ML051250404
ML051250404 | |
Person / Time | |
---|---|
Site: | Peach Bottom ![]() |
Issue date: | 04/27/2005 |
From: | Braun R Exelon Nuclear |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
+kBR1SISP20060424 | |
Download: ML051250404 (25) | |
Text
iw Exe 16 nSm Exelon Nuclear Telephone 717.456.7014 ExeI l ea Peach Bottom Atomic Power Station www.exeloncorp.com 1848 Lay Road Delta, PA 17314-9032 April 27, 2005 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. 47 January 1, 2004 through December 31, 2004 Enclosed are two copies of the Radioactive Effluent Release Report No. 47, January 1, 2004, through December 31, 2004, 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 for the ISFSI required by the Offsite Dose Calculation Manual (ODCM).
No Revisions were made to the ODCM.
Sincerely, Robert C. Braun Site Vice President, Peach Bottom Atomic Power Station RCB/JPG/FLJ/GRS Enclosures (2) ccn 05-14052 cc:
S. J. Collins, Administrator, Region I, US NRC G. F. Wunder, Project Manager, US NRC US NRC Senior Resident Inspector, PBAPS A4
- $tV7
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. 47 JANUARY 1, 2004 THROUGH DECEMBER 31, 2004 Submitted to The United States Nuclaea~r Regulatory Commission P~,rsua-nt to Fa cility 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 7
Meteorological Data 7
Gaseous Effluents - Summation of All Releases 8
Gaseous Effluents for Elevated Release Point - Main Stack 9
Gaseous Effluents for Ground Level Release Points -
10 Unit 2 and Unit 3 Roof Vents and Aux Boiler Stacks Liquid Effluents - Summation of All Releases 11 Liquid Effluents Release Points - Liquid Radwaste & RHR Leaks 12 Classes of Solid Radioactive Waste Shipments 13 Technical Concurrences: (for accuracy of information)
Chemistry / Radwaste 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, 2004 through December 31, 2004. 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 two unplanned releases of liquid radioactive material.
There were no gaseous or liquid radioactive releases from the Independent Spent Fuel Storage"Installation, NRC Dncket No-72-29 (ISFSI).
Revision 3 to RW-AA-1 00 "Process Control 'Program for Radioactive Waste" was approved to correct typographical errors, clarify definitions and the approval process requirements. None of the changes in this revision changed the actual station Process Control Program. This procedure is enclosed with this report.
There were no changes to the ODCM during this reporting period.
Exelon common procedures which provide consistent expectations and standards for Radioactive Effluents Controls Program were used to generate this report. They are:'-
- CY-AA-170-000, Radioactive Effluent and Environmental Monitoring Program
- CY-AA-170-100, Radiological Environmental Monitoring Program
- CY-AA-1 70-200, 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 Calculatioh Manual Revisions 1
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 mRemNr
- 2.
- 10
- 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.
O 1500 mRemIYr
- any organ
- 2.
< 15 mRem
-anyorgan
- 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
- 75
- 25
- 3.0 mRem mRem mRem 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
- 55 mRem 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. Thermaximum permissible dose rates for gaseous releasesare 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 3.8.8.1.
The total activity concentration for all dissolved or entrained gases is limited to
- 2E-04 gCi/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. Iodines:
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.
32
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, kILC 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-170-21 00, Estimated Errors of Effluent Measurements, provides the methodology to obtain an overall estimate of the error associated with radioactive effluents.
4
I Facility: Peach Bottom Units 2 &3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC
- 5. Batch Releases:
A. Liquid:
l QTR 1 QTR 2 QTR 3 QTR 4 Number of batch releases:
-49 6
12 19 Total Time for batch releases 13074 1506 3333 4566
-(minutes)
Maximum time period for batch
- 335 300 302 332 release (minutes)
- -:
- _i_-_-
Average time period for batch release 267 251 278 240 (minutes):
Minimum time period for batch 85 91 223 35 release l
(minutes):
,i Dilution volume (liters):
4.16E10 7.70E9 1.03E10 1.48E10 B. Gaseous:
QTR 1 QTR 2 QTR 3 QTR 4 Number of batch releases:
- 1 0
°_l Total Time for batch releases 1
0 0
0 I
(minutes)-.
Maximum time period for batch I
1 0
jo 0
- re lease (m inutes).
Average time period for batch release-1 0
0 0
(minutes):
i';
Minimum time period for batch 1
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 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 2004 (0.006 gpm)
Analysis of Releases It was estimated that the contaminated water released to the discharge canal for all of 2004 was responsible for 8.17E-4 mRem total body dose, and 9.82E-3 mRem Critical Organ (Teen Liver) 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 2004.
Analysis of Releases It was estimated that the contaminated water released to the discharge canal for all of 2004 was responsible for 1.47E-3 mRem total body dose, and 3.20E-3 mRem Critical Organ (Teen Liver) 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.
B. Gaseous:
No abnormal releases.
- 7. Minimum Detectable Concentrations:
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, 2004 through December 31, 2004.
7.:
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Gaseous Effluents - Summation Of All Releases Period: 2004 A.
Fission & Activation Gases Unit Quarter Quarter Quarter Quarter 1Est. Total Un__________________
it___
1 2
3 J
4 JError %
- 1. Total Release Ci 2.60E+02 1.23E+02 1.92E+02 1.68E+02 3.51 E+01
- 2. Average release rate for the period pCi/sec 3.07E+01 1.57E+01 2.44E+01 2.14E+01
- 3. Percent of ODCM limit - Gamma 2.55E-01 2.09E-01 2.15E-01 J 1.86E-01
- Beta 8.85E-02 l 7.20E-02 7.65E-02 6.55E-02 B. Iodine
- 1. Total iodine - 131 Ci 1.28E-04 3.38E-04 5.27E-04 1.05E-04 1.76E+01
- 2. Average release rate for period pCi/sec 1.51 E-05 4.30E-05 6.70E-05 1.34E-05
- 3. Percent of limit C. Particulates
- 1. Particulates with half-lives > 8 days Ci 1.90E-04 1.61 E-04 1.11 E-04 7.11 E-05 1.94E+01
- 2. Average release rate for the period pCi/sec 2.25E-05 2.05E-05 1.41 E-05 9.04E-06
- 3. Percent of limit
- 4. Gross alpha radioactivity Ci
<LLD
<LLD
<LLD
<LLD D. Tritium
- 1. Total release Ci
<LLD
<LLD
<LLD
<LLD 1.11 E+01
- 2. Average release rate for the period pCi/sec
<LLD
<LLD
<LLD
<LLD
- 3. Percent of limit
!E. Iodine 131 & 133,Tritium & Particulate l
- 1. Percent of ODCM limit 4.64E-03 1.41 E-02 2.36E-02 3.02E-03
8
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Gaseous Effluents Release Point - Main Stack Period: 2004 lNUCLIDES RELEASED CONTINUOUS MODE l
BATCH MODE
- 1. Fission g Unitl Ouarter l Ouarter [
Ouarter l Ouarter]( Ouarter J Ouarter Quarter j Ouarter 1 l 3
l l
2 l
3 l
4 l
Kr-85 Ci
<LLD
<LLD
<LLD I <LLD
<LLD
<LLD
<LLD
<LW Kr-85m Ci 1.48E+01 3.14E+00 2.23E+00 8.61 E+00
<LLD
<LLD
<LLD
<LLD Kr-87 Ci 5.58E-01
< <LLD
-LLD 6.77E-01
<LLD
<LLD
- <LLD
<LLD Kr-88 Ci 8.68E+00
<LLD 1.44E-01 4.48E+00
<LLD
<LLD
<LLD
<LLD Xe-133 Ci 1.33E+02 3.72E+01 6.64E+01 6.74E+01
<LLD
<LW
<LLD
<LLD Xe-135 Ci 4.87E+0C 1.26E+00 1.00E+00 1.19E+O1
<LLD
<LLD
<LLD
<LLD Xe-135m Ci
<LLD
<LLD
<LLD. ; <LLD i
<LLD
<LLD
<LLD
<LLD Xe-1 38 Ci
<LLD
<LLD 1.47E+OC
<LLD
<LLD
<LLD
<LLD
<LLD Ar-41 Ci
'<LLD.<LLD
<LLD
<LLD
<LLDW
<LLD
<LLD
<LLD Xe-133m Ci
<LLD
'<LLD
<LWD
<LLD
<LLD
<LLD
<LLD
<LLD Unidentified Ci-
<LLD
<cLLD
<LD 3.69E+00
<LLD
<LLD
<LLD
<LLD Total for Period Ci 1.62E+02 4.16E+01 7.12E+01 9.68E+01
<LLD I <LLD
<LLD
<LLD
[2. lodines U_--
t:
I1-131 Ci - 8.58E-05 1.46E-04 1.42E-04 7.96E-05
<LLD
<LLD
<LLD
<LLD 1-1 33!
Ci 4.63E-05 1.18E-04.1.31E-04 4.58E-05
<LLD
<LLD
<LLD
<LLD 1-135 Ci
.<LLD
<LLD
.,<LLD
<LLD I<LLD
<LLD
-<LLD
<LLD Total fOr Period Ci 1.32E-04 2.64E-04 2.73E-04 1.25E-04
<LLD
<LLD
<LLD
<LLD
[3. Particulates I UnitII 7
i 1
Sr-89 Ci 8.05E-05 8.63E-05 6.59E-05 3.93E-05
<LLD
<LLD I <LLD
<LLD Sr-90 Ci
'<LLD
- 1 <LLD l
- <LLD I <LLD I<LLD i<LLD
<LLD I LLD CS-19 Ci
- <LLD
- <LLD
<LLD -
<LLD
<LLD
<LLD
<LLD
<LLD Cs137 Ci
<LLD 1.60E-07
<LLD
<LLD
<LLD
-<LLD
<LLD I <LLD Ba-140 Ci 5.41E-05 5.47E-05 2.95E-05 2.90E-05
<LLD
<LLD
<LLD
<LLD La-140 Ci
<LLD
<LLD -
<LLD
- <LLD
<LLD
<LLD
<LLD
<LLD Cr-51 Ci
< <LD
<LW^
<LLD ---
<LLD
<LLD
<LLD -
<LLD
-<LLD Mn-54 a
<LLD
<- LLD
--- <LLD
-<LLD -I --<LLD-
<LLD
<LLD
-<LLD Co -
Ci
-<LLD 2.10E-07
<LLD -
<LLD
<LLD
-. <LLD --
<LLD
<LLD -
Co-60 Ci
<LLD 3.20E-07 8.40E-07 2.07E-06
<LLD I <LLD
<LLD 1 <LLD Mo-99
- Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LW I <LLD
<LLD:
Ag-110m C----
Ci
<LID
- <LW
<LLD
< LLD -
<LLD
<LLD
<LLD
<LLD Ce-141 -
Ci
<LLD
<LLD LLD
<LLD
<LLD-
<LLD
<LLD
<LLD Ce-144 Ci
<LLj<LLD
<LW
<LID
<LLD I
<LLD
<LID
<LLD Y-88 C
C
- <LLD
<LLD I<LWD 6.80E-07
<LLD -
<LLD
<LID
<LLD Ci 1 _
1--
-7I
.for Pe Ci-I___ i
-. LL
<LLD
<LLD
<LLD Total for Period Ci 1.35E-0 1.42E-04 l9.62 E-05 7.11 E-05l
<LLD I<LLD 7<I ID I<LLDI 9,.,
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 Period: 2004 INuclides Released
_Continuous Mode Batch Mode
- 1. Fission gasesl Unit Quarter Quarter Quarter l Quarter Quarter Quarter Quarter I Quarter ll I1 I
2 l
3 l
4 l1 12 3
4 Kr-85m Ci
<LLD
<LLD
<LLD
<LLD
<LID
<LLD
<LLD
<LLD Kr-85m Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LID
<LLD
<LLD Kr-87 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Kr-88 Ci
<LLD
<LLD
<LLD
<LID
<LLD
<LLD
<LLD
<LLD Xe-133 Ci
<LLD
<LLD 3.50E+01
<LLD
<LLD
<LLD
<LLD
<LLD Xe-135 Ci
<LID
<LLD 3.46E+OO
<LID
<LLD
<LLD
<LLD
<LLD Xe-135m Ci
<LID
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Xe-138 Ci
<LID
<LLD
<LLD
<LID
<LLD
<LLD
<LLD
<LLD Ar-41 Ci
<LLD
<LLD
<LLD
<LID
<LLD
<LLD
<LLD
<LLD Xe-133m Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Unidentified Ci 9.81E+01 8.17E+01 8.25E+01 7.17E+01
<LLD
<LLD
<LLD
<LLD Total for Period Ci 9.81 E+01 8.17E+01 1.21 E+02 7.17E+01
<LLD
<LID
<LLD
<LLD
[2. lodines l Unit-l
]-
1-131 Ci 4.22E05 1.92E-04 3.85E-04 2.55E-05 j <LLD l <L l
L l<LLD 1-133 Ci
<LLD
<LLD 5.06E-05
<LLD
<LLD
<LLD
<LLD
<LLD 1-135 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Total for Period Ci 4.22E-05 1.92E-04 4.36E-04 2.55E-05
<LLD
<LLD
<LLD
<LLD
- 13. Particulates I jitI I
I_
Sr-89 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Sr-90 Ci
<LLD
<LLD
<LLD
<LLD
<LID
<LLD
<LLD
<LLD Cs-134 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD CS 37 Ci 4.77E-06 1.93E-05 5.37E-06
<LLD
<LLD
<LLD
<LLD
<LLD Ba-140 Ci
<LLD
<LLD
<LLD
<LLD
<LID
<LLD
<LLD
<LLD La-140 Ci
<LLD
<LID
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cr-51 Ci
<LLD
<LID
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Mn-54 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Co-58 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Co-60 Ci 1.62E-05
<LID 9.52E-06
<LLD 3.35E-07
<LLD
<LLD
<LLD Mo-99 Ci
<LLD
<LLD
<LLD
<LLD
<LID
<LLD
<LLD
<LLD A9-11 Om Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ce-141 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ce-144 Ci
<LLD
<LID
<LLD
<LID
<LLD
<LLD
<LLD
<LLD Zn-65 Ci 3.43E-05
<LID
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD lotal for Period Ci 5.53E-05 1.93E-05 1.49E-05 l<LLD 3.35E-07
<LLD
<LLD
<LU) 10
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Liquid Effluents - Summation Of All Releases Period: 2004 A.
FISSION & ACTIVATION PRODUCTS Unit Quarter Quarter Quarter Quarter Est. Total 1
2 3
4 Error %
- 1. Total Release (not including tritium, gases
& alpha)
Ci 4.01 E-02 3.74E-02 3.88E-02 3.81 E-02 2.11 E+01
- 2. Average diluted concentration during batch discharqes for the period iCl/mC-L 9.64E-10 8.99E-10 9.34E-10 9.15E-10
- 3. Percent of ODCM limit - Whole Body 1.99E-02 1.94E-02 4.50E-02 2.1 OE-02
- Organ I3.30E-02 3.28E-02 4.47E-02 3.44E-02 B. TRITIUM 1
- 1. Total Release
-Ci.
l1.63E+01 l2.67E+00l 4.84E+00l 6.53E+00l 6.40E+00l
- 2. Average diluted concentration during batch discharges for the period 1
C~mL 3.91 E-07 3.47E-07 4.70E-07 -4.41 E-07 4
- 3. Percent of 10 CFR 20 limit 3.91 E-02 3.47E-02 4.70E-02 4.41 E-02.
C. DISSOLVED & ENTRAINED GASES 1
1.TtlRlae-i-
.65E-05l 7.38E-06l 6.46E-05l 1.28-4 2.1 1 E+01l
- 2. Average diluted concentration during batch discharges for the period pCVmL 1.84E-12 9.58E-13 6.27E-12 8.64E-12
- 3. Percent of ODCM limit 9.19E-07 4.79E-07 3.13E-06 4.32E-06 D. GROSS ALPHA ACTIVITY
- 1. Total release' Ci
<LLD
<LLD
<LLD L
l<LD 2.30E+01
- 2. Average diluted concentration during batch discharges for the period
'IC~mL dLD
<LLD
<LLD
<LLD I
E. VOLUME OF WASTE RELEASED (prior to dilution)
Liters 3.21 E+06 4.00E+05 8.59E+05 1.12E+406 5.00E+00 F. VOLUME OF DILUTION WATER USED DURING BATCH DISCHARGES Liters 4.16E+10 7.70E+69 1.03E+10 1.48E+10 2.22E+01 G. TOTAL VOLUME OF DILUTION WATER USED DURING PERIOD Liters 4.18E+111 5.90E+1 1 5.71 E+11 5.26E+11 2.22E+01 I
I,
I I-.
I 11 "I
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC Liquid Effluents Release Point - Liquid Radwaste & RHR Leaks Period: 2004 lNUCLIDES RELEASEDF[
CONTINUOUS MODE II BATCH MODE it] Quarter j Quarter O
Quarteer Quarter II Quarter Quarter I
l l
1 l
2 l
3 l
4 ll 1
l 2
l 3
1 4
Sr-89 Ci 8.46E-07 8.46E-07 8.55E-07 8.55E-07
<LLD
<LLD 1.79E-05
<LLD Sr-90 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Cs-134 Ci 1.05E-05 1.05E-05 1.06E-05 1.06E-05
<LLD
<LLD 3.26E-05
<LLD Csl 37 Ci 8.78E-05 8.78E-05 8.88E-05 8.88E-05 8.60E-06 1.39E-06 1.81 E-04 6.59E-06 1-131 Ci 5.59E-06 5.59E-06 5.65E-06 5.65E-06
<LLD
<LLD 4.02E-05
<LLD Co-58 Ci 4.03E-04 4.03E-04 4.08E-04 4.08E-04
<LLD
<LLD 1.07E-05
<LLD Co-60 Ci 1.57E-02 1.57E-02 1.58E-02 1.58E-02 9.38E-05 6.58E-05 3.11 E-04 2.36E-04 Fe-59 Ci 5.42E-04 5.42E-04 5.48E-04 5.48E-04
<LLD
<LLD
<LLD
<LLD Zn-65 Ci 1.85E-03 1.85E-03 1.87E-03 1.87E-03 2.50E-05 4.97E-05 2.85E-04 2.28E-04 Mn-54 Ci 6.03E-03 6.03E-03 6.1 OE-03 6.1OE-03 5.76E-07 9.39E-06 2.16E-05 1.75E-05 Cr-51 Ci I 4.66E-03 4.66E-03 4.71 E-03 4.71 E-03
<LLD
<LLD 2.23E-05 3.81 E-05 Zr-95 Ci 2.77E-05 2.77E-05 2.80E-05 2.80E-05
<LLD
<LLD
<LLD
<LLD Nb-95 Ci 4.67E-05 4.67E-05 4.72E-05 4.72E-05
<LLD
<LLD
<LLD
<LLD Mo-99 Ci 2.82E-06 2.82E-06 2.85E-06 2.85E-06
<LLD
<LLD
<LLD
<LLD Tc-99m Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Ba-140 Ci 7.02E-06 7.02E-06 7.09E-06 7.09E-06
<LLD
<LLD
<LLD
<LLD La-140 Ci 2.29E-05 2.29E-05 2.32E-05 2.32E-05
<LLD
<LLD
<LLD
<LLD Ce-1 41 Ci 1.78E-06 1.78E-06 1.80E-06 1.80E-06
<LLD
<LLD
<LLD
<LLD Ag-11Om Ci 1.11 E-04 1.11E-04 1.12E-04 1.12E-04 2.54E-05 5.98E-05 2.45E-05 4.27E-05 Fe-55 Ci 7.53E-03 7.53E-03 7.61 E-03 7.61 E-03 2.76E-03
<LLD 2.73E-04
<LLD P-32 Ci 5.73E-07 5.73E-07 5.79E-07 5.79E-07 5.41 E-05 7.16E-05 1.75E-04
<LLD Sb-124 Ci 2.83E-05 2.83E-05 2.86E-05 2.86E-05
<LLD
<LLD
<LLD
<LLD Hf-181 Ci 1.36E-05 1.36E-05 1.37E-05 1.37E-05
<LLD
<LLD
<LLD
<LLD Nb-97 Ci 3.30E-05 3.30E-05 3.33E-05 3.33E-05 9.71 E-06
<LLD
<LLD 1.32E-05 As-76 Ci
<LLD
<LLD
<LLD
<LLD
<LLD 1.05E-05
<LLD
<LLD Y-93 Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 2.37E-05 Zn-69m Ci 4.41 E-06 4.41 E-06 4.46E-06 4.46E-06
<LLD
<LLD
<LLD
<LLD ci ciI Total for Period Ci 3.71 E-02 3.71 E-02 3.75E-02 3.75E-02 2.98E-03 2.68E-04 1.39E-03 6.06E-04
= I I
I lXe-133 l Ci l
<LLD I <LLD I <LLD I <LLD I 2.12E-05l 4.98E-06 l 6.15E-05 l 1.16E-04 IXe-135 I Ci 11 <LLD I <LLD I <LLD I
<LLD ]l5.53E-05 2.40E-06 3.07E-06 1.19E05 12
Facility: Peach Bottom Units 2 & 3 Licensee: Exelon Generation Company, LLC PSEG Nuclear, LLC EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (01/01/04-12/31/04)
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 8
Dewatered Resin HlC/Type A Cask 195.7 1565.6 4.92E+01 Co-60, Zn-65, Fe-55, M_-54. Cs-1 37 1
Dewatered Filters HIC/Type A Cask 202.1 202.1 11.05E+01 Co-60, Fe-55, Mn-54, Zn-65, Ni-63 1
Dewtrd Filters & DAW HlC/Type A Cask 202.1 202.1 7.84E+00 Co-60, Fe-55, Mn-54, Zn-65, Ni-63 78 DAW (1)
Metal BoxSTC variable 2917.7 1.45E+00 Co-60, Fe-55, Cs-137, Mn_54, Zn-65
()
Asbestos (1)
Metal BoxISTC variable 85.7 9.39E-03 Co-60, Mn-54, Cs-137, Zn-65, Ag-11Om
(')
Dewatered Metal BoxWSTC variable 359.8 1.37E+00 Co-60, Fe-55, Zn-65, Filters (1)
()
Incinerator Metal Box/STC variable 34.6 1.75E-01 Co-60, Fe-55, Mn-54, Ash (1)
Cs-137, Zn-65 4
DAW (2)
Metal BoxISTC variable 2510.1 3.64E-01 Co-60, Fe-55, Mn-54,
_Cr-51, Zn-65 CLASS B 1
DAW&Filters HlC/TypeACask 195.7 195.7 5.47E+00 Co-60,Cs 137, Ni-63, lFe-55, Mn-54 CLASS C NONE l
l TOTALS 8073.3 7.64E+01 NOTES:
(1) - Indicates actual total PBAPS waste shipped from Duratek to burial after processing.
(2) -Indicates actual total PBAPS waste shipped frcrn Alaron to burial after processing.
() Shipment total Included with DAW from Duratek as these shipments contained osmingled waste streams.
13
RW-AA-100 Revision 3 Exek~n.Page I of 9 Nuclear Level 3 - Information Use PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES
- 1.
PURPOSE 1.1.
The purpose of the Process Control Program'(PCP) is to:.
1.1.1.
Establish the process and boundary conditions for the preparation of specific procedures for processing sampling, analysis, packaging, storage, 'and shipment of' solid radwaste in accordance with local, state, and federal requirements. (CM-1) 1.1.2.
Establish parameters which will provide reasonable assurance that all Low Level Radioactive Wastes (LLRW), processed by the in-plant waste process systems on-site OR by on-site vendor supplied waste processin'g 'systems, meet the acceptance criteria to a Licensed 'Burial Facility, as required by IOCFR Part 20, 10CFR Part 61, 10CFR Part 71, 49CFR Parts 171-172, "'Technical Position on Waste Form (Revision 1)" [1/91],-"Low-Level Waste'Licen'sing Branch Technical Position on Radioactive Waste Classification" [5/83], and the Station Technical
'Specifications, as applicable.
1.1.3.
Provide reasonable assurance that waste placed in "on-site storage" meets the requirements as addressed within the Safety Analysis Reports for the low level radwaste storage facilities for dry and/or processed wet waste.
- 2.
TERMS AND DEFINITIONS 2.1.
'Process Control Program (PCP): The program'which contains'the current formulas, sampling, analysis, tests, and determinations to be made to ensure that processing and packaging of solid radioactive waste based on demonstrated processing of actual or simulated wet solid wastes wNill be accomplished in' such a way as to assure the waste meets the stabilization criteria specified in 10CFR Parts 20, 61 'and 71, state regilations7,rid burial site requirements.'
2.2. Solidification
Liquid waste processed to either an unstable or stable form per 1 OCFR61 requirements. Waste'solidified does not have to meet the 300-year free standing monolith criteria. Approved formulas,'sarples'and testsdo not have to meet NRC approval f6r wastes s6lidified in a container meeting stability (e.g. High Integrity Container).
2.3.
' Stabilization: Liquid w
~ate'pr6c-ssed to'a "stable state" per 10CFR61 Requirements. Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification 'stabilization" criteria. This processing method is' currently not available," because the NRC'recognizes that waste'picked in a High Integrity Container meets the 300-year stabilization criteria. In the event that this processing method becomes an acceptable method, then the NRC shall approve the stabilization formulas, samples, tests, etc.'
RW-AA-1 00 Revision 3 Page 2 of 9 2.4.
Solidification Media: An approved media (e.g. Barnwell - vinyl ester styrene, cement, bitumen) when waste containing greater than 5-year half lives is solidified in a container when the activity is greater than 1 micro curie/cc. Waste solidified in a HIC is approved by the commission meeting the 10CFR61 stabilization criteria, including 1% free standing liquids by volume when the waste is packaged to a "stable" form and < 0.5% when waste is packaged to an "unstable" form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stability criteria.
2.4.1.
Solidification to an unstable or stable state are performed by vendors, when applicable. Liquid waste solidified to meet stabilization criteria (10CFR61 and 01-91 Branch Technical Requirements) must have documentation available that shows that the process is approved by the NRC or disposal facility.
2.5. Dewatering
The process of removing fluids from liquid waste streams to produce a waste form that meets the requirements of 10CFR Part 61 and applicable burial site criteria, <0.5% by volume when the waste is packaged to an "unstable" state, or
<1% by volume when the waste is packaged to a "stable" form.
2.6.
High Integrity Container (HIC): A disposable container that is approved to the container's Certificate of Compliance 1 OCFR Part 61 Requirements for meeting stability. The use of HIC's is an alternative to solidification or encapsulation in a steel container to meet burial stability. HIC's are used to package dewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), or dry active waste.
2.7. Encapsulation
The process of placing a component (e.g. cartridge filters or mechanical components) into a special purpose disposable container and then completely surrounding the waste material with an approved stabilization media, such as cement.
2.8.
Liquid Waste Processinq Systems: In-plant or vendor supplied processing systems consisting of equipment utilized for evaporation, filtration, demineralization, dewatering, solidification, or reverse osmosis (RO) for the treatment of liquid wastes (such as Floor Drains, Chemical Drains and Equipment Drain inputs).
2.9.
Incineration, RVR, and/or Glass Vitrification of Liquid or Solid: Dry or wet waste processed via incineration and/or thermal processing where the volume is reduced by thermal means meets 1 OCFR61 requirements.
2.10.
Compaction: When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.
2.11.
Waste Streams: Consist of but are not limited to Filter media (powdered, bead resin and fiber),
Filter cartridges, Pre-coat body feed material, Contaminated charcoal, Fuel pool activated hardware,
RW-AA-100 Revision 3 Page3of9 Fuel Pool Crud Sump and tank sludges, High activity filter cartridges,
- Concentrated liquids, Contaminated waste oil, Dried sewage or wastewater.plant waste, PDry Active Waste.(DAW): Waste such as filters, air filters, low activity cartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, and metals, etc, which have become contariniarted as a consequence of normal operating, housekeeping and maintenance activities.
=
Other radioactive waste generated from cleanup of inadvertent contamination.
- 3.
RESPONSIBILITIES 3.1.
Implementation of this Process Control Program (PCP) is described in procedures at each station and is the responsibility of the each site.
- ~.-
- 4.
MAIN BODY 4.1: -
Process Control Pro-ram Requirements 4.1.1..
A change to this PCP (Radioactive Waste Treatment Systems) may be made provided -that the change is reported as part of the annual radioactive effluent release report, Regulatory Guide 1.21, and is approved by the Plant Operations Review Committee (PORC).
4.1.2.
Changes become effective upon acceptance p'er'station requirements.
4.1.3.
Records of reviews performed shall be retained for the duration of the unit operating license. This documentation shall contain:
- 1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change, and
- ^
- 2. 'A determination which documents that the change'will maintain the overall conformance of waste products to Federal (10CFR61 and the Branch Technical Position), State, or other applicable requirements, including
- applicable burial site criteria. - -
4.1.4.
A solidification media, approved by the burial site, MAY BE REQUIRED when liquid radwaste is solidified to a stable/unstable state-.
RW-AA-1 00 Revision 3 Page 4 of 9 4.1.5.
When processing liquid radwaste to meet solidification stability using a vendor supplied solidification system:
- 1.
If the vendor has its own Quality Assurance (QA) Program, then the vendor SHALL ADHERE to its own QA Program and SHALL HAVE SUBMITTED its process system topical report to the NRC or agreement state.
- 2.
If the vendor DOES NOT HAVE its own Quality Assurance Program, then the vendor SHALL ADHERE to an approved Quality Assurance Topical Report standard belonging to the Station or to another vendor.
4.1.6.
The vendor processing system(s) is/are controlled per the following:
- 1.
A commercial vendor supplied processing system(s) MAY BE USED for the processing of LLRW streams.
- 2.
Vendors that process liquid LLRW at the sites must meet applicable QA Topical Report and Augmented Quality Requirements.
4.1.7.
Vendor processing system(s) operated at the site WILL BE OPERATED and CONTROLLED in accordance with vendor approved procedures or station procedures based upon vendor approved documents.
4.1.8.
All waste streams processed for burial or long term on-site storage SHALL MEET the waste classification and characteristics specified in 10CFR Part 61.55, Part 61.56, the 5-83 Branch Technical Position for waste classification, and the applicable burial site acceptance criteria (for any burial site operating at the time the waste was processed).
4.2.
General Waste Processinq Requirements 4.2.1.
On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resin water slurry or vacuuming into approved waste containers, and, when applicable, dewatering for burial.
4.2.2.
Vendor resin beds MAY BE USED for decontamination of plant systems, such as, Spent Fuel Pool, RWCU (reactor water cleanup), and SDC (Shut Down Cooling).
These resins ARE then PROCESSED via the station or vendor processing system.
4.2.3.
Various drains and sump discharges WILL BE COLLECTED in tanks or suitable containers for processing treatment. Water from these tanks MAY BE SENT through a filter, demineralizer, concentrator or vendor supplied processing systems.
4.2.4.
Process waste (e.g. filter media, sludges, resin, etc) WILL BE periodically DISCHARGED to the station or vendor processing system for onsite waste treatment or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.
RW-AA-100 Revision 3 Page 5 of 9 4.2.5.
Process water (e.g. chemical, floor, equipment drain, etc.) MAY BE SENT to either the site waste process systems or vendor waste processing systems for further filtration, demineralization for plant re-use, or discharge.'
4.2.6.
All dewatering and solidification/stabilization WILL BE PERFORMED by either utility site personnel or by on-site vendors or WILL BE PACKAGED and SHIPPED to an off-site vendor' low-level radwaste processing facility..
4.2.7.
Dry'Active'Waste (DAW) WILL'BE HANDLED and PROCESSED p'er the following:
- 1.
DAW WILL BE COLLECTED and SURVEYED and MAY BE SORTED for compactable and non-compactable wastes.
- 2.
"DAW may be packaged'in 'containers to facilitate on-site pre-compaction and/or off-site vendor contract requirements
- 3.
DAW items MAY BE SURVEYED for release onsite or offsite when applicable.
- 4.
Contaminated filter cartridges WILL BE PLACED into a HIC or WILL BE ENCAPSULATED in'an-in-situ linierfor disposal or SHIPPED to an offsite waste processor.in drums, boxes or steel liners per-the vendor site criteria for processing and disposal.
4.2.8.
Filtering devices using pre-coat media' MAY BE USED for'the'removal of suspended solids from liquid waste streams. -The pre-coat material or cartridges from these devices MAY BE routinely REMOVED from the filter vessel and discharged to a Filter Sludge Tank or Liner/HIC. Periodically, the filter sludge MAY BE DISCHARGED to the vendor processing system for waste treatment onsite or PACKAGED in '
containers for shipment to offsite vendor for volume reduction processing.
4.2.9.-
Activated hardware stored in the'Spent Fuel Pools WILL BE PROCESSED periodically using remote handling equipment and MAY then BE PUT into a container for shipment or.storage, 4.2.10.
High Integrity Containers (HIC) -
- 1.
Vendors who supply HIC's to-the station MUST PROVIDE a copy of the HIC Certificate of Compliance, which details specific limitations on use of the HIC.
- 2.
Vendors who supply HIC's to the station MUST PROVIDE a handling procedure, which establishesgiuidelinre's for the utilization of the HIC. These guidelines serve to protect the integrity of the HIC and ensure the HIC is handled in accordance with the requirements of the Certificate of Compliance.
4.2.11.
Lubricants and oils contaminated as a consequence of normal operating and maintenance activities MAY BE PROCESSED on-site (by incineration, for oils meeting i OCFR20.2004 and applicable state requirements, or by an approved vendor process) or SHIPPED offsite (for incinieration or other acceptable processing
-method).
RW-AA-1 00 Revision 3 Page 6 of 9 4.2.12.
Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas MAY BE USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byron.
4.2.13 Certain waste, including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite under the provisions of 1 OCFR20.2002 permit. Specific requirements associated with the disposal shall be incorporated into station implementing procedures. (CM-2) 4.3.
Burial Site Requirements 4.3.1.
Waste sent directly to burial WILL COMPLY with the applicable parts of 49CFR, 10CFR61, and 10CFR71, and the acceptance criteria for the applicable burial site.
4.4.
Shipping and Inspection Requirements 4.4.1.
All shipping/storage containers WILL BE INSPECTED, as required by station procedures, for compliance with applicable requirements (Department Of Transportation (DOT), Nuclear Regulatory Commission (NRC), station, on-site storage, and/or burial site requirements) prior to use.
4.4.2.
Containers of solidified liquid waste WILL BE INSPECTED for solidification quality and/or dewatering requirements per the burial site, offsite vendor acceptance, or station acceptance criteria, as applicable.
4.4.3.
Shipments sent to an off site processor WILL BE INSPECTED to ensure that the applicable processor's waste acceptance criteria are being met.
4.5.
Inspection and Corrective Action 4.5.1.
Inspection results that indicate non-compliance with applicable NRC, State, vendor, or site requirements WILL BE IDENTIFIED and TRACKED through the Corrective Action Program.
4.5.2.
Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures. If the provisions of the Process Control Program are not satisfied, then SUSPEND shipments of defectively packaged radioactive waste from the site. (CM-1) 4.5.3.
If freestanding water or solidification not meeting program requirements is observed, then samples of the particular series of batches WILL BE TAKEN to determine the cause. Additional samples WILL BE TAKEN, as warranted, to ensure that no freestanding water is present and solidification requirements are maintained.
4.6.
Procedure and Process Reviews 4.6.1.
The Exelon Nuclear Process Control Program and changes to it (other than editorial/minor changes) SHALL BE APPROVED in accordance with the station procedures and Technical Requirements Manual (TRM) or Operation Requirements Manual (ORM), as applicable, for the respective station. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.
RW-AA-1 00 Revision 3 Page 7 of 9 4.6.2.
The station or vendor's implementing processing procedures for the purpose of this Process Control Program SHALL BE REVIEWEDDand APPROVED in accordance with the plant specific TRM or ORM (either CTS or ITS, as applicable for the respective stations). These include the following,'when applicable:
- 1.
procedures for set-up and operation of dewatering equipment (e.g., set-up and operation of RDS 1000 Unit). --
- 2.
solidification procedures affecting waste stabilization for waste processed in a steel containers (This'processing method is not currently in use due to waste loading and volume reduction.)
- 3.
High Integrity Container handling procedure.
- 4.
operating waste sampling equipment for solidification and dewatering processes.
4.6.3.
All other vendor waste processing procedures SHALL BE technically REVIEWED, as appropriate.
4.6.4.
Station processes, including procedures related to waste manifests, shipment inspections, and container activity determination,'ARE CONTROLLED by each station.
- 1.
Site waste processing IS'CONTROLLED by site operating procedures.
- 2.
Liquid processed by vendor equipment WILL BE DONE in accordance with vendor procedures.
4.7.
Waste Tvpes, Point of Generation, and Processinq Method lI Methods of processing and individual vendors MAY CHANGE due to changing financial and regulatory options. The table below is a representative sample. It is not intended be all encompassing.
Waste Stream POINTS OF GENERATION AVAILABLE WASTE PROCESSING i
METHODS Bead Resin Systems - Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Che'Mical'and' Volume Control'Systems, Floor Thermal Processing Drain, Maximum Recycle, Blowdown, Boric Acid Recycling System, Vendor Free Release to a Land Fil.
Supplied Processing'Systems, and Portable Demin Systrn
ai RW-AA-1 00 Revision 3 Page 8 of 9 Waste Stream POINTS OF GENERATION AVAILABLE WASTE PROCESSING METHODS Powdered Resin Systems - (Condensate System, Dewatering, solidification to an Floor Drain/Equipment Drain unstable/stable state filtration, Fuel Pool)
Thermal Processing Concentrated Waste Waste generated from Site Solidification to an unstable/stable state Evaporators resulting typically from the Floor Drain and Equipment Drain Thermal Processing Systems Sludge Sedimentation resulting from various Dewatering, solidification to an sumps, condensers, tanks, cooling unstable/stable state tower, emergency spray pond, holding pond, and oily waste Thermal Processing separators..
Evaporation on-site or at an offsite processor On-site disposal per IOCFR20.2002 permit Filter cartridges Systems - Floor/Equipment Drains, Dewatering, solidification to an Fuel Pool; cartridge filters are unstable/stable state typically generated from clean up activities within the fuel pool, torus, Processed by a vendor for volume etc.
reduction Dry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Release, metal, and etc. resulting from daily plant activities.
Compaction/Super-compaction Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal melting to an ingot Contaminated Oil Oil contaminated with radioactive Solidification unstable state materials from any in-plant system.
Thermal Processing by Incineration Free Release for recycling Drying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burial Treatment Facilities Metals See DAW See DAW Irradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packaging efficiencies
RW-AA-100 Revision 3 Page 9 of 9
- 5.
DOCUMENTATION - None
- 6.
REFERENCES 6.1.
Technical Specifications:
6.1.1.
The details contained in Current Tech Specs (CTS) or Improved Technical Specifications (ITS), as applicable, in regard to the Process Control Program (PCP),
are to be relocated to the Licensee Controlled Documents. Some facilities have elected to relocate these details into the Operational Requirements Manual (ORM).
Relocation of the description of the PCP from the CTS or ITS does not affect the safe operation of the facility. Therefore, the relocation details are not required to be in the CTS or the ITS to provide adequate protection of the public health and safety.
6.2.
Source Documents:
6.2.1.
Code Of Federal Regulations: 10 CFR Part 20, Part 61, Part 71, 49 CFR Parts 171-172 6.2.2.
Low Level Waste Licensing Branch Technical Position On Radioactive Waste Classification, May 1983 6.2.3.
Technical Position on Waste Form (Revision 1), January 1991 6.2.4.
Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 6.2.5.
Regulatory Guide 1.21 6.2.6.
I.E. Circular 80.18, 10CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems 6.2.7.
Quality Assurance Program 6.3.
Station Commitments:
6.3.1.
Peach Bottom CM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29,94, transmitting TSCR 93-16 (Improved Technical Specifications).
6.3.2.
Limerick CM-2, T03896, 10CFR20.2002 permit granted to Limerick via letter dated July 10,1996.
- 7.
ATTACHMENTS - None