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{{Adams
#REDIRECT [[PNP 2011-038, 2010 Annual Radioactive Effluent Release and Waste Disposal Report]]
| number = ML11129A078
| issue date = 05/02/2011
| title = Palisades & Big Rock Point - 2010 Annual Radioactive Effluent Release and Waste Disposal Report
| author name = Anderson P K
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000155, 05000255, 07200043
| license number = DPR-006, DPR-020
| contact person =
| case reference number = PNP 2011-038
| document type = Environmental Monitoring Report, Letter
| page count = 18
}}
 
=Text=
{{#Wiki_filter:Entergy Entergy Nuclear Operations, Inc.Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043 Tel 269 764 2000 Paula K. Anderson Licensing Manager PNP 2011-038 May 2, 2011 10 CFR 50.36a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
 
==Subject:==
2010 Annual Radioactive Effluent Release and Waste Disposal Report Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Big Rock Point Dockets 50-155 and 72-043 License No. DPR-6
 
==Dear Sir or Madam:==
Attached are the Entergy Nuclear Operations, Inc. 2010 Annual Radioactive Effluent Release and Waste Disposal Reports for Palisades Nuclear Plant (PNP) and Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). These reports are submitted in accordance with 10 CFR 50.36a(a)(2).
Attachment 1 contains the report for PNP. Attachment 2 contains the report for the BRP ISFSI.These reports provide a summary of the quantities of radioactive liquid and gaseous effluent releases and solid radioactive waste processed during the period of January 1,2010, through December 31, 2010.This letter contains no new commitments and no revision to existing commitments.
Sin~ce ely, ka/bed'aýAttachment 1: Palisades Nuclear Plant 2010 Radioactive Effluent Release Report Attachment 2: Big Rock Point Independent Spent Fuel Storage Installation 2010 Radioactive Effluent Release Report CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC NRC NMSS Project Manager 7F -t ATTACHMENT 1 PALISADES NUCLEAR PLANT 2010 RADIOACTIVE EFFLUENT RELEASE REPORT 2010 Plant Operating History Palisades Nuclear Plant (PNP) was on line on January 1, 2010. PNP was taken off line on June 24, 2010, to repair control rod drive mechanism leakage. The plant was returned to service on July 3, 2010. PNP was taken off line on October 3, 2010, for a refueling outage, and was returned to service on October 29, 2010. PNP remained on line for the remainder of 2010.A. Gaseous Effluents Tables A-i, "Gaseous Effluents
-Summation of All Discharges," A-1 A, "Gaseous Effluents
-Ground-Level Release -Batch Mode," and A-1 B, "Gaseous Effluents
-Ground-Level Release -Continuous Mode," list and summarize gaseous effluents released during this reporting period.B. Liquid Effluents Tables A-2, "Liquid Effluents
-Summation of All Discharges," A-2A, "Liquid Effluents
-Batch Mode," and A-2B, "Liquid Effluents
-Continuous Mode," list and summarize liquid effluents released during this reporting period.C. Solid Waste Storage and Shipments Table A-3, "Low-Level Waste for Waste Classification A, B and C, summarizes solid radioactive waste shipped for processing or burial in 2009 for the following waste streams: resins, filters and evaporator bottoms, dry active waste, irradiated components, other waste, and sum of all waste.D. Dose Assessments Tables A-4, "Dose Assessments, 10 CFR Part 50, Appendix I," and A-5, "EPA 40 CFR Part 190, Individual in the Unrestricted Area," lists annual dose to the members of the public.E. Supplemental Information
: 1. Abnormal Discharges In December 2007, tritium was detected in a groundwater monitoring well at a level of 22,000 pCi/L. The source of the activity is leakage associated with T-91, the utility water storage tank, and associated piping. T-91 is used to store processed liquid waste prior to discharge.
No radionuclides other than tritium have been detected in the groundwater.
Tritium is still being released to the environment (Lake Michigan) via an unmonitored pathway, as demonstrated by the continued detection of monitoring well sample activity.Page 1 of 6 However, repairs have been made and tritium concentrations have dropped to approximately 90% of values seen in previous years. A definitive release rate or total activity released cannot be determined.
Conservatively, 0.5% of the total tritium activity released via batch releases, or half of the percentage that was used in 2007, 2008, and 2009, was used for 2010 effluent calculations.
Date and Duration -Tritium was first detected in a monitoring well in December 2007 and release to the environment is still occurring.
Location -The location is between the northwest corner of the auxiliary building and Lake Michigan; the plume roughly paralleling piping associated with T-91.Volume -The volume release is conservatively estimated at 0.5% of liquid radioactive waste discharge volume -3886 gallons.Estimated Activity of Each Radionuclide
-3.37 curies of tritium Effluent Monitoring Results -PNP has no offsite monitoring wells as part of the ground water monitoring program.On-site Monitoring Results -Monitoring well sample results range in concentration from < MDA to 11,029 pCi/L for the most affected well.Depth to Local Water Table -The depth is approximately eight to nine feet.Classification of Subsurface Aquifers -Not used for drinking water.Size and Extent of Any Groundwater Plume -Fifteen yards wide by fifty yards long.Expected Movement/Mobility of Groundwater Plume -Westerly direction down-gradient toward Lake Michigan at approximately two feet per day.Land Use Characteristics
-PNP site property, water not used for drinking or irrigation.
Remedial Actions Considered or Taken -None Calculated Member of Public Dose Attributable to the Release -Total body and organ dose are both 2.65E-6 mrem.Calculated Member of Public Dose Attributable to the Discharge
-Total body and organ dose are both 2.65E-6 mrem.Page 2 of 6 Actions Taken to Prevent Recurrence
-T-91 has been repaired and recirculation piping from the auxiliary building to T-91 has been replaced.The T-90/T-91 overflow line is drained routinely.
NRC Notification, Date and contact Organization
-The NRC was notified on December 10, 2007, by PNP.2. Non-Routine Planned Discharges None.3. Radioactive Waste Treatment System Changes None.4. Annual Land Use Census Changes The garden critical receptor is now located in the southeast sector at 1.47 miles. The residence critical receptor is unchanged.
Also unchanged is that there are no beef cattle, dairy cows or goats located within five miles of the plant.5. Effluent Monitoring System Inoperability The effluent monitors that were out of service for greater than 30 days were: RIA-2323, B steam generator main steam line monitor, was out of service from March 28, 2010, to July 26, 2010 (120 days). RIA-2327, high range noble gas monitor, was out of service from July 4, 2010, to December 15, 2010 (142 days).6. Offsite Dose Calculation Manual (ODCM) Changes The ODCM was revised on July 7, 2010. Changes included:* Tables 1.3, "Palisades XOQDOQ," 1.4, "Land Use Census," and Table 1.4a, "Critical Receptors," were removed and placed in a site procedure.
-Removed Section C, "Design--Basis Quantities Limits" and all references to Design Basis Quantities (DBQ).* Removed Section I D, Optional Quarterly Dose Calculations.
* Editorial changes.ODCM, Appendix A Changes:* Removed asterisk from the Mo-99 isotope that permitted a higher lower limit of detection (LLD) from Tables B-1 and D-1.Page 3 of 6
* Removed the phrase "Xe-133 content" and replaced it with "dose consequences" from Section III E 2 a.* On Table E-3, Lower Limit of Detection, Listed Ba-140 and La-140 in two separate lines and changed the LLD value for Ba-140 from 15 pCi/I to 60 pCi/l. Also listed Zr-95 and Nb-95 on two separate lines and changed the LLD for Zr-95 from 15 pCi/L to 30 pCi/I.* Removed the majority of Section IV A, that described what was to be included in the Annual Radioactive Effluent Release Report, and instead stated that the contents and format should follow the guidance of Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste.* Added a new section, Section VI, Onsite Ground Water Monitoring.
This section provides a brief description of the ground water monitoring wells added in 2007 and 2008.* Editorial changes.Enclosure 1 contains the ODCM, Revision 24, per the requirements of Technical Specification 5.5.1 .c.3.7. Process Control Program Changes None.8. Errata/Corrections to Previous Reports None 9. Other Groundwater Monitorinq PNP installed five groundwater monitoring wells in 2007, and added an additional nine wells in 2008. These wells were strategically placed within the owner controlled area, both inside and outside the protected area to allow detection of radioactive contamination of ground water due to leaks or spills from plant systems. Monitoring well (MW) 3 is most indicative of the leak described in the Abnormal Leaks section. Tritium levels ranged from a less than minimum detectable activity (MDA) to 11,029 pCi/L. Monitoring wells MW2 and MW1 1 tritium levels ranged from <MDA to 2944 and 1217 pCi/L, respectively.
The remaining wells showed no activity throughout the year. Well locations are depicted in Figure 1.Page 4 of 6 Carbon-14 In 2010, PNP and other facilities participated in an EPRI task force to build a model to accurately estimate gaseous C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc). This work was completed in November 2010. The estimates for C-14 were constructed using the aforementioned EPRI methodology contained with EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents.
Using the C-14 curie estimates, the annual dose to man was derived from guidance contained within Regulatory Guide 1.109. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required. (Reg Guide 1.21 Rev 2)Annual C-14 release PNP and subsequent doses Total Gaseous C-14 Released Curies = 7.69 Gaseous C-14 as C02 Curies = 2.31 Effective Child TB Dose, C-14 mrem = 0.0207 Effective Child Bone Dose, C-14 mrem = 0.104 The quarterly curies released are provided in Tables A-1 A and A-1 B.Airborne doses due to C-14 are grouped under the category of Particulate, Iodine, and Tritium which are contained in Table A-4.Page 5 of 6 FOGUE I1 GRUND'MWATER MOTORDM WE~LL LOCATIONS OR> P~c TF-TRAkGE ~//mW10-O&8'9)P~iMaRY , MMGAWI///-, A MMA-08 ------LEGEND FENCELINE SHEET PE AIING WALL APPROXIMATE SHORELINE MONITORING WELL LOCATION SOIL BORING LOCATION figure 4.1 GROUNDWATER MONITORING WELL LOCATIONS PALISADES NUCLEAR POWER PLANT 27780 BLUE STAR HWY.Covert, Michigan UOIlSit$UCIUUL?31*UCUUOILJV I
iv Page 6 of 6 ATTACHMENT 1 Palisades
-Table A-1 Gaseous Effluents
-Sum of All Releases Summation of i [ 1 [ 1 [ 1 Uncertainty All Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%)Fission and Activation Gases Ci 3.258E+00 1.025E+01 2.572E+01 2.288E+01 6.211 E+01 d17 Average Release Rate pCi/s 4.190E-01 1.303E+00 3.235E+00 2.879E+00 1.969E+00% of Limit % 3.069E-03 4.165E-03 3.174E-02 1.020E-02 1.237E-02 lodines (Halogens)
Ci 2.751E-04 9.455E-04 8.619E-04 8.084E-03 1.017E-02 Average Release Rate JCi/s 3.538E-05 1.203E-04 1.084E-04 1.017E-03 3.224E-04% of Limit % 1.775E-05 1.082E-04 1.01 7E-04 6.011 E-04 2.085E-04 Particulates Ci 1.094E-08 0.OOOE+00 1.043E-07 1.510E-06 1.625E-06 Average Release Rate .Ci/s 1.407E-09 0.OOOE+00 1.312E-08 1.900E-07 5.154E-08% of Limit % 1.695E-09 O.OOOE+00 5.276E-08 4.578E-08 2.526E-08 Tritium Ci 5.144E+00 5.156E+00 4.873E+00 7.819E+00 2.299E+01 Average Release Rate _pCi/s 6.616E-01 6.557E-01 6.130E-01 9.836E-01 7.290E-01% of Limit % 1.594E-03 1.580E-03 1.477E-03 2.371 E-03 1.757E-03 Gross Alpha Ci 5.125E-07 ND ND 5.511E-07 1.064E-06 C-14 Ci 2.117E+00 1.980E+00 2.099E+00 1.495E+00 7.691E+00 Average Release Rate pCi/s 2.723E-01 2.518E-01 2.641E-01 1.880E-01 2.439E-01% of Limit % 2.188E-06 2.023E-06 2.121E-06 1.511E-06 1.959E-06 I AI I MA -4 Page 1 of 1 ATTACHMENT 1 Palisades
-Table A-1A Effluents
-Ground Level Release, Batch Mode Gaseous Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Gases Ar-41 Ci ND ND ND ND Kr-85 Ci 1.212E-01 4.891E-01 8.468E-01 4.432E-01 Kr-85m Ci ND ND 3.919E-05 ND Kr-87 Ci ND ND ND ND Kr-88 Ci ND ND ND ND Xe-131m Ci 4.860E-04 2.275E-02 1.502E-01 1.945E-01 Xe-133 Ci 1.204E-03 6.706E-01 5.820E+00 5.708E+00 Xe-1 33m Ci ND 2.636E-03 2.952E-02 4.750E-03 Xe-1 35 Ci ND 8.435E-04 4.329E-03 ND Xe-135m Ci ND ND ND ND Xe-138 Ci ND ND ND ND (List Others) Ci 1.229E-01 1.186E+00 6.851E+00 6.351E+00 Total Ci Quarter 1 Quarter 2 Quarter 3 Quarter 4 lodines/Halogens Units ND 1.161E-08 2.014E-05 6.806E-06 1-131 Ci ND ND 5.535E-08 ND 1-132 Ci ND ND 9.433E-08 ND 1-133 Ci ND ND ND ND 1-134 Ci ND ND ND ND 1-135 Ci O.OOOE+00 1.161E-08 2.029E-05 6.806E-06 Total Ci I Quarter 1 Quarter 2 Quarter 3 Quarter 4 Particulates Units ND ND 1.822E-08 ND Co-58 Ci ND ND ND ND Co-60Q Ci NR NR NR NR Sr-89 Ci NR NR NR NR Sr-90 Ci ND ND ND ND Cs-134 Ci ND ND ND ND Cs-137 Ci O.OOOE+00 O.OOOE+00 1.822E-08 O.OOOE+00 Total Ci ND 4.622E-01 ND 9.314E-02 Tritium Ci I I NR NR NR NR Gross Alpha Ci NR NR NR NR C-14 Ci ND ND ND ND ND = Measurements performed but no activity detected.NR = Analysis not required and not performed Page 1 of 1 ATTACHMENT 1 Palisades
-Table A-1 B Gaseous Effluents
-Ground Level Release, Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Gases Ar-41 Ci ND ND ND ND Kr-85 Ci 1.212E-01 4.891E-01 8.468E-01 4.432E-01 Kr-85m Ci ND ND 3.919E-05 ND Kr-87 Ci ND ND ND ND Kr-88 Ci ND ND ND ND Xe-131m Ci 4.860E-04 2.275E-02 1.502E-01 1.945E-01 Xe-1 33 Ci 1.204E-03 6.706E-01 5.820E+00 5.708E+00 Xe-1 33m Ci ND 2.636E-03 2.952E-02 4.750E-03 Xe-135 Ci ND 8.435E-04 4.329E-03 ND Xe-135m Ci ND ND ND ND Xe-138 Ci ND ND ND ND (List Others) Ci 1.229E-01 1.186E+00 6.851 E+00 6.351 E+00 Total Ci Quarter 1 Quarter 2 Quarter 3 Quarter 4 lodines/Halogens Units ND 1.161 E-08 2.014E-05 6.806E-06 1-131 Ci ND ND 5.535E-08 ND 1-132 Ci ND ND 9.433E-08 ND 1-133 Ci ND ND ND ND 1-134 Ci ND ND ND ND 1-135 Ci 0.OOOE+00 1.161E-08 2.029E-05 6.806E-06 Total Ci Quarter 1 Quarter 2 Quarter 3 Quarter 4 Particulates Units ND ND 1.822E-08 ND Co-58 Ci ND ND ND ND Co-60 Ci NR NR NR NR Sr-89 Ci NR NR NR NR Sr-90 Ci ND ND ND ND Cs-134 Ci ND ND ND ND Cs-1 37 Ci 0.OOOE+00 O.OOOE+00
'1.822E-08 0.OOOE+00 Total Ci ND 4.622E-01 ND 9.314E-02 Tritium Ci I I NR NR NR NR Gross Alpha Ci I I NR NR NR NR C-14 Ci ND ND ND ND ND = Measurements performed but no activity detected.Page 1 of 1 ATTACHMENT 1 Palisades
-Table A-2 Liquid Effluents
-Sum of All Releases Summation of All Uncertainty Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%)Fission and Activation Products (excluding tritium, gases, and gross aloha)Ci 1.696E-04 1.156E-02 3.031 E-02 1.942E-02 6.146E-02 114 Average Concentration pCi/ml 4.322E-12 3.084E-10 7.555E-1 0 6.230E-1 0 4.152E-1 0% of Limit % 9.577E-05 4.534E-03 8.339E-03 7.659E-03 5.047E-03 Tritium Ci 2.008E+01 2.123E+02 3.901E+02 5.193E+01 6.744E+02 Average Concentration pCi/ml 5.116E-07 5.662E-06 9.724E-06 1.666E-06 4.556E-06% of Limit % 5.116E-02 5.662E-01 9.724E-01 1.666E-01 4.556E-01 Dissolved and Entrained Gases Ci 1.150E-05 0.OOOE+00 9.894E-03 1.084E-03 1.099E-02 Average Concentration pCi/ml 2.930E-13 O.OOOE+00 2.466E-1 0 3.476E-1 1 7.424E-1 1% Of Limit % 1.465E-07 O.OOOE+00 1.233E-04 1.738E-05 3.712E-05 Gross Alpha Ci 0.OOOE+00 1.771 E-04 0.OOOE+00 3.815E-06 1.809E-04 Average Concentration pCi/ml O.OOOE+00 4.723E-12 O.OOOE+00 1.224E-13 1.222E-12 Volume of Primary System Liquid Effluent (Before Dilution)
Liters 1.060E+05 4.560E+05 1.565E+06 8.147E+05 2.942E+06 Dilution Water Used for Above Liters 3.924E+10 3.750E+10 4.011E+10 3.118E+10 1.480E+11 Volume of Secondary or Balance-of-Plant Liquid Effluent (e.g., low-activity or unprocessed)
ABefore Dilution)
Liters 7.838E+09 8.233E+09 9.797E+09 8.144E+09 3.401E+10 Average Stream Flow m 3/s 5.047E+00 4.769E+00 5.047E+00 3.922E+00 4.696E+00 4.U I 6.6 4.6 1 Dilution flow rate (gal/qtr)
= # of Dilution pumps running x days running/qtr x 4000 gpm/pump x min/day Page 1 of 1 ATTACHMENT 1 Palisades
-Table A-2A Liquid Effluents
-Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Products Cr-51 Ci ND ND ND ND Mn-54 Ci ND 2.015E-04 8.460E-05 5.182E-05 Fe-55 Ci ND 1.988E-03 7.091E-03 2.221E-03 Fe-59 Ci ND ND 2.955E-04 ND Co-57 Ci ND 3.237E-05 ND ND Co-58 Ci 1.236E-05 1.147E-03 1.148E-02 9.454E-03 Co-60 Ci 6.270E-05 4.081 E-03 5.706E-03 3.907E-03 Sr-89 Ci ND 1.244E-05 2.152E-05 2.223E-05 Sr-90 Ci ND ND ND ND Nb-95 Ci ND 1.021E-04 9.238E-05 5.411E-04 Ag-110m Ci ND 5.254E-04 1.832E-03 1.060E-03 Sn-113 Ci ND ND ND ND Sb-124 Ci ND ND ND ND Sb-125 Ci 2.01OE-05 5.987E-04 1.127E-04 ND 1-131 Ci ND ND 4.178E-04 2.814E-04 1-133 Ci ND ND ND ND 1-135 Ci ND ND ND ND Cs-134 Ci ND ND ND ND Cs-137 Ci 1.480E-05 1.150E-04 ND 7.830E-05 Ni-63 Ci 5.967E-05 2.760E-03 3.119E-03 1.395E-03 Zn-65 Ci ND ND ND ND Zr-95 Ci ND ND ND 2.487E-04 La-140 Ci ND ND 4.833E-05 1.621E-04 Totals Ci 1.696E-04 1.156E-02 3.031E-02 1.942E-02 Page 1 of 2 ATTACHMENT 1 Palisades
-Table A-2A Liquid Effluents
-Batch Mode Dissolved and Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Entrained Gases Kr-85 Ci ND ND ND ND Kr-85m Ci ND ND ND ND Kr-88 Ci ND ND ND ND Xe-131m Ci ND ND ND ND Xe-133 Ci 1.150E-05 ND 9.894E-03 1.084E-03 Xe-133m Ci ND ND ND ND Xe-135 Ci ND ND ND ND Xe-135m Ci ND ND ND ND Totals 1.150E-05 O.OOOE+00 9.894E-03 1.084E-03 Tritium Ci 2.001E+01 2.123E+02 3.901E+02 5.193E+01 Gross Alpha Ci ND 9.678E-06 ND 3.815E-06 ND = None Detected Page 2 of 2 ATTACHMENT 1 Palisades
-Table A-2B Liquid Effluents
-Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Products Cr-51 Ci ND ND ND ND Mn-54 Ci ND ND ND ND Fe-55 Ci ND ND ND ND Fe-59 Ci ND ND ND ND Co-57 Ci ND ND ND ND Co-58 Ci ND ND ND ND Co-60 Ci ND ND ND ND Sr-89 Ci ND ND ND ND Sr-90 Ci ND ND ND ND Nb-95 Ci ND ND ND ND Ag-110m Ci ND ND ND ND Sn-113 Ci ND ND ND ND Sb-124 Ci ND ND ND ND Sb-125 Ci ND ND ND ND 1-131 Ci ND ND ND ND 1-133 Ci ND ND ND ND 1-135 Ci ND ND ND ND Cs-134 Ci ND ND ND ND Cs-137 Ci ND ND ND ND Ni-63 Ci ND ND ND ND Zn-65 Ci ND ND ND ND Zr-95 Ci ND ND ND ND La-140 Ci ND ND ND ND Totals Ci O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Page 1 of 2 ATTACHMENT 1 Palisades
-Table A-2B Liquid Effluents
-Continuous Mode Dissolved and Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Entrained Gases Kr-85 Ci ND ND ND ND Kr-85m Ci ND ND ND ND Kr-88 Ci ND ND ND ND Xe-131m Ci ND ND ND ND Xe-133 Ci ND ND ND ND Xe-133m Ci ND ND ND ND Xe-135 Ci ND ND ND ND Xe-135m Ci ND ND ND ND Totals O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+OO Tritium Ci 6.650E-02 3.910E-02 8.197E-04 9.571E-03 Gross Alpha Ci ND 1.674E-04 ND ND ND = None Detected Page 2 of 2 ATTACHMENT 1 Palisades
-Table A-3 Low Level Waste Resins, Filters, and Volume Curies Shipped Evaporator Bottoms Waste Class ft 3  m 3  Curies A 1.44E+02 4.08E+00 4.33E-05 B 0.OOE+00 O.OOE+00 0.OOE+00 C 1.40E+02 3.96E+00 2.OOE+02 ALL 2.84E+02 8.04E+00 2.OOE+02 Major Nuclides for the Above Table: Mn-54, Fe-55, Co-58, Co-60, Ni-63, Zn-65, Sb-125, Cs-134, Cs-137 Dry Active Waste Volume Curies Shipped Waste Class ft 3  m 3  Curies A 1.01 E+04 2.85E+02 2.55E+00 B O.OOE+00 0.OOE+00 0.OOE+00 C O.OOE+00 0.OOE+00 O.OOE+00 ALL 1.01 E+04 2.85E+02 2.55E+00 Major Nuclides for the Above Table: H-3, Co-58, Co-60, Ni-63 Irradiated Components Volume Curies Shipped Waste Class ft 3 m Curies A O.0OE+00 0.OOE+00 0.O0E+00 B 0.OOE+00 O.0OE+00 0.OOE+00 C 0.OOE+00 0.OOE+00 O.OOE+00 ALL 0.OOE+00 0.OOE+00 0.OOE+00 Major Nuclides for the Above Table: Other Waste Volume Curies Shipped Waste Class ft 3  mi 3  Curies A 3.73E+02 1.06E+01 8.91 E+00 B 0.OOE+00 0.OOE+00 O.OOE+00 C O.OOE+00 0.OOE+00 0.OOE+00 ALL 3.73E+02 1.06E+01 8.91 E+00 Major Nuclides for the Above Table: Fe-55, Co-58, Co-60, Ni-63, Cs-137, Sb-125, Cs-134, Cs-137 Page 1 of 2 ATTACHMENT 1 Palisades
-Table A-3 Low Level Waste Sum of All Low-Level Volume Curies Shipped Waste Shipped from Site Waste Class ft 3  m 3  Curies A 1.06E+04 3.OOE+02 1.15E+01 B O.OOE+00 O.OOE+00 0.0OE+00 C 1.40E+02 3.96E+00 2.OOE+02 ALL 1.08E+04 3.04E+02 2.11 E+02 Major Nuclides for the Above Table: H-3, Mn-54, Fe-55, Co-58, Co-60, Ni-63, Zn-65, Sb-125, Cs-134, Cs-137 Page 2 of 2 ATTACHMENT 1 Palisades
-Table A-4 Dose Assessments, 10 CFR Part 50, Appendix I Quarter 1 Quarter 2 Quarter 3 Quarter 4 Yearly Liquid Effluent Dose Limit, Total 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem Body Total Body Dose 5.OOE-05 1.99E-03 2.65E-03 2.26E-03 6.95E-03% Of Limit 0.00% 0.13% 0.18% 0.15% 0.23%Liquid Effluent Dose Limit, Any 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Organ Organ Dose 6.95E-05 2.38E-03 3.11 E-03 4.97E-03 1.05E-02% of Limit 0.00% 0.05% 0.06% 0.10% 0.11%Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Gamma Air Gamma Air Dose 1.10E-03 1.43E-03 9.77E-03 3.01 E-03 1.53E-02% of Limit 0.02% 0.03% 0.20% 0.06% 0.15%Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Beta Air Beta Air Dose 7.05E-04 1.33E-03 5.46E-03 2.68E-03 1.02E-02% of Limit 0.007% 0.013% 0.055% 0.027% 0.051%Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ (Iodine, Tritium, Particulates with >8 day half-life)
Gaseous Effluent Organ Dose 2.86E-02 2.68E-02 2.90E-02 2.05E-02 1.05E-01 (Iodine, Tritium, Particulates with>8-Day half-life)
% of Limit 0.38% 0.36% 0.39% 0.27% 0.70%Palisades
-Table A-5 EPA 40 CFR Part 190, Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Dose 4.71 E-02 3.66E-02 1.05E-02% of Limit 0.19% 0.05% 0.04%Page 1 of 1}}

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