ML102300140
| ML102300140 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/16/2010 |
| From: | Patricia Anderson Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RG-1.021 | |
| Download: ML102300140 (19) | |
Text
~ Entergy August 16, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel 269 764 2000 Paula K. Anderson Licensing Manager RG 1.21
Subject:
Corrections to Palisades Nuclear Plant 2007 and 2009 Radioactive Effluent Release and Waste Disposal Reports Palisades Nuclear Plant Docket 50-255 License No. DPR-20
References:
- 1.
- 2.
Dear Sir or Madam:
Letter dated April 29,2008, "2007 Annual Radioactive Effluent Release and Waste Disposal Report" Letter dated April 30, 2010, "2009 Annual Radioactive Effluent Release and Waste Disposal Report" Entergy Nuclear Operations, Inc. (ENO) submitted reference 1 on April 29, 2008. It was recently discovered that the second page of Attachment 2 titled, "Radioactive Effluent Release Report, Gaseous Effluents - Summation of Releases, January -
December 2007," was inadvertently omitted from the submittal. The correct tables are provided in Enclosure 1.
ENO submitted reference 2 on April 30, 2010. It was subsequently discovered that incorrect gaseous and liquid Sr-89, Sr-90 and alpha values were listed in Attachment 1 to that report, and used for effluent calculations. Additionally, when the correct values were used for liquid effluent dose calculations, doses comparable to doses from previous years were obtained. Therefore, the last paragraph in Section 9 of the Supplemental Information titled, "Sr-89, Sr-90 and Liquid Doses," is no longer valid and has been deleted. These corrections are provided in Enclosure 2.
In accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the corrected attachments have been provided in their entirety, and revision bars have been used to indicate the locations of the changes.
This letter contains no new commitments and no revisions to existing commitments.
pka/bed : Correction to 2007 Annual Radioactive Effluent and Waste Disposal Report : Correction to 2009 Annual Radioactive Effluent and Waste Disposal Report CC Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
1 2 Pages Follow
Est Fission and Activation Error
- a.
Gases
- Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year (1 )
Quarterly sum of total curies Ci 1.24E+02 6.86E+Oi 1.i4E+02 3.4SE+01 3.41 E+02 4.7 (2)
Average release rate IJCi/sec i.60E+01 8.73E+00 1.43E+Oi 4.34E+00 p
(3)
Percent of limit 7.10E-03 3.67E-03 6.21 E-03 i.80E-03 Ar-41 Ci
< LLD
< LLD S.S1 E-02
< LLD Kr-8S Ci 1.S9E+00 1.42E+00 1.27E+00 2.01E+00 Kr-8Sm Ci 7.39E-03 S.83E-04 1.31E-04
< LLD Kr-87 Ci 4.12E-04 6.34E-04
< LLD
< LLD Kr-88 Ci
< LLD
< LLD
< LLD
< LLD (4)
Xe-131m Ci i.11E+00 6.33E-01 2.46E-01 S.1SE-01 Xe-133 Ci 1.20E+02 6.63E+01 1.12E+02 3.20E+01 Xe-i33m Ci 4.23E-01 2.60E-01 1.18E-02 i.88E-OS Xe-i3S Ci i.10E+00 1.40E-02 2.80E-02 i.S6E-03 Xe-i3Sm Ci 3.29E-03 3.67E-03 1.84E-03 2.S1 E-03 Xe-138 Ci
< LLD
< LLD
< LLD
< LLD
- b.
lodines (1 )
Total Iodine Ci 2.27E-03 2.44E-03 3.03E-02 7.S2E-04 3.S7E-02 I 10.0 I (2)
Average release rate IJCi/sec 2.91 E-04 3.10E-04 3.81 E-03 9.47E-OS (3)
% of limit for Iodine 131/133 2.46E-04 2.i2E-04 3.91 E-03 9.17E-OS 1-131 Ci 1.68E-03 i.3SE-03 2.89E-02 6.68E-04 (4) 1-133 Ci S.86E-04 1.09E-03 1.39E-03 8.44E-OS 1-13S Ci
< LLD
< LLD
< LLD
< LLD c
Particulates half-life> 8 days (1 )
Total Release Ci 1.41 E-OS 2.74E-OS 8.41 E-OS 1.77E-OS 1.43E-04 I 21.9 I Average release rate for (2) period IJCi/sec 1.81 E-06 3.48E-06 i.06E-OS 2.23E-06 (3)
% of limit 6.43E-OS i.24E-04 3.7SE-04 7.67E-OS Mn-S4 Ci
< LLD
< LLD
< LLD
< LLD Co-S8 Ci
< LLD
< LLD
< LLD
< LLD Fe-S9 Ci
<LLD
<LLD
<LLD
<LLD Co-60 Ci
< LLD
< LLD
< LLD
< LLD Zn-6S Ci
< LLD
< LLD
< LLD
< LLD Y-88 Ci
< LLD
< LLD
< LLD
< LLD (4)
Nb-9S Ci
< LLD
< LLD
< LLD 3.46E-07 Sr-89 Ci
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD Cs-134 Ci
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD Ce-141 Ci
< LLD
< LLD
< LLD 1.67E-07 Ce-144 Ci
<LLD
<LLD
<LLD
<LLD Total For Period Ci O.OOE+OO O.OOE+OO O.OOE+OO S.i3E-07 (S)
Gross alpha radioactivity Ci i.69E-06 2.44E-06 7.17E-06 3.36E-06 Page 1 of 2
- d. Tritium
- 1. Total Release Ci 1.56E+01 1.64E+01 1.80E+01 1.68E+01
- 2. Average release rate for period wCi/sec 2.01E+OO 2.09E+OO 2.26E+OO 2.11 E+OO
- 3. Percent of limit 4.27E-03 4.44E-03 4.82E-03 4.50E-03
- e. Whole Body Dose
- 1. Beta airdose at site boundary due to noble gases (ODCM App A III.C) mrads 1.06E-02 5.84E-03 9.58E-03 6.25E-04
- 2. Percent limit 0/0 1.06E-01 5.84E-02 9.58E-02 6.25E-03
- 3. Gamma Airdose at Site boundary due to noble gasses (ODCM App A III.C) mrads 3.56E-03 1.88E-03 3.19E-03 9.94E-05
- 4. Percent limit 7.12E-02 3.76E-02 6.38E-02 1.99E-03
- f. Organ Dose
- 1. Maximum organ dose to public based on critical receptors (ODCM App A III.D) mrem 2.00E-02 1.62E-02 3.27E-01 8.26E-03
- 2. Percent of limit 2.67E-01 2.16E-01 4.36E+OO 1.10E-01 I Net Unidentified beta 1.41 E-05 I 2.7 4E-05 I 8.41 E-05 I 1.72E-05 I I Un ID Beta % of Release 4.19E-05 I Page 2 of 2
2 Waste 13 Pages Follow
2009 Plant Operating History Palisades Nuclear Plant (PNP) was on line on January 1,2009. PNP was taken off line on February 17, 2009, due to excessive control rod drive mechanism leakage. The plant was returned to service on February 21, 2009. PNP was taken off line on March 22, 2009, for a refueling outage, and was returned to service on May 2,2009.
PNP remained on line for the remainder of 2009.
A. Gaseous Effluents Tables A-1, "Gaseous Effluents - Summation of All Discharges," A-1A, "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, Band 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.
Dose Assessments "Dose Assessments, 10 1
I 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 Page 1 of 5
A definitive release rate or total activity released cannot be determined.
Conservatively, the same upper limit of 1 % estimate of total tritium activity released via batch releases that was used in 2007 and 2008 will be used for 2009 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 1 % of liquid radioactive waste discharge volume - 7698 gallons.
Estimated Activity of Each Radionuclide - 2.943 curies of tritium Effluent Monitoring Results - NI A On-site Monitoring Results - Monitoring well sample results are from 755 PCi/L to 217,351 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.
Remedial Actions Considered or Taken - None Calculated Member of Public Dose Attributable to the Release - Total body and organ dose are both 3.93E-4 mrem.
Calculated Member of Public Dose Attributable to the Discharge - Total body and organ dose are both 3.93E-4 mrem.
Page 2 of 5
1 repaired has been replaced.
NRC Notification, Date and contact Organization - The NRC was notified on December 10,2007, by P.
Non-Routine Planned Discharges During excavation to replace suspect piping, 5569 gallons of tritiated groundwater were pumped out and discharged to the mixing basin.
- 3.
Radioactive Waste Treatment System Changes None.
- 4.
Annual Land Use Census Changes
- 5.
There are no longer any beef cattle within five miles of the plant. Beef cattle were previously located in the southeast sector at 4.3 miles from the plant.
The garden previously located in the southeast sector at 1.49 miles from the plant is no longer there. The garden critical receptor is now located in the northeast sector at 1.67 miles. The residence critical receptor is unchanged.
Also unchanged is that there are no dairy cows or goats located within five miles of the plant.
Effluent System Inoperability No effluent monitor was out of service for more than 30 days.
on December
, 2009, and issued on Table 1.3, "Palisades show run use census information and 2004 to 2008 meteorological data.
1.4, Use Census," was updated to show the results of the 2009 land use census.
Table 1.4a, "Critical Receptors," was updated to show the critical receptors and their revised XOQ and DOQ values. Enclosure 1 contains the ODCM, Revision 23, per the requirements of Technical Specification 5.5.1.c.3.
- 7.
Process Control Program Changes None.
Page 3 of 5
None.
Groundwater Monitoring 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 pr.otected area to allow detection of radioactive contamination of ground water due to leaks or spills from plant systems. Monitoring well 3-07 is most indicative of the leak described above. Tritium levels ranged from a low of 755 pCi/L to a high of 217,351 pCilL. Monitoring wells 2-07 and 11-08 had tritium level highs of 1493 and 2854 pCi/L, respectively, and both showed lows of less than the minimum detectable activity. The remaining wells showed no activity throughout the year. Well locations are depicted in Figure 1.
SF 89, SF 90 and Liquid Doses In 2009, PNP used a nelA' vendor te analyze effluent samples for hard to detect radionuclides. This vendor has the ability to detect a lower concentration for Sr 89 and SF 90. These radionuclides IJllere detected in service vlater and turbine sump samples at low level concentrations. The maximum value Vilas 2.66E 8 IlCilm!. Consoquently, due to the high yearly service 'Nater volume (1.05 E10 gallons), this resulted in high Sr 89 and Sr 90 release activities. This in turn, resulted in higher calculated liquid organ doses to the public. (In 2008, the organ dose 'vivas 2.13E 3 mrem. In 2009, the organ dose '1.'as 3.70E 1 mrem). It is strongly believed that the Sr 89 and Sr 90 values are due to background radioactivity. Currently, PNP Page 4 of 5
r ii.~',jh1~ !
- rr./i'l3
.1!
Mwe*oe Bl-i12 FENCEUtJ2 Sf-IEETPILElRETAlNING WALL APPROXlMATESHOREUNE MONITORING \\\\lElL lOCAi!ON SOil BORING LOCATION figure 4.1 GROUNDWATER MONITORING WELL LOCATIONS PALISADES NUCLEAR POWER PLANT 27780 BLUE STAR HWY.
Covert Michigan 5
5
Summation of Units Quarter 1 All Releases Quarter 2 Quarter 3 Quarter 4 Total Uncertainty Fission and Activation Gases Ci 2.922E+01 1.941 E+OO 1.146E+00 1.977E+00 3.428E+01 8.344%
Average Release Rate 3.7S7E+00 2.469E-01 1.442E-01 2.488E-01 1.978E-03 1.19SE-04 7.2S9E-OS 8.736E-04 Ci 8.42SE-04 3.SSSE-04 3.S9SE-04 2.296E-04 Average Release Rate 4.523E-OS 2.888E-OS
% of Limit 1.401 E-OS Particulates O.OOOE+OO 4.04SE-07 Average Release Rate 1.068E-08 O.OOOE+OO
% of Limit O.OOOE+OO Tritium S.921 E+OO 4.112E+01 Average Release Rate Page 1 of 1
Fission and Activation Units Quarter 1 Quarter 2 Gases Ar-41 Ci NO NO Kr-85 Ci 1.890E-03 NO Kr-85m Ci 5.830E-04 NO Kr-87 Ci NO NO Kr-88 Ci NO NO Xe-131m Ci 3.636E-02 1.737E-02 Xe-133 Ci 5.790E+OO 1.053E+OO Xe-133m Ci 8.768E-02 4.420E-04 Xe-135 Ci 3.916E-01 NO Xe-135m Ci NO NO Xe-138 Ci NO NO (List Others)
Ci NO NO Total Ci 6.308E+OO 1.070E+OO lodines/Halogens Units Quarter 1 Quarter 2 1-131 Ci 1.832E-06 3.342E-07 1-132 Ci 1.020E-06 NO 1-133 Ci 2.244E-06 NO 1-134 Ci NO NO 1-135 Ci NO NO Total Ci 5.096E-06 3.342E-07 Particulates Units I Quarter 1 Quarter 2 Co-58 Ci NO NO Co-60 Ci NO NO Sr-89 Ci NR NR Sr-90 Ci NR NR Cs-134 Ci NO NO Cs-137 Ci NO NO Total Ci O.OOOE+OO O.OOOE+OO I Tritium I Ci 11.316E+01 I NR Gross Alpha NR NR NO = Measurements performed but no activity detected.
NR = Analysis not required & not performed Page 1 1
Quarter 3 Quarter 4 Total NO NO O.OOOE+OO NO NO 1.890E-03 NO NO 5.830E-04 NO NO O.OOOE+OO NO NO O.OOOE+OO NO NO 5.373E-02 4.793E-03 4.057E-04 6.847E+OO NO NO 8.812E-02 NO 7.700E-06 3.916E-01 NO NO O.OOOE+OO NO NO O.OOOE+OO NO NO O.OOOE+OO 4.793E-03 4.134E-04 7.383E+OO Quarter 3 Quarter 4 Total NO NO 2.166E-06 NO NO 1.020E-06 NO NO 2.244E-06 NO NO O.OOOE+OO NO NO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.430E-06 Quarter 3 Quarter 4 Total NO NO O.OOOE+OO NO NO O.OOOE+OO NR NR O.OOOE+OO NR NR O.OOOE+OO NO NO O.OOOE+OO NO NO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO I NR I NR 1 1.31 6E+01 I NR NR O.OOOE+OO
Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Gases Ar-41 Ci NO NO NO 3.358E-02 3.358E-02 Kr-85 Ci NO NO NO NO O.OOOE+OO Kr-85m Ci NO NO NO 1.812E-02 1.812E-02 Kr-87 Ci NO NO 7.500E-04 4.724E-02 4.799E-02 Kr-88 Ci NO NO NO 5.014E-02 5.014E-02 Xe-131 m Ci NO NO NO NO O.OOOE+OO Xe-133 Ci 2.290E+01 8.703E-01 1.138E+00 1.344E+00 2.626E+01 Xe-133m Ci NO NO NO NO O.OOOE+OO Xe-135 Ci 1.952E-03 6.920E-04 1.658E-03 2.072E-01 2.115E-01 Xe-135m Ci 3.920E-03 NO I 1.140E-03 9.600E-02 1.011 E-01 Xe-138 Ci NO NO NO 1.811 E-01 1.811 E-01 (List Others)
Ci NO NO NO NO 10.000E+00 Total Ci 2.291 E+01 8.710E-01 1.141 E+OO 1.977E+00 2.690E+01 lodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total 1-131 Ci 1.402E-04 1.986E-04 7.881 E-05 5.714E-05 4.747E-04 1-132 Ci 4.060E-04 NO NO NO 4.060E-04
\\-133 Ci 2.912E-04 1.566E-04 2.807E-04 1.724E-04 9.009E-04 1-134 Ci NO NO NO NO O.OOOE+OO 1-135 Ci NO NO NO NO O.OOOE+OO Total Ci 8.374E-04 3.552E-04 3.595E-04 2.296E-04 1.782E-03 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Co-58 Ci 1.190E-07 8.580E-08 3.270E-08 NO 2.375E-07 Co-60 Ci 2.240E-08 9.240E-08 3.910E-08 NO 1.539E-07 Sr-89 Ci NO NO NO NO O.OOOE+OO Sr-90 Ci NO NO N!:>
N!:>
O.OOOE+OO Cs-134 Ci NO NO NO NO O.OOOE+OO Cs-137 Ci NO NO 1.310E-08 NO 1.310E-08 Total Ci 1.414E-07 1.782E-07 8.490E-08 O.OOOE+OO 4.045E-07 I Tritium I Ci I 6.967E+00 I 9.187E+00 I 5.881 E+OO I 5.921 E+OO I 2.796E+01 I I I Gross Alpha I Ci I NO I NO I NO I NO I O.OOOE+OO I NO = Measurements performed but no activity detected.
Page 1 of 1
Summation of All Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Uncertai Fission and Activation Products (excluding tritium, gases, and gross alpha)
Ci 1.294E-02 5.022E-04 3.328E-04 9.190E-05 i.387E-02 15.438%
Average Concentration Ci/ml 3.905E-10 1.745E-11 8.297E-12 2.355E-12 of Limit 3.812E-04 2.625E-04 5.973E-05 Tritium 1.924 4.561 E+01 3.718E+01 2.219E+01 Average Concentration Cilml 5.806E-06 1.585E-06 9.268E-07 5.685E-07 2.108E-06 mit 5.749E-01 1.569E-01 9.154E-02 2.086E-01 Dissolved and Entrained Gases Ci 9.957E-03 1.760E+00 O.OOOE+OO O.OOOE+OO Average Concentration 3.005E-10 6.116E-08 O.OOOE+OO O.OOOE+OO 1.255E-08
% Of Lim 1.502 3.058E-02 O.OOOE+OO O.OOOE+OO 6.274E-03 Gross Alpha 9.767E-05 i.588E-05 2.557E-06 O.OOOE+OO 1.161 E-04 Average Concentration 2.947E-12 5.519E-13 6.373E-14 O.OOOE+OO 8.232E-13 Volume of Primary System Liquid Effluent (Before Dilution)
Liters 1.756E+06 6.959E+05 3.226E+05 1.390E+05 Dilution Water Used for Above Liters 3.314E+10 2.878E+10 4.011 E+10 3.902E+10 1.411 E+ 11 Volume of Secondary or Balance-of-Plant Liquid Effluent (e.g., low-activity or unprocessed)
(Before Dilution)
Liters 8.058E+09 1.507E+10 8.621E+09 8.012E+09 3.976E+10 Average Stream Flow m3/s 4.262E+00 3.660E+00 5.047E+00 4.910E+00 4.470E+00 Dilution flow rate (gal/qtr) = # of Dilution pumps running x days running/qtr x 4000 gpm/pump x min/day Page 1 of 1
Fission and Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Activation Products Cr-51 Ci ND ND ND ND O.OOOE+OO Mn-54 Ci 3.793E-04 ND ND ND 3.793E-04 Fe-55 Ci O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.274E-06 9.274E-06 Fe-59 Ci 1.854E-04 ND ND ND 1.854E-04 Co-57 Ci ND ND ND ND O.OOOE+OO Co-58 Ci 3.156E-03 2.369E-04 8.421 E-05 1.207E-05 3.489E-03 Co-60 Ci 8.538E-03 2.230E-04 2.179E-04 5.649E-05 9.036E-03 Sr-89 Ci 1.838E-05 ND 3.276E-06 ND 2.166E-05 Sr-90 Ci 6.014E-07 ND 6.172E-07 ND 1.219E-06 Nb-95 Ci 2.280E-05 ND ND ND 2.280E-05 Ag-110m Ci 4.589E-04 2.260E-05 ND 4.600E-06 4.861 E-04 Sn-113 Ci ND ND ND ND O.OOOE+OO Sb-124 Ci ND ND ND ND O.OOOE+OO Sb-125 Ci ND ND ND ND O.OOOE+OO 1-131 Ci 2.670E-06 ND ND ND 2.670E-06 1-133 Ci ND ND ND ND O.OOOE+OO 1-135 Ci ND ND ND ND O.OOOE+OO Cs-134 Ci ND ND ND ND O.OOOE+OO Cs-137 Ci ND 1.976E-05 2.683E-05 2.950E-06 4.954E-05 Ni-63 Ci O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.518E-06 6.518E-06 Zn-65 Ci 1.320E-05 ND ND ND 1.320E-05 Zr-95 Ci 9.300E-06 ND ND ND 9.300E-06 La-140 Ci 1.414E-04 ND ND ND 1.414E-04 Totals Ci 1.293E-02 5.022E-04 3.328E-04 9.190E-05 1.385E-02 Dissolved and Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Entrained Gases Kr-85 Ci ND ND ND ND O.OOOE+OO Kr-85m Ci ND ND ND ND O.OOOE+OO Kr-88 Ci ND ND ND ND O.OOOE+OO Xe-131 m Ci ND ND ND ND O.OOOE+OO Xe-133 Ci 9.957E-03 ND ND ND 9.957E-03 Xe-133m Ci ND ND ND ND O.OOOE+OO Xe-135 Ci ND ND ND ND O.OOOE+OO Xe-135m Ci ND ND ND ND O.OOOE+OO Totals 9.957E-03 O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.957E-03 Tritium Ci 1.905E+02 4.515E+01 3.672E+01 2.191 E+01 2.943E+02 Gross Alpha Ci 2.861 E-05 ND 2.557E-06 ND 3.116E-05 ND = None Detected Page 1 of 1
Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Products Cr-51 Ci NO NO NO NO O.OOOE+OO Mn-54 Ci NO NO
~O NO O.OOOE+OO Fe-55 Ci NO NO
~O NO O.OOOE+OO Fe-59 Ci NO NO NO NO O.OOOE+OO Co-57 Ci NO NO NO NO O.OOOE+OO Co-58 Ci NO NO NO NO O.OOOE+OO Co-60 Ci NO NO NO NO O.OOOE+OO Sr-89 Ci NO NO NO
'NO O.OOOE+OO Sr-90 Ci 1.528E-05 NO NO NO 1.528E-05 Nb-95 Ci NO NO NO NO O.OOOE+OO Ag-110m Ci NO NO NO NO O.OOOE+OO Sn-113 Ci NO NO NO NO O.OOOE+OO Sb-124 Ci NO NO NO NO O.OOOE+OO Sb-125 Ci NO NO NO NO O.OOOE+OO 1-131 Ci NO NO NO 0
O.OOOE+OO 1-133 Ci NO NO NO NO O.OOOE+OO 1-135 Ci NO NO NO NO O.OOOE+OO Cs-134 Ci NO NO NO NO O.OOOE+OO Cs-137 Ci NO NO NO NO O.OOOE+OO Ni-63 Ci NO NO NO NO O.OOOE+OO Zn-65 Ci NO NO NO NO O.OOOE+OO Zr-95 Ci NO NO NO NO O.OOOE+OO La-140 Ci NO NO NO NO O.OOOE+OO Totals Ci 1.528E-05 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.528E-05 Oissolved and Entrained Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Gases Kr-85 Ci NO 1.760E+OO NO NO 1.760E+OO Kr-85m Ci NO NO NO NO O.OOOE+OO Kr-88 Ci NO NO NO NO O.OOOE+OO Xe-131 m Ci NO NO NO NO O.OOOE+OO Xe-133 Ci NO NO NO NO O.OOOE+OO Xe-133m Ci NO NO I NO NO O.OOOE+OO Xe-135 Ci NO NO NO NO O.OOOE+OO Xe-135m Ci NO NO NO NO O.OOOE+OO Totals O.OOOE+OO 1.760E+OO O.OOOE+OO O.OOOE+OO 1.760E+OO I Tritium 1.912E+OO I 4.573E-01 4.586E-01 2.761 E-01 3.104E+OO I I Gross Alpha 6.907E-05 I i.588E-05 I NO 8.495E-05 I NO = None Oetected Page 1 of 1
Resins, Filters, and Volume Curies Shipped Evaporator Bottoms Waste Class ft" m"
Curies A
1.40E+02 3.96E+OO 1.45E-05 B
O.OOE+OO O.OOE+OO O.OOE+OO C
O.OOE+OO O.OOE+OO O.OOE+OO ALL 1.40E+02 3.96E+OO 1.45E-05 Major Nuclides for the Above Table:
H-3, Fe-55, Co-58, Co-60, Sr-90, Tc-99, Cs-134, Cs-137, Ce-144, Pu-241 Dry Active Waste Volume Curies Shipped Waste Class ft~
m~
Curies A
3.29E+04 9.33E+02 5.98E+OO B
O.OOE+OO O.OOE+OO O.OOE+OO C
O.OOE+OO O.OOE+OO O.OOE+OO ALL 3.29E+04 9.33E+02 5.98E+OO Major Nuclides for the Above Table:
H-3, Cr-51, Mn-54, Fe-55, Fe-59, Co-58, Co-60, Ni-63, Zr-95, Nb-95, Ag-110m, 1-131 Irradiated Components Volume Curies Shipped Waste Class ft~
m~
Curies A
O.OOE+OO O.OOE+OO O.OOE+OO B
O.OOE+OO O.OOE+OO O.OOE+OO C
O.OOE+OO O.OOE+OO O.OOE+OO ALL O.OOE+OO O.OOE+OO O.OOE+OO Other Waste Volume Curies Shipped Waste Class ft~
m~
Curies A
1.86E+03 5.27E+01 8.72E-01 B
O.OOE+OO O.OOE+OO O.OOE+OO C
O.OOE+OO O.OOE+OO O.OOE+OO ALL 1.86E+03 5.27E+01 8.72E-01 Major Nuclides for the Above Table:
H-3, Mn-54, Co-58, Co-60, Ni-63, Cs-137 Volume Curies Shipped Sum of All Low-Level Waste Shipped from Site Waste Class ft" m"
Curies A
3.49E+04 9.90E+02 6.85E+OO B
O.OOE+OO O.OOE+OO O.OOE+OO C
O.OOE+OO O.OOE+OO O.OOE+OO ALL 3.49E+04 9.90E+02 6.85E+OO Major Nuclides for the Above Table:
H-3, Cr-51, Mn-54, Fe-55, Fe-59, Co-58, Co-60, Ni-63, Zr-95, Nb-95, Ag-110m, 1-131, Cs-137 Page 1 of 1
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 4.11 E-03 1.83E-04 1.30E-04 3.83E-05 4.46E-03
% Of Limit 0.27%
0.01%
0.01%
0.00%
0.15%
Liquid Effluent Dose Limit, Any 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Organ Organ Dose 4.36E-03 2.21 E-04 1.65E-04 4.22E-05 4.79E-03
% of Limit 0.09%
0.00%
0.00%
0.00%
0.05%
Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Gamma Air Gamma Air Dose 8.42E-04 5.26E-05 3.19E-05 3.27E-04 1.25E-03
% of Limit 0.02%
0.00%
0.00%
0.01%
0.01%
Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Beta Air Beta Air Dose 2.41 E-03 1.57E-04 9.33E-05 2.80E-04 2.94E-03
% of Limit 0.024%
0.002%
0.001%
0.003%
0.015%
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 3.53E-03 2.46E-03 1.27E-03 1.14E-03 8.39E-03 (Iodine, Tritium, Particulates with
>8-Day half-life)
% of Limit 0.05%
0.03%
0.02%
0.02%
0.06%
Whole Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Dose 4.46E-03 8.39E-03 4.79E-03
% of Limit 0.02%
0.01%
0.02%
Page 1 of 1