ML041250411
ML041250411 | |
Person / Time | |
---|---|
Site: | Peach Bottom ![]() |
Issue date: | 04/25/2004 |
From: | Braun R Exelon Nuclear |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
+kBR1SISP20060424, -RFPFR, CCN 04-14042 | |
Download: ML041250411 (17) | |
Text
Exelkn.M Exelon Nuclear Telephone 717.456.7014 Nuclear Peach Bottom Atomic Power Station www.exeloncorp.com 1848 Lay Road Delta, PA 17314-9032 April 25, 2004 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station Unit Nos. 2 and 3
& Independent Spent Fuel Storage Installation (ISFSI)
Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 & ISFSI Docket 72-29
SUBJECT:
Radioactive Effluent Release Report No. 46 January 1, 2003 through December 31, 2003 Enclosed are two copies of the Radioactive Effluent Release Report No. 46, January 1, 2003 through December 31, 2003 for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.
This report is being submitted in compliance with 10CFR 50.36a (2) and the Technical Specifications of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of Regulatory Guide 10.1.
Additionally, this report is submitted to satisfy annual effluent reporting requirements of 10CFR72.44(d)(3).
No Revisions were made to the Offsite Dose Calculation Manual (ODCM) or Station Process Control Program (PCP) during this report period.
Sincerely, Robert C. Braun Site Vice President, Peach Bottom Atomic Power Station RCB/JAS/FLJ/dlo Enclosure Cc:
H. J. Miller, Administrator, Region I, USNRC J. Jang, Region I, USNRC Craig Smith, USNRC Senior Resident Inspector, PBAPS G. F. Wunder, Project Manager [PBAPS] USNRC ccn C) 4-I4o 1° 2E
PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 PBAPS Independent Spent Fuel Storage Installation Docket Number 72-29 RADIOACTIVE EFFLUENT RELEASE REPORT NO. 46 JANUARY 1, 2003 THROUGH DECEMBER 31, 2003 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56
TABLE OF CONTENTS SECTION PAGE Introduction 1
Regulatory Limits 2
Maximum Permissible Concentrations 3
Average Energy 3
Measurements and Approximations of Total Radioactivity 3
Batch Releases 5
Abnormal Releases 6
Minimum Detectable Concentrations 8
Meteorological Data 8
Gaseous Effluents - Summation of All Releases 9
Gaseous Effluents for Elevated Release Point - Main Stack 10 Gaseous Effluents for Ground Level Release Points -
11 Unit 2 and Unit 3 Roof Vents and Aux Boiler Stacks Liquid Effluents - Summation of All Releases 12 Liquid Effluents Release Points - Liquid Radwaste & RHR Leaks 13 Classes of Solid Radioactive Waste Shipments 14 Technical Concurrences: (for accuracy of information)
C risptqL Radste Manager
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC INTRODUCTION In accordance with the Reporting Requirements of Technical Specification 5.6.3 applicable during the reporting period, this report summarizes the Effluent Release Data for Peach Bottom Atomic Power Station Units 2 and 3 for the period January 1, 2003 through December 31, 2003. The notations E and E-are used to denote positive and negative exponents to the base 10, respectively.
The release of radioactive materials during the reporting period was within the Offsite Dose Calculation Manual Specification limits.
There were three unplanned releases of liquid radioactive material.
There were no gaseous or liquid radioactive releases from the Independent Spent Fuel Storage Installation, NRC Docket No 72-29 (ISFSI).
There were no changes to the station Process Control Program.
There were no changes to the ODCM during this reporting period. However, several procedures have been introduced which either relate to the ODCM or relate to this report.
The following common procedures provide consistent expectations and standards for Radioactive Effluents Controls Program.
- CY-AA-170-2100, Estimated Errors of Effluent Measurement
- CY-AA-170-000, Radioactive Effluent and Environmental Monitoring Program
- CY-AA-170-100, Radiological Environmental Monitoring Program CY-AA-170-200, Radioactive Effluent Controls Program
- CY-AA-170-300, Offsite Dose Calculation Manual Administration
- CY-AA-170-2100, Estimated Errors of Effluent Measurement
- CY-AA-1 70-31 00, Offsite Dose Calculation Manual Revisions I
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC
- 1. Regulatory Limits A. Noble Gases:
- 1.
' 500 mRem/Yr
<'3000 mRem/Yr
- 2.
' 1 0
<20
- 3.
'20
'40 mRad mRad mRad mRad
- total body
- skin
- air gamma
- air beta
- air gamma
- air beta ODCMS 3.8.C.1.a quarterly air dose limits ODCMS 3.8.C.2.a and b yearly air dose limits ODCMS 3.8.C.2.c and d B. lodines, Tritium, Particulates with Half Life >8 days:
- 1.
' 1500 mRem/Yr
- any organ
- 2.
' 15 mRem
- any organ
- 3.
' 30 mRem
- any organ C. Liquid Effluents
- 1.
Concentration ' 10 times 10 CFR 20, Appendix B, Table 2, Col. 2 ODCMS 3.8.C.1.b quarterly dose limits ODCMS 3.8.C.3.a yearly dose limits ODCMS 3.8.C.3.b ODCMS 3.8.B.1.a
- 2.
'3.0
< 10
- 3.
'6.0
' 20 mRem mRem mRem mRem
- total body
- any organ
- total body
- any organ quarterly dose limits ODCMS 3.8.B.2.a yearly dose limits ODCMS 3.8.B.2.b D. 40 CFR 190 and 10 CFR 72.104
< 25 mRem
' 75 mRem
< 25 mRem
< 3.0 mRem
< 55 mRem
- total body
- thyroid
- any other organ
- from liquid and gaseous effluent
- thyroid from gases ODCMS 3.8.D.1.a ODCMS 3.8.D.1.b ODCMS 3.8.D.1.c ODCMS 3.8.D.1.d ODCMS 3.8.D.1.e 2
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC
- 2. Maximum Permissible Concentrations:
Gaseous dose rates rather than effluent concentrations are used to calculate permissible release rates for gaseous releases. The maximum permissible dose rates for gaseous releases are defined in ODCMS 3.8.C.1a. and 3.8.C.1.b.
The Effluent Concentrations Limits (ECL) specified in 10 CFR 20, Appendix B, Table 2, Column 2 times 10, for identified nuclides, are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Offsite Dose Calculation Manual Specification 3.8.B.1.
The total activity concentration for all dissolved or entrained gases is limited to
< 2E-04 ACi/ml.
- 3. Average Energy:
The Peach Bottom ODCM limits the dose equivalent rates due to the release of noble gases to less than or equal to 500 mRem/year to the total body and less than or equal to 3000 mRem/year to the skin. Therefore, the average beta and gamma energies of the radionuclide mixture in releases of fission and activation gases as described in Regulatory Guide 1.21, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," are not applicable to Peach Bottom.
- 4. Measurements and Approximations of Total Radioactivity:
A. Fission and Activation Gases:
The method used for Gamma Isotopic Analysis is the Canberra Genie System with a gas Marinelli beaker. Grab samples are taken and analyzed at least monthly to determine the isotopic mixture of noble gas activity released for the month. Airborne effluent gaseous activity was continuously monitored and recorded in accordance with ODCMS Table 4.8.C.1. The data from the noble gas radiation monitor was analyzed to report noble gas effluent activities. When no activity was found in the grab isotopic analysis, the isotopic mixture was assumed to be that specified in ODCM IV.B. If activity was found in the grab isotopic analysis, the isotopic mixture for the Noble Gas Monitor was determined from that isotopic mixture.
B. lodines:
The method used is the Canberra Genie System with a charcoal cartridge.
Iodine activity was continuously sampled and analyzed in accordance with ODCMS Table 4.8.C.1.
3
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC C. Particulates:
The method used is the Canberra Genie System with a particulate filter (47 mm).
Particulate activity was continuously sampled and analyzed in accordance with ODCM Table 4.8.C.1.
Composite particulate air samples and gross alpha were submitted to an offsite vendor laboratory for analysis of Sr-89, Sr-90 and gross alpha.
D. Liquid Effluents:
Gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release using the Canberra Genie System in accordance with ODCMS Table 4.8.B.1. The total activity of a released batch is determined by multiplying each nuclide's concentration by the total volume discharged.
Composite liquid radwaste samples counted for tritium and submitted to an offsite vendor laboratory for analysis of Fe-55, Sr-89, Sr-90 and gross alpha.
E. Estimated Total Error Present CY-AA-170-2100, Estimated Errors of Effluent Measurements, provides the methodology to obtain an overall estimate of the error associated with radioactive effluents.
4
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC
- 5. Batch Releases:
A. Liquid:
QTR 1 QTR 2 QTR 3 QTR 4 Number of batch releases:
12 7
5 12 Total Time for batch releases 2854 1791 1143 2744 (minutes)
Maximum time period for batch 282 307 275 290 release (minutes):
Average time period for batch release 238 256 229 229 (minutes):
Minimum time period for batch 140 155 80 80 release (minutes):
Dilution volume (liters):
7.29E9 8.67E9 5.84E9 1.25E10 B. Gaseous:
QTRI QTR 2 QTR 3 QTR 4 Number of batch releases:
0 0
0 0-I0 Total Time for batch releases 0
0 0
0 (minutes)
Maximum time period for batch 0
0 0
0 release (minutes):
Average time period for batch release 0
0 0
0 (minutes):
Minimum time period for batch 0
0 0
0 release (minutes):
5
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC
- 6. Abnormal Releases:
A. Liquid:
- 1. Event description - 2C Residual Heat Removal (RHR) to High Pressure Service Water (HPSW) leak On 5/16/01, routine sampling of the HPSW effluent to the discharge canal detected low-level radioactive contamination. Subsequent investigation determined that a trace amount (0.060 gpm) of condensate stay-full or primary coolant water was leaking through the Unit 2C RHR heat exchanger into the 2A loop of the HPSW system. Multiple attempts to locate and repair this leak have been partially successful. However, the 2C RHR continued to be a source of contamination through all of 2003 Analysis of Releases It was estimated that the contaminated water released to the discharge canal for all of 2003 was responsible for 7.25E-4 mRem total body dose, and 4.28E-3 mRem Critical Organ dose. This dose contribution was well below the limits specified in the ODCM.
Representative samples were analyzed for all the parameters of radioactive effluent releases. The dose contributions and isotope quantities from the releases were added to this Radioactive Effluent Release Report for the applicable reporting periods.
- 2. Event description - 3A Residual Heat Removal (RHR) to High Pressure Service Water (HPSW) leak On 09/30/02, routine sampling of the 3A HPSW effluent radiation monitor to the discharge canal detected low-level radioactive contamination.
Subsequent investigation determined that a trace amount (0.012 gpm) of condensate stay-full or primary coolant water was leaking through the Unit 3A RHR heat exchanger into the 3A loop of the HPSW system. Attempts to locate and repair this leak have been partially successful. However, the 3A RHR continued to be a source of contamination through all of 2003 Analysis of Releases It was estimated that the contaminated water released to the discharge canal for all of 2003 was responsible for 8.94E-4 mRem total body dose, and 2.29E-3 mRem Critical Organ dose. This dose contribution was well below the limits specified in the ODCM.
6
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Representative samples were analyzed for all the parameters of radioactive effluent releases. The dose contributions and isotope quantities from the releases were added to this Radioactive Effluent Release Report for the applicable reporting periods.
- 3. Event description - 3D Residual Heat Removal (RHR) to High Pressure Service Water (HPSW) leak On 07/11/02, sampling of the 3B HPSW effluent radiation monitor, in response to the HPSW radiation alarm during pump run, detected low-level radioactive contamination. Subsequent investigation determined that a trace amount (0.071 gpm) of condensate stay-full or primary coolant water was leaking through the Unit 3D RHR heat exchanger into the 3B loop of the HPSW system. The leak was repaired on 07/09/03.
Analysis of Releases It was estimated that the contaminated water released to the discharge canal for all of 2003 was responsible for 1.41 E-3 mRem total body dose, and 2.37E-3 mRem Critical Organ dose. This dose contribution was well below the limits specified in the ODCM.
Representative samples were analyzed for all the parameters of radioactive effluent releases. The dose contributions and isotope quantities from the releases were added to this Radioactive Effluent Release Report for the applicable reporting periods.
B. Gaseous:
No abnormal releases.
7
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC
- 7. Minimum Detectable Concntrations:
A. Liquid:
If a radionuclide was not detected,< LLD was reported for that isotope.
Samples were analyzed with techniques that achieved the required Lower Limits of Detection (LLD) as specified in Offsite Dose Calculation Manual Specification Table 4.8.B.1, Radioactive Liquid Waste Sampling and Analysis. In all cases, the LLD requirements were satisfied.
B. Gaseous:
If a radionuclide was not detected, < LLD was reported for that isotope.
Samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in Offsite Dose Calculation Manual Specification Table 4.8.C.1, Radioactive Gaseous Waste Sampling and Analysis from Main Stack and Vent Stack. In all cases, the LLD requirements were satisfied.
- 8. Meteorological Data The meteorological data can be found in the Annual Radiation Dose Assessment Report for January 1, 2003 through December 31, 2003.
8
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC
-PSEG Nuclear, LLC Gaseous Effluents - Summation Of All Releases Period: 2003 A. F n A
o Quarter Quarter Quarter Quarter Est. Total A.
Fission & Activation Gases Unit 1
2 3
4 Error %
- 1. Total Release Ci 8.24E+01 9.51E+01 2.98E+02 3.09E+02 3.51E+01
- 2. Average release rate for the period pCi/sec 1.05E+01 1.21 E+01 3.78E+01 3.93E+01
- 3. Percent of ODCM limit - Gamma 1.68E-01 1.94E-01 3.21 E-01 2.61E-01
- Beta 5.90E-02 6.75E-02 1.12E-01 1.01E-01 B. lodines
- 1. Total iodine - 131 Ci 8.44E-05 1.20E-04 l 5.59E-04 3.11E-04 1.76E+01
- 2. Average release rate for period pCi/seci 1.07E-05 1.52E-05 7.11 E-05 3.96E-05
- 3. Percent of ODCM Limit C. Particulates
- 1. Particulates with half-lives > 8 days Ci 1.27E-04 7.15E-05 7.91E-05 1.62E-04 1.94E+01
- 2. Average release rate for the period pCi/sec 1.61E-05 9.10E-06 1.01E-05 2.06E-05
- 3. Percent of ODCM Limit
- 4. Gross alpha radioactivity Ci 5.37E-06
<LLD
<LLD
<LLD D. Tritium
- 1. Total release Ci
<LLD
<LLD 11.89E+01
<LLD 1.11E+01
- 2. Average release rate for the period pCi/sec
<LLD
<LLD 2.40E+00
<LLD
- 13. Percent of ODCM Limit I %
- 1
- 17_
E. Iodine 131 & 133,Tritium & Particulate
- 11. Percent of ODCM limit I % I 3.86E-03 I 5.37E-03 I 2.33E-02 I 1.34E-02l
9
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Gaseous Effluents Release Point - Main Stack Period: 2003 INUCLIDES RELEASED CONTINUOUS MODE l_
BATCH MODE F_
Quarter I Quarter j Quarter Quarter Quarter Quarter Quarter Quarter
- 1. FsingssUit 1
l 2
3 1
4 l 1 I 3
4 Kr-85 Ci
<LLD
<LLD
<LLD
<LD
<LLD
<LLD
<LLD
<LLD Kr-85m Ci
<LLD 1.53E+00 1.82E+00 6.74E+00
<LLD
<LLD
<LLD
<LLD Kr-87 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Kr-88 Ci
<LLD
<LLD 6.16E-01 3.63E-01
<LLD
<LLD
<LLD
<LLD Xe-1 33 Ci
<LLD 6.95E+00 1.18E+02 3.94E+01
<LLD
<LLD
<LLD
<LLD Xe-135 Ci
<LLD 2.13E+00 3.99E+01 7.18E-01
<LLD
<LLD
<LLD
<LLD Xe-135m Ci
<LLD
<LLD 1.07E+01
<LLD
<LLD
<LLD
<LLD
<LLD Xe-I 38 Ci
<LLD
<LLD 8.68E-01
<LLD
<LLD
<LLD
<LLD
<LLD Ar-41 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Xe-133m Ci
<LLD
<LLD 1.71 E+00
<LLD
<LLD
<LLD
<LLD
<LLD Unidentified Ci 1.78E+01 9.65E+oO
<LLD
<LLD
<LLD
<LLD
<LLD CLLD Total for Period -Ci
.78E+01 2.03E+01 1.74E+02 4.72E+01
<LLD
<LLD
<LLD
<LLD
[2. Iodines U Initll 1-;---
7 1-131 Ci 2.30E-05 l 3.72E-05 l 2.55E-04 1.26E-04
'<LLD l <LLD
<LLD
< <LLD 1-133 Ci 2.59E-05l 7.26E-05 1.92E-04 2.17E-05
<LLD 1 <LLD
<LLD
.<LLD 1-135 Ci
<LLD
<LLD
<LLD
<LLD
<LLD l <LLD
<LLD
<LLD Total for Period Ci 4.89E-05 1.10E-04l 4.47E-04l 1.48E-04l <LLD r <LLD
<LLD
<LLD
- 13. Particulates I Unitll -_-__
Sr-89 Ci 3.21E-05 3.39E-05 3.01E-05 7.90E-05
<LLD
<LLD
<LLD
<LLD Sr-90 Ci
<LLD 4.OOE-08
<LLD-
<LLD
<LLD
<LLD
<LLD
<LLD Cs-I 34 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cs137 Ci I
<LLD
<LLD
<LLD 4.40E-07
<LLD
<LLD
<LLD
<LLD Ba-140
- Ci 2.26E-05 1.77E-05 5.35E-06 5.26E-05
<LLD
<LLD
<LLD
<LLD La-140 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cr-51 Ci
<LLD
<LLD 3.06E-06
<LLD 1
LD
<LLD
<LLD
<LLD Mn-54 Ci
<LLD
<LLD
<LLD
<LLD 1<LLD
<LLD
<LLD
<LLD Co-58 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Co-60 Ci
<LLD 3.OOE-07 1.06E-06
<LLD
<LLD
<LLD
<LLD
<LLD Mo-99 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ag-110m Ci
<LLD
<LLD
<LLD 7.60E-07
<LLD
<LLD
<LLD
<LLD Ce-141 Ci
<LLD
<LLD 1.30E-07
<LLD
<LLD
<LLD
<LLD
<LLD Ce-144 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD I
I C i 11_
1_
1_
1_1 1_
_1 I
I C i 11 1
1 1
11 1
_1_1_1 Total for Period C
5.47E-05 5.19E-05 3.97E-05 1.33E-04ll
<LLD
<LLD
<LLD
<LLDl 10
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Gaseous Effluents Release Point - Unit 2 & Unit 3 Roof Vents & Aux Boiler Stacks Nuclides Released Continuous Mode Batch Mode Fs Uit Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1
mI
<LLI gases D
<LLD 2
3 4
I 2
3 4
Kr-85m Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Kr-85m Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Kr-87 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Kr-88 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Xe-133 Ci
<LLD
<LLD
<LLD 1.64E+02
<LLD
<LLD
<LLD
<LLD Xe-135 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Xe-1 35m Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Xe-138 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ar-41 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Xe-133m 0
i
<LLD
<LLDW <LLD X <LLAD
<LLD <LLD= <LLDS <LLD Unidentified Ci 6.46E+01 7.48E+01 1.24E+02 9.80E+01
<LLD
<LLD
<LLD
<LLD Total for Period Ci 6.46E+01 7.48E+01 1.24E+02 2.62E+02
<LLD
<LLD
<LLD
<LLD
- 12. lodines I UnitIl - - -
1-131 Ci 6.14E-05 8.26E-05 3.04E-04 1.85E.04
<LLD
<LLD
<LLD [
<LLD 1-133 Ci 7.63E-05 1.08E-04
<LLD
<LLD
<LLD
<LLD
<LLD I <LLD 1-135 l
<LLD I <LLD l <LLD
<LLD
<LLD
<LLD
<LLD l <LLD TotalforPeriod T _Ci_1
_38E-04_1.90E-04 3.04E-04 1.85E-04
<LLD
<LLD
<LLD
<LLD 13U Particulates
..nit.l
-_ -=_:_-_____----r -
-- II -
Sr-89 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Sr-90 Ci 9.80E-07
<LLD-
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cs-134 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cs137 Ci 2.19E-05 1.96E-05 3.08E-05
<LLD
<LLD
<LLD
<LLD
<LLD Ba-140 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD La-140 Ci
<LLD I <LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cr-51 Ci l<LLD
<LLD lLLD
<LLD
<LLD
<LLD
<LLD
<LLD Mn-54 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Co-58 Ci
<LLD
<LLD CLLD
<LLD
<LLD
<LLD
<LLD
<LLD Co-60 Ci 2.14E-05
<LLD 8.56E-06
<LLD
<LLD
<LLD
<LLD
<LLD Mo-99 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Aq-11Om l Cl
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ce-141 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ce-144 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Zn-65 Ci 2.78E-05l
<LLD
<LLD 2.95E-05
<LLD
<LLD
<LLD
<LLD Total for Period Ci 7.20E-05 1.96E-05l 3.94E-05l 2.95E-05
<LLD
< LLD
<LLD
<LLD I1I
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Liquid Effluents - Summation Of All Releases Period: 2003 A. FISSION & ACTIVATION Quarter Quarter Quarter Quarter Est. Total PRODUCTS Unit 1
2 3
4 Error %
- 1. Total Release (not including tritium, Ci 2.72E-02 2.73E-02 1.62E-02 3.49E-02 2.11 E+01 gases & alpha)
- 2. Average diluted concentration during PjCVmL 3.73E-09 3.75E-09 2.22E-09 4.78E-09 batch discharges for the period
- 3. Percent of ODCM limit - Whole Body 5.15E-02 2.88E-02 1.01E-02 2.56E-02
- Organ 3.47E-02 2.08E-02 1.21E-02 2.90E-02 B. TRITIUM
- 1. Total Release Ci 7.03E+00 3.44E+00 2.43E+00 3.56E+00 6.40E+00l
- 2. Average diluted concentration during pCi/mL 9.64E-07 3.96E-07 4.15E-07 2.84E-07 batch discharges for the period
- 3. Percent of ODCM limit C. DISSOLVED & ENTRAINED GASES
- 1. Total Release Ci 3.66E-06 3.66E-06 3.66E-06 3.66E-06 2.11E+01
- 2. Average diluted concentration during pCi/mL 5.02E-13 4.22E-13 6.27E-13 2.93E-13 batch discharges for the period
- 3. Percent of ODCM limit D. GROSS ALPHA ACTIVITY
- 1. Total release Ci
<LLD
<LLD
<LLD 5.28E-05 2.30E+01
- 2. Average diluted concentration during pCimL
<LLD
<LLD
<LLD 4.22E-12 batch discharges for the period E. VOLUME OF WASTE RELEASED Liters 6.61E+05 4.13E+05 3.05E+05 6.59E+05 5.00E+00 (prior to dilution)
Lits I
F. VOLUME OF DILUTION WATER USED DURING BATCH Liters 7.29E+09 8.67E+09 5.84E+09 1.25E+10 2.22E+01 DISCHARGES WATER USED DURING FERIOD Liters 3.98E+11 5.9E+11 5.59E+11 4.73E+11 2.22E+01
12
- e :
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Liquid Effluents Release Point - Liquid Radwaste & RHR Leaks Period: 2003
[NUCLIDES RELEASED CONTINUOUS MODE 1_
BATCH MODE I
.Fssiongasesnt Quarter Quarter Quarter Quarter ][Quarter Quarter Quarter JQuarter
- 1. FsngssU it 1
2 3
4 l1 I
2 3
4 Sr-89 Ci 1.86E-06 1.88E-06 6.90E-07 6.73E-06
<LLD
<LLD
<LLD
<LLD Sr-90 Ci 6.90E-07 6.98E-07 1.79E-07 1.29E-07
<LLD
<LLD
<LLD
<LLD Cs-i 34 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cs137 Ci 3.73E-04 3.77E-04 9.47E-05 6.74E-05 1.1 8E-04 1.26E-05
<LLD 2.26E-06 1-131 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Co-58 Ci 2.88E-04 2.92E-04 2.95E-04 8.44E-04
<LLD
<LLD
<LLD
<LLD Co-60 Ci 1.64E-02 1.66E-02 8.32E-03 1.25E-02 3.45E-05 3.64E-05 1.12E-04 2.02E-04 Fe-59 Ci 3.47E-04 3.51 E-04 3.55E-04 1.42E-03
<LLD
<LLD
<LLD
<LLD Zn-65 Ci 1.30E-03 1.31 E-03 8.25E-04 2.94E-03 6.52E-05 4.92E-05 2.41E-04 1.48E-04 Mn-54 Ci 7.15E-03 7.23E-03 4.80E-03 7.15E-03
<LLD
<LLD 3.38E-05 3.51 E-05 Cr-51 Ci 7.73E-04 7.81E-04 7.90E-04 8.06E-03
<LLD
<LLD
<LLD 3.08E-04 Zr-95 Ci 1.21E-04 1.22E-04 5.43E-05 4.77E-05
<LLD
<LLD
<LLD
<LLD Nb-95 Ci 5.15E-05 5.21 E-05 5.27E-05 1.27E-04
<LLD
<LLD
<LLD
<LLD Mo-99 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Tc-99m Ci
<LD
<LD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ba-140 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD La-140 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ce-141 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ag-11Om Ci 7.25E-05 7.33E-05 2.51E-05 1.27E-04
<LLD
<LLD 5.53E-05 3.12E-04 Fe-55 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1.01E-04 4.55E-04 P-32 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Sb-124 Ci 3.08E-05 3.11E-05 3.14E-05 9.76E-05
<LLD
<LLD
<LLD
<LLD Hf-181 Ci
<LLD
<LLD
<LLD 2.98E-05
<LLD
<LLD
<LLD
<LLD ci ci
_ T ci Ci Total for Period Ci 2.70E-02 2.73E-02 1.56E-02 3.34E-02 2.18E-04 9.82E-05 5.43E-04 1.46E-03 IXe-133 Ci R LLD I <LLD I <LLD
<LLD II LLD I <LLD I 2.09E-061
<LLD IXe-135 l CI
<LLD I <LLD I <LLD
<LLD 11
<LLD 11.57E-061
<LLD I <LLD I 13
I V Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (O1/01/03712/31/03)
PEACH BOTTOM UNITS 2 & 3 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS Individual Total Total # of Waste Description Volume Volume Total Principal Shipments (source of waste)
Container/Type (cubic ft)
(cubic ft)
Curies Radionuclides CLASS A 17 Dewatered Resin HIC/Type A Cask 195.7 3326.9 1.38E+02 Co-60, Zn-65, Fe-55, Cs-137, Mn-54 I
DAW (Metal)
HIC/Type A Cask 95.9 95.9 7.66E+00 Co-60, Mn-54, Fe-55, Zn-65, Ag-1 Om. Ni-63 X
DAW (1)
Metal BoxISTC variable 1391.0 7.31 E-02 Co-60, Mn-54, Cs-137, Zn-65, Fe-55 53 DAW (2)
Metal BoxISTC variable 830.7 9.67E-02 Co-60, Mn-54, Cs-137, l_
Zn-65, Fe-55
(*)
Dewatered Metal Box/STC variable 165.5 1.16E+00 Co-60, Cs-137, Mn-54, Filters (2)
Zn-65, Fe-55 (M)
Incinerator Metal Box/STC variable 21.1 7.53E-02 Co-60, Fe-55, Mn-54, Ash (2)
Metal BoxISTC variable 3283.7 2.41E-0I Co-60, Mn-54, Cs-137, Zn-65, Fe-55 CLASS B 2
Dewatered Resin HIC/Type A Cask 195.7 391.4 2.14E+02 Co-60, Fe-55, Zn-65, Cs-137, Mn-54 I
Dewatered Resin HICtType B Cask 135.8 135.8 6.25E+02 Co-60, Fe-55, Mn-54, Ni-63, Zn-65 I
Dewatered Filters HIC/Type B Cask 120.3 120.3 5.90E+01 Co-60, Mn-54, Zn-65 Fe-55, Fe-59 1
Dewtrd Filters & DAVV HIC/Type B Cask 120.3 120.3 1.30E+02 Co-60, Mn-54, Fe-55,
_ _Cr-51.
Zn-65 CLASS C 4
Irradiated Hardware f Liner/Type B Cask 57.4 229.6 f 5.81 E+04 MC-60, Fe-55, Ni-63, l
l l
l l
Mn-54, Ta-1 82 TOTALS 10112.2 5.93E+04 NOTES:
(1) - Indicates actual total PBAPS waste shipped from Radiological Assistance, Consulting & Engineering (RACE) to burial after processing.
(2) - Indicates actual total PBAPS waste shipped from Duratek to burial after processing.
(3) - Indicates actual total PBAPS waste shipped from Alaron to burial after processing.
( ) - Shipment total Included with DAW from Duratek as these shipments contained comingled waste streams.
14