ML021000099
| ML021000099 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/26/2002 |
| From: | Lahti L Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML021000099 (142) | |
Text
Committed to Nuclear (xellene Palisades Nuclear Plant Operated by Nuclear Management Company, LLC March 26, 2002 10 CFR 50.36a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 DOCKET 50-255 - LICENSE DPR PALISADES PLANT 2001 ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT Enclosed is the 2001 Annual Radioactive Effluent Release and Waste Disposal Report for the Palisades Plant which is submitted in accordance with 10 CFR 50.36a(a)(2) and Palisades Technical Specification 5.6.3.
This report provides a summary of the quantities of radioactive liquid and gaseous effluent releases and solid radioactive waste processed during the period of January 1,2001, through December 31, 2001.
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
Laurie A. Lahti Manager, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Enclosure 27780 Blue Star Memorial Highway 0 Covert, MI 49043 Telephone: 616.764.2000
ENCLOSURE NUCLEAR MANAGEMENT COMPANY, LLC PALISADES PLANT DOCKET 50-255 2001 ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT March 2002 4 pages follow
PALISADES NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY - DECEMBER 2001 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, 2001 through December 31, 2001. The report is required by 10 CFR 50.36a(a)(2) and Plant Technical Specification 5.6.3. The report format is detailed in the Offsite Dose Calculation Manual (ODCM), Appendix A.
Plant Operating History Palisades was taken off line on March 30, 2001 for a refueling outage. The Plant returned to service on May 10, 2001, and remained in service until June 20, 2001, when it was taken off line to repair Primary Coolant System (PCS) leakage. The Plant remained off line for the remainder of 2001 to replace control rod drive mechanism seal housings.
- 1. 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.
D. Results of the 2001 Radiochemistry Cross Check Program with Analytics are shown in Attachment 6. All results were in agreement for all isotopes on all three detectors. There were a total of 271 measurements made.
E. Radioactive Effluent Monitoring Instrumentation No radioactive effluent monitoring instrument channels were inoperable for more than 30 days during this reporting period.
1
- 2. Gaseous Effluents Attachment 2 lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 3.74E-05% of the total release.
Gaseous effluents (noble gasses) and resultant beta and gamma doses released during 2001 were 10% lower than the previous year. This is attributed to the extended outage Palisades experienced in 2001. Organ dose (long lived particulates and iodine) was 50% higher than in 2000, due to the release from the containment structure Integrated Leak Rate Test (ILRT) performed during the refueling outage.
- 3. Liquid Effluents Attachment 3 lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 3.51 E-05% of the total release.
No liquid batch releases occurred during the 3rd quarter of 2001, therefore, the total release (not including tritium) was zero. Since only tritium was released in the second quarter, the resultant calculated organ dose was the same value as calculated for the whole body dose.
Overall dose from liquid effluents released during 2001 was about half of that released in 2000, even though liquid release volumes were nearly identical. This is a function of total Curies released. The fission and activation Curies released in 2001 were one-third that of 2000. Release tanks continue to be recirculated through the demineralizers prior to release which reduces activity concentration. Total dilution flow in the second half of 2001 was lower than 2000 due to the extended plant outage.
- 4. Estimate of Uncertainty Both the Gaseous and Liquid Summation of Release data sheets include an estimate of the uncertainty associated with the measurement of radioactive effluents. These estimates are based on a statistical analysis of a series of sample results as described in the ODCM, Appendix A. These results are listed in the "Est Total Error %" columns on the Gaseous and Liquid Summation Report.
- 5. Solid Waste Attachment 4 summarizes all solid radwaste classification, sources, volume shipped, curie and nuclide content. Radwaste shipments were made either to Barnwell Waste Management Facility in Barnwell, South Carolina or to Envirocare of Utah, Inc. The 2001 2
waste volume was slightly higher than 2000, however, the Curies shipped in 2001 were a fraction of that of the previous year. The reduction in Curies shipped was due to no shipments of irradiated hardware being made in 2001.
- 6. 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 maximum total body dose to an individual in unrestricted water-related exposure pathways was:
First Quarter 3.81 E-05 millirem (adult)
Second Quarter 2.55 E-04 millirem (adult)
Third Quarter 3.35 E-08 millirem (adult)
Fourth Quarter- 3.89 E-04 millirem (adult).
The maximum organ doses were:
First Quarter 3.70 E-05 millirem (adult GI tract)
Second Quarter 2.15 E-04 millirem (adult GI tract)
Third Quarter 3.35 E-08 millirem (adult)
Fourth Quarter- 4.80 E-04 millirem (adult liver)
B. The offsite air doses at the site boundary (0.48 mi SSE) due to noble gases were:
First Quarter 2.13 E-04 millirad beta and 7.25 E-05 millirad gamma Second Quarter 2.14 E-04 millirad beta and 7.82 E-05 millirad gamma Third Quarter 1.56 E-06 millirad beta and 5.26 E-07 millirad gamma Fourth Quarter - 0.00 millirad beta and 0.00 millirad gamma The maximum noble gas offsite air dose to the nearest residence (0.50 mi S) for beta and gamma occurred during the second quarter, being 1.39 E-04 millirads beta and 5.10 E-05 millirads for gamma. There were no noble gasses released during the fourth quarter.
C. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases were:
First Quarter 5.64 E-03 millirem (child thyroid)
Second Quarter 1.62 E-02 millirem (child thyroid)
Third Quarter 5.47 E-03 millirem (child thyroid Fourth Quarter - 4.98 E-03 millirem (child GI tract) 3
D. 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 4.28 E-04 person-Rem and 3.69 E-07 millirem Second Quarter 2.54 E-03 person-Rem and 2.19 E-06 millirem Third Quarter 3.84 E-07 person-Rem and 3.31 E-10 millirem Fourth Quarter - 2.97 E-03 person-Rem and 2.56 E-06 millirem E. 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 1.62 E-02 person-Rem and 1.40 E-05 millirem Second Quarter 5.10 E-02 person-Rem and 4.40 E-05 millirem Third Quarter 1.81 E-02 person-Rem and 1.56 E-05 millirem Fourth Quarter - 1.68 E-02 person-Rem and 1.45 E-05 millirem.
There was no revision to the Process Control Program in 2001.
Attachment 7 contains the ODCM, Revision 16, along with the safety evaluation per the requirements of Technical Specification 6.5.1 .c.3.
Revision 16 to the ODCM involved changes as a result of use of the 2000 Land Use Survey.
The Land Use Survey is utilized to ensure that the impact of effluent dose is accurate. These changes are listed below.
- 1) Update of Table 1.4, 2000 Palisades Land Use Census (rev 14)
- 2) Update of Table 1.4a, 2000 Palisades Land Use Census - Critical Receptor Items
- 3) Update of Table 1.9, 2001 Palisades Gaseous Design - Objective Annual Quantities 4
ATTACHMENT 1 NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES January - December 2001 1 page follows
TABLE HP 10.5-1 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT BATCH RELEASES January 1, 2001 to December 31, 2001 A. GASEOUS Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Number of Releases 5 9 5 4 Total Release Time Minutes 497 1127 495 391 Maximum Release Time Minutes 150 185 135 180 Average Release Time Minutes 99 125 99 98 Minimum Release Time Minutes 67 82 67 58 B. LIQUID Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Number of Releases 1 2 0 1 Total Release Time Minutes 347 1156 N/A 1947 Maximum Release Time Minutes 347 594 N/A 1947 Average Release Time Minutes 347 578 N/A 1947 Minimum Release Time Minutes 347 562 N/A 1947 ATTACHMENT 2 NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January - December 2001 3 pages follow
TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January 1, 2001 to December 31, 2001 Est Total A. FISSION AND ACTIVATION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Error %
- 1. Total release Ci 3.01E+00 2.92E+00 2.21E-02 0.00
- 2. Average release rate for 5.6 period pCi/sec 3.88E-01 3.72E-01 2.78E-03 0.00
- 3. Percent of annual avg EC % 1.67E-04 1.84E-04 1.16E-06 0.00 B. IODINES
- 1. Total Iodine
- Ci 5.52E-04 3.85E-04 5.69E-05 0.00
- 2. Average release rate for 10.3 period pCi/sec 7.09E-05 4.90E-05 7.16E-06 0.00
- 3. Percent of annual avg EC % 3.93E-65 3.52E-05 7.62E-06 0.00 C. PARTICULATES
- 1. Particulates with half-life
> 8 days Ci 2.80E-06 2.36E-05 7.72E-06 7.09E-06
- 2. Average release rate for 18.0 period pCi/sec 3.59E-07 3.01E-06 9.71E-07 8.92E-07
- 3. Percent of annual avg EC % 8.47E-06 1.92E-05 2.38E-05 2.12E-05
- 4. Gross alpha radioactivity Ci 5.17E-07 2.01E-06 3.72E-06 2.07E-06 D. TRITIUM
- 1. Total Release Ci 4.81E+00 1.53E+01 5.27E+00 4.93E+00
- 2. Average release rate for period pCi/sec 6.18E-01 1.95E+00 6.63E-01 6.20E-01
- 3. Percent of annual avg EC % 1.31E-03 4.15E-03 1.41E-03 1.32E-03 E.
- 1. Beta Airdose at Site Boundary Due to Noble Gases (ODCM App A III.C) mrads 2.13E-04 2.14E-04 1.56E-06 0.00
- 2. Percent limit % 2.13E-03 2.14E-03 1.56E-05 0.00
- 3. Gamma Airdose at Site Boundary Due to Noble Gases (ODCM App A Ill.C) mrads 7.25E-05 7.82E-05 5.26E-07 0.00
- 4. Percent limit % 1.45E-03 1.56E-03 1.05E-05 0.00 F.
- 1. Maximum Organ Dose to Public Based on Critical Receptors (ODCM App A III.D) mrem 5.64E-03 1.62E-02 5.47E-03 4.98E-03
- 2. Percent of limit % 7.52E-02 2.16E-01 7.29E-02 6.64E-02
- NOTE: Data is reported for 1-131 and 1-133 only.
TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS January 1, 2001 to December 31, 2001
- 1. FISSION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Argon-41 Ci 7.33E-04 <LLD <LLD <LLD Krypton-85 Ci <LLD <LLD <LLD <LLD Krypton-85m Ci <LLD <LLD <LLD <LLD Krypton-87 Ci 2.31E-04 <LLD <LLD <LLD Krypton-88 Ci <LLD <LLD <LLD <LLD Xenon-131m Ci 4.29E-03 6.11E-03 <LLD <LLD Xenon-133 Ci 3.OOE+O0 2.83E+00 2.21E-02 <LLD Xenon-133m Ci <LLD <LLD <LLD <LLD Xenon-135 Ci 2.21E-03 8.53E-02 <LLD <LLD Xenon-135m Ci 4.44E-03 9.41E-04 <LLD <LLD Xenon-138 Ci <LLD <LLD <LLD <LLD Total for Period Ci 3.01E+00 2.92E+00 2.21E-02 <LLD
- 2. IODINES Iodine-131 Ci 2.22E-04 2.28E-04 5.69E-05 <LLD Iodine-132 Ci <LLD 1.OOE-03 <LLD <LLD Iodine-133 Ci 3.30E-04 1.57E-04 <LLD <LLD Iodine-134 Ci <LLD <LLD <LLD <LLD Iodine-135 Ci <LLD <LLD <LLD <LLD Total for Period Ci 5.52E-04 1.39E-03 5.69E-05 <LLD TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT
- 3. PARTICULATES* Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Chromium-51 Ci <LLD 1.80E-06 <LLD <LLD Cobalt-58 Ci <LLD 1.47E-05 <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD 4.16E-07 <LLD 1.82E-06 Zinc-65 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 9.75E-07 8.25E-07 9.95E-07 7.95E-07 Strontium-90 Ci 4.80E-07 5.15E-07 4.95E-07 4.65E-07 Niobium-95 Ci <LLD 3.92E-07 <LLD <LLD Zirconium-95 Ci <LLD 5.57E-07 <LLD <LLD Ruthenium-103 Ci <LLD 1.29E-07 <LLD <LLD Cesium-137 Ci <LLD 7.92E-07 1.51E-06 <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD Net unidentified beta Ci 1.34E-06 3.51E-06 4.72E-06 4.01E-06 Total 2.80E-06 2.36E-05 7.72E-06 7.09E-06
- Particulates with half-lives > 8 days.
ATTACHMENT 3 NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF RELEASES January - December 2001 2 pages follow
TABLE HP 10.5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January 1, 2001 to December 31, 2001 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 2.81E-06 2.45E-04 0.000 3.68E-05
- 2. Average release rate for 26.0 period pCi/mQ 7.35E-14 9.68E-12 N/A 3.79E-12
- 3. Percent of EC % 1.29E-05 6.02E-04 N/A 3.91E-04 B. TRITIUM
- 1. Total Release Ci 2.73E+01 9.87E+01 6.80E-03 3.70E+01
- 2. Average diluted concentration during period pCi/me 7.15E-07 3.90E-06 6.36E-10 3.82E-06 4.01
- 3. Percent of EC % 7.15E-02 3.90E-01 6.36E-05 3.82E-01 C. DISSOLVED AND ENTRAINED GASES
- 1. Total Release Ci 0.000 0.000 0.000 0.000
- 2. Average diluted concentration during period pCi/mQ N/A N/A N/A N/A N/A
- 3. Percent of EC % N/A N/A N/A N/A D. GROSS ALPHA RADIOACTIVITY (Total Release) Ci 7.45E-08 2.13E-06 0.000 1.65E-07 E. VOLUME OF WASTE RELEASED (Prior to Dilution) Liters 1.02E+05 3.78E+05 0.000 1.70E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 3.82E+10 2.53E+10 1.07E+10 9.68E+09 G. MAXIMUM DOSE COMMITMENT WHOLEBODY mrem 3.81E-05 2.55E-04 3.35E-08 3.89E-04 Percent of ODCM App A III.H limit 2.54E-03 1.70E-02 2.23E-06 2.59E-02 H. MAXIMUM DOSE COMMITMENT ORGAN mrem 3.70E-05 2.15E-04 3.35E-08 4.80E-04 Percent of ODCM App A III.H limit % 7.40E-04 4.30E-03 6.70E-07 9.60E-03 1-
TABLE 1-P 10.5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS January 1, 2001 to December 31, 2001
- 1. NUCLIDES RELEASED Units Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Manganese-54 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD 2.23E-05 <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD 3.44E-05 <LLD <LLD Zirconium-95 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 3.57E-07 1.02E-06 <LLD 5.44E-07 Strontium-90 Ci 2.45E-06 1.97E-06 <LLD 1.62E-06 Silver-110m Ci <LLD 1.28E-04 <LLD <LLD Iodine-131 Ci <LLD <LLD <LLD <LLD Cesium-134 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD <LLD 3.46E-05 Niobium-95 Ci <LLD <LLD <LLD <LLD Silver-110m Ci <LLD <LLD <LLD <LLD Antimony-125 Ci <LLD <LLD <LLD <LLD Net unidentified beta Ci <LLD 5.72E-05 <LLD <LLD Fission & Activation Product Total Ci 2.81E-06 2.45E-04 0.00 3.68E-05 Tritium Ci 2.73E+01 9.87E+01 6.80E-03 3.70E+01 Grand Total Ci 2.73E+01 9.87E+01 6.80E-03 3.70E+01 ATTACHMENT 4 NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE January - December 2001 1 page follows
SOLID WASTE January 1, 2001 To December 31, 2001 Waste Source of Solidification Container Volume *Tota I *Pri nci pal Class Waste Agent Type (cu ft) Curi es Radionuclides AS DAW N/A HIC 194.1 1.05 Co-60, Cs-137, Co-58, Cs-134, Mn-54, Fe-55, Nb-95, Ag-110m Zr-95, Sb- 125 Ni -63 B DAW N/A HIC 195.7 0.63 Same as above AU DAW N/A LSA 1638.8 0.47 Same as above AS Evap Bottoms N/A HIC 256.0 4.25 Co-60, Cs-137, Co-58, Cs-134, Mn-54, Fe-55, Zn-65, Sb-125 Ni -63, Ag-110m 2284.6 ft 3 TOTAL 6.40 Ci
- NOTE: Gamma isotopes are measured quantities; all other isotopes are estimated ATTACHMENT 5 NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS January - December 2001 1 page follows
I ,V-AIr, I IRAIOQ n Yl IC Il* 1,.TI,I Cl %1n iDA I ICA PC 9=9I II TlIl
-I Gaseous Effluents Nuclide LLD (uci/cc)*
Mn-54 1.36E-14 Co-58 2.33E-14 Fe-59 5.51E-14 Co-60 6.49E-14 Zn-65 6.36E-14 01-042-St Zr-95 3.02E-14 01 -040-G Mo-99 1.22E-13 1-131 2.80E-14 1-133 1.83E-14 Cs-134 2.15E-14 Cs-137 2.81E-14 Ce-141 2.02E-14 Ce-144 9.46E-14 Kr-87 1.78E-06 Kr-88 1.14E-06 Xe-1 33 6.75E-07 Xe-1 33m 1.93E-06 Xe-135 2.64E-07 Xe-138 3.44E-05 Liquid Effluents Nuclide LLD (uci/ml)**
Mn-54 1.30E-07 Fe-59 2.49E-07 Co-58 1.02E-07 Co-60 2.17E-07 Zn-65 2.1OE-07 Liquid Batch Release Mo-99 8.89E-07 01-005-R 1-131 9.05E-08 01-019-R Cs- 134 1.09E-07 Cs-137 1.34E-07 Ce-141 1.12E-07 Ce-144 3.59E-07
- From a typical Stack release analysis.
- From a typical Liquid release analysis.
ATTACHMENT 6 NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT RESULTS OF 2001 RADIOCHEMISTRY CROSS CHECK PROGRAM 15 pages follow
ANALYTICS 1380 Seaboard Industrial Blvd.
Atlanta, Georgia 30318, U.S.A, Phone (404) 352-8677 Fax (404) 352-2837 RESULTS OF RADIOCHEMISTRY CRo-SS CECK PROGRAM CONSUMERS POWER COMPANY PALISADES PLANT First Quarter 2001 Daniel M. MOnmgomery, QA Manager 4--
PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/Ca/mL mic0oCi/coimL ANALYTICS RESOLUTION COMPARISON A14016-66 Ce-141 3.22E-05 3.30E-05 0.98 20 AGREEMENT SOLID Cr-51 9.59E-05 9.64E-05 0.99 20 AGREEMENT DET. #1 Cs-134 2.26E-05 2.27E-05 1.00 20 AGREEMENT Cs-137 .80E-5 ...... 74-05 .. 1.04 20 AGREEMENT Co-58 I.14E-05 i.113E-05 1.01 20 AGREEMENT Mn-54 2.02E-05 1. 86E-05 1.09 20 AGREEMENT Fe-59 2.62E-05 2.44E-05 1.08 20 AGREEMENT Zn-65 3.57E-05 3.S0E-05 1.02 20 AGREEMENT Co-60 2.47E-05 2.53E-05 0.98 20 AGREEMENT A14016-66 Ce-141 3.28E-05 3.30E-05 1.00 20 AGREEMENT SOLID Cr-51 9.19E-05 9.64E-05 0.95 20 AGREEMENT DET.#2 Cs-134 2.17E-05 2.27E-05 0.96 20 AGREEMENT Cs-137 1.69E-05 1. 74E-05 0.97 20 AGREEMENT Co-58 1. 11E-05 1.13E-05 0.98 20 AGREEMENT Mn-54 1.84E-05 1.86E-05 0.99 20 AGREEMENT Fe-59 2.41E-05 2.44E-05 0.99 20 AGREEMENT Zn-65 3.39E-05 3.50E-05 0.97 20 AGREEMENT Co-60 2.45E-05 2.53E-05 0.97 20 AGREEM al AnI C-c ******************** ***************** ******************
SOLID **=
-+/-+/- u-o Cr-51 * .18 -0 9.65E-05 3.0E050.96 9.64E-05 20 AGREEMENT 1.00 20 AGREEMENT DET#3 Cs-134 2.25E-05 2.27E-05 0.99 20 AGREEMENT Cs-137 1.78E-05 1.74E-05 1.03 20 AGREEMENT Co-58 1.12E-05 1.13E-05 0.99 20 AGREEMENT Mn-54 ... I,97E-05 1. 86E-05 1.06 20 AGREEMENT Fe-59 2.59E-05 2.44E-05 1.06 20 AGREEMENT Zn-65 3.56E-05 3.50E-05 1.02 20 AGREEMENT Co-60 2.43E-05 2.53E-05 0.96 20 AGREEMENT
PALISADES ANALYTICS RATIO SAMPLE ANALYSIS VALUE microCi/cc/mýL VALUE mi cror-i/cc/mL PALISADES:
ANALY-TICS RESOLUTION COMPARISON A14017-66 Ce-141 3.10E-05 3.28E-0. 0.94 20 GAS Cr-51 9.12E-05 AGREEMENT 9.60E-05 0.95 20 DET. #1 Cs-134 AGREEMENT 2.06E-05 0.91 Q6E-5 20 AGREEMENT Cs-137 1.59E-05 1. 73E-05 0.92 20 AGREEMENT Co-58 1.12E-05 1.13E-05 0.99 20 AGREEMENT Mn-54 1.829-05 1.85E-05 0.98 20 AGREEMENT Fe-59 2.38E7Q5 2143E-5 0.98 20 AGREEMENT Zn-65 3 E35*05 3.489-05 0.96 20 ACREEMENT Co-60 2.38E-05 2.$2E97 5 0.95 20 AGREEMENT A14017-66 Ce-141 3.06E-05 3.28E.05 0.93 20 GAS Cr-51 AGREEMENT 9.10E-05 9.60E-05 0.95 DET. #2 Cs-134 20 AGREEMENT 2.05E-05 2.26E-05 0.91 Cs-137 20 AGREEMENT I.6A!-7 *3EX5..... 7 .93 20 AGREEMENT Co-58 1.11E-05 1.13E-05 0.98 20 AGREEMENT Mn-54 1.81E-05 1.85E-05 0.98 20 AGREEMENT Fe-59 2.43E-05 2.43E-05 1.00 20 AGREEMENT Zn-65 3.15E-05 3.48E-05 0.90 20 AGREEMENT Co-60 227E02.5-05 0.90 20 AGREEMENT A14017-66 Ce-141 2.97E-05 3.28E-05 0.90 20 GAS Cr-51 AGREEMENT 9.16E-05 9.60E-05 0.95 DET. #3 20 AGREEMENT Cs-134 2.12E-05 2.26E-05 0.94 20 AGREEMENT Cs-137 !.67E-05 1.73E-05 0.97 20 AGREEMENT Co-58 1.13E-05 1.13E-05 1.00 20 AGREEMENT Mn-54 1.83E-05 1.85E-05 0.99 20 AGREEMENT Fe-59 2.45E-05 2.43E-05 1.01 20 AGREEMENT Zn-65 3.31E-05 3.48E-05 0.95 20 AGREEMENT Co-60 2.40E-05 2.52E-05 0.95 20 AGREEMENT
- ** ** **-3 * **
- PALISADES ANALYTICS RATIO SAMPLE VALUE VALUE PALISADES:
ANALYSIS microCi/cc/mL microCi/cc/mL ANALYTICS RESOLUTION COMPARISON A14018-66 Ce-141 4-52E-04 4135E-04 1.04 20 SOLID Cr-51 AGREEMENT I,36S-03 1.21E-03 1.07 DET. #1 20 AGREEMENT Cs-134 2.84E-04 2.99E-04 0.95 20 AGREEMENT Cs-137 2.34E-04 2.29-0A
-..... 1.02 20 AGREEMENT Co-58 I.159E-04 1.49E-04 1.07 20 AGREEMENT Mn-54 2.66E-04 2.45E-04 1.08 20 AGREEMENT Fe-59 3.39.,04 3.21E-04 1.06 20 AGREEMENT Zn-65 4.90E-04 4.61.-04 1.06 20 AGREEMENT Co-60 3.34E- 0 4 3.33Z-04 20 AGREEMENT A14018-66 Ce-141 3.42t-04 4.35E-04 0.79 20 SOLID Cr-51 AGREEMENT 1.25E,03 1.27!E-03 0.98 DET. #2 Cs-134 2.77E-04 2.99E-04 20 AGREEMENT 0.93 20 AGREEMENT cs-137 2.24E-04 2.29E-04 0.98 20 AGREEMENT Co-58 1.51E-04 1.49E-04 1.01 20 AGREEMENT Mn-54 2.47E-04 2.45E-04 1.01 20 AGREEMENT Fe-59 3.08E-04 3.21E-04 0.96 20 AGREEMENT Zn-65 4.58E-04 4.61E-04 0.99 20 AGREEMENT Co-60 3 .0 .-04 333 4 B-. .E3b 20 AGREEMENT SOLID O-,&
R.. =4.2.0E-04 Cr-51 1.29E-03 4.35E-04 0.97 20 AGREEMENT 1 .27E-b3 1.01 20 DET. #3 Cs-134 2.93E.04 AGREEMENT 2;99E-04 0.98 20 AGREEMENT Cs-137 2.24Et-04 2.29E-04 0.98 20 AGREEMENT Co-58 1.57E-04 1.49E-04 1.05 20 AGREEMENT 2.54609-04 2:454-o4 1.06 Fe-59 3.3BE-04 20AGEMN 3.21E-04 1.05 20 Zn-65 4.'65E-04 AGREEMENT 4.61E-04 1.01 20 Co-60 AGREEMENT 3.22E-04 3.33E-04 0.97 20 AGREEMENT
PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/cc/mL micro.c/cc/mL ANALYTICS RESOLUTION COMPARISON A14019-66 Gross Beta 3.34E-03 3.62E-03 0.92 17 AGREEMENT LIQUID
- * * * **102764 DET. * * ** * * * * * * * * * * * * * * * * * * * * * *-* * **
A14019-66 Gross Beta 3,493k-03 3.62E-0 0.97 17 AGREEMENT LIQUID DET. 8428-01130 .
ANALYTICS 1380 Seaboard Industrial Blvd.
Atlanta, Georgia 30318- U.S.A.
Phone (404) 352-8677 Fax (404) 352-2837 RESULTS OF RADIOCHEMISTRY CROSS CHECK PROGRAM CONSUMERS POWER COMPANY PALISADES PLANT SECOND QUARTER 2001 Daniel M. Montgomery, QA Manager
)
PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON A144U4-66 Ce-141 4.70E-02 4.94E-02 0.95 20 AGREEMENT FILTER Cr-51 7.59E-02 7.71E-02 0.98 20 AGREEMENT DET. #1 Cs-134 1.81E-02 2.03E-02 0.89 20 AGREEMENT Cs-137 1.91E-02 1.79E-02 1.07 20 AGREEMENT Co-58 2.01E-02 1.98E-02 1.02 20 AGREEMENT Mn-54 2.54E-02 2.39E-02 1.06 20 AGREEMENT Fe-59 2.42E-02 2.18E-02 1.11 20 AGREEMENT Zn-65 3.14E-02 2.94E-02 1.07 20 AGREEMENT Co-60 2.OOE-02 2.01E-02 0.99 20 AGREEMENT A14404-66 Ce-141 4.88E-02 4.94E-02 0.99 20 AGREEMENT FILTER Cr-51 7.56E-02 7.71E-02 0.98 20 AGREEMENT DET. #2 Cs-134 1.88E-02 2.03E-02 0.93 20 AGREEMENT Cs-137 1.91E-02 1.79E-02 1.07 20 AGREEMENT Co-58 2.OOE-02 1.98E-02 1.01 20 AGREEMENT Mn-54 2.52E-02 2.39E-02 1.06 20 AGREEMENT Fe-59 2.26E-02 2.18E-02 1.04 20 AGREEMENT Zn-65 2.98E-02 2.94E-02 1.01 20 AGREEMENT Co-60 1.94E-02 2.01E-02 0.96 20 AGREEMENT
- d J m A m *
- A14404-66 Ce-141 4.74E-02 4.94E-02 0.96 20 AGREEMENT FILTER Cr-51 7.64E-02 7.71E-02 0.99 20 AGREEMENT DET. #3 Cs-134 1.90E-02 2.03E-02 0.94 20 AGREEMENT Cs-137 1.98E-02 1.79E-02 1.11 20 AGREEMENT Co-58 2.06E-02 1.98E-02 1.04 20 AGREEMENT Mn-54 2.60E-02 2.39E-02 1.09 20 AGREEMENT Fe-59 2.36E-02 2.18E-02 1.08 20 AGREEMENT Zn-65 3.11E-02 2.94E-02 1.06 20 AGREEMENT Co-60 2.04E-02 2.01E-02 1.01 20 AGREEMENT PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON A14405-66 Ce-141 4.70E-02 5.11E-02 0.92 20 AGREEMENT CARTRIDGE Cr-51 7.59E-02 7.97E-02 0.95 20 AGREEMENT DET. #1 Cs-134 1.81E-02 2.09E-02 0.86 20 AGREEMENT Cs-137 1.91E-02 1.85E-02 1.04 20 AGREEMENT Co-58 2.01E-02 2.04E-02 0.98 20 AGREEMENT Mn-54 2.54E-02 2.46E-02 1.03 20 AGREEMENT Fe-59 2.42E-02 2.25E-02 1.07 20 AGREEMENT Zn-65 3.14E-02 3.04E-02 1.03 20 AGREEMENT Co-60 2.OOE-02 2.08E-02 0.96 20 AGREEMENT B
A144U5-66 Ce-141 5.26E-02 5.11E-02 1.03 20 AGREEMENT CARTRIDGE Cr-51 7.98E-02 7.97E-02 1.00 20 AGREEMENT DET. #2 Cs-134 1.99E-02 2.09E-02 0.95 20 AGREEMENT Cs-137 1.98E-02 1.85E-02 1.07 20 AGREEMENT Co-58 2.10E-02 2.04E-02 1.03 20 AGREEMENT Mn-54 2.65E-02 2.46E-02 1.08 20 AGREEMENT Fe-59 2.47E-02 2.25E-02 1.10 20 AGREEMENT Zn-65 3.37E-02 3.04E-02 1.11 20 AGREEMENT Co-60 2.18E-02 2.08E-02 1.05 20 AGREEMENT A14405-66 Ce-141 4.80E-02 5.11E-02 0.94 20 AGREEMENT CARTRIDGE Cr-51 7.66E-02 7.97E-02 0.96 20 AGREEMENT DET. #3 Cs-134 1.89E-02 2.09E-02 0.90 20 AGREEMENT Cs-137 1.86E-02 1.85E-02 1.01 20 AGREEMENT Co-58 1.98E-02 2.04E-02 0.97 20 AGREEMENT Mn-54 2.54E-02 2.46E-02 1.03 20 AGREEMENT Fe-59 2.37E-02 2.25E-02 1.05 20 AGREEMENT Zn-65 3.18E-02 3.04E-02 1.05 20 AGREEMENT Co-60 2.11E-02 2.08E-02 1.01 20 AGREEMENT A14406-66 Tritium 1.90E-03 1.77E-03 1.07 12.5 AGM i.EMENT LIQUID 2 / 1*****l
ANALYTICS 1380 Seaboard Industrial Blvd.
Atlanta, Georgia 30318. U.S.A.
Phone (404) 352-8677 Fax (404) 352-2837 RESULTS OF RADIOCHEMISTRY CROSS CHECK PROGRAM CONSUMERS POWER COMPANY PALISADES PLANT THIRD QUARTER 2001 Daniel M. Montgomery, QA Manager PALI SADES ANALYTICS RATIO VALUE VALUE PALISADES:
ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON SAMPLE Ce-141 4.15E-04 4.05E-04 1.02 20 AGREEMENT A14687-66 1.44E-03 1.43E-03 1.01 20 AGREEMENT SIMULATED Cr-51 2.12E-04 2.29E-04 0.93 20 AGREEMENT GAS Cs-134 Cs-137 4.56E-04 4.43E-04 1.03 20 AGREEMENT DET. 1 3.82E-04 3.67E-04 1.04 20 AGREEMENT Co-58 3.31E-04 3.11E-04 1.06 20 AGREEMENT Mn-54 2.43E-04 2.26E-04 1.08 20 AGREEMENT Fe-59 4.20E-04 3.96E-04 1.06 20 AGREEMENT Zn-65 Co-60 3.83E-04 3.73E-04 1.03 20 AGREEMENT Ce-141 3.94E-04 4.05E-04 0.97 20 AGREEMENT A14687-66 Cr-51 1.31E-03 1.43E-03 0.92 20 AGREEMENT SIMULATED Cs-134 2.08E-04 2.29E-04 0.91 20 AGREEMENT GAS Cs-137 4.18E-04 4.43E-04 0.94 20 AGREEMENT DET. 2 Co-58 3.55E-04 3.67E-04 0.97 20 AGREEMENT 3.04E-04 3.11E-04 0.98 20 AGREEMENT Mn-54 Fe-59 2.25E-04 2.26E-04 1.00 20 AGREEMENT Zn-65 3.63E-04 3.96E-04 0.92 20 AGREEMENT Co-60 3.40E-04 3.73E-04 0.91 20 AGREEMENT Ce-141 4.34E-04 4.05E-04 1.07 20 AGREEMENT A14687-66 Cr-51 1.52E-03 1.43E-03 1.06 20 AGREEMENT SIMULATED Cs-134 2.32E-04 2.29E-04 1.01 20 AGREEMENT GAS Cs-137 4.76E-04 4.43E-04 1.08 20 AGREEMENT DET. 3 Co-58 4.02E-04 3.67E-04 1.10 20 AGREEMENT Mn-54 3.78E-04 3.11E-04 1.22 20 AGREEMENT Fe-59 2.49E-04 2.26E-04 1.10 20 AGREEMENT Zn-65 4.48E-04 3.96E-04 1.13 20 AGREEMENT Co-60 4.05E-04 3.73E-04 1.09 20 AGREEMENT
PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON A14688-66 Ce-141 2.79E-05 2.92E-05 0.95 20 AGREEMENT SAND Cr-51 9.89E-05 1.03E-04 0.96 20 AGREEMENT DET. 1 Cs-134 1.54E-05 1.65E-05 0.93 20 AGREEMENT Cs-137 3.16E-05 3.19E-05 0.99 20 AGREEMENT Co-58 2.65E-05 2.65E-05 1.00 20 AGREEMENT Mn-54 2.20E-05 2.24E-05 0.98 20 AGREEMENT Fe-59 1.65E-05 1.63E-05 1.01 20 AGREEMENT Zn-65 2.80E-05 2.85E-05 0.98 20 AGREEMENT Co-60 2.65E-05 2.69E-05 0.98 20 AGREEMENT A14688-66 Ce-141 2.85E-05 2.92E-05 0.97 20 AGREEMENT SAND Cr-51 9.72E-05 1.03E-04 0.94 20 AGREEMENT DET. 2 Cs-134 1.50E-05 1.65E-05 0.91 20 AGREEMENT Cs-137 3.07E-05 3.19E-05 0.96 20 AGREEMENT Co-58 2.55E-05 2.65E-05 0.96 20 AGREEMENT Mn-54 2.11E-05 2.24E-05 0.94 20 AGREEMENT Fe-59 1.48E-05 1.63E-05 0.91 20 AGREEMENT Zn-65 2.95E-05 2.85E-05 1.03 20 AGREEMENT Co-60 2.54E-05 2.69E-05 0.94 20 AGREEMENT A14688-66 Ce-141 2.78E-05 2.92E-05 0.95 20 AGREEMENT SAND Cr-51 1.07E-04 1.03E-04 1.04 20 AGREEMENT DET. 3 Cs-134 1.55E-05 1.65E-05 0.94 20 AGREEMENT Cs-137 3.10E-05 3.19E-05 0.97 20 AGREEMENT Co-58 2.75E-05 2.65E-05 1.04 20 AGREEMENT Mn-54 2.20E-05 2.24E-05 0.98 20 AGREEMENT Fe-59 1.74E-05 1.63E-05 1.07 20 AGREEMENT Zn-65 2.77E-05 2.85E-05 0.97 20 AGREEMENT Co-60 2.74E-05 2.69E-05 1.02 20 AGREEMENT
PALI SADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON A14689-66 Ce-141 2.89E-02 2.93E-02 0.99 20 AGREEMENT CARTRIDGE Cr-51 1.00E-01 1.03E-01 0.97 20 AGREEMENT DET. 1 Cs-134 1.54E-02 1.66E-02 0.93 20 AGREEMENT Cs-137 3.34E-02 3.20E-02 1.04 20 AGREEMENT Co-58 2.74E-02 2.66E-02 1.03 20 AGREEMENT Mn-54 2.40E-02 2.25E-02 1.07 20 AGREEMENT Fe-59 1.77E-02 1.63E-02 1.08 20 AGREEMENT Zn-65 3.11E-02 2.86E-02 1.09 20 AGREEMENT Co-60 2.72E-02 2.70E-02 1.01 20 AGREEMENT A14689-66 Ce-141 2.78E-02 2 .93E-02 0.95 20 AGREEMENT CARTRIDGE Cr-51 9.52E-02 1. 03E-01 0.92 20 AGREEMENT DET. 2 Cs-134 1. 49E-02 1. 66E-02 0.90 20 AGREEMENT Cs-137 3.17E-02 3.20E-02 0.99 20 AGREEMENT Co-58 2.65E-02 2 .66E-02 1.00 20 AGREEMENT Mn-54 2.27E-02 2 .25E-02 1.01 20 AGREEMENT Fe-59 1. 66E-02 1. 63E-02 1.02 20 AGREEMENT Zn-65 2.87E-02 2.86E-02 1.00 20 AGREEMENT Co-60 2.55E-02 2.70E-02 0.94 20 AGREEMENT k******* 2** k*********
A14689-66 Ce-141 2.88E-02 2.93E-02 0.98 20 AGREEMENT CARTRIDGE Cr-51 1. 04E-01 1.03E-01 1.01 20 AGREEMENT DET. 3 Cs-134 1.56E-02 1. 66E-02 0.94 20 AGREEMENT Cs-137 3.25E-02 3.20E-02 1.01 20 AGREEMENT Co-58 2. 68E-02 2. 66E-02 1.01 20 AGREEMENT Mn-54 2.36E-02 2.25E-02 1.05 20 AGREEMENT Fe-59 1.71E-02 1. 63E-02 1.05 20 AGREEMENT Zn-65 3. 01E-02 2.86E-02 1 .05 20 AGREEMENT Co-60 2.75E-02 2.70E-02 1 .02 20 AGREEMENT
ANALYTICS 1380 Seaboard Industrial Blvd.
Atlanta, Georgia 30318 U.S.A.
Phone (404) 352-8677 Fax (404) 352-2837 RESULTS OF RADIOCHEMISTRY CROSS CHECK PROGRAM CONSUMERS POWER COMPANY PALISADES PLANT T-HIR UARTER 2001 Daniel M. M~ontgomery, QA Manager
-135-
PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON A14984-66 Ce-141 6.03E-02 6.03E-02 1.00 20 AGREEMENT CARTRIDGE Cr-51 8.95E-02 8.73E-02 1.03 20 AGREEMENT 34 l I Cs-134 1.68E-02 1.82E-02 0.92 20 AGREEMENT Cs-137 3.12E-02 2.84E-02 1.10 20 AGREEMENT Co-58 1.17E-02 1.05E-02 1.11 20 AGREEMENT Mn-54 1.56E-02 1.41E-02 1.11 20 AGREEMENT Fe-59 1.53E-02 1.38E-02 1.11 20 AGREEMENT Zn-65 2.22E-02 1.99E-02 1.12 20 AGREEMENT Co-60 3.16E-02 3.18E-02 0.99 20 AGREEMENT A14984-66 Ce-141 5.93E-02 6.03E-02 0.98 20 AGREEMENT CARTRIDGE Cr-51 8.62E-02 8.73E-02 0.99 20 AGREEMENT
,1), Cs-134 1.69E-02 1.82E-02 0.93 20 AGREEMENT Cs-137 3.03E-02 2.84E-02 1.07 20 AGREEMENT Co-58 1.13E-02 1.05E-02 1.08 20 AGREEMENT Mn-54 1.54E-02 1.41E-02 1.09 20 AGREEMENT Fe-59 1.54E-02 1.38E-02 1.11 20 AGREEMENT Zn-65 2.16E-02 1.99E-02 1.09 20 AGREEMENT Co-60 3.09E-02 3.18E-02 0.97 20 AGREEMENT A14984-66 Ce-141 6.06E-02 6.03E-02 1.01 20 AGREEMENT CARTRIDGE Cr-51 8.82E-02 8.73E-02 1.01 20 AGREEMENT be A Cs-134 1.71E-02 1.82E-02 0.94 20 AGREEMENT Cs-137 2.96E-02 2.84E-02 1.04 20 AGREEMENT Co-58 1.13E-02 1.05E-02 1.08 20 AGREEMENT Mn-54 1.51E-02 1.41E-02 1.07 20 AGREEMENT Fe-59 1.59E-02 1.38E-02 1.15 20 AGREEMENT Zn-65 2.26E-02 1.99E-02 1.14 20 AGREEMENT Co-60 3.37E-02 3.18E-02 1.06 20 AGREEMENT
- Il-
PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:
SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON A14985-66 Ce-141 1.70E-03 1.77E-03 0.96 20 AGREEMENT SOLID Cr-51 2.30E-03 2.56E-03 0.90 20 AGREEMENT Mf me4 Cs-134 5.28E-04 5.34E-04 0.99 20 AGREEMENT Cs-137 8.62E-04 8.35E-04 1.03 20 AGREEMENT Co-58 3.12E-04 3.09E-04 1.01 20 AGREEMENT Mn-54 4.33E-04 4.15E-04 1.04 20 AGREEMENT Fe-59 4.52E-04 4.06E-04 1.11 20 AGREEMENT Zn-65 5.71E-04 5.84E-04 0.98 20 AGREEMENT Co-60 9.44E-04 9.35E-04 1.01 20 AGREEMENT A14985-66 Ce-141 1.74E-03 1.77E-03 0.98 20 AGREEMENT SOLID Cr-51 2.60E-03 2.56E-03 1.01 20 AGREEMENT it Cs-134 5.77E-04 5.34E-04 1.08 20 AGREEMENT Cs-137 8.37E-04 8.35E-04 1.00 20 AGREEMENT Co-58 3.13E-04 3.09E-04 1.01 20 AGREEMENT Mn-54 3.81E-04 4.15E-04 0.92 20 AGREEMENT Fe-59 3.16E-04 4.06E-04 0.78 20 AGREEMENT Zn-65 6.45E-04 5.84E-04 1.10 20 AGREEMENT Co-60 8.85E-04 9.35E-04 0.95 20 AGREEMENT A14985-66 Ce-141 1.66E-03 1.77E-03 0.94 20 AGREEMENT SOLID Cr-51 2.62E-03 2.56E-03 1.02 20 AGREEMENT A 0.3 Cs-134 5.45E-04 5.34E-04 1.02 20 AGREEMENT Cs-137 8.89E-04 8.35E-04 1.06 20 AGREEMENT Co-58 3.59E-04 3.09E-04 1.16 20 AGREEMENT Mn-54 4.30E-04 4.15E-04 1.04 20 AGREEMENT Fe-59 4.14E-04 4.06E-04 1.02 20 AGREEMENT Zn-65 6.34E-04 5.84E-04 1.09 20 AGREEMENT Co-60 9.04E-04 9.35E-04 0.97 20 AGREEMENT
ATTACHMENT 7 NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT OFFSITE DOSE CALCULATION MANUAL 106 pages follow
I PA M1 .10r
- . -..- Prod No 3.07 Attachrmnt I Revision 10 NO* lof I 1 Log No SDR- --. 7 Item Idjfcation: Now .. Rev he Titl /)- II, . .
Describe lssuelChange: e'a4'i/ /.4/
Reason for Issue/Change: ' - e,*,,4' /I43 £A#g/A_-
-I I_ ,%la'de.... . , ,
"
- 0 UwRN i involve a cnange to procqdures as described in the FSAR?
'm Yes No PSAR Sections affected v 4 FSAR Sections reviewed
- 2. Does the item involve a change to the rflity as described or implied in the FSAR?
FSAR Sections affected ... ._ _ _... .
FSAR Sections reviewed 'i/
- 3. Does the item involve a test or experime t not described in the p.-
9 FSAR?
FSAR Sections affected /13tg...
FSAR Sections reviewed -.
- 4. Should the Technical Specifications or any of their Bases be changed in conjunction with this item?
TS Sections affected TS Sections reviewed ____.
O(,M . - f;, e ,J,. ) t If any Safety Review question listed above is answered "YES,"
perform a written USO Evaluation. Justify "NO" answers below if logic is not obvious:
Cg, C-06' eAo0-. a...r
... r7& T*M A-NOTIE: DBD change requests shall be processed in accordance with Administrative Procedure 3.1 S. 4 I, DBD Sections Reviewed _ _ _/ _ _ _ Affected ____-
Sf I
I This attachment shall accompany other review materials for the item to document whether or not a USO Evaluation was required.
Prepared by Date Reviewed by Dat 3
I=
1 LogNoSR- 2--1-9 37 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?
V
- 4. Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
I,-
- 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 equipment important to safety 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 nat bA imnnlrnantarl with,.im+ Al;^. K2I--0S4 ....... -*...
SECTION II
- 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 thisitem?
M SECTION III a-I I //vio=
Preparid bv /.2 7ocDa8te a V, IWVV:I.4 my
-;I -
Proc N,3.0 A tchmaht UGL~fil LQJTRevIslo"9 OALIA12ffiý page I of 1 EItem Identification~: 4,6 Oev L.. Log No SDR Cw= fflofthl AC V="page e~t~A,9R4,07b A10AW yalos vawe . a7 e Ajisw!,
-7 (jIA~~
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-M11
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 Table of Contents I. GASEOUS EFFLUENTS .................................. 1 A. ALARM/TRIP SETPOINT METHOD ................... 1
- 1. Allowable Concentration .............. 2
- 2. Monitor Response .................. 3 B. DOSE RATE CALCULATION ........................ 4 C. DESIGN OBJECTIVE QUANTITY (DBQ) LIMITS ON BATCH AND CONTINUOUS RELEASES ..................... 21
- 1. Batch Releases .................... 21
- 2. Continuous Releases ............... 22
- 3. Exceeding DBQ Limits .............. 22
- 4. Releasing Radionuclides Not Listed in Table 1.9 ...................... 22 D. OPTIONAL QUARTERLY DOSE CALCULATIONS ......... 23
- 1. Methodology for Optional Quarterly Dose Calculations ............... 23 E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION 26
- 1. System Description ................ 26
- 2. Determination of Satisfactory Operation . 27 F. RELEASE RATE FOR OFFSITE EC ..... ..... ........ 27 G. PARTICULATE AND IODINE SAMPLING . . . . . . . . . . . . ., 28 H. NOBLE GAS SAMPLING ........... 29 I. TRITIUM SAMPLING .............. .... ......... 29 J. FIGURES AND TABLES ............ . . . . . . . . . . . . . 30
- i v-
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 Table of Contents IH. LIQUID EFFLUENTS .......................... .. ... .. .. 69 A. CONCENTRATION .................... . .... . .. . 69
- 1. Requirements ................... 69
- 2. Prerelease Analysis .s ............... 69
- 3. Effluent Concentration (EC) - Sum of the Ratios ...................... 70 B. INSTRUMENT SETPOINTS ........................ 71
- 1. Setpoint Determination ... 71
- 2. Composite Samplers .... 71
- 3. Post-Release Analysis ... 72 C. D OS E . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .......... 72
- 1. RETS Requirement ...... .. .......... 72
- 2. Release Analysis ....... .. .......... 73 D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT 77 E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr) . . 78 F. FIGURES AND TABLES ................... 79 II1. URANIUM FUEL CYCLE DOSE ..................... 100 A. SPECIFICATION ........................ 100 B. ASSUMPTIONS ........................ 100 C. DOSE CALCULATION .................... 101 Appendix A, "Relocated Technical Specification" Appendix B, "Request to Retain Soil in Accordance With 10 CFR 20.302"
,- V-
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 GASEOUS EFFLUENTS A. ALARM/TRIP SETPOINT METHOD Appendix A,Section III.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-1 31, for iodine-1 33, 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 III.A.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged over 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, will not be greater than Appendix A,Section III.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
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 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, 10 CFR 20:
R(k) - (F)
C.'_ = *- 5. 0 ECi (1.1)
If gaseous tritium and noble gasses are not present then:
Rik) _<10 where:
Ci = Actual or measured concentration, at ambient temperature and pressure of nuclide i (pCi/cc)
EC = The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 Rik) = 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 2
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 5.0.
- 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-1 33). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-1 33, however.
Monitor response for the two categories of monitor is determined as follows:
- a. Normal Release (aged fission gasses)
Total gas concentration (ftCi/cc) at the monitor is calculated.
The calibration curve or constant for cpm//jCi/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 = bxc (1.2)
- b. 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 pCi/cc (or R/hr and pCi/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.
3
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 10 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 millirem 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.
b) 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/Q's shown in Table 1.3.
4
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 g) Raw meteorological data consists of wind speed and direction measurements at 10m and temperature measurements at 1Om 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.
o) 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 --
5
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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, B=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:
Xi fjk Qp [exp ix j=1 k=1 zkUJ (2 x/n) U)
(1.3) where:
XI = Air concentration of radionuclide i, UCi/M 3 .
f -k Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
Qi = Average release rate of radionuclide i, pCi/s.
p Fraction of radionuclide remaining in plume.
zk = Vertical dispersion coefficient for stability class k (m).
uj = Midpoint value of wind speed class interval j, m/s.
6
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 x = Downwind distance, m.
n = Number of sectors, 16.
- Radioactive decay coefficient of radionuclide i, s-1.
2 x/n = Sector width at point of interest, m.
For determining the total body dose rate:
DTB = i Xi DFB1 (1.4) where:
DTB = Total body dose rate, mrem/y.
X = Air concentration of radionuclide I, 3
pCi/m .
DFB1 = Total body dose factor due to gamma radiation, mrem/y per pCi/i 3 (Table 1.5).
For determining the skin dose rate:
DS = i xi (DFSi + 1.11 DFYi)
(1 .5) where:
Ds = Skin dose rate, mrem/y.
X = Air concentration of radionuclide i, /JCi/m3 DFSi = Skin dose factor due to beta radiation, mrem/y per pCi/m 3 (Table 1.5).
7
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 1.1 1 The average ratio of tissue to air energy absorption coefficients, mrem/mrad.
DFY = Gamma-to-air dose factor for 3 radionuclide i, mrad/y per/lCi/m (Table 1.5).
For determining dose rate to a point in air:
Da Xi (DFYi or DFBi)
(1.6) where:
Da = Air dose rate, mrad/yr.
DFB1 = 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.
c) 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.
8
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 1Om and temperature measurements at 10m 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.
- 1) 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.
p) 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).
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 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:
Di = 1 x 10 6 Xi DFIi BR (1.7) where:
D = Organ dose rate due to inhalation, mrem/y.
XI = Air concentration of radionuclide i, pCi/m 3 .
DFIi = 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.
1xl 06 = pCi/pCi conversion factor.
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 b) Ground Contamination For determining the ground concentration of any nuclide; 7fk Qi DR [1-exp-( i tb)]
G = 3.15 x 107 k=1 (2 x/n) 1 (1.8) where:
G1 = Ground concentration of radionuclide i, pCi/m 2 .
k = Stability class.
fk = Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction.
Q = Average release rate of radionuclide i, pCi/s.
DR = Relative deposition rate, m 1 (Fig 1.2).
x = Downwind distance, m.
n = Number of sectors, 16.
2 x/n = Sector width at point of interest, m.
i Radioactive decay coefficient of radionuclide i, y-1.
tb Time for buildup of radionuclides on the ground, 15 y.
3.15x 1 07 s/y conversion factor.
11
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 Corrected Figure 1.2 uarv 1977 10-3 10-4 z
w uj 10 uji LU
-j LU 10-6 1-I 104 1.0 10.0 100.0 200.0 0.1 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 7. Relative Deposition for Ground Level Releases (All Atmospheric Stability Classes) 12
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 dose For determining the total body or organ For determining the total body or organ dose rate from ground contamination:
DG = (8,760)(1 X 10)(0.7) Gi DFGi 1.9) where:
DG = Dose rate due to ground contamination, mrem/y.
G= Ground concentration of radionuclide i, pCi/m 2 .
DFGi = Dose factor for standing on contaminated ground, mrem/h per pCi/m 2 (Table 1.8).
8,760 = Occupation time, h/y.
1x10 6 = pCi/pCi 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:
CVi - 3,600 7 fk Qi DR rr[l -exp (_
Yv Ei Eite)] + Biv[ 1 -exp (
i itb)]tI exp-( ith)
k=1 (2 x/n)
(1.10) where:
Concentration of radionuclide i in CVj and on vegetation, pCi/kg.
k Stability class.
13
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 fk Frequency of this stability class and wind direction combination, expressed as a fraction.
Q = Average release rate of radionuclide i, pCi/s.
DR = Relative deposition rate, m-1 (Figure 1.2).
x Downwind distance, m.
n = Number of sectors, 16.
2 x/n Sector width at point of interest, m.
r = Fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates).
Ei = Effective removal rate constant, Ei = i + w, where iis the radioactive decay coefficient, h- 1 ,
and w is a measure of physical loss by weathering
( w = 0.0021 h-).
te = Period over which deposition occurs, 720 h.
YV = Agricultural yield, 0.7 kg/M 2 .
B = Transfer factor from soil to vegetation of radionuclide i (Table 1.6).
-= Radioactive decay coefficient of radionuclide i, h 1 .
tb = Time for buildup of radionuclides 5
on the ground, 1.31x10 h (15Y).
14
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 p = Effective surface density of soil, 240 kg/M 2 .
3,600 = s/h conversion factor.
th = Holdup time between harvest and consumption of food (2,160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> for stored food).
For determining the concentration of C-14 in vegetation:
CV 14 =1 X 103 X 14 (0.11/0.16)
(1.11) where:
CV 14 Concentration of C-1 4 in vegetation, pCi/kg.
X14 = Air concentration of C-14, pCi/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 .
lx103 = g/kg conversion factor.
For determining the concentration of H-3 in vegetation:
CVT =lx 103 XT (0.75)(0.5/H)
(1.12) where:
CVT Concentration of H-3 in vegetation, pCi/m 3 .
XT Air concentration of H-3, pCi/m 3 .
15
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 0.75 = Fraction of total Plant mass that is 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 .
1x10 3 g/kg conversion factor.,
For determining the concentration of any nuclide in cow's or goat's milk:
CMi = CVi FM1 Qf exp (- i tf) (1.13) where:
CM = Concentration of radionuclide i (including C-14 and H-3) in milk, pCi/ .
CVi Concentration of radionuclide i in and on vegetation, pCi/kg.
FM1 Transfer factor from feed to milk for radionuclide i, d/ (Table 1.6).
Qf Amount of feed consumed by the milk animal per day, kg/d (cow, 50 kg/d or goat 6 kg/d).
Radioactive decay coefficient of radionuclide i, d-1 .
tf Transport time of activity from feed to milk to receptor, 2 days.
16
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 For determining the organ dose rate from ingestion of green leafy vegetables and milk:
D = 1 x 106 i CM, DF1 UM (1.14) where:
D = Organ dose rate due to ingestion, mrem/y.
CM = Concentration of radionuclide i in vegetables or milk, pCi/kg (or liters).
DFi = Ingestion dose factor, mrem/pCi (Table 2.1).
UM = Ingestion rate for milk, 330 /y; for vegetables 26 kg/yr (child), no ingestion by infant.
lx106 = pCi/pCi conversion factor.
d) Meat Ingestion (Beef)
To calculate the concentration of a nuclide in animal flesh:
Cfi = Ffi CVi Qfi exp ( its) (1.15) where:
Cf1 Concentration of nuclide i in the animal flesh, pCi/kg.
Ffi Fraction of animal's daily intake which appears in each kg of flesh, days/kg (Table 1.6).
CVi Concentration of radionuclide i in the animal's feed (Equation 1.10).
17
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 Qf Amount of feed consumed by the cow per day, 50 kg/d.
ts Average time from slaughter to consumption, 20 days.
To determine the organ dose from ingestion of beef:
D f = Cfi Dfi Uf (1.16) where:
Dfj Ingestion dose factor for age group, mrem/pCi (Table 2.1) for nuclide i.
Uf Ingestion rate of meat for age group, kg/y (child-41, teen-65, adult- 110).
e) Organ Dose Rates For determining the total body and organ dose rate from iodines and particulates:
D = D, + DG + DM + Dv + DF (1.1 7) where:
D Total organ dose rate, mrem/y.
D= Dose rate due to inhalation, mrem/y.
DG Dose rate due to ground contamination, mrem/y.
DM Dose rate due to milk ingestion, mrem/y.
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 Dv Dose rate due to vegetable ingestion, mrem/y.
DF 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 1.B) are used to calculate design basis quantities as described in Section I.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) 15 millirem to any organ of an individual from iodines and particulates with half-life greater than 8 days (Appendix A,Section III.D.1).
- 2) 15 millirem to skin of an individual from noble gas (Appendix A,Section III.C.1 .b).
- 3) 5 millirem to the total body of an individual from noble gas (Appendix A, Section II1.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 of radionuclide used.
DBQ = (CD)
(1.18) 19
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 where:
DAI Appendix I dose limit (mrem or mrad).
Dc = Calculated dose (mrem or mrad).
c = 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 CcIDc in the above equation (ie, Dc/CJ) is a useful value, since it represents the most limiting dose per unit quantity of each nuclide released. Use of the DC/Co ratio in quarterly evaluation of offsite dose is discussed in Section D. Values of Dc/Co 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.
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- e. Gaseous Releases From the Steam Generator Blowdown 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 100 percent of Noble Gases, 10 percent of the lodines 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.
C. 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:
Ai Ai_ < 1.0 (DBQ)i (1.19)
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.
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 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 B.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 cblculations 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.
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 10% 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.
22
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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.
- a. 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.
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 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:
i DG = AiG(Dc/CCG < 5 millirad/quarter, 10 mrad/yr 0
(1.20) where:
DG = Dose from gaseous effluents (mrad).
AiG = Quantity of gaseous nuclide i released (Ci).
(Dc/CA)iG Dose per Ci factor for gaseous nuclide i (mrad/Ci).
24
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 10 millirem/quarter and 20 millirem/year.
For determining tritium, particulate and iodine dose to organs:
DTPI ATPHi (DJ/Cc)TPHi < 7.5 mrem/q, 15 mrem/y (1.21) where:
DTPI Dose from particulates and iodines (mrem).
ATP, Quantity of particulate or iodine nuclide i released (Ci).
(Dc/Cc)TPli Dose per Ci factor for particulate or iodine nuclide i (mrad/Ci).
- 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.
25
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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.
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.
26
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 2. Determination of Satisfactory Operation Design basis quantity fraction will be calculated for batch and continuous releases as described in Section I.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 13-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 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 inhaled or ingested continuously for one year will result in a dose of 50 mrem whole body except for submersion dose isotopes (gaseous tritium and noble gasses) which will results in a dose of 100 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 10 CFR 20.1302 limits but still within those limits. Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement.
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 2.1 5E-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.
27
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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.
28
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 1E-06 pCi/cc. Sampling and analysis will be performed per Appendix A, Table B-1 requirements.
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.
29
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 J. FIGURES AND TABLES is I ia
-u I-
_o LL<
M CO,,
LUC)
-J CL 30
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.1 PALISADES GASEOUS AND LIQUID SOURCE TERMS, CURIES/YEAR (1)
Nuclide Gaseous(2) Liauid(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-131m 2.2 NA Xe-1 33 1493 NA Xe-1 33m 0.43 NA Xe-1i35 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 2.1E-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-1 27 NA 3.5E-05 Cs-1 34 4.5E-05 0.7 Cs-1 36 NA 1.8E-06 Cs-1 37 2.6E-04 1.36E-02 Ba-1 40 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.
31
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA 1 (days) (l/s) (MEV/DIS) (MEV/DIS) 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 CO-58 7.13E 01 1 .12E-07 3.41 E-02 9.78E-01 14 CO-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 1.01E 00 2.05E-00 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 7.1OE-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.OOE-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 3.61E-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 MO-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 40 TC-99m 2.50E-01 3.21 E-05 1.56E-02 1.26E-01 32
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.2 (continued)
BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA 1 GAMMA 1 (days) (1/s) (MEV/DIS) (MEV/DIS) 41 TC-99 7.74E 07 1.04E-1 3 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.OOE-01 2.33E-01 45 1-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 46 1-131 8.05E 00 9.96E-07 1.94E-01 3.81E-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 3.61E-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 1.18E 01 6.80E-07 1.43E-01 2.01E-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-1 35m 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 2.71E 03 2.96E-03 1.77E 00 1.88E-01 57 XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E O0 58 CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 59 CS-135 1.10E 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 1.10E 04 7.29E-10 1.71E-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 2.31E 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 3.18E 00 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.
33
USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE- 970513
- PALISADES XOQDOQ82 ***** USING (11/01/92 - 12/31/96 MET DATA
- GROUND LEVEL RELEASE - TOP OF CONrAINMENT BUILDING NO DECAY, UNDEPLETED ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 SECTOR 0.250 0.500 0.750 4.208E-06 1.381E-06 7.556E-07 4.993E-07 2.782E-07 1.842E-07 1.340E-07 1.033E-07 8.298E-08 6.867E-08 5.813E-08 S 6.528E-08 5.413E-08 4.590E-08 3.870E-07 2.160E-07 1.437E-07 1.048E-07 8.108E-08 SSW 3.330E-06 1.086E-06 5.856E-07 5.267E-08 2.413E-07 1.614E-07 1.184E-07 9.203E-08 7.440E-08 6.191E-08 SW 3.890E-06 1.242E-06 6.590E-07 4.333E-07 5.477E-08 9.484E-08 7.694E-08 6.422E-08 WSW 4.060E-06 1.279E-06 6.715E-07 4.401E-07 2.450E-07 3.349E-07 1.648E-07 2.249E-07 1.215E-07 1.657E-07 1.292E-07 1.047E-07 8.735E-08 7.447E-08 0 W 5.554E-06 1.759E-06 9.224E-07 6.035E-07 9.937E-08 In 4.487E-07 3.010E-07 2.216E-07 1.726E-07 1.399E-07 1.166E-07 1.235E-06 8.084E-07 WNW 7.378E-06 2.346E-06 2.974E-06 1.551E-06 1.012E-06 5.610E-07 3.784E-07 2.800E-07 2.191E-07 1.781E-07 1.490E-07 1.273E-07 In NW 9.531E-06 2.391E-07 2.003E-07 1.715E-07 7.443E-07 5.039E-07 3.741E-07 2.935E-07 1.286E-05 3.959E-06 2.052E-06 1.339E-06 1.462E-07 NNW 1.087E-05 3.347E-06 1.739E-06 1.138E-06 6.348E-07 4.3003-07 3.192E-07 2.504E-07 2.040E-07 1.709E-07 7.501E-08 m
N 1.664E-07 1.299E-07 1.054E-07 8.793E-08 NNE 9.119E-07 6.000E-07 3.353E-07 2.256E-07 a 0 V) 5.487E-06 1.717E-06 1.049E-07 8.657E-08 7.312E-08 3.578E-07 2.355E-07 1.705E-07 1.310E-07 NE 5.450E-06 1.803E-06 9.856E-07 6.476E-07 9.850E-08 7.885E-08 6.507E-08 5.496E-08 2.697E-07 1.773E-07 1.282E-07 4.258E-06 1.379E-06 7.464E-07 4.886E-07 2.990E-07 1.959E-07 1.413E-07 1.082E-07 8.645E-08 7.120E-08 6.002E-08 U)
ESE 4.618E-06 1.531E-06 8.321E-07 5.438E-07 2.848E-07 1.860E-07 1.338E-07 1.023E-07 8.153E-08 6.704E-08 5.644E-08 m 4.436E-06 1.479E-06 8.008E-07 5.210E-07 9.217E-08 7.586E-08 6.391E-08 :m (D C) V)
SE 5.091E-06 1.678E-06 9.044E-07 5.872E-07 3.207E-07 2.096E-07 1.509E-07 1.155E-07 7.858E-08 _<
SSE 6.044E-06 2.000E-06 1.088E-06 7.106E-07 3.901E-07 2.557E-07 1.845E-07 1.415E-07 1.131E-07 9.317E-08 2 CO 0m r m
ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE 30.000 35.000 40.000 45.000 50.000 -A m
SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 C,
S 2.837E-08 1.901E-08 1. 086E-08 7.328E-09 5.410E-09 4.227E-09 3.433E-09 2.869E-09 2.450E-09 2.127E-09 5.010E-08 3.431E-09 2.793E-09 2.338E-09 2.000E-09 1.740E-09 3.963E-08 2.257E-08 1.519E-08 8.728E-09 5.913E-09 4.379E-09 SSW 3.405E-09 2.863E-09 2.458E-09 2.145E-09 SW 4. 5603-08 2.627E-08 1.782E-08 1.037E-08 7.086E-09 5.284E-09 4.163E-09 0 WSW 4.753E-08 2.763E-08 3.749E-08 1.886E-08 2.557E-08 1.106E-08
- 1. 498E-08 7.602E-09 1.029E-08 5.693E-09 7.706E-09 4.501E-09 6.091E-09 3.693E-09 4.996E-09 3.113E-09 4.211E-09 2.678E-09 3.623E-09 2.342E-09 3.168E-09 z W 6.459E-08 6.606E-09 5.565E-09 4.785E-09 4.183E-09 WNW 4.992E-08 3.400E-08 1.989E-08 1.364E-08 1.021E-08 8.059E-09 8.615E-08 6.449E-09 5.649E-09 8.857E-09 7.481E-09 NW 1.106E-07 1.492E-07 6.471E-08 8.772E-08 4.436E-08 6.035E-08 2.618E-08 3.579E-08 1.808E-08 2.479E-08 1.359E-08 1.867E-08 1.077E-08 1.483E-08 1.221E-08 1.033E-08 8.915E-09 7.817E-09 z --q 3.045E-08 2.107E-08 1.586E-08 1.259E-08 1.036E-08 8.762E-09 7.559E-09 6.625E-09 N 1. 273E-07 7.475E-08 5.139E-08 3.654E-09 3.194E-09
- 1. 513E-08 1.039E-08 7.781E-09 6.148E-09 5.042E-09 4.248E-09 NNE 6.508E-08 3.782E-08 2.581E-08 3.000E-09 2.604E-09 1.342E-08 9.033E-09 6.656E-09 5.193E-09 4.213E-09 3.517E-09 NE 6.291E-08 3.539E-08 2.361E-08 1.993E-09 6.847E-09 5.056E-09 3.951E-09 3.211E-09 2.684E-09 2.293E-09 ENE 4.729E-08 2.665E-08 1.781E-08 1. 015E-08 7.262E-09 5.337E-09 4.155E-09 3.366E-09 2.806E-09 2.392E-09 2.074E-09 E 5.155E-08 2.883E-08 1.915E-08 1. 083E-08 1.007E-08 6.742E-09 4.948E-09 3.848E-09 3.114E-09 2.594E-09 2.210E-09 1.915E-09 ESE 4.843E-08 2.698E-08 1.788E-08 5.702E-09 4.445E-09 3.604E-09 3.008E-09 2.566E-09 2.227E-09 5.488E-08 3.069E-08 2.039E-08 1. 154E-08 7.748E-09 SE 4.466E-09 3.727E-09 3.179E-09 2.758E-09 3.785E-08 2.519E-08 1.428E-08 9.595E-09 7.064E-09 5.507E-09 SSE 6.753E-08 VENT AND BUILDING PARAMETERS:
RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 (METERS) 58.1 (METERS) 0.00 BUILDING HEIGHT DIAMETER (SQ.METEBS) 2000.0 0.00 BLDG .MIN. CRS. SEC. AREA EXIT VELOCITY (METERS) (CAL/SEC) 0.0 HEAT EMISSION RATE 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 CONTAINME BUILDING NO DECAY, UNDEPLETED CHI/O (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 DIRECTION .5-1 FROM SITE 5.448E-09 3.445E-09 1.351E-07 8.334E-08 5.828E-08 2.904E-08 1.110E-08 2.454E-09 S 7.808E-07 2.856E-07 2.308E-08 8, 912E-09 4.409E-09 2.802E-09 2.004E-09 6.085E-07 2.219E-07 1.057E-07 6.555E-08 4.602E-08 SSW 1.057E-08 5.316E-09 3.415E-09 2.462E-09 5.279E-08 2.681E-08 SW 6.883E-07 2.484E-07 1.193E-07 7.468E-08 2.81SE-08 1.126E-08 5.725E-09 3.703E-09 2.683E-09 0 7.038E-07 2.527E-07 1.224E-07 7.721E-08 5.489E-08 WSW 3.821E-08 1.525E-08 7.749E-09 5.010E-09 3.629E-09 W 9.666E-07 3.457E-07 1.669E-07 1.051E-07 7.463E-08 In 1.404E-07 9.958E-08 5.089E-08 2.025E-08 1.026E-08 6.625E-09 4,793E-09 1.292E-06 4.630E-07 2,232E-07 2.819E-07 1.787E-07 1.276E-07 6.587E-08 2.662E-08 1.366E-08 8.879E-09 6.458E-09 In NW 1.627E-06 5.8OOE-07 1.877E-08 1.224E-08 8.928E-09 1.718E-07 B.923E-08 3.636E-08 0 r NNW 2.159E-06 7.69SE-07 3.765E-07 2.399E-07 1.465E-07 7.604E-08 3.093E-08 1.594E-08 1. 039E-08 7.569E-09 1.829E-06 6.557E-07 3.212E-07 2.046E-07 0 Co N 3.854E-08 1.540E-08 7.825E-09 5.056E-09 3.660E-09 3.454E-07 1.676E-07 1.057E-07 7.516E-08 NNE 9,521E-07 3.627E-08 1.374E-08 6.704E-09 4.227E-09 3,006E-09 NE 1.017E-06 3.678E-07 1.720E-07 1.054E-07 7.332E-08 5.092E-09 3.222E-09 2.298E-09 ENE 7.724E-07 2.773E-07 1.294E-07 7.922E-08 8,686E-08 5.511E-08 6.020E-08 2.731E-08 2.958E-08 1.038E-08 1.109E-08 5.378E-09 3.378E-09 2.397E-09 rn) 0m E 8,592E-07 3.076E-07 1.426E-07 3.126E-09 2.214E-09 C) Co 8.271E-07 2.934E-07 1.351E-07 8.193E-08 5.661E-08 2.770E-08 1.033E-08 4.986E-09 -I ESE 3.149E-08 1.182E-08 5.745E-09 3.617E-09 2.571E-09 (U SE 9.353E-07 3.305E-07 1.524E-07 9.262E-08 6,411E-08 1.462E-08 7.116E-09 4.482E-09 3.186E-09 w 2 SSE 1.123E-06 4.016E-07 1. 863E-07 1. 136E-07 7.881E-08 3.882E-08 r C, C (A) m rl 0 0,1 -a r
.. % m IA) 0) 0 z
r r
2
-I
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 CONTAIN= BUILDING 2.260 DAY 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 2
S 4.205E-06 1.379E-06 7.540E-07 4.979E-07 2.769E-07 1.831E-07 1.330E-07 1.024E 07 8.212E-08 6.785E-08 5.735E-08 SSW 3.327E-06 1.084E-06 5.842E-07 3.858E-07 2.150E-07 1.428E-07 1.040E-07 8.032E-08 6.457E-08 5.346E-08 4.526E-08 SW 3.887E-06 1.240E-06 6.575E-07 4.319E-07 2.402E-07 1.604E-07 1.175E-07 9.117E-08 7.359E-08 6.114E-08 5.193E-08 0 WSW 4.057E-06 1.277E-06 6.699E-07 4.388E-07 2.439E-07 1.637E-07 1.206E-07 9.394E-08 7.609E-08 6.341E-08 5.400E-08 5.550E-06 1.757E-06 9.203E-07 6,016E-07 3.334E-07 2.235E-07 1.644E-07 1.280E-07 1.036E-07 8.628E-08 7.344E-08 -n w
7.373E-06 2.343E-06 1.232E-06 8.062E-07 4.468E-07 2.993E-07 2.200E-07 1.712E-07 1.385E-07 1.153E-07 9.810E-08 MWN NNW 9.524E-06 2.969E-06 1.547E-06 1.009E-06 5.585E-07 3.761E-07 2.779E-07 2.171E-07 1.762E-07 1.472E-07 1.256E-07 NW 1.285E-05 3.953E-06 2.047E-06 1.335E-06 7.408E-07 5.008E-07 3.712E-07 2.907E-07 2.365E-07 1.979E-07 1.691E-07 N 1.087E-05 3.341E-06 1.735E-06 1.134E-06 6.316E-07 4.271E-07 3.165E-07 2.478E-07 2.016E-07 1.686E-07 1.440E-07 NNE 5.483E-06 1.714E-06 9.099E-07 5.982E-07 3.338E-07 2.242E-07 1.652E-07 1.287E-07 1.042E-07 8.687E-08 7.398E-08 NE 5.447E-06 1.800E-06 9.837E-07 6.458E-07 3.563E-07 2.343E-07 1.693E-07 1.299E-07 1.039E-07 8.564E-08 7.223E-08 rm ENE 4.255E-06 1.377E-06 7.448E-07 4.872E-07 2.685E-07 1.763E-07 1.273E-07 9.763E-08 7.804E-08 6.431E-08 5.423E-08 0
E 4.615E-06 1.528E-06 8.303E-07 5.423E-07 2.977E-07 1.948E-07 1.403E-07 1.073E-07 8.559E-08 7.039E-08 8.075E-08 6.631E-08 5.925E-08 5.575E-08 CD m
ESE 4.433E-06 1.477E-06 7.992E-07 5.196E-07 2.837E-07 1.850E-07 1.328E-07 1.014E-07 SE 2.085E-07 1.499E-07 1.145E-07 9.128E-08 7.502E-08 6.312E-08 _S. 0o (A)
SSE 5.088E-06 6.040E-06 1.676E-06 1.997E-06 9.026E-07 1.086E-06 5.856E-07 7.087E-07 3.194E-07 3.885E-07 2.543E-07 1.833E-07 1.403E-07 1.120E-07 9.213E-08 7.760E-08 C', z m 0 0,)
ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE 0
50.000 SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 -CA 0, I m S 4.936E-08 2.774E-08 1.845E-08 1.039E-08 6.911E-09 5.029E-09 3.874E-09 3.103E-09 2.557E-09 2.153E-09 1.844E-09 SSW 3.901E-08 2.204E-08 1.472E-08 8.327E-09 5.555E-09 4.051E-09 3.126E-09 2.506E-09 2.067E-09 1.742E-09 1.492E-09 SW 4.489E-08 2.566E-08 1.727E-08 9.893E-09 6.657E-09 4.889E-09 3.793E-09 3.056E-09 2.531E-09 2.140E-09 1.840E-09 WSW 4.678E-08 2.698E-08 1.827E-08 1.055E-08 7.141E-09 5.267E-09 4.101E-09 3.314E-09 2.751E-09 2.332E-09 2.009E-09 W 6.361E-08 3.664E-08 2.480E-08 1.431E-08 9.688E-09 7.147E-09 5.566E-09 4.500E-09 3.738E-09 3.170E-09 2.732E-09 NW 8.494E-08 4.886E-08 3.304E-08 1.906E-08 1.289E-08 9.508E-09 7.405E-09 5.987E-09 4.975E-09 4.220E-09 3.639E-09 z z N
1.090E-07 1.469E-07 6.323E-08 8.570E-08 4.301E-08 5.851E-08 2.500E-08 3.417E-08 1.700E-08 2.331E-08 1.259E-08 1.730E-08 9.836E-09 1.354E-08 7.972E-09 1.099E-08 6.638E-09 9.164E-09 5.641E-09 7.796E-09 4.872E-09 6.739E-09 z --I NNE 1.251E-07 7.285E-08 4.966E-08 2.893E-08 1.969E-08 1.458E-08 1.139E-08 9.223E-09 7.674E-09 6.516E-09 5.622E-09 6.410E-08 3.697E-08 2.504E-08 1.446E-08 9.786E-09 7.218E-09 5.620E-09 4.541E-09 3.771E-09 3.196E-09 2.754E-09 NE 6.206E-08 3.468E-08 2.298E-08 1.289E-08 8.558E-09 6.223E-09 4.791E-09 3.836E-09 3.160E-09 2.662E-09 2.280E-09 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 2.018E-09 1.730E-09 E
5.082E-08 2.822E-08 1.861E-08 1.037E-08 6.861E-09 4.973E-09 3.819E-09 3.051E-09 2.509E-09 2.110E-09 1.805E-09 ESE 4.776E-08 2.643E-08 1.739E-08 9.664E-09 6.380E-09 4.619E-09 3.544E-09 2.830E-09 2.327E-09 1.956E-09 1.673E-09 SE SE 5.413E-08 3.005E-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 1.943E-09 6.659E-08 3.706E-08 2.449E-08 1.369E-08 9.073E-09 6.588E-09 5.066E-09 4.053E-09 3.337E-09 2.808E-09 2.404E-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.
VERSION 2.0 RUN DATE: 970513 USNRC COMPUTER CODE - xOQDOQ, PALISADES XOQDOQ82 ***** USING 01/01/92 - 12/31/96 MET DATA P****
- GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING 2.260 DAY DECAY, UNDEPLEIED CHI/Q (SEC=/EMER CUBED) FOR EACH SE2MENT SEGM4ENT BOUNDARIES IN MILES FRUOM "TnH SITE 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 DIRECTION .5-1 FROM SITE 5.069E-09 3.115E-09 1.341E-07 8.248E-08 5.750E-08 2.842E-08 1. 064E-08 4.082E-09 2.516E-09 2.158E-09
- 1. 746E-09 S 7.791E-07 2.843E-07 4.537E-08 2.256E-08 8.515E-09 2.209E-07 1.049E-07 6.484E-08 4.922E-09 3.066E-09 2.145E-09 SSW 6.072E-07 5.205E-08 2.621E-08 1. 010E-08 2.473E-07 1.184E-07 7.387E-08 5.300E-09 3.324E-09 2.337E-09 0 SW 6.867E-07 5.412E-08 2.751E-08 1. 075E-08 2.516E-07 1.214E-07 7.636E-08 1.459E-08 7.192E-09 4.514E-09 3.176E-09 WSW 7.022E-07 1.040E-07 7.360E-08 3.737E-08 ,n W 9,645E-07 3.441E-07 1. 656E-07 1. 942E-08 9.569E-09 6.007E-09 4.229E-09 1.390E-07 9.832E-08 4.985E-08 5.651E-09 WNW 1.290E-06 4.611E-07 2.216E-07 6.441E-08 2.545E-08 1.267E-08 7.996E-09 5.775E-07 2.798E-07 1.768E-07 1. 258E-07 1.740E-08 1.102E-08 7.810E-09 NW 1.624E-06 2.373E-07 1.694E-07 8.722E-08 3.475E-08 m 2.154E-06 7.661E-07 3.736E-07 2.943E-08 1.466E-08 9.251E-09 6.528E-09 NNW 2.022E-07 1. 443E-07 7.415E-08 N 1.825E-06 6.524E-07 3.185E-07 1.473E-08 7.263E-09 4.556E-09 3.203E-09 V 1.663E-07 1. 046E-07 7.414E-08 3.770E-08 2.668E-09 NNE 9.500E-07 3.438E-07 3.557E-08 1.321E-08 6.272E-09 3.851E-09 0 3.664E-07 1.709E-07 1. 044E-07 7.244E-08 2.916E-09 2.023E-09 NE 1.015E-06 5.439E-08 2.673E-08 9.950E-09 4.739E-09 W) 2.761E-07 1.285E-07 7.840E-08 1. 064E-08 5.015E-09 3.064E-09 2.115E-09 m 0)
ENE 7.708E-07 8.600E-08 5,943E-08 2.897E-08 1.416E-07 E 8.574E-07 3.063E-07 2.922E-07 1.342E-07 8.115E-08 5.592E-08 2.715E-08 9.921E-09 4.659E-09 2.842E-09 3.286E-09 1.961E-09 2.274E-09 cm ESE 8.255E-07 3.086E-08 1. 135E-08 5.364E-09 *0 SE 9.335E-07 3.292E-07 1.514E-07 9.173E-08 6.332E-08 3.804E-08 1. 404E-08 6.642E-09 4.070E-09 2.815E-09 _(. z 1.850E-07 1.125E-07 7.783E-08 SSE 1.121E-06 4. 000E-07 OW
<. C Co 4 m
-A rl m
LCa) 0 z
z
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 CONTAINMENT 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 1.5232-07 1.083E-07 8.186E-08 6.456E-08 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 3.681E-06 1.134E-06 5.869E-07 3.789E-07 2.047E-07 1.334E-07 9.572E-08 7.291E-08 5.787E-08 4.7362-08 3.966E-08 WSW 3.842E-06 1.168E-06 5.980E-07 3.849E-07 2.078E-07 1.362E-07 9.823E-08 7.513E-08 5.985E-08 4.912E-08 4.125E-08 0 W 5.256E-06 1.606E-06 8.215E-07 5.278E-07 2.841E-07 1.859E-07 1.339E-07 1.023E-07 8.146E-08 6.682E-08 5,608E-08 WNW NW 6.982E-06 2.141E-06 1.100E-06 7.071E-07 3.806E-07 2.488E-07 1.791E-07 1.368E-07 1.088E-07 8.923E-08 7.486E-08 NNW 9.018E-06 2.715E-06 1.381E-06 8.848E-07 4.758E-07 3.128E-07 2.263E-07 1.736E-07 1.386E-07 1.140E-07 9.588E-08 N 1.217E-05 3.613E-06 1.827E-06 1.171E-06 6.312E-07 4.165E-07 3.024E-07 2.325E-07 1.860E-07 1.532E-07 1.291E-07 1.029E-05 3.055E-06 1.549E-06 9.954E-07 5.384E-07 3.554E-07 2.579E-07 1.983E-07 1.586E-07 1.307E-07 1.101E-07 m NNE 5.192E-06 1.567E-06 8.121E-07 5.248E-07 2.844E-07 1. 865E-07 1.345E-07 1.029E-07 8.196E-08 6.727E-08 5.649E-08 a NE 5.157E-06 1.646E-06 8.778E-07 5.664E-07 3.035E-07 1. 947E-07 1.378E-07 1.038E-07 8.162E-08 6.625E-08 5.509E-08 0 ENE 4.029E-06 1.259E-06 6.648E-07 4.273E-07 2.287E-07 1.466E-07 1.037E-07 7.804E-08 6.135E-08 4.978E-08 4.139E-08 U)
E 4.370E-06 1.397E-06 7.4105-07 4.756E-07 2.536E-07 1.620E-07 1.142E-07 8.576E-08 6.727E-08 5.448E-08 4.522E-08 m ESE 4.198E-06 1.350E-06 7.132E-07 4.557E-07 2.416E-07 1.538E-07 1.081E-07 8.103E-08 6.344E-08 5.130E-08 4.252E-08 rn SE 4.817E-06 1.532E-06 8.055E-07 5,136E-07 2.720E-07 1.733E-07 1.220E-07 9.152E-08 7.172E-08 5.805E-08 4.815E-08 _<. 0, m
CA SSE 5.719E-06 1.826E-06 9.691E-07 6.216E-07 3.309E-07 2.114E-07 1.492E-07 1.121E-07 8.798E-08 7.129E-08 5.920E-08 0
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
-A rn S 3.719E-08 1.987E-08 1.266E-08 6.668E-09 4.208E-09 2.931E-09 2.174E-09 1.683E-09 1.345E-09 1.102E-09 9.195E-10 SSW 2.941E-08 1.5802-08 1.011E-08 5.355E-09 3.392E-09 Vn 2.370E-09 1.762E-09 1.367E-09 1.094E-09 8.973E-10 7.499E-10 SW 3.384E-08 1.840E-08 1.187E-08 6.362E-09 4.065E-09 2.860E-09 2.138E-09 1.667E-09 1.340E-09 1. 103E-09 9.248E-10 0 WSW 3.527E-08 1.935E-08 1.256E-08 6.786E-09 4.361S-09 3.081E-09 2.311E-09 1.807E-09 1.457E-09 1.202E-09 1. 010E-09 z W 4.794E-08 2.626E-08 1.703E-08 9.195E-09 5.907E-09 4.173E-09 3.130E-09 2.448E-09 1.973E-09 1.628E-09 1.368E-09 WNW 6,396E-08 3.498E-08 2.266E-08 1.222E-08 7.839E-09 5.533E-09 4.148E-09 3.241E-09 2.612E-09 2.154E-09 1.810E-09 NW 8.212E-08 4.532E-08 2.954E-08 1.607E-08 1.037E-08 7.352E-09 5.531E-09 4.335E-09 3.502E-09 2.894E-09 2,436E-09 NNW 1.107E-07 6.143E-08 4.019E-08 2.196E-08 1.422E-08 1.011E-08 7.617E-09 5.980E-09 4.836E-09 4.002E-09 3.371E-09 z N 9.439E-08 5.231E-08 3.419E-08 1.866E-08 1.207E-08 8.564E-09 6.449E-09 5.058E-09 4.087E-09 3.379E-09 2.844E-09 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 1.379E-09 NE 4.671E-08 2.481E-08 1.574E-08 8.249E-09 5.194E-09 3.612E-09 2.676E-09 2.070E-09 1.653E-09 1.353E-09 1.129E-09 ENE 3.510E-08 1.867E-08 1.186E-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 1.276E-08 6.651E-09 4.172E-09 2.894E-09 2.139E-09 1.652E-09 1.317E-09 1. 077E-09 8.971E-10 ESE 3.596E-08 1.891E-08 1.192E-08 6.190E-09 3.875E-09 2.684E-09 1.981E-09 1.529E-09 1.219E-09 9.955E-10 8.292E-10 SE 4.075E-08 2.150E-08 1.359E-08 7.089E-09 4.453E-09 3.093E-09 2.288E-09 1.769E-09 1.413E-09 1. 156E-09 9.641E-10 SSE 5.014E-08 2.653E-08 1.679E-08 8.772E-09 5.515E-09 3.831E-09 2.836E-09 2.192E-09 1.750E-09 1.432E-09 1. 194E-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.HETERS) 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 CON1'AINMEZQT BUILDING 8.000 DAY DECAY, DEPLETED CHI/Q (SECIMETER CUBED) FOR EACH SEME21NT SBa4N 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 6.986E-07 2.434E-07 1.094E-07 6.492E-08 4.393E-08 2.052E-08 6.907E-09 2.969E-09 1. 695E-09 1.106E-09 SSW 5.445E-07 1.891E-07 8.560E-08 5.1053-08 3.468E-08 1.630E-08 5.540E-09 2. 399E-09 1.376E-09 9.011E-10 SW 6.1608-07 2.117E-07 9.664E-08 5.816E-08 3.979E-08 1.893E-08 6.565E-09 2.892E-09 1. 677E-09 1.107E-09 0
WSW 6.299E-07 2.153E-07 9.911E-08 6.013E-08 4.137E-08 1. 987E-08 6.991E-09 3.114E-09 1.818E-09 1.206E-09 W 8.653E-07 2.946E-07 1.351E-07 8.184E-08 5.625E-08 2.697E-08 9.475E-09 4.218E-09 2.462E-09 1.634E-09 WNW 1.157E-06 3.946E-07 1.808E-07 1. 094E-07 7.508E-08 3.594E-08 1.259E-08 5.594E-09 3.261E-09 2.162E-09 NW 1.457E-06 4.943E-07 2.283E-07 1. 392E-07 9.614E-08 4.648E-08 1.653E-08 7.429E-09 4.359E-09 2.904E-09 m NNW 1.932E-06 6.557E-07 3.049E-07 1.868E-07 1.295E-07 6.295E-08 2.257E-08 1. 021E-08 6.012E-09 4.016E-09 N 1.637E-06 5.586E-07 2.601E-07 1.593E-07 1.104E-07 5.361E-08 1.918E-08 8.652E-09 5.085E-09 3.391E-09 a NNE 8.521E-07 2.943E-07 1.357E-07 8.234E-08 5.665E-08 2.721E-08 9.569E-09 4.260E-09 2.485E-09 1.648E-09 0 NE 9.1O1E-07 3.136E-07 1.394E-07 8.210E-08 5.529E-08 2.565E-08 8.556E-09 3.659E-09 2.084E-09 1.359E-09 Un ENE 6.913E-07 2.364E-07 1. 049H-07 6.171E-08 4.155E-08 1.930E-08 6.461E-09 2.775E-09 1.585E-09 1.036E-09 m E 7.689E-07 2.622E-07 1. 156E-07 6.768E-08 4.539E-08 2.091E-08 6.908E-09 2.932E-09 1.663E-09 1.081E-09 -I CD C) r ESE 7.403E-07 2.502E-07 1.0953-07 6.384E-08 4.269E-08 1.959E-08 6.434E-09 2.721E-09 1. 540E-09 1. 000E-09 m SE 8.371E-07 2.818E-07 1.235E-07 7.217E-08 4.834E-08 2.226E-08 7.362E-09 3.134E-09 1. 782E-09 1.161E-09 03 (0 SSE 1.005E-06 3.424E-07 1. 510E-07 8.852E-08 5.943E-08 2.745E-08 9.106E-09 3. 882E-09 2.208E-09 1.438E-09 r m 0 m
-a 0
2 2
C
USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 970513 PALISADES XOQDOQ82 ***** USING I 01/01/92 - 12/31/96 MET DATA
- GROUND LEVEL RELEASE - TOP OF CONTAIN4MET BUILDING RELATIVE DEPOSITION PER UNIT AREA (M**-2) AT FIXED POINTS BY DONWIND SECTORS 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-08 8.794E-09 4.515E-09 2.772E-09 1.382E-09 8.383E-10 5.668E-10 4.107E-10 3.123E-10 2.460E-10 1.992E-10 SSW 1.731E-08 5.852E-09 3.005E-09 1.845E-09 9.198E-10 5.579E-10 3.772E-10 2.733E-10 2.078E-10 1.637E-10 1.325E-10 SW 1.866E-08 6.309E-09 3.239E-09 1.989E-09 9.916E-10 6.014E-10 4.066E-10 2.946E-10 2.240E-10 1.765E-10 1.429E-10 WSW 1.829E-08 6.183E-09 3.175E-09 1.949E-09 9.719E-10 5.894E-10 3.985E-10 2.888E-10 2.196E-10 1.730E-10 1.401E-10 W 2.673E-08 9.040E-09 4.641E-09 2.850E-09 1.421E-09 8.618E-10 5.826E-10 4.222E-10 3.210E-10 2.529E-10 2.048E-10 34W 4.142E-08 1.401E-08 7.191E-09 4.416E-09 2.201E-09 1.335E-09 9.027E-10 6.541E-10 4.974E-10 3.919E-10 3.172E-10 0 NW 4.847E-08 1.639E-08 8.416E-09 5.168E-09 2.576E-09 1.563E-09 1.056E-09 7.656E-10 5.821E-10 4.586E-10 3.713E-10 NNW 5.897E-08 1.994E-08 1.024E-08 6.287E-09 3.135E-09 1.901E-09 1.285E-09 9.314E-10 7.082E-10 5.580E-10 4.517E-10 ,n N 4.172E-08 1.411E-08 7.244E-09 4.448E-09 2.218E-09 1.345E-09 9.093E-10 6.589E-10 5.010E-10 3.947E-10 3.196E-10 rn NNE 2.423E-08 8.194E-09 4.207E-09 2.583E-09 1.288E-09 7.811E-10 5.281E-10 3.827E-10 2.910E-10 2.292E-10 1.856E-10 NE 4.208E-08 M 1.423E-08 7.306E-09 4.486E-09 2.237E-09 1.356E-09 9.171E-10 6.646E-10 5.053E-10 3.981E-10 3.223E-10 EE 3,387E-08 1.145E-08 5.881E-09 3.611E-09 1.800E-09 1.092E-09 7.382E-10 5.349E-10 4.067E-10 3.204E-10 2.594E-10 s 3.926E-08 1.328E-08 6.816E-09 4.185E-09 2.087E-09 1.266E-09 8.556E-10 6.200E-10 4.715E-10 3.714E-10 3.007E-10 0 ESE 4.148E-08 1.403E-08 7.202E-09 4.423E-09 2.205E-09 1.337E-09 9.041E-10 6.552E-10 4.982E-10 3.925E-10 3.177E-10 SE 4.919E-08 1.663E-08 8.540E-09 5.244E-09 2.614E-09 1.586E-09 1.072E-09 7.769E-10 5.907E-10 4.654E-10 3.768E-10 SSE 5.133E-08 1.736E-08 8.913E-09 5.473E-09 2.728E-09 1.655F-09 1.119E-09 8.107E-10 6.165E-10 4.857E-10 3.932E-10 m Y) 40 DIRECTION DISTANCES IN MILES Co z 0 FROM SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 -35.00 40.00 45.00 50.00 0 c SSW S 1.648E-10 1.096E-10 8.074E-11 5.373E-11 5.066E-11 3.371E-11 2.561E-11 1.704E-11 1.550E-11 1.031E-11 1.039E-11 6.915E-12 7.446E-12 4.955E-12 5.591E-12 3.721E-12 4.347E-12 2.893E-12 3.473E-12 2.834E-12 m
-A 0. V)0.
2.311E-12 1.886E-12 r,
-J SW WSW 1.182E-10 1.159E-10 5.792E-11 5.677E-11 3.634E-11 3.562E-11 1.837E-11 1.801E-11 1.112E-11 1.090E-11 7.455E-12 7.307E-12 5.342E-12 5.236E-12 4.011E-12 3.931E-12 3.119E-12 3.057E-12 2.491E-12 2.442E-12 2.033E-12 1.993E-12 i4 z m W 1.694E-10 8.300E-11 5.208E-11 2.632E-11 1.593E-11 1. 068E-11 7.654E-12 5.748E-12 4.469E-12 3.570E-12 2.914E-12 WNW 2.624E-10 1.286E-10 8.069E-11 4.078E-11 2.468E-11 1.655H-11 1.186E-11 8.905E-12 6.924E-12 5.531E-12 4.514E-12 NW 3.071E-10 1.505E-10 9.443E-11 4.773E-11 2.889E-11 1.937E-11 1.388E-11 1.042E-11 8.103E-12 6.473E-12 5.283E-12 3mW 3.736E-10 1.831E-10 1.149E-10 5.807E-11 3.515E-11 2.357E-11 1.689E-11 1.268E-11 9.859E-12 7.875E-12 6.428E-12 N 2.643E-10 1.295E-10 8.128E-11 4.108E-11 2.487E-11 1.667E-11 1.195E-11 8.970E-12 6.975E-12 5.571E-12 4.547E-12 NNE 1.535E-10 7.523E-11 4.720E-11 2.386E-11 1.444E-11 9.682E-12 6.938E-12 5.210E-12 4.051E-12 3.236E-12 2.641E-12 2~ -q NE 2.666E-10 1.306E-10 8.198E-11 4.143E-11 2.508E-11 1. 681E-11 1.205E-11 9.047E-12 7.034E-12 5.619E-12 4.586E-12 2.146E-10 1.052E-10 6.598E-11 3.335E-11 2.019E-11 1.353E-11 9.698E-12 7.282E-12 5.662E-12 4.523E-12 3.692E-12 E 2.487E-10 1.219E-10 7.648E-11 3.866E-11 2.340E-11 1.569E-11 1.124E-11 8.441E-12 6.563E-12 5.242E-12 4.279E-12 ESE 2.628E-10 1.288E-10 8.081E-11 4.085E-11 2.472E-11 1. 658E-11 1.188E-11 8.919E-12 6.935E-12 5.539E-12 4.521E-12 SE 3.117E-10 1.527E-10 9.583E-11 4.844E-11 2.932E-11 1.966E-11 1.408E-11 1.058E-11 8.223E-12 6.569E-12 5.361E-12 SSE 3.2522-10 1.594E-10 1.000E-10 5.055E-11 3.059E-11 2.051E-11 1.470E-11 1.104E-11 8.581E-12 6.855E-12 5.595E-12
USNRC COMPUTER CODE - XOQWOQ, VERSION 2.0 RUN DATE: 970513
-**** PALISADES XOQDOQ82 ***** USING 01/01/92 - 12/31/96 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING
- ** ************** ***
- RELATIVE DEPOSITION PER UNIT AREA (M**-2) BY DOWNWIND SECTORS * *** *** ** ********** ****
- SEGMENT BOUNDARIES IN MILES DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 4.691E-09 1.4449E-09 5.768E-10 3.152E-10 2.003E-10 8.604E-11 2.668E-11' 1.057E-11 5.647E-12 3.495E-12 SSW 3.122E-09 9.645E-10 3.838E-10 2.097E-10 1.333E-10 5.726E-11 1.776E-11 7.037E-12 3.758E-12 2.326E-12 SW 3.366E-09 1.040E-09 4.138E-10 2.261E-10 1.437E-10 6.173E-11 1. 914E-11 7.587E-12 4.051E-12 2.508E-12 WSW 3.299E-09 1.019E-09 4.055E-10 2.216E-10 1.409E-10 6.050E-11 1.876E-11 7.436E-12 3.971E-12 2.458E-12 0 In W 4.823E-09 1.490E-09 5.929E-10 3.240E-10 2.059E-10 8.845E-11 2.743E-11 1.087E-11 5.805E-12 3.593E-12 NW 7.472E-09 2.308E-09 9.186E-10 5.020E-10 3.190E-10 1. 370E-10 4.249E-11 1.684E-11 8. 994E-12 5.567E-12 In 8.745E-09 2.702E-09 1.075E-09 5.875E-10 3.734E-10 1.604E-10 4.974E-11 1.971E-11 1. 053E-11 6.516E-12 1.064E-08 3.287E-09 1.3083-09 7.147E-10 4.543E-10 1.951E-10 6.051E-11 2.398E-11 1.281E-11 7.927E-12 N
7.527E-09 2.325E-09 9.253E-10 5.057E-10 3.214E-10 1.380E-10 4.281E-11 1.697E-11 9.060E-12 5.608E-12 m NNE NE 4.371E-09 1.351E-09 5.374E-10 2.937E-10 1. 866E-10 8.017E-11 2.4863-11 9.853E-12 5.262E-12 3.257E-12 V NNE 7.591E-09 2.345E-09 9.333E-10 5.100E-10 3.241E-10 1.392E-10 4.317E-11 1.711E-11 9.138E-12 5.656E-12 0 NE 6. 110E-09 1. 888E-09 7.512E-10 4.105E-10 2.609E-10 1.121E-10 3.475E-11 1.377E-11 7.355E-12 4.552E-12 Ui) 7.082E-09 2.188E-09 8.707E-10 4.758E-10 3.024E-10 1.299E-10 4.028E-11 1.596E-11 8. 525E-12 5.277E-12 m ESE 7.484E-09 2.312E-09 9.200E-10 5.028E-10 3.195E-10 1.373E-10 4.256E-lI 1.687E-11 9.008E-12 5.576E-12 SE 8.874E-09 2.742E-09 1.091E-09 5.962E-10 3.789E-10 1.628E-10 5.047E-11 2.000E-11 1.068E-11 6.612E-12 0 SSE 9.261E-09 2.861E-09 1.139E-09 6.222E-10 3.954E-10 1.699E-10 5.267E-11 2.088E-11 1.115E-11 6.900E-12 m 4:
-- A m S..
Co VENT AND BUILDING PARAMETERS:
-A 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.SBC.AREA (SQ.MEnRS) 2000.0 z HEAT SMISSION RATE (CAL/SEC) 0.0 0
ALL GROUND LEVEL REIEASES. z
-q z
c r,
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 CONTAINMENT BUILDING SPECIFIC POINTS OF INTEREST RELEASE TYPE OF DIRECTION DISTANCE X/Q X/Q X/Q D/Q ID LOCATION FROM SITE (MILES) (METERS) (SEC/CUB.METER) (SEC/CUB.METER) (SEC/CUB.METM) (PER SQ.METER)
NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLETED UNDEPLETED DEPLETED SITE BOUNDARY NNE 0.50 805. 1.72E-06 1.71E-06 1.57E-06 8.19E-09 SITE BOUNDARY NE 0.65 1046. 1.22E-06 1.22E-06 1.10E-06 9.30E-09 0 SITE BOUNDARY ENE 0.87 1400. 5.99E-07 5.98E-07 5.29E-07 4.58E-09 SITE BOUNDARY E 0.82 1320. 7.28E-07 C,n 7.27E-07 6.45E-07 5.86E-09 SITE BOUNDARY ESE 0.76 1223. 7.85E-07 7.83E-07 6.98E-07 7.04E-09 SITE BOUNDARY SE 0.63 1014. 1.18E-06 1.18E-06 1.06E-06 1.14E-08 SITE BOUNDARY SSE 0.48 772. 2.13E-06 2.12E-06 1.95E-06 1.86E-08 m
SITE BOUNDARY S 0.42 676. 1.78E-06 1.78E-06 1.64E-06 1.16E-08 a SITE BOUNDARY SSW 0.48 772. 1.16E-06 1.15E-06 1.06E-06 6.26E-09 0 GARDEN NNE 1.60 2575. 3.06E-07 3.04E-07 2.58E-07 1.15E-09 CiA GARDEN NE 1.20 1931. 4.96E-07 4.95E-07 4.28E-07 3.29E-09 m rn GARDEN ENE 2.70 4345. 1.15E-07 1.14E-07 9.20E-08 6.45E-10 _S.
GARDEN E 2.20 3541. 1.70E-07 1.69E-07 1.40E-07 1.07E-09 41h GARDEN ESE 2.30 3701. 1.51E-07 1.50E-07 1.23E-07 1.05E-09 1i GARDEN SE 1.80 2897. 2.45E-07 2.44E-07 2.04E-07 1.91E-09 m 0 GARDEN SSE 1.60 2575. 3.55E-07 3.53E-07 2.99E-07 2.44E-09 0,
GARDEN S 1.50 2414. 2.78E-07 2.77E-07 2.36E-07 1.38E-09 ~CA) m BEEF COW NE 2.90 4667. 1.38E-07 1.36E-07 1.09E-07 7.06E-10 BEEF COW ENE 4.00 6437. 6.51E-08 6.43E-08 4.98E-08 3.20E-10 BEEF COW E 3.50 5633. 8.64E-08 8.56E-08 6.73E-08 4.71E-10 BEEF COW ESE 4.00 6437. 6.70E-08 6.63E-08 5.13E-08 3.93E-10 BEEP COW SSE 3.00 4828. 1.41E-07 1.40E-07 1.12E-07 8.11E-10 DAIRY COW SE 4.30 6920. 6.83E-08 6.75E-08 5.18E-08 4.09E-10 GOAT NE 3.20 5150. 1.19E-07 1.18E-07 9.39E-08 5.93E-10 GOAT ESE 3.00 4828. 1.02E-07 1.01E-07 8.10E-08 6.55E-10 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 CONTAINMENT BUILDING SPECIFIC POINTS OF INTEREST RELEASE TYPE OF DIRECTION DISTANCE X/Q X/Q X/Q D/Q ID LOCATION FROM SITE (MILES) (METERS) (SEC/CUB.ME*ER) (SEC/CUB.METER) (SEC/CUB.METER) (PER SQ.HETER)
NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLETED UNDEPLETED DtPLETED 0.50 805. 1.72E-06 1.71E-06 1.57E-06 8.19E-09 0 A SITE BOUNDARY NNE 9.30E-09 A SITE BOUNDARY NE 0.65 1046. 1.22E-06 1.22E-06 1.10E-06 ENE 0.87 1400. 5.99E-07 5.98E-07 5.29E-07 4.58E-09 A SITE BOUNDARY 5.86E-09 -n A SITE BOUNDARY E 0.82 1320. 7.28E-07 7.27E-07 6.45E-07 ESE 0.76 1223. 7.85E-07 7.83E-07 6.98E-07 7.04E-09 A SITE BOUNDARY A SITE BOUNDARY SE 0.63 1014. 1.18E-06 1.18E-06 1.06E-06 1.14E-08 m SSE 0.48 772. 2.13E-06 2.12E-06 1.95E-06 1.86E-08 A SITE BOUNDARY 1.16E-08 S 0.42 676. 1.78E-06 1.78E-06 1.64E-06 0 A SITE BOUNDARY c; SSW 0.48 772. 1.16E-06 1.15E-06 1.06E-06 6.26E-09 A SITE BOUNDARY 2.20E-09 m A RESIDENCE NNE 1.10 1770. 5.23E-07 5.21E-07 4.55E-07 rn NE 1.20 1931. 4.96E-07 4.95E-07 4.28E-07 3.29E-09 -I A RESIDENCE ENE 1.30 2092. 3.33E-07 3.31E-07 2.85E-07 2.30E-09 A RESIDENCE 4.19E-09 A RESIDENCE E 1.00 1609. 5.44E-07 5.42E-07 4.76E-07 m
ESE 1.00 1609. 5.21E-07 5.20E-07 4.56E-07 4.42E-09 (A) A RESIDENCE SE 5.86E-07 5.14E-07 5.25E-09 U, A RESIDENCE 1.00 1609. 5.87E-07 0.
SSE 0.70 1127. 1.21E-06 1.20E-06 1.08E-06 1.00E-08 A RESIDENCE S 0.50 805. 1.38E-06 1.38E-06 1.26E-06 8.79E-09 A RESIDENCE SSW 0.70 1127. 6.50E-07 6.49E-07 5.81E-07 3.37E-09 A RESIDENCE NE 2.90 4667. 1.38E-07 1.36E-07 1.09E-07 7.06E-10 0 A
A BEEF COW BEEF COW 4.00 6437. 6.51E-08 6.43E-08 4.98E-08 3.20E-10 z E 3.50 5633. 8.64E-08 8.56E-08 6.73E-08 4.71E-10 A BEEF COW ESE 4.00 6437. 6.70E-08 6.63E-08 5.13E-08 3.93E-10 A BEEF COW A BEEF COW SSE 3.00 4828. 1.41E-07 1.40E-07 1.12E-07 8.11E-10 4.09E-10 z
A DAIRY COW SE 4.30 6920. 6.83E-08 6.75E-08 5.18E-08 c
3.20 5150. 1.19E-07 1.18E-07 9.39E-08 5.93E-10 A GOAT ESE 3.00 4828. 1.02E-07 1.01E-07 8.10E-08 6.55E-10 A GOAT VENT AND BUILDING PARAMETEERS:
RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 0.00 BUILDING HEIGHT (METERS) 58.1 DIAMETER (METERS)
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 16 TABLE 1.4 2000 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 NNE 1.1 ml 1.8 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 ml 3.3 mi 1.8 mi >5 mi >5 mi E 1.0 mi 2.1 mi 3.5 mi >5 mi >5 mi ESE 1.0 mi *1.0 mi *4.0 mi >5 ml "*2.0 mi SE 1.0 mi *1.0 mi 2.2 mi 4.3 mi "*2.0 mi SSE 0.7 ml 1.6 mi >5 mi >5 mi >5 mi S 0.5 ml 4.0 mi >5 mi >5 mi 4.7 mi SSW 0.7 ml 4.9 mi >5 mi >5 mi >5 mi I *Note: Garden and Farm bisected by ESE/SE sector line.
44
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.4a 2000 PALISADES LAND USE CENSUS Critical Receptor Items Distance Sector Miles Location/Description Item *X/Q (sec/m3" 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 ENE 1.8 22595 76th Ave .3 miles N of Beef 2.14E-07 24th, East side of road Cattle SE 4.3 72401 36th Ave Dairy 6.83E-08 Cow SE 2.0 SE corner of 30th Goat 2.1 OE-07 and 76th
- Based on Palisades 5-year composite meteorological data, 1992 - 1996.
45
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.5 DOSE FACTORS FOR R SUBMERSION IN NOBLE GASES*
DOSE FACTORS F 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-1 31 m 9.15(+1) 1.56(+2) 4.76(+2) 1.11(+3)
Xe-1 33m 2.51(+2) 3.27(+2) 9.94(+2) 1.48(+3)
Xe- 133 2.94(+2) 3.53(+2) 3.06(+2) 1.05(+3)
Xe-1 35m 3.12(+3) 3.36(+3) 7.11(+2) 7.39(+3)
Xe-1 35 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-1 38 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 /Ci/m3
- 2. mrad/y per pCi/m3
- 3. 1.17(+3) = 1.17x 103
- 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).
46
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.6 STABLE ELEMENT TRANSFER DATA Fm - MILK (COW) Fm - MILK (GOAT) Ff - MEAT Biv ELEMENT (DAYS/L) (DAYS/L) (DAYS/KG) (VEG/SOIL)
H 1.OE-02 1.7E-01 1.2E-02 4.8E-00 C 1.2E-02 1.OE-01 3.1 E-02 5.5E-00 Na 4.OE-02 4.OE-02 3.OE-02 5.2E-02 P 2.5E-02 2.5E-01 4.6E-02 1.1E-OO Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.OE-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.OE-02 6.6E-04 Co 1.OE-03 1.OE-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.OE-02 4.OE-O1 Rb 3.OE-02 3.OE-02 3.1 E-02 1.3E-01 Sr 8.OE-04 1.4E-02 6.OE-04 1.7E-02 Y 1.OE-05 1.OE-05 4.6E-03 2.6E-03 Zr 5.OE-06 5.OE-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.OE-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.OE-01 2.5E-01 Ru 1.0E-06 1.OE-06 4.OE-01 5.OE-02 Rh 1.OE-02 1.OE-02 1.5E-03 1.3E +01 Ag 5.OE-02 5.OE-02 1.7E-02 1.5E-01 Te 1.OE-03 1.OE-03 7.7E-02 1.3E-00 I 6.OE-03 6.OE-02 2.9E-03 2.OE-02 Cs 1.2E-02 3.OE-01 4.OE-03 1.OE-02 Ba 4.OE-04 4.OE-04 3.2E-03 5.OE-03 La 5.OE-06 5.OE-06 2.OE-04 2.5E-03 Ce 1.OE-04 1.OE-04 1.2E-03 2.5E-03 Pr 5.OE-06 5.0E-06 4.7E-03 2.5E-03 Nd 5.OE-06 5.OE-06 3.3E-03 2.4E-03 W 5.0E-04 5.OE-04 1.3E-03 1.8E-02 Np 5.OE-06 5.OE-06 2.OE-04 2.5E-03 47
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 BE1O 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. 6.1OE-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.OOE-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. 1.10E-09 1.58E-10 0. 7.86E-1 0 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 C058 0. 8.71 E-07 1.30E-06 0. 0. 5.55E-04 7.95E-06 C060 0. 5.73E-06 8.41 E-06 0. 0. 3.22E-03 2.28E-05 N159 1.81 E-05 5.44E-06 3.1OE-06 0. 0. 5.48E-05 6.34E-07 N163 2.42E-04 1.46E-05 8.29E-06 0. 0. 1.49E-04 1.73E-06 N165 1.71 E-09 2.03E- 10 8.79E-1 1 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-1 1 6.91 E-11 5.13E-1 2 0. 2.87E-1 1 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 SR90+D 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05 SR91 + D 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05 SR92 + D 7.50E-09 0. 2.79E-10 0. 0. 1.70E-05 1.OOE-04 Includes a 50% increase to account for percutaneous transpiration.
48
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 GI-LLI Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 Y91M+D 2.91 E-10 0. 9.90E-1 2 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-1 0 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 6.18 E-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.OOE-04 NB93M 1.38E-04 3.59E-05 1.15 E-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-1 1 1.88E-1 1 0. 4.07E-1 1 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-1 1 0. 2.22E-1 1 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-1 4 5.88E-1 4 5.80E-1 3 0. 6.99E-13 4.17E-07 6.03E-07 RU1O3+D 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15 E-05 RU105+D 8.74E-10 0. 2.93E-10 0. 6.42E-10 1 .12E-05 3.46E-05 RU106+D 6.20E-05 0. 7.77E-06 0. 7.61 E-05 8.26E-03 1 .17E-04 RH105 8.26E-09 5.41 E-09 3.63E-09 0. 1.50E-08 2.08E-05 1.37E-05 PD107 0. 4.92E-07 4.11 E-08 0. 2.75E-06 6.34E-05 7.33E-07 PD109 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 AGi 11 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 SN 123 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.OOE-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 2.71 E-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 SB1127 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 6.81 E-10 3.49E-1 0 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-1 1 2.48E-1 1 1.34E-1 1 4.82E-1 1 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-1 1 5.87E-1 2 3.57E- 12 1.13E-11 2.85E-1 1 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-O5 TE133M+D 6.13E-11 3.59E-1 1 2.74E-1 1 5.52E-1 1 1.72E-10 3.92E-06 1.59E-05 TE134+D 3.18E-1 1 2.04E- 11 1.68E-11 2.91E-11 9.59E-1 1 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 1131 +D 2.71 E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0. 7.56E-07 49
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IrN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-04 2.82E-06 0. 1.36E-06 1133+D 9.46E-06 1.37E-05 4.OOE-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 2.1OE-07 1.11 E-07 0. 8.50E-08 2.OOE-08 1.16 E-07 CS134 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07 CS135 1.OOE-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 CS 138 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 BA139 1.06E-09 7.03E- 13 3.07E-1 1 0. 4.23E-1 3 4.25E-06 3.64E-05 BA140+D 4.OOE-05 4.OOE-08 2.07E-06 0. 9.59E-09 1 .14E-03 2.74E-05 BA141 +D 1 .12E-10 7.70E-14 3.55E-1 2 0. 4.64E-1 4 2.12E-06 3.39E-06 BA142+D 2.84E-1 1 2.36E-14 1.40E- 12 0. 1.36E-14 1.11 E-06 4.95E-07 LAl 40 3.61 E-07 1.43E-07 3.68E-08 0. 0. 1.20E-04 6.06E-05 LA1 41 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-1 1 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.OOE-05 3.74E-06 4.99E-07 0. 1.41 E-06 3.09E-04 2.66E-05 PR144 3.42E-1 1 1.32E-1 1 1.72E-12 0. 4.80E-1 2 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 PM 147 3.91 E-04 3.07E-05 1.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PM148M-+ D 5.OOE-05 1.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05 PM 148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05 PM 149 3.1OE-07 4.08E-08 1.78E-08 0. 4.96E-08 6.50E-05 3.01 E-05 PM151 7.52E-08 1 .1OE-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 1.1 2E-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 W185 1.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.1 2E-05 W187 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05 50
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 GI-LLI PB210+D 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05 B1210+D 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.OOE-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-00 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+00 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+00 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 .1OE-02 2.86E-02 0. 5.61 E-02 4.65E+00 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+00 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+00 3.87E-05 TH232+D 3.86E+00 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+00 3.29E-05 TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 1.62E-03 7.40E-05 PA231 +D 9.1OE+00 3.OOE-01 3.62E-01 0. 1.62E+00 3.85E-01 4.61 E-05 PA233 6.84E-06 1.32E-06 1.19E-06 0. 3.68E-06 2.19E-04 9.04E-06 U232+D 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+00 4.36E-05 U233+D 5.44E-02 0. 3.83E-03 0. 1.09E-02 3.56E-01 4.03E-05 U234 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 3.71 E-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+00 2.32E-01 1.26E-01 0. 7.69E-01 3.49E-01 5.1OE-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+00 6.33E-01 1.27E-01 0. 4.64E-01 9.03E-01 4.69E-05 PU239 5.50E + 00 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 PU240 6.49E + 00 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. 1.15 E-02 7.62E-04 8.97E-07 PU242 5.09E + 00 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05 PU244 5.95E+00 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+00 8.44E-01 1. 31 E-01 0. 7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+00 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01 E-05 AM243 1.82E+00 8.10E-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 5.1OE-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+00 7.04E-01 8.89E-02 0. 3.21 E-01 4.08E-01 4.86E-05 CM245 2.26E+00 8.80E-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 CM246 2.24E + 00 8.79E-01 1.36E-01 0. 5.23E-01 3.99E-01 4.45E-05 CM247 + D 2.18E+00 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05 CM248 1.82E+01 7.12E+00 1 .1OE+00 0. 4.24E + 00 3.23E + 00 9.43E-04 CF252 4.26E+00 0. 1.01 E-01 0. 0. 1.37E+00 1.85E-04 51
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 BE1O 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 2.31E-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-1 1 0. 4.52E-10 3.55E-06 3.33E-05 FE55 1.28E-05 6.80E-06 2.1OE-06 0. 0. 3.OOE-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 C060 0. 3.55E-06 6.12E-06 0. 0. 1.91 E-03 2.60E-05 N159 1.66E-05 4.67E-06 2.83E-06 0. 0. 2.73E-05 6.29E-07 N163 2.22E-04 1.25E-05 7.56E-06 0. 0. 7.43E-05 1.71 E-06 N165 8.08E-1 0 7.99E-1 1 4.44E-1 1 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 1.15 E-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 2.71 E-05 ZN69 1.81E-11 2.61E-11 2.41E-12 0. 1.58E-1 1 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. 5.11 E-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 SR92+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.
52
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 1.11 E-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 Y91M+D 1.37E-10 0. 4.98E-1 2 0. 0. 7.60E-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 0. 0. 7.1OE-04 4.97E-05 Y92 5.50E-09 0. 1.57E-1 0 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.OOE-04 7.1OE-04 1.47E-05 ZR95 + D 5.13E-05 1.13E-05 1.OOE-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.OOE-05 NB97 1.16E-10 2.08E-1 1 9.74E-12 0. 2.31 E-1 1 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 1.15 E-08 0. 1.06E-07 3.66E-05 3.42E-05 TC99M 4.81E-13 9.41E-13 1.56E-1 1 0. 1.37E-1 1 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-1 3 0. 3.92E-1 3 1.58E-07 4.41 E-09 RU1O3+D 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 1.21E-05 RU105+D 4.13E-10 0. 1.50E-10 0. 3.63E-1 0 4.30E-06 2.69E-05 RU1O6+D 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1 .16E-04 RH105 3.91 E-09 2.1OE-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05 PD107 0. 2.65E-07 2.51 E-08 0. 1.97E-06 3.16E-05 7.26E-07 PD 109 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 AGi 11 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. 5.13 E-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.OOE-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.OOE-08 0. 2.86E-04 5.67E-05 SB1127 1.36E-07 2.09E-09 4.70E-08 1.51 E-09 0. 6.17E-05 3.82E-05 TE1 25M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TE1 27M + D 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 TE1 27 7.49E- 10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71 E-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 TE1 29 2.64E-1 1 9.45E- 12 6.44E-12 1.93E-1 1 6.94E-1 1 7.93E-07 6.89E-06 TE1 31 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-1 2 2.28E-1 2 1.78E-12 4.59E-12 1.59E-1 1 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-1 1 1.51 E-1 1 1.50E-1 1 2.32E-1 1 1.01E-10 1.60E-06 4.77E-06 TE134+D 1.53E-1 1 8.81 E-1 2 9.40E-1 2 1.24E-1 1 5.71 E-1 1 1.23E-06 4.87E-07 1129 1.05E-05 6.40E-06 5.71E-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 1131 +D 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07 53
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 5.72E-07 1 .1OE-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07 1132 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0. 1.48E-06 1133+D 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0. 2.58E-07 1134 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0. 1.20E-06 1135+D
- 0. 0. 0. 0. 0. 3.30E-09 0.
XE131M
- 0. 0. 0. 0. 0. 4.36E-09 0.
XE133M
- 0. 0. 0. 0. 0. 3.66E-09 0.
XE133
- 0. 0. 0. 0. 0. 4.48E-09 0.
XE135M
- 0. 0. 0. 0. 0. 9.09E-09 0.
XE135
- 0. 0. 0. 0. 0. 4.07E-08 0.
XE137 XE138+D 0. 0. 0. 0. 0. 5.17E-08 0.
6.33E-08 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08 CS134M+D 1.76E-04 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06 CS134 6.23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07 CS135 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.13E-06 CS136 CS137+D 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81 E-05 9.78E-07 1.71 E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E-08 CS138 1.09E-07 1.15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7.23E-1 2 CS139+D 4.98E-10 2.66E-1 3 1.45E-1 1 0. 2.33E-1 3 1.56E-06 1.56E-05 BA139 2.OOE-05 1.75E-08 1.17E-06 0. 5.71 E-09 4.71 E-04 2.75E-05 BA140+ D 5.29E-1 1 2.95E-1 4 1.72E-12 0. 2.56E-1 4 7.89E-07 7.44E-08 BA141 +D 1.35E-1 1 9.73E-15 7.54E-13 0. 7.87E-1 5 4.44E-07 7.41 E-10 BA142+D LA1 40 1.74E-07 6.08E-08 2.04E-08 0. 0. 4.94E-05 6.1OE-05 2.28E-09 5.31 E- 10 1.15 E- 10 0. 0. 4.48E-06 4.37E-05 LA141 3.50E-1 0 1.11 E-10 3.49E-1 1 0. 0. 2.35E-06 2.05E-05 LA142 1.06E-05 5.28E-06 7.83E-07 0. 2.31 E-06 1.47E-04 1.53E-05 CE141 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05 CE143+D 1.83E-03 5.72E-04 9.77E-05 0. 3.17E-04 3.23E-03 1.05E-04 CE144+D PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11 E-07 1.17 E-04 2.63E-05 1.61 E-1 1 4.99E-1 2 8.1OE-13 0. 2.64E-1 2 4.23E-07 5.32E-08 PR144 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-05 ND147+D 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 PM147 3.31 E-05 6.55E-06 6.55E-06 0. 9.74E-06 5.72E-04 3.58E-05 PM148M+D PM148 1.61 E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.01 E-05 1.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 PM 149 PM151 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 1.24E-05 2.50E-05 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM151 7.24E-08 4.51 E-08 4.35E-09 0. 1.37E-08 1.37E-05 1.87E-05 SM1 53 EU 152 7.42E-04 1.37E-04 1.61 E-04 0. 5.73E-04 9.OOE-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 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05 EU156 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 TB160 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. 5.71 E-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 W185 W187 4.41 E-09 2.61 E-09 1.17E-09 0. 0. 1.11 E-05 2.46E-05 54
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
CHILD INHALA TION DOSE ( MOMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 8.03E-02 1.85E-02 3.18E-03 0. 6.31 E-02 8.74E-02 3.75E-05 B1210+D 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.OOE-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 2.67E-04 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. 5.41 E-02 3.34E+00 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+00 3.27E-05 TH234 6.94E-06 3.07E-07 2.OOE-07 0. 1.62E-06 6.31 E-04 7.32E-05 PA231 + D 8.62E+00 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 U232+D 2.19E-01 0. 1.56E-02 0. 1.67E-02 7.42E-01 4.33E-05 U233+D 4.64E-02 0. 2.82E-03 0. 7.62E-03 1.77E-01 4.OOE-05 U234 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+00 2.21 E-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+00 6.05E-01 1.21 E-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. 1.1OE-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+00 7.10E-01 1.41 E-01 0. 5.27E-01 6.30E-01 6.20E-05 AM241 1.74E+00 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05 AM242M 1.79E+00 7.65E-01 1.27E-01 0. 7.71 E-01 8.14E-02 5.96E-05 AM243 1.72E+00 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+00 7.33E-01 9.95E-02 0. 3.74E-01 2.10E-01 4.98E-05 CM244 1.33E +00 6.48E-01 8.31 E-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 6.61 E +00 1.04E + 00 0. 4.08E+00 1.61 E + 00 9.35E-04 CF252 3.92E+00 0. 9.33E-02 0. 0. 6.62E-01 1 .84E-04 55
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 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. 7.1OE-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. 1.16 E-05 AR39 0. 0. 0. 0. 0. 4.OOE-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. 1.59E-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 C060 0. 1.89E-06 2.48E-06 0. 0. 1.09E-03 3.24E-05 N159 5.44E-06 2.02E-06 9.24E-07 0. 0. 1.41 E-05 6.48E-07 N163 7.25E-05 5.43E-06 2.47E-06 0. 0. 3.84E-05 1.77E-06 N165 2.73E-10 3.66E-1 1 1.59E-1 1 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-1 3 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. 5.41 E-08 0. 0. 0. 0.
BR85 0. 0. 2.29E-09 0. 0. 0. 0.
KR83M 0. 0. 0. 0. 0. 9.97E-1 0 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. 2.21 E-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-1 5 RB89 + D 0. 4.40E-08 2.91 E-08 0. 0. 0. 4.22E-1 7 SR89 + 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 1.1OE-08 0. 4.39E-1 0 0. 0. 7.59E-06 3.24E-05 SR92 + D 1.19E-09 0. 5.08E-1 1 0. 0. 3.43E-06 1.49E-05
- Includes a 50% increase to account for percutaneous transpiration.
56
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM150Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 3.73E-07 0. 1.OOE-08 0. 0. 3.66E-05 6.99E-05 Y91M+D 4.63E-11 0. 1.77E-12 0. 0. 4.OOE-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 3.41E-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 1.21 E-05 NB97 3.92E-11 9.72E-12 3.55E-12 0. 1.1 4E-11 4.91 E-07 2.71 E-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-1 2 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 RU105+D 1.40E-10 0. 5.42E-11 0. 1.76E-10 2.27E-06 1 .13E-05 RU106+D 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.01 E-03 1.20E-04 RH105 1.32E-09 9.48E-10 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 PD107 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07 PD109 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.OOE-05 3.OOE-05 CD113M 0. 2.17E-04 7.1OE-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 5.1OE-05 SN123 4.31E-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 2.1OE-06 1.22E-08 0. 4.81 E-04 4.98E-05 SB125+D 9.23E-06 1.01E-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 6.1OE-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 2.81E-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-1 1 4.12E-07 2.02E-07 TE131M+D 1.23E-08 7.51E-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 1.01E-1 1 7.33E-12 5.71E-12 8.18E-12 5.07E-1 1 8.71 E-07 1.23E-07 TE134+D 5.31 E-12 4.35E-1 2 3.64E-1 2 4.46E-1 2 2.91 E- 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 1131 +D 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0. 8.11 E-07 57
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. 1.59E-07 1133+D 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+D 4.62E-07 1.18 E-06 4.36E-07 7.76E-05 1.86E-06 0. 8.69E-07 XE131M 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+D 0. 0. 0. 0. 0. 4.38E-08 0.
CS134M+D 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+D 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-1 1 CS139+D 3.65E-08 5.12E-08 1.97E-08 0. 4.34E-08 4.86E-09 1.66E-23 BA1 39 1.67E-10 1.18E-13 4.87E-1 2 0. 1.11 E- 13 8.08E-07 8.06E-07 BA140+D 6.84E-06 8.38E-09 4.40E-07 0. 2.85E-09 2.54E-04 2.86E-05 BA141 +D 1.78E-11 1.32E-14 5.93E-1 3 0. 1.23E-14 4.11 E-07 9.33E-1 4 BA142+D 4.62E-12 4.63E-1 5 2.84E-1 3 0. 3.92E-1 5 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-1 1 0. 0. 2.31 E-06 1.54E-05 LA142 1.20E-10 5.31 E-1 1 1.32E-1 1 0. 0. 1.27E-06 1.50E-06 CE141 3.55E-06 2.37E-06 2.71 E-07 0. 1.11 E-06 7.67E-05 1.58E-05 CE143+D 3.32E-08 2.42E-08 2.70E-09 0. 1.08E-08 1.63E-05 3.19E-05 CE144+D 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-1 2 2.20E-1 2 2.72E-1 3 0. 1.26E-12 2.19E-07 2.94E-14 ND147+D 9.83E-07 1.07E-06 6.41 E-08 0. 6.28E-07 4.65E-05 2.28E-05 PM 147 1.15 E-04 1.10E-05 4.50E-06 0. 2.1OE-05 1 .14E-04 5.87E-06 PM148M+D 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.1OE-05 PM 148 5.44E-07 8.88E-08 4.48E-08 0. 1.60E-07 6.52E-05 6.14E-05 PM 149 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 2.1OE-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM1 53 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 EU 154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05 EU155 2.OOE-04 1.96E-05 1.21 E-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.OOE-04 6.24E-04 1.68E-05 W181 8.90E-09 2.88E-09 3.01 E-1 0 0. 0. 2.95E-06 2.69E-07 W185 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 1.14E-05 W187 1.50E-09 1.22E-09 4.29E-10 0. 0. 5.92E-06 2.21 E-05 58
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 3.09E-02 8.28E-03 1.07E-03 0. 2.95E-02 4.52E-02 3.87E-05 BI210+D 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91 E-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 3.11E-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 + 00 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+00 1.36E-01 4.45E-01 0. 6.67E-01 5.05E+00 3.36E-04 TH230 2.34E+00 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05 TH232+D 2.61E+00 1.14E-01 9.21E-02 0. 5.60E-01 8.60E-01 3.36E-05 TH234 2.32E-06 1.35E-07 6.71E-08 0. 7.73E-07 3.26E-04 7.49E-05 PA231 +D 5.32E+00 2.OOE-01 2.07E-01 0. 1.12E+00 9.91E-02 4.71E-05 PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.OOE-05 U232 + D 7.31E-02 0. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05 U233 + D 1.55E-02 0. 9.42E-04 0. 3.63E-03 9.18E-02 4.12E-05 U234 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. 8.1OE-04 0. 3.12E-03 7.89E-02 3.62E-05 NP237+D 1.77E+00 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 8.11E-06 1.65E-05 PU238 2.86E +00 4.06E-01 7.22E-02 0. 3.1OE-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+00 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 +00 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05 PU244 3.59E +00 4.96E-01 8.88E-02 0. 3.79E-01 3.23E-01 6.39E-05 AM241 1.06E+00 4.07E-01 7.1OE-02 0. 5.32E-01 1.05E-01 4.88E-05 AM242M 1.07E+00 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 1.41E-03 0. 6.40E-03 6.76E-02 5.21 E-05 CM243 8.45E-01 3.50E-01 5.OOE-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+00 4.11E-01 7.53E-02 0. 3.52E-01 1.01 E-01 4.63E-05 CM246 1.31E+00 4.11E-01 7.52E-02 0. 3.51E-01 1.03E-01 4.54E-05 CM247 + D 1.28E +00 4.04E-01 7.41E-02 0. 3.46E-01 1.01 E-01 5.97E-05 CM248 1.06E+01 3.33E+00 6.11E-01 0. 2.85E+00 8.32E-01 9.63E-04 CF252 1.29E+00 0. 3.07E-02 0. 0. 3.43E-01 1.89E-04 59
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 BE1O 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-1 1 0. 1.63E-10 1.18 E-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 C060 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-05 N159 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.11 E-07 N163 5.40E-05 3.93E-06 1.81 E-06 0. 0. 2.23E-05 1.67E-06 N165 1.92E-10 2.62E-1 1 1 .14E-1 1 0. 0. 7.O0E-07 1.54E-06 CU64 0. 1.83E-10 7.69E-1 1 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-1 2 8.14E-12 5.65E-13 0. 5.27E-1 2 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 3.21 E-06 0. 0. 0. 2.88E-07 RB88 0. 4.84E-08 2.41 E-08 0. 0. 0. 4.18E-1 9 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 SR92 + D 8.43E-1 0 0. 3.64E-1 1 0. 0. 2.06E-06 5.38E-06
- Includes a 50% increase to account for percutaneous transpiration.
60
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 2.61 E-07 0. 7.01 E-09 0. 0. 2.12E-05 6.32E-05 Y91M+D 3.26E-1 1 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 4.81E-05 Y92 1.29E-09 0. 3.77E-1 1 0. 0. 1.96E-06 9.19E-06 Y93 1 .18E-08 0. 3.26E-1 0 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 2.21E-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 3.1OE-05 1.01 E-05 2.49E-06 0. 1.16E-05 3.11E-05 2.38E-06 NB95 1.76E-06 9.77E-07 5.26E-07 0. 9.67E-07 6.31E-05 1.30E-05 NB97 2.78E-1 1 7.03E- 12 2.56E-1 2 0. 8.18E-12 3.OOE-07 3.02E-08 M093 0. 1.17 E-06 3.17E-08 0. 3.55E-07 5.11E-05 3.79E-06 M099+D 0. 1.51 E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.10E-05 TC99M 1.29E-13 3.64E-13 4.63E-1 2 0. 5.52E-1 2 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 TC1O1 5.22E-1 5 7.52E-1 5 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 6.31E-05 1.38E-05 RU1O5+D 9.88E-1 1 0. 3.89E-1 1 0. 1.27E-10 1.37E-06 6.02E-06 RU1O6+D 8.64E-06 0. 1.09E-06 0. 1.67E-05 1.17E-03 1.14E-04 RH105 9.24E-10 6.73E-10 4.43E-10 0. 2.86E-09 2.41E-06 1.09E-05 PD 107 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07 PD 109 0. 4.63E-10 1.16E-10 0. 2.35E-09 1.85E-06 1.52E-05 AG110M+D 1.35E-06 1.25E-06 7.43E-07 0. 2.46E-06 5.79E-04 3.78E-05 AG 111 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-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.OOE-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. 3.1OE-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 SB1127 3.30E-08 7.22E-1 0 1.27E-08 3.97E-10 0. 2.05E-05 3.77E-05 TEl 25M 4.27E-07 1.98E-07 5.84E-08 1.31 E-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-1 1 3.87E-1 1 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 TEl 29 6.22E-1 2 2.99E-1 2 1.55E-1 2 4.87E-1 2 2.34E-1 1 2.42E-07 1.96E-08 TE1 31 M + 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 1.17 E- 12 5.46E-1 2 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-1 2 3.74E-1 1 5.51E-07 5.49E-08 TE134+D 3.84E- 12 3.22E-1 2 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 1131 +D 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0. 7.85E-07 61
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED I1h SFIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.08E-08 1133+D 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 + D 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 0. 6.56E-07 XE131M 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+D 0. 0. 0. 0. 0. 2.44E-08 0.
CS134M + D 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 9.1OE-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-+ D 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E-06 CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.OOE-08 6.07E-09 2.33E-1 3 CS139-+ D 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-1 2 0. 7.78E-14 4.70E-07 1.12E-07 BA140+D 4.88E-06 6.13E-09 3.21 E-07 0. 2.09E-09 1.59E-04 2.73E-05 BA141 +D 1.25E-11 9.41E-15 4.20E-13 0. 8.75E-15 2.42E-07 1.45E-17 BA142+D 3.29E-12 3.38E-1 5 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-1 1 9.65E-1 2 0. 0. 7.91 E-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+D 2.33E-08 1.72E-08 1.91 E-09 0. 7.60E-09 9.97E-06 2.83E-05 CE144+D 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-1 8 ND147+D 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+D 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.18E-05 PM 148 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91 E-05 5.80E-05 PM 149 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.OOE-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 9.1OE-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 EU155 1.01 E-04 1.43E-05 9.21 E-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 2.21E-05 0. 2.75E-06 0. 9.1OE-06 1.92E-04 2.68E-05 H0166M 3.37E-04 1.05E-04 8.OOE-05 0. 1.57E-04 3.94E-04 1.59E-05 W181 6.23E-09 2.03E-09 2.17E-10 0. 0. 1.71 E-06 2.53E-07 W185 1.95E-07 6.47E-08 6.81 E-09 0. 0. 5.57E-05 1.07E-05 W187 1.06E-09 8.85E-1 0 3.10E-10 0. 0. 3.63E-06 1.94E-05 62
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.7 (continued)
ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 B1210+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 1.80E-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.OOE-04 3.56E-07 5.99E-05 0. 1.01 E-05 2.92E-02 2.71E-04 RA226 + D 1.25E-01 2.39E-06 9.14E-02 0. 6.77E-05 1.1 7E-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.OOE-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.OOE-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 5.08E+00 1.91 E-01 1.98E-01 0. 1.07E+00 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 U232+D 5.14E-02 0. 3.66E-03 0. 5.56E-03 2.22E-01 4.21 E-05 U233+D 1.09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05 U234 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.OOE-02 0. 6.20E-04 0. 2.39E-03 5.OOE-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 3.41 E-05 NP237+D 1.69E+00 1.47E-01 6.87E-02 0. 5.10E-01 5.22E-02 4.92E-05 NP238 2.96E-07 8.OOE-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+00 4.31 E-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+00 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 1.01 E+00 3.59E-01 6.71 E-02 0. 5.04E-01 6.06E-02 4.60E-05 AM242M 1.02E+00 3.46E-01 6.73E-02 0. 5.01 E-01 2.44E-02 5.79E-05 AM243 1.01 E+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 +00 3.59E-01 7.14E-02 0. 3.33E-01 5.85E-02 4.36E-05 CM246 1.25E+00 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 5.851E-02 5.63E-05 CM248 1.01E+01 2.91 E+00 5.79E-01 0. 2.70E+00 4.82E-01 9.09E-04 CF252 9.78E-01 0. 2.33E-02 0. 0. 1.99E-01 1.78E-04 63
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFGI)
(MREM/HR PER PCI/M 2 )
FI FMFNT TOTAl RODY 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 1.1OE-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.OOE-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.OOE-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.OOE-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-1 1 9.30E-1 1 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.OOE-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-1 3 6.50E-1 3 Sr-91 7.1 0E-09 8.30E-09 Sr-92 9.OOE-09 1.OOE-08 Y-90 2.20E-1 2 2.60E-1 2 Y-91 m 3.80E-09 4.40E-09 Y-91 2.40E-1 1 2.70E-1 1 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.OOE-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.1 OE-09 6.OOE-09 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.1OE-09 Tc-101 2.70E-09 3.OOE-09 64
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.8 (continued)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFGI1 (MREM/HR PER PCI/M 2 )
FI FMFNT TOTAL BODY SKIN Ru-i 03 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.1OE-09 Ru-106 1.50E-09 1.80E-09 Ag-1 1Om 1.80E-08 2.1OE-08 Te-1 25m 3.50E-1 1 4.80E-1 1 Te-1 27m 1.10E-12 1.30E-12 Te-127 1.OOE-1 1 1.1OE-i 1 Te-1 29m 7.70E-10 9.OOE-1 0 Te-129 7.1OE-10 8.40E- 10 Te-1 31 m 8.40E-09 9.90E-09 Te-1 31 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.OOE-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- 1 34 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-1 37 4.20E-09 4.90E-09 Cs-1 38 2.1OE-08 2.40E-08 Ba-1 39 2.40E-09 2.70E-09 Ba- 140 2.1OE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba- 142 7.90E-09 9.OOE-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-1 44 3.20E-10 3.70E- 10 Pr- 143 0.0 0.0 Pr- 144 2.OOE-1 0 2.30E-1 0 Nd- 147 1.OOE-09 1.20E-09 W-187 3.1OE-09 3.60E-09 Np-239 9.50E-10 1.1OE-09 65
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.9 2001 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ Mrem/Ci Ci Ag-11 On GI-Tract-T 2.13E+00 7.04E+00 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 1.01E+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+00 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 + 00 2.19E+00 Cr-51 GI Tract-A 3.75E - 03 1.33E+03 Cs- 1 34 Liver-C 8.77E+00 1.71E+00 Cs-1 36 Liver-I 5.32E-01 2.82E+01 Cs-1 37 Bone-C 9.58E+00 1.57E+00 Cs-1 38 Total body-C 1.O0E - 01 5.0OE+01 Fe-55 Bone-C 2.06E - 01 7.28E + 01 Fe-59 GI Tract-T 3.20E - 01 4.69E+01 H-3 Total Body-C 2.19E - 04 2.28E+04 1-129 Thyroid-A 3.66E+02 4.1OE - 02 1-131 Thyroid-I 1.97E+01 7.61 E - 01 1-132 Thyroid-C 1.12E - 02 1.34E +03 1-133 Thyroid-C 2.46E - 01 6.11E+01 1-134 Thyroid-C 2.45E - 03 6.12E+03 1-135 Thyroid-C 4.93E - 02 3.04E + 02 66
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.9 2001 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ Mrem/Ci Ci 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-i 40 GI Tract-T 3.04E - 02 4.93E+02 Mn-54 GI Tract-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 3.44E - 06 1.45E +06 Na-24 Total Body-C 4.02E - 03 1.24E + 03 Nb-95 GI Tract-A 1.92E - 01 7.81E+01 Ni-63 Bone-C 1.21E+01 1.24E+O0 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 2.1OE+05 Ru- 103 GI Tract-A 2.93E - 01 5.12E+01 Ru-105 GI Tract-C 5.82E - 03 2.58E+03 Sb- 1 24 GI Tract-T 9.47E - 01 1.58E+01 Sb-1 25 GI Tract-T 4.35E - 01 3.45E+01 Sr-89 Bone-C 8.98E+00 1.67E+00 Sr-90 Bone-C 3.73E+02 4.02E - 02 Sr-91 Bone-I 2.46E + 00 6.1OE+00 Sr-92 GI Tract-C 1.37E - 02 1.09E+03 67
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 1.9 2001 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Oracn Mrem/Ci Ci Tc-99 GI Tract-T 5.85E - 01 2.62E+01 Tc-99m GI Tract-T 3.64E - 04 4.12E+04 Tc-1 01 GI Tract-T 8.33E - 05 1.80E+05 Te-127 GI Tract-T 4.87E - 03 3.08E+03 Xe-131m Skin 4.03E - 05 3.72E + 05 Xe-1 33 Total Body 1.39E - 05 3.60E+05 Xe-1 33m Skin 8.39E - 05 1.79E+05 Xe-1 35 Total Body 8.32E - 05 6.01E+04 Xe-1 35m Total Body 9.55E - 05 5.24E + 04 Xe-137 Skin 5.85E - 04 2.56E+04 Xe-1 38 Total body 2.70E - 04 1.85E+04 Zn-65 Liver-C 9.38E - 01 1.60E+01 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 68
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 II. LIQUID EFFLUENTS A. CONCENTRATION
- 1. Requirements Appendix A, Section lll.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 pCi/ml total activity. To ensure compliance, the following approach will be used for each release.
- 2. Prerelease 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.
n C = Ci (2.1) where:
C Total concentration in the liquid effluent at the release point, pCi/ml.
Cj Concentration of a single radionuclide i, pCi/ml.
69
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 3. Effluent Concentration (EC) - Sum of the Ratios The EC-Fraction (R1) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:
R1 < 10.0 ECi (2.2) where:
C = Effluent concentration of radionuclide i, pCi/ml.
EC The EC of radionuclide i, 10 CFR 20, Appendix B, Table 2, Column 2 - pCi/ml.
a = The Total EC-Fraction for the release point.
The sum of the ratios at the discharge to the lake must be
_< 10 due to the releases from any or all concurrent releases.
The following relationship will assure this criterion is met:
f1(Rj-1) + f2 (R 2 -1) + f 3(R 3 -1) < F (2.3) where:
f1If2,f3 The effluent flow rate (gallons/minute) for the respective releases, determined by Plant personnel.
R1,R12 R3 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.
70
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 B. INSTRUMENT SETPOINTS
- 1. Setpoint Determination Appendix A, Section IlI.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A,Section III.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:
S =bxC (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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per Appendix A, Table C-1, Action 3.
71
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 3. Post-Release Analysis 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 III.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.
72
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 2. Release Analysis Calculations shall be performed for each batch release, and weekly for continuous releases according to the formula:
AiA !C*
_0.5 (2.5) where:
Ai Cumulative quarterly activity of nuclide i identified in liquid release (Ci).
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 III.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:
i Di (DCF)ij x 1, i=l (2.6) where:
Dj Dose for the jth organ from radionuclides releases, mrem.
= The organ of interest.
73
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 (DCF)ij Ingestion dose commitment factor for the jth organ from the ith radionuclide mrem/pCi, see Table 2.1.
I = Activity ingested of the ith radionuclide, pCi.
Ii is described by:
Ii=(Ai)(V)(365)(1E Ii = (1E06) 6 (1 000)(d) 2.7) where:
365 = Days per year.
A. = Annual activity released of ith radionuclide, pCi.
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 = Dispersion factor from discharge to nearest drinking water supply.
1E06 = Conversion pCi to pCi.
The dose equation then becomes:
Di = (3.65E05)(V) (DCF)ij x A, mrem d i=4 l-- l (2.8) 74
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- 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 (1) is described by:
I AiB F(1 E09)
__ 1 ___=__ = pCi 15d (2.9) where:
A. = Annual released of ith radionuclide, pCi.
I0 i/gm radionuclide PCi/mI B = Fish concentration factor of ith (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 pCi and Kgm to gross.
Substitution of Equation 2.9 into Equation 2.6 gives:
Dj (6.7E07)F d Ai x Bi x DCFi mrem d(210 (2.1 0) 75
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16
- c. Annual Analysis A complete analysis utilizing the NRC computer code LADTAP 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 LADTAP. The dose to the jth organ from m radionuclides, Dj, is described by:
m Dj = Di, mrem i=1 (2.11) m
- (DCF)ij x I mrem i=1 where:
Di Dose to the jth organ from the ith radionuclide, mrem.
The organ of interest (bone, GI tract, thyroid, liver, kidney, lung, or total body).
(DCF)ij 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, pCi.
lI for water ingestion is described by:
A 1 Vr Ii-li=Ai V c
. Ci vd (2.13) and for fish ingestion lI is described by:
A i 131F r c i-vd pCi 76
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 where:
A. = Activity release of jth radionuclide during the year, pCi.
V = Average rate of water consumption (2000 ml/d).
F = Number of days during the year (365 d).
v = Dispersion factor from point of discharge to point of exposure.
d = Dilution water volume (ml).
Bi Fish concentration factor of the ith radionuclide, pCi/gm pCi/mI 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, III.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.
77
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement.
The LADTAP 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.
78
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 F. FIGURES AND TABLES Figure 2-1
- ý G 0
1 IIa Zr-. 02
/
- m 0 z I oz -- , .*.
-4 3-1-)
79
PALISADES RADWASTE EFFLUENTS - LIOUID CI.FAN WASTE syATiM STEAM GEN BLOWDOWN PRIMARYTANK ISYSTEM I7 ISTORAGE 0707 z TREATED TN z WASTE T6I3A T 6B 9
-Z (L o TANKS 121 cc - R TRIP & FLOW CONTROL 1049RE833 4 to SERVICE
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 2.0 BIOACCUMULATION FACTORS MCi/gm per uCi/ml FRESHWATER ELEMENT FISH H 9.OE-01 C 4.6E 03 NA 1.OE 02 P 1.OE 05 CR 2.OE 02 MN 4.OE 02 FE 1.OE 02 Co 5.OE 01 NI 1.OE 02 CU 5.OE 01 ZN 2.OE 03 BR 4.2E 02 RB 2.OE 03 SR 3.OE 01 Y 2.5E 01 ZR 3.3E 00 NB 3.OE 04 MO 1.OE 01 TC 1.5E 01 RU 1.OE 01 RH 1.OE 01 TE 4.OE 02 I 1.5E 01 CS 2.OE 03 BA 4.OE 00 LA 2.5E 01 CE 1.OE 00 PR 2.5E 01 ND 2.5E 01 W 1.2E 03 NP 1.OE 01 81
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BEO 0 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.OOE-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. 4.08E-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. 1.15 E-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 N159 4.78E-05 1.45E-05 8.17E-06 0. 0. 0. 7.16 E-07 N163 6.34E-04 3.92E-05 2.20E-05 0. 0. 0. 1.95E-06 N165 4.70E-06 5.32E-07 2.42E-07 0. 0. 0. 4.05E-05 CU64 0. 6.09E-07 2.82E-07 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. 2.1OE-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 2.51 E-03 0. 7.20E-05 0. 0. 0. 5.16E-05 SR90+D 1.85E-02 0. 4.71 E-03 0. 0. 0. 2.31 E-04 SR91 + D 5.OOE-05 0. 1.81 E-06 0. 0. 0. 5.92E-05 SR92+D 1.92E-05 0. 7.13E-07 0. 0. 0. 2.07E-04 82
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 Y91M+D 8.10E-10 0. 2.76E-1 1 0. 0. 0. 2.70E-06 Y91 1 .13E-06 0. 3.01 E-08 0. 0. 0. 8.1OE-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. 2.71 E-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 NB93M 1.23E-07 3.33E-08 1.04E-08 0. 3.25E-08 0. 3.98E-06 NB95 4.20E-08 1.73E-08 1.OOE-08 0. 1.24E-08 0. 1.46E-05 NB97 4.59E-1 0 9.79E-1 1 3.53E-1 1 0. 7.65E-1 1 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. 1OE-08 0. 4.26E-08 2.07E-09 1.15 E-06 TC99 1.08E-06 1.46E-06 4.55E-07 0. 1.23E-05 1.42E-07 6.31E-06 TC101 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07 RU1O3+D 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05 RU1O5+D 1.36E-07 0. 4.58E-08 0. 1.OOE-06 0. 5.41 E-05 RU1O6+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 AGi 11 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 CD1 15M 0. 1.42E-05 4.93E-07 0. 7.41 E-06 0. 8.09E-05 SN123 2.49E-04 3.89E-06 6.50E-06 3.91 E-06 0. 0. 6.58E-05 SN125+D 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.11 E-04 SN126+D 5.53E-04 7.26E-06 1.80E-05 1.91 E-06 0. 0. 2.52E-05 SB124 2.14E-05 3.15 E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.60E-05 SB125+D 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05 SB126 8.06E-06 1.58E-07 2.91 E-06 6.19E-08 0. 5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15 E-06 5.91 E-05 TE1 25M 2.33E-05 7.79E-06 3.15 E-06 7.84E-06 0. 0. 1.11 E-05 TE1 27M + D 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.36E-05 TEl 27 1.OOE-06 3.35E-07 2.15 E-07 8.14E-07 2.44E-06 0. 2.1OE-05 TE1 29M + D 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0. 5.97E-05 TE1 29 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 TEl 32+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.OOE-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. 1.51 E-06 83
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI 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. 3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15 E-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 XE131M 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 CS 134 3.77E-04 7.03E-04 7.1OE-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 1.10E-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 3.10E-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. 3.51 E- 10 3.54E-1 0 5.58E-05 BA 140 + 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 2.91 E-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-1 1 7.59E-07 LA1 40 2.11 E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05 LA1 41 2.89E-09 8.38E-10 1.46E-10 0. 0. 0. 9.61 E-05 LA142 1.1OE-09 4.04E-10 9.67E-1 1 0. 0. 0. 6.86E-05 CE141 7.87E-08 4.80E-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 8.18E-08 3.04E-08 4.03E-09 0. 1.13E-08 0. 4.29E-05 PR144 2.74E-10 1.06E-1 0 1.38E-1 1 0. 3.84E-1 1 0. 4.93E-06 ND147+D 5.53E-08 5.68E-08 3.48E-09 0. 2.19E-08 0. 3.60E-05 PM 147 3.88E-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 6.18E-09 9.01 E-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 1.51 E-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 84
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI PB210+D 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 B1210+D 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05 P0210 3.10E-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.OOE-04 0. 3.86E-04 RA225 + D 5.78E-02 6.42E-05 1.15 E-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.OOE-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. 8.1OE-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. 2.11E-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 5.61 E-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 7.18 E-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 9.1OE-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 1.51E-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 85
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI H3 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 BE1O 1.35E-05 1.57E-06 3.39E-07 0. 1.11 E-06 0. 2.75E-05 C14 1.21 E-O5 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 N13 3.1OE-08 3.1OE-08 3.1OE-08 3.1OE-08 3.1OE-08 3.1OE-08 3.10E-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 5.8OE-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.OOE-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 6.1OE-06 1.89E-06 0. 0. 3.45E-06 1.13 E-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 N159 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.10 E-07 N163 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06 N165 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 7.1OE-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 86
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI Y90 4.11 E-08 0. 1 .1OE-09 0. 0. 0. 1.17 E-04 Y91M+D 3.82E-10 0. 1.39E-1 1 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-1 0 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-1 1 1.83E-11 0. 4.35E-1 1 0. 1.21 E-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. 1.10E-05 TC99M 9.23E-10 1.81 E-09 3.OOE-08 0. 2.63E-08 9.19E-1 0 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-1 0 3.56E-09 RU103+D 7.31E-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 RH 105 5.14E-07 2.76E-07 2.36E-07 0. 1.1OE-06 0. 1.71 E-05 PD 107 0. 4.72E-07 4.01 E-08 0. 3.95E-06 0. 9.37E-07 PD 109 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 AGi 11 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. 1.10E-04 SN126+D 3.33E-04 4.15 E-06 9.46E-06 1 .14E-06 0. 0. 2.50E-05 SB1 24 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. 2.1OE-06 8.87E-05 SB1127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0. 4.60E-07 5.97E-05 TE1 25M 1 .14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. 1.10E-05 TE127M+D 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0. 2.34E-05 TEl 27 4.71 E-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 TEl 29 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 6.51 E-06 4.15 E-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 87
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI 1132 8.OOE-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 I134 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 XE131M 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 8.1OE-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 3.13 E-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. 1.21 E-07 1.22E-08 1.45E-1 1 BA139 4.14E-07 2.21 E-10 1.20E-08 0. 1.93E-10 1.30E-10 2.39E-05 BA 140 + 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.OOE-07 1.12E-10 6.51 E-09 0. 9.69E-1 1 6.58E-1 0 1.14E-07 BA142+D 8.74E-08 6.29E-1 1 4.88E-09 0. 5.09E-1 1 3.70E-1 1 1.14E-09 LA1 40 1.01 E-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05 LA1 41 1.35E-09 3.17E-10 6.88E-1 1 0. 0. 0. 7.05E-05 LA142 5.24E-10 1.67E-10 5.23E-1 1 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-1 1 6.49E-1 2 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 PM 147 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 PM 148 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 2.31 E-10 0. 6.02E-1 0 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. 6.91 E- 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 EU 55 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 88
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI PB210+D 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.57E-05 B1210+D 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. 3.21 E-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.OOE-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. 6.1OE-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. 2.12 E-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.OOE-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.OOE-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 1.41 E-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. 4.1 OE-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 1.41 E-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 89
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI H3 0. 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1 .06E-07 1.06E-07 BE1O 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 1.15 E-08 1.15E-08 1 .15E-08 1.15 E-08 1.15E-08 1 .15E-08 1.15 E-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.OOE-09 7.89E-10 5.14E-09 6.05E-07 MN54 0. 5.90E-06 1.17E-06 0. 1.76E-06 0. 1.21 E-05 MN56 0. 1.58E-07 2.81 E-08 0. 2.OOE-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 CO58 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-05 C060 0 2.81 E-06 6.33E-06 0. 0. 0. 3.66E-05 N159 1.32E-05 4.66E-06 2.24E-06 0. 0. 0. 7.31 E-07 N163 1.77E-04 1.25E-05 6.OOE-06 0. 0. 0. 1.99E-06 N165 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.OOE-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. 3.11 E-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 6.11 E-06 0. 0. 0. 6.11 E-07 RB88 0. 8.52E-08 4.54E-08 0. 0. 0. 7.30E-1 5 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 90
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI Y90 1.37E-08 0. 3.69E-10 0. 0. 0. 1.13E-04 1.29E-10 0. 4.93E-1 2 0. 0. 0. 6.09E-09 Y91M+D 2.01 E-07 0. 5.39E-09 0. 0. 0. 8.24E-05 Y91 Y92 1.21 E-09 0. 3.50E-1 1 0. 0. 0. 3.32E-05 Y93 3.83E-09 0. 1.05E-1 0 0. 0. 0. 1.17 E-04 5.53E-08 2.73E-08 1.49E-08 0. 9.65E-08 0. 2.58E-05 ZR93+D 4.12E-08 1.30E-08 8.94E-09 0. 1.91 E-08 0. 3.OOE-05 ZR95+D 2.37E-09 4.69E-10 2.16E-10 0. 7.11E-10 0. 1.27E-04 ZR97+D 3.44E-08 1 .13E-08 2.83E-09 0. 1.32E-08 0. 4.07E-06 NB93M NB95 8.22E-09 4.56E-09 2.51 E-09 0. 4.42E-09 0. 1.95E-05 7.37E-1 1 1.83E-1 1 6.68E-1 2 0. 2.14E-1 1 0. 4.37E-07 NB97
- 0. 1.06E-05 2.90E-07 0. 3.04E-06 0. 1.29E-06 M093 M099+D 0. 6.03E-06 1.15 E-06 0. 1.38E-05 0. 1.08E-05 TC99M 3.32E-1 0 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 2.55E-07 0. 1.09E-07 0. 8.99E-07 0. 2.13E-05 RU1O3+D 2.18E-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 RU105+D RU1O6+D 3.92E-06 0. 4.94E-07 0. 7.56E-06 0. 1.88E-04 RH 105 1.73E-07 1.25E-07 8.20E-08 0. 5.31 E-07 0. 1.59E-05 PD 107 0. 2.08E-07 1.34E-08 0. 1.88E-06 0. 9.66E-07 PD 109 0. 2.51 E-07 5.70E-08 0. 1.45E-06 0. 2.53E-05 2.05E-07 1.94E-07 1.18E-07 0. 3.70E-07 0. 5.45E-05 AG110M+D 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 0. 4.80E-05 AGi 11
- 0. 4.51 E-06 1.45E-07 0. 4.99E-06 0. 2.71 E-05 CD113M
- 0. 2.60E-06 8.39E-08 0. 2.08E-06 0. 8.23E-05 CD 115M SN123 4.44E-05 7.29E-07 1.08E-06 5.84E-07 0. 0. 6.71 E-05 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.12E-04 SN125+D SN126+D 1 .16E-04 2.16E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0. 3.38E-06 7.80E-05 SB124 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05 SB125+D 1.59E-06 3.25E-08 5.71 E-07 8.99E-09 0. 1.1 4E-06 9.41 E-05 SB126 SB127 3.63E-07 7.76E-09 1.37E-07 4.08E-09 0. 2.47E-07 6.16E-05 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0. 0. 1 .13E-05 TE1 25M TE127M+D 9.67E-06 3.43E-06 1.15 E-06 2.30E-06 3.92E-05 0. 2.41 E-05 TE1 27 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 TE1 29 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07 TE131M+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 1.15 E-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.OOE-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.OOE-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 91
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI 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 6.1OE-07 0. 5.1OE-09 1135+D 6.1OE-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0. 1.74E-06 XE131M 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 .1OE-07 1.28E-08 6.76E-1 1 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-1 1 4.05E-09 0. 9.22E-1 1 6.74E-1 1 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.o01E-11 2.24E-09 0. 4.65E-1 1 3.43E-1 1 1.43E-13 BA142+D 2.99E-08 2.99E-1 1 1.84E-09 0. 2.53E-1 1 1.99E-1 1 9.18E-20 LA1 40 3.48E-09 1.71 E-09 4.55E-1 0 0. 0. 0. 9.82E-05 LA1 41 4.55E-10 1.40E-10 2.31 E-11 0. 0. 0. 2.48E-05 LA142 1.79E-10 7.95E-1 1 1.98E-1 1 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 1.91 E-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-1 1 1.76E-11 2.18E-12 0. 1.01 E-11 0. 4.74E-1 4 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 PM 148 1.02E-08 1.66E-09 8.36E-1 0 0. 3.OOE-09 0. 9.90E-05 PM 149 2.17E-09 3.05E-10 1.25E-10 0. 5.81 E- 10 0. 4.49E-05 PM151 9.87E-10 1.63E-10 8.25E-1 1 0. 2.93E-1 0 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-1 1 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 EU1 54 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 EU 156 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 3.57E-07 1.1OE-07 7.96E-08 0. 1.61 E-07 0. 0.
H0166M W181 1.42E-08 4.58E-09 4.79E-1 0 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 92
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI 1.81E-02 5.44E-03 7.01E-04 0. 1.72E-02 0. 5.74E-05 PB210+D B1210+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
- 0. 0. 0. 0. 0. 0. 0.
RN222+D RA223 + D 7.11E-03 1.08E-05 1.42E-03 0. 3.1OE-04 0. 3.43E-04 2.31E-03 5.52E-06 4.61E-04 0. 1.58E-04 0. 3.71 E-04 RA224 + D 9.37E-03 1 .1 OE-05 1.87E-03 0. 3.15E-04 0. 3.27E-04 RA225 + D 3.22E-01 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51 E-04 RA226 + D RA228 + D 1.37E-01 4.41 E-06 1.51 E-01 0. 1.26E-04 0. 5.98E-05 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04 AC225 2.05E-03 3.03E-04 1.22E-04 0. 8.81 E-05 0. 8.68E-05 AC227 + D 1.96E-05 3.52E-07 5.65E-07 0. 2.01 E-06 0. 5.75E-04 TH227+D TH228 + D 6.80E-04 1.1 4E-05 2.30E-05 0. 6.41 E-05 0. 5.97E-04 TH229 8.39E-03 1.26E-04 4.11E-04 0. 6.1OE-04 0. 5.43E-04 2.16E-03 1.23E-04 6.OOE-05 0. 5.99E-04 0. 6.38E-05 TH230 2.42E-03 1.05E-04 1.63E-04 0. 5.11 E-04 0. 5.43E-05 TH232 + D TH234 1.14E-07 6.68E-09 3.31E-09 0. 3.81E-08 0. 1.21 E-04 PA231 + D 4.31E-03 1.62E-04 1.68E-04 0. 9.1OE-04 0. 7.60E-05 7.33E-09 1.41 E-09 1.26E-09 0. 5.32E-09 0. 1.61 E-05 PA233 5.89E-03 0. 4.21E-04 0. 6.38E-04 0. 7.19E-05 U232 + D 1.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05 U233 + D 1.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51 E-05 U234 U235+D 1.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05 1.14E-03 0. 7.09E-05 0. 2.73E-04 0. 6.11 E-05 U236
- 0. 2.1OE-08 0. 3.24E-07 0. 2.09E-05 U237 7.89E-08
- 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05 U238+D 1.09E-03 NP237 + D 1.44E-03 1.25E-04 5.85E-05 0. 4.33E-04 0. 8.41 E-05 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05 NP238 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 2.01E-05 0. 8.57E-05 0. 7.06E-05 8.26E-04 1.12E-04 2.01E-05 0. 8.56E-05 0. 7.19E-05 PU240 1.84E-05 9.42E-07 3.69E-07 0. 1.71 E-06 0. 1.48E-06 PU241 + D 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 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.23E-05 AM243 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.OOE-05 1.07E-03 3.33E-04 6.1OE-05 0. 2.85E-04 0. 7.46E-05 CM245 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.OOE-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 3.51E-04 0. 8.37E-06 0. 0. 0. 3.05E-04 93
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN GI-LLI FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG
- 0. 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 H3 3.18E-06 4.91 E-07 7.94E-08 0. 3.71 E-07 0. 2.68E-05 BE1O 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 C14 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 N13 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08 F18 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 NA22 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 NA24 1.93E-04 1.20E-05 7.46E-06 0. 0. 0. 2.17E-05 P32
- 0. 0. 0. 0. 0. 0. 0.
AR39
- 0. 0. 0. 0. 0. 0. 0.
AR41 1.83E-05 0. 2.OOE-05 0. 0. 0. 1.84E-07 CA41 5.51 E-09 1.07E-08 3.11 E-09 0. 9.99E-09 0. 5.21 E-05 SC46
- 0. 0. 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 CR51
- 0. 4.57E-06 8.72E-07 0. 1.36E-06 0. 1.40E-05 MN54
.0. 1.15 E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06 MN56 2.75E-06 1.90E-06 4.43E-07 0. 0. 1.06E-06 1.09E-06 FE55 4.34E-06 1.02E-05 3.91 E-06 0. 0. 2.85E-06 3.40E-05 FE59
- 0. 1.75E-07 2.91 E-07 0. 0. 0. 4.44E-06 C057
- 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51 E-05 CO58
- 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05 C060 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07 N159 1.30E-04 9.01 E-06 4.36E-06 0. 0. 0. 1.88E-06 N163 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1.74E-06 N165
- 0. 8.33E-08 3.91 E-08 0. 2.1OE-07 0. 7.10E-06 CU64 4.84E-06 1.54E-05 6.96E-06 0. 1.03E-05 0. 9.70E-06 ZN65 1.70E-07 4.08E-07 3.73E-08 0. 2.47E-07 0. 2.49E-05 ZN69M + D 1.03E-08 1.97E-08 1.37E-09 0. 1.28E-08 0. 2.96E-09 ZN69
- 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. 5.38E-07 SE79
- 0. 0. 2.26E-06 0. 0. 0. 2.59E-06 BR82
- 0. 0. 4.02E-08 0. 0. 0. 5.79E-08 BR83 + D
- 0. 0. 5.21 E-08 0. 0. 0. 4.09E- 13 BR84
- 0. 0. 2.14E-09 0. 0. 0. 0.
BR85
- 0. 0. 0. 0. 0. 0. 0.
KR83M
- 0. 0. 0. 0. 0. 0.
KR85M 0.
- 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. 2.11 E-05 9.83E-06 0. 0. 0. 4.16E-06 RB86
- 0. 1.23E-05 4.28E-06 0. 0. 0. 5.76E-07 RB87
- 0. 6.05E-08 3.21 E-08 0. 0. 0. 8.36E-1 9 RB88
- 0. 4.01 E-08 2.82E-08 0. 0. 0. 2.33E-21 RB89+D 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05 SR89+D 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04 SR90+D 5.67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05 SR91 +D 2.15E-06 0. 9.30E-08 0. 0. 0. 4.26E-05 SR92+D 94
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04 Y91M+D 9.09E-1 1 0. 3.52E-1 2 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-1 1 0. 0. 0. 1.48E-05 Y93 2.68E-09 0. 7.40E-1 1 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-1 0 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. 2.1OE-05 NB97 5.22E-1 1 1.32E-11 4.82E-1 2 0. 1.54E-1 1 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 1.1OE-21 RU1O3+D 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E-05 RU105+D 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 RH 105 1.21 E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41 E-05 PD 107 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.11 E-07 PD 109 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 AGi 11 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.OOE-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 3.1OE-09 0. 1.53E-07 5.90E-05 TE1 25M 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 TE1 27 1 .1OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0. 8.68E-06 TE129M+D 1.15 E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05 TE1 29 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 95
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN GI-LLI FIRST YR)
LIVER TOTAL BODY THYROID KIDNEY LUNG ISOTOPE BONE 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07 1132 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0. 2.22E-06 1133+D 1.42E-06 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51 E-1 0 1134 1.06E-07 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1.31 E-06 1135+D
- 0. 0. 0. 0. 0. 0. 0.
XE131M
- 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 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08 CS134M+D 6.22E-05 1.48E-04 1.21 E-04 0. 4.79E-05 1.59E-05 2.59E-06 CS134 1.80E-05 7.99E-06 0. 6.81 E-06 2.04E-06 4.21 E-07 CS135 1.95E-05 6.51E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06 CS136 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.11 E-06 CS137+D 6.52E-08 1.09E-07 5.40E-08 0. 8.01 E-08 7.91 E-09 4.65E-1 3 CS 138 3.41 E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.1OE-30 CS139+D 9.70E-08 6.91 E- 11 2.84E-09 0. 6.46E-1 1 3.92E-1 1 1.72E-07 BA139 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05 BA 140+ D 2.03E-05 4.71 E-08 3.56E-1 1 1.59E-09 0. 3.31 E-1 1 2.02E-1 1 2.22E-17 BA141 +D 2.13E-08 2.19E-11 1.34E-09 0. 1.85E-1 1 1.24E-1 1 3.OOE-26 BA 142 + D 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05 LAl 40 3.19E- 10 9.90E-1 1 1.62E-1 1 0. 0. 0. 1.18E-05 LAl 41 1.28E-10 5.82E-1 1 1.45E-1 1 0. 0. 0. 4.25E-07 LA142 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CE141 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-1 0 0. 4.56E-05 CE143+D 4.88E-07 2.04E-07 2.62E-08 0. 1.21 E-07 0. 1.65E-04 CE144+D 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05 PR143 3.01E-11 1.25E-1 1 1.53E-12 0. 7.05E-12 0. 4.33E-18 PR144 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05 ND147+D 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06 PM 147 3.07E-08 7.95E-09 6.08E-09 0. 1.20E-08 0. 6.74E-05 PM148M+D 7.17E-09 1.19 E-09 5.99E-1 0 0. 2.25E-09 0. 9.35E-05 PM 148 1.52E-09 2.15E-10 8.78E-1 1 0. 4.06E-1 0 0. 4.03E-05 PM149 1.17E-10 5.91 E-11 0. 2.09E-10 0. 3.22E-05 PM151 6.97E-10 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06 SM151 7.15E-10 5.22E-1 1 0. 2.31 E- 10 0. 2.55E-05 SM153 8.57E-10 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05 EU 52 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05 EU154 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06 EU 155 1.06E-08 1.71E-09 0. 7.08E-09 0. 7.26E-05 EU156 1.37E-08
- 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05 TB160 4.70E-08 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0.
H0166M 9.91 E-09 3.23E-09 3.46E- 10 0. 0. 0. 3.68E-07 W181 1.35E-07 1.42E-08 0. 0. 0. 1.56E-05 W185 4.05E-07 1.03E-07 8.61 E-08 3.01 E-08 0. 0. 0. 2.82E-05 W187 96
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 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-LLI PB210+D 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05 B1210+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. 3.21 E-04 RA224 + D 1.61 E-03 3.90E-06 3.23E-04 0. 1.1OE-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.OOE-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.OOE-04 1.50E-04 0. 4.82E-04 0. 5.12E-05 TH234 8.01 E-08 4.71 E-09 2.31 E-09 0. 2.67E-08 0. 1.13E-04 PA231 + D 4.1OE-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 1.1 9E-04 5.54E-05 0. 4.12E-04 0. 7.94E-05 NP238 1.37E-08 3.69E-1 0 2.13E-10 0. 1.25E-09 0. 3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-1 1 0. 3.65E-10 0. 2.40E-05 PU238 6.80E-04 9.58E-05 1.71 E-05 0. 7.32E-05 0. 7.30E-05 PU239 7.87E-04 1.06E-04 1.91 E-05 0. 8.11 E-05 0. 6.66E-05 PU240 7.85E-04 1.06E-04 1.91 E-05 0. 8.1OE-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 1.17 E-04 2.11E-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 2.1OE-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. 7.81 E-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 97
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 2.2 PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors (mrem/Ci) Individual/Organ (Curies)
H-3 12.3 yr 1.75E-06 Adult/TB 1.71E+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 Mn-54 303 d 3.50E-02 Teen/TB 85.7 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 4.71 E-01 Teen/TB 6.37 Cu-64 12.8 h 1.32E-03 Teen/Gl (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 + 00 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-1 03 39.5 d 2.74E-03 Teen/TB 1,094.9 Ag-110m 255 d 7.75E-02 Teen/TB 38.7 98
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 TABLE 2.2 (continued)
PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Mh ic~lic*p HIlf-I ifp. FnRotor-, (mrem/Cil Individual/Oroan (Curies)
Nuclide Cd-113m 13.6 yr 6.02E-02 Adult/GI (LLI) 166.1 Sb-124 60 d 1.51E-02 Teen/TB 198.7 Sb-1 25 2.7 yr 5.11 E-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-1 29m 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-1 31 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+00 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-1 36 13.7 d 4.13E-01 Adult/TB 7.26 Cs-1 37 30 yr 1.71E+00 Adult/TB 1.75 Cs-1 38 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-1 41 32.5 d 3.70E-04 Teen/TB 8,108.0 Ce-1 44 284 d 1.56E-03 Teen/TB 1,923.0 Eu-1 52 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 99
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 1ll. URANIUM FUEL CYCLE DOSE 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 III.C.1, III.D.1, or III.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 I1.C.2.1 and I1.C.2.2.
- 2. Amount of shore line fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for the fourth quarter and 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for the first quarter.
100
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 16 C. DOSE CALCULATION 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.
D40 = DG + DL + (RT)(T) (2.15) where:
D4 = 40 CFR 190 dose (mrem).
DG = Limiting dose to an individual from gaseous source term (mrem).
DL = Limiting dose to an individual from liquid source term (mrem).
RT = 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).
101