provided in Attachment 1.
B. Abnormal releases None C. Lower Limits of Detection (LLD's) for gaseous and liquid effluents are provided in Attachment 5. 1
D. Radioactive Effluent Monitoring Instrumentation:
- 1. Steam Generator Slowdown Effluent Line (RIA 0707), Out of Service For 119 days.
The ODCM, Appendix A, Table C-1 requires that when a radioactive liquid effluent monitoring instrument channel becomes inoperable, best efforts must be made to return the instrument to operable status within 30 days and, if unsuccessful, report the incident in the next Radioactive Effluent Release Report. The ODCM, Appendix A, Table C-1 further stipulates that effluent releases via this pathway may continue to be made with less than the required amount of operable channels providing that, at least once per 24 hours, grab samples are collected and analyzed for radioactivity for principle gamma emitters and 1-131. On September 3, 1998 RIA-0707 was declared inoperable due to a failure of its associated Low Leve*1 Alarm (FIS 2328) to function (annunciation in control room) during performance of the quarterly functional test. On September 4, 1998 found FIS 2328 photo sensor lens in the flow tube had failed, with no replacement part in stock. On October 10, 1998 photo sensor lens was determined to be obsolete, and Engineering Assistance Request EAR-98-0661 to replace obsolete photo detector was initiated. Replacements parts located and will be installed per WO# 284714. Replacement parts installed, system tested and declared operational on February 24, 1999. During this period of inoperability, RIA-0707 remained functional. Flow through the monitor was maintained and monitored. Automatic isolation trip functions, alert and alarm annunciations and check source response were verified. The Steam Generator Slowdown Effluent Line, RIA-0707 is normally operated as a closed-loop system, and not as an effluent pathway. During the period of inoperability, the system was not operated as an effluent pathway, hence the 24 hour grab samples/analysis were not necessary.
- 2. Gaseous Effluents Attachment 2 lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 9.56E-05% of the total release .
- Gaseous effluents released during 1998 were up slightly (30%) from that of the previous year. Once again fuel integrity over cycle 13/14 remained stable.
2
- 3. Liquid Effluents
- Attachment 3 lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 6.73E-05 % of the total release.
Overall liquid effluents released during 1998 were slightly lower (36%) than those of 1997. 1998 liquid release volumes were lower than those of 1997, accounting for this reduction.
- 4. Solid Waste Attachment 4 summarizes all solid radwaste classification, sources, volume shipped, curie and nuclide content. All radwaste shipments were made to Barnwell Waste Management Facility in Barnwell, South Carolina.
- 5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The quarterly values for curies released were input for each nuclide and summarized as follows:
A. The offsite air doses at the site boundary (0.48 SSE) due to noble gases were: First Quarter - 8.95 E-04 millirad beta and 3.05 E-04 millirad gamma Second Quarter - 4.80 E-04 millirad beta and 1.64 E-04 millirad gamma Third Quarter - 2.82 E-04 millirad beta and 9.51 E-05 millirad gamma Fourth Quarter - 2.72 E-04 millirad beta and 9.22 E-05 millirad gamma The maximum noble gas offsite air dose to the nearest residence (0.50 mi S) for beta and gamma occurred during the first quarter, being 5.82 E-04 millirads beta and 2.01 E-04 millirads for gamma. B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases were: First Quarter - 3.41 E-03 mil Ii rem (child thyroid) Second Quarter - 9.44 E-03 millirem (child bone) Third Quarter - 4.06 E-03 millirem (child thyroid) Fourth Quarter - 4.00 E-03 millirem (child thyroid) 3 L _ __ _
C. Integrated total body doses to the general population and average doses to individuals within the population from gaseous effluent release pathways to a distance of 50 miles from the site boundary were: First Quarter - 1.02 E-02 person-Rem and 8.79 E-06 millirem Second Quarter- 2.50 E-02 person-Rem and 2.16 E-05 millirem Third Quarter - 1.26 E-02 person-Rem and 1.09 E-05 millirem Fourth Quarter - 1.26 E-02 person-Rem and 1.09 E-05 millirem. D. The maximum total body dose to an individual in unrestricted water-related exposure pathways was: First Quarter - 7.12 E-04 millirem (adult) Second Quarter- 2.51 E-03 millirem (adult) Third Quarter - 5.19 E-04 millirem (adult) Fourth Quarter - 1.99 E-07 millirem (adult). The maximum organ doses were: First Quarter - 1.04 E-03 millirem (teenage liver) Second Quarter- 4.11 E-03 millirem (teenage liver) Third Quarter - 7.42 E-04 millirem(teenage liver) Fourth Quarter - 1.99 E-07 millirem (adult) The calculated organ dose for the fourth quarter was the same value as whole body for all organs, since the only isotope released in this quarter was tritium. E. Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent release pathways to a distance of 50-miles from the site boundary were: First Quarter - 3.06 E-03 person-Rem and 2.64 E-06 millirem Second Quarter- 1.02 E-02 person-Rem and 8. 79 E-06 millirem Third Quarter - 2.25 E-03 person-Rem and 1.94 E-06 millirem Fourth Quarter - 2.28 E-06 person-Rem and 1.97 E-09 millirem. 4
Process Control Program (PCP) There was no revision to the Process Control Program in 1998.
- 7. Offsite Dose Calculation Manual (ODCM)
Attachment 6 contains the ODCM, Revision 12, along with the safety evaluation per the requirements of Technical Specification 6.5.1.c.3. There was one change to the ODCM as a result of using updated meterological data. The 5-year data from 1992-1996 replaced the data from the 1988-1992 time period, which is used to generate Table 1.3. There were also several changes to the ODCM during this reporting period as a result of use of the 1997 Land Use Survey. The land Use Survey is utilized to ensure that the impact of effluent dose is accurate. These changes (detailed in #'s 1-4 below) will maintain the level of radioactive effluent control required by 10 CFR 20.1301, 4 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and do not affect any monitor or release set point calculations. In addition Attachment 6 also contains Revision 7 to the ODCM Appendix A "Relocated
- Technical Specifications Per NRG Generic Letter 89-01 11 (TAC NO 75060). A change (detailed in# 5 below) was made to Section Ill K. This change does not effect radioactive effluent control, and does not effect any monitor or release set point calculations.
- 1) Update of Table 1.3, Palisades XOQDOQ82 Using 01/01/92 - 12/31/96 Met Data
- 2)
- Update of Table 1.4, 1997 Palisades Land Use Census
- 3) Update of Table 1.4a; 1997 Palisades Land Use Census - Critical Receptor Items
- 4) Update of Table 1.9; 1998 Palisades Gaseous Design - Objective Annual Quantities
- 5) Calculational methodology to ensure the <1000 EC limit is maintained in the SIRW or Temporary Liquid Storage Tanks was added to the Surveillance Requirement Section.
5
- ATTACHMENT 1 Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES January - December 1998 1 Page
TABLE HP 10.5-1 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT BATCH RELEASES January 1. 1998 to December 31. 1998 A. GASEOUS Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Number of Releases 2 10 6 2 Total Release Time Minutes 171 851 584 292 Maximum Release Time Minutes 86 143 161 147 Average Release Time Minutes 86 85 97 146 Minimum Release Time Minutes 85 49 53 145 B. LIQUID Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Number of Releases 1 2 1 0 Total Release Time Minutes 453 895 448 N/A Maximum Release Time Minutes 453 499 448 N/A Average Release Time Minutes 453 448 448 N/A Minimum Release Time Minutes 453 396 448 N/A
ATTACHMENT 2 Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January - December 1998 3 Pages
TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January 1. 1998 to December 31. 1998 Est Total A. FISSION AND ACTIVATION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Error %
- 1. Total release Ci l.26E+Ol 6.62E+OO 3.97E+OO 3.88E+OO
- 2. Average release rate for 14.7 period µCi/sec l.62E+OO 8.42E-01 5.00E-01 4.83E-01
- 3. Percent of annual avg EC % 7.03E-04 3.SOE-04 2.14E-04 2.0SE-04 B. IODINES
- 1. Total Iodine* Ci 5.61E-04 4.68E-04 4.53E-04 2.66E-04
- 2. Average release rate for 9.1 period µCi/sec 7.21E-05 5. 96E-05 5.69E-05 3.35E-05
- 3. Percent of annual avg EC % 3.29E-05 3. 96E-05 2.52E-05 1.79E-05 C. PARTICULATES
- 1. Particulates with half-life
> 8 days Ci 7.94E-06 3.93E-05 6.76E-06 5.74E-06 Average release rate for 25.5 period µCi/sec 1.02E-06 5.00E-06 8.52E-07 7.22E-07
- 3. Percent of annual avg EC % 3.35E-05 1.14E-04 2.67E-05 2.22E-05
- 4. Gross alpha radioactivity Ci 2.39E-06 1.42E-05 3.47E-06 6.14E-07 D. TRITIUM
- 1. Total Release Ci 2.69E+OO 6.50E+OO 3.55E+OO 3.59E+OO
- 2. Average release rate for period µCi/sec 3.46E-01 8.27E-01 4.47E-Ol 4.52E-Ol
- 3. Percent of* annual avg EC % 7.36E-04 1.76E-03 9.51E-04 9.62E-04 E.
- 1. Beta Airdose at Site Boundary Due to Noble Gases (ODCM App A III.C) mrads 8.95E-04 4.SOE-04 2.82E-04 2.72E-04
- 2. Percent limit % 8.95E-03 4.SOE-03 2.82E-03 2.72E-03
- 3. Gamma Airdose at Site Boundary Due to Noble Gases (ODCM App A III.C) mrads 3.05E-04 1.64E-04 9.51E-05 9.22E-05
- 4. Percent limit % 6. lOE-03 3.28E-03 l.90E-03 1. 84E-03 F.
Maximum Organ Dose to Public Based on Critical Receptors (ODCM App A III.D) mrem 3.41E-03 9.44E-03 4.06E-03 4.00E-03
- 2. Percent of limit % 4.55E-02 1.26E-01 5.41E-02 5.33E-02
- NOTE: Data is reported for I-131 and I-133 only.
TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE
- EFFLUENT REPORT GASEOUS EFFLUENTS January 1. 1998 to December 31. 1998
- 1. FISSION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Argon-41 Ci 2.28E-03 7.21E-04 <LLD <LLD Krypton-85 Ci <LLD 7.22E-02 1. 04E-02 <LLD Krypton-85m Ci 4.85E-04 1.27E-04 2.89E-04 2.18E-04 Krypton-87 Ci 1.32E-03 9.41E-04 <LLD 2.96E-04 Krypton-88 Ci <LLD <LLD <LLD <LLD Xenon-131m Ci <LLD 2.90E-02 1.12E-03 3.35E-03 Xenon-133 Ci 1.26E+Ol 6.44E+OO 3.95E+OO 3.82E+OO Xenon-133m Ci <LLD 8.83E-05 <LLD 6.67E-04 Xenon-135 Ci 7.02E-03 7.08E-02 3.17E-03 2.89E-03 Xenon-135m Ci 1. 47E-02 6.19E-03 8.22E-03 6.05E-03 Xenon-138 Ci 5.06E-03 1.21E-03 <LLD 1.39E-03 Total for Period Ci 1. 26E+Ol 6.62E+OO 3.97E+OO 3.83E+OO
- 2. IODINES Iodine-131 Ci 1.60E-04 2.49E-04 1.22E-04 1. OlE-04 Iodine-132 Ci <LLD 2.08E-03 <LLD <LLD Iodine-133 Ci 4.0lE-04 2.19E-04 3.31E-04 1. 65E-04 Iodine-134 Ci <LLD <LLD <LLD <LLD Iodine-135 Ci <LLD <LLD <LLD <LLD Total for Period Ci 5.61E-04 2.55E-03 4.53E-04 2.66E-04
TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE
- 3. PARTICULATES*
Manganese-54 Ci EFFLUENT REPORT Units 1st Qtr
<LLD 2nd Qtr
<LLD 3rd Qtr
<LLD 4th Qtr
<LLD Cobalt-58 Ci <LLD 1.16E-05 <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD <LLD <LLD Zinc-65 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 6.55E-07 8.25E-07 8.40E-07 8.35E-07 Strontium-90 Ci 4.20E-07 3.70E-07 4.75E-07 4.80E-07 Molybdenum-99 Ci <LLD <LLD <LLD <LLD Cesium-134 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD 1. 86E-06 <LLD <LLD Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD Net unidentified beta Ci 6.87E-06 2.47E-05 5.45E-06 4.43E-06 Total 7.94E-06 3.93E-05 6.76E-06 5.74E-06
- *Particulates with half-lives> 8 days.
ATTACHMENT 3 Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF RELEASES January - December 1998 2 Pages
TABLE HP 10. 5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT
- LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January 1. 1998 to December 31, 1998 A. FISSION AND ACTIVATION Est Total PRODUCTS Units Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Error %
- 1. Total release (not including tritium. gases.
alpha) Ci 4.09E-04 1.41E-03 2.55E-04 0.000
- 2. Average release rate for 10.3 period µCi /mQ 1.67E-11 7.61E-11 1. 02E-11 N/A
- 3. Percent of EC % 1. 65E-03 5.06E-03 1.0SE-03 N/A B. TRITIUM
- 1. Total Release Ci 3.22E+Ol 7.29E+Ol 2.50E+Ol 9.0SE-02
- 2. Average diluted concentration during period µCi /mQ l.31E-06 3.94E-06 9.96E-07 3.75E-09 4.01
- 3. Percent of EC % 1. 31E-01 3.94E-01 9. 96E-02 3.75E-04 ISSOLVED AND ENTRAINED GASES
- 1. Total Release Ci 0.000 0.000 0.000 0.000
- 2. Average diluted concentration during period µCi /mQ N/A N/A N/A N/A NIA
- 3. Percent of EC % N/A N/A N/A N/A D. GROSS ALPHA RADIOACTIVITY (Total Release) Ci 1. 75E-07 3.23E-07 4.22E-07 0.000 E. VOLUME OF WASTE RELEASED (Prior to Dilution) Liters 1. 25E+05 3.06E+05 1. 28E+05 0.000 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.45E+10 l.85E+10 2.51E+10 2.42E+10 G. MAXIMUM DOSE COMMITMENT -
WHOLEBODY mrem 7.12E-04 2.51E-03 5.19E-04 l.99E-07 Percent of ODCM App A III.H limit % 4.75E-02 l.67E-01 3.46E-02 1.33E-05 H. MAXIMUM DOSE COMMITMENT - RGAN mrem l.04E-03 4.llE-03 7.42E-04 1.99E-07 Percent of ODCM App A III.H limit % 2.0SE-02 8.22E-02 1.48E-02 3.98E-06
TABLE HP 10.5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT
- LIQUID EFFLUENTS January l, 1998 to December 31, 1998
- 1. NUCLIDES RELEASED Units Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Manganese-54 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci 2.46E-05 5.08E-05 <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci 6.23E-05 5.67E-04 3.37E-05 <LLD Zirconium-95 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 3.25E-07 9.89E-07 2.94E-07 <LLD Strontium-90 Ci 1.15E-06 2.47E-06 1. OlE-06 <LLD
- Molybdenum-99 Iodine-131 Cesium-134 Ci Ci Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 3.33E-05 1.23E-04 3.68E-05
<LLD
<LLD
<LLD Cesium-137 Ci 2.32E-04 6.02E-04 1.51E-04 <LLD Niobium-95 Ci <LLD <LLD <LLD <LLD Sil ver-llOm Ci <LLD <LLD <LLD <LLD Antimony-125 Ci <LLD 6.32E-05 <LLD <LLD Net unidentified beta Ci 5.52E-05 0.000 3.24E-05 0.000 Fission &Activation Product Total Ci 4.09E-04 1.41E-03 2.55E-04 0.000
- Tritium Grand Total Ci Ci 3.22E+Ol 7.29E+Ol 2.50E+Ol 9.08E-02 3.22E+Ol 7.29E+Ol 2.50E+Ol 9.08E-02
ATTACHMENT 4 Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE January - December 1998
- 1 Page
SOLID WASTE
- Waste Source of January 1. 1998 To December 31. 1998 Solidification Container Volume *Total *Principal Class Waste Agent Type <cu ft) Curies Radionuclides AU DAW N/A LSA 236.3 0.3 Co-60. Cs-137.
Co-58, Cs-134. Mn-54. Fe-55, Ni-63 AS DAW N/A HIC 195.7 3.9 Same as above AU Evap Bottoms Asphalt LSA 46.4 0.2 Co-60, Cs-137. Co-58. Cs-134. Mn-54. Fe-55, Ni-63. Sb-125 AS Evap Bottoms N/A HIC 256.0 0.5 Same as above
- B Resins N/A HIC 202.1 27.0 Co-60, Cs-137, Co-58, Cs-134, Ag -11 Om , Ni -63 ,
Fe-55. Sb-125 c Irr Hardware N/A Steel 14.6 117. 7 Co-60, Co-58, Liner Mn-54, Fe-55, Ni-63 AS Filters N/A HIC 205.8 8.2 Co-60, H-3, Sr-90, Ni-63, Cs-137, Fe-55, B Filters Cement Steel 360.0 0.5 Co-60. Cs-134, Liner Cs-137, Ni-63, Fe-55, Sr-90
- TOTAL 1516.9 158.3
*NOTE: Gamma isotopes are measured quantities; all other isotopes are estimated.
ATTACHMENT 5 Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS January - December 1998
- 1 Page
_________________ J
- LOWER LIMITS OF DETECTION (LLDs) FOR PALISADES EFFLUENTS Gaseous Effluents Nuclide LLD (uci/cc)*
Cr-51 1.50E-13 Mn-54 1.56E-14 Co-58 1.47E-14 Fe-59 5.33E-14 Co-60 4.88E-14 Stack Gas Analysis Zn-65 3.80E-14 98-025-St Se-75 2.10E-14 Nb-95 2.94E-14 Zr-95 2.68E-14 Mo-99 1.14E-13 Sb-125 4.56E-14 1-131 1.73E-14 1-133 2.34E-14 Cs-134 2.44E-14 Cs-137 2.19E-14 Ce-141 1.98E-14 Ce-144 8.26E-14 Liquid Effluents Nuclide LLD (uci/I)** Mn-54 1.16E-07 Fe-59 1.73E-07 Co-58 2.24E-07 Co-60 8.77E-08 Zn-65 2.51E-07 Liquid Batch Release Mo-99 6.11 E-07 98-005-R 1-131 1.36E-07 98-012-R Cs-134 1.27E-07 Cs-137 1.06E-07 Ce-141 1.55E-07 Ce-144 6.87E-07
- From a typical Stack release analysis.
** From a typical Liquid release analysis.
- ATTACHMENT 6 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT
- OFFSITE DOSE CALCULATION MANUAL
- 171 Pages
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 Table of Contents I. GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 A. ALARM/TRIP SETPOINT METHOD . . . . . . . . . . . . . . . . . . . 1
- 1. Allowable Concentration . . . . . . . . . . . . . . . . . . . 1
- 2. Monitor Response . . . . . . . . . . . . . . . . . . . . . . . . 2 B. DOSE RATE CALCULATION . . . . . . . . . . . . . . . . . . . . . . . . 3 C. DESIGN OBJECTIVE QUANTITY (DBQ) LIMITS ON BATCH AND CONTINUOUS RELEASES . . . . . . . . . . . . . . . . . . . . . 20
- 1. Batch Releases . . . . . . . . . . . . . . . . . . . . . . . . . 20
- 2. Continuous Releases . . . . . . . . . . . . . . . . . . . . . 20
- 3. Exceeding DBQ Limits . . . . . . . . . . . . . . . . . . . . 20
- 4. Releasing Radionuclides Not Listed in Table 1 .9 .. 21 D. OPTIONAL QUARTERLY DOSE CALCULATIONS . . . . . . . . . 21
- 1. Methodology for Optional Quarterly Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION 24
- 1. System Description . . . . . . . . . . . . . . . . . . . . . . 24
- 2. Determination of Satisfactory Operation . . . . . . . . 25 F. RELEASE RATE FOR OFFSITE EC (50 mrem/yr) . . . . . . . . . 25 G. PARTICULATE AND IODINE SAMPLING . . . . . . . . . . . . . . 26 H. NOBLE GAS SAMPLING . . . . . . . . . . . . . . . . . . . . . . . . . 27 I. TRITIUM SAMPLING . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 J. FIGURES AND TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . 28
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 Table of Contents II. LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67 A. CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67
- 1. Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . 67
- 2. Prerelease Analysis . . . . . . . . . . . . . . . . . . . . . . 6 7
- 3. Effluent Concentration (EC) - Sum of the Ratios .. 68 B. INSTRUMENT SETPOINTS . . . . . . . . . . . . . . . . . . . . . . . . 69
- 1. Setpoint Determination . . . . . . . . . . . . . . . . . . . 69
- 2. Composite Samplers . . . . . . . . . . . . . . . . . . . . . 69
- 3. Post-Release Analysis . . . . . . . . . . . . . . . . . . . . 70 C. DOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70
- 1. RETS Requirement . . . . . . . . . . . . . . . . . . . . . . . 70
- 2. Release Analysis . . . . . . . . . . . . . . . . . . . . . . . . 70 D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT . . . . . . 75 E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr) . . . . . . . . . 76 F. FIGURES AND TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . 77 Ill. URANIUM FUEL CYCLE DOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 A. SPECIFICATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 B. ASSUMPTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 C. DOSE CALCULATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Appendix A, "Relocated Technical Specification" Appendix B, "Request to Retain Soil in Accordance With 10 CFR 20.302"
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- I. GASEOUS EFFLUENTS Revision 12 A. ALARM/TRIP SETPOINT METHOD Appendix A, Section 111.B.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and For iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. Appendix A, Section 111.A.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged over 1 hour, will not be greater than Appendix A, Section 111.B.1. This section of the ODCM describes the methodology that will be used to determine these setpoints. The methodology for determining alarm/trip setpoints is divided into two major parts. The first consists of calculating an allowable concentration for the nuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors.
- 1. Allowable Concentration The total EC-fraction (Rk) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 1 0 CFR 20:
-(xi RCk> - Q (F) I:i (1 . 1 )
- 1
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- where:
Revision 12 Actual or measured concentration, at ambient temperature and pressure of nuclide i (µCi/cc) The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 = 50 mrem/yr - total body The total EC-fraction for release point k X/Q = Most conservative sector site boundary dispersion (sec/m 3 ) - Table 1.3 F = Release flow rate (83,000 cfm = 39.2 m 3 /sec) for stack monitor considerations; variable for other monitors NOTE: If a batch release is made while a continuous release or another batch release is in progress, the sum of all values of Rk must be less than 10.0.
- 2. Monitor Response Normal radioactivity releases consist mainly of well-decayed fission gases. Therefore, monitor response calibrations are performed to fission gas typical of normal releases (mainly Xe-133). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-133, however.
Monitor response for the two categories of monitor is determined as follows:
- a. Normal Release (aged fission gasses)
Total gas concentration (µCi/cc) at the monitor is calculated. The calibration curve or constant for cpm/µCi/cc) is applied to determine cpm expected. The setting for monitor alarms is established at some factor (b) greater than 1 but less than 1 /Rk (Equation 1.1) times the measured concentration (c): s =bx c ( 1 .2) . 2
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- b.
Revision 12 Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions. These setpoints are established in accordance with Emergency Plan requirements for defining Emergency Action Levels and associated actions. Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between cpm and µCi/cc (or R/hr and µCi/cc), depending on monitor type, for fission product mixtures as a function of mixture decay time. When these monitors are utilized for other than accident conditions, either an appropriately decayed "accident" conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, setpoints are established as in 1 .A above. Setpoints of accident monitors (if set to monitor normal releases) are reset to the accident alarm settings at the end of normal release. Setpoints of other release monitors are maintained at the level used at the latest release (well below the level which would allow 1 0 times EC to be exceeded at the site boundary), or are reset to approximately three times background in order to detect leakage or inadvertent releases of low level gases. B. DOSE RATE CALCULATION
- 1. Dose rates are calculated for (1) noble gases and (2) iodines and particulates. Dose rates as defined in this section are based on 10 CFR 50 Appendix I limits of mrem per quarter and mi Iii rem per year. All dose pathways of major importance in the Palisades environs are considered.
- a. Equations and assumptions for calculating doses from noble gases are as follows:
- 1) Assumptions a) Doses to be calculated are the maximum offsite point in air, total body and skin.
3
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- b)
Revision 12 Exposure pathway is submersion within a cloud of noble gases. c) Noble gas radionuclide mix is based on the historically observed source term given in Table 1.1, plus additional nuclides. d) Basic radionuclide data are given in Table 1.2. e) All releases are treated as ground-level. f) Meteorological data expressed as joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the period resulting in X/Q's and D/O's shown in Table 1.3. g) Raw meteorological data consists of wind speed and direction measurements at 1 Om and temperature measurements at 1 Om and 60m. h) Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist (overland sector site boundaries), and nearest residents. i) Potential maximum population (resident) exposure points are identified in Table 1 .4. j) A semi-infinite cloud model is used. k) For person exposures, credit is taken for shielding by residence (factor of 0. 7). I) Radioactive decay is considered for the plume. m) Building wake effects on effluent dispersion are considered .
- n) A sector-average dispersion equation is used.
4
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- o)
Revision 12 The wind speed classes that are used are as follows: Wind Speed Class Number Range (m/s) Midpoint (m/s) 1 0.0-0.4 0.2 2 0.4-1.5 0.95 3 1.5-3.0 2.25 4 3.0-5.0 4.0 5 5.0-7.5 6.25 6 7.5-10.0 8.75 7 > 10.0 p) The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A= 1 , 8=2, ... , G=7. q) Terrain effects are not considered.
- 2) Equations To calculate the dose for any one of the exposure points, the following equations are used.
For determining the air concentration of any radionuclide: g 7
~=I: I:
j=f Iv=/ ( 1 .3) where:
= Air concentration of radionuclide i, µCi/m 3 *
= Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
5
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12
= Average release rate of radionuclide i, µCi/s.
p = Fraction of radionuclide remaining in plume.
= Vertical dispersion coefficient for stability class k (m).
u* J = Midpoint value of wind speed class interval j, m/s. x = Downwind distance, m. n = Number of sectors, 16.
= Radioactive decay coefficient of radionuclide i, s- 1
- 2nx/n = Sector width at point of interest, m.
For determining the total body dose rate: Q) (§aJ = :E,; mi SB&ai ( 1 .4) where: DTB Total body dose rate, mrem/y. Air concentration of radionuclide I,
µCi/m 3 .
Total body dose factor due to gamma radiation, mrem/y per µCi/m 3 (Table 1 .5). For determining the skin dose rate: Q)' = ~ BJ, (Q)c.S3&; + 1.ff Q)c.S3~
- 6
( 1 .5)
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 where: Ds = Skin dose rate, mrem/y. xi = Air concentration of radionuclide i, µCi/m 3 DFSi = Skin dose factor due to beta radiation, mrem/y per µCi/m 3 (Table 1.5). 1.11 = The average ratio of tissue to air energy absorption coefficients, mrem/mrad. Gamma-to-air dose factor for radionuclide i, mrad/y per µCi/m 3 (Table 1 .5). For determining dose rate to a point in air: ( 1. 6) where: Air dose rate, mrad/yr. Air dose factor for beta radiation (Table 1 .5).
- b. Equations and assumptions for calculating doses from radioiodines and particulates are as follows:
- 1) Assumptions a) Dose is to be calculated for the critical organ, thyroid, and the critical age groups (adult, teen, child, infant), infant (milk) and child (green, leafy vegetables).
b) Exposure pathways from iodines and particulates are milk ingestion, ground contamination, green leafy vegetables from home gardens, and inhalation. 7
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- c)
Revision 12 The radioiodine and particulate mix is based on the historically observed source term given in Table 1.1. d) Basic radionuclide data are given in Table 1 .2. e) All releases are treated as ground-level. f) Mean annual average X/Q's are given in Table 1.3. g) Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 1 Om and temperature measurements at 1 Om and 60m. h) Dose is to be evaluated at the potential offsite exposure points where maximum doses to man are expected to exist. i) Real cow, goat and garden locations are considered. j) Potential maximum exposure points (Table 1.4) considered are the nearest cow, goat; and home garden locations in each sector. k) Terrain effects and open terrain recirculation factors are not considered. I) Building wake effects on effluent dispersion are considered. m) Plume depletion and radioactive decay are considered for air-concentration calculations. n) Radioactive decay is considered for ground-concentration calculations .
- o) Deposition is calculated based on the curves given in Figure 1 .2.
8
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- p)
Revision 12 Milk cows and goats obtain 100% of their food from pasture grass May through October of each year. Use default values of 0.58 for cows and 0.67 for goats for fraction of year on pasture. q) Credit is taken for shielding by residence (factor of 0. 7).
- 2) Equations To calculate the dose for any one of the potential maximum-exposure points, the following equations in Section 1 .2.2 are used.
a) Inhalation Equation for calculating air concentration, Xi is the same as in the Noble Gas Section (Equation 1.3). For determining the organ dose rate: sg,; = 1a;10° I:i BJ. S9r53Q}-. aJSZ6 ( 1 . 7) where:
= Organ dose rate due to inhalation, mrem/y.
Xi Air concentration of radionuclide i,
µCi/m 3 .
DFli Inhalation dose factor, mrem/pCi (Table 1. 7). BR = Breathing rate 1400 m 3 /y infant; 3700 m 3 /y child; or 8000 m 3 /y teen and adult . 1x10 6 = pCi/µCi conversion factor. 9
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 b) Ground Contamination For determining the ground concentration of any nuclide; 7
&>, = s.1s a; 10" L 1>=1 where:
= Ground concentration of radionuclide i, µCi/m 2
- k = Stability class.
= Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction.
= Average release rate of radionuclide i, µCi/s.
DR = Relative deposition rate, m- 1 (Fig 1.2). x = Downwind distance, m. n = Number of sectors, 16. 2nx/n = Sector width at point of interest, m.
= Radioactive decay coefficient of radionuclide i, y- 1 *
= Time for buildup of radionuclides on the ground, 15 y .
3.15x10 7 = s/y conversion factor. 10
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- io-3 Revision 12 Figure 1.2 Corrected January 1977 i
I I I:\ I
.I :
~ t'-........ ..
I io-4 a:
- ~
... i i
w I- l w
~
a: w a. w I- "' '-. I'
<[
a: ~ fillli,_ z 10-5 0 j:: u; - ...... 2w I' Q w ~~
> ~
i=
<[
LU a:
""' ~~
I 10-S ~........ I I I I I !
- l ;
I I io-7 II 1111 I I ; 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) Figur* 7. Rtlltive Deposition for Ground Level R*leuH (All Atmospheric Stability Classes)
- n - -- ,...
11
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 For determining the total body or organ dose rate from ground contamination:
c!J. ShSEc!J. (1 .9) where:
= Dose rate due to ground contamination, mrem/y.
= Ground concentration of radionuclide i, µCi/m 2
- Dose factor for standing on contaminated ground, mrem/h per pCi/m 2 (Table 1 .8).
8,760 = Occupation time, h/y. 1x106 = pCi/µCi conversion factor. 0.7 = Shielding factor accounting for a distance of 1.0 meter above ordinary ground, dimensionless. c) Milk and Vegetation Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation:
'.(;'§)} =
- J,6'00 L 7
i=f
!,; ~ S!J!l6
{2rta;/~ (,,ft-ea:;. (-/..:ef)/ a;:, A~ ' + 1 -ea:;. OJJc£1A*. l (-/../// [tea:;.-(1..//~ ( 1 . 1 0) where: Concentration of radionuclide i in and on vegetation, µCi/kg. k = Stability class. 12
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 fk = Frequency of this stability class and wind direction combination, expressed as a fraction.
Qi = Average release rate of radionuclide i, µCi/s. DR = Relative deposition rate, m- 1 (Figure 1 .2). x = Downwind distance, m. n Number of sectors, 16. 2nx/n = Sector width at point of interest, m. r = Fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates). AEi Effective removal rate constant, AEi = Ai + Aw, where Ai is the radioactive decay coefficient, h- 1 , and Aw is a measure of physical loss by weathering (Aw = 0.0021 h-). te - Period over which deposition occurs, 720 h. Yv = Agricultural yield, 0. 7 kg/m 2 . Biv = Transfer factor from soil to vegetation of radionuclide i (Table 1.6). Ai Radioactive decay coefficient of radionuclide i, h- 1 *
- tb 13
= Time for buildup of radionuclides on the ground, 1.31x105 h (15Y).
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 p = Effective surface density of soil, 240 kg/m 2
- 3,600 = s/h conversion factor.
= Holdup time between harvest and consumption of food (2, 160 hours for stored food).
For determining the concentration of C-14 in vegetation:
'(;WII/ = 1 a; 1r! BJII/ (o.1110.16)
(1.11) where: Concentration of C-14 in vegetation, µCi/kg. Air concentration of C-14, µCi/m 3
- 0.11 = Fraction of total Plant mass that is natural carbon.
0.16 = Concentration of natural carbon in the atmosphere, g/m 3
- 1x103 = g/kg conversion factor.
For determining the concentration of H-3 in vegetation: (1 .12) where: CVT Concentration of H-3 in vegetation,
µCi/m 3 .
Air concentration of H-3, µCi/m 3 . 0.75 = Fraction of total Plant mass that is 14
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 water.
0.5 Ratio of tritium concentration in Plant water to tritium concentration in atmospheric water. H = Absolute humidity of the atmosphere, g/m 3
- 1x103 = g/kg conversion factor.
For determining the concentration of any nuclide in cow's or goat's milk: ( 1. 13) where: Concentration of radionuclide i (including C-14 and H-3) in milk,
µCi/Q.
CVi Concentration of radionuclide i in and on vegetation, µCi/kg. Transfer factor from feed to milk for radionuclide i, d/Q (Table 1.6). Amount of feed consumed by the milk animal per day, kg/d (cow, 50 kg/d or goat 6 kg/d). Ai = Radioactive decay coefficient of radionuclide i, d- 1
- Transport time of activity from feed to milk to receptor, 2 days .
- 15
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 For determining the organ dose rate from ingestion of green leafy vegetables and milk:
SD = I a; 10° Li ~~SD&". i Qt~ ( 1 . 14) where: D = Organ dose rate due to ingestion, mrem/y. Concentration of radionuclide i in vegetables or milk, µCi/kg (or liters). Ingestion dose factor, mrem/pCi (Table 2.1 ). UM Ingestion rate for milk, 330 Vy; for vegetables 26 kg/yr (child), no ingestion by infant. 1x106 = pCi/µCi conversion factor. d) Meat Ingestion (Beef) To calculate the concentration of a nuclide in animal flesh: (1.15) where: Concentration of nuclide i in the animal flesh, pCi/kg. Fraction of animal's daily intake which appears in each kg of flesh, days/kg (Table 1.6). Concentration of radionuclide i in the animal's feed (Equation 1.10). 16
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12
= Amount of feed consumed by the cow per day, 50 kg/d.
= Average time from slaughter to consumption, 20 days.
To determine the organ dose from ingestion of beef: ( 1 . 1 6) where:
= Ingestion dose factor for age group, mrem/pCi (Table 2.1) for nuclide i.
= Ingestion rate of meat for age group, kg/y (child-41, teen-65, adult-11 0).
e) Organ Dose Rates For determining the total body and organ dose rate from iodines and particulates: ( 1 . 1 7) where: D = Total organ dose rate, mrem/y.
= Dose rate due to inhalation, mrem/y.
= Dose rate due to ground contamination, mrem/y.
= Dose rate due to milk ingestion, mrem/y.
17
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12
= Dose rate due to vegetable ingestion, mrem/y.
= Dose rate due to beef ingestion, mrem/y.
- 3) The maximum organ dose rate, maximum total body dose rate, and maximum skin dose rate calculated in the previous section (Sec l.B) are used to calculate design basis quantities as described in Section l.B.1 .3.
- c. Design Basis Quantities The design basis quantity of a radionuclide emitted to the atmosphere is the amount of that nuclide, when released in one year, which would result in a dose not exceeding any of the following:
- 1) 1 5 millirem to any organ of an individual from iodines and particulates with half-life greater than 8 days (Appendix A, Section 111.D.1).
- 2) 1 5 millirem to skin of an individual from noble gas (Appendix A, Section 111.C.1 .b).
- 3) 5 millirem to the total body of an individual from noble gas (Appendix A, Section 111.C.1.a).
Design basis quantity (Ci) is the smallest value for each nuclide, calculated by dividing the dose limits (a through c above) by the appropriate dose calculated from the amount of radionuclide (Ci) used to conservatively estimate the doses of Section D, as listed in Table 1 .1 (or a hypothetical 1 Ci/year); the result is then multiplied by the amount' 6f radionuclide used. ( 1 . 1 8) where:
= Appendix I dose limit (mrem or mrad).
18
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 Calculated dose (mrem or mrad}.
Quantity of nuclide resulting in dose Dc (Ci}. DBQ = Design Basis Quantity (Ci}. The limiting values for Design Basis Quantities for radionuclides released to the atmosphere are given in Table 1.9. The inverse of the ratio Cc/Dc in the above equation (ie, Dc/Cc} is a useful value, since it represents the most limiting dose per unit quantity of each nuclide released. Use of the Dc/Cc ratio in quarterly evaluation of offsite dose is discussed in Section D. Values of DJCc are given in Table 1 .9.
- d. Land Use Census and DBQ Changes Appendix A, Sections J.3.b and J.3.c describe the requirements for an annual land use census and revision of the ODCM for use in the following calendar year. Areas of the ODCM which will be reviewed, and changed if appropriate, are Table 1.4 (Land Use Census Data by Sector), Table 1 .4a (Critical Receptors), and Table 1 .9 (Gaseous Design Basis Objective Annual Quantities}.
Changes will be effective on January 1 of the year following the year of the survey.
- e. Gaseous Releases From the Steam Generator Slowdown Vent and Atmosphere Release Valves Releases from the steam generator blowdown vent and atmospheric relief valves are difficult to quantify as there are no sampling capabilities on these steam release systems.
However, neither system is a normal release path. The steam generator blowdown vent is normally routed to the main condenser and recirculated. Radioactive releases will be calculated by analyzing steam generator blowdown liquid and assuming that 1 00 percent of Noble Gases, 1 0 percent of the Iodines and 1 percent of the Particulates will be released to the environment in the steam phase. Volumes
- will be released to the environment in the steam phase.
Volumes will be calculated using water balances or alternate means as available. 19
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- c.
Revision 12 DESIGN OBJECTIVE QUANTITY (DBQ) LIMITS ON BATCH AND CONTINUOUS RELEASES
- 1. Batch Releases Prior to each batch release (waste decay tank release or Containment purge), the quantity of each nuclide identified is summed with the quantity of that nuclide released since the first of the current calendar year. The cumulative total for each nuclide then is divided by the design objective quantity for each nuclide (from Table 1.9), and the resultant fractions are summed in order to assure that the sum fraction of all nuclides does not exceed 1.0:
< 1.0
( 1 . 1 9) The amount in any calendar quarter should not exceed 0.5. This is checked by subtracting the value obtained at the end of the previous quarter from the value obtained from the cumulative total to date, including the batch to be released.
- 2. Continuous Releases Low level continuous releases from the vent gas collection header and other low level sources are totaled on a weekly basis and summed with any batch releases for the week in order to establish the cumulative DBQ fraction from batch plus continuous released for the year-to-date. Calculations are performed in the same manner as for batch releases described in C.1.
- 3. Exceeding DBQ Limits As discussed under 8.1.3, the DBQ is a very conservative estimate of activity which could give doses at Appendix I limits. Because different organs are summed together and doses to different people are summed, the DBQ typically overestimates dose by about a factor of five. Thus, if calculations of DBQ fraction exceed 1 .0 for year-to-date or 0.5 for the quarter, technical specifications probably still would not be exceeded. However, further discretionary releases should be deferred until an accurate assessment of dose is made by use of GASPAR computer code or by analysis of appropriate release data via the segment gaussian dose model used in emergency planning (inhalation dose, total body external dose, and boundary dose in air). See also Section D.1.2.
20
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 It should be noted that Palisades Plant to date (based on review of semiannual effluent data) has never exceeded the annual or quarterly DBQ fraction, despite its conservatism. Thus, it is not expected that an alternate to the DBQ method will be required
- unless the Plant is in a significantly off-normal condition.
- 4. Releasing Radionuclides Not Listed in Table 1 .9 Table 1 .9 contains all nuclides identified to date as routine constituents of gaseous releases at Palisades Plant, plus those common to PWRs in general, even if not previously detected at Palisades. From time to time, however, other nuclides may be detected.
If the unlisted nuclide constitutes less than 1 0% of the EC-fraction for the release, and all unlisted nuclides total less than 25% of the EC-fraction, the nuclide may be considered not present. If the unlisted nuclide constitutes greater than 10% of the EC-fraction, or all unlisted nuclides together constitute greater than 25%, then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen, or particulate). Should a nuclide not listed in Table 1 .9 begin to appear in significant quantities on a routine basis, revision to this ODCM should be made in order to include a design basis quantity specific to that nuclide. D. OPTIONAL QUARTERLY DOSE CALCULATIONS
- 1. Methodology for Optional Quarterly Dose Calculations This option may be used in place of, or in addition to, the Design Basis Quantity (DBQ) fraction calculation described by Equation 1 .19. This optional conservative calculation relates the DBQ fraction to the doses from which it was originally derived.
Use of this method may assist in identification of the critical dose pathway or characteristics of the assumed critical individual (infant,
- child, teen, and adult), since Table 1 .9 indicates these parameters.
21
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- a.
Revision 12 Simplified Conservative Approach This method utilizes a limiting dose concept such that the limiting dose for each nuclide is summed with the limiting dose for each other nuclide, regardless if such sum is physically possible. It also assumes critical pathways, such as milk and vegetables, are in effect even in winter when the pathway is absent. As such, the method is highly conservative and significantly over-estimates dose. If limits appear to be exceeded by this method, Section D.1 .2 (a concise method, but requiring computer support) will be utilized.
- 1. Assumptions a) All assumptions of Section 1 .1 are utilized.
b) Limiting doses for each gaseous nuclide are summed, regardless of limiting decay mode (gamma or beta). c) Limiting doses for each particulate and iodine nuclide are summed, regardless of dose point location, exposure pathway, or organ affected. d) Doses are summed for detected nuclides such that all nuclides which contribute greater than 10% individually or 25% in aggregate, to the EC of released radioactivity, are included in the dose calculation.
- 2. Equations For determining gaseous effluent dose:
- 22 (1.20)
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- where:
Revision 12 DG = Dose from gaseous effluents (mrad).
= Quantity of gaseous nuclide i released (Ci).
Dose per Ci factor for gaseous nuclide i (mrad/Ci). The limit for this mixture is conservatively taken as that for gamma exposure (5 mrem/quarter, 10 mrem/year) although as indicated in Table 1 .9, a majority of the gaseous effluents are beta-limiting and on an individual basis have the higher limit of 1 0 millirem/quarter and 20 millirem/year. For determining tritium, particulate and iodine dose to organs: ( 1 .21) where: Dose from particulates and iodines (mrem). Quantity of particulate or iodine nuclide i released (Ci). Dose per Ci factor for particulate or iodine nuclide i (mrad/Ci) .
- 23
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12
- b. Realistic Calculation This methodology is to be used if the highly conservative calculations described in C.1 or D.1 yield values that appear to exceed applicable limits.
Doses for released particulates, iodines and noble gases will be determined by use of the NRC GASPAR computer code. The computer run will utilize the annual average joint frequency meteorological data based on not less than 3 years of meteorological measurement, and will reflect demographic and land use information from the land use survey generated in the most recent prior year. Where appropriate, seasonal adjustments will be applied to obtain realistic dose estimates since both recreational and agricultural activities can vary greatly in relation to season of the year. An alternative to GASPAR for offsite dose calculation is the use of the Palisades Segmented Gaussian Plume Emergency offsite dose calculation program. This dose model allows evaluation of dose under the actual meteorological conditions present at the time of release. It is anticipated that the system may be used in major short-term releases such as Containment purges are to be made under conditions which depart significantly from mean annual conditions. E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.
- 1. System Description A flow diagram for the GRTS is given in Figure 1-1. The system consists of three waste-gas compressor packages, six gas decay tanks, and the associated piping, valves, and instrumentation.
Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid
- accumulation in the tanks connected to the vent header, and boron recycle process operation.
24
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12
- Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow diaphragm compressors and system electrical grounding), and minimization of leakage outside the system. Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the' system by operational experience over the past 13 years.
- 2. Determination of Satisfactory Operation Design basis quantity fraction will be calculated for batch and continuous releases as described in Section l.C. These calculations will be used to ensure that the GRTS is operating as designed.
Because the Plant was designed to collect and hold for decay a vast majority of the high level gases generated within the primary system, and because the 1 3-year operating history (to date of writing the initial ODCM) of the Plant has demonstrated the system's consistent performance well below Appendix I limits, no additional operability requirements are specified .
- F. RELEASE RATE FOR OFFSITE EC (50 mrem/yr) 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year.
(Note: there are no unrestricted areas anywhere within the site boundary as defined by Figure 1-1 .) Concentrations at this level if present for one year will result in a dose of 50 mrem whole body. 10 CFR 50.36a requires that the release of radioactive materials be kept as low as reasonably achievable. However, the section further states that the licensee is permitted the flexibility of operation, to assure a dependable source of power even under unusual operating conditions, to release quantities of material higher than a small percentage of 1 0 CFR 20. 1 302 limits but still within those limits. Appendix I to 1 0 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement .
- 25
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 The GASPAR code has been run to determine the dose due to external radiation and inhalation. The source term used is listed in Table 1.1. The meteorology data is given in Table 1.3. Dose using annual average meteorology, to the most limiting organ of the person assume to be residing at the site boundary with highest X/Q, is 2.15E-02 mrem (for one year). The release rate which would result in a dose rate equivalent to 50 mrem/year (using the more conservative total body limit) is the curies/year given in Table 1 .1 multiplied by 50/2.15E-02 or 0.11 Ci/sec. G. PARTICULATE AND IODINE SAMPLING Particulate an iodine samples are obtained from the continuous sample stream pulled from the Plant stack. Samples typically are obtained to represent an integrated release from a gas batch (waste gas decay tank or Containment purge, for example), or a series of samples are obtained to follow the course of a release. In any event, sample intervals are weekly, at a minimum. Because HEPA filters are present between most source inputs to the stack and the sample point, releases of particulates normally are significantly less than pre-release calculations indicate. This provides for conservatism in establishing setpoints and in estimation of pre-release design basis quantity fraction. However, for the sake of maintaining accurate release totals, monitor results (for gases) and sample results (for particulates and iodines) utilized rather than the pre-release estimates, for cumulative records. Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Beta and alpha counting also is performed on the particulate filters. Beta yields of the gamma isotopes detected on particulate filters are applied to determine "identified" beta, an the "identified" count rate is subtracted from the observed count rate to give "unidentified" beta. The "unidentified" beta is assumed to be Sr-90 until results on actual Sr-90 (chemically separated from a quarterly composite of filters) are obtained. Sampling and analysis will be performed per Appendix A, Table B-1 requirements. 26
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 H. NOBLE GAS SAMPLING Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. Analysis of these samples will be used for accountability of noble gases. Off gas will be sampled at least weekly and used to calculate monthly noble gas releases. Nonroutine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of 1 E-06 µCi/cc. Sampling and analysis will be performed per Appendix A, Table B-1 requirements. I. TRITIUM SAMPLING Tritium has a low dose consequence to the public because of low production rates. The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded). Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will be estimated using conservative evaporation rate calculations from the fuel pool and reactor cavity .
- 27
* (....
PALISAD~S GASEOUS EFFLUENTS STACK ::!! G) c
- J:I lI m en WASTE GAS I SURGE TANK _J )>
RE 1 '13 NOBLE 2 0 RE 2320 GAS . c "TI
,.c:r-----.,__-.&.0......__... ATMOSPHERE -I "TI en
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~ LOWLEV'L GAS COLLECTION------'"'"""' J--.....;_-+
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- J:I m CONOENSEft CD n en N EAST r--------, I OFF GAS <
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r-2 c co SAFE AUX BLDG I HEPA/CHARCOAL 0 on GUARD RAD- :J C I WASTE RE 1809° r- m AREA )> )> WEST HEPA SAFE ::! :J:I GUARD RE 1811 0 ,, HEPA (NORMAL) 2r SIJPPL Y FUEL HANDLG CONTAIN-MENT RE 1117 s
)> 2 l>
BLDG AREA 2 -I HEPA/CHARCOAL c
!REFUELING I )>
r---------, r-r--- - - - - - - - - , 1 FUEL Q Q RAIJ- ~ AREA lh---- su; .'LY SUPPLY ~}-] WASTE RE 5712
- ADDITN
-----, AREA AOOITN RE 5711" "RE 1ll09_ 5711 AND 5712 TRIP SUPPLY AND ONE OF r,.\) EXHAUST£RS.
FLOW IS NOT TERMINATED PALISAERlft.~EUIH\tfftfJ#>pATHS GASEcfuslEOUS
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.1 PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIES/YEAR (1)
Nuclide Gaseous(2) Liquid(2) H-3 5.5 159 Kr-85 4.1 NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2.1 E-01 NA Ar-41 3.1 E-02 NA Xe-131 m 2.2 NA Xe-133 1493 NA Xe-133m 0.43 NA Xe-135 1 .11 NA Xe-135m 0.3 NA 1-131 0.025 3.21 E-03 1-132 2.91 E-03 NA 1-133 6.5E-03 4.7E-05 1-134 4.8E-04 NA 1-135 1.84E-02 NA Na-24 1.5E-06 NA Cr-51 2.5E-04 3.9E-03 Mn-54 4.1 E-04 7.8E-03 Co-57 2.1 E-06 3.2E-05 Co-58 8.6E-04 2.9E-02 Fe-59 6.6E-06 4.1 E-04 Co-60 1.1 E-03 1.24E-02 Se-75 3.7E-06 NA Nb-95 2.4E-05 4.53E-04 Zr-95 4.7E-06 1. 79E-04 Mo-99 1.5E-07 NA Ru-103 .3E-07 .1 E-05 Sb-127 NA 3.5E-05 Cs-134 4.5E-05 0.7 Cs-136 NA 1.8E-06 Cs-137 2.6E-04 1.36E-02 Ba-140 2.8E-07 NA La-140 7.5E-07 1.1 E-04 Unidentified beta 3.9E-04 3.3E-03 (1) Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4. (2) Nuclide values listed as NA have not been observed at detectable levels in these waste streams. 29
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA 1 GAMMA 1 (days) 1.1.Lfil !MEV/DISl !MEV/DISl 1 Tritium 4.49E 03 1.79E-09 5.68E-03 0.0 2 C-14 2.09E 06 3.84E-12 4.95E-02 . 0.0 3 N-13 6.94E-03 1.16E-03 4.91 E-01 1.02E 00 4 0-19 3.36E-04 2.39E-02 1.02E 00 1.05E 00 5 F-18 7.62E-02 1.05E-04 2.50E-01 1.02E 00 6 NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 00 7 P-32 1.43E 01 5.61 E-07 6.95E-01 0.0 8 AR-41 7.63E-02 1.05E-04 4.64E-01 1.28E 00 9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-01 11 MN-56 1.07E-01 7.50E-05 8.29E-01 1.69E 00 12 FE-59 4.50E 01 1.78E-07 1.18E-01 1.19E 00 13 C0-58 7.13E01 1.12E-07 3.41 E-02 9.78E-01 14 C0-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00 15 ZN-69m 5. 75E-01 1.39E-05 2.21 E-02 4.16E-01 16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 BR-84 2.21 E-02 3.63E-04 1.28E 00 1.77E 00 18 BR-85 2.08E-03 3.86E-03 1.04E 00 6.60E-02 19 KR-85m 1.83E-01 4.38E-05 2.53E-01 1.59E-01 20 KR-85 3.93E 03 2.04E-09 2.51 E-01 2.21 E-03 21 KR-87 5.28E-02 1.52E-04 1.32E 00 7.93E-01 22 KR-88 1.17E-01 6.86E-05 3.61 E-01 1.96E 00 23 KR-89 2.21 E-03 3.63E-03 1.36E 00 1.83E 00 24 RB-88 1.24E-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 1.07E-02 7.50E-04 1.01 E 00 2.05E-OO 26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 28 SR-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01 29 SR-92 1.13E-01 7.10E-05 1.95E-01 1.34E 00 30 SR-93 5.56E-03 1.44E-03 9.20E-01 2.24E 00 31 Y-90 2.67E 00 3.00E-06 9.36E-01 0.0 32 Y-91m 3.47E-02 2.31 E-04 2.73E-02 5.30E-01 33 Y-91 5.88E 01 1.36E-07 6.06E-01 3.61 E-03 34 Y-92 1.47E-01 5.46E-05 1.44E 00 2.50E-01 35 Y-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 ZR-95 6.50E 01 1.23E-07 1.16E-01 7.35E-01 37 NB-95m 3.75E 00 2.14E-06 1.81 E-01 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7 .64E-01 39 M0-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01 30
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.2 {continued)
BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA 1 GAMMA 1 (days) (1 /sl (MEV/DISl IMEV/DISl 41 TC-99 7.74E 07 1.04E-13 8.46E-02 0.0 42 TC-104 1.25E-02 6.42E-04 1.60E 00 1 .95E 00 43 RU-106 3.67E 02 2.19E-08 1.01 E-02 0.0 44 TE-132 3.24E 00 2.48E-06 1.00E-01 2.33E-01 45 1-129 6.21 E 09 1.29E-15 5.43E-02 2.46E-02 46 1-131 8.05E 00 9.96E-07 1.94E-01 3.81 E-01 47 1-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00 48 1-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 49 1-134 3.61 E-02 2.22E-04 6.16E-01 2.59E 00 50 1-135 2.79E-01 2.87E-05 3.68E-01 1.55E 00 51 XE-131 m 1.18E01 6.80E-07 1.43E-01 2.01 E-02 52 XE-133m 2.26E 00 3.55E-06 1.90E-01 4.15E-02 53 XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 54 XE-135m 1.08E-02 7.43E-04 9.58E-02 4.32E-01 55 XE-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 XE-137 2.71E03 2.96E-03 1.77E 00 1.88E-01 57 XE-138 9.84E-03 8.15E-04 6.65E-01 1.1 OE 00 58 CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 59 CS-135 1.1 OE 09 7.29E-15 5.63E-02 0.0 60 CS-136 1.30E 01 6.17E-07 1.37E-01 2.15E 00 61 CS-137 1.1 OE 04 7.29E-10 1. 71 E-01 5.97E-01 62 CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 63 BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 64 BA-140 1.28E 01 6.27E-07 3.15E-01 1. 71 E-01 65 LA-140 1.68E 00 4.77E-06 5.33E-01 2.31 E 00 66 CE-144 2.84E 02 2.82E-08 9.13E-02 1.93E-02 67 PR-143 1.36E 01 5.90E-07 3.14E-01 0.0 68 PR-144 1.20E-02 6.68E-04 1.21 E 00 3.18EOO Average energy per disintegration values were obtained from ICRP Publication No 38, Radionuclide Transformations: Energy and Intensity of Emissions 1983 and NUREG/CR-1413 (ORNL/NUREG-70), a Radionuclide Decay Data Base - Index and Summary Table, DC Kocher, May 1980. 31
- USNRC COMPUTER CODE - XOQOOQ, VERSION 2 . 0 RUN DATE: 970513
***** PALISADES XOQOOQ82 ***** USING al/01/92 - 12/31/96 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING NO DECAY, UNDEPLETED ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 '2.500 3.000 3.500 4.000 4.500 S 4.20BE-06 l.3BlE-06 7.556E-07 4.993E-07 2.782E-07 l.842E-07 l.340E-07 1.033E-07 8.298E-08 6.867E-OB 5.813E-OB SSW 3.330E-06 l.086E-06 5.856E-07 3.870E-07 2.160E-07 l.437E-07 l.048E-07 8.108E-08 6.528E-08 5.413E-08 4.590E-08 SW 3.890E-06 l.242E-06 6.590E-07 4.333E-07 2.413E-07 1.614E-07 l.184E-07 9.203E-08 7.440E-08 6.191E-08 5.267E-08 WSW 4.060E-06 1.279E-06 6.715E-07 4.401E-07 2.450E-07 1.64BE-07 l.215E-07 9.484E-08 7.694E-08 6.422E-08 5.477E-08 0 W 5.554E-06 1.759E-06 9.224E-07 6.035E-07 3.349E-07 2.249E-07 1.657E-07 l.292E-07 l.047E-07 8.735E-08 7.447E-08 "T1 WNW 7.378E-06 2.346E-06 1.235E-06 8.084E-07 4.487E-07 3.0lOE-07 2.216E-07 l.726E-07 l.399E-07 l.166E-07 9.937E-08 "T1 NW 9.531E-06 2.974E-06 l.551E-06 l.012E-06 5.610E-07 3.784E-07 2.BOOE-07 2.191E-07 l.781E-07 l.490E-07 1.273E-07 en NNW N l.286E-05 l.087E-05 3.959E-06 3.347E-06 2.052E-06 l.739E-06 l.339E-06 1.138E-06 7.443E-07 6.348E-07 5.039E-07 4.300E-07 3.741E-07 3.192E-07 2.935E-07 2.504E-07 2.391E-07 2.040E-07 2.003E-07 l.709E-07 l.715E-07 1.462E-07 rri ;g NNE 5.487E-06 l.717E-06 9.119E-07 6.000E-07 3.353E-07 2.256E-07 l.664E-07 1.299E-07 l.054E-07 8.793E-08 7.SOlE-08 Cr NE 5.450E-06 l.803E-06 9.B56E-07 6.476E-07 3.578E-07 2.355E-07 l.705E-07 1.310E-07 l.049E-07 8.657E-08 7.312E-08 o en ENE E 4.258E-06 4.618E-06 l.379E-06 l.531E-06 7.464E-07 B.321E-07 4.886E-07 5.43BE-07 2.697E-07 2.990E-07 l.773E-07 l.959E-07 1.282E-07 l.413E-07 9.B50E-OB l.082E-07 7.885E-OB 8.645E-08 6.507E-OB 7.120E-08 5.496E-08 6.002E-08 en l> ESE 4.436E-06 l.479E-06 8.008E-07 5.210E-07 2.848E-07 l.860E-07 l.338E-07 l.023E-07 B.l53E-08 6.704E-08 5.644E-08 mC m
-I n en SE 5.091E-06 l.678E-06 9.044E-07 5.872E-07 3.207E-07 2.096E-07 l.509E-07 1.155E-07 9.217E-08 7.586E-08 6.391E-08 )>
SSE 6.044E-06 2.000E-06 l.088E-06 7.106E-07 3.901E-07 2.557E-07 l.845E-07 l.415E-07 1.131E-07 9.317E-08 7.858E-08 al )> z w r I' c N ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE m (") (") SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 c: r-
....lo rm S 5.0lOE-08 2.837E-08 l.901E-OB l.OB6E-OB 7.328E-09 5.410E-09 4.227E-09 3.433E-09 2.869E-09 2.450E-09 2.127E-09 N )> )>
SSW 3.963E-08 2.257E-08 l.519E-OB B.728E-09 5.913E-09 4.379E-09 3.431E-09 2.793E-09 2.338E-09 2.000E-09 l.740E-09 ~ ::0 SW 4.560E-08 2.627E-08 l.782E-08 l.037E-08 7.086E-09 5.284E-09 4.163E-09 3.405E-09 2.863E-09 2.458E-09 2.145E-09 0 WSW 4.753E-08 2.763E-08 l.886E-08 1.106E-08 7.602E-09 5.693E-09 4.501E-09 3.693E-09 3.113E-09 2.678E-09 2.342E-09 2~ W WNW 6.459E-08 B.615E-08 3.749E-08 4.992E-OB 2.557E-08 3.400E-08 l.498E-08 l.989E-OB 1.029E-08 l.364E-OB 7.706E-09 1.021E-08 6.091E-09 8.059E-09 4.996E-09 6.606E-09 4.211E-09 5.565E-09 3.623E-09 4.785E-09 3.16BE-09 4.183E-09 s:)> )>z NW 1.106E-07 6.471E-08 4.436E-08 2.61BE-08 1.808E-08 l.359E-08 1.077E-08 B.857E-09 7.481E-09 6.449E-09 5.649E-09 NNW 1.492E-07 B.772E-OB 6.035E-08 3.579E-OB 2.479E-OB l.867E-OB 1.483E-08 l.221E-08 l.033E-08 8.915E-09 7.817E-09 2 -I N NNE l.273E-07 6.508E-08 7.475E-08 3.782E-08 5.139E-08 2.581E-08 3.045E-OB l.513E-08 2.107E-08 l.039E-08 l.586E-08 7.781E-09 l.259E-08 6.148E-09 1.036E-08 5.042E-09 8.762E-09 4.248E-09 7.559E-09 3.654E-09 6.625E-09 3.194E-09 c
)>
NE 6.291E-08 3.539E-08 2.361E-08 1.342E-08 9.033E-09 6.656E-09 5.193E-09 4.2i3E-09 3.517E-09 3.000E-09 2.604E-09 r ENE 4.729E-08 2.665E-08 l.781E-08 l.015E-08 6.847E-09 5.056E-09 3.951E-09 3.211E-09 2.684E-09 2.293E-09 1.993E-09 E 5.155E-08 2.883E-08 l.915E-08 l.083E-08 7.262E-09 5.337E-09 4.155E-09 3.366E-09 2.806E-09 2.392E-09 2.074E-09 ESE 4.843E-08 2.698E-08 l.788E-08 l.007E-08 6.742E-09 4.948E-09 3.848E-09 3.ll4E-09 2.594E-09 2.210E-09 l.915E-09 SE 5.488E-08 3.069E-08 2.039E-08 l.154E-08 7.748E-09 5.702E-09 4.445E-09 3.604E-09 3.00BE-09 2.566E-09 2.227E-09 SSE 6.753E-08 3.785E-08 2.519E-08 l.428E-08 9.595E-09 7.0G4E-09 5.507E-09 4.466E-09 3.727E-09 3.179E-09 2.758E-09 VENT AND BUILDING PARAMETERS: RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERS) 0.00 BUILDING HEIGHT (METERS) 58.1 EXIT VELOCITY (METERS) 0.00 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2000.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.
USNRC COMPUTER CODE - XOQDOQ, VERSION 2. 0 RUN DATE: 970513
***** PALISADES XOQDOQ82 ***** USING 01/01/92 - 12/31/96 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONTAINMENI' BUILDING NO DECAY, UNDEPLETED CHI/Q (SEC/MEI'ER CUBED) FOR EACH SEGMENT S:mMEm' BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4::-5 5-10 10-20 20-30 30-40 40-50 FROM SITE s 7.BOBE-07 2.B56E-07 1.351E-07 8.334E-08 5.B2BE-OB 2.. 904E-OB 1.llOE-08 5.44BE-09 3.445E-09 2.454E-09 SSW 6.0B5E-07 2.219E-07 1.057E-07 6.555E-08 4.602E-OB 2.30BE-OB B.912E-09 4.409E-09 2.B02E-09 2.004E-09 SW 6.B83E-07 2.484E-07 1.193E-07 7.468E-OB 5.279E-OB 2.681E-OB 1.057E-OB 5.316E-09 3.415E-09 2.462E-09 WSW 7.03BE-07 2.527E-07 1.224E-07 7.721E-OB 5.489E-OB 2.815E-OB 1.126E-08 5.725E-09 3.703E-09 2.683E-09 0 w 9.666E-07 3.457E-07 1.669E-07 1.051E-07 7.463E-08 3.B21E-OB 1.525E-08 7.749E-09 5.0lOE-09 "T1 3.629E-09 "T1 WNW NW 1.292E-06 1.627E-06 4.630E-07 5.BOOE-07 2.232E-07 2.B19E-07 1.404E-07 l.787E-07 9.95BE-OB 1.276E-07 5.089E-OB 6.587E-08 2.025E-08 2.662E-08 1.026E-08 l.366E-08 6.625E-09 8.879E-09 4.793E-09 6.458E-09 en
- ""D NNW 2.159E-06 7.695E-07 3.765E-07 2.399E-07 1. 718E-07 8.923E-08 3.636E-OB 1.B77E-08 1.224E-08 8.928E-09 -4 )>
N 1.829E-06 6.557E-07 3.212E-07 2.046E-07 1.465E-07 7.604E-08 3.093E-08 1.594E-08 1.039E-OB 7.569E-09 m r-NNE NE 9.521E-07 l.017E-06 3.454E-07 3.678E-07 l.676E-07 l.720E-07
- 1. 057E-07 1.054E-07 7.516E-08 7.332E-OB 3.854E-OB 3.627E-OB 1.540E-OB 1.374E-OB 7.825E-09 6.704E-09 5.056E-09 4.227E-09 3.660E-09 3.006E-09 oe -en ENE 7.724E-07 2.773E-07 1.294E-07 7.922E-OB 5.511E-OB 2.731E-08 1.038E-08 5.092E-09 3.222E-09 2.29BE-09 en l>
E 8.592E-07 3.076E-07 1.426E-07 B.686E-OB 6.020E-08 2.958E-OB 1.109E-08 5.378E-09 3.378E-09 2.397E-09 mC
-4 ::c m ESE SE 8.271E-07 9.353E-07 2.934E-07 3.305E-07 l.351E-07 1.524E-07 8.193E-08 9.262E-08 5.661E-OB 6.411E-08 2.770E-OB 3.149E-08 1.033E-OB 1.182E-08 4.986E-09 5.745E-09 3.126E-09 3.617E-09 2.214E-09 2.571E-09 )> C1> n en SSE 1.123E-06 4.016E-07 1. 863E-07 l.136E-07 7.881E-08 3.882E-08 1.462E-08 7.116E-09 4.482E-09 3.186E-09 DJ
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- USNRC COMPUTER CODE - XOQOOQ, VERSION 2. 0 RUN DATE: 970513
***** PALISADES XOQDOQ82 ***** USING 01/01/92 - 12/31/96 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING 2.260 DAY DECAY, UNDEPLETED ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FRCM THE SITE SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S 4.205E-06 l.379E-06 7.540E-07 4.979E-07 2.769E-07 l.831E-07 l.330E-07 1.024E~07 8.212E-08 6.785E-08 5.735E-08 SSW 3.327E-06 l.084E-06 5.842E-07 3.858E-07 2.150E-07 l.42BE-07 1.040E-07 B.032E-OB 6.457E-OB 5.346E-OB 4.526E-OB SW 3.8B7E-06 l.240E-06 6.575E-07 4.319E-07 2.402E-07 l.604E-07 l.175E-07 9.117E-OB 7.359E-OB 6.114E-08 5.193E-08 0 WSW 4.057E-06 l.277E-06 6.699E-07 4.388E-07 2.439E-07 l.637E-07 1.206E-07 9.394E-08 7.609E-08 6.341E-08 5.400E-08 "T1 W 5.550E-06 l.757E-06 9.203E-07 6.016E-07 3.334E-07 2.235E-07 l.644E-07 l.280E-07 l.036E-07 8.628E-08 7.344E-08 "T1 WNW 7.373E-06 2.343E-06 l.232E-06 8.062E-07 4.468E-07 2.993E-07 2.200E-07 l.712E-07 1.385E-07 1.153E-07 9.BlOE-08 en NW 9.524E-06 2.969E-06 l.547E-06 l.009E-06 5.585E-07 3.761E-07 2.779E-07 2.171E-07 l.762E-07 l.472E-07 l.256E-07 -I ""C NNW N l.285E-05 l.087E-05 3.953E-06 3.341E-06 2.047E-06 l.735E-06 l.335E-06 l.134E-06 7.408E-07 6.316E-07 5.00BE-07 4.271E-07 3.712E-07 3.165E-07 2.907E-07 2.478E-07 2.365E-07 2.016E-07 l.979E-07 l.686E-07 l.691E-07 l.440E-07 m~ NNE 5.4B3E-06 l.714E-06 9.099E-07 5.982E-07 3.338E-07 2.242E-07 l.652E-07 1.287E-07 l.042E-07 B.687E-08 7.39BE-OB c-o en NE 5.447E-06 l.BOOE-06 9.837E-07 6.45BE-07 3.563E-07 2.343E-07 l.693E-07 l.299E-07 l.039E-07 8.564E-08 7.223E-08 ENE 4.255E-06 l.377E-06 7.448E-07 4.B72E-07 2.685E-07 l.763E-07 l.273E-07 9.763E-OB 7.804E-08 6.431E-08 5.423E-OB en l> mC E 4.615E-06 l.528E-06 8.303E-07 5.423E-07 2.977E-07 l.948E-07 1.403E-07 1.073E-07 8.559E-OB 7.039E-08 5.925E-08
-I :lJ m ESE 4.433E-06 1.477E-06 7.992E-07 5.196E-07 2.837E-07 1.850E-07 l.32BE-07 1.014E-07 B.075E-OB 6.631E-08 5.575E-08
)> CD n rn SE 5.0BBE-06 l.676E-06 9.026E-07 5.B56E-07 3.194E-07 2.085E-07 l.499E-07 1.145E-07 9.12BE-08 7.502E-0B 6.312E-08 cg < )> 2 SSE 6.040E-06 l.997E-06 l.086E-06 7.087E-07 3.885E-07 2.543E-07 l.833E-07 1.403E-07 l.120E-07 9.213E-0B 7.760E-08 r ~: re m 0 C') C')
ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE ::I Cr SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 rm
)> )>
SSW S 4.936E-OB 3.901E-08 2.774E-08 2.204E-08 l.B45E-OB 1.472E-08 l.039E-08 8.327E-09 6.911E-09 5.555E-09 5.029E-09 4.051E-09 3.874E-09 3.126E-09 3.103E-09 2.506E-09 2.557E-09 2.067E-09 2.153E-09 l.742E-09 l.844E-09 l.492E-09
- ! ::1l SW 4.489E-08 2.566E-08 1.727E-08 9.893E-09 6.657E-09 4.B89E-09 3.793E-09 3.056E-09 2.531E-09 2.140E-09 l.840E-09 0 ""C 4.678E-08 2.69BE-08 l.827E-08 l.055E-08 7.141E-09 5.267E-09 4.lOlE-09 3.314E-09 2.751E-09 2.332E-09 2.009E-09 Zr WSW WNW W 6.361E-08 8.494E-08 3.664E-08 4.886E-08 2.480E-08 3.304E-08 l.431E-08 l.906E-08 9.688E-09 l.289E-OB 7.147E-09 9.SOBE-09 5.566E-09 7.405E-09 4.SOOE-09 5.987E-09 3.73BE-09 4.975E-09 3.170E-09 4.220E-09 2.732E-09 3.639E-09 s:)> )>2 NW 1.090E-07 6.323E-OB 4.301E-OB 2.SOOE-08 l.700E-OB 1.259E-08 9.836E-09 7.972E-09 6.638E-09 5.641E-09 4.B72E-09 2 -I NNW l.469E-07 8.570E-08 5.851E-08 3.417E-08 2.331E-08 l.730E-08 l.354E-08 l.099E-08 9.164E-09 7.796E-09 6.739E-09 N l.251E-07 7.285E-08 4.966E-08 2.893E-08 l.969E-08 l.458E-08 l.139E-08 9.223E-09 7.674E-09 6.516E-09 S.622E-09 c NNE 6.410E-08 3.697E-OB 2.504E-OB l.446E-08 9.7B6E-09 7.218E-09 5.620E-09 4.541E-09 3.771E-09 3.196E-09 2.754E-09 )>
NE 6.206E-OB 3.468E-OB 2.298E-08 1.289E-08 B.558E-09 6.223E-09 4.791E-09 3.B36E-09 3.160E-09 2.662E-09 2.2BOE-09 I ENE 4.659E-08 2.607E-08 1.729E-08 9.711E-09 6.459E-09 4.702E-09 3.624E-09 2.904E-09 2.395E-09 2.0lBE-09 1.730E-09 E 5.082E-08 2.B22E-08 1.861E-08 1.037E-08 6.861E-09 4.973E-09 3.819E-09 3.0SlE-09 2.509E-09 2.llOE-09 l.805E-09 ESE 4.776E-OB 2.643E-08 l.739E-08 9.664E-09 6.3BOE-09 4.619E-09 3.544E-09 2.830E-09 2.327E-09 l.956E-09 l.673E-09 SE 5.413E-08 3.00SE-08 1.983E-08 1.106E-08 7.329E-09 5.320E-09 4.091E-09 3.273E-09 2.695E-09 2.268E-09 l.943E-09 SSE 6.659E-OB 3.706E-08 2.449E-08 l.369E-OB 9.073E-09 6.SBBE-09 5.066E-09 4.053E-09 3.337E-09 2.BOBE-09 2.404E-09 VEm' AND BUILDING PARAMETERS: RELEASE HEIGHT (METERS) SB.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (MJITERS) 0.00 BUILDING HEIGHT (METERS) SB.1 EXIT VELOCITY (MIITERS) 0.00 BLDG.MIN.CRS.SEC.AREA (SQ. METERS) 2000.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.
*USNRC COMPUTER CODE - XOQOOQ, VERSION 2. 0 RUN*
DATE: 970513
***** PALISADES XOQOOQ82 ***** USING Ql/01/92 - 12/31/96 MET DATA *****
GROUND LEI/EL RELEASE - TOP OF CONI'AINMENT BUILDING
- 2. 260 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SmMENT SEX3MENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 7.791E-07 2.843E~07 1.341E-07 B.24BE-OB 5.750E-08 2.842E-08 1.064E-08 5.069E-09 3.115E-09 2.lSBE-09 SSW 6. 072E-07 2.209E-07 1.049E-07 6.484E-08 4.537E-OB 2.256E-08 8.515E-09 4.082E-09 2.516E-09 1. 746E-09 l.OlOE-08 4.922E-09 3.066E-09 2.145E-09
.,,.,,0 SW 6.867E-07 2.473E-07 1.184E-07 7.387E-OB 5.205E-OB 2.621E-08 WSW 7.022E-07 2.516E-07 1.214E-07 7.636E-08 5.4PE-OB 2.751E-08 1.075E-08 5.JOOE-09 3.324E-09 2.337E-09 W 9.645E-07 3.441E-07 l.656E-07 1.040E-07 7.360E-08 3.737E-08 1.459E-08 7.192E-09 4.514E-09 3.176E-09 WNW 1.290E-06 4.611E-07 2.216E-07 1.390E-07 9.832E-08 4.985E-OB 1.942E-OB 9.569E-09 6.007E-09 4.229E-09 t/)
NW 1.624E-06 5.775E-07 2.79BE-07 1.768E-07 1.25BE-07 6.441E-OB 2.545E-08 1.267E-08 7.996E-09 5.651E-09 - "tJ NNW 2.154E-06 7.661E-07 3.736E-07 2.373E-07 1.694E-07 B.722E-08 3.475E-08 1. 740E-OB 1.102E-OB 7.BlOE-09 -I )> N 1.825E-06 6.524E-07 3.lBSE-07 2.022E-07 1.443E-07 7.415E-OB 2.943E-OB 1.466E-08 9.251E-09 6.52BE-09 mr NNE 9.500E-07 3.438E-07 1.663E-07 l.046E-07 7.414E-08 3.770E-08 1.473E-08 7.263E-09 4.556E-09 3.203E-09 2.66BE-09 c-ot/) )> t/) NE 1. OlSE-06 3.664E-07 1. 709E-07 1.044E-07 7.244E-08 3.557E-OB 1.321E-OB 6.272E-09 3.BSlE-09 ENE 7.708E-07 2.761E-07 1.2BSE-07 7.B40E-OB 5.439E-08 2.673E-OB 9.950E-09 4.739E-09 2.916E-09 2.023E-09 E B.574E-07 3.063E-07 l.416E-07 B.600E-OB 5.943E-OB 2.897E-OB 1.064E-08 5.0lSE-09 3.064E-09 2.115E-09 mC
-I :a m ESE B.255E-07 2.922E-07 1.342E-07 B.llSE-08 9.173E-08 5.592E-OB 6.332E-08 2.715E-OB 3.086E-08 9.921E-09 1.135E-08 4.659E-09 5.364E-09 2.B42E-09 3.286E-09 1.961E-09 2.274E-09 l> CD o en SE 9.335E-07 3.292E-07 1.514E-07 1.125E-07 7.783E-08 3.804E-08 l.404E-08 6.642E-09 4.070E-09 2.B15E-09 D:J
< )> z w SSE 1.121E-06 4.000E-07 1. BSOE-07 r ~: re CJ1 m 0 on
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*USNRC COMPUTER CODE - XOQDOQ, VERSION 2. 0 RUN DATE: 970513
***** PALISADES XOQDOQ82 ***** USING,01/01/92 - 12/31/96 MET DATA*****
GROUND LEVEL RELEASE - TOP OF CONl'AINMENr BUILDING 8.000 DAY DECAY, DEPLETED ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S 3.982E-06 1.261E-06 6.730E-07 4.367E-07 2.359E-07 l.523E-07 l.083E-07 8.186E-08 6.456E-OB 5.254E-08 4.378E-08 SSW 3.150E-06 9.913E-07 5.215E-07 3.384E-07 1.832E-07 1.187E-07 8.473E-08 6.423E-08 5.078E-08 4.141E-08 3.457E-08 SW WSW W 3.681E-06 3.842E-06 5.256E-06 1.134E-06 l.16BE-06 l.606E-06 5.869E-07 5.9BOE-07 8.215E-07 3.789E-07 3.849E-07 5.278E-07 2.047E-07 2.07BE-07 2.841E-07 l.334E-07 l.362E-07 l.859E-07 9.572E-08 9.823E-OB l.339E-07 7.291E-0B 7.513E-08 l.023E-07 5.787E-OB 5.985E-OB 8.146E-08 4.736E-OB 4.912E-08 6.682E-08 3.966E-08 4.125E-08 5.608E-08
.,,.,,0 WNW 6.982E-06 2.141E-06 1.lOOE-06 7.071E-07 3.806E-07 2.488E-07 l.791E-07 l.368E-07 l.088E-07 8.923E-OB 7.486E-08 CJ)
NW 9.018E-06 2.715E-06 l.381E-06 8.848E-07 4.758E-07 3.128E-07 2.263E-07 l.736E-07 l.386E-07 1.140E-07 9.58BE-08 ""C 1.217E-05 3.613E-06 1.827E-06 l.171E-06 6.312E-07 4.165E-07 3.024E-07 2.325E-07 1.860E-07 1.532E-07 l.291E-07 -I )> NNW m NNE N l.029E-05 5.192E-06 3.055E-06 l.567E-06 1.549E-06 8.121E-07 9.954E-07 5.248E-07 5.384E-07 2.844E-07 3.554E-07 l.865E-07 2.579E-07 l.345E-07 1.983E-07 l.029E-07 1.586E-07 8.196E-08 l.307E-07 6.727E-08 l.lOlE-07 5.649E-08 c cCJ) NE 5.157E-06 l.646E-06 8.778E-07 5.664E-07 3.035E-07 1.947E-07 l.378E-07 l.038E-07 8.162E-08 6.625E-08 5.509E-OB 0 )> ENE 4.029E-06 l.259E-06 6.648E-07 4.273E-07 2.287E-07 l.466E-07 l.037E-07 7.804E-08 6.135E-08 4.97BE-08 4.139E-OB CJ) E 4.370E-06 l.397E-06 7.410E-07 4.756E-07 2.536E-07 l.620E-07 l.142E-07 B.576E-OB 6.727E-OB 5.44BE-08 4.522E-0B
- 0 mc m ESE 4.19BE-06 l.350E-06 7.132E-07 4.557E-07 2.416E-07 1.538E-07 1.0BlE-07 B.103E-OB 6.344E-08 5.130E-08 4.252E-08 -I CD ("') rn SE 4.817E-06 l.532E-06 8.055E-07 5.136E-07 2.720E-07 1.733E-07 l.220E-07 9.152E-08 7.172E-08 5.805E-08 4.815E-08 )> < )>
w SSE 5.719E-06 1.B26E-06 9.691E-07 6.216E-07 3.309E-07 2.114E-07 l.492E-07 l.121E-07 8.798E-08 7.129E-08 5.920E-0B Ctl en' r z r m (") c: (j) ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE
~
0
- l c: n r
SECTOR 5. 000 7. 500 10. 000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 ..... r m S 3.719E-08 l.987E-08 l.266E-08 6.668E-09 4.208E-09 2.931E-09 2.174E-09 l.683E-09 l.345E-09 l.102E-09 9.195E-10 w N
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-I :::0 SSW 2.941E-08 l.580E-08 l.OllE-08 5.355E-09 3.392E-09 2.370E-09 1.762E-09 l.367E-09 l.094E-09 8.973E-10 7.499E-10 SW 3.384E-08 l.840E-08 l.187E-08 6.362E-09 4.065E-09 2.860E-09 2.138E-09 l.667E-09 l.340E-09 l.103E-09 9.248E-10 0 ""C WSW 3.527E-08 1.935E-08 1.256E-OB 6.786E-09 4.361E-09 3.081E-09 2.311E-09 l.B07E-09 1.457E-09 l.202E-09 l.OlOE-09 z I WNW W 4.794E-08 6.396E-08 2.626E-08 3.49BE-08 l.703E-OB 2.266E-08 9.195E-09 l.222E-08 5.907E-09 7.839E-09 4.173E-09 5.533E-09 3.130E-09 4.148E-09 2.448E-09 3.241E-09 1.973E-09 2.612E-09 l.628E-09 2.154E-09 l.368E-09 l.810E-09 s)> )>z NW NNW 8.212E-08 1.107E-07 4.532E-OB 6.143E-08 2.954E-08 4.019E-08 l.607E-08 2.196E-08 l.037E-08 l.422E-08 7.352E-09 1.0llE-08 5.531E-09 7.617E-09 4.335E-09 5.980E-09 3.502E-09 4.836E-09 2.B94E-09 4.002E-09 2.436E-09 3.371E-09 z -I N 9.439E-08 5.231E-08 3.419E-08 l.B66E-08 1.207E-08 8.564E-09 6.449E-09 5.058E-09 4.087E-09 3.379E-09 2.844E-09 c NNE 4.831E-08 2.649E-08 1.719E-08 9.289E-09 5.967E-09 4.214E-09 3.160E-09 2.470E-09 1.991E-09 1.642E-09 l.379E-09 )>
NE 4.671E-08 2.481E-08 l.574E-08 8.249E-09 5.194E-09 3.612E-09 2.676E-09 2.070E-09 l.653E-09 l.353E-09 l.129E-09 r ENE 3.510E-08 l.867E-08 l.186E-08 6.231E-09 3.932E-09 2.740E-09 2.032E-09 1.574E-09 1.259E-09 1.031E-09 8.614E-10 E 3.827E-08 2.020E-08 l.276E-08 6.651E-09 4.172E-09 2.894E-09 2.139E-09 l.652E-09 l.317E-09 l.077E-09 8.971E-10 ESE 3.596E-08 l.891E-08 l.192E-08 6.190E-09 3.875E-09 2.684E-09 l.981E-09 l.529E-09 1.219E-09 9.955E-10 8.292E-10 SE 4.075E-08 2.150E-08 l.359E-08 7.089E-09 4.453E-09 3.093E-09 2.288E-09 l.769E-09 1.413E-09 l.156E-09 9.641E-10 SSE 5.014E-08 2.653E-08 l.679E-08 8.772E-09 5.515E-09 3.831E-09 2.836E-09 2.192E-09 l.750E-09 l.432E-09 l.194E-09 VEN!' AND BUILDING PARAMETERS: RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERS) 0.00 BUILDING HEIGHT (METERS) 58.1 EXIT VELOCITY (METERS) 0.00 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2000.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.
USNRC COMPUTER CODE - XOQIXJQ, VERSION 2.0 RUN DATE: 970513
***** PALISADES XOQIXJQB2 ***** USING, 01/01/92 - 12/31/96 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONl'AINMENT BUILDING 8.000 DAY DECAY, DEPLETED CHI/Q (SEC/METER CUBED) FOR EACH S~ SOOMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE s 6.9B6E-07 2.434E-07 l.094E-07 6.492E-OB 4.393E-OB 2.052E-OB 6.907E-09 2.969E-09 1.695E-09 l.106E-09 SSW 5.445E-07 1.B91E-07 B.5608-08 5.1058-08 3.4608-0B l.630E-08 5.5408-09 2.399E-09 1.3768-09 9.0llE-10 SW 6.160E-07 2.117E-07 9.664E-08 5.0168-08 3.979E-OB 1.8938-0B 6.565E-09 2.B92E-09 1.6778-09 1.107E-09 0 WSW 6.299E-07 2.153E-07 9.911E-OB 6.0138-08 4.137E-OB 1.9B7E-OB 6.991E-09 3.114E-09 1.0188-09 1.206E-09 w B.653E-07 2.9468-07 1.3518-07 B.1048-0B S.625E-OB 2.6978-08 9.475E-09 4.2188-09 2.462E-09 1.6348-09 en WNW 1.157E-06 3.946E-07 l.80BE-07 1.094E-07 7.50BE-OB 3.594E-OB 1.259E-OB 5.594E-09 3.261E-09 2.162E-09 ::j -0 l.457E-06 4.943E-07 2.2B3E-07 m~ NW l.392E-07 9.614E-OB 4.64BE-OB 1.653E-OB 7.429E-09 4.359E-09 2.904E-09 NNl'I 1.932E-06 6.557E-07 3.049E-07 1. B6BE-07 l.295E-07 6.295E-OB 2.257E-OB l.021E-OB 6.012E-09 4.016E-09 N NNE l.637E-06 8.521E-07 S.586E-07 2.943E-07 2.601E-07 1.357E-07 1.593E-07 B.234E-08 1.104E-07 5.665E-OB S.361E-08
- 2. 721E-08 l.91BE-08 9.569E-09 B.6528-09 4.260E-09 S.085E-09 2.4BSE-09 3.391E-09 1.64BE-09 oc- en NE 9.lOlE-07 3.136E-07 l.394E-07 8.210E-OB 5.529E-08 2.565E-OB B.556E-09 3.659E-09 2.084E-09 1.359E-09 en l>
ENE 6.913E-07 2.364E-07 1. 049E-07 6.171E-08 4.lSSE-OB l.930E-08 6.461E-09 2.775E-09 1.585E-09 l.036E-09 mC m E 7.689E-07 -I :a ESE 7.403E-07 2.622E-07 1.156E-07 6.76BE-08 4.539E-08 2.091E-08 6.908E-09 2.932E-09 1.663E-09 1.0BlE-09
)> (1) o en SE 8.371E-07 2.502E-07 2.818E-07 1.095E-07 1.235E-07 6.384E-OB 7.217E-08 4.269E-OB 1.959E-08 6.434E-09 2.721E-09 1.540E-09 1.0008-09 al
< )> 2 w SSE 1. OOSE-06 3.424E-07 1.SlOE-07 8.852E-08 4.B34E-OB 5.943E-08 2.226E-OB 2.745E-OB 7.362E-09 9.106E-09 3.134E-09 3.B82E-09 1.782E-09 2.20BE-09 1.161E-09 1.438E-09 r- !!!: r- c
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*USNRC COMPUTER CODE - XOQDOQ, VERSION 2 . 0 RUN DATE: 970513
*****PALISADES XOQDOQB2 ***** USING,01/01/92 - 12/31/96 MET DATA*****
GROUND LEVEL RELFASE - TOP OF CONl'AINMmn' BUILDING
********************* RELATIVE DEPOSITION PER UNIT AREA (M**-2) AT FIXED POINI'S BY Da'lNWIND ~RS ********************
DIRECTION DISTANCES IN MILES FROM SITE 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 S 2.600E-OB B.794E-09 4.515E-09 2.772E-09 l.382E-09 B.383E-10 5.66BE-10 4.107E-10 3.123E-10 2.460E-10 l.992E-10 SSW l.731E-OB 5.B52E-09 3.005E-09 l.B45E-09 9.19BE-10 5.579E-10 3.772E-10 2.73JE-10 2.07BE-10 l.637E-10 l.325E-10 SW l.B66E-OB 6.309E-09 3.239E-09 l.989E-09 9.916E-10 6.014E-10 4.066E-10 2.946E-10 2.240E-10 l.765E-10 l.429E-10 WSw l.B29E-OB 6.lBJE-09 3.175E-09 l.949E-09 9.719E-10 5.B94E-10 3.985E-10 2.BBBE-10 2.196E-10 l.730E-10 l.401E-10 W 2.673E-OB 9.040E-09 4.641E-09 2.B50E-09 l.421E-09 B.61BE-10 5.826E-10 4.222E-10 3.210E-10 2.529E-10 2.04BE-10 WNW 4.142E-OB l.401E-OB 7.191E-09 4.416E-09 2.201E-09 l.335E-09 9.027E-10 6.541E-10 4.974E-10 3.919E-10 3.172E-10 0 "T1 NW 4.847E-08 l.639E-08 8.416E-09 5.16BE-09 2.576E-09 l.563E-09 l.056E-09 7.656E-10 5.821E-10 4.586E-10 3.713E-10 "T1 NNW 5.897E-08 l.994E-08 l.024E-08 6.2B7E-09 3.135E-09 l.901E-09 l.285E-09 9.314E-10 7.082E-10 5.580E-10 4.517E-10 en N 4.172E-08 l.411E-08 7.244E-09 4.44BE-09 2.218E-09 l.345E-09 9.093E-10 6.5B9E-10 5.0lOE-10 3.947E-10 3.196E-10 -4 ""C 2.423E-08 8.194E-09 4.207E-09 2.583E-09 l.288E-09 7.BllE-10 5.281E-10 3.827E-10 2.910E-10 2.292E-10 l.B56E-10 m~ NNE NE 4.208E-08 l.423E-08 7.306E-09 4.486E-09 2.237E-09 l.356E-09 9.171E-10 6.646E-10 5.053E-10 3.981E-10 3.223E-10 ENE E 3.387E-OB l.145E-08 5.BBlE-09 3.611E-09 3.926E-08 l.328E-08 6.816E-09 4.185E-09 l.BOOE-09 l.092E-09 7.3B2E-10 5.349E-10 4.067E-10 2.0B7E-09 l.266E-09 B.556E-10 6.200E-10 4.715E-10 J.204E-10 3.714E-10 2.594E-10 3.007E-10 oc- en ESE 4.14BE-08 l.403E-OB 7.202E-09 4.423E-09 2.205E-09 l.337E-09 9.041E-10 6.552E-10 4.982E-10 3.925E-10 3.177E-10 en l> SE 4.919E-OB l.663E-OB B.540E-09 5.244E-09 2.614E-09 l.5B6E-09 l.072E-09 7.769E-10 5.907E-10 4.654E-10 3.76BE-10 mC m SSE 5.133E-OB l.736E-08 8.913E-09 5.473E-09 2.72BE-09 l.655E-09 l.119E-09 8.107E-10 6.165E-10 4.B57E-10 3.932E-10 -4 n en
)>
DIRECTION DISTANCES Dl )> z w FROM SITE 5.00 7.50 10.00 15.00 20.00 IN MILES 25.00 30.00 35.00 40.00 45.00 50.00 r- r- c(") 00 s 1.64BE-10 B.074E-ll 5.066E-11 2.561E-ll 1.550E-ll l.039E-ll 7.446E-12 5.591E-12 4.347E-12 3.473E-12 2.BJ4E-12 m (") SSW l.096E-10 5.373E-11 3.371E-ll l.704E-ll l.OJlE-11 6.915E-12 4.955E-12 3.721E-12 2.B93E-12 2.JllE-12 1.BB6E-12 c r-r- m SW l.182E-10 5.792E-ll 3.634E-ll l.837E-ll l.112E-ll 7.455E-12 5.342E-12 4.0llE-12 3.119E-12 2.491E-12 2.033E-12 l> )> WSW l.159E-10 5.677E-11 3.562E-ll l.BOlE-11 l.090E-ll 7.307E-12 5.236E-12 3.931E-12 3.057E-12 2.442E-12 l.993E-12 w l.694E-10 B.JOOE-11 5.20BE-ll 2.632E-ll l.593E-ll l.06BE-ll 7.654E-12 5.74BE-12 4.469E-12 3.570E-12 2.914E-12 :::! :xJ WNW 2.624E-10 l.286E-10 8.069E-ll 4.078E-11 2.46BE-ll l.655E-ll l.186E-ll B.905E-12 6.924E-12 5.531E-12 4.514E-12 0 ""C NW 3.071E-10 l.505E-10 9.443E-ll 4.773E-ll 2.889E-ll l.937E-ll l.388E-11 1.042E-ll 8.103E-12 6.473E-12 5.283E-12 z r-NNW N 3.736E-10 2.643E-10 1.831E-10 l.295E-10 1.149E-10 B.128E-ll 5.B07E-ll 4.lOBE-11 3.515E-ll 2.487E-ll 2.357E-ll 1.667E-ll l.689E-ll l.195E-11 1.26BE-ll B.970E-12 9.B59E-12 6.975E-12 7.B75E-12 5.571E-12 6.42BE-12 4.547E-12 s)> )>z NNE l.535E-10 7.523E-ll 4.720E-ll 2.386E-ll l.444E-ll 9.682E-12 6.93BE-12 5.210E-12 4.051E-12 3.236E-12 2.641E-12 2! -4 NE 2.666E-10 l.306E-10 B.19BE-ll 4.143E-ll 2.508E-ll l.681E-ll 1.205E-ll 9.047E-12 7.034E-12 5.619E-12 4.586E-12 ENE 2.146E-10 l.052E-10 6.598E-ll 3.335E-ll 2.019E-ll l.353E-ll 9.69BE-12 7.282E-12 5.662E-12 4.523E-12 3.692E-12 c E 2.487E-10 l.219E-10 7.648E-ll 3.866E-ll 2.340E-ll l.569E-ll 1.124E-ll 8.441E-12 6.563E-12 5.242E-12 4.279E-12 )> ESE 2.628E-10 l.288E-10 B.OBlE-11 4.085E-ll 2.472E-ll l.65BE-ll l.lBBE-11 8.919E-12 6.935E-12 5.539E-12 4.521E-12 r-SE 3.117E-10 l.527E-10 9.58JE-ll 4.844E-ll 2.932E-ll l.966E-ll l.40BE-ll l.OSBE-11 B.223E-12 6.569E-12 5.361E-12 SSE 3.252E-10 1.594E-10 l.OOOE-10 5.055E-ll 3.059E-ll 2.0SlE-11 l.470E-ll l.104E-ll B.581E-12 6.855E-12 5.595E-12
USNRC COMPUTER CODE - XOQIXlQ, VERSION 2 . 0 RUN DATE: 970513
***** PALISADES XOQIXlQ82 ***** USING,01/01/92 - 12/31/96 MET DATA*****
GROUND LEVEL RELEASE - TOP OF CONI'AINMENT BUILDING
************************ RELATIVE DEPOSITION PER UNIT AREA (M**-2) BY IX>WNWIND SECTORS ************************
SJ:)3MENI' BOUNDARIES IN MILES DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FRCM SITE
- s. 4.691E-09 l.449E-09 5.76BE-10 3.152E-10 2.003E-10 8.604E-ll 2.668E-ll
- l.057E-ll 5.647E-12 3.495E-12 SSW 3.122E-09 9.645E-10 3.83BE-10 2.097E-10 1. 333E-10 5. 726E-ll l.776E-ll 7.037E-12 3.758E-12 2.326E-12 WSW SW W
3.366E-09 3.299E-09 4.823E-09 l.040E-09 l.019E-09 l.490E-09 4.138E-10 4.055E-10 S.929E-10 2.261E-10 2.216E-10 3.240E-10 l.437E-10 l.409E-10 2.059E-10 6.173E-ll 6.050E-ll 8.845E-ll l.914E-ll l.876E-ll 2.743E-ll 7.5B7E-12 7.436E-12 l.087E-ll 4.051E-12 3.971E-12 5.BOSE-12 2.SOBE-12 2.45BE-12 3.593E-12 0
\'lNW 7.472E-09 2.308E-09 9.1B6E-10 5.020E-10 3.190E-10 l.370E-10 4.249E-ll l.684E-ll B.994E-12 5.567E-12 en NW 8.745E-09 2.702E-09 l.075E-09 5.B75E-10 3.734E-10 l.604E-10 4.974E-ll l.971E-ll l.053E-ll 6.516E-12 -I )> "ti NNW l.064E-08 3.287E-09 l.308E-09 7.147E-10 4.543E-10 l.951E-10 6.051E-ll 2.398E-ll l.281E-ll 7.927E-12 m c cen N 7.527E-09 2.325E-09 9.253E-10 5.057E-10 3.214E-10 l.380E-10 4.281E-ll 1. 697E-ll 9.060E-12 5.608E-12 NNE 4.371E-09 l.351E-09 5.374E-10 2.937E-10 1. B66E-10 B.017E-ll 2.486E-ll 9.853E-12 5.262E-12 3.257E-12 NE 7.591E-09 2.345E-09 9.333E-10 5.lOOE-10 3.241E-10 l.392E-10 4.317E-ll 1. 711E-ll 9.13BE-12 5.656E-12 0 )>
ENE 6.llOE-09 l.888E-09 7.512E-l0 4.lOSE-10 2.609E-10 l.121E-10 3.475E-ll l.377E-11 7.355E-12 4.552E-12 en c E 7.082E-09 2.lBSE-09 B.707E-10 4.75BE-10 3.024E-10 l.299E-10 4.02BE-ll l.596E-ll B.525E-12 5.277E-12 m m
-I ::IJ ESE 7.4B4E-09 2.312E-09 9.200E-10 5.028E-10 3.195E-10 l.373E-10 4.256E-ll l.687E-ll 9.00BE-12 5.576E-12 en (') en
)>
SE 8.874E-09 2.742E-09 l.091E-09 5.962E-10 3.789E-10 1. 628E-10 5.047E-ll 2.000E-11 l.06BE-ll 6.612E-12 < )> SSE 9.261E-09 2.861E-09 1.139E-09 6.222E-10 3.954E-10 l.699E-10 5.267E-ll 2.0B8E-ll l.115E-ll 6.900E-12 DJ f!i: r- z VJ r m 0 (') c c.o VENI' AND BUILDING PARAMETERS: ::I cr- (") RELEASE HEIGHT (MEI'ERS I 58.10 REP. WIND HEIGffi' (MEI'ERS) 10.0 --'
...... r-DIAMETER (METERS) 0.00 BUILDIN3 HEIGHT (METERS) 58.1 w )> m )>
~
EXIT VEWCITY (MEI'ERS) 0.00 BLOO .MIN. CRS. SEC .AREA HEAT EMISSION RATE (SQ .METERS) (CAL/SEC) 2000.0 0.0
- ! :a 0 "ti z r-ALL GROUND LEVEL RELEASES.
s)> )>z z -I c
)>
r-
USNRC COMPUTER CODE - XOQDJQ, VERSION 2.0 RUN DATE: 970513
***** PALISADES XOQDJQ82 ***** USING 01/01/92 - 12/31/96 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING SPECIFIC POINTS OF INTEREST RELEASE TYPE OF DIRECTION DISTANCE X/Q XIQ X/Q D/Q ID LOCATION FROM SITE (MILES) (METERS) (SEC/CUB.METER) (SEC/CUB. METER) (SEC/CUB.METER) (PER SQ.METER) NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLETED UNDEPLETED LlEPLETED A SITE BOUNDARY NNE 0.50 805. 1. 72E-06 l.71E-06 1. 57E-06 8.19E-09 A SITE BOUNDARY NE 0.65 1046. 1.22E-06 1.22E-06 1.lOE-06 9.30E-09 0 A SITE BOUNDARY ENE 0.87 1400. 5.99E-07 "T1 5.98E-07 5.29E-07 4.SBE-09 "T1 A A SITE BOUNDARY SITE BOUNDARY E ESE 0.82
- 0. 76 1320.
1223. 7.28E-07 7.27E-07 6.45E-07 5.86E-09 en 7.B5E-07 7.B3E-07 6.9BE-07 A SITE BOUNDARY SE 0.63 1014. 7.04E-09 -I "tJ
)>
l.18E-06 l.18E-06 l.06E-06 1.14E-OB m r-A SITE BOUNDARY SSE 0.48 772. 2.13E-06 2.12E-06 l.95E-06 1.B6E-OB A SITE BOUNDARY s 0.42 676. 1.7BE-06 1.7BE-06 l.64E-06 l.16E-OB c en A SITE BOUNDARY SSW 0.48 772. 1.16E-06 l.15E-06 1. 06E-06 0 )> A GARDEN NNE 1. 60 2575. 3.06E-07 3.04E-07 2.5BE-07 6.26E-09 1.15E-09 en c A GARDEN 1.20 1931. m m NE 4.96E-07 4.95E-07 4.2BE-07 3.29E-09 -I :J:J A GARDEN ENE 2.70 4345. l.15E-07 1.14E-07 9.20E-OB 6.45E-10 )> CD (") en A GARDEN E 2.20 3541. 1.70E-07 l.69E-07 l.40E-07 1.07E-09 OJ ~- en
)>
r- 2 +::- A GARDEN ESE 2.30 3701. 1.51E-07 l.50E-07 l.23E-07 1.05E-09 r- (") c::: 0 A GARDEN SE 1. BO 2897. m 0 A GARDEN SSE 1.60 2575. 2.45E-07 3.55E-07 2.44E-07 3.53E-07 2.04E-07 2.99E-07 l.91E-09 2.44E-09 ~
- I c r
(") r-A GARDEN s 1. 50 2414. 2.7BE-07 2.77E-07 2.36E-07 l.3BE-09 w
....1'
)> )>m I\)
A BEEF COW 2.90 4667. A BEEF COW NE ENE 4.00 6437. 1.38E-07 6.51E-OB
- 1. 36E-07 6.43E-OB l.09E-07 4.9BE-08 7.06E-10 3.20E-10
- ! :J:J A BEEF COW E 3.50 5633.
0 "O B.64E-0B B.56E-OB 6.73E-OB 4.71E-10 2 r A BEEF COW A BEEF COW ESE SSE 4.00 3.00 6437. 4828. 6.70E-OB 1.41E-07 6.63E-OB 1.40E-07 5.13E-08 1.12E-07 3.93E-10
- 8. llE-10 s)> )>z A DAIRY COW SE 4.30 6920. 6.83E-08 6.75E-08 5.lBE-08 4.09E-10 A GOAT NE 3.20 5150. 1.19E-07 1.lBE-07 9.39E-08 5.93E-10 2 -I A GOAT ESE 3.00 4828. l.02E-07 1.0lE-07 B.lOE-08 6.55E-10 c
)>
VENT AND BUILDING PARAMETERS: r-RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMEl'ER (METERS) 0.00 BUILDJN:; HEIGHT (METERS) 58.1 EXIT VELOCITY (METERS) 0.00 BLDG.MIN.CHS.SEC.AREA (SQ .METERS) 2000.0 HEAT EMISSION RATE (CAL/SEC) a.a ALL GROUND LEVEL RELEASES.
- USNRC COMPUTER CODE - XOQOOQ, VERSION 2. 0 RUN DATE: 970513
***** PALISADES XOQOOQ82 ***** USING Ql/01/92 - 12/31/96 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONI'AINMENT BUILDING SPECIFIC POINTS OF INI'EREST RELEASE TYPE OF DIRECI'ION DISTANCE X/Q X/Q X/Q D/Q ID LOCATION FROM SITE (MILES) (METERS) (SEC/CUB. METER) (SEC/CUB.METER) (SEC/CUB.METER) (PER SQ.METER) NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLETED UNDEPLETED DEPLETED A SITE BOUNDARY NNE 0.50 805. l.72E-06 1.71E-06 l.57E-06 8.19E-09 0 A SITE BOUNDARY NE 0.65 1046. l.22E-06 1.22E-06 1.lOE-06 9.30E-09 "T1 A SITE BOUNDARY ENE 0.87 1400. 5.99E-07 5.98E-07 5.29E-07 4.58E-09 "T1 A SITE BOUNDARY E 0.82 1320. 7.28E-07 7.27E-07 6.45E-07 5.86E-09 rn A A SITE BOUNDARY SITE BOUNDARY ESE SE 0.76 0.63 1223. 1014. 7.85E-07 l.18E-06 7.83E-07 l.18E-06 6.98E-07 l.06E-06 7.04E-09 1.14E-08 rri ;g A SITE BOUNDARY SSE 0.48 772. 2.13E-06 2.12E-06 1.95E-06 1.86E-08 c r-A SITE BOUNDARY s 0.42 676. 1.78E-06 l.78E-06 1.64E-06 l.16E-08 0 rn A SITE BOUNDARY SSW 0.48 772. l.16E-06 1.15E-06 1. 06E-06 6.26E-09 rn l> A RESIDENCE NNE 1.10 1770. 5.23E-07 5.21E-07 4.55E-07 2.20E-09 mC
-I :::a m A RESIDENCE NE 1.20 1931. 4.96E-07 4.95E-07 4.28E-07 3.29E-09 l> CD o rn A RESIDENCE ENE 1.30 2092. 3.33E-07 3.31E-07 2.85E-07 2.30E-09 :s. l> z A
A RESIDENCE RESIDENCE E ESE 1.00 1.00 1609. 1609. 5.44E-07 5.21E-07 5.42E-07 5.20E-07 4.76E-07 4.56E-07 4.19E-09 4.42E-09
.-m o:J
~-
0 r- c: (") (") A RESIDENCE SE 1. 00 1609. 5.87E-07 5.86E-07 5.14E-07 5.25E-09 ::I c: r- m r-A RESIDENCE SSE 0.70 1127. 1.21E-06 l.20E-06 1.0BE-06 1. OOE-08 A RESIDENCE s 0.50 805. 1.38E-06 l.3BE-06 1.26E-06 8.79E-09 l> l> A RESIDENCE SSW 0.70 1127. 6.50E-07 6.49E-07 5.81E-07 3.37E-09 ::! :::a A BEEF COW NE 2.90 4667. 1.38E-07 1.36E-07 1. 09E-07 7.06E-10 0 "'ti A BEEF COW ENE 4.00 6437. 6.51E-OB 6.43E-OB 4.98E-08 3.20E-10 z r-A A BEEF COW BEEF COW E ESE 3.50 4.00 5633. 6437. B.64E-OB 6.70E-08 8.56E-OB 6.63E-08 6.73E-08 5.13E-08 4.71E-10 3.93E-10 s:l> l> z A BEEF COW DAIRY COW SSE SE 3.00 4.30 4828. 6920. 1.41E-07 6.83E-08 1.40E-07 6.75E-OB 1.12E-07 5.lBE-08 8.llE-10 4.09E-10 z -I A A GOAT NE 3.20 5150. 1.19E-07 l.18E-07 9.39E-08 5.93E-10 c: A GOAT ESE 3.00 4828. 1.02E-07 1. OlE-07 8.lOE-08 6.55E-10 .-l> VEN!' AND BUILDING PARl\Mfil'ERS: RELEASE HEIGHT (Mm'ERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (Mm'ERS) 0.00 BUILDING HEIGHT (METERS) 58.1 EXIT VELOCITY (METERS) 0.00 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2000.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.4 1997 PALISADES LAND USE CENSUS Distance to the nearest residence, garden, dairy/beef cattle, and goat in each sector.
SECTOR RESIDENCE GARDEN BEEF CATTLE DAIRY COW GOAT N >5 mi >5 mi >5 mi >5 mi >5 mi NNE 1.1 mi 1.6 mi >5 mi >5 mi >5 mi NE 1.2 mi 1.2 mi 2.9 mi >5 mi 3.2 mi ENE 1.3 mi 3.3 mi 4.0 mi >5 mi >5 mi E 1.0 mi 2.1 mi 3.5 mi >5 mi >5 mi ESE 1.0 mi 1.9 mi *4.0 mi >5 mi 3.0 mi SE 1.0 mi 1.0 mi *4.0 mi 4.3 mi >5 mi SSE 0.7 mi 1.6 mi >5 mi >5 mi >5 mi s 0.5 mi >5 mi >5 mi >5 mi 4.7 mi SSW 0.7 mi >5 mi >5 mi >5 mi >5 mi
*Note: Farm bisected by ESE/SE boundary line .
- 42
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 1.4a 1997 PALISADES LAND USE CENSUS Critical Receptor Items Distance Sector Miles Location/Description Item *X/Q (sec/m 3 l SSE 0.48 Site Boundary N/A 2.13E-06 s 0.50 Residence, Palisades Park; Residence 1.38E-06 1/2 mile west of 29th Avenue and Blue Star intersection SE 1.0 77550 28th Avenue Garden 5.87E-07 NE 2.9 18847 M-140, .25 miles N of Beef 1.38E-07 20th, West side of road Cattle SE 4.3 72401 36th Ave Dairy 6.83E-08 Cow NE 3.2 C Bernt Goat 1,19E-07 18019 M-140
*Based on Palisades 5-year composite meteorological data, 1992 - 1996 .
- 43
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 1.5 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES* DFR 1 DFY 2 DFS 1 DFB 2 Kr-85m 1.17(+3) 3 1.23(+3) 1.46(+3) 1.97(+3) Kr-85 1.61(+1) 1.72(+1) 1.34( +3) 1.95(+3) Kr-87 5.92( + 3) 6.17(+3) 9. 73( + 3) 1.03( +4) Kr-88 1.47(+4) 1.52( +4) 2.37( + 3) 2.93( + 3) Kr-89 1.66( +4) 1.73( +4) 1.01(+4) 1.06( + 4) Xe-131 m 9.15(+1) 1.56(+2) 4.76(+2) 1.11(+3)
- Xe-133m Xe-133 Xe-135m 2.51(+2) 2.94( + 2) 3.12(+3) 3.27( + 2) 3.53( + 2) 3.36( + 3) 9.94( + 2) 3.06(+2) 7 .11 ( + 2) 1.48(+3) 1.05( + 3) 7.39(+3)
Xe-135 1.81(+3) 1 .92( + 3) 1.86(+3) 2.46( + 3) Xe-137 1.42(+3) 1.51(+3) 1.22( +4) 1.27( +4) Xe-138 8.83( + 3) 9.21 ( +3) 4.13(+3) 4. 75( + 3) Ar-41 8.84( + 3) 9.30( + 3) 2.69( + 3) 3.28( +3)
- 1. mrem/y per µCi/m 3
- 2. mrad/y per µCi/m 3
- 3. 1.17(+3) = 1 .17x 0 3
*Dose factors for exposure to a semi-infinite cloud of noble gases. Values
- were obtained from USNRC Regulatory Guide 1.109, Revision 1 (October 1977).
44
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 1.6 STABLE ELEMENT TRANSFER DATA Fm - MILK (COW) Fm - MILK (GOAT) Ft - MEAT Biv ELEMENT lDAYS/U (DAYS/U (DAYS/KG) CVEG/SOIU H 1.0E-02 1. 7E-01 1.2E-02 4.8E-OO c 1.2E-02 1.0E-01 3.1 E-02 5.5E-OO Na 4.0E-02 4.0E-02 3.0E-02 5.2E-02 p 2.5E-02 2.5E-01 4.6E-02 1.1 E-00 Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.0E-02 6.6E-04 Co 1.0E-03 1.0E-03 1 .3E-02 9.4E-03 Ni 6.7E-03 6. 7E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 8.0E-03 1.2E-01 Zn 3.9E-02 3.9E-02 3.0E-02 4.0E-01 Rb 3.0E-02 3.0E-02 3.1 E-02 1.3E-01 Sr 8.0E-04 1.4E-02 6.0E-04 1.7E-02 y 1.0E-05 1.0E-05 4.6E-03 2.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 1.7E-04 Nb 2.5E-03 2.5E-03 2.8E-01 9.4E-03 Mo 7.5E-03 7.5E-03 8.0E-03 1 .2E-01 Tc 2.5E-02 2.5E-02 4.0E-01 2.5E-01 Ru 1.0E-06 1.0E-06 4.0E-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.5E-03 1.3E+01 Ag 5.0E-02 5.0E-02 1.7E-02 1.5E-01 Te 1.0E-03 1.0E-03 7.7E-02 1.3E-OO I 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1.2E-02 3.0E-01 4.0E-03 1.0E-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 2.0E-04 2.5E-03 Ce 1.0E-04 1.0E-04 1.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.7E-03 2.5E-03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03 w 5.0E-04 5.0E-04 1.3E-03 1.8E-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03
- 45
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.7 INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 BE10 9.49E-04 1.25E-04 2.65E-05 0. 0. 1.49E-03 1.73E-05 C14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 N13 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 F18 3.92E-06 0. 3.33E-07 0. 0. 0. 6.1 OE-07 NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 NA24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P32 1.45E-03 8.03E-05 5.53E-05 0. 0. 0. 1.15E-05 AR39 0. 0. 0. 0. 0. 1.00E-08 0. AR41 0. 0. 0. 0. 0. 3.14E-08 0. CA41 7.48E-05 0. 8.16E-06. 0. 0. 6.94E-02 2.96E-07 SC46 3.75E-04 5.41 E-04 1.69E-04 0. 3.56E-04 0. 2.19E-05 CR51 0. 0. 6.39E-08 4.11 E-08 9.45E-09 9.17E-06 2.55E-07 MN54 0. 1.81 E-05 3.56E-06 0. 3.56E-06 7.14E-04 5.04E-06 MN56 0. 1.1 OE-09 1.58E-10 0. 7.86E-10 8.95E-06 5.12E-05 FE55 1.41 E-05 8.39E-06 2.38E-06 0. 0. 6.21 E-05 7.82E-07 FE59 9.69E-06 1.68E-05 6.77E-06 0. 0. 7.25E-04 1.77E-05 C057 0. 4.65E-07 4.58E-07 0. 0. 2. 71 E-04 3.47E-06 -~
- 0. 8. 71 E-07 1.30E-06 0. 0. 5.55E-04 7.95E-06
- 0. 5.73E-06 8.41 E-06 0. 0. 3.22E-03 2.28E-05 1.81 E-05 5.44E-06 3.10E-06 0. 0. 5.48E-05 6.34E-07 Nl63 2.42E-04 1.46E-05 8.29E-06 0. 0. 1.49E-04 1.73E-06 Nl65 1. 71 E-09 2.03E-10 8.79E-11 0. 0. 5.80E-06 3.58E-05 CU64 0. 1.34E-09 5.53E-10 0. 2.84E-09 6.64E-06 1.07E-05 ZN65 1.38E-05 4.47E-05 2.22E-05 0. 2.32E-05 4.62E-04 3.67E-05 ZN69M+D 8.98E-09 1.84E-08 1.67E-09 0. 7.45E-09 1.91 E-05 2.92E-05 ZN69 3.85E-11 6.91 E-11 5.13E-12 0. 2.87E-11 1.05E-06 9.44E-06 SE79 0. 2.25E-06 4.20E-07 0. 2.47E-06 2.99E-04 3.46E-06 BR82 0. 0. 9.49E-06 0. 0. 0. 0.
BR83+D 0. 0. 2.72E-07 0. 0. 0. 0. BR84 0. 0. 2.86E-07 0. 0. 0. 0. BR85 0. 0. 1.46E-08 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 2.50E-09 0. KR85M 0. 0. 0. 0. 0. 1.31 E-08 0. KR85 0. 0. 0. 0. 0. 1.16E-08 0. KR87 0. 0. 0. 0. 0. 6.59E-08 0. KR88+D 0. 0. 0. 0. 0. 1.38E-07 0. KR89 0. 0. 0. 0. 0. 8.67E-08 0. RB86 0. 1.36E-04 6.30E-05 0. 0. 0. 2.17E-06 RB87 0. 7 .11 E-05 2.64E-05 0. 0. 0. 2.99E-07 RB88 0. 3.98E-07 2.05E-07 0. 0. 0. 2.42E-07 RB89+D 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08 SR89+D 2.84E-04 0. 8.15E-06 0. 0. 1.45E-03 4.57E-05 "1+0 SR90+D 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05 2+0 7.50E-09 0. 2.79E-10 0. 0. 1.70E-05 1.00E-04 Includes a 50% increase to account for percutaneous transpiration. 46
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.7 (continued)
INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 Y91 M +D 2.91E-10 0. 9.90E-12 0. 0. 1.99E-06 1.68E-06 Y91 4.20E-04 0. 1.12E-05 0. 0. 1.75E-03 5.02E-05 Y92 1.17E-08 0. 3.29E-10 0. 0. 1. 75E-05 9.04E-05 Y93 1.07E-07 0. 2.91 E-09 0. 0. 5.46E-05 1.19E-04 ZR93+D 2.24E-04 9.51 E-05 6.18E-05 0. 3.19E-04 1.37E-03 1.48E-05 ZR95+D 8.24E-05 1.99E-05 1.45E-05 0. 2.22E-05 1.25E-03 1.55E-05 ZR97+D 1.07E-07 1.83E-08 8.36E-09 0. 1.85E-08 7.88E-05 1.00E-04 NB93M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 NB95 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 NB97 2.44E-10 5.21 E-11 1.88E-11 0. 4.07E-11 2.37E-06 1.92E-05 M093 0. 6.46E-06 2.22E-07 0. 1.54E-06 3.40E-04 3.76E-06 M099+D 0. 1.18E-07 2.31 E-08 0. 1.89E-07 9.63E-05 3.48E-05 TC99M 9.98E-13 2.06E-12 2.66E-11 0. 2.22E-11 5.79E-07 1.45E-06 TC99 2.09E-07 2.68E-07 8.85E-08 0. 2.49E-06 6.77E-04 7.82E-06 TC101 4.65E-14 5.88E-14 5.80E-13 0. 6.99E-13 4.17E-07 6.03E-07 RU103+D 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E-05 f06+D RU105+D
~05 107 8.74E-10 6.20E-05 8.26E-09 0.
0. 0. 5.41 E-09 4.92E-07 2.93E-10 7.77E-06 3.63E-09 4.11 E-08 0. 0. 0. 0. 6.42E-10 7 .61 E-05 1.50E-08 2.75E-06 1 .12E-05 8.26E-03 2.08E-05 6.34E-05 3.46E-05 1.17E-04 1.37E-05 7.33E-07 109 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E-05 2.85E-05 AG110M +D 7.13E-06 5.16E-06 3.57E-06 0. 7.80E-06 2.62E-03 2.36E-05 AG111 3.75E-07 1.45E-07 7.75E-08 0. 3.05E-07 2.06E-04 3.02E-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.80E-04 1.40E-03 1.65E-05 CD115M 0. 1.73E-04 6.19E-06 0. 9.41 E-05 1.47E-03 5.02E-05 SN123 2.09E-04 4.21 E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.08E-05 SN125 + D 1 .01 E-05 2.51 E-07 6.00E-07 2.47E-07 0. 6.43E-04 7.26E-05 SN126+D 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05 SB124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05 SB125 + D 3.69E-05 3.41 E-07 7.78E-06 4.45E-08 0. 1.17E-03 1.05E-05 SB126 3.08E-06 6.01 E-08 1.11 E-06 2.35E-08 0. 6.88E-04 5.33E-05 SB127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E-05 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0. 3.19E-04 9.22E-06 TE127M+D 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1. 74E-05 TE129M+D 1.01 E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131M+D 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 TE131 +D 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132+D 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 TE133M+D 6.13E-11 3.59E-11 2.74E-11 5.52E-11 1.72E-10 3.92E-06 1.59E-05 TE134+D 3.18E-11 2.04E-11 1.68E-11 2.91 E-11 9.59E-11 2.93E-06 2.53E-06 1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.88E-05 0. 2.12E-07 1130 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 0. 1.42E-06 1+0 2.71 E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0. 7.56E-07 47
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1. 7 (continued)
INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU 1132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-04 2.82E-06 0. 1.36E-06 1133+0 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0. 1.54E-06 1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0. 9.21 E-07 1135 + D 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0. 1.31 E-06 XE131M 0. 0. 0. 0. 0. 6.77E-09 0. XE133M 0. 0. 0. 0. 0. 8.89E-09 0. XE133 0. 0. 0. 0. 0. 7.41 E-09 0. XE135M 0. 0. 0. 0. 0. 8.05E-09 0. XE135 0. 0. 0. 0. 0. 1.80E-08 0. XE137 0. 0. 0. 0. 0. 8.30E-08 0. XE138+D 0. 0. 0. 0. 0. 9.78E-08 0. CS134M+D 1.32E-07 2.1 OE-07 1.11 E-07 0. 8.50E-08 2.00E-08 1.16E-07 CS134 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07 CS135 1.00E-04 8.66E-05 4.73E-06 0. 2.58E-05 1.01 E-05 2.18E-07 CS136 3.45E"05 9.61 E-05 3.78E-05 0. 4.03E-05 8.40E-06 1.02E-06 CS137+D 3.92E-04 4.37E-04 3.25E-05 0. 1.23E-04 5.09E-05 9.53E-07 CS138 3.61 E-07 5.58E-07 2.84E-07 0. 2.93E-07 4.67E-08 6.26E-07 CS139+D 2.32E-07 3.03E-07 1.22E-07 0. 1.65E-07 2.53E-08 1.33E-08 A139 1.06E-09 7.03E-13 3.07E-11 0. 4.23E-13 4.25E-06 3.64E-05 J40+D 4.00E-05 4.00E-08 2.07E-06 0. 9.59E-09 1.14E-03 2.74E-05 41 +D 1.12E-10 7.70E-14 3.55E-12 0. 4.64E-14 2.12E-06 3.39E-06 A142+D 2.84E-11 2.36E-14 1.40E-12 0. 1.36E-14 1.11 E-06 4.95E-07 LA140 3.61 E-07 1.43E-07 3.68E-08 0. 0. 1.20E-04 6.06E-05 LA141 4.85E-09 1.40E-09 2.45E-10 0. 0. 1.22E-05 5.96E-05 LA142 7.36E-10 2.69E-10. 6.46E-11 0. 0. 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 0. 3.75E-06 3.69E-04 1.54E-05 CE143 + D 2.09E-07 1.38E-07 1.58E-08 0. 4.03E-08 8.30E-05 3.55E-05 CE144+D 2.28E-03 8.65E-04 1.26E-04 0. 3.84E-04 7.03E-03 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 0. 1.41E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 0. 4.80E-12 1.15E-06 3.06E-06 ND147+D 5.67E-06 5.81 E-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05 PM147 3.91 E-04 3.07E-05 1.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PM148M+D 5.00E-05 1.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05 PM149 3.10E-07 4.08E-08 1. 78E-08 0. 4.96E-08 6.50E-05 3.01 E-05 PM151 7.52E-08 1.10E-08 5.55E-09 0. 1.30E-08 3.25E-05 2.58E-05 SM151 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 1.53E-07 1.18E-07 9.06E-09 0. 2.47E-08 3.70E-05 1.93E-05 EU152 7.83E-04 1. 77E-04 1.72E-04 0. 5.94E-04 1.48E-03 9.88E-06 EU154 2.96E-03 3.46E-04 2.45E-04 0. 1.14E-03 3.05E-03 2.84E-05 EU155 5.97E-04 5.72E-05 3.46E-05 0. 1.58E-04 5.20E-04 5.19E-05 EU156 1.56E-05 9.59E-06 1.54E-06 0. 4.48E-06 6.12E-04 4.14E-05 TB160 1.12E-04 0. 1.40E-05 0. 3.20E-05 1.11 E-03 2.14E-05 H0166M 1.45E-03 3.07E-04 2.51 E-04 0. 4.22E-04 2.05E-03 1.65E-05 W181 4.86E-08 1.46E-08 1.67E-09 0. 0. 1.33E-05 2.63E-07 85 1.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.12E-05 87 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05 48
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.7 (continued)
INFANT INHALATION DOSE COMMITMENT FACTORS {MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210+ D 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05 81210+0 0. 1.33E-05 1.18E-06 0. 1.03E-04 9.96E-03 3.27E-05 P0210 2.98E-03 5.63E-03 7.12E-04 0. 1.30E-02 2.40E-01 4.36E-05 RN222+D 0. 0. 0. 0. 0. 9.88E-06 0. RA223+D 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04 RA224+D 1.77E-04 4.00E-07 3.54E-05 0. 7.30E-06 7.91 E-02 3.42E-04 RA225+D 2.57E-03 2.88E-06 5.13E-04 0. 5.31 E-05 2.57E-01 2.87E-04 RA226+D 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04 RA228+D 1.60E-01 7.61 E-06 1.80E-01 0. 1.53E-04 1.09E-OO 5.19E-05 AC225 3.69E-03 4.72E-03 2.48E-04 0. 3.49E-04 1.96E-01 2. 71 E-04 AC227+D 5.29E+OO 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+OO 5.27E-05 TH227+D 1.82E-03 3.03E-05 5.24E-05 0. 1.13E-04 3.27E-01 3.53E-04 TH228 + D 8.46E-01 1.1 OE-02 2.86E-02 0. 5.61 E-02 4.65E+OO 3.62E-04 TH229 1.34E+01 1.82E-01 6.62E-01 0. 8.99E-01 1.22E+01 3.29E-04 TH230 3.46E+OO 1. 79E-01 9.65E-02 0. 8.82E-01 2.1 BE+OO 3.87E-05 TH232+ D 3.86E+OO 1 .53E-01 2.29E-01 0. 7.54E-01 2.09E+OO 3.29E-05 t33 TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 1.62E-03 7.40E-05 PA231 +D 9.10E+OO 3.00E-01 3.62E-01 0. 1.62E+OO 3.85E-01 4.61 E-05 6.84E-06 1.32E-06 1.19E-06 0. 3.68E-06 2.19E-04 9.04E-06 2+D 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+OO 4.36E-05 3+D 5.44E-02 0. 3.83E-03 0. 1.09E-02 3.56E-01 4.03E-05 4 5.22E-02 0. 3.75E-03 0. 1.07E-02 3.49E-01 3.95E-05 U235 +D 5.01 E-02 0. 3.52E-03 0. 1.01 E-02 3.28E-01 5.02E-05 U236 5.01 E-02 0. 3.60E-03 0. 1.03E-02 3.35E-01 3.71E-05 U237 3.25E-07 0. 8.65E-08 0. 8.08E-07 9.13E-05 1.31 E-05 U238+D 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05 NP237+D 3.03E+OO 2.32E-01 1.26E-01 0. 7.69E-01 3.49E-01 5.1 OE-05 NP238 2.67E-06 6.73E-08 4.16E-08 0. 1.47E-07 9.19E-05 2.58E-05 NP239 2.65E-07 2.37E-08 1.34E-08 0. 4.73E-08 4.25E-05 1. 78E-05 PU238 5.02E+OO 6.33E-01 1 .27E-01 0. 4.64E-01 9.03E-01 4.69E-05 PU239 5.50E+OO 6. 72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 PU240 6.49E+OO 6. 71 E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05 PU241 +D 1 .55E-01 6.69E-03 3.11 E-03 0. 1.15E-02 7.62E-04 8.97E-07 PU242 5.09E+OO 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05 PU244 5.95E+OO 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+OO 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+OO 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01 E-05 AM243 1.82E+OO 8.1 OE-01 1 .27E-01 0. 7. 72E-01 3.85E-01 5.60E-05 CM242 8.58E-02 7.44E-02 5.70E-03 0. 1.69E-02 2.97E-01 5.1 OE-05 CM243 1.73E+00 7.94E-01 1.06E-01 0. 3.91 E-01 4.24E-01 5.02E-05 CM244 1.43E+OO 7.04E-01 8.89E-02 0. 3.21 E-01 4.08E-01 4.86E-05 CM245 2.26E+OO 8.80E-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 CM246 2.24E+OO 8.79E-01 1.36E-01 0. 5.23E-01 3.99E-01 4.45E-05 CM247+D 2.18E+OO 8.64E-01 1 .33E-01 0. 5.15E-01 3.92E-01 5.85E-05 CM248 1.82E+01 7.12E+OO 1.10E +00 0. 4.24E+OO 3.23E+00 9.43E-04 52 4.26E+OO 0. 1.01 E-01 0. 0. 1.37E +oo 1.85E-04 49
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.7 (contd)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 BE10 8.43E-04 9.83E-05 2.12E-05 0. 0. 7.41 E-04 1. 72E-05 C14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 F18 1.88E-06 0. 1.85E-07 0. 0. 0. 3.37E-07 NA22 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 NA24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P32 7.04E-04 3.09E-05 2.67E-05 0. 0. 0. 1.14E-05 AR39 0. 0. 0. 0. 0. 4.89E-09 0. AR41 0. 0. 0. 0. 0. 1.68E-08 0. CA41 7.06E-05 0. 7.70E-06 0. 0. 7.21 E-02 2.94E-07 SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.45E-05 CR51 0. 0. 4.17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 MN54 0. 1.16E-05 2.57E-06 0. 2.71 E-06 4.26E-04 6.19E-06 MN56 0. 4.48E-10 8.43E-11 0. 4.52E-10 3.55E-06 3.33E-05 FE55 1.28E-05 6.80E-06 2.1 OE-06 0. 0. 3.00E-05 7.75E-07 FE59 5.59E-06 9.04E-06 4.51 E-06 0. 0. 3.43E-04 1.91 E-05 C057 0. 2.44E-07 2.88E-07 0. 0. 1.37E-04 3.58E-06 C058 0. 4.79E-07 8.55E-07 0. 0. 2.99E-04 9.29E-06 60 0. 3.55E-06 6.12E-06 0. 0. 1.91 E-03 2.60E-05 9 1.66E-05 4.67E-06 2.83E-06 0. 0. 2.73E-05 6.29E-07 63 2.22E-04 1.25E-05 7.56E-06 0. 0. 7.43E-05 1.71 E-06 Nl65 8.08E-10 7.99E-11 4.44E-11 0. 0. 2.21 E-06 2.27E-05 CU64 0. 5.39E-10 2.90E-10 0. 1.63E-09 2.59E-06 9.92E-06 ZN65 1.15E-05 3.06E-05 1.90E-05 0. 1.93E-05 2.69E-04 4.41 E-06 ZN69M+D 4.26E-09 7.28E-09 8.59E-10 0. 4.22E-09 7.36E-06 2.71E-05 ZN69 1.81 E-11 2.61 E-11 2.41 E-12 0. 1.58E-11 3.84E-07 2.75E-06 SE79 0. 1.23E-06 2.60E-07 0. 1.71 E-06 1.49E-04 3.43E-06 BR82 0. 0. 5.66E-06 0. 0. 0. 0. BR83+D 0. 0. 1.28E-07 0. 0. 0. 0. BR84 0. 0. 1.48E-07 0. 0. 0. 0. BR85 0. 0. 6.84E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 1.22E-09 0. KR85M 0. 0. 0. 0. 0. 6.58E-09 0. KR85 0. 0. 0. 0. 0. 5.66E-09 0. KR87 0. 0. 0. 0. 0. 3.38E-08 0. KR88+D 0. 0. 0. 0. 0. 6.99E-08 0. KR89 0. 0. 0. 0. 0. 4.55E-08 0. RB86 0. 5.36E-05 3.09E-05 0. 0. 0. 2.16E-06 RB87 0. 3.16E-05 1.37E-05 0. 0. 0. 2.96E-07 RB88 0. 1.52E-07 9.90E-08 0. 0. 0. 4.66E-09 RB89+D 0. 9.33E-08 7.83E-08 0. 0. 0. 5.11E-10 SR89+D 1.62E-04 0. 4.66E-06 0. 0. 5.83E-04 4.52E-05 SR90+D 2.73E-02 0. 1.74E-03 0. 0. 3.99E-03 9.28E-05 SR91 +D 3.28E-08 0. 1.24E-09 0. 0. 1.44E-05 4.70E-05 2+D 3.54E-09 0. 1.42E-10 0. 0. 6.49E-06 6.55E-05
*Includes a 50% increase to account for percutaneous transpiration.
50
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1 . 7 (contd)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 1.11 E-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 Y91 M+D 1.37E-10 0. 4.98E-12 0. 0. 7.60E-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 0. 0. 7.10E-04 4.97E-05 Y92 5.50E-09 0. 1.57E-10 0. 0. 6.46E-06 6.46E-05 Y93 5.04E-08 0. 1.38E-09 0. 0. 2.01 E-05 1.05E-04 ZR93+D 2.07E-04 7.80E-05 5.55E-05 0. 3.00E-04 7.10E-04 1.47E-05 ZR95+D 5.13E-05 1.13E-05 1.00E-05 0. 1.61 E-05 6.03E-04 1.65E-05 ZR97+D 5.07E-08 7.34E-09 4.32E-09 0. 1.05E-08 3.06E-05 9.49E-05 NB93M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06 NB95 6.35E-06 2.48E-06 1.77E-06 0. 2.33E-06 1.66E-04 1.00E-05 NB97 1.16E-10 2.08E-11 9.74E-12 0. 2.31 E-11 9.23E-07 7.52E-06 M093 0. 3.76E-06 1.35E-07 0. 1.06E-06 1.70E-04 3.78E-06 M099+D 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05 TC99M 4.81E-13 9.41E-13 1.56E-11 0. 1.37E-11 2.57E-07 1.30E-06 TC99 1.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06 TC101 2.19E-14 2.30E-14 2.91 E-13 0. 3.92E-13 1.58E-07 4.41 E-09 RU103+D 7.55E-07 0. 2.90E-07 0. 1.90E-06 1. 79E-04 1.21 E-05 -05 RU105+D 4.13E-10 0. 1.50E-10 0. 3.63E-10 4.30E-06 2.69E-05 RU106+D 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1.16E-04 3.91 E-09 2.1 OE-09 1. 79E-09 0. 8.39E-09 7.82E-06 1.33E-05 07 0. 2.65E-07 2.51 E-08 0. 1.97E-06 3.16E-05 7.26E-07 09 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 AG110M+D 4.56E-06 3.08E-06 2.47E-06 0. 5.74E-06 1.48E-03 2. 71 E-05 AG111 1.81 E-07 5.68E-08 3.75E-08 0. 1.71 E-07 7.73E-05 2.98E-05 CD113M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 1.63E-05 CD115M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05 SN123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 0. 9.59E-04 4.05E-05 SN125+D 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05 SN126 + D 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1.63E-05 SB124 1.55E-05 2.00E-07 5.41 E-06 3.41 E-08 0. 8.76E-04 4.43E-05 SB125 + D 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 1.09E-05 SB126 1. 72E-06 2.62E-08 6.16E-07 1.00E-08 0. 2.86E-04 5.67E-05 SB127 1.36E-07 2.09E-09 4.70E-08 1.51 E-09 0. 6.17E-05 3.82E-05 TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TE127M + D 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1. 72E-05 4.00E-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71E-06 1.52E-05 TE129M+D 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE131 M + D 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 +D 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE132+D 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 TE133M+D 2.93E-11 1 . 51 E-11 1.50E-11 2.32E-11 1.01E-10 1.60E-06 4.77E-06 TE134+ D 1.53E-11 8.81 E-12 9.40E-12 1.24E-11 5.71 E-11 1.23E-06 4.87E-07 1129 1.05E-05 6.40E-06 5. 71 E-06 4.28E-03 1.08E-05 0. 2.15E-07 1130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 0. 1.38E-06 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07 .1+D 51
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 1.7 (contd) CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 5.72E-07 1.1 OE-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07 1133 + D 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0. 1.48E-06 1134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0. 2.58E-07 1135 + D 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0. 1.20E-06 XE131 M 0. 0. 0. 0. 0. 3.30E-09 0. XE133M 0. 0. 0. 0. 0. 4.36E-09 0. XE133 0. 0. 0. 0. 0. 3.66E-09 0. XE135M 0. 0. 0. 0. 0. 4.48E-09 0. XE135 0. 0. 0. 0. 0. 9.09E-09 0. XE137 0. 0. 0. 0. 0. 4.07E-08 0. XE138 + D 0. 0. 0. 0. 0. 5.17E-08 0. CS134M+D 6.33E-08 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08 CS134 1.76E-04 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06 CS135 6.23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07 CS136 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.13E-06 CS137+D 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81 E-05 9.78E-07 CS138 1. 71 E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E-08 CS139+D 1.09E-07 1 .15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7 .23E-12 A139 4.98E-10 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 1.56E-05
~40+D 2.00E-05 1.75E-08 1.17E-06 0. 5. 71 E-09 4.71 E-04 2.7,5E-05 41 +D 5.29E-11 2.95E-14 1.72E-12 0. 2.56E-14 7.89E-07 7.44E-08 A142+D 1.35E-11 9.73E-15 7.54E-13 0. 7.87E-15 4.44E-07 7.41E-10 LA140 1.74E-07 6.08E-08 2.04E-08 0. 0. 4.94E-05 6.1 OE-05 LA141 2.28E-09 5.31E-10 1.15E-10 0. 0. 4.48E-06 4.37E-05 LA142 3.50E-10 1 .11E-10 3.49E-11 0. 0. 2.35E-06 2.05E-05 CE141 1.06E-05 5.28E-06 7.83E-07 0. 2.31 E-06 1.47E-04 1.53E-05 CE143+D 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05 CE144+D 1.83E-03 5.72E-04 9.77E-05 0. 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11 E-07 1.17E-04 2.63E-05 PR144 1 .61 E-11 4.99E-12 8.10E-13 0. 2.64E-12 4.23E-07 5.32E-08 ND147+D 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-05 PM147 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 PM148M+D 3.31 E-05 6.55E-06 6.55E-06 0. 9.74E-06 5.72E-04 3.58E-05 PM148 1.61 E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.01 E-05 PM149 1.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 PM151 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 1.24E-05 2.50E-05 SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM153 7.24E-08 4.51 E-08 4.35E-09 0. 1.37E-08 1.37E-05 1.87E-05 EU152 7.42E-04 1.37E-04 1.61 E-04 0. 5.73E-04 9.00E-04 1.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0. 1.09E-03 1.66E-03 2.98E-05 EU155 5.60E-04 4.05E-05 3.18E-05 0. 1.51 E-04 2.79E-04 5.39E-05 EU156 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05 TB160 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 H0166M 1.34E-03 2.81 E-04 2.37E-04 0. 4.01 E-04 1.13E-03 1.63E-05 W181 2.66E-08 6.52E-09 8.99E-10 0. 0. 5.71E-06 2.61 E-07 8.31 E-07 2.08E-07 2.91 E-08 0. 0. 1.86E-04 1.11 E-05
.85 4.41 E-09 2.61 E-09 1.17E-09 87 0. 0. 1.11 E-05 2.46E-05 52
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1. 7 (contd)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU PB210+D 8.03E-02 1 .85E-02 3.18E-03 0. 6.31 E-02 8. 74E-02 3. 75E-05 81210+0 0. 5.11 E-06 5.65E-07 0. 5. 76E-05 3. 70E-03 3.21 E-05 P0210 1. 70E-03 2. 76E-03 4.09E-04 0. 8.85E-03 1 .05E-01 4.32E-05 RN222+D 0. 0. 0. 0. 0. 4.82E-06 0. RA223+D 7.69E-04 8.89E-07 1.54E-04 0. 2.36E-05 8.48E-02 3.00E-04 RA224+D 8.44E-05 1.53E-07 1.69E-05 0. 4.06E-06 2.92E-02 3.34E-04 RA225+D 1 .28E-03 1.14E-06 2.56E-04 0. 3.02E-05 9. 74E-02 2.84E-04 RA226+D 2.34E-01 7 .66E-06 1 .92E-01 0. 2.03E-04 3.90E-01 3.02E-04 RA228+D 1 .49E-01 3.94E-06 1.68E-01 0. 1.04E-04 5.37E-01 5.14E-05 AC225 1.81 E-03 1.87E-03 1.21 E-04 0. 1 .99E-04 7 .37E-02 2.67F04 AC227+D 4.96E +00 8.05E-01 3.07E-01 0. 1.77E-01 8.04E-01 5.22E-05 TH227+D 9.24E-04 1 .26E-05 2.67E-05 0. 6.67E-05 1.26E-01 3.49E-04 TH228+D 8.06E-01 1 .04E-02 2. 72E-02 0. 5.41E-02 3.34E+OO 3.59E-04 TH229 1.28E+01 1. 76E-01 6.31 E-01 0. 8.68E-01 1.04E + 01 3.27E-04 TH230 3.30E + 00 1. 73E-01 9.20E-02 0. 8.52E-01 1.85E + 00 3.84E-05 TH232+D 3.68E + 00 1.47E-01 1.28E-01 0. 7.28E-01 1.77E+OO 3.27E-05 TH234 6.94E-06 3.07E-07 2.00E-07 0. 1.62E-06 6.31 E-04 7.32E-05 PA231 +D 8.62E+OO 2.86E-01 3.43E-01 0. 1.56E+00 1.92E-01 4.57E-05 PA233 4.14E-06 6.48E-07 7.25E-07 0. 2.38E-06 9. 77E-05 8.95E-06 2+D 2.19E-01 0. 1.56E-02 0. 1 .67E-02 7 .42E-01 4.33E-05 3+D 4.64E-02 0. 2.82E-03 0. 7 .62E-03 1. 77E-01 4.00E-05 34 4.46E-02 0. 2. 76E-03 0. 7 .47E-03 1. 74E-01 3.92E-05 U235+D 4.27E-02 0. 2.59E-03 0. 7.01 E-03 1.63E-01 4.98E-05 U236 4.27E-02 0. 2.65E-03 0. 7.16E-03 1.67E-01 3.67E-05 U237 1.57E-07 0. 4.17E-08 0. 4.53E-07 3.40E-05 1 .29E-05 U238+D 4.09E-02 0. 2.42E-03 0. 6.55E-03 1.53E-01 3.51 E-05 NP237+D 2.88E+OO 2.21E-01 1.19E-01 0. 7.41 E-01 1.74E-01 5.06E-05 NP238 1 .26E-06 2.56E-08 1.97E-08 0. 8.16E-08 3.39E-05 2.50E-05 NP239 1.26E-07 9.04E-09 6.35E-09 0. 2.63E-08 1.57E-05 1.73E-05 PU238 4.77E+OO 6.05E-01 1.21E-01 0. 4.47E-01 6.08E-01 4.65E-05 PU239 5.24E + 00 6.44E-01 1.28E-01 0. 4.78E-01 5.72E-01 4.24E-05 PU240 5.23E + 00 6.43E-01 1.27E-01 0. 4.77E-01 5.71 E-01 4.33E-05 PU241 +D 1 .46E-01 6.33E-03 2.93E-03 0. 1.1 OE-02 5.06E-04 8.90E-07 PU242 4.85E + 00 6.20E-01 1.23E-01 0. 4.60E-01 5.50E-01 4.16E-05 PU244 5.67E+OO 7.10E-01 1.41E-01 0. 5.27E-01 . 6.30E-01 6.20E-05 AM241 1.74E+OO 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05 AM242M 1.79E+OO 7.65E-01 1.27E-01 0. 7.71E-01 8.14E-02 5.96E-05 AM243 1.72E+OO 7.53E-01 1.20E-01 0. 7.42E-01 1.92E-01 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03 0. 1.34E-02 1.31 E-01 5.06E-05 CM243 1.61E+OO 7.33E-01 9.95E-02 0. 3. 74E-01 2.1 OE-01 4.98E-05 CM244 1.33E+OO 6.48E-01 8.31E-02 0. 3.06E-01 2.02E-01 4.82E-05 CM245 2.14E + 00 8.16E-01 1.28E-01 0. 5.03E-01 1.95E-01 4.49E-05 CM246 2.13E + 00 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41 E-05 CM247+D 2.07E + 00 8.02E-01 1 .26E-01 0. 4.95E-01 1.95E-01 5.80E-05 CM248 1.72E+01 6.61E+OO 1.04E+OO 0. 4.08E+OO 1.61E+OO 9.35E-04 52 3.92E + 00 0. 9.33E-02 0. 0. 6.62E-01 1 .84E-04 53
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1. 7 (contd}
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU H3* 0. 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 BE10 2.78E-04 4.33E-05 7.09E-06 0. 0. 3.84E-04 1. 77E-05 C14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 N13 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 F18 6.52E-07 0. 7.1 OE-08 0. 0. 0. 3.89E-08 NA22 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1. 76E-05 1.76E-05 1.76E-05 NA24 1. 72E-06 1. 72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P32 2.36E-04 1.37E-05 8.95E-06 0. 0. 0. 1.16E-05 AR39 0. 0. 0. 0. 0. 4.00E-09 0. AR41 0. 0. 0. 0. 0. 1.44E-08 0. CA41 4.05E-05 0. 4.38E-06 0. 0. 1 .01 E-01 3.03E-07 SC46 7.24E-05 1.41 E-04 4.18E-05 0. 1.35E-04 0. 2.98E-05 CR51 0. 0. 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN54 0. 6.39E-06 1.05E-06 0. 1.5_9E-06 2.48E-04 8.35E-06 MN56 0. 2.12E-10 3.15E-11 0. 2.24F-10 1.90E-06 7.18E-06 FE55 4.18E-06 2.98E-06 6.93E-07 0. 0. 1.55E-05 7.99E-07 FE59 1.99E-06 4.62E-06 1.79E-06 0. 0. 1.91 E-04 2.23E-05 C057 0. 1.18E-07 1.15E-07 0. 0. 7.33E-05 3.93E-06 C058 0. 2.59E-07 3.47E-07 0. 0. 1.68E-04 1.19E-05 0 0. 1.89E-06 2.48E-06 0. 0. 1.09E-03 3.24E-05 9 5.44E-06 2.02E-06 9.24E-07 0. 0. 1.41 E-05 6.48E-07 63 7.25E-05 5.43E-06 2.47E-06 0. 0. 3.84E-05 1.77E-06 Nl65 2.73E-10 3.66E-11 1.59E-11 0. 0. 1 .17E-06 4.59E-06 CU64 0. 2.54E-10 1.06E-10 0. 8.01E-10 1.39E-06 7.68E-06 ZN65 4.82E-06 1.67E-05 7.80E-06 0. 1.08E-05. 1.55E-04 5.83E-06 ZN69M+D 1.44E-09 3.39E-09 3.11E-10 0. 2.06E-09 3.92E-06 2.14E-05 ZN69 6.04E-12 1 . 15E-11 8.07E-13 0. 7.53E-12 1.98E-07 3.56E-08 SE79 0. 5.43E-07 8. 71 E-08 0. 8.13E-07 7.71 E-05 3.53E-06 BR82 0. 0. 2.28E-06 0. 0. 0. 0. BR83+D 0. 0. 4.30E-08 0. 0. 0. 0. BR84 0. 0. p.41 E-08 0. 0. 0. 0. BR85 0. 0. 2.29E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 9.97E-10 0. KR85M 0. 0. 0. 0. 0. 5.46E-09 0. KR85 0. 0 .. 0. 0. 0. 4.63E-09 0. KR87 0. 0. 0. 0. 0. 2.82E-08 0. KR88+D 0. 0. 0. 0. 0. 5.81 E-08 0. KR89 0. 0. 0. 0. 0. 3.85E-08 0. RB86 0. 2.38E-05 1.05E-05 0. 0. 0. 2.21E-06 RB87 0. 1.40E-05 4.58E-06 0. 0. 0. 3.05E-07 RB88 0. 6.82E-08 3.40E-08 0. 0. 0. 3.65E-15 RB89+D 0. 4.40E-08 2.91 E-08 0. 0. 0. 4.22E-17 SR89 ;t-D 5.43E-05 0. 1.56E-06 0. 0. 3.02E-04 4.64E-05 SR90+D 1.35E-02 0. 8.35E-04 0. 0. 2.06E-03 9.56E-05 SR91 + D 1.1 OE-08 0. 4.39E-10 0. 0. 7.59E-06 3.24E-05 1.19E-09 0. 5.08E-11 0. 0. 3.43E-06 1.49E-05 .2+D
*Includes a 50% increase to account for percutaneous transpiration.
54
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.7 (contd)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU Y90 3.73E-07 0. 1.00E-08 0. 0. 3.66E-05 6.99E-05 Y91M+D 4.63E-11 0. 1. 77E-12 0. 0. 4.00E-07 3. 77E-09 Y91 8.26E-05 0. 2.21 E-06 0. 0. 3.67E-04 5.11 E-05 Y92 1.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05 Y93 1.69E-08 0. 4.65E-10 0. 0. 1.04E-05 7.24E-05 ZR93+D 6.83E-05 3.38E-05 1.84E-05 0. 1.16E-04 3.67E-04 1.60E-05 ZR95 +D 1.82E-05 5.73E-06 3.94E-06 0. 8.42E-06 3.36E-04 1.86E-05 ZR97+D 1.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05 NB93M 4.14E-05 1.36E-05 3.41 E-06 0. 1.59E-05 5.36E-05 2.52E-06 NB95 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21E-05 NB97 3.92E-11 9.72E-12 3.55E-12 0. 1 . 14E-11 4.91 E-07 2.71E-07 M093 0. 1.66E-06 4.52E-08 0. 5.06E-07 8.81 E-05 3.99E-06 M099+D 0. 2.11 E-08 4.03E-09 0. 5.14E-08 1.92E-05 3.36E-05 TC99M 1.73E-13 4.83E-13 6.24E-12 0. 7.20E-12 1.44E-07 7.66E-07 TC99 4.48E-08 6.58E-08 1.79E-08 0. 8.35E-07 1.74E-04 7.99E-06 TC101 7.40E-15 1.05E-14 1.03E-13 0. 1.90E-13 8.34E-08 1.09E-16 RU103+D 2.63E-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 1.36E-05 t06+D RU105+D 105 07 1.40E-10 1.23E-05 1.32E-09 0. 0. 0. 9.48E-10 1.17E-07 5.42E-11 1.55E-06 6.24E-10 8.39E-09 0. 0. 0. 0. 1.76E-10 2.38E-05 4.04E-09 9.39E-07 2.27E-06 2.01 E-03 4.09E-06 1.63E-05 1.13E-05 1.20E-04 1.23E-05 7.49E-07 09 0. 6.56E-10 1.66E-10 0. 3.36E-09 3.19E-06 1.96E-05 AG110M+D 1.73E-06 1.64E-06 9.99E-07 0. 3.13E-06 8.44E-04 3.41 E-05 AG111 6.07E-08 2.52E-08 1.26E-08 0. 8.17E-08 4.00E-05 3.00E-05 CD113M 0. 2.17E-04 7.1 OE-06 0. 2.43E-04 3.59E-04 1.68E-05 CD115M 0. 3.48E-05 1.14E-06 0. 2.82E-05 3.03E-04 5.1 OE-05 SN123 4.31 E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 SN125+D 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 SN126+D 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1. 72E-03 1.68E-05 SB124 5.38E-06 9.92E-08 2.1 OE-06 1.22E-08 0. 4.81 E-04 4.98E-05 SB125 + D 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05 SB126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.01 E-05 SB127 4.64E-08 9.92E-10 1.75E-08 5.21E-10 0. 3.31 E-05 3.94E-05 TE125M 6.1 OE-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06 TE127M+D 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01 E-05 TE129M + D 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE131M+D 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131 +D 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132+D 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 TE133M + D 1 .01 E-11 7.33E-12 5. 71 E-12 8.18E-12 5.07E-11 8.71E-07 1.23E-07 TE134+D 5.31 E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-11 6.75E-07 1.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0. 1.14E-06 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0. 8.11E-07 .1+D 55
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1. 7 (contd)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU 1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. 1.59E-07 1133 + 0 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0. 1.29E-06 1134 1.11 E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0. 2.55E-09 1135 + 0 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0. 8.69E-07 XE131 M 0. 0. 0. 0. 0. 2.70E-09 0. XE133M 0. 0. 0. 0. 0. 3.59E-09 0. XE133 0. 0. 0. 0. 0. 2.99E-09 0. XE135M 0. 0. 0. 0. 0. 3.88E-09 0. XE135 0. 0. 0. 0. 0. 7.55E-09 0. XE137 0. 0. 0. 0. 0. 3.33E-08 0. XE138+0 0. 0. 0. 0. 0. 4.38E-08 0. CS134M+O 2.20E-08 4.35E-08 2.35E-08 0. 2.54E-08 4.56E-09 2.02E-08 CS134 6.28E-05 1.41 E-04 6.86E-05 0. 4.69E-05 1.83E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07 CS136 6.44E-06 2.42E-05 1. 71 E-05 0. 1.38E-05 2.22E-06 1.36E-06 CS137+0 8.38E-05 1.06E-04 3.89E-05 0. 3.80E-05 1.51E-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 0. 8.28E-08 .9.84E-09 3.38E-11 CS139+0 3.65E-08 5.12E-08 1.97E-08 0. 4.34E-08 4.86E-09 1.66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 0. 1 . 11 E-13 8.08E-07 8.06E-07 140+0 6.84E-06 8.38E-09 4.40E-07 0. 2.85E-09 2.54E-04 2.86E-05 41 +O 1.78E-11 1.32E-14 5.93E-13 0. 1.23E-14 4.11 E-07 9.33E-14 142+0 4.62E-12 4.63E-15 2.84E-13 0. 3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.09E-05 LA141 7.63E-10 2.35E-10 3.87E-11 0. 0. 2.31 E-06 1.54E-05 LA142 1.20E-10 5.31 E-11 1.32E-11 0. 0. 1.27E-06 1.50E-06 CE141 3.55E-06 2.37E-06 2.71E-07 0. 1.11 E-06 7.67E-05 1.58E-05 CE143+0 3.32E-08 2.42E-08 2.70E-09 0. 1.08E-08 1.63E-05 3.19E-05 CE144+0 6.11 E-04 2.53E-04 3.28E-05 0. 1.51 E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 0. 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 0. 1.26E-12 2.19E-07 2.94E-14 N0147+0 9.83E-07 1.07E-06 6.41 E-08 0. 6.28E-07 4.65E-05 2.28E-05 PM147 1.15E-04 1.1 OE-05 4.50E-06 0. 2.1 OE-05 1.14E-04 5.87E-06 PM148M+O 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.1 OE-05 PM148 5.44E-07 8.88E-08 4.48E-08 0. 1.60E-07 6.52E-05 6.14E-05 PM149 4.91 E-08 6.89E-09 2.84E-09 0. 1.31 E-08 1.24E-05 2.79E-05 PM151 1.20E-08 1.99E-09 1.01 E-09 0. 3.57E-09 6.56E-06 2.27E-05 SM151 1.07E-04 2.1 OE-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.01 E-08 1.47E-09 0. 6.56E-09 7.11 E-06 1. 77E-05 EU152 2.96E-04 7.19E-05 6.30E-05 0. 3.34E-04 5.01 E-04 1.35E-05 EU154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05 EU155 2.00E-04 1.96E-05 1.21E-05 0. 7.65E-05 1.51 E-03 5.97E-05 EU156 2.70E-06 2.03E-06 3.30E-07 0. 1.36E-06 1.37E-04 4.56E-05 TB160 3.04E-05 0. 3.79E-06 0. 1.20E-05 2.97E-04 2.60E-05 H0166M 4.40E-04 1.36E-04 9.87E-05 0. 2.00E-04 6.24E-04 1.68E-05 W181 8.90E-09 2.88E-09 3.01E-10 0. 0. 2.95E-06 2.69E-07 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 1.14E-05 .85 87 1.50E-09 1.22E-09 4.29E-10 0. 0. 5.92E-06 2.21 E-05 56
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.7 (contd)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU PB210+D 3.09E-02 8.28E-03 1.07E-03 0. 2.95E-02 4.52E-02 3.87E-05 Bl210+D 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91E-03 3.19E-05 P0210 5.68E-04 1.22E-03 1.37E-04 0. 4.21E-03 5.41E-02 4.45E-05 RN222+D 0. 0. 0. 0. 0. 3.94E-06 0. RA223+D 2.57E-04 3.93E-07 5.14E-05 0. 1 .12E-05 4.39E-02 3.04E-04 RA224+D 2.83E-05 6. 77E-08 5.65E-06 0. 1.93E-06 1.51 E-02 3.29E-04 RA225+D 4.28E-04 5.04E-07 8.56E-05 0. 1.44E-05 5.04E-02 2.89E-04 RA226+D 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-01 3.11 E-04 RA228+D 5.34E-02 1. 74E-06 5.88E-02 0. 4.97E-05 2.78E-01 5.30E-05 AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81E-02 2.70E-04 AC227+D 2.49E+OO 3.69E-01 1.48E-01 0. 1.07E-01 4.16E-01 5.38E-05 TH227+D 3.09E-04 5.56E-06 8.93E-06 0. 3.18E-05 6.50E-02 3.57E-04 TH228 + D 2.60E-01 4.37E-03 8. 78E-03 0. 2.45E-02 1.69E + 00 3. 70E-04 TH229 9.06E+OO 1.36E-01 4.45E-01 0. 6.67E-01 5.05E + 00 3.36E-04 TH230 2.34E+OO 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05 TH232 + D 2.61E+OO 1.14E-01 9.21E-02 0. 5.60E-01 8.60E-01 3.36E-05 TH234 2.32E-06 1.35E-07 6. 71 E-08 0. 7. 73E-07 3.26E-04 7 .49E-05 PA231 +D 5.32E + 00 2.00E-01 2.07E-01 0. 1.12E + 00 9.91 E-02 4. 71 E-05 PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.00E-05 2+D 7.31 E-02 0. 5.23E-03 0. 7 .94E-03 3.84E-01 4.46E-05 3+D 1.55E-02 0. 9.42E-04 0. 3.63E-03 9.18E-02 4. 12E-05 234 1 .48E-02 0. 9.23E-04 0. 3.55E-03 8.99E-02 4.04E-05 U235+D 1 .42E-02 0. 8.67E-04 0. 3.34E-03 8.44E-02 5.13E-05 U236 1 .42E-02 0. 8.86E-04 0. 3.41 E-03 8.62E-02 3. 79E-05 U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1. 76E-05 1.29E-05 U238+D 1.36E-02 0. 8.1 OE-04 0. 3.12E-03 7.89E-02 3.62E-05 NP237+D 1.77E+OO 1.54E-01 7.21E-02 0. 5.35E-01 8.99E-02 5.22E-05 NP238 4.23E-07 1 .13E-08 6.59E-09 0. 3.88E-08 1. 75E-05 2.38E-05 NP239 4.23E-08 3.99E-09 2.21 E-09 0. 1.25E-08 8.11 E-06 1 .65E-05 PU238 2.86E+OO 4.06E-01 7.22E-02 0. 3.1 OE-01 3.12E-01 4. 79E-05 PU239 3.31E+00 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05 PU240 3.31E+OO 4.49E-01 8.04E-02 0. 3.43E-01 2.93E-01 4.46E-05 PU241 +D 6.97E-02 3.57E-03 1.40E-03 0. 6.47E-03 2.60E-04 9.17E-07 PU242 3.07E+OO 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05 PU244 3.59E+OO 4.96E-01 8.88E-02 0. 3. 79E-01 3.23E-01 6.39E-05 AM241 1.06E+00 4.07E-01 7 .1 OE-02 0. 5.32E-01 1.05E-01 4.88E-05 AM242M 1.07E+OO 3.93E-01 7.15E-02 0. 5.30E-01 4.21E-02 6.14E-05 AM243 1.06E + 00 3.92E-01 6.95E-02 0. 5.21 E-01 9.91 E-02 5.72E-05 CM242 2.12E-02 2.14E-02 1.41 E-03 0. 6.40E-03 6.76E-02 5.21E-05 CM243 8.45E-01 3.50E-01 5.00E-02 0. 2.34E-01 1.09E-01 5.13E-05 CM244 6.46E-01 3.03E-01 3.88E-02 0. 1.81 E-01 1.05E-01 4.96E-05 CM245 1.32E+OO 4.11E-01 7.53E-02 0. 3.52E-01 1.01 E-01 4.63E-05 CM246 1.31E+OO 4.11E-01 7.52E-02 0. 3.51 E-01 1.03E-01 4.54E-05 CM247+D 1.28E + 00 4.04E-01 7 .41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05 CM248 1.06E + 01 3.33E + 00 6.11 E-01 0. 2.85E + 00 8.32E-01 9.63E-04 1.29E+00 0. 3.07E-02 0. 0. 3.43E-01 1.89E-04 .52 57
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1. 7 (contd)
ADULT INHALATION DOSE COMMITMENT FACTORS {MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU H3* 0. 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 BE10 1.98E-04 3.06E-05 4.96E-06 0. 0. 2.22E-04 1.67E-05 C14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 N13 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 F18 4. 71 E-07 0. 5.19E-08 0. 0. 0. 9.24E-09 NA22 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 NA24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P32 1.65E-04 9.64E-06 6.26E-06 0. 0. 0. 1.08E-05 AR39 0. 0. 0. 0. 0. 2.08E-09 0. AR41 0. 0. 0. 0. 0. 8.06E-09 0. CA41 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86E-07 SC46 5.51 E-05 1.07E-04 3.11 E-05 0. 9.99E-05 0. 3.23E-05 CR51 0. 0. 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN54 0. 4.95E-06 7.87E-07 0. 1.23E-06 1.75E-04 9.67E-06 MN56 0. 1.55E-10 2.29E-11 0. 1.63E-10 1.18E-06 2.53E-06 FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.01 E-06 7.54E-07 FE59 1.47E-06 3.47E-06 1.32E-06 0. 0. 1.27E-04 2.35E-05 C057 0. 8.65E-08 8.39E-08 0. 0. 4.62E-05 3.93E-06 C058 0. 1.98E-07 2.59E-07 0. 0. 1.16E-04 1.33E-05 60 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-05 9 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.11E-07 63 5.40E-05 3.93E-06 1.81 E-06 0. 0. 2.23E-05 1.67E-06 Nl65 1.92E-10 2.62E-11 1.14E-11 0. 0. 7.00E-07 1.54E-06 CU64 0. 1.83E-10 7.69E-11 0. 5.78E-10 8.48E-07 6.12E-06 ZN65 4.05E-06 1.29E-05 5.82E-06 0. 8.62E-06 1.08E-04 6.68E-06 ZN69M+D 1.02E-09 2.45E-09 2.24E-10 0. 1.48E-09 2.38E-06 1.71 E-05 ZN69 4.23E-12 8.14E-12 5.65E-13 0. 5.27E-12 1.15E-07 2.04E-09 SE79 0. 3.83E-07 6.09E-08 0. 5.69E-07 4.47E-05 3.33E-06 BR82 0. 0. 1.69E-06 0. 0. 0. 1.30E-06 BR83+D 0. 0. 3.01 E-08 0. 0. 0. 2.90E-08 BR84 0. 0. 3.91 E-08 0. 0. 0. 2.05E-13 BR85 0. 0. 1.60E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 5.19E-10 0. KR85M 0. 0. 0. 0. 0. 2.91 E-09 0. KR85 0. 0. 0. 0. 0. 2.41 E-09 0. KR87 0. 0. 0. 0. 0. 1.53E-08 0. KR88+D 0. 0. 0. 0. 0. 3.13E-08 0. KR89 0. 0. 0. 0. 0. 2.13E-08 0. RB86 0. 1.69E-05 7.37E-06 0. 0. 0. 2.08E-06 RB87 0. 9.86E-06 3.21E-06 0. 0. 0. 2.88E-07 RB88 0. 4.84E-08 2.41 E-08 0. 0. 0. 4.18E-19 RB89+D 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21 SR89+D 3.80E-05 0. 1.09E-06 0. 0. 1.75E-04 4.37E-05 SR90+D 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05 SR91 +D 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05 8.43E-10 0. 3.64E-11 0. 0. 2.06E-06 5.38E-06 .2+D
*Includes a 50% increase to account for percutaneous transpiration.
58
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1. 7 (contd)
ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU Y90 2.61 E-07 0. 7 .01 E-09 0. 0. 2.12E-05 6.32E-05 Y91M+D 3.26E-11 0. 1.27E-12 0. 0. 2.40E-07 1.66E-10 Y91 5.78E-05 0. 1.55E-06 0. 0. 2.13E-04 4.81 E-05 Y92 1.29E-09 0. 3.77E-11 0. 0. 1.96E-06 9.19E-06 Y93 1.18E-08 0. 3.26E-10 0. 0. 6.06E-06 5.27E-05 ZR93+D 5.22E-05 2.92E-06 1.37E-06 0. 1.11 E-05 2.13E-05 1.51E-06 ZR95+D 1.34E-05 4.30E-06 2.91 E-06 0. 6.77E-06 2.21 E-04 1.88E-05 ZR97+D 1.21 E-08 2.45E-09 1.13E-09 0. 3. 71 E-09 9.84E-06 6.54E-05 NB93M 3.1 OE-05 1.01 E-05 2.49E-06 0. 1.16E-05 3.11 E-05 2.38E-06 NB95 1.76E-06 9.77E-07 5.26E-07 0. 9.67E-07 6.31 E-05 1.30E-05 NB97 2.78E-11 7.03E-12 2.56E-12 0. 8.18E-12 3.00E-07 3.02E-08 M093 0. 1.17E-06 3.17E-08 0. 3.55E-07 5.11 E-05 3.79E-06 M099+D 0. 1.51 E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.1 OE-05 TC99M 1.29E-13 3.64E-13 4.63E-12 0. 5.52E-12 9.55E-08 5.20E-07 TC99 3.13E-08 4.64E-08 1.25E-08 0. 5.85E-07 1.01 E-04 7.54E-06 TC101 5.22E-15 7.52E-15 7.38E-14 0. 1.35E-13 4.99E-08 1.36E-21 RU103+D 1.91 E-07 0. 8.23E-08 0. 7.29E-07 6.31 E-05 1.38E-05 -05 RU105 +D RU106+D 07 09 AG110M +D AG111 9.88E-11 8.64E-06 9.24E-10 0. 0. 1.35E-06 4.25E-08 0. 0. 6.73E-10 8.27E-08 4.63E-10 1.25E-06 1.78E-08 3.89E-11 1.09E-06 4.43E-10 5.87E-09 1.16E-10 7.43E-07 8.87E-09 0. 0. 0. 0. 0. 0. 0. 1.27E-10 1.67E-05 2.86E-09 6.57E-07 2.35E-09 2.46E-06 5.74E-08 1.37E-06 1.17E-03 2.41 E-06 9.47E-06 1.85E-06
- 5. 79E-04 2.33E-05 6.02E-06 1.14E-04 1.09E-05 7.06E-07 1.52E-05 3.78E-05 2.79E-05 CD113M 0. 1.54E-04 4.97E-06 0. 1.71 E-04 2.08E-04 1.59E-05 CD115M 0. 2.46E-05 7.95E-07 0. 1.98E-05 1. 76E-04 4.80E-05 SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05 SN125+D 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81 E-05 SN126+D 1.58E-04 4.18E-06 6.00E-06 1.23E-06 0. 1.17E-03 1.59E-05 SB124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0. 3.10E-04 5.08E-05 SB125+D 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0. 2.18E-04 1.26E-05 SB126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 0. 9.57E-05 6.01 E-05 SB127 3.30E-08 7.22E-10 1.27E-08 3.97E-10 0. 2.05E-05 3.77E-05 TE125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE127M + D 1.58E-06 7 .21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1. 75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M + D 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE131M+D 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE131 +D 1.39E-12 7 .44E-13 4.49E-13 1.17E-12 5.46E-12 1. 74E-07 2.30E-09 TE132+D 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 TE133M + D 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-11 5.51 E-07 5.49E-08 TE134+D 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.343-07 2.97E-11 1129 2.48E-06 2.11 E-06 6.91 E-06 5.54E-03 4.53E-06 0. 2.22E-07 1130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 0. 9.61 E-07 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0. 7.85E-07
.1+D 59
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 1.7 (contd) ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.08E-08 1133 + 0 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0. 1.11 E-06 1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0. 1.26E-10 1135 + 0 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 0. 6.56E-07 XE131 M 0. 0. 0. 0. 0. 1.40E-09 0. XE133M 0. 0. 0. 0. 0. 1.89E-09 0. XE133 0. 0. 0. 0. 0. 1.57E-09 0. XE135M 0. 0. 0. 0. 0. 2.22E-09 0. XE135 0. 0. 0. 0. 0. 4.05E-09 0. XE137 0. 0. 0. 0. 0. 1. 74E-08 0. XE138+0 0. 0. 0. 0. 0. 2.44E-08 0. CS134M+O 1.59E-08 3.20E-08 1.72E-08 0. 1.83E-08 2.93E-09 7.92E-09 CS134 4.66E-05 1.06E-04 9.1 OE-05 0. 3.59E-05 1.22E-05 1.30E-06 CS135 1.46E-05 1.29E-05 5.99E-06 0. 5.11 E-06 1.57E-06 2.11E-07 CS136 4.88E-06 1.83E-05 1.38E-05 0. 1.07E-05 1.50E-06 1.46E-06 CS137+0 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 l.05E-06 CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.00E-08 6.07E-09 2.33E-13 CS139+0 2.56E-08 3.63E-08 1.39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA139 1.17E-10 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 140+0 4.88E-06 6.13E-09 3.21 E-07 0. 2.09E-09 1.59E-04 2.73E-05 41 +O 1.25E-11 9.41E-15 4.20E-13 0. 8.75E-15 2.42E-07 1.45E-17 142+0 3.29E-12 3.38E-15 2.07E-13 0. 2.86E-15 1.49E-07 1.96E-26 LA140 4.30E-08 2.17E-08 5.73E-09 0. 0. 1.70E-05 5.73E-05 LA141 5.34E-10 1.66E-10 2. 71 E-11 0. 0. 1.35E-06 7.31 E-06 LA142 8.54E-11 3.88E-11 9.65E-12 0. 0. 7.91E-07 2.64E-07 CE141 2.49E-06 1.69E-06 1.91 E-07 0. 7.83E-07 4.52E-05 1.50E-05 CE143+0 2.33E-08 1. 72E-08 1.91 E-09 0. 7.60E-09 9.97E-06 2.83E-05 CE144+0 4.29E-04 1. 79E-04 2.30E-05 0. 1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.80E-08 0. 2. 70E-07 3.51 E-05 2.50E-05 PR144 3. 76E-12 1.56E-12 1.91 E-13 0. 8.81E-13 1.27E-07 2.69E-18 N0147+0 6.59E-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2.16E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0. 1.49E-05 6.60E-05 5.54E-06 PM148M+O 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.18E-05 PM148 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91 E-05 5.80E-05 PM149 3.44E-08 4.87E-09 1.99E-09 0. 9.19E-09 7.21 E-06 2.50E-05 PM151 8.50E-09 1.42E-09 7.21 E-10 0. 2.55E-09 3.94E-06 2.00E-05 SM151 8.59E-05 1.48E-05 3.55E-06 0. 1.66E-05 4.45E-05 3.25E-06 SM153 1.70E-08 1.42E-08 1.04E-09 0. 4.59E-09 4.14E-06 1.58E-05 EU152 2.38E-04 5.41 E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 EU154 7.40E-04 9.1 OE-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 EU155 1.01 E-04 1.43E-05 9.21E-06 0. 6.59E-05 9.46E-05 5.95E-06 EU156 1.93E-06 1.48E-06 2.40E-07 0. 9.95E-07 8.56E-05 4.50E-05 TB160 2.21 E-05 0. 2.75E-06 0. 9.1 OE-06 1.92E-04 2.68E-05 H0166M 3.37E-04 1.05E-04 8.00E-05 0. 1.57E-04 3.94E-04 1.59E-05 W181 6.23E-09 2.03E-09 2.17E-10 0. 0. 1.71E-06 2.53E-07 1.95E-07 6.47E-08 6.81 E-09 0. 0. 5.57E-05 1.07E-05 .85 87 1.06E-09 8.85E-10 3.10E-10 0. 0. 3.63E-06 1.94E-05 60
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1o7 (contd)
ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210+D 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 8121 O+ D 0. 1 .59E-06 1 .32E-07 0. 1.92E-05 1 .11 E-03 2.95E-05 P0210 3.97E-04 8.60E-04 9.58E-05 0. 2.95E-03 3.14E-02 4.19E-05 RN222+D 0. 0. 0. 0. 0. 2.05E-06 0. RA223+D 1 .BOE-04 2. 77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04 RA224+D 1 .98E-05 4. 78E-08 3.96E-06 0. 1 .35E-06 8. 77E-03 3.01 E-04 RA225+D 3.00E-04 3.56E-07 5.99E-05 0. 1.01 E-05 2.92E-02 2.71 E-04 RA226+D 1 .25E-01 2.39E-06 9.14E-02 0. 6. 77E-05 1 .17E-01 2.94E-04 RA228+D 4.41 E-02 1.23E-06 4. 78E-02 0. 3.48E-05 1.61 E-01 5.00E-05 AC225 4.23E-04 5.82E-04 2.84E-05 0. 6.63E-05 2.21 E-02 2.52E-04 AC227+D 2.30E + 00 3.05E-01 1 .36E-01 0. 9.82E-02 2.41 E-01 5.08E-05 TH227+D 2.17E-04 3.92E-06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04 TH226+D 2.00E-01 3.39E-03 6. 77E-03 0. 1.89E-02 1.01E+00 3.49E-04 TH229 8.88E +00 1.33E-01 4.36E-01 0. 6.52E-01 3.49E + 00 3.17E-04 TH230 2.29E +00 1.31 E-01 6.36E-02 0. 6.40E-01 6.21 E-01 3. 73E-05 TH232+D 2.56E + 00 1 .12E-01 9.04E-02 0. 5.47E-01 5.96E-01 3.17E-05 TH234 1.63E-06 9.56E-08 4.70E-08 0. 5.41 E-07 1.89E-04 7.03E-05 PA231 +D 5.0BE+OO 1.91E-01 1.98E-01 0. 1.07E +oo 5.75E-02 4.44E-05 PA233 1.21 E-06 2.42E-07 2.09E-07 0. 9.15E-07 3.52E-05 1 .02E-05 2+0 5.14E-02 0. 3.66E-03 0. 5.56E-03 2.22E-01 4.21 E-05 3+D 1 .09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05 34 1 .04E-02 0. 6.46E-04 0. 2.49E-03 5.22E-02 3.81 E-05 U235 +D 1 .OOE-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-05 U236 1.00E-02 0. 6.20E-04 0. 2.39E-03 5.00E-02 3.57E-05 U237 3.67E-08 0. 9. 77E-09 0. 1.51 E-07 1.02E-05 1 .20E-05 U238+D 9.58E-03 0. 5.67E-04 0. 2.18E-03 4.58E-02 3.4 lE-05 NP237+D 1.69E + 00 1.47E-01 6.87E-02 0. 5.1 OE-01 5.22E-02 4.92E-05 NP238 2.96E-07 8.00E-09 4.61 E-09 0. 2. 72E-08 1 .02E-05 2.13E-05 NP239 2.87E-08 2.82E-09 1.55E-09 0. 8.75E-09 4.70E-06 1.49E-05 PU238 2. 74E + 00 3.87E-01 6.90E-02 0. 2.96E-01 1.82E-01 4.52E-05 PU239 3.19E+OO 4.31E-01 7.75E-02 0. 3.30E-01 1. 72E-01 4.13E-05 PU240 3.18E + 00 4.30E-01 7. 73E-02 0. 3.29E-01 1.72E-01 4.21 E-05 PU241 +D 6.41 E-02 3.28E-03 1.29E-03 0. 5.93E-03 1.52E-04 8.65E-07 PU242 2.95E+OO 4.15E-01 7.46E-02 0. 3.17E-01 1 .65E-01 4.05E-05 PU244 3.45E + 00 4. 76E-01 8.54E-02 0. 3.64E-01 1 .89E-01 6.03E-05 AM241 1.01E+00 3.59E-01 6. 71 E-02 0. 5.04E-01 6.06E-02 4.60E-05 AM242M 1.02E+OO 3.46E-01 6.73E-02 0. 5 .01 E-01 2.44E-02 5. 79E-05 AM243 1.01E+00 3.47E-01 6.57E-02 0. 4.95E-01 5.75E-02 5.40E-05 CM242 1.48E-02 1.51 E-02 9.84E-04 0. 4.48E-03 3.92E-02 4.91 E-05 CM243 7 .86E-01 2.97E-01 4.61 E-02 0. 2.15E-01 6.31 E-02 4.84E-05 CM244 5.90E-01 2.54E-01 3.51 E-02 0. 1 .64E-01 6.06E-02 4.68E-05 CM245 1.26E+OO 3.59E-01 7.14E-02 0. 3.33E-01 5.85E-02 4.36E-05 CM246 1.25E+OO 3.59E-01 7.13E-02 0. 3.33E-01 5.96E-02 4.29E-05 CM247+D 1.22E +00 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05 CM248 1.01 E+01 2.91 E+OO 5.79E-01 0. 2. 70E + 00 4.82E-01 9.09E-04
- 9. 78E-01 0. 2.33E-02 0. 0. 1 .99E-01 1. 78E-04
.52 61
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFG 1l
<MREM/HR PER PCl/M 2 l ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.1 OE-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.1 OE-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.1 OE-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.1 OE-09 Tc-101 2.70E-09 3.00E-09 62
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1 .8 (continued)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFG 1l (MREM/HR PER PCl/M 2 ) ELEMENT TOTAL BODY SKIN Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.1 OE-09 Ru-106 1.50E-09 1.SOE-09 Ag-11 Om 1.SOE-08 2.1 OE-08 Te-125m 3.50E-11 4.SOE-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1 . 1 OE-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131 m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.1 OE-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.1 OE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.1 OE-09 3.60E-09 Np-239 9.50E-10 1.1 OE-09 63
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 1 .9 {Continued}
1998 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES {Continued} Design Objective Dose Factor Annual Quantity Nuclide Organ MremLCi Ci Na-24 Total Body-C 4.02E - 03 1.24E+03 Nb-95 GI Tract-T 1.49E - 01 1.01E+02 Ni-63 Bone-C 1.21E+01 1.24E +00 Ni-65 GI Tract-C 4.70E - 03 3.19E+03 Np-239 GI Tract-T 8.13E - 03 1.84E +03 Rb-88 Total Body-C 2.38E - 05 2.10E+05 Ru-103 GI Tract-A 1.56E - 01 9.62E +01 Ru-105 GI Tract-C 5.82E - 03 2.58E+03 Sb-124 GI Tract-T 9.47E - 01 1.58E+01 Sb-125 GI Tract-T 4.35E - 01 3.45E+01 Sr-89 Bone-C 8.98E+OO 1.67E +00 Sr-90 Bone-C 3.73E+02 4.02E - 02 Sr-91 Bone-I 2.46e+OO 6.10E+OO Sr-92 GI Tract-C 1.37E - 02 1.09E+03 Tc-99 GI Tract-T 5.85E - 01 2.62E+01 Tc-99m GI Tract-T 3.64E - 04 4.12E+04 Tc-101 GI Tract-I 8.33E - 05 1.80E+05 Te-127 GI Tract-T 4.87E - 03 3.08E+03 Xe-131 m Skin 4.03E - 05 3.72E+05 Xe-133 Total Body 1.39E - 05 3.60E + 05 Xe-133m Skin 8.39E - 05 1.79E+05 Xe-135 Total Body 8.32E - 05 6.01 E+04 Xe-135m Total Body 9.55E - 05 5.24E+04 Xe-137 Skin 5.85E - 04 2.56E+04
- Xe-138 Zn-65 Total body Liver-C 64 2.70E-04 9.38E - 01 1.85E+04 1.60E+01
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 1.9 (Continued} 1998 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES (Continued} Design Objective Dose Factor Annual Quantity Nuclide Organ MremLCi Ci Zr-95 GI Tract-T 3.90E - 01 3.85E+01 Pu-238 Bone-T 1.42E+03 1.06E - 02 Pu-239 Bone-T 1.64E+03 9.15E - 03 Pu-241 Bone-T 3.45E+01 4.35E - 01 Am-241 Bone-T 5.25E+02 2.86E - 02 Cm-242 Lung-T 3.35E+01 4.48E - 01 Cm-244 Bone-T 3.20E+02 4.69E - 02 Ag-11 Om Gl-Tract-T 2.13E+OO 7.04E+OO Ar-41 Total Body 3.64E - 04 1.37E+04 Ba-139 GI Tract-C 2.97E - 03 5.05E+03 Ba-140 Lung-T 1 .26E - 01 1.19E+02 Br-82 total Body-C 4.97E - 03 1.01 E+03 C-14 Bone-C 1.48E - 01 1.01E+02 Ce-141 GI Tract-T 1.34E- 01 1.12E + 02 Ce-144 GI Tract-T 3.37E+OO 4.45E + 00 Co-57 GI Tract-T 8.53E - 02 1.76E+02 Co-58 GI Tract-T 2.59E - 01 5.79E+01 Co-60 GI Tract-T 6.86E+OO 2.19E+OO Cr-51 GI Tract-A 3.75E - 03 1.33E+03 Cs-134 Liver-C 8.77E+OO 1.71E+00 Cs-136 Liver-I 1 .99E - 01 7.54E+01 Cs-137 Bone-C 9.58E+OO 1.57E+OO Cs-138 Total body-C 1.00E - 01 5.00E+01 Fe-55 Bone-C 2.06E - 01 7.28E+01
- Fe-59 H-3 GI Tract-T Total Body-C 65 3.20E - 01 2.19E - 04 4.69E+01 2.28E+04
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 1 .9 {Continued} 1998 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES {Continued} Design Objective Dose Factor Annual Quantity Nuclide Organ Mrem[Ci Ci 1-129 Thyroid-A 3.66E+02 4. 1 OE - 02 1-131 Thy'roid-1 7.35E+OO 2.04E+OO 1-132 Thyroid-C L 12E - 02 1 .34E+03 1-133 Thyroid-C 2A6E - 01 6.11E+01 1-134 Thyroid-C 245E - 03 6.12E+03 1-135 Thyroid-C 4.93E - 02 3.04E+02 Kr-83m Skin 8.82E - 07 1 .70E+07 Kr-85 Skin 9.14E - 05 1.64E+05 Kr-85m Total Body 5.22E - 05 9.58E+04 Kr-87 Skin 8.03E - 04 1 .87E+04 Kr-88 Total Body 6.35E - 04 7.87E+03 Kr-89 Total Body 5.08E - 04 9.84E+03 La-140 GI Tract-T 3.04E - 02 4.93E+02 Mn-54 GI lract-T 6.29E - 01 2.38E+01 Mn-56 GI Tract-C 6.91E - 03 2.17E+03 Mo-99 GI Tract-T 1 .66E - 02 9.04E+02 N-13 Total Body-C 3A4E - 06 1A5E+06 66
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- 11. LIQUID EFFLUENTS Revision 12 A. CONCENTRATION
- 1. Requirements Appendix A, Section 111.G requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to ten times the Effluent Concentration (EC) specified in 10 CFR 20, Appendix B, Table 2, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 µCi/ml total activity .. To ensure compliance, the following approach will be used for each release.
- 2. _Pre release Analysis ___ .
Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be used to determine appropriate recirculation time. Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclide determined.
~=I:~-,
,;=1 (2. 1) where:
c = Total concentration in the liquid effluent at the release point, µCi/ml.
= Concentration of a single radionuclide i, µCi/ml.
- 67
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- 3.
Revision 12 Effluent Concentration (EC) - Sum of the Ratios The EC-Fraction (R) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 1 0 CFR 20: J!6 = j L..J _~. _' ~ 10.0
-\:S~.
<;l?
i (2.2) where:
= Effluent concentration of radionuclide i, µCi/ml.
= The EC of radionuclide i, 10 CFR 20, Appendix B, Table 2, Column 2 - µCi/ml.
= The Total EC-Fraction for the release point.
The sum of the ratios at the discharge to the lake must be ~ 1 0 due to the releases from any or all concurrent releases. The following relationship will assure this criterion is met: fl{J/6 f -t) + I.~ l'f 2 2
-t) + I.~
J J
-t) ~ c.SE' (2.3) where:
= The effluent flow rate (gallons/minute) for the respective releases, determined by Plant personnel.
= The Total EC-Fractions for the respective releases as determined by Equation 2.2.
F = Minimum required dilution flow rate. Normally, a conservatively high dilution flow rate is used, that is, flow rate used = (bi) (F) where bi is a conservative factor greater than 1 .0. 68
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- B. INSTRUMENT SETPOINTS Revision 12
- 1. Setpoint Determination Appendix A, Section 111.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A, Section 111.G are not exceeded. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The identification number for each liquid effluent radiation detector is contained in Figure 2-2.
The respective alarm/trip setpoints at each release point will be set such that the sum of the ratios at each point, as calculated by Equation 2.2, will not be exceeded. The value of R is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the value of R. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm/trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint (S) be set above the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. That is: [JP= ta; r_g (2.4) Liquid effluent flow paths and release points are indicated in Figure 2.1.
- 2. Composite Samplers Effluent pathways, Turbine Sump and Service Water, are equipped with continuous compositors to meet the requirements of Appendix A, Table D-1. These compositors are adjustable and normally set in a time mode and collect three to six samples hourly, 24 hours a day with a total collection of approximately one gallon per day. A representative sample is collected daily from the compositor and saved for the weekly, monthly analysis requirements of Appendix A, Table D-1. In the event that a compositor is not operational, effluent releases via this pathway may continue provided that grab samples are collected and analyzed for gross beta or gamma radioactivity at least once per 24 hours per Appendix A, Table C-1, Action 3.
69
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- 3. Post-Release Analysis Revision 12 A post-release analysis will be done using actual release data to ensure that the limits specified in Section 1 were not exceeded.
A composite list on concentrations (Ci), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section 1 . This data and setpoints will be recorded in auditable records by Plant personnel. C. DOSE
- 1. RETS Requirement Appendix A, Section 111.H.1 requires that the quantity of radionuclides released by limited such that the dose or dose commitment to an individual from radioactive materials in liquid effluents release to unrestricted areas from the reactor (see Figure 2-1) will not exceed:
- a. During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ, and
- b. During any calendar year, 3 mrem to the total body and 10 mrem to any organ.
To ensure compliance, quantities of activity of each radionuclide released will be summed for each release and accumulated for each quarter as follows in Section 2.
- 2. Release Analysis Calculations shall be performed for each batch release, and weekly for continuous releases according to the formula:
~ c,4/':, ~ 0.5 (2.5) 70
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 where:
= Cumulative quarterly activity of nuclide i identified in liquid release (Ci).
= Design objective annual quantity of radionuclide i from Table 2.2.
The design basis quantities are derived in such a conservative manner that doses may be greatly overestimated by this technique. As a consequence of this conservatism, and in light of historically consistent operations with releases well below annual design basis quantities, the Appendix A, effluent requirements do not require monthly dose projections. Instead, if at any time, calculations by Equation (2.5) results in values greater than 0.5 for a given quarter or 1 .0 for year-to-date, the NRC LADTAP code will be run to ensure that Appendix A, Section 111.H.1 has been met. Values for the design basis quantities (Ci), and the dose per Curie (Dc/Cc)i for each nuclide i shown in Table 2.2, were calculated as follows in Sections 2.1 and 2.2.
- a. Water Ingestion The dose to an individual from ingestion of radioactivity from any source as described by the following equation:
!aj L ~~Jg)? a; Q},
i=I (2.6) where:
= Dose for the jth organ from radionuclides releases, mrem.
= The organ of interest.
(DCF)ii = Ingestion dose commitment factor for the jth organ from the ith radionuclide mrem/pCi, see Table 2.1. 71
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12
= Activity ingested of the ith radionuclide, pCi.
Ii is described by: (c,4)(§)))(36'5) Qj.i = , (1:Got[) (1ooo) {r-/) (2.7) where: 365 = Days per year. Annual activity released of ith radionuclide, µCi. v = Average rate of water consumption (2000 ml/d - adult, 1400 ml/d - teen and child, 900 ml/d - infant, ICRP 23, p 358). d = Dilution water flow for year, ml.
- 1000 1 E06 =
= Dispersion factor from discharge to nearest drinking water supply.
Conversion µCi to pCi. The dose equation then becomes: (2.8)
- b. Fish Ingestion The dose to an individual from the consumption of fish is described by Equation 2.10. In this case, the activity ingested of the ith radionuclide (Ii) is described by:
Qj.i c>>t
= __
.a _r.53(1!60.9)
' _.___ = f~i 15cl (2.9)
- 72
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- where:
Revision 12
= Annual released of ith radionuclide, µCi.
= Fish concentration factor of ith radionuclide (see Table 2.0).
F = Amount of fish eaten per year (21 kg adult, 16 kg teen, 6.9 kg child, none infant). 15 = Dispersion factor from discharge to fish exposure point. d = Dilution water flow for year, ml. 1E09 = Conversion of µCi and Kgm to gross.
- Substitution of Equation 2.9 into Equation 2.6 gives:
(2.10) 73
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- c. Annual Analysis Revision 12 A complete analysis utilizing the NRC computer code LADT AP with the total source release will be done annually in conjunction with the annual environmental report. This analysis will provide estimates of dose to the total body and various organs in addition to the dose limiting organs considered in the method of Section 2. The following approach is utilized on LADT AP. The dose to the r organ from m radionuclides, Dj, is described by:
.Q), = " .Q) .. ~
"' L fl
,;=/
(2.11) i=/ where:
= Dose to the jth organ from the ith radionuclide, mrem.
= The organ of interest (bone, GI tract, thyroid, liver, kidney, lung, or total body).
= Adult ingestion dose commitment factor for the jth organ from the ith radionuclide, mrem/pCi (see Table 2.1 ).
= Activity ingested of the ith radionuclide, µCi.
Ii for water ingestion is described by:
~. :§V-r Q}, = ' µ':(;,;
vd (2.13) and for fish ingestion Ii is described by:
~.a.~r Q}, = ' ' µ':(;,;
v cl 74
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- where:
Revision 12
= Activity release of jth radionuclide during the year, µCi.
v = Average rate of water consumption (2000 ml/d). r Number of days during the year (365 d). v = Dispersion factor from point of discharge to point of exposure. d = Dilution water volume (ml).
= Fish concentration factor of the ith radionuclide, Table 2.0, F = Amount of fish eaten per day (57 .5 gm/d).
D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT The Palisades liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (by recycle or shipment for disposal) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2-1) will not exceed the limits of Appendix A, 111.H.1. Maintaining the cumulative fraction if allowable release for each batch release and weekly for continuous releases assures compliance with this requirement. In addition, 13 years of operating experience (to the date this ODCM was first adopted) has shown that design basis quantities never have been exceeded .
- 75
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr} 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this Effluent Concentration (EC) level, if ingested for one year, will result in a dose of 50 millirem to the total body. In addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as low as is reasonably achievable. Appendix I to 1 0 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement. The LADT AP code has been run to determine the dose due to drinking water at Plant discharge concentration ( 1 ,000 x nearest drinking water intake concentration). The nominal average source term used is given in Table 1 .1. Dose to the most limiting organ of the person hypothetically drinking this water is 3.88E-03 mrem. This is only 0.13% of the more conservative 50 mrem/yr total body value. 76
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.0 BIOACCUMULATION FACTORS pCi/gm per pCi/ml FRESHWATER ELEMENT FISH H 9.0E-01 c 4.6E 03 NA 1.0E 02 p 1.0E 05 CR 2.0E 02 MN 4.0E 02 FE 1.0E 02 co 5.0E 01 NI 1.0E 02 cu 5.0E 01 ZN 2.0E 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 y 2.5E 01 ZR 3.3E 00 NB 3.0E 04 MO 1 .OE 01 TC 1.5E 01 RU 1 .OE 01 RH 1 .OE 01 TE 4.0E 02 I 1.5E 01 cs 2.0E 03 BA 4.0E 00 LA 2.5E 01 CE 1.0E 00 PR 2.5E 01 ND 2.5E 01 w 1.2E 03
- NP 79 1 .OE 01
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BE10 1.71 E-05 2.49E-06 5.16E-07 0. 1.64E-06 0. 2.78E-05 C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 N13 5.85E-08 5.85E-08 5.85E-08 5.835E-08 5.85E-08 5.85E-08 5.85E-08 F18 5.19E-06 0. 4.43E.07 0. 0. 0. 1.22E-06 NA22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 NA24 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 P32 1.70E-03 1.00E-04 6.59E-05 0. 0. 0. 2.30E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 3.74E-04 0. 4.0BE-05 0. 0. 0. 1.91 E-07 SC46 3.75E-08 5.41 E-08 1.69E-08 0. 3.56E-08 0. 3.53E-05 CR51 0. 0. 1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.11 E-07 MN54 0. 1.99E-05 4.51 E-06 0. 4.41 E-06 0. 7.31 E-06 MN56 0. 8.18E-07 1.41 E-07 0. 7.03E-07 0. 7.43E-05 FE55 1.39E-05 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05 0. 0. 1.59E-05 2.57E-05 C057 0. 1.15E-06 1.87E-06 0. 0. 0. 3.92E-06 C058 0. 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06 C060 0. 1.08E-05 2.55E-05 0. 0. 0. 2.57E-05 Nl59 4.78E-05 1.45E-05 8.17E-06 0. 0. 0. 7.16E-07 Nl63 6.34E-04 3.92E-05 2.20E-05 0. 0. 0. 1.95E-06 Nl65 4.70E-06 5.32E-07 2.42E-07 0. 0. 0. 4.05E-05 CU64 0. 6.09E-07 2.82E707 0. 1.03E-06 0. 1.25E-05 ZN65 1.84E-05 6.31 E-05 2.91 E-05 0. 3.06E-05 0. 5.33E-05 ZN69M+D 1.50E-06 3.06E-06 2.79E-07 0. 1.24E-06 0. 4.24E-05 ZN69 9.33E-08 1.68E-07 1.25E-08 0. 6.98E-08 0. 1.37E-05 SE79 0. 2.1 OE-05 3.90E-06 0. 2.43E-05 0. 5.58E-07 BR82 0. 0. 1.27E-05 0. 0. 0. 0. BR83+D 0. 0. 3.63E-07 0. 0. 0. 0. BR84 0. 0. 3.82E-07 0. 0. 0. 0. BR85 0. 0. 1.94E-08 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88+D 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 1.70E-04 8.40E-05 0. 0. 0. 4.35E-06 RB87 0. 8.88E-05 3.52E-05 0. 0. 0. 5.98E-07 RB88 0. 4.98E-07 2.73E-07 0. 0. 0. 4.85E-07 RB89+D 0. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08 .SR89+D 2.51E-03 0. 7.20E-05 0. 0. 0. 5.16E-05 SR90+D 1.85E-02 0. 4. 71 E-03 0. 0. 0. 2.31E-04 SR91 + D 5.00E-05 0. 1.81E-06 0. 0. 0. 5.92E-05 SR92+D 1.92E-05 0. 7.13E-07 0. 0. 0. 2.07E-04 80
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 Y91M+D 8.10E-10 0. 2.76E-11 0. 0. 0. 2. 70E-06 Y91 1.13E-06 0. 3.01 E-08 0. 0. 0. 8.1 OE-05 Y92 7.65E-09 0. 2 .. 15E-10 0. 0. 0. 1.46E-04 Y93 2.43E-08 0. 6.62E-10 0. 0. 0. 1.92E-04 ZR93+D 1.93E-07 9.18E-08 5.54E-08 0. 2.71E-07 0; 2.39E-05 ZR95 +D 2.06E-07 5.02E-08 3.56E-08 0. 5.41 E-08 0. 2.50E-05 ZR97 +D 1.48E-08 2.54E-09 1.16E-09 0. 2.56E-09 0. 1.62E-04 N893M 1.23E-07 3.33E-08 1.04E-08 0. 3.25E-08 0. 3.98E-06 N895 4.20E-08 1.73E-08 1.00E-08 0. 1.24E-08 0. 1.46E-05 N897 4.59E-10 9.79E-11 3.53E-11 0. 7.65E-11 0. 3.09E-05 M093 0. 5.65E-05 1.82E-06 0. 1.13E-05 0. 1.21 E-06 M099+D 0. 3.40E-05 6.63E-06 0. 5.08E-05 0. 1.12E-05 TC99M 1.92E-09 3.96E-09 5.1 OE-08 0. 4.26E-08 2.07E-09 1.15E-06 TC99 1.08E-06 1.46E-06 4.55E-07 0. 1.23E-05 1.42E-07 6.31 E-06 TC101 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07 RU103 + D 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05 RU105+D 1.36E-07 0. 4.58E-08 0. 1.00E-06 0. 5.41 E-05 RU106+D 2.41 E-05 0. 3.01 E-06 0. 2.85E-05 0. 1.83E-04 RH105 1.09E-06 7.13E-07 4.79E-07 0. 1.98E-06 0. 1.77E-05 PD107 0. 1.19E-06 8.45E-08 0. 6.79E-06 0. 9.46E-07 PD109 0. 1.50E-06 3.62E-07 0. 5.51 E-06 0. 3.68E-05 AG110M+D 9.96E-07 7.27E-07 4.81 E-07 0. 1.04E-06 0. 3.77E-05 AG111 5.20E-07 2.02E-07 1.07E-07 0. 4.22E-07 0. 4.82E-05 CD113M 0. 1. 77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05 CD115M 0. 1.42E-05 4.93E-07 0. 7.41E-06 0. 8.09E-05 5N123 2.49E-04 3.89E-06 6.50E-06 3.91 E-06 0. 0. 6.58E-05 5N125+D 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.11 E-04 5N126+D 5.53E-04 7.26E-06 1.80E-05 1.91 E-06 0. 0. 2.52E-05 58124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.60E-05 58125 + D 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05 58126 8.06E-06 1.58E-07 2.91 E-06 6.19E-08 0. 5.07E-06 8.35E-05 58127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15E-06 5.91 E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0. 0. 1.11 E-05 TE127M+D 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.1 OE-05 TE129M+D 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0. 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0. 2.27E-05 TE131M+D 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 0. 1.03E-04 TE131 +D 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0. 7.11 E-06 TE132+D 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 0. 3.81 E-05 TE133M+D 3.91 E-07 1.79E-07 1. 71 E-07 3.45E-07 1.22E-06 0. 1.93E-05
- TE134+D 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 0. 3.06E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51 E-05 0. 4.24E-07 1130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0. 2.83E-06 1131 +D 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0. 1.51E-06 81
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU 1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0. 2.73E.06 1133 + D 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 0. 3.0BE-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0. 1.84E-06 1135 + D 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06 XE131 M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138+D 0. 0. 0. 0. 0. 0. 0. CS134M+D 1.76E-07 2.93E-07 1.48E-07 0. 1.13E-07 2.60E-08 2.32E-07 CS134 3.77E-04 7.03E-04 7.1 OE-05 0. 1.81 E-04 7.42E-05 1.91 E-06 CS135 1.33E-04 1.21 E-04 6.30E-06 0. 3.44E-05 1.31 E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1.1 OE-05 2.05E-06 CS137+D 5.22E-04 6.11 E-04 4.33E-05 0. 1.64E-04 6.64E-05 1.91 E-06 CS138 4.81 E-07 7.82E-07 3.79E-07 0. 3.90E-07 6.09E-08 1.25E-06 CS139 + D 3.1 OE-07 4.24E-07 1.62E-07 0. 2.19E-07 3.30E-08 2.66E-08 BA139 8.81 E-07 5.84E-10 2.55E-08 0. 3.51E-10 3.54E-10 5.58E-05 BA140+D 1.71 E-04 1.71 E-07 8.81 E-06 0. 4.06E-08 1.05E-07 4.20E-05 BA141 + D 4.25E-07 2.91E-10 1.34E-08 0. 1.75E-10 1.77E-10 5.19E-06 BA142+D 1.84E-07 1.53E-10 9.06E-09 0. 8.81 E-11 9.26E-11 7.59E-07 LA140 2.11 E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05 LA141 2.89E-09 8.38E-10 1.46E-10 0. 0. 0. 9.61 E-05 LA142 1.1 OE-09 4.04E-10 9.67E-11 0. 0. 0. 6.86E-05 CE141 7.87E-08 4.BOE-08 5.65E-09 0. 1.48E-08 0. 2.48E-05 CE143+D 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5.73E-05 CE144+D 2.98E-06 1.22E-06 1.67E-07 0. 4.93E-07 0. 1.71 E-04 PR143 8.1 BE-08 3.04E-08 4.03E-09 0. 1.13E-08 0. 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 0. 3.84E-11 0. 4.93E-06 ND147+D 5.53E-08 5.68E-08 3.48E-09 0. 2.19E-08 0. 3.60E-05 PM147 3.BBE-07 3.27E-08 1.59E-08 0. 4.88E-08 0. 9.27E-06 PM148M+D 1.65E-07 4.18E-08 3.28E-08 0. 4.80E-08 0. 5.443-05 PM148 6.32E-08 9.13E-09 4.60E-09 0. 1.09E-08 0. 9.74E-05 PM149 1.38E-08 1.81 E-09 7.90E-10 0. 2.20E-09 0. 4.86E-05 PM151 6.1 BE-09 9.01E-10 4.56E-10 0. 1.07E-09 0. 4.17E-05 SM151 2.90E-07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06 SM153 7.72E-09 5.97E-09 4.58E-10 0. 1.25E-09 0. 3.12E-05 EU152 6.74E-07 1.79E-07 1.51E-07 0. 5.02E-07 0. 1.59E-05 EU154 2.64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08 0. 1.40E-07 0. 8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05 TB160 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05
- H0166M 1.25E-06 2.69E-07 2.13E-07 0. 3.57E-07 0. 0.
W181 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07 W185 3.62E-06 1.13E-06 1.29E-07 0. 0. 0. 1.62E-05 W187 9.03E-07 6.28E-07 2.17E-07 0. 0. 0. 3.69E-05 82
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU PB21 O+ D 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 8121 O+ D 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05 P0210 3.1 OE-03 5.93E-03 7.41 E-04 0. 1.26E-02 0. 6.61 E-05 RN222+D 0. 0. 0. 0. 0. 0. 0. RA223+D 4.41 E-02 6.42E-05 8.82E-03 0. 1.17E-03 0. 3.43E-04 RA224+D 1.46E-02 3.29E-05 2.91 E-03 0. 6.00E-04 0. 3.86E-04 RA225+D 5.78E-02 6.42E-05 1.15E-02 0. 1.19E-03 0. 3.24E-04 RA226+D 6.20E-01 4.76E-05 5.14E-01 0. 8. 71 E-04 0. 3.44E-04 RA228+D 4.32E-01 2.58E-05 4.86E-01 0. 4.73E-04 0. 5.86E-05 AC225 3.92E-05 5.03E-05 2.63E-06 0. 3.69E-06 0. 4.36E-04 AC227+D 4.49E-03 7.67E-04 2.79E-04 0. 1.56E-04 0. 8.50E-05 TH227+D 1.20E-04 2.01 E-06 3.45E-06 0. 7.41 E-06 0. 5.70E-04 TH228+D 2.47E-03 3.38E-05 8.36E-05 0. 1.58E-04 0. 5.84E-04 TH229 1.48E-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31 E-04 TH230 3.80E-03 1.90E-04 1.06E-04 0. 9.12E-04 0. 6.24E-05 TH232+D 4.24E-03 1.63E-04 1.65E-04 0. 7.79E-04 0. 5.31 E-05 TH234 6.92E-07 3.77E-08 2.00E-08 0. 1.39E-07 0. 1.19E-04 PA231 +D 7.57E-03 2.50E-04 3.02E-04 0. 1.34E-03 0. 7.44E-05 PA233 3.11 E-08 6.09E-09 5.43E-09 0. 1.67E-08 0. 1.46E-05 U232+D 2.42E-02 0. 2.16E-03 0. 2.37E-03 0. 7.04E-05 U233 + D 5.08E-03 0. 3.87E-04 0. 1.08E-03 0. 6.51 E-05 U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.37E-05 U235 +D 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.1 OE-05 U236 4.67E-03 0. 3.64E-04 0. 1.01 E-03 0. 5.98E-05 U237 4.95E-07 0. 1.32E-07 0. 1.23E-06 0. 2.11 E-05 U238+D 4.47E-03 0. 3.33E-04 0. 9.28E-04 0. 5. 71 E-05 . NP237+D 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.23E-05 NP238 1.24E-07 3.12E-09 1.92E-09 0. 6.81 E-09 0. 4.17E-05 NP239 1.11 E-08 . 9.93E-10 5.61E-10 0. 1.98E-09 0. 2.87E-05 PU238 1.34E-03 1.69E-04 3.40E-05 0. 1.21 E-04 0. 7.57E-05 PU239 1.45E-03 1. 77E-04 3.54E-05 0. 1.28E-04 0. 6.91 E-05 PU240 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 7.04E-05 PU241 +D 4.38E-05 1.90E-06 8.82E-07 0. 3.17E-06 0. 1.45E-06 PU242 1.35E-03 1.70E-04 3.41 E-05 0. 1.23E-04 0. 6.77E-05 PU244 1.57E-03 1.95E-04 3.91 E-05 0. 1.41 E-04 0. 1.01 E-04 AM241 1.53E-03 7.18E-04 1.09E-04 0. 6.55E-04 0. 7.70E-05 AM242M 1.58E-03 7.02E-04 1.13E-04 0. 6.64E-04 0. 9.69E-05 AM243 1.51 E-03 6.88E-04 1.06E-04 0. 6.36E-04 0. 9.03E-05 CM242 1.37E-04 1.24E-04 9.10E-06 0. 2.62E-05 0. 8.23E-05 CM243 1.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.1 OE-05 CM244 1.22E-03 6.16E-04 7 .59E-05 0. 2.71 E-04 0. 7.84E-05 CM245 1.88E-03 7.49E-04 1.13E-04 0. 4.32E-04 0. 7.30E-05 CM246 1.87E-03 7.49E-04 1.13E-04 0. 4.31 E-04 0. 7.17E-05 CM247+D 1.82E-03 7.36E-04 1.11 E-04 0. 4.24E-04 0. 9.43E-05 CM248 1.51 E-02 6.07E-03 9.16E-04 0. 3.50E-03 0. 1.52E-03 CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.99E-04 83
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU H3 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 BE10 1.35E-05 1.57E-06 3.39E-07 0. 1.11 E-06 0. 2.75E-05 C14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 N13 3.1 OE-08 3.1 OE-08 3.1 OE-08 3.1 OE-08 3.1 OE-08 3.1 OE-08 3.1 OE-08 F18 2.49E-06 0. 2.47E-07 0. 0. 0. 6.74E-07 NA22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P32 8.25E-04 3.86E-05 3.18E-05 0. 0. 0. 2.28E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 3.47E-04 0. 3.79E-05 0. 0. 0. 1.90E-07 SC46 1.97E-08 2.70E-08 1.04E-08 0. 2.30E-08 0. 3.95E-05 CR51 0. 0. 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54 0. 1.07E-05 2.85E-06 0. 3.00E-06 0. 8.98E-06 MN56 0. 3.34E-07 7.54E-08 0. 4.04E-07 0. 4.84E-05 FE55 1.15E-05 6.1 OE-06 1.89E-06 0. 0. 3.45E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05 0. 0. 7.74E-06 2.78E-05 C057 0. 4.93E-07 9.98E-07 0. 0. 0. 4.04E-06 C058 0. 1.80E-06 5.51 E-06 0. 0. 0. 1.05E-05 C060 0. 5.29E-06 1.56E-05 0. 0. 0. 2.93E-05 Nl59 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.1 OE-07 Nl63 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06 Nl65 2.22E-06 2.09E-07 1.22E-07 0. 0. 0. 2.56E-05 CU64 0. 2.45E-07 1.48E-07 0. 5.92E-07 0. 1.15E-05 ZN65 1.37E-05 3.65E-05 2.27E-05 0. 2.30E-05 0. 6.41 E-06 ZN69M+D 7.1 OE-07 1.21 E-06 1.43E-07 0. 7.03E-07 0. 3.94E-05 ZN69 4.38E-08 6.33E-08 5.85E-09 0. 3.84E-08 0. 3.99E-06 SE79 0. 8.43E-06 1.87E-06 0. 1.37E-05 0. 5.53E-07 BR82 0. 0. 7.55E-06 0. 0. 0. 0. BR83+D 0. 0. 1. 71 E-07 0. 0. 0. 0. BR84 0. 0. 1.98E-07 0. 0. 0. 0. BR85 0 0. 9.12E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88+D 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 6.70E-05 4.12E-05 0. 0. 0. 4.31 E-06 RB87 0. 3.95E-05 1.83E-05 0. 0. 0. 5.92E-07 RB88 0. 1.90E-07 1.32E-07 0. 0. 0. 9.32E-09 RB89+D 0. 1.17E-07 1.04E-07 0. 0. 0. 1.02E-09 SR89+D 1.32E-03 0. 3.77E-05 0. 0. 0. 5.11 E-05 SR90+D 1. 70E-02 0. 4.31 E-03 0. 0. 0. 2.29E-04 SR91 +D 2.40E-05 0. 9.06E-07 0. 0. 0. 5.30E-05 SR92+D 9.03E-06 0. 3.62E-07 0. 0. 0. 1.71 E-04 84
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE l.,.IVER TOTAL BODY THYROID KIDNEY LUNG GI-LU Y90 4.11 E-08 0. 1.1 OE-09 0. 0. 0. 1.17E-04 Y91M+D 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. 1.61 E-08 0. 0. 0. 8.02E-05 Y92 3.60E-09 0. 1.03E-10 0. 0. 0. 1.04E-04 Y93 1.14E-08 0. 3.13E-10 0. 0. 0. 1.70E-04 ZR93+D 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05 ZR95 +D 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97+D 6.99E-09 1.01 E-09 5.96E-10 0. 1.45E-09 0. 1.53E-04 NB93M 1.05E-07 2.62E-08 8.61 E-09 0. 2.83E-08 0. 3.95E-06 NB95 2.25E-08 8.76E-09 6.26E-09 0. 8.23E-09 0. 1.62E-05 NB97 2.17E-10 3.92E-11 1.83E-11 0. 4.35E-11 0. 1.21E-05 M093 0. 2.41 E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06 M099+D 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.1 OE-05 TC99M 9.23E-10 1.81 E-09 3.00E-08 0. 2.63E-08 9.19E-10 1.03E-06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC101 1.07E-09 1.12E-09 1.42E-08 0. 1.91 E-08 5.92E-10 3.56E-09 RU103+D 7.31 E-07 0. 2.81 E-07 0. 1.84E-06 0. 1.89E-05 RU105 +D 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21 E-05 RU106+D 1.17E-05 0. 1.46E-06 0. 1.58E-05 0. 1.82E-04 RH105 5.14E-07 2.76E-07 2.36E-07 0. 1.1 OE-06 0. 1. 71 E-05 PD107 0. 4.72E-07 4.01 E-08 0. 3.95E-06 0. 9.37E-07 PD109 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05 AG110M+D 5.39E-07 3.64E-07 2.91 E-07 0. 6.78E-07 0. 4.33E-05 AG111 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.75E-05 CD113M 0. 1.02E-05 4.34E-07 0. 1.05E-05 0. 2.63E-05 CD115M 0. 5.89E-06 2.51 E-07 0. 4.38E-06 0. 8.01 E-05 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.52E-05 SN125 +D 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0. 0. 1.1 OE-04 SN126+D 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0. 0. 2.50E-05 SB124 1.11 E-05 1.44E-07 3.89E-06 2.45E-08 0. 6.16E-06 6.94E-05 SB125 + D 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0. 3.99E-06 1.71 E-05 SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0. 2.1 OE-06 8.87E-05 SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0. 4.60E-07 5.97E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. 1.1 OE-05 TE127M+D 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0. 2.34E-05 TE127 4.71E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 0. 1.84E-05 TE129M + D 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06 TE131M+D 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 0. 1.01 E-04 TE131 + D 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 0. 4.36E-07 TE132 + D 1 .01 E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0. 4.50E-05 TE133M+D 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 0. 5.77E-06 TE134+D 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 0. 5.89E-07 1129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 0. 4.29E-07 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0. 2.76E-06 1131 + D 1.72E-05 1. 73E-05 9.83E-06 5.72E-03 2.84E-05 0. 1.54E-06 85
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1. 73E-06 1133 + D 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0. 2.95E-06 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0. 5.16E-07 1135 + D 1. 75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06 XE131 M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138+D 0. 0. 0. 0. 0. 0. 0. CS134M+D 8.44E-08 1.25E-07 8.16E-08 0. 6.59E-08 1.09E-08 1.58E-07 CS134 2.34E-04 3.84E-04 8.10E-05 0. 1.19E-04 4.27E-05 2.07E-06 CS135 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81 E-06 4.33E-07 CS136 2.35E-05 6.46E-05 4.18E-05 0. 3.44E-05 5.13E-06 2.27E-06 CS137+D 3.27E-04 3.13E-04 4.62E-05 0. 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01 E-07 0. 2.23E-07 2.40E-08 1.46E-07 CS139+D 1.45E-07 1.61 E-07 7.74E-08 0. 1.21E-07 1.22E-08 1.45E-11 BA139 4.14E-07 2.21 E-10 1.20E-08 0. 1.93E-10 1.30E-10 2.39E-05 BA140+D 8.31 E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21 E-05 BA141 +D 2.00E-07 1.12E-10 6.51 E-09 0. 9.69E-11 6.58E-10 1.14E-07 BA142+D 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-11 1.14E-09 LA140 1.01 E-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05 LA141 1.35E-09 3.17E-10 6.88E-11 0. 0. 0. 7.05E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0. 0. 0. 3.31 E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05 CE143+D 6.99E-09 3.79E-06 5.49E-10 0. 1.59E-09 0. 5.55E-05 CE144+D 2.08E-06 6.52E-07 1.11 E-07 0. 3.61 E-07 0. 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0. 6.39E-09 0. 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 0. 2. 11 E-11 0. 8.59E-08 ND147+D 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.58E-05 PM147 3.18E-07 2.27E-08 1.22E-08 0. 4.01 E-08 0. 9.19E-06 PM148M+D 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.78E-05 PM148 3.02E-08 3.63E-09 2.35E-09 0. 6.17E-09 0. 9.70E-05 PM149 6.49E-09 6.90E-10 3.74E-10 0. 1.22E-09 0. 4. 71 E-05 PM151 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05 SM151 2.56E-07 3.81 E-08 1.20E-08 0. 3.94E-08 0. 5.53E-06 SM153 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05 EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05 EU154 2.30E-06 2.07E-07 1.89E-07 0. 9.09E-07 0. 4.81 E-05 EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E-07 0. 8.69E-05 EU156 5.62E-08 3.01 E-08 6.23E-09 0. 1.94E-08 0. 6.83E-05 TB160 1.66E-07 0. 2.06E-08 0. 4.94E-08 0. 3.68E-05 .H0166M 1.08E-06 2.26E-07 1 .91 E-07 0. 3.22E-07 0. 0. W181 4.23E-06 1.04E-08 1.43E-09 0. 0. 0. 3.79E-07 W185 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61 E-05 W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05 86
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PC! INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU PB210+D 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.57E-05 81210+0 1.97E-06 1.02E-05 1.69E-07 0. 1.15E-04 0. 5.17E-05 P0210 1.52E-03 2.43E-03 3.67E-04 0. 7.56E-03 0. 6.55E-05 RN222+D 0. 0. 0. 0. 0. 0. 0. RA223+D 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.38E-04 RA224+D 6.89E-03 1.25E-05 1.38E-03 0. 3.31 E-04 0. 3.78E-04 RA225+D 2.80E-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21E-04 RA226+D 5. 75E-01 1.84E-05 4.72E-01 0. 4.88E-04 0. 3.41 E-04 RA228+D 3.85E-01 9.99E-06 4.32E-01 0. 2.65E-04 0. 5.81 E-05 AC225 1.88E-05 1.94E-05 1.26E-06 0. 2.07E-06 0. 4.31 E-04 AC227+D 4.12E-03 6.63E-04 2.55E-04 0. 1.46E-04 0. 8.43E-05 TH227 + D 5.85E-05 7.96E-07 1.69E-06 0. 4.22E-06 0. 5.63E-04 TH228+D 2.07E-03 2.65E-05 7.00E-05 0. 1.38E-04 0. 5.79E-04 TH229 1.38E-02 1.81 E-04 6.80E-04 0. 8.84E-04 0. 5.27E-04 TH230 3.55E-03 1. 78E-04 9.91 E-05 0. 8.67E-04 0. 6.19E-05 TH232+D 3.96E-03 1.52E-04 3.01 E-04 0. 7.41 E-04 0. 5.27E-05 TH234 3.42E-07 1.51 E-08 9.88E-09 0. 8.01 E-08 0. 1.18E-04 .PA231+D 7.07E-03 2.34E-04 2.81 E-04 0. 1.28E-03 0. 7.37E-05 PA233 1.81 E-08 2.82E-09 3.16E-09 0. 1.04E-08 0. 1.44E-05 U232+D 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.98E-05 U233+D 3.72E-03 0. 2.25E-04 0. 6.1 OE-04 0. 6.45E-05 U234 3.57E-03 0. 2.21 E-04 0. 5.98E-04 0. 6.32E-05 U235+D 3.42E-03 0. 2.07E-04 0. 5.61 E-04 0. 8.03E-05 U236 3.42E-03 0. 2.12E-04 0. 5.73E-04 0. 5.92E-05 U237 2.36E-07 0. 6.27E-08 0. 6.81 E-07 0. 2.08E-05 U238+D 3.27E-03 0. 1.94E-04 0. 5.24E-04 0. 5.66E-05 NP237 +D 2.36E-03 1 .81 E-04 9.79E-05 0. 6.05E-04 0. 8.16E-05 NP238 5.83E-08 1.18E-09 9.08E-10 0. 3.76E-09 0. 4.04E-05 NP239 5.25E-09 3.77E-10 2.65E-10 0. 1.09E-09 0. 2.79E-05 PU238 1.25E-03 1.56E-04 3.16E-05 0. 1.15E-04 0. 7.50E-05 PU239 1.36E-03 1.65E-04 3.31 E-05 0. 1.22E-04 0. 6.85E-05 PU240 1.36E-03 1.65E-04 3.31 E-05 0. 1.22E-04 0. 6.98E-05 PU241 +D 4.00E-05 1.72E-06 8.04E-07 0. 2.96E-06 0. 1.44E-06 PU242 1.26E-03 1.59E-04 3.19E-05 0. 1.17E-04 0. 6. 71 E-05 PU244 1.47E-03 1.82E-04 3.65E-05 0. 1.35E-04 0. 1.00E-04 AM241 1.43E-03 6.40E-04 1.02E-04 0. 6.23E-04 0. 7.64E-05 AM242M 1.47E-03 6.25E-04 1.04E-04 0. 6.30E-04 0. 9.61 E-05 AM243 1.41E-03 6.14E-04 9.83E-05 0. 6.06E-04 0. 8.95E-05 CM242 8.80E-05 6.73E-05 5.84E-06 0. 1.87E-05 0. 8.16E-05 CM243 1.33E-03 6.03E-04 8.24E-05 0. 3.08E-04 0. 8.03E-05 CM244 1.11 E-03 5.36E-04 6.93E-05 0. 2.54E-04 0. 7.77E-05 CM245 1.76E-03 6.64E-04 1.05E-04 0. 4.11 E-04 0. 7.24E-05 .CM246 1.74E-03 6.64E-04 1.05E-04 0. 4.10E-04 0. 7.11 E-05 CM247+D 1.70E-03 6.53E-04 1.03E-04 0. 4.04E-04 0. 9.35E-05 CM248 1.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51 E-03 CF252 1.07E-03 0. 2.54E-05 0. 0. 0. 2.96E-04 87
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU H3 0. 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 BE10 4.48E-06 6.94E-07 1.13E-07 0. 5.30E-07 0. 2.84E-05 C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 N13 1.15E-08 1.15E-08 1.15E-08 1.15E-08 1.15E-08 1.15E-08 1.15E-08 F18 8.64E-07 0. 9.47E-08 0. 0. 0. 7.78E-08 NA22 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71 E-05 1.07E-05 0. 0. 0. 2.32E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 1.97E-04 0. 2.13E-05 0. 0. 0. 1.95E-07 SC46 7.24E-09 1.41 E-08 4.18E-09 0. 1.35E-08 0. 4.80E-05 CR51 0. 0. 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN54 0. 5.90E-06 1.17E-06 0. 1.76E-06 0. 1.21E-05 MN.56 0. 1.58E-07 2.81 E-08 0. 2.00E-07 0. 1.04E-05 FE55 3.78E-06 2.68E-06 6.25E-07 0. 0. 1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0. 0. 4.32E-06 3.24E-05 C057 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06 C058 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-05 C060 0 2.81E-06 6.33E-06 0. 0. 0. 3.66E-05 Nl59 1.32E-05 4.66E-06 2.24E-06 0. 0. 0. 7.31 E-07 Nl63 1. 77E-04 1.25E-05 6.00E-06 0. 0. 0. 1.99E-06 Nl65 7.49E-07 9.57E-08 4.36E-08 0. 0. 0. 5.193-06 CU64 0. 1.15E-07 5.41 E-08 0. 2.91 E-07 0. 8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0. 1.28E-05 0. 8.47E-06 ZN69M+D 2.40E-07 5.66E-07 5.19E-08 0. 3.44E-07 0. 3.11E-05 ZN69 1.47E-08 2.80E-08 1.96E-09 0. 1.83E-08 0. 5.16E-08 SE79 0. 3.73E-06 6.27E-07 0. 6.50E-06 0. 5. 70E-07 BR82 0. 0. 3.04E-06 0. 0. 0. 0. BR83+D 0. 0. 5.74E-08 0. 0. 0. 0. BR84 0. 0. 7.22E-08 0. 0. 0. 0. BR85 0. 0. 3.05E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88+D 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 2.98E-05 1.40E-05 0. 0. 0. 4.41 E-06 RB87 0. 1. 75E-05 6.11E-06 0. 0. 0. 6.11E-07 RB88 0. 8.52E-08 4.54E-08 0. 0. 0. 7.30E-15 RB89+D 0. 5.50E-08 3.89E-08 0. 0. 0. 8.43E-17 SR89+D 4.40E-04 0. 1.26E-05 0. 0. 0. 5.24E-05 SR90+D 8.30E-03 0. 2.05E-03 0. 0. 0. 2.33E-04 SR91 +D 8.07E-06 0. 3.21 E-07 0. 0. 0. 3.66E-05 SR92+D 3.05E-06 0. 1.30E-07 0. 0. 0. 7.77E-05 88
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU Y90 1.37E-08 0. 3.69E-10 0. 0. 0. 1.13E-04 Y91M+D 1.29E-10 0. 4.93E-12 0. 0. 0. 6.09E-09 Y91 2.01 E-07 0. 5.39E-09 0. 0. 0. 8.24E-05 Y92 1.21 E-09 0. 3.50E-11 0. 0. 0. 3.32E-05 Y93 3.83E-09 0. 1.05E-10 0. 0. 0. 1.17E-04 ZR93+D 5.53E-08 2.73E-08 1.49E-08 0. 9.65E-08 0. 2.58E-05 ZR95+D 4.12E-08 1.30E-08 8.94E-09 0. 1 .91 E-08 0. 3.00E-05 ZR97+D 2.37E-09 4.69E-10 2.16E-10 0. 7.11E-10 0. 1.27E-04 NB93M 3.44E-08 1.13E-08 2.83E-09 0. 1.32E-08 0. 4.07E-06 NB95 8.22E-09 4.56E-09 2.51 E-09 0. 4.42E-09 0. 1.95E-05 NB97 7.37E-11 1.83E-11 6.68E-12 0. 2.14E-11 0. 4.37E-07 M093 0. 1.06E-05 2.90E-07 0. 3.04E-06 0. 1.29E-06 M099+D 0. 6.03E-06 1.15E-06 0. 1.38E-05 0. 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.14E-10 6.08E-07 TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.72E-08 6.44E-06 TC101 3.60E-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.75E-17 RU103+D 2.55E-07 0. 1.09E-07 0. 8.99E-07 0. 2.13E-05
- RU105+D 2.18E-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 RU106+D 3.92E-06 0. 4.94E-07 0. 7.56E-06 0. 1.88E-04 RH105 1.73E-07 1.25E-07 8.20E-08 0. 5.31 E-07 0. 1.59E-05 PD107 0. 2.08E-07 1.34E-08 0. 1.88E-06 0. 9.66E-07 PD109 0. 2.51 E-07 5.70E-08 0. 1.45E-06 0. 2.53E-05
. AG110M+D 2.05E-07 1.94E-07 1.18E-07 0. 3.70E-07 0. 5.45E-05 AG111 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 0. 4.80E-05 CD113M 0. 4.51 E-06 1.45E-07 0. 4.99E-06 0. 2. 71 E-05 CD115M 0. 2.60E-06 8.39E-08 0. 2.08E-06 0. 8.23E-05 SN123 4.44E-05 7.29E-07 1.0SE-06 5.84E-07 0. 0. 6.71 E-05 SN125+D 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.12E-04 SN126+D 1.16E-04 2.16E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 SB124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0. 3.38E-06 7.80E-05 SB125+D 2.48E-06 2. 71 E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05 SB126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 0. 1.14E-06 9.41 E-05 SB127 3.63E-07 7.76E-09 1.37E-07 4.08E-09 0. 2.47E-07 6.16E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0. 0. 1.13E-05 TE127M+D 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0. 2.41 E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0. 1.22E-05 TE129M+D 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0. 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07 TE131 M+D 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0. 9.39E-05 TE131 +D 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0. 2.29E-09 TE132+D 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 0. 7.00E-05 TE133M+D 6.44E-08 3.66E-08 3.56E-08 5.11 E-08 3.62E-07 0. 1.48E-07
- TE134+D 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 0. 1.66E-09 1129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7 .01 E-06 0. 4.57E-07 1130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0. 2.29E-06 1131 + D 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 0. 1.62E-06 89
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0. 3.18E-07 1133 + D 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0. 2.58E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.1 OE-07 0. 5.1 OE-09 1135 + D 6.1 OE-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0. 1.74E-06 XE131 M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137. 0. 0. 0. 0. 0. 0. 0. XE138+D 0. 0. 0. 0. 0. 0. 0. CS134M + D 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08 CS134 8.37E-05 1.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 CS135 2.78E-05 2.55E-05 5.96E-06 0. 9.73E-06 3.52E-06 4.46E-07 CS136 8.59E-06 3.38E-05 2.27E-05 0. 1.84E-05 2.90E-06 2.72E-06 CS137+D 1.12E-04 1.49E-04 5.19E-05 0. 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0. 1.1 OE-07 1.28E-08 6.76E-11 CS139+D 4.87E-08 7.17E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.33E-23 BA139 1.39E-07 9.78E-11 4.05E-09 0. 9.22E-11 6.74E-11 1.24E-06 BA140+D 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05 BA141 +D 6. 71 E-08 5.01E-11 2.24E-09 0. 4.65E-11 3.43E-11 1.43E-13 BA142+D 2.99E-08 2.99E-11 1.84E-09 0. 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1. 71 E-09 4.55E-10 0. 0. 0. 9.82E-05 LA141 4.55E-10 1.40E-10 2.31 E-11 0. 0. 0. 2.48E-05 LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0. 4.18E-09 0. 2.54E-05 CE143+D 2.35E-09 1.71 E-06 1.91E-10 0. 7.67E-10 0. 5.14E-05 CE144+D 6.96E-07 2.88E-07 3.74E-08 0. 1. 72E-07 0. 1. 75E-04 PR143 1.31 E-08 5.23E-09 6.52E-10 0. 3.04E-09 0. 4.31 E-05 PR144 4.30E-11 1.76E-11 2.18E-12 0. 1.01E-11 0. 4.74E-14 ND147+D 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.68E-05 PM147 1.05E-07 9.96E-09 4.06E-09 0. 1.90E-08 0. 9.47E-06 PM148M+D 4.14E-08 1.05E-08 8.21 E-09 0. 1.59E-08 0. 6.61 E-05 PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.00E-09 0. 9.90E-05 PM149 2.17E-09 3.05E-10 1.25E-10 0. 5.81E-10 0. 4.49E-05 PM151 9.87E-10 1.63E-10 8.25E-11 0. 2.93E-10 0. 3.66E-05 SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 SM153 1.22E-09 1.01 E-09 7.43E-11 0. 3.30E-10 0. 2.85E-05 EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.17E-05 EU154 7.91 E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.39E-05 EU155 1.74E-07 1.68E-08 1.04E-08 0. 6.57E-08 0. 9.63E-05 EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05 TB160 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05
- H0166M 3.57E-07 1.1 OE-07 7.96E-08 0. 1.61 E-07 0. 0.
W181 1.42E-08 4.58E-09 4.79E-10 0. 0. 0. 3.90E-07 W185 5.79E-07 1.91 E-07 2.02E-08 0. 0. 0. 1.65E-05 W187 1.46E-07 1.19E-07 4.17E-08 0. 0. 0. 3.22E-05 90
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU PB210+ D 1.81 E-02 5.44E-03 7.01 E-04 0. 1. 72E-02 0. 5.74E-05 8121 O+ D 6.59E-07 4.51 E-06 5.66E-08 0. 5.48E-05 0. 5.15E-05 P0210 6.09E-04 1.07E-03 1.23E-04 0. 3.60E-03 0. 6.75E-05 RN222+D 0. 0. 0. 0. 0. 0. 0. RA223+D 7.11 E-03 1.08E-05 1.42E-03 0. 3.10E-04 0. 3.43E-04 RA224+D 2.31 E-03 5.52E-06 4.61 E-04 0. 1.58E-04 0. 3. 71 E-04 RA225 +D 9.37E-03 1.1 OE-05 1.87E-03 0. 3.15E-04 0. 3.27E-04 RA226+D 3.22E-01 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51 E-04 RA228+D 1.37E-01 4.41 E-06 1.51E-01 0. 1.26E-04 0. 5.98E-05 AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04 AC227+D 2.05E-03 3.03E-04 1.22E-04 0. 8.81 E-05 0. 8.68E-05 TH227 + D 1.96E-05 3.52E-07 5.65E-07 0. 2.01 E-06 0. 5.75E-04 TH228+D 6.80E-04 1.14E-05 2.30E-05 0. 6.41 E-05 0. 5.97E-04 TH229 8.39E-03 1.26E-04 4.11 E-04 0. 6.1 OE-04 0. 5.43E-04 TH230 2.16E-03 1.23E-04 6.00E-05 0. 5.99E-04 0. 6.38E-05 TH232+D 2.42E-03 1.05E-04 1.63E-04 0. 5.11 E-04 0. 5.43E-05 TH234 1.14E-07 6.68E-09 3.31 E-09 0. 3.81 E-08 0. 1.21 E-04 .PA231+0 4.31 E-03 1.62E-04 1.68E-04 0. 9.10E-04 0. 7.60E-05 PA233 7.33E-09 1.41 E-09 1.26E-09 0. 5.32E-09 0. 1.61 E-05 U232+D 5.89E-03 0. 4.21 E-04 0. 6.38E-04 0. 7.19E-05 U233+D 1.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05 U234 1.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51 E-05 U235+D 1.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05 U236 1.14E-03 0. 7.09E-05 0. 2.73E-04 0. 6.11E-05 U237 7.89E-08 0. 2.1 OE-08 0. 3.24E-07 0. 2.09E-05 U238+D 1.09E-03 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05 NP237+D 1.44E-03 1.25E-04 5.85E-05 0. 4.33E-04 0. 8.41 E-05 NP238 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05 NP239 1.76E-09 1.66E-10 9.22E-11 0. 5.21E-10 0. 2.67E-05 PU238 7.21 E-04 1.02E-04 1.82E-05 0. 7.80E-05 0. 7.73E-05 PU239 8.27E-04 1.12E-04 2.01 E-05 0. 8.57E-05 0. 7.06E-05 PU240 8~26E-04 1.12E-04 2.01 E-05 0. 8.56E-05 0. 7.19E-05 PU241 +D 1.84E-05 9.42E-07 3.69E-07 0. 1.71 E-06 0. 1.48E-06 PU242 7.66E-04 1.08E-04 1.94E-05 0. 8.25E-05 0. 6.92E-05 PU244 8.95E-04 1.23E-04 2.22E-05 0. 9.45E-05 0. 1.03E-04 AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31 E-04 0. 7.87E-05 AM242M 8.70E-04 3.19E-04 5.80E-05 0. 4.30E-04 0. 9.90E-05 AM243 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.23E-05 CM242 2.94E-05 2.97E-05 1.95E-06 0. 8.89E-06 0. 8.40E-05 CM243 6.91 E-04 2.86E-04 4.09E-05 0. 1.91 E-04 0. 8.28E-05 CM244 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-04 0. 8.00E-05 CM245 1.07E-03 3.33E-04 6.1 OE-05 0. 2.85E-04 0. 7.46E-05 .CM246 1.06E-03 3.32E-04 6.09E-05 0. 2.84E-04 0. 7.33E-05 CM247+D 1.03E-03 3.27E-04 6.00E-05 0. 2.80E-04 0. 9.63E-05 CM248 8.60E-03 2.69E-03 4.95E-04 0. 2.31 E-03 0. 1.55E-03 CR252 3.51 E-04 0. 8.37E-06 0. 0. 0. 3.05E-04 91
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 BE10 3.18E-06 4.91 E-07 7.94E-08 0. 3. 71 E-07 0. 2.68E-05 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 F18 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08 NA22 1.74E-05 1. 74E-05 1.74E-05 1.74E-05 1.74E-05 1. 74E-05 1.74E-05 NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1. 70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0. 0. 0. 2.17E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 1.83E-05 0. 2.00E-05 0. 0. 0. 1.84E-07 SC46 5.51 E-09 1.07E-08 3.11 E-09 0. 9.99E-09 0. 5.21 E-05 CR51 0. 0. 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN54 0. 4.57E-06 8.72E-07 0. 1.36E-06 0. 1.40E-05 MN56 0. 1.15E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06 FE55 2.75E-06 1.90E-06 4.43E-07 0. 0. 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91 E-06 0. 0. 2.85E-06 3.40E-05 C057 0. 1.75E-07 2.91 E-07 0. 0. 0. 4.44E-06 C058 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51 E-05 C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05 Nl59 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07 Nl63 1.30E-04 9.01 E-06 4.36E-06 0. 0. 0. 1.88E-06 Nl65 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1.74E-06 CU64 0. 8.33E-08 3.91 E-08 0. 2.1 OE-07 0. 7.1 OE-06 ZN65 4.84E-06 1.54E-05 6.96E-06 0. 1.03E-05 0. 9.70E-06 ZN69M+D 1.70E-07 4.08E-07 3.73E-08 0. 2.47E-07 0. 2.49E-05 ZN69 1.03E-08 1.97E-08 1.37E-09 0. 1.28E-08. 0. 2.96E-09 SE79 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. 5.38E-07 BR82 0. 0. 2.26E-06 0. 0. 0. 2.59E-06 BR83+D 0. 0. 4.02E-08 0. 0. 0. 5.79E-08 BR84 0. 0. 5.21 E-08 0. 0. 0. 4.09E-13 BR85 0. 0. 2.14E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88+D 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 2.11 E-05 9.83E-06 0. 0. 0. 4.16E-06 RB87 0. 1.23E-05 4.28E-06 0. 0. 0. 5.76E-07 RB88 0. 6.05E-08 3.21 E-08 0. 0. 0. 8.36E-19 RB89+D 0. 4.01 E-08 2.82E-08 0. 0. 0. 2.33E-21 .SR89+D 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05 SR90+D 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04 SR91 + D 5.67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05 SR92+D 2.15E-06 0. 9.30E-08 0. 0. 0. 4.26E-05 92
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04 Y91M+D 9.09E-11 0. 3.52E-12 0. 0. 0. 2.67E-10 Y91 1.41 E-07 0. 3.77E-09 0. 0. 0. 7.76E-05 Y92 8.45E-10 0. 2.47E-11 0. 0. 0. 1.48E-05 Y93 2.68E-09 0. 7.40E-11 0. 0. 0. 8.50E-05 ZR93+D 4.18E-08 2.34E-09 1.09E-09 0. 8.87E-09 0. 2.43E-06 ZR95 +D 3.04E-08 9.75E-09 6.60E-09 0. 1.53E-08 0. 3.09E-05 ZR97+D 1.68E-09 3.39E-10 1.55E-10 0. 5.12E-10 0. 1.05E-04 NB93M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06 NB95 6.22E-09 3.46E-09 1.86E-09 0. 3.42E-09 0. 2.10E-05 NB97 5.22E-11 1.32E-11 4.82E-12 0. 1.54E-11 0. 4.87E-08 M093 0. 7.51 E-06 2.03E-07 0. 2.13E-06 0. 1.22E-06 M099+D 0. 4.31 E-06 8.20E-07 0. 9.76E-06 0. 9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0. 1.06E-08 3.42E-10 4.13E-07 TC99 1.25E-07 1.86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.08E-06 TC101 2.54E-10 3.66E-10 3.59E-09 0. 6.59E-09 1.87E-10 1.10E-21 RU103+D 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E-05
- RU105+0 1.54E-08 0. 6.08E-09 0. 1.99E-07 0. 9.42E-06 RU106+D 2.75E-06 0. 3.48E-07 0. 5.31 E-06 0. 1. 78E-04 RH105 1.21 E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41 E-05 PD107 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.11E-07 PD109 0. 1.77E-07 3.99E-08 0. 1 .01 E-06 0. 1.96E-05 AG110M+D 1.60E-07 1.48E-07 8.79E-08 0. 2.91 E-07 0. 6.04E-05 AG111 5.81 E-08 2.43E-08 1.21 E-08 0. 7.84E-08 0. 4.46E-05 CD113M 0. 3.18E-06 1.02E-07 0. 3.50E-06 0. 2.56E-05 CD115M 0. 1.84E-06 5.87E-08 0. 1.46E-06 0. 7.74E-05 SN123 3.11 E-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 SN125+D 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0. 1.04E-04 SN126+D 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 SB124 2.80E-06 5.29E-08 1.11 E-06 6.79E-09 0. 2.18E-06 7.95E-05 SB125 + D 1. 79E-06 2.00E-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05 SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 SB127 2.58E-07 5.65E-09 9.90E-08 3.1 OE-09 0. 1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0. 1.07E-05 TE125M+D 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0. 2.27E-05 TE127 1.1 OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0. 8.68E-06 TE129M+D 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 0. 2.37E-08 TE131M+D 1. 73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0. 8.40E-05 TE131 +D 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0. 2.79E-09 TE132+D 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0. 7.71 E-05 TE133M+D 4.62E-08 2.70E-08 2.60E-08 3.91 E-08 2.67E-07 0. 6.64E-08
- TE134+D 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0. 3.59E-11 1129 3.27E-06 2.81 E-06 9.21 E-06 7.23E-03 6.04E-06 0. 4.44E-07 1130 7.56E-07 2.23E-06 8.80E-07 . 1.89E-04 3.48E-06 0. 1.92E-06 1131 + D 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 0. 1.57E-06 93
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07 1133 + D 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0. 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51E-10 1135 + D 4.43E-07 1.16E-06 4.28E-07 7 .65E-05 1.86E-06 0. 1.31 E-06 XE131 M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 + D 0. 0. 0. 0. 0. 0. 0. CS134M+D 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08 CS134 6.22E-05 1.48E-04 1.21 E-04 0. 4.79E-05 1.59E-05 2.59E-06 CS135 1.95E-05 1.80E-05 7.99E-06 0. 6.81 E-06 2.04E-06 4.21 E-07 CS136 6.51 E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06 CS137 +D 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.11 E-06 CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.01 E-08 7 .91 E-09 4.65E-13 CS139+D 3.41 E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.1 OE-30 BA139 9.70E-08 6.91 E-11 2.84E-09 0. 6.46E-11 3.92E-11 1.72E-07 BA140+D 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05 BA141 +D 4.71E-08 3.56E-11 1.59E-09 0. 3.31 E-11 2.02E-11 2.22E-17 BA142+D 2.13E-08 2.19E-11 1.34E-09 0. 1.85E-11 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05 LA141 3.19E-10 9.90E-11 1.62E-11 0. 0. 0. 1.18E-05 LA142 1.28E-10 5.82E-11 1.45E-11 0. 0. 0. 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CE143+D 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-10 0. 4.56E-05 CE144+D 4.88E-07 2.04E-07 2.62E-08 0. 1.21E-07 0. 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05 PR144 3.01E-11 1.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18 ND147+D 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05 PM147 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06 PM148M+D 3.07E-08 7.95E-09 6.08E-09 0. 1.20E-08 0. 6.74E-05 PM148 7.17E-09 1.19E-09 5.99E-10 0. 2.25E-09 0. 9.35E-05 PM149 1.52E-09 2.15E-10 8.78E-11 0. 4.06E-10 0. 4.03E-05 PM151 6.97E-10 1.17E-10 5.91 E-11 0. 2.09E-10 0. 3.22E-05 SM151 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06 SM153 8.57E-10 7.15E-10 5.22E-11 0. 2.31E-10 0. 2.55E-05 EU152 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05 EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05 EU155 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06 EU156 1.37E-08 1.06E-08 1. 71 E-09 0. 7.08E-09 0. 7.26E-05 TB160 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05 H0166M 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0. W181 9.91 E-09 3.23E-09 3.46E-10 0. 0. 0. 3.68E-07 W185 4.05E-07 1.35E-07 1.42E-08 0. 0. 0. 1.56E-05 W187 1.03E-07 8.61 E-08 3.01 E-08 0. 0. 0. 2.82E-05 94
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210+D 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05 8121 O+ D 4.61 E-07 3.18E-06 3.96E-08 0. 3.83E-05 0. 4.75E-05 P0210 3.56E-04 7.56E-04 8.59E-05 0. 2.52E-03 0. 6.36E-05 RN222+D 0. 0. 0. 0. 0. 0. 0. RA223+D 4.97E-03 7.65E-06
- 9.94E-04 0. 2.17E-04 0. 3.21E-04 RA224+D 1.61 E-03 3.90E-06 3.23E-04 0. 1.10E-04 0. 3.40E-04 RA225+D 6.56E-03 7.78E-06 1.31 E-03 0. 2.21 E-04 0. 3.06E-04 RA226+D 3.02E-01 5.74E-06 2.20E-01 0. 1.63E-04 0. 3.32E-04 RA228+D 1.12E-01 3.12E-06 1.21 E-01 0. 8.83E-05 0. 5.64E-05 AC225 4.40E-06 6.06E-06 2.96E-07 0. 6.90E-07 0. 4.07E-04 AC227+D 1.87E-03 2.48E-04 1.11 E-04 0. 8.00E-05 0. 8.19E-05 TH227 + D 1.37E-05 2.48E-07 3.95E-07 0. 1.41 E-06 0. 5.40E-04 TH228+D 4.96E-04 8.40E-06 1.68E-05 0. 4.67E-05 0. 5.63E-04 TH229 7.98E-03 1.19E-04 3.91 E-04 0. 5.75E-04 0. 5.12E-04 TH230 2.06E-03 1.17E-04 5.70E-05 0. 5.65E-04 0. 6.02E-05 TH232+D 2.30E-03 1.00E-04 1.50E-04 0. 4.82E-04 0. 5.12E-05 TH234 8.01 E-08 4. 71 E-09 2.31E-09 0. 2.67E-08 0. 1.13E-04 PA231 +D 4.10E-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05 PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05 U232+D 4.13E-03 0. 2.95E-04 0. 4.47E-04 0. 6.78E-05 U233+D 8. 71 E-04 0. 5.28E-05 0. 2.03E-04 0. 6.27E-05 U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 0. 6.14E-05 U235 + D 8.01 E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81 E-05 U236 8.01 E-04 0. 4.96E-05 0. 1.91 E-04 0. 5.76E-05 U237 5.52E-8 0. 1.47E-08 0. 2.27E-07 0. 1.94E-05 U238+D 7.67E-04 0. 4.54E-05 0. 1. 75E-04 0. 5.50E-05 NP237+D 1.37E-03 1.19E-04 5.54E-05 0. 4.12E-04 0. 7.94E-05 NP238 1.37E-08 3.69E-10 2.13E-10 0. 1.25E-09 0. 3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 0. 2.40E-05 PU238 6.80E-04 9.58E-05 1.71E-O~ 0. 7.32E-05 0. 7.30E-05 PU239 7.87E-04 1.06E-04 1 .91 E-05 0. 8.11E-05 0. 6.66E-05 PU240 7.85E-04 1.06E-04 1 .91 E-05 0. 8.1 OE-05 0. 6.78E-05 PU241 +D 1.65E-05 8.44E-07 3.32E-07 0. 1.53E-06 0. 1.40E-06 PU242 7.29E-04 1.02E-04 1.84E-05 0. 7 .81 E-05 0. 6.53E-05 PU244 8.52E-04 1.17E-04 2.11 E-05 0. 8.95E-05 0. 9.73E-05 AM241 8.19E-04 2.88E-04 5.41 E-05 0. 4.07E-04 0. 7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 0. 8.70E-05 CM242 2.06E-05 2.1 OE-05 1.37E-06 0. 6.22E-06 0. 7.92E-05 CM243 6.39E-04 2.41 E-04 3.75E-05 0. 1. 75E-04 0. 7.81E-05 CM244 4.83E-04 2.07E-04 2.87E-05 0. 1.34E-04 0. 7.55E-05 CM245 1.02E-03 2.87E-04 5.76E-05 0. 2.69E-04 0. 7.04E-05 CM246 1.01 E-03 2.87E-04 5. 75E-05 0. 2.68E-04 0. 6.91 E-05 CM247+D 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 0. 9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04 0. 2.18E-03 0. 1.47E-03 CF252 2.64E-04 0. 6.29E-06 0. 0. 0. 2.88E-04 95
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 12 TABLE 2.2 PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors (mrem/Cil Individual/Organ (Curies)
H-3 12.3 yr 1.75E-06 Adult/TB 1.71 E+06 Na-24 15 h 5.44E-03 Teen/TB 551.5 Sc-46 83.9 d 2.02E-02 Teen/TB 148.5 Cr-51 27.8 d 1.56E-03 Adult/GI (LLI) 6,410.0
- 1 Mn-54 303 d 3.50E-02 Teen/TB 85.7 I Fe-55 2.6 yr 4.48E-03 Child/Bone 2,232.0 Mn-56 2.576 h 1.86E-03 Teen/TB 1,612.0 Co-57 270 d 4.39E-03 Teen/TB 683.4 Co-58 71.3 d 1.03E-02 Teen/TB 291.3 Fe-59 45.6 d 4.08E-02 Adult/GI (LLI) 245.1 Co-60 5.26 yr 4.71E-01 Teen/TB 6.37 Cu-64 12.8 h 1.32E-03 Teen/GI (LLI) 7,575.0 Ni-65 2.56 h 5.82E-04 Teen/TB 5, 154.0 Zn-65 245 d 1.83E-01 Teen/TB 16.4 Br-84 31.8 mo 2.02E-03 Teen/TB 1,485.2 Rb-86 1.02 mo 3.06E-01 Child/TB 9.80 Rb-88 17.8 mo 6.92E-04 Teen/TB 4,335.3 Sr-89 52.7 d 1 .56E-01 Child/Bone 64.1 Sr-90 27.7 yr 2. 71 E-00 Adult/Bone 3.69 Sr-91 9.67 h 1.16E-03 Teen/TB 2,586.0 Sr-92 2.71 h 1.51 E-03 Teen/TB 1,986.8 Y-92 3.53 h 2.69E-04 Teen/TB 11, 150.0 Nb-95 35 d 7.24E+OO Adult/GI (LLI) 1.38 Zr-95 65.5 d 6.17E-03 Teen/TB 486.2 Nb-97 72 mo 6.95E-04 Teen/TB 4,316.6 Zr-97 17 h 9.28E-04 Teen/TB 3,232.8 Mo-99 66.7 h 1.11 E-03 Teen/Kidney 9,009.0 Tc-99m 6.05 h 1.42E-04 Teen/TB 21,126.8 Ru-103 39.5 d 2.74E-03 Teen/TB 1,094.9 Ag-110m 255 d 7.75E-02 Teen/TB 38.7 96
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 12 TABLE 2.2 (continued) PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors (mrem/Cil Individual/Organ (Curies) Cd-113m 13.6 yr 6.02E-02 Adult/GI (LLI) 166.1 Sb-124 60 d 1.51 E-02 Teen/TB 198.7 Sb-125 2.7 yr 5.11E-02 Teen/TB 58.7 Te-127 9.4 h 7.38E-03 Teen/GI (LLI) 1,355.0 Te-127m 109 d 1.39E-01 Teen/Kidney 71.9 Te-129m 34.1 d 2.66E-01 Adult/GI (LLI) 37.6 1-130 12.3 h 1.17E-02 Child/Thyroid 854.7 1-131 8.05 d 3.27E-01 Child/Thyroid 30.6 Te-131 m 30 h 2.27E-01 Adult/GI (LLI) 44.0 1-132 2.26 h 3.18E-05 Teen/TB 94,339.0 Te-132 77.7 h 2.93E-01 Adult/GI (LLI) 34.1 1-133 20.3 h 3.94E-02 Child/Thyroid 253.8 Cs-134 2 yr 2.86E+OO Adult/TB 1.04 1-134 52 mo 2.43E-03 Teen/TB 1,234.0 1-135 6.68 h 1.64E-03 Child/Thyroid 6,097.0 Cs-136 13.7 d 4.13E-01 Adult/TB 7.26 Cs-137 30 yr 1.71 E+OO Adult/TB 1.75 Cs-138 32.2 mo 2.31 E-03 Teen/TB 1,298.0 Ba-139 82.9 mo 4.66E-05 Teen/TB 64,377.0 Ba-140 12.8 d 7.96E-04 Teen/TB 3,768.0 La-140 40.22 h 1.85E-02 Adult/GI {LLI) 540.5 Ce-141 32.5 d 3.70E-04 Teen/TB 8, 108.0 Ce-144 284 d 1.56E-03 Teen/TB 1,923.0 Eu-152 12. 7 yr 3.24E-01 Teen/TB 9.25 W-187 23.9 h 1.98E-01 Adult/GI (LLI) 50.5 Np-239 2.346 d 2.26E-03 Adult/GI (LLI) 4,424.0
- 97
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- 111. URANIUM FUEL CYCLE DOSE Revision 12 A. SPECIFICATION In accordance with Appendix A, Section 111.1.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Appendix A, Sections 111.C.1, 111.D.1, or 111.H.1, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be calculated. The dose is to be determined for the member of the public protected to be the most highly exposed to these combined sources.
B. ASSUMPTIONS
- 1. The full time resident determined to be maximally exposed individual (excluding infant) is assumed also to be a fisherman.
This individual is assumed to drink water and ingest local fish at the rates specified in Sections 11.C.2.1 and 11.C.2.2 .
- 2. Amount of shore line fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours per quarter (average of approximately 1 /2 hour per day each day of the quarter) for the second and third quarters of the year, 36 hours for the fourth quarter and 1 6 hours for the first quarter .
- 98
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- c. DOSE CALCULATION Revision 12 Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP and GASPAR computer codes, and doses to like organs and total body summed. Added to this sum will be a mean dose rate, calculated or measured for the shoreline due to Plant present curing the quarter in question, times the assumed fishing time.
(2.15) where:
= 40 CFR 190 dose (mrem).
= Limiting dose to an individual from gaseous source term (mrem).
= Limiting dose to an individual from liquid source term (mrem).
= Mean dose rate calculated to be applicable to Lake Michigan shoreline adjacent to Plant site (mrem/hr).
T = Assumed shoreline fishing time for the quarter in questions (hours) .
- 99
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Proo t4o 3.01 Ati~fiment 1 Revision 8 Page 1of1 PS&Llog No 97-;l(J/ 6 Item Identification: No ~o.o,.c..,.M._____ Rev_.1,.2___ Title Offsjte Dose catlation Manual " "SE REV Describe Issue/Change: UQdited Tables 1.3. 1.4. 1.4 A. and 1.9 Reason for lss~e/Change: Tata 1.3.gonfalns the "new" fjye year average falisades meteorpl9£1icaldafa. Tablg 1.4. 1.4.A.. and 1.9 are ypdat&d on an annual basis. as they reflect changes In critical recgijo[spr d!plgri ' oblectiye quantities which are based on the fa!lsades Land Use Census wblcb Is conjycted annua!J,V.
- 1. Does the item involve a change to procedures as described In the FSAR? Yes No FSAR Sections affected .....i.:Nmou:ne_--..1....__ _ _ _ _ _ _ _ _ __
FSAR Sections reviewed ___.1.... 1..,.2....5.___ _ _ _ _ _ _ _ _ _ _ __
-~
"'2. Does the itern involve a change to the facility as described-or implied in the FSAR?
FSAR Sections affected . . 1Nlr:l o1111.n1.111e.. __ _ _ _ _ _ _ _ _ _ _ __ FSAR Sections reviewed __._11....... 2.....s______________ DBD Sections reviewed --1Nwoiu.nme..lil5all'jppl&l l mica....,b....le...__ _ _ _ _ _ _ _ _ __ 1--- .:-
~ '3. Does the item involve a test or experiment not described in1he FSAR?
FSAR Sections affected _...N.,.o.... ne_ _ _ _ _ _ _ _ _ _ _ _ __
- FSAR Sections reviewed __....11...,..-2,,...5_.1....,4....__ _ _ _ _ _ _ _ _ _ _ __
DBD Sections reviewed _ ....N...o,.,.ne.....,ap_p_lica ......b_le_ _ _ _ _ _ _ _ _ __
*"v/
- 4. Should the Technical Specifications or any of their Bases be changed in conjunction with this item?
TS Sections affected None IJ 1X NI TS Sections reviewed __.6......... o_o....c..,M.___ _ _ _ _ _ _ _ _ _ _ __ 1..*C.~t}$1AJ6 . ' " ' ' "DoQ)lflc'-'r Justify "NO" answers below if logic is not obvious: Meteorological data (Table 1.3) is based on ~ s~year
~ .;".**fMl .." *" .* " ,".'"**""'......4 average, and is U:,Jdated every 5 years. The OOCM requires a Land Use Survey be perfOtmed to Identify real offslte dose parameters. This data can be used to*predlct doses based on actual parameter,- rather than using default data, and making conservative estimates based on 24 hour occupancy at the site 'boundary.
If any Safety Review question listed above Is answered YES," perform a written USQ Evaluation according *to Section 5.3. if all Safety Review questions listed above are answered "NO," written USQ Evaluation Is not required. However, this attachment shall accompany other revlow materials for the Item to document that a Safety Evaluation was not required. __.....___ ------'---"'--"---'~-"*:""".',,-<w.:;~*c2'*"°""'~<.:*,~i~~~**~ris~~*J1~1~~~2;h;~;i*~l~i~i~~::~~~*~~~:i~;~;j~1~~~ --~\!;~~J;i~l£~~~{h~.d~* ~l:U~.i ...;.*~!,1j,;._<, 'i**.; *t~*,. ........1;.*.,~ ~*;\***i*j!;;*:;;.~; ~1-:.<1i~: .: .**: i,
' .~
PS~L log No*
' - _., *: :: - ~ ' ~:t.
S~'tiONl Yes. Np
- 1. Wiii the probability of an accident previously evaluated iri the FSAR be Increased?
- 2. Will the consequences of an accident previously evaluated in the FSAR be*
rncreased? x
- 3. Wiii the probability of "11J!functlons of equipment important to safety previously evaluated in the FSAR be increaeed? *
- 4. Wiii the consequences of a malfunction of ~quipment important to safety previously evaluated In the FSAR be Increased? x
- 5. Will the possibility of an accident of a different tyje than any previously evaluated in the FSAR be created? * ~ x
- 6. Will the possibility of a malfunction of a different type tttan any previously .*
evaluated in the FSAR be created?
- x
- 7. Will the margin of safety as defined by Plant Licensing Bases be reduced? x A written Safety Analysis which documents the beses for these answers sh-0,accomp-~y.thi~.fcm~* Jf . Ji:'.
any of the above questions are answered "YES/ an u"revieWed safety questic>ii is lnvolve.d tiJild.tllEJJt~ 1r6. shall not be im lamented without prior NRC co~curretlca. . .1 * ... ,, SECTION II
- 1. Should this be Included In an FSAR update?
- 2. Is an application for amendment to the Palisades* Operating License. reqµlr,~?
- 3. Is NRC approval required prior to Implementation of this item? x*
SECTION Ill
~. Pr4'parad JSv 14f.,/11 Da~'9
- _._,,,\_ .. .
..:,':,.. *.;..:**\,':....
" I'
PALISADES NUCI EAR PLANT Proc No 3.07 10CFR50.59 SAFETY REVIEW Attachment 1 Revlalon 8 Page 1of1 PS&L Log No 9e - o"' '17 Item Identification: No Rev Title nCFs1nr tt-:ir SE h.tJ.u.1. ~.uJ N'J..-J~At- {" ~,. WJ) /I~ - - ~~1 A. REV
- " r ,
- 1. Does the item involve a change~ures as described in the FSAR? Yes No FSAR Sections atfacted _ _..~~..:;.:;;:::;~----------
FSAR Sectfons reviewed _ __....H_,_,_k~~~~~~~~~~-
- 2. Does the Item Involve a change to the facility as described or Implied In the FSAR? _J '
FSAR Sections affected _ _u_~~ ......- - - - - - - - - - - - FSAR Sections reviewed __ 1_1..,...,_.'------------- DBD Sections reviewed ____ ~-YA~~~~~~~~~~~~-
- 3. Does the item involve a test or?;fe riment not described in the FSAR?
FSAR Sections affected -._.c,j-~:;..._----------- FSAR Sections reviewed __ /.;...;...,;i';..c':;..._------------ DBD Sections reviewed-----------------
- 4. Should the Technical Specific:ations or any of their Bases be changed In conjunction with this itam? ~ ~ .A TSSeclionS- V/X/n_,,-. ~
TS Sections reviewed f"!:f:! L1_ -~&
~~
___L__!!l11;;;r= Justify "NO" answers below if logic Is not obvious: If any Safety Review question listed above is answered "YES," perform* written USQ Evaluallon according to Section 5.3. If aH Safety Review questions listed above are answered "NO,* written USQ Evaluation It not required. However, this attachment shall accompany other review materials for the item to document that 1 8afety Evaluation was not required.
~
I :J-f,#' Prepared By Date
~~--*--**---*-*
PALISADES NUCLEAR PLANT Proc No 3.07 1OCEB&0.59 UNREVIEWED SAFm QUESTION EVALUATION Attachment 2 Revision 8 Page 1 of 1
- Item Identification: No - - - - - Rev 4' A Title PS&L Log No q f!J - 01q7
_....:,O...;.D.....;C=N1L.:....'-_....;l/~{Ji-~..;:;Ol;.;;..::l>~i:k.r.......c../.)=---- SECTION I Yes No
- 1. Will the probability of an accident previously evaluated in the FSAR be increased?
- 2. Will the consequences of an accident previously evaluated in the FSAR be increased?
- 3. Will the probability of malfunctions of equipment important to safety previously evaluated in the FSAR be increased?
- 4. Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
- 5. Will the possibility of an accident of a different type than any previously evaluated in the FSAR be created?
- 6. Will the possibility of a malfunction of a different type than any previously evaluated in the FSAR be created?
- 7. Will the margin of safety as defined by Plant Licensing Bases be reduced?
/
A written Safety Analysis which documents the bases for these answers shall accompany this form. If any of the above questions are answered "YES," an unreviewed safety question is involved and the item shall not be implemented without prior NRC concurrence. SECTION II Yes No
- 1. Should this be included in an FSAR update?
- 2. Is an application for amendment to the Palisades Operating License required?
- 3. Is NRC approval required prior to implementation of this item?
SECTIONU~ Prepared By I 2-:"f~r Gauif.~, :i-11-tt~ Date Reviewed By Date
*' ,:'\'
ODCM Appendix A Revision 7
- PALISADES NUCLEAR PLANT Issued Date 3/13/98 OFFSITE DOSE CALCULATION MANUAL TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060)
~{)~ I 3-9.,ff Procedure Sponsor Date
'\
~ l 76 Technical Reviewer Date User Reviewer Date Plant Manager - Operations
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060)
Page i Table of Contents I. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 II. DEFINITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 A. Channel Calibration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 B. Channel Check . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 C. Channel Functional Test . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 D. Source Check . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 E. Offsite Dose Calculation Manual . . . . . . . . . . . . . . . . . . . . . . . 2 F. Gaseous Rad waste Treatment System . . . . . . . . . . . . . . . . . . . 2 G. Members of the Public . . . . . . . . . . ~ . . . . . . . . . . . . . . . . . . . 2 H. Process Control Program lPCP> ... ; . . . . . . . . . . . . . . . . . . . . 3 I. Site Boundary . . . . . . . . . . . .* . . . . . . . . . . . . . . . . . . . . . . . . 3 J. Unrestricted Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 K. Ventilation Exhaust Treatment System . . . . . . . . . . . . . . . . . . . 3 Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES ... 4 A. Radioactive Gaseous Effluent Monitoring Instrumentation ...... 4
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . 4
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 B. Gaseous Effluents Dose Rate. . .. * . . . . . . . . . . . . . . . . . . . . . 1 0
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 10
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 C. Noble Gases Dose .... ~ . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 12
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page ii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060) Table of Contents D. 1-131. 1-133. Tritium. and Particulates . . . . . . . . . . . . . . . . . . 14
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 14
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 E. Gaseous Waste Treatment System . . . . . . . . . . . . . . . . . . . . 18
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 18
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~ ... 18 F. Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . 19
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19
- 2. Action . . . . . . *. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 20
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 G. Liguid Effluents Concentration . . . . . . . . . . . . . . . . . . . . . . . . 25
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 25
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 H. Liguid Effluent Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 29
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .30
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page iii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 {TAC NO 75060) Table of Contents I. Total Dose ......... *. . . . . . . . . . . . . . . . . . . . . . . . . . . . 31
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31
- 3. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . 32
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 J. Radiological Environmental Monitoring . . . . . . . . . . . . . . . . . . 34
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34
- 2. Action .* . . . . . . . . . . . . . . . . *. . . . . . . . . . . . . . . . . . . 34
- 3. Surveillance Requirements ....................... 35
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 K. SIRW or Temporary Liguid Storage Tank . . . . . . . . . . . . . . . . 47
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
- 3. Surveillance Requirement . . . . . . . . . . . . . . . . . . . . . . 47
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 L. Surveillance Requirement Time Intervals . . . . . . . . . . . . . . . . . 48
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48
- 3. Surveillance Requirements ....................... 49
- 4. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 M. Sealed Source Contamination ......................... 49
- 1. Requirement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49
- 2. Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49
- 3. Surveiliance Requirements . . . . . . . . . . . . . . . . . . . . . . 50
- 4. Bases . . . . . . . . . . . *. . . . . . . . . . . . . . . . . . . . . . . . . 51
PALISADES NUCLEAR PLANT ODCM OFFSITE POSE CALCULATION MANUAL Appendix A Revision 7 Page iv TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 {TAC NO 75060) Table of Contents IV. REPORTING REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 A. Radiological Effluent Release Report . . . . . . . . . . . . . . . . . . . 51
- 1. Supplemental Information . . . . . . . . . . . . . . . . . . . . . . 52
- 2. Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . 52
- 3. Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54
- 4. Radiological Impact on Man . . . . . . . . . . . . . . . . . . . . . 56
- 5. ODCM Changes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56
- 8. Radiological Environmental Operating Report . . . . . . . . . . . . . . 57 C. Nonroutine Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . 60 A. Licensee Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60
- 8. Definition of Major Radwaste System Modification . . . . . . . . . 60 TABLES A-1 Radioactive Gaseous Effluent Monitoring Instrumentation A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 8-1 Radioactive Gaseous Waste Sampling and Analysis Program C-1 Radioactive Liquid Effluent Monitoring Instrumentation C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements D-1 Radioactive Liquid Waste Sampling and Analysis Program E-1 Radiological Environmental Monitoring Program E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples E-3 Detection Capabilities for Environmental Sample Analysis F-1 Environmental Radiological Monitoring Program Summary
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060)
Page 1 of 61 I. INTRODUCTION The NRC, through 10CFR50.36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01, dated January 31, 1989, allowed relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 85, November 9, 1984). The relocated procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated procedural reporting requirements follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specification to satisfy the regulatory requirements of 1 OCFR50.36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance, and changes to the Offsite __ Dose Calculation Manual (ODCM) as well as record retention and reporting requirements .
- 11. DEFINITIONS A. Channel Calibration - a Channel Calibration shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Function Test. The Channel Calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
B. Channel Check - a Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 2 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060) C. Channel Functional Test - a Channel Functional Test shall be:
- 1. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.
- 2. Bistable channels - the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions.
D. Source Check - a source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. E. Offsite Dose Calculation Manual - (per Plant Technical Specification) - the Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain; 1 ) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by the Technical Specifications and, 2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the Technical
-Specifications.
F. Gaseous Radwaste Treatment System - any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. G. Members of the Public - 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060)
Page 3 of 61 H. Process Control Program (PCP) - shall contain the current formula, sampling, analyses, tests and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Part 20, 1 OCFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste. I. Site Boundary - that line beyond which the land is neither owned nor otherwise controlled by the licensee. J. Unrestricted Area - any area at or beyond the Site Boundary access which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or, any area within the Site Boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. K. Ventilation Exhaust Treatment System - any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric c!eanup systems are not considered to be ventilation exhaust treatment system components .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 4 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060) 111. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES A. Radioactive Gaseous Effluent Monitoring Instrumentation
- 1. Requirement:
The radioactive gaseous effluent monitoring instrumentation channels shown in Table A-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of requirement 111.B. l are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
- 2. Action:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above requirement, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table A-1. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- 3. Surveillance Requirements:
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check, Source Check, Channel Calibration and Channel Functional Test operations at the frequencies shown in Table A-2.
I PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 5 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060)
- 4. Bases:
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 1 OCFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 1 OCFR Part 50.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 6 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060)
Table A-1 Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action I
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor (RIA 111 3)
Providing Alarm and Automatic Termination of Release (1) At All Times 1
- 2. CONDENSER EVACUATION SYSTEM (RIA 0631)
- a. Noble Gas Activity Monitor (1) Above 210° F 3
- b. Evacuation Flow Indicator (Fl-0631 or Fl-06321 (1) * *
- Above 210°F 2
- 3. STACK GAS EFFLUENT SYSTEM
- a. Noble Gas Activity Monitor (RIA 2326) (1) At All Times 3
- b. Iodine/Particulate/Sampler/Monitor (RIA 23251 ( 1) At All Times 3
- c. Sampler Flow Rate Monitor (1) At All Times 2
- d. Hi Range Noble Gas (RIA 23271 * (1) Above 210° F 4
- 4. STEAM GENERATOR BLOWDOWN VENT SYSTEM
- a. Noble Gas Activity Monitor (RIA 23201 ( 1) Above 210° F 3
- 5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE
- a. Gross Gamma Activity Monitor* 1 per Main Above 325° F 4 (RIA 2323 and 2324) Steam Line
- 6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM
- a. Noble Gas Activity Monitor *
- 1 per Room Above 210° F 5 IRIA 1810 and 18111
- Setpoints for these instruments are exempted from 111.B. 1 limits, but are governed by Emergency Implementing Procedures or Operating procedures.
** Setpoints for these instruments are exempted from 111.B.1 limits, but are governed by Technical Specification Section 3.16 and Table 3.16. Minimum Operable Channels are defined by Technical Specification Table 3.17.3 (4) .
- Documentation of operability not required.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-09 (TAC NO 75060)
Page 7 of 61 Table A-1 <Cont'd) TABLE NOTATION - ACTION STATEMENTS ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels requirements, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the Facility staff independently verify the release rate calculations and discharge valve line up; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 2 - With the number of channels operable less thar:i required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 24 hours. ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. ACTION 4 - With the number of operable channels less than required by the Minimum Operable Channels requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours, and:
- a. Either restore the inoperable channel(s) to operable status within 7 days of
.the event, or
- b. Prepare and submit a Special Report to the NRC within 30 days following the event outlining the actions taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.
ACTION 5 - If either channel fails low or is otherwise inoperable, the ventilation dampers associated with that channel shall be closed immediately and action shall be taken to have the affected channel repaired. The dampers associated with the channel shall nm be opened until the affected channel has been declared operable. (Reference Technical Specification 3.17.3.4.)
PALISADES CLEAR PLANT ODC-OFFSITE DOSE ULATION MANUAL Appe Revisio Page 8 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Modes in Which Channel Source Channel Instrument Functional Surveillance Check Check Calibration T .. c:t "'--**'---'
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor-Providing Alarm and 0(4) p R(3) 0(1 )(2)
- Automatic Termination of Release
- 2. CONDENSER EVACUATION SYSTEM
- a. Noble Gas Activity Monitor 0 M R(3) 0(2) Above 210° F
- b. Evacuation Flow Indicator (Fl-0632) or 0(4) N/A R N/A Above 210°F
- c. Evacuation Flow Indicator (Fl-0631 l 0(4) N/A N/A N/A Above 210°F
- 3. ST ACK GAS EFFLUENT SYSTEM
- a. Noble Gas Activity Monitor 0 M R(3) 0(2) *
- b. Iodine Particulate Sampler/Monitor w M** R(3l** NA *
- c. Sampler Flow Rate Monitor 0 NA R NA *
- d. Hi Range Noble Gas 0 M R(3) 0(2) Above 210° F
- 4. STEAM GENERATOR BLOWDOWN VENT SYSTEM
- a. Noble Gas Activity Monitor 0 M R(3) 0(2) Above 210° F
- 5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE
- a. Gross Gamma Activity Monitor 0 M R(3) 0(2) Above 325° F
- 6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM
- a. Noble Gas Activity Monitor s M R(31 M(1 )(21 Above 210° F IT~~hni,..,.I c..,<>rifir,.ti~n T,.hl~ .IL 17 ~ lt<>m .II.I
- At all times other than when the line is valved out and locked.
- Sampler not applicable
PALISADES CLEAR PLANT ODCM OFFSITE DOSE C.ILATION MANUAL AppenA Revisio1lll' Page 9 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-2 (Cont'd) TABLE NOTATION ( 1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint. (2) The Channel Functional Test shall also demonstrate that control room alarm annunciation occurs if either of the following conditions exists.
- a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Range Noble Gas).
- b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
- b. For subsequent Channel Calibration, sources that have been related to the (1) calibration may be used.
(4) Channel Check shall be made at least once per 24 hours on days on which continuous or batch releases are made. TABLE FREQUENCY NOTATION S At least once per 1 2 hours D At least once per 24 hours M At least once per 31 days P Prior to radioactive batch release Q At least once per 92 days R At least once per 1 8 months W At least once per week
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 10 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) B. Gaseous Effluents Dose Rate
- 1. Requirement:
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
- a. For noble gases: Less than or equal to 500mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For lodine-131, for Iodine-: 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1 500 mrems/yr to any organ.
- 2. Action:
With the dose rate(s) averaged over a period of one hour exceeding *the above limits, without delay, restore the release rate to within the above limit(s).
- 3. Surveillance Requirements:
- a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of 8.1.a in accordance with the methodology and parameters in the ODCM.
- b. The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of 8.1.b in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 8-1 .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 11 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases:
This is provided to ensure that the dose at any time at and beyond the Site Boundary from gaseous effluents from all units on the site will be within 10 times the annual dose limits of 1 OCFR Part 20 to Unrestricted Areas. The annual dose limits are the doses associated with the concentrations of 10 times 10CFR Part 20, Appendix B, Table 2, Column 1 . These restrictions provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either within or outside the Site Boundary, to annual exposure greater than design objectives of 10CFR 50, Appendix I, Section 11.B.1. For Members of the Public who may at times be within the Site Boundary, the occupancy of the Member of the Public 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, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rate above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrems/yr to the total body.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 12 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER C.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Noble Gases Dose
- 1. Requirement:
The air dose due to noble gases released in gaseous effluents to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
- 2. Action:
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- 3. Surveillance Requirements:
Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 13 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 {TAC NO 75060)
- 4. Bases:
This requirement is provided to implement the requirements of Sections 11.B, Ill.A, and IV.A of Appendix I, 1 OCFR Part 50. The limiting Condition for Operation implements the guides set forth in Section 11.B of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV .A of Appendix I to assure that the releases of radioactive material in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.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 dose calculation methodology and parameters 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 1 OCFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for
.Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1 977. The ODCM equations provided for determining the air doses at and beyond the Site Boundary are based upon the historical average atmospheric conditions.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 14 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER D.
NRC GENERIC LETTER 89-01 (TAC NO 75060) 1-131. 1-133. Tritium. and Particulates
- 1. Requirement:
The dose to a Member of the Public from lodine-1 31 , lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
- 2. Action:
With the calculated dose from the release of lodine-1 31 , lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit and define(s) the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- 3. Surveillance Requirements:
Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, lodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 15 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 4.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Bases: This requirement is provided to implement the requirements of Sections 11.C, Ill.A, and IV.A of Appendix I, 1 OCFR Part
- 50. The requirements are the guides set forth in Section 11.C of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section II.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 methodology and parameters 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 11 Evaluating Compliance with 1 OCFR Part 50, Appendix I, Revision 1, October 1 977 and Regulatory Guide 1 . 111, "Methods for Estimating Atmospheric Transport and
. Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors, 11 Revision 1, July 1 977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate requirements for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in 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.
- ODC~
PALISADE UCLEAR PLANT OFFSITE DOSE .. ULATION MANUAL Appe Revisio Page 16 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table B-1 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Type Sampling Minimum Type of Lower Limit Frequency Analysis Activity Analysis Detection (LLD)a FrP-nl 1onrv fuCi/ml\ A. Waste Gas Storage Tank p Each Tank p Grab Sample Each Tank Principal Gamma Emittersb 1x1ff4
- 8. Containment PURGE p Each PURGE p Grab Sample Each PURGE Prin~ipal Gamma Emittersb 1 x 10-4 C. Stack Gas Effluent wa.e Continuousc Charcoal 1-1 31 , 1-1 33 1 x 10- 12 Sample wa,e 11 Continuousc Particulate Principal Gamma Emittersb 1x1ff Sample (1-131, Others)
Q Continuousc Composite Sr-89, Sr-90 and 1 x 10- 11 Particulate Gross Alpha Sample Noble Gas Noble Gases 1 E-06 Continuousc Monitor Gross Beta or Gamma
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 17 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
Table B-1 (Cont'd) TABLE NOTATION aThe LLD is defined, in Table E-3, note C. bThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99*, Cs-134, Cs-137, Ce-141, and Ce-144
- for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.
*Ten times the LLD because of low gamma yields.
cThe ratio of the sample flow rate to the sample stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with requirements 111.B.1, 111.C.1, and 111.D.1. d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing or after removal from sampler. 8 With channels operable on iodine monitor RIA 2325 less than required per 111.A.1, sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, start-up or Thermal Power change exceeding 1 5 percent of Rated Thermal Power in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 1 0. This requirement does not apply if, 1 ) analysis shows that the Dose Equivalent 1-1 31 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 .
PALISADES NUCLEAR PLANT ODCM OFESITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 18 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER E.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Gaseous Waste Treatment System
- 1. Requirement:
When gaseous waste exceeds a Xe-133 concentration of 1 E-05 µCi/cc, the Waste Gas Decay Tank System shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the system for a minimum of 1 5 days up to 60 days.
- 2. Action:
- a. If a waste gas decay tank is required to be released with less than 60 days holdup time, the system waste gas tank contents shall be evaluated and the waste gas decay tank with the lowest Xe-1 33 content shall be released .
- b. Gaseous waste may be discharged directly from the waste gas surge tank through a high-efficiency filter or from a waste gas decay tank with less than 1 5 days of holdup directly to the stack for a period not to exceed 7 days if the holdup system equipment is not available and the release rates meet requirements 111.B, C, and D.
- 3. Surveillance Requirements:
Not Applicable.
- 4. Bases:
The requirement that the appropriate portions of these systems 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" by meeting the design objectives given in Section 11.D *of Appendix I to 1 OCFR50 .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 19 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
It is expected that releases of radioactive materials in effluents shall be kept at small fractions of the limits specified in 20.1302 of 10CFR20. At the same time the licensee is permitted the flexibility of operation, compatible with considerations 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 111.8, C, and 0. F. Radioactive Ligujd Effluent Monitoring Instrumentation
- 1. Requirement:
The radioactive liquid effluent monitoring instrumentation channels shown in Table C-1 shall be operable. with their alarm/trip setpoints set to ensure that the limits of 111.G are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).
- 2. Action:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels Operable, take the Action shown in Table C-1 . Exert best efforts to return the instruments to Operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 20 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 3.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Surveillance Requirements: Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated Operable by performance of the Channel Check, Source Check, Channel Calibration and Channel Functional Test operations at the frequencies shown in Table C-2.
- 4. Bases:
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 releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 1 OCFR Part 20. The Operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 1 OCFR Part 50*.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 21 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
Table C-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Instrument Operable Action Channels
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line (RIA 1049) ( 1) 1
- b. Steam Generator Slowdown Effluent Line (RIA 0707) (1) 2
- 2. GROSS BETA OR GAMMA RADIOACTIVE MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent Line (RIA 0833) (1) 3
- b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211) (1) 3
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line (FIC 1051 or 1050) ( 1) 4
-1
- 4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip Setpoints are not applicable)
- a. Turbine Building Sumps Effluent Line ( 1) 3
- b. Service Water System Effluent ( 1) 3
- c. Steam Generator Slowdown Effluent (1) 3
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 22 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
Table C-1 (Cont'd) TABLE NOTATION ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with requirements and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
With the* number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue ~ provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131 at least once per 12 hours. ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided that, at least once per 24 hours, grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131 . ACTION 4 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves or tank levels may be used to estimate flow .
LEAR PLANT ODCMt LATION MANUAL Appen Revision Page 23 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Channel Source Channel Instrument Functional Check Check Calibration TP-st *
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OE RELEASE
- a. Liquid Radwaste Effluent Line (RIA 1049) p p R(3) 0(1)(2)
- b. Steam Generator Slowdown Effluent Line (RIA 0707) D M R(3) 0( 1)(2)
- 2. GROSS GAMMA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OE RELEASE
- a. Service Water System Effluent Line (RIA 0833) D M R(3) 0(2)
- b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211) D M R(3) 0(2)
- 3. FLOW RATE MEASUREMENT DEVICES (5)
- a. Liquid Radwaste Effluent Line (FIC 1051 or 1 050) 0(4) NA R NA
- 4. TURBINE SUMP EFFLUENT COMPOSITER 0(4) NA NA NA
- 5. SERVICE WATER SYSTEM EFFLUENT COMPOSITE SAMPLER 0(4) NA NA NA
- 6. STEAM GENERATOR BLOWDOWN EFFLUENT COMPOSITER 0(4) NA NA NA
PALISADES CLEAR PLANT ODC-OFFSITE DOSE ULATION MANUAL Appe Revisio Page 24 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-2 (Cont'd) TABLE NOTATION (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint. (2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists:
- a. Instrument indicates measure.d levels above the alarm setpoint.
- b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
- b. For subsequent Channel Calibration, sources that have been related to the (a) calibration may be used.
(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check shall be made at least once per 24 hours on days on which continuous or batch releases are made. (5) Turbine Sump Discharge Flow Meter FQl-5210 was calibrated at factory and doesn't require recalibration. TABLE FREQUENCY NOTATION D At least once per 24 hours Q At least once per 92 days M At least once per 31 days R At least once per 1 8 months p Prior to radioactive batch release,£-~ W At least once per week
' t
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 25 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER G.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Liquid Effluents Concentration
- 1. Requirement:
The concentration of radioactive material released in liquid effluents to Unrestricted Areas shall be limited to 1 0 times the concentrations specified in 1 OCFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml total activity.
- 2. Action:
With the concentration of radioactive material released in liquid effluents to Unrestricted Areas exceeding the above limits, without delay, restore the concentration to within the above limits.
- 3. Surveillance Requirements:
- a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table D-1 .
- b.
- The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of G.1 above.
PALISAD~S NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 26 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 4.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Bases: This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to Unrestricted Areas will be less than 10 times the concentration levels specified in 1 OCFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in Unrestricted Areas will result in exposures within the Section II.A design objectives of Appendix I, 1 OCFR Part 50, to a Member of the Public. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and 10 times the effluent concentration in air (submersion) was converted to an. equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other. detection limits can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-93 (19_68), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES 'CLEAR PLANT ODCM OFFSITE DOSE C JLATION MANUAL Appen. Revisio Page 27 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table D-1 Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Type Sampling Minimum Type of Lower Limit 8 Frequency Analysis Activity Analysis Detection (LLD1 Frequency (µCi/mil b p p c -7 A. Batch Waste Release Tanks Principal Gamma Emitters 5 x 10_6 Each Batch Each Batch 1-131 1x10 5 p M Dissolved and Entrained Gases 1 x 1o-One Batch/M (Gamma Emitters) p -5 M H-3 1x10_ d 7 Each Batch Composite Gross Alpha 1 x 10 8 p Q d Sr-89, Sr-90 5 x 1o-Each Batch Composite e f c -7 B. Continuous Releases Continuous w f Principal Gamma Emitters 5 x 10_6 (Turbine Sump, Steam Generator Composite 1-131 1 x 10 Slowdown, and Service Water) M M Dissolved and Entrained Gases 5 Grab Sample (Gamma Emitters) 1 x 10-f -5 Continuous M f H-3 1 x 10_7 Composite Gross Alpha 1 x 10 f 8 Continuous Q Sr-89, Sr-90 5 x 1o-f Comoosite Frequency Notation P Prior to batch release M Calendar month Q Calendar quarter W Calendar week
PALISADES NUCLEAR PLANT ODCM OFFSITE POSE CALCULATION MANUAL Appendix A Revision 7 Page 28 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 {TAC NO 75060)
Table D-1 (Cont'd) TABLE NOTATION aThe LLD is defined, in Table E-3, Note C. bA batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. cThe principal gamma emitters for which the LLD specification applies exclusively are 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 considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.
*LLD - 5E-06 because of low gamma yields.
dA composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. eA continuous release is the discharge of liquid wastes of a nondiscrete volume; eg, from a volume of a system that has an input flow during the continuous release. fTo be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in a series of aliquots of constant volume collected at regular time intervals and combined to form a single sample. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 29 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) H. Liquid Effluent Dose
- 1. Requirement:
The dose or dose commitment to a Member of the Public from radioactive materials in liquid effluents released from each reactor unit to Unrestricted Areas shall be limited:
- a. During any calendar quarter to less than or equal to 1 . 5 mrems to the total body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 1 0 mrems to any organ ..
- 2. Action:
- With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will
.be in compliance with the above limits. This Special Report shall also include the results of radiological analyses of the drinking water source.
- 3. Surveillance Requirements:
Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days.
\ -
PALISADES NU.CLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 30 of 61
.f TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases:
This requirement is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I, 1 OCFR Part
- 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV .A of Appendix I to assure that the releases of radioactive material in liquid effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." Also, for freshwater sites with drinking water supplies that can be potentially affected by Plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR Part 141 . The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.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 equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculatign of Annual Doses to Man From Routine Releases of ReactoVEffluerits*for the Purpose of Evaluating Compliance with 10CFR 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 .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 31 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER I.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Total Dose
- 1. Requirement:
The annual (calendar year) dose or dose commitment to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
- 2. Action:
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of 111.C.1.a, 111.C.1.b, 111.D.1 .a, 111.D.1.b, 111.H.1 .a, or 111.H.1 .b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of 111.1.1 have been exceeded. If such is the case, prepare and submit to the NRC within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 1 OCFR Part 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR Part 1 90 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR Part 1 90. Submittal of the report is considered a timely request and a variance is granted until staff action on the request is complete.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 32 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 3.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Surveillance Requirements:
- a. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with 111.C.1, 111.D.1 and 111.H. 1 and in accordance with the methodology and parameters in the ODCM.
- b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Action 1.2 above .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 33 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 4.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Bases: This requirement is provided to meet the dose limitations of 40CFR Part 1 90 that have been incorporated into 1 OCFR Part 20 by 46 FR 18525. It also requires the preparation and submittal of a Special Report whenever the calculated doses from Plant generated radioactive effluents and direct radiation exceed .25 mrems to the total body or any organ, except for thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a Member of the Public will exceed the dose limits of 40CFR Part 1 90 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a Member of the Public to within the 40CFR Part 1 90 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the Member of the Public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any Member of the Public is estimated to exceed the requirements of 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR Part 1 90 have not already been corrected), in accordance with the provisions of 40CFR Part 190.11 and 1 OCFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 1 90 and does not apply in any way to the other requirements for dose limitation of 1 OCFR Part 20. An individual is not considered a Member of the Public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 34 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER J.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Radiological Environmental Monitoring
- 1. Requirement:
The radiological environmental monitoring program shall be conducted as specified in Table E-1.
- 2. Action:
- a. With the radiological environmental monitoring program not being conducted as specified in Table E-1, prepare and submit to the NRC, in the Annual Radiological Environmental Operating Report a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of Plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table E-2 when averaged over any calendar quarter, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents.
.~ *-~~: When more than one of the radionuclides in Table E-2
*are detected in the sampling medium, this report shall be submitted if:
Concentration ( 1 ) + Concentration (2) + .... 2_ 1.0 Reporting Level ( 1) Reporting Level (2) When radionuclides other than those in Table E-2 are detected and are the result of Plant effluents, this report shall be submitted if the potential annual dose to a Member of the Public is equal to or greater than the calendar year limits of 111.C.1, 111.D.1, and 111.H.1. This report is not required if the measured level of
- radioactivity was not the result of Plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 35 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
The specific locations from which samples were unavailable may then be deleted from the monitoring program. Identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radiological Environmental Report.
- 3. Surveillance Requirements:
- a. The radiological environmental monitoring samples shall be collected pursuant to Table E-1 and shall be analyzed pursuant to the requirements of Table E-1 and the detection capabilities required by Table E-3.
- b. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 overland meteorological sectors of the nearest milk animal, the nearest resid~ce and ~he nearest garden of greater than 50 m (500 ft ) producing broad leaf vegetation.
Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. For broad leaf vegetation sampling, Table E-1, item 4c, shall be followed, including analysis of control samples.
- c. The land use census shall be conducted during the growing season at least once per 1 2 months using*
that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report and shall be included in a revision of the ODCM for use in the following calendar year.
PALISADES NUCLEAR PLANT ODCM OFFSITE POSE CALCULATION MANUAL Appendix A Revision 7 Page 36 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- d. Analyses shall be performed on radioactive materials
*~--
supplied as part of an lntedaboratory Comparison Program that has been approved by the NRC.
- e. A summary of the results obtained as part of the above required lnterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.
- f. The environmental air samplers shall be operationally checked monthly and airflow verified annually.
- 4. Bases:
- a. Monitoring Program The radiological environmental monitoring program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential. radiation exposures of Members of the Public resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and thereby 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. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection {LLDs). The LLDs required by Table E-3 are considered optimum for routine environmental measurements in industrial laboratories.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 37 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-92 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-15 (June 1975).
- b. Land Use Census:
This requirement is provided to ensure that 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 results of this census. The best information from the door-to-door survey, from aerial survey or from
- consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.8.3 of Appendix I to 1 OCFR Part 50.
R~tricting the census to gardens of greater than 40 m provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity ( 1 6 kg/yr) of leafy vegetables assumed in Regulatory Guide 1 . 1 09 for consumption by a child. To determine this minimum garden size, the following assumptions were made: ( 1) 20% of the garden was used for growing broad leaf vegetation (ie, similar to lettuce ~md cabbage), and (2) a vegetation yield of 2 kg/m .
PALISADES NUCLEAR PLANT ODCM OFFSITE POSE CALCULATION MANUAL Appendix A Revision 7 Page 38 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- c. lnterlaboratory Comparison Program:
The requirement for participation in an approved lnterlaboratory 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 valid for the purposes of Section IV.B.2 of Appendix I to 1 OCFR Part 50.
LEAR PLANT LATION MANUAL ODCIV., Appen Revision Page 39 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-1 Radiological Environmental Monitoring Program Exposure Pathway Number of Representative Sampling and Type of Frequency a and/or Sample Samples and Sample Locations Collection Frequency of Analysis
- 1. DIRECT RADIATIONb 21 routine monitoring stations either with two or Quarterly Gamma dose quarterly more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
An inner ring of stations, one in each overland meteorological sector (9) in the general area of the Site Boundary. An outer ring of stations, one in each overland meteorological sector (9) within the 1 2 km range from the site. The balance of the stations (3) to be placed to serve as control stations.
PALISADES LEAR PLANT ODCM OFFSITE DOSE LATION MANUAL AppenA Revisio. Page 40 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Exposure Pathway Number of Representative Sampling and Type of Frequency a and/or Sample Samples and Sample Locations Collection Frequency of Analysis
- 2. AIRBORNE Radioiodine and Samples from 5 locations. Continuous sample Radioiodine Canister:
Particulates operation with sample 1-131 analysis weekly for 3 samples from within 6 km of the Site Boundary collection weekly or more each filter change. in different sectors (2.4 km-SSW, 5.6 km-ESE, frequently if required by and 1.6 km-NI. dust loading. Particulate Sam(;!ler: Gross beta radioactivity 1 sample from the vicinity of a community having analysi~ following filter the highest calculated annual average ground level change . Gamma isotopic 9 D/Q (Covert-5.6 km-SE). analysis if !!oss beta
> 1.0 pCi/m .
1 sample from a control location in the least prevalent wind direction c (Grand Rapids 89 km-NNE).
- 3. WATERBORNE
- a. Lake (surface) Plant lake water inlet. Composite sample over Gross beta I> 10 pCi/I 1-month period . requires gamma) and tritium monthly.
- b. Well (drinking) Samples from Plant, State Park, and Covert Monthly - grab sample. Gross beta ( > 10 pCi/I Township Park wells. requires gamma) and tritium monthly.
- c. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample over Gross beta ( > 10 pCi/I 1-month period . requires gamma) and tritium monthly.
9
- d. Sediment from 1 sample from between north boundary and Van Semiannually Gamma isotopic analysis shoreline Buren State Park beach. semiannually.
ODCIV'- Appen Revision Page 41 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Exposure Pathway Number of Representative Sampling and Type of Frequency 8 and/or Sample Samples and Sample Locations Collection Frequency of Analysis
- 4. INGESTION
- a. Milk Samples from milking animals in 3 locations Monthly Gamma isotopic e and 1-131 between 5-13 km distance. analysis monthly.
1 sample from milking animals at a control location, 15-30 km distance.
- b. Fish and Sample 2 species of commercially and/or Sample in season or Gamma isotopic analysise on Invertebrates recreationally important species in vicinity of Plant semiannually if they are edible portions.
discharge area. 1 sample of same species in areas not seasonal. not influence by Plant discharge. 1 sample each of two principal fruit crops At time of harvest9 . Gamma isotopice and 1-1 31 (blueberries and apples). analysis. Samples of 3 different kinds of broad leaf Monthly when available. Gamma isotopic e and 1-131 vegetation grown nearest each of two different analysis. offsite locations of highest predicted annual average ground level D/Q if milk sample is not performed. (SE or SSE sectors near site). 1 sample of each of the similar broad leaf Monthly when available. Gamma Isotopic" and 1-131 vegetation grown 1 5-30 km distance in the least analysis. prevalent wind direction if milk sampling is not oerformed. ISSW or S sectors!.
PALISADES LEAR PLANT ODCMI FFSITE DOSE LATION MANUAL Appen Revision Page 42 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-1 (Cont'd) Table Notation "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability. malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. bone or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors or phosphor readout zones in a packet are considered as two or more dosimeters. 0 The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. dAirborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
"Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. 'A composite sample is one in which the quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in which the method of sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composites which meet this criteria are acceptable).
11 1f harvest occurs more than once a year, sampling shall be performed during each discrete harvest.
PALISADES LEAR PLANT ODCIV. OFFSITE DOSE LATION MANUAL Appen Revision 7 Page 43 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Reporting Levels Analysis Water Airborne Particulates Fish Milk Food Products 3 (pCill) or Gases (pCi/ml ) (pCi/kg, Wet) (pCill) (pCi/kg, Wet) 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 2 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 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.
PALISADES LEAR PLANT ODCMA OFFSITE DOSE LATION MANUAL Appen9 Revision 7 Page 44 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 8 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)bc Water Airborne Particulates Fish Milk Food Products Sediment Analysis (pCi/I) or Gases (pCi/m 31 (pCi/kg, Wet) (pCi/I} (pCi/kg, Wet) (pCi/kg, Dry) Gross Beta 4 0.01 H-3 2,000* Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1d 0.07 1 60 Cs-134 15 0.05 130 15 80 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15
- If no drinking water pathway exists, a value of 3,000 pCi/I may be used.
PALISADE~ LEAR PLANT OFFSITE DOSE LATION MANUAL Appe Revision Page 45 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 (Cont'd) TABLE NOTATION
- This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.
bRequired detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. cThe LLD is defined 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 = 4.66. b E
- V
- 2.22
- Y
- Exp (-Mt)
Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume. sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute. Eis the counting efficiency, as counts per disintegration. Vis 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. A is the radioactive decay constant for the particular radionuclide. bot for 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 bot should be used in the calculation.
CLEAR PLANT LATION MANUAL ODC~ Appe Revision Page 46 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 (Cont'd) Table Notation 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 "a posteriori" (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, unavoidable 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 Ra~iological Environmental Operating Report. dLLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 47 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER K.
NRC GENERIC LETTER 89-01 (TAC NO 75060) SIRW or Temporary Liquid Storage Tank
- 1. Requirement:
The concentration of radioactive material contained in the SIRW tank or any unprotected outside temporary tank* shall be limited such that the mixture radionuclides do not exceed 1,000 times the effluent concentration (EC) as listed in 1 OCFR Part 20, Appendix B, Table 2, Column 2. Ca + .C.b *** + Ci = < 1000 ECa ECb ECi
- 2. Action:
With the quantity of radioactive material in any of the above listed tanks exceeding the above concentration, immediately
- suspend all additions of radioactive material to the tank, within 48 hours reduce the tank contents to .within the limit, and describe the events leading to this condition in the next Radiological Effluent Release Report.
- 3. Surveillance Requirement:
The concentration of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. A calculational methodology performed prior to the material being transferred may be used to show compliance with the requirement of this section if a representative sample cannot be obtained at least once per seven days. A representative sample of the radioactive material to be added to the SIRW or Temporary Liquid Storage Tank shall be analyzed and a calculation performed to show compliance with the 1 000 EC limit.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 48 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases:
This requirement will provide reasonable assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an Unrestricted Area. (The dilution between Palisades and the South Haven drinking water supply has been established as 1000).
*Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
NOTE: The limit for the SIRW Tank may be exceeded for operational flexability if the condWons of this section are met. L. Surveillance Reguirement Time Intervals
- 1. Requirement:
Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
- 2. Action:
Failure to perform a Surveillance Requirement within the allowed surveillance interval shall constitute noncompliance with the operability requirements. The time limits of the action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The action requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allowed outage time limits of the action requirements are
- less than 24 hours. Surveillance Requirements do not have to be performed on inoperable equipment.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 49 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 3.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Surveillance Requirements: The applicable surveillance interval frequencies are specified in Tables A-2 and C-2. The applicable sampling and/or analysis frequencies are specified in Tables A-1, B-1, C-1, D-1, and E-1 . Extendable surveillance requirements are limited to channel checks, source checks, channel calibrations, channel functional checks, sampling frequencies and/or analysis frequencies.
- 4. Bases:
The maximum allowable extension for a surveillance interval is consistent with the surveillance requirements specified in the Technical Specifications, Section 4.0. Until relocated in the ODCM, all of the effluent surveillances were subject to these same requirements .
- M. Sealed Source Contamination
- 1. Requirement:
Each sealed source containing radioactive material either in excess of 1 00 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be
.free of greater than or equal to 0.005 microcuries of removable contamination.
- 2. Action:
- a. With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:
(1) Decontaminate and repair the sealed source, or (2) Dispose of the sealed source in accordance with applicable regulations.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 50 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- b. A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.
- 3. Surveillance Requirements:
- a. Each category of sealed .sources as described in the requirement with a half-life greater than 30 days (excluding Hydrogen-3), and in any other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed 6 months.
- b. The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
- c. The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.
- d. The periodic leak test does not apply to sealed sources that are stored and not being used. These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous 6 months.
Sealed sources which are continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
- e. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 51 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 4.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Bases: The_requirement, actions, and surveillance requirements are the same as contained in the Technical Specification 6.21 prior to relocation to the ODCM and will provide assurance that sealed sources are tested to demonstrate that source integrity is being maintained. IV. REPORTING REQUIREMENTS A. Radiological Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with 1 OCFR 50.36a by March 31 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be ( 1 ) consistent with the objectives
- outlined in the ODCM and Process Control Program and (2) in conformance with 1 OCFR 50.36a and Section IV.B ..1 of Appendix I to 1 OCFR 50.
The report shall include an estimate of the uncertainty associated with the measurement of radioactive effluents. This error term is included to provide an estimate of the uncertainty and is nQ1 to be considered the absolute error associated with the measurements or to be used in determining compliance with these requirements. These estimates will be based on a statistical analysis of a series of sample results (weighed appropriately for counting statistics) taken once a year from a minimum of one typical gaseous waste tank and from a minimum of one typical liquid waste tank. For noble gases released to the atmosphere from other than the waste gas system the error term will be estimated (and weight-averaged with the waste gas tank error) based on a statistical analysis of a series of sample results taken once a year (or the stack gas monitor counting statistics taken over one release per year) from each source contributing more than 1 0% of the total annual release .
- The error term for iodine and particulates released to the atmosphere will be based on the counting statistics for one stack gas sample taken during the year.
- PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 52 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
The report shall include an estimate of the lower level of detection (in µCi/ml) if the unidentified portion of the release exceeds 10% of the total annual releases. This estimate of the lower level of detection will be made for those gamma emitting isotopes listed in Appendix B of Regulatory Guide 1 .21 (June 1974) and will be provided based on a typical background gamma spectrum. The report shall provide the following specific terms:
- 1. Supplemental Information
- a. Batch Releases:
The report should provide information relating to batch releases of liquid and gaseous effluents which are discharged to the environment. This information should include the number of releases, total time period for batch releases, and the maximum, mean, and minimum time period of release.
- b. Abnormal .Releases The number of abnormal releases of radioactive material to the environment should be reported. The total curies of radioactive materials released as a result of abnormal releases should be included.
- 2. Gaseous Effluents
- a. Gases (1) Total curies of fission and activation gases releases.
(2) Average release rates (µCi/s) of fission and activation gases for the quarterly periods covered by the report .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 53 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
(3) Percent of limit for releases of fission and activation gases. (4) Quarterly sums of total curies for each of the radionuclides determined to be released, based on analyses of fission and activation gases.
- b. Iodines
( 1) Total curies of each of the isotopes, lodine-1 31 , lodine-133 and lodine-1 35 determined to be released. (2) Average release rate (µCi/s) of lodine-131/133. (3) Percent of Hmit for lodine-131 /1 33.
- c. Particulates (1) Total curies of radioactive material in particulate form with half-lives greater than 8 days determined to be released.
(2) Average release rate (µCi/s) of radioactive material in particulate form with half-lives greater than 8 days. (3)
- Percent of limit for radioactive material in particulate form with half-lives greater than 8 days.
(4) Total curies for each of the radionuclides in particulate form determined to be released based on analyses performed. (5) Total curies of gross alpha radioactivity determined to be released.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 54 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- d. Tritium
( 1) Total curies of tritium determined to be released in gaseous effluents. (2) Average release rate (µCi/s) of tritium. (3) Percent of applicable limits for tritium.
- 3. Liquid Effluents
- a. Mixed Fission and Activation Products (1) Total curies of radioactive material determined to be released in liquid effluents (not including tritium, dissolved and/or entrained gases, and alpha-emitting material).
(2) Average concentrations (µCi/ml) of mixed fission and activation products released to unrestricted areas, averaged over the quarterly periods covered by the report. (3) Percent of applicable limit of average concentrations released to unrestricted areas. (4) Quarterly sums of total curies for each of the radionuclides determined to be released in liquid effluents based on analyses performed.
- b. Tritium (1) Total curies of tritium determined to be released in liquid effluents.
(2) Average concentrations (µCi/ml) of tritium released in liquid effluents to unrestricted areas, averaged over the quarterly periods covered by the report. (3) Percent of applicable limit of average concentrations released to unrestricted areas.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 55 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- c. Dissolved and/or Entrained Gases
( 1) Total curies of gaseous radioactive material determined to be released in liquid effluents. (2) Average concentrations (µCi/ml) of dissolved and/or entrained gaseous radioactive material released to unrestricted areas, averaged over the quarterly periods covered by the report. (3) Percent of applicable limit of average concentrations released to unrestricted areas. (4) Total curies for each of the radionuclides determined to be released as dissolved and/or entrained gases in liquid effluents.
- d. Alpha Radioactivity Total curies of gross alpha-emitting material determined to be released in liquid effluents.
- e. Volumes (1) Total measured volume (liters), prior to dilution, of liquid effluent released.
(2)
- Total determined volume, in liters, of dilution water used during the period of the report .
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 56 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 4.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Radiological Impact on Man: The Radioactive Effluent Release Report shall include potential doses to individuals and populations calculated using measured effluent and averaged meteorological data in accordance with the methodologies in the ODCM.
- a. Total body and significant organ doses (greater than 1 millirem to individuals in unrestricted areas from receiving water-related exposure pathways.
- b. The maximum offsite air doses (greater than 1 millirad) due to beta and gamma radiation at locations near ground level from gaseous effluents.
- c. Organ doses (greater than 1 millirem) to individuals in unrestricted areas from radioactive iodine and radioactive material in particulate form from the major pathways of exposure.
- d. Total body doses (greater than 1 manrem) to the population and average doses (greater than 1 millirem) to individuals in the population from receiving water-related pathways to a distance of 50 miles from the site.
- e. Total body doses (greater than 1 manrem) to the population and average doses (greater than 1 millirem) to individuals in the population from gaseous effluents to a distance of 50 miles from the site.
- 5. ODCM Changes:
The Radiological Effluent Release Report shall include any changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to 111.J.3.c.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 57 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER B.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Radiological Environmental Operating Report The Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in; (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to 1 OCFR50. The Annual Radiological Environmental Operating Reports shall include summaries, interpretation and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the Plant operation on the environment. The reports shall also include the results of land use census pursuant to 111.J.3.c. - The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Table F-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following; a summary description of the radiological environmental monitoring program, including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by 111.J.3.c and results of the lnterlaboratory Comparison Program required by 111.J.3.e.
PALISAPES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 58 of 61
- TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER C.
NRC GENERIC LETTER 89-01 (TAC NO 75060) Nonroutine Reports A report shall be submitted to the NRC in the event that; 1) the Radiological Environmental Monitoring Programs are not substantially conducted as described in Section 111.J, or 2) an unusual or important event occurs from Plant operation that causes a significant environmental impact or affects a potential environmental impact. Reports shall be submitted within 30 days.
. I
PALISADEf LEAR PLANT ODCIV. OFFSITE DOSE LATION MANUAL Appe Revision 7 Page 59 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table F-1 Environmental Radiological Monitoring Program Summary Name of Facility Docket No Location of Facility Reporting Period (County, State) Type/Total Lower Limit All Indicator Medium or Pathway b Control Loc<gions Number of Number of of Locationg Name Mean ll} Sampled a Mean If~ REPORTABLE Analyses Detection Distance & Direction Range (Unit of Measure) - . *rl II I n \ Mean ll} a .... ,:, ..
- Range OCCURRENCES Air Particuftes Gross B 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/104)- 1 (pCi/m l (200/312) 5 miles 340° (0.08-2.0) (0.05-1.40) y-Spec 32 (0.05-2.0)
Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LLD 4 (0.03-0.131 2.5 miles 160° (0.03-0.13) Ba-140 0.003 0.03 (2/24) Podunk 0.05 12/4) 0.02 (1/8) 1 (0.01-0.081 4 miles 270° (0.01-0.08) Sr-89 40 0.002 <LLD -- -- <LLD 0 Sr-90 40 0.0003 <LLD -- -- <LLD 0 Fish y-Spec 8 pCi/kg (dry weight) Cs-137 80 <LLD -- <LLD 90 (1/41 0 Cs-134 80 <LLD -- <LLD <LLD 0 Co-60 80 120 (3/41 River Mile 35 See <LLD 0 190-200! Podunk River Column 4 Nominal Lower L1m1t of Detection (LLD) as defined in table notation c of Table E-3. b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is indicated in parentheses (f). dNOTE: The example data are provided for illustrative purposes only.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 60 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS A. Licensee Modifications Licensee initiated major modifications to the radioactive liquid and gaseous waste systems.
- 1. Shall be reported to the NRC pursuant to 1 OCFR 50.59. The discussion of each modification shall contain:
- a. A summary of the evaluation that led to the determination that the modification could be made in accordance with 1 OCFR Part 50.59.
- b. A description of the equipment, components and processes involved, and the interfaces with other Plant systems.
- c. Documentation of the fact that the modification was reviewed and found acceptable by the PRC.
- 2. Shall become effective upon review and acceptance by the Plant General Manager.
B. Definition of Major Radwaste System Modification 1.
Purpose:
The purpose of this definition is to assure that this requirement will be satisfied under clearly identifiable circumstances, and with the objective that current radwaste system capabilities are not jeopardized.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 7 Page 61 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 2. Definition:
A major ra~waste system modification is a modification which would remove (either by bypassing for greater than 7 days or physical removal) or replace with less efficient equipment, any components of the radwaste system:
- a. Letdown filters or demineralizers.
- b. Vacuum degassifier (not applicable when the reactor is in cold shutdown and depressurized).
- c. Miscellaneous or clean waste evaporators.
- d. The present waste gas compressor/decay tank system .
- e.
f. g. Fuel Pool filters/demineralizers. Radwaste polishing demineralizers. Radwaste Solidification system. Improvements or additions to improve efficiency will not be considered major modifications unless a complete substitution of equipment or systems is made with equipment of unrelated design. Examples would be; 1) replacement of mechanical degassifier with steam, jet degassifier, 2) replacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and
- 4) change from deep bead resins to Powdex, etc.}}