ML031250172
| ML031250172 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 04/24/2003 |
| From: | Shriver B Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PLA-5618 | |
| Download: ML031250172 (110) | |
Text
Susquehanna Steam Electric Station Units I &2 Radioactive Effluent and Waste Disposal Report 2002 Annual
-Report
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SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT REPORT PERIOD: 01/01/02 - 12131102 Prepared by:
Francis J. HicketV o
Health Physicist Reviewed by:
Raymh d E. Doebler Chemistry Support Supervisor - SSES Approved by:
Bruce E. Rhoads Chemistry Supervisor - SSES PPL Susquehanna, LLC Susquehanna Steam Electric Station (NUCSA3) 769 Salem Blvd.
Berwick, Pennsylvania 18603
TABLE OF CONTENTS SECTION PAGE
- 1. Introduction and Supplemental Information 1-1
- 2. Effluent and Waste Disposal Data 2-1
- 3. Meteorological Data and Dispersion Estimates 3-1
- 4. Dose Measurements and Assessments 4-1
- 5. Changes to the Offsite Dose Calculation Manual (ODCM),
5-1 Technical Requirements Manual (TRM) and the Solid Radioactive Waste Process Control Program
- 7. Corrections to Doses Reported in Previous 7-1 Semiannual or Annual Effluent and Waste Disposal Reports
- 8. Effluent from Systems Classified as Insignificant Effluent Pathways 8-3 Appendix A SSES ODCM/TRM
LIST OF TABLES Table 1-1 Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 2-5 Table 2-6 Table 2-7 Table 2-8 Table 2-9 Table 2-10 Table 2-11 Table 2-12 Table 2-13 Technical Requirement Limits Airborne Effluent-Summation of All Releases Airborne Effluent Radionuclides Released Waterborne Effluent - Summation of All Releases Waterborne Effluent Radionuclides Released Annual Effluent and Waste Disposal Report Estimated Total Errors Associated with Effluents Measurements Data Period: January 1, 2002 - December 31, 2002 Annual Effluent and Waste Disposal Report Solid Waste and Irradiated Fuel Shipments LRW Filter Media - Class A HIC (Dewatered)
RWCU Filter Media - Class A HIC (Dewatered)
Asbestos - Class A Strong Tight Container (Compacted)
Ash - Class A Strong Tight Container (Incineration)
Bead Resin/Charcoal - Class A HIC (Pyrolysis)
CFS Filters - Class A Strong Tight Container (Compacted)
Condensate Demineralizer/Radwaste Demineralizer Class A HIC (Pyrolysis)
PAGE 1-10 2-4 2-5 2-8 2-9 2-12 2-16 2-17 2-18 2-19 2-20 2-21 2-22 2-23
LIST OF TABLES (cont.)
PAGE 2-24 Table 2-14 Table 2-15 Table 2-16 Table 2-17 Table 2-18 Table 2-19 Table 2-20 Table 2-21 Table 2-22 Table 2-23 Contaminated Waste Oil - Class A (Fuel Blending for Co-Generation)
Liquid Radwaste Filter Media - Class A HIC (Pyrolysis)
Phosphoric Acid - Class A Drums (Incineration)
Processed DAW - Class A Strong Tight Container (Compacted)
RWCU Filter Media - Class B HIC (Dewatered)
Condensate Demineralizer/Radwaste Demineralizer Class B HIC (Pyrolysis)
Liquid Radwaste Filter Media - Class B HIC (Pyrolysis)
Cartridge Filters - Class C HIC (Non-Processed)
Non-Processed DAW - Class C HIC (Non-Processed)
Liquid Radwaste Filter Media - Class C HIC (Pyrolysis) 2-25 2-26 2-27 2-28 2-29 2-30 2-31 2-32 2-33 Table 3-1 SSES Meteorological Data Recovery for 2002 3-3 Table 3-2 Table 3-3 Table 3-4 Table 3-5 SSES Joint Frequency Distribution of Wind Speed and Direction 1 Om versus Delta Temperature 60-1 Om for the Period of January 1, 2002 through December 31, 2002 3-4 SSES Joint Frequency Distribution of Wind Speed and Direction 60m versus Delta Temperature 60-1 Om for the Period of January 1, 2002 through December 31, 2002 2002 SSES Annual Relative Concentrations No Decay, Undepleted X/Q (sec/n 3) 3-12 3-20 2002 SSES Annual Relative Concentrations 2.26-Day 3-21 Decay, Undepleted X/Q (sec/n 3)
LIST OF TABLES (cont.)
PAGE Table 3-6 Table 3-7 Table 3-8 2002 SSES Annual Relative Concentrations 8-Day Decay, Depleted X/Q (sec/M 3) 2002 SSES Annual Relative Deposition - D/Q (meters-2) 2002 Atmospheric Dispersion Estimates for RETDAS Input at Selected Locations 3-22 3-23 3-24 4-2 Table 4-1 Site-Specific Parameters Used for RETDAS Calculations (Danville Receiver): for 2002 Table 4-2 Summary of Maximum Individual Offsite Doses and Dose Commitments to Members of the Public 4-4 Table 4-3 Table 4-4 Table 8-1 Calculated Collective Doses to Members of the Public Within the Riverlands/Information Center Complex Calculated Maximum Doses for Individuals and Locations Within the SSES Site Boundary and Nearest Residence, Garden, Dairy and Meat Producing Farm Annual Release from Systems Classified as Insignificant Effluent Pathways 4-5 4-6 8-3
LIST OF FIGURES Figure 1-1 Figure 1-2 Figure 2-1 Figure 2-2 Figure 3-1 Figure 3-2 Figure 3-3 Figure 4-1 SSES Airborne Effluent Points SSES Waterborne Effluent Pathway Susquehanna River Monthly Average Flow Rates SSES Monthly Liquid Radwaste Discharge Totals SSES 2002 Annual Wind Rose: 10-Meter Level Primary Tower SSES 2002 Annual Wind Rose: 60-Meter Level Primary Tower SSES Pasquil Stability Class Prevalences Locations for which Airborne Dose Calculations are Performed PAGE 1-5 1-6 2-10 2-11 3-26 3-27 3-28 4-7
SECTION 1 INTRODUCTION AND SUPPLEMENTAL INFORMATION 1-1
INTRODUCTION The submittal of the 2002 Annual Radioactive Effluent and Waste Disposal Report is in accordance with 1 OCFR50.36a. The enclosed information is consistent with the objectives outlined in the SSES ODCM and Process Control Program. The 2002 Annual Radioactive Effluent and Waste Disposal Report is in conformance with 10CFR50.36a and 10CFR50, Appendix I, Section IV.B.1.
The Susquehanna Steam Electric Station (SSES) is located in Salem Township, Luzerne County, Pennsylvania. It is on the west bank of the Susquehanna River, 8 km northeast of Berwick. The Station consists of two boiling water reactor generating units, each with about 1,100 MW net electrical capacity. The reactor and generating units were supplied by General Electric, while the Bechtel Corporation served as architect-engineer and constructor.
Construction of the Station began in the early 1970s. Fuel load began in Unit 1 in July of 1982. Initial criticality was achieved in the Unit 1 reactor on September 10, 1982.
The reactor reached 100% power for the first time on February 4,1983. Commercial operation of Unit 1 was declared on June 8,1983. Initial criticality of Unit 2 occurred on May 8,1984. Unit 2 was declared commercial on February 12, 1985.
Airborne effluents are released from the Susquehanna Station via five rooftop vents on the reactor building (see Figure 1-1). Each vent is continuously monitored, and a program of periodic sampling and analysis is conducted as specified in the plant Technical Requirements. All waterborne effluents are released in batch mode and are sampled and analyzed prior to release. Waterborne effluents from the site are released into the cooling tower blowdown line for dilution prior to release to the Susquehanna River (see Figure 1-2). Blowdown line flow rates are at least 5,000 gpm during periods of liquid radwaste release. The diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed. The diffuser serves to rapidly and uniformly mix the station discharge with the main flow of the river.
This report presents a summary of the quantities of radioactive materials which were released from the Susquehanna Steam Electric Station during the period from January 1, 2002 to December 31, 2002. In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to the SSES Offsite Dose Calculation Manual (ODCM) and Solid Radioactive Waste Process Control Program (PCP) and documentation of any exceptions to the SSES effluent monitoring program which must be reported per Technical Requirements.
Airborne and waterborne radioactive effluent releases to the environment during the report period were sampled and analyzed in accordance with the Technical Requirements. All radioactive effluent releases were within the concentration and release limits specified in the Technical Requirements. Calculations and terms utilized in this report are those outlined in the SSES ODCM.
1-2
Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant. Included are regulatory limits (Table 1-1), sampling and analysis methods, and characterization of the number and duration of batch and abnormal releases, if any.
Section 2 contains effluent and waste disposal data for the report period. Table 2-1 contains a summation of all airborne releases, grouped into the radionuclide categories of gases, particulates, iodines, and tritium. Average release rates are presented and compared to the applicable limits. Table 2-2 presents the activity totals of specific radionuclides in airborne effluents.
Waterborne effluents are summarized in Table 2-3. Average diluted concentrations are presented and compared to the applicable limits. Table 2-4 presents the release quantities of specific radionuclides in waterborne effluents over the report period.
Figures present the Susquehanna River Monthly Average Flow Rates for 2002 and the SSES Monthly Liquid Radwaste Discharge Totals for 2002.
Table 2-5 contains estimates of the errors associated with the measurements involved in quantifying effluents. Sampling errors, counting errors, and errors associated with determining effluent flow rates and volumes all contribute to the total error of effluent measurements. Error estimates are presented for each category of radionuclide detected in airborne and waterborne effluents and solid wastes during the report period.
Tables 2-7 through 2-20 present a characterization of the solid radioactive waste shipped offsite during the report period. Included are the volumes and curie contents associated with each type of solid waste. An estimate of major nuclide composition is presented for each waste type, as well as the number of waste shipments from the site, how they were transported, and their final destination.
Section 3 presents meteorological data for 2002 including data recovery, joint frequency distribution of wind speed and direction, stability class distribution, and atmospheric dispersion estimates for selected locations.
Section 4 of this report contains an assessment of the calculated doses attributed to the reported radiological effluents for the calendar year. The Radioactive Effluent Tracking and Dose Assessment Software (RETDAS) computer code was used for calculation of doses from waterborne effluents. Site-specific parameters used in the calculations for the Danville receiver are shown in Table 4-1. The RETDAS code was also used for calculation of doses from airborne effluents. The calculated doses and direct radiation estimates can be used to estimate the doses to maximally exposed members of the public. Table 4-2 summarizes maximum calculated doses and dose commitments to members of the public from airborne and waterborne effluents and direct radiation.
Table 4-3 presents calculated collective doses to members of the public within the Riverlands/Information Center Complex. Table 4-4 summarizes the calculated doses 1-3
for residences and other occupied areas within the SSES site boundary and nearest dairy.
Section 5 of this report documents changes to the Offsite Dose Calculation Manual and the Solid Radioactive Waste Process Control Program.
Section 6 presents a listing of cases (if any) in which airborne or waterborne effluent monitoring instrumentation was declared inoperable and was not restored to operability within the time period specified in Technical Requirements 3.11.1.4, 3.11.1.5 and 3.11.2.6 Action Statements. In addition, this section presents issues (if any) with the collection of milk or fresh leafy vegetables per Technical Requirement 3.11.4.1 and change due to the land use census per Technical Requirement 3.11.4.2.
Section 7 contains corrections (if any) to doses reported in previous Semiannual or Annual Effluent and Waste Disposal Reports.
Section 8 contains information on effluent and offsite dose from the systems classified as insignificant effluent pathways.
1-4
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FIGURE 1-2 SSES WATERBORNE EFFLUENT PATHWAY I.
FRNEYAPORAT R HEATING ST`AM OND N SATE ETURN TANK FROM PHASE SEPARATORS (DECANT)
(SUP M RHX SYSTEM 1
l;DtOPOOL TRANSFERS)
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R EACTOR WELL SEAL. LEAK DRAIN REACTOR BOUILDING DRAINS DRYWELL DRAINS l[
TURBINE BJUILDING DRAINS l
RADWASTE BUILDING DRAINS SSESUCUID EFFLUENT RELEASE FLO WPATH I
(M.161. M.162. M-163 AND M.164)
LIQUID RADWASTE RECYCLE LIQUID LIDWASTW COLLECTIO N AND SURGE TANNKS PUMP OT -302A THXU r OT -304A THRU D t
ADWASTE R ADWAT I
RADWASTE FLTERS MINERLE AMPLE TANKS LIUDRDAT F 302A &
- a 30 OT 303A THRU r CO LLECTION TANK PUMP TO
- TO01, a
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WATE IXIN TAKS )
t SENT ESI TANS _2 l
LIQUID XADWASTE AMPLE TANK PUM1PS
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CHEHICAL OECON LABJ & DECON DRAINSl AUX BOILER BLOWw CHEMICAL DRAIN TANK CHEMICAL WASTE TANK OT-314 141CAL WASTE TANK UMPS OP-326A, 0 (2)
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TRALIZING TA KS IT-ICA, B 2T-130A, B HIMICAL WASTE NEUTRALIZING TANK UMPS P.1;0A, -b I I
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REGULATED SHOP DRAII L
LAUNDRY I LAUNDRY DRAIN TANKS SA PLE TANKS
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K Y DRAIN P_
PUMPJ SAMPLE ;ANK PUMPS A
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(3) CONTAMINATED CLOTHING CURRENTLY (I) RADWASTE EVAPORATORS ARE NOT USED (2) CONS DEMIN RESINS CURRENTLY NOT REGENERATED (3) CONTAINATED CLOTHING CURTENTLY NOT LAUNDERED ONSITE SUSQUEHANNA RIVER 1-6
SUPPLEMENTAL INFORMATION
- 1.
Regulatory Limits Technical Requirements 3.11.1 and 3.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively. Concentration of radioactive materials released in liquid effluents and dose or dose commitment resultant thereof are limited in unrestricted areas. Dose and dose rate due to radioactive materials released in gaseous effluents are limited in areas at or beyond the site boundary. Technical Requirement limits are listed in Table 1-1.
- 2.
Maximum Permissible Concentrations in Waterborne Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas is limited to 10 times the concentrations specified in 10 CFR Part 20 Appendix B Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration is limited to 2.OE-04,pCVml total activity (TRO 3.11.1.1).
- 3.
Average Energy of Fission and Activation Gas The Calculation of Noble Gas Effluent Average Energies E-Bar Beta and Gamma for 2002 resulted in an Annual E-Bar Beta value of 4.64E-01 and an E-Bar Gamma activity of 1.28.
- 4.
Measurements and Approximations of Total Radioactivity Analyses of specific radionuclides in effluent samples are used to evaluate the radioactive composition and concentration of effluents.
- 5.
Methods of Quantifyinq Effluents
- a.
Fission and Activation Gases: Gas samples are routinely collected monthly and analyzed with a high resolution (HPGE) detector system which incorporates a data reduction program to determine radionuclide composition in terms of specific activity. Data tapes from the continuous vent monitors are used to determine the average concentration of noble gases. The high resolution (HPGE) isotopic scan is used to convert the continuous vent monitor activity to actual activity based on the determined nuclide mixture.
The vent and sample flow rates are continuously monitored and the average flow rates for each vent are used to calculate the total activity released in a given time period. When the continuous monitors are out of service, manual 1-7
grab samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).
- b.
Iodines: Iodine is continuously collected on charcoal or silver zeolite cartridges via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a high resolution (HPGE) system. The daily average flow rates for the vents and sample pumps are averaged for the duration of the sampling period and a ratio of vent flow rate to sample flow rate is determined. The ratio is used to determine the total activity of each isotope released during the time period in question. When the continuous monitors are out of service, iodine is continuously collected on charcoal cartridges attached to air samplers which draw directly from the affected rooftop vent(s) or from alternate sampling ports available on the sample lines.
- c.
Particulates: Particulates are continuously collected via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a high resolution (HPGE) system. Flow rate corrections are performed as for iodines. When the continuous vent monitors are out of service, particulates are continuously collected directly from the affected rooftop vent(s) or from alternate sampling ports available on the sample lines.
- d.
Tritium: Airborne tritium is collected monthly via bubbler sampler. The sample is collected for one hour at a flow rate of approximately 1000 cc/min.
Tritium activity in the bubbler sample is determined by liquid scintillation counting. The liquid sample tritium concentration is converted to air concentration by volume proportion, then compared to the Technical Requirement Table (TRO) 3.11.2.1.-i Lower Limit of Detection (1 E-6 pCi/cc).
- e.
Waterborne Effluents: Each tank of liquid radwaste is sampled and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling to ensure that a representative sample is obtained. Samples are analyzed on a high resolution (HPGE) system and release permits are generated based on the values obtained from the isotopic analysis and the most recent values for tritium, gross alpha, iron-55, and strontium-89 and -90. An aliquot based on release volume is saved and added to monthly and quarterly composite containers. The monthly tritium analysis is done in-house. The monthly liquid radwaste composite sample is also analyzed offsite for P-32. The quarterly composite is sent to a vendor laboratory for iron-55, strontium-89 and -90, and gross alpha analyses.
The concentration of each radionuclide in each batch is decay-corrected from the time of counting to the midpoint of the release period, and is then multiplied by the volume of the batch to determine the total quantity of each 1-8
nuclide released in each batch. The isotopic totals for each are summed to determine the total source term for the report period.
1-9
TABLE 1-1
- 1.
TECHNICAL REQUIREMENT LIMITS A.
NOBLE GASES:
- 1.
<500 mrem/year - TOTAL BODY
- 3000 mrem/year - SKIN dose rate limit at and beyond the site boundary (TRO 3.11.2.1)
- 2.
- 5 mrad - AIR GAMMA
<10 mrad -AIR BETA quarterly air dose limits per reactor unit at and beyond the site boundary (TRO 3.11.2.2a)
- 3.
<10 mrad - AIR GAMMA
<20 mrad - AIR BETA annual air dose limits per reactor unit at and beyond the site boundary (TRO 3.11.2.2.b)
B.
AIRBORNE 1-131,1-133, TRITIUM, PARTICULATES WITH HALF-LIVES > 8 DAYS:
- 1.
<1500 mremlyear-ORGAN (inhalation pathways only) dose rate limit at and beyond the site boundary (TRO 3.11.2.1.Il.A)
- 2.
- 7.5 mrem - ORGAN quarterly dose limit per reactor unit at and beyond the site boundary (TRO 3.11.2.3.a)
- 3.
<15 mrem - ORGAN annual dose limit per reactor unit at and beyond the site boundary (TRO 3.11.2.3.b) 1-10
C.
LIQUID EFFLUENTS:
- 1.
<1.5 mrem - TOTAL BODY
- 2.
<3.0 mrem - TOTAL BODY
D.
AIRBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLE TECHNICAL REQUIREMENT LIMIT Fission and Activation Gases A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1.1.A) limit of 500 mrem/yr was calculated from the expected mix of noble gas radionuclides presented in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564). The limit is 8.51 E+05 pC~min (1.42E+04 uCi/sec).
lodines A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1.1.A) limit of 1500 mrem/yr from 1-131, 1-133, tritium and particulates with half-lives greater than 8 days was calculated from the annual release quantity of 1-131 provided in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564). The limit is 1.04E+02 pCi/min (1.73E+00 /Cisec).
Particulates A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1.1l.A) limit of 1500 mrem/yr from 1-131, 1-133, tritium and particulates with half-lives greater than 8 days was calculated based on the expected mix of particulate radionuclides presented in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564). The limit is 7.72E+02 pCi/min (1.29E+01,pCOsec).
1-11
Tritium A derived release rate was calculated based on the 10 CFR 20, Appendix B, Table 2, Column 1, Effluent Concentration Limit for tritium (1.OE-07 yCi/cc) to unrestricted areas. A relative concentration of 4.1 E-05 sec/m 3 was assumed.
The limit is 1.46E+05 pCi/min (2.44E+03,pCisec).
E.
WATERBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLE TECHNICAL REQUIREMENT LIMIT Fission and Activation Products Concentrations of fission and activation products in liquid effluent from radwaste effluent are determined for each batch prior to release. Each isotope concentration is compared to ten times the 1 OCFR20 Appendix B, Table 2, Column 2 Effluent Concentration Values. No Technical Requirement limit for the total concentration of fission and activation products in liquid effluents is applicable for this category.
Tritium Liquid effluent tritium concentrations are compared to ten times the 10 CFR 20 Appendix B, Table 2, Column 2, Effluent Concentration value of 1.OE-03 pCi/ml to unrestricted areas.
Dissolved and Entrained Gases Liquid effluent concentrations for dissolved and entrained gases are compared to the limiting value for a noble gas of 2.OE-04 pCi/ml.
1-12
SECTION 2 EFFLUENTAND WASTE DISPOSAL DATA 2-1
Airborne Effluents Summaries of the radionuclide total curie activities and average release rates are included in Tables 2-1 and 2-2.
- 1. Number of Batch Releases:
o
- 2. Total Time Period for Batch Release:
NA
- 3. Maximum Time Period for a Batch Release:
NA
- 4. Average Time Period for a Batch Release:
NA
- 5. Minimum Time Period for a Batch Release:
NA Abnormal Releases
- 1. Number of Releases o
- 2. Total Activity Released NA If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in the SSES Technical Requirement (TRO)
Table 3.11.2.1-1, Radioactive Gaseous Effluent Sampling and Analysis Program. In all cases, these LLDs were less than the levels required by Technical Requirements. The following are typical LLDs.
Radionuclide LLD (pCi/cc)
Kr-87 4.6 E-08 Kr-88 5.3 E-08 Xe-1 33 5.4 E-08 Xe-1 33m 1.3 E-07 Xe-1 35 1.5 E-08 Xe-1 35m 5.0E-08 Xe-138 1.2 E-07 Mn-54 2.9 E-14 Fe-59 2.8 E-14 Co-58 1.8 E-14 Co-60 3.8 E-14 Zn-65 4.4 E-14 Mo-99 3.3 E-13 Cs-1 34 2.4 E-14 2-2
Radionuclide LLD (pC!cc)
Cs-137 Ce-1 41 Ce-1 44 1-131 Sr-89 Sr-90 H-3 Gross Alpha 2.1 E-14 1.5 E-14 7.0 E-14 4.4 E-14 2.0 E-1 5 3.0 E-16 2.6 E-08 5.0 E-1 6 2-3
TABLE 2-1 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2002)
AIRBORNE EFFLUENT - SUMMATION OF ALL RELEASES First Second Third Fourth Unit Quarter I
Quarter I
Quarter I
Quarter A. Fission and Activation Gas Total Release Ci 0
0 0
9.68E+00 Average Release Rate for Period
/pCVsec 0
0 0
1.22E+00
% of TRM Limit
_0 0
0 8.6E-03 B. lodines Total 1-131 Ci 00 0
0 1
Total 1-133 Ci O
Average Release Rate for Period pCi/sec 0
Percent TRM Limit 0
0 0
C. Particulate Particulate with Half-Life >8 Days Ci 2.43E-03 l 1.32E-03 4.42E-04 2.11 E-03 Average Release Rate for Period p01ilsec 3.13E-04 j 1.68E-04 5.56E-05 2.65E-04 Percent TRM Limit I
2.43E-03 1.31 E-03 4.32E-04 2.06E-03 Gross Alpha Radioactivity Ci 0
3.33E-06 2.1OE-06 7.74E-06 D. Tritium Total Release Ci 4.32E+01 3.1OE+01 4.53E+01 1.74E+01 Average Release Rate for Period pCVsec 5.55E+00 3.95E+00 5.70E+00 2.19E+00 Percent TRM Limit 2.28E-01 1.62E-01 2.34E-01 8.98E-02 2-4
TABLE 2-2 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2002)
AIRBORNE EFFLUENT r
Releases in Continuous Mode I
First Second Third Fourth Nuclides Released l
Unit Quarter Quarter Quarter Quarter A. Fission and Activation Gases Ar-41 Ci 0
0 0
9.68E+00 Kr-85 Ci 0
0 0
0 Kr-85m C
0 0
0 0
Kr-87 Ci 0
0 0
0 Kr-88 Ci 0
0 0
0 Xe-133 Ci 0
0 0
0 Xe-133m Ci 0
0 0
0 Xe-135 Ci 0
0 0
0 Xe-135m Ci 0
0 0
0 Xe-138 Ci 0
0 0
0 Total for Period Ci 0
0 0
9.68E+00 B. lodines 1-131 Ci 0
0 0
0 1-133 Ci 0
0
.0 0
1-135 Ci 0
0 0
0 Total for Period Ci 0
0 0
0 C. Particulate Cr-51 Ci 1.54E-03 6.65E-04 2.94E-04 8.06E-04 Mn-54 Ci 5.82E-04 4.49E-04 1.30E-04 4.57E-05 Fe-59 Ci 1.41 E-04 9.08E-05 0
0 Co-58 Ci 3.50E-05 2.12E-05 0
0 Co-60 Ci 1.35E-04 6.58E-05 1.46E-05 1.26E-03 Zn-65 Ci 0
0 0
0 Sr-89 Ci 0
0 0
0 Sr-90 Ci 1.28E-07 2.88E-05 6.01 E-07 0
Cs-134 Ci 0
0 0
0 Cs-1 37 Ci 0
0 3.23E-06 0
Ce-141 Ci 0
0 0
0 Ce-144 Ci 0
0 0
0 AG-i1 OM Ci 2.72E-07 0
0 2.05E-06 NB-95 Ci 0
0 0
0
- AS-76 Ci 1.40E-03 0
0 4.58E-04
- NA-24 Ci 8.08E-05 0
0 0
- TC-99M Ci 1.40E-04 0
3.83E-05 0
Ba-La-140 Ci 0
0 0
0 Total for Period Ci 2.43E-03 1.32E-03 4.42E-04 2.11 E-03
- Particulate with less than eight (8) day half-life.
2-5
Waterborne Effluents K>
Summaries of the radionuclide total curie activities, average diluted concentrations, and percent of applicable Technical Requirement limits are included in Tables 2-3 and 2-4.
Batch Releases*
Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual
- 1.
Number of Batch Releases 18 20 19 26 83
- 2.
Total Time Period for a Batch Release 3.27E+03 7.50E+03 3.49E+03 4.78E+03 1.90E+04
- 3.
Maximum Time Period for a Batch Release 5.25E+02 1.61 E+03 2.91 E+02 2.93E+02 1.61 E+03
- 4.
Average Time Period for a Batch Release 1.82E+02 3.75E+02 1.83E+02 1.84E+02 2.29E+02
- 5.
Minimum Time Period for a Batch Release 2.1 OE+01 2.30E+01 2.50E+01 2.80E+01 2.1 OE+01
- 6.
Average Cooling Tower Blowdown 6.25E+03 7.32E+03 1.20E+04 7.44E+03 8.03E+03 Flow Rate During Periods of Release
- 7.
Susquehanna River Flow Rate 6.75E+06 1.09E+07 1.05E+06 6.94E+06 6.40E+06
- Units of time and flow are expressed in minutes and gallons per minute (gpm),
respectively.
Abnormal Releases
- 1.
Number of Releases 0
0 0
0
- 2.
Volume Released N/A N/A N/A N/A
- 3.
Total Activity Released N/A N/A N/A N/A If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required K>
Lower Limits of Detection (LLD) as specified in the SSES Technical Requirement 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. In all cases, these LLDs were less than the levels required by Technical Requirements. The following are typical LLDs.
Radionuclide LLD (uCVml)
Mn-54 4.5 E-08 Fe-59 5.0 E-08 Co-58 2.4 E-08 Co-60 5.4 E-08 Zn-65 4.9 E-08 Mo-99 1.7 E-07 1-131 2.0 E-08 Cs-1 34 2.2 E-08 2-6
Radionuclide Cs-1 37 Ce-1 41 Ce-1 44 Sr-89 Sr-90 Fe-55 H-3 Gross Alpha LLD (vCimI) 2.6 E-08 3.2 E-08 1.3 E-07 4.0 E-08 4.0 E-09 1.0 E-06 4.6 E-06 3.0 E-08 2-7
TABLE 2-3 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2002)
WATERBORNE EFLUENT - SUMMATION OF ALL RELEASES 1*~
,l
=
First AMiartar Second
- t..artar Third Minartar Fourth Minrhmr A
-4 Dr~1111^f
I nit ru B.
C.
D.
V1001wil dllU tlvuul r%&1ULuuu~t: vWwaz wmmXs
-uz -----
- 1. Total Release (excluding: Tritium, Ent.
Gases, Alpha)
Ci 1.03E-02 1.82E-03 1.50E-03 1.62E-02
- 2. Average Diluted Concentration During Period
,uCVml 1.34E-07 8.74E-09 9.46E-09 1.20E-07 Tritium
- 1. Total Release Ci 4.02E+00 1.77E+01 1.69E+01 2.75E+01
- 2. Average Diluted Concentration During Period
[PCVml 5.19E-05 8.54E-05 1.06E-04 2.04E-04
- 3. Percent of Applicable Limit (1.OE-2) 5.19E-01 8.54E-01 1.06E+00 2.04E+00 Dissolved and Entrained Gases
- 1. Total Release Ci 4.99E-05 4.13E-05 6.83E-05 1.35E-04
- 2. Average Diluted Concentration
,PCiml 6.45E-1 0 1.99E-1 0 4.31 E-1 0 1.OOE-09 During Period
- 3. Percent of Applicable Limit (2.0E-4) 3.23E-04 9.93E-05 2.15E-04 5.01 E-04 Gross Alpha Radioactivity
- 1. Total Release Ci 1.61E-06 1.14E-07 1.75E-06 0
E. Volume of Water Released (Prior to Dilution)
F. Volume of Dilution Water Used During Period of Release G. Volume of Dilution Water Used Over Entire Period I Gallons I 8.80E+04 I
2.96E+05 I 2.88E+05 l 3.91 E+05 I
I Liters I 3.33E+05 I
1.12E+06 I 1.09E+06 I 1.48E+06 I
l Gallons l 2.04E+07 I
5.47E+07 I 4.17E+07 l 3.51 E+07 I
Liters 7.70E+07 2.07E+08 1.58E+08 1.33E+08 l
Gallons l 6.63E+08 I
1.12E+09 I 1.50E+09 I 7.76E+08 l
Liters l 2.51 E+09 I
4.24E+09 I 5.69E+09 I 2.94E+09 2-8
TABLE 2-4 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2002)
WATERBORNE EFFLUENT 1
j Releases in Batch Mode Nuclides Unit First l
Second Third Fourth Released Quarter l Quarter Quarter l
Quarter A. Fission and Activation Products F-18 Ci 0
0 0
0 Na-24 Ci0 0
0 0
P-32 Ci 3.OOE-05 6.33E-07 0
0 Cr-51 Ci 3.58E-03 7.00E-04 3.74E-05 7.22E-03 Mn-54 Ci 9.16E-04 7.18E-04 8.39E-04 5.21 E-03 Fe-55 Ci 4.36E-03 0
9.47E-05 2.00E-03 Fe-59 Ci 1.88E-05 6.67E-05 3.52E-05 4.91 E-04 Co-58 Ci 1.17E-04 2.69E-05 9.24E-06 1.39E-04 Co-60 Ci 1.32E-03 3.04E-04 4.85E-04 1.1 6E-03 Zn-65 Ci 4.28E-06 0
0 0
As-76 Ci 0
0 0
0 Rb-86 Ci0 0
0 0
Sr-89 Ci 0
0 0
0 Sr-90 Ci 0
0 0
0 Sr-92 Ci 0
0 0
0 Nb-95 Ci 0
0 0
0 Mo-99 Ci 0
0 0
0 A-11 Om Ci 0
0 0
0 Cs-137 Ci 0
0 0
0 Total for Period Ci 1.03E-02 1.82E-03 1.50E-03 1.62E-02 B Tritium Total for Period I Ci 4.02E+00 l
1.77E+01 l
1.69E+01 l
2.75E+01 C. Dissolved and Entrained Gases Ar-41 Ci 0
0 0
0 Kr-85 Ci 0
0 0
0 Kr-86m Ci 0
0 0
0 Kr-87 Ci 0
0 0
0 Kr-88 Ci 0
0 0
0 Xe-131m Ci 0
0 0
0 Xe-133m Ci 0
0 0
0 Xe-1 33 Ci 4.54E-05 2.33E-05 1.38E-05 7.60E-05 Xe-1 35m Ci 0
0 0
4.97E-06 Xe-1 35 Ci 4.48 E-06 1.80E-05 5.45E-05 5.40E-05 Total for Period Cl 4.99E-05 4.13E-05 6.83E-05 1.35E-04 2-9
Figure 2-1 Susquehanna River Monthly Average Flow Rates Data Period: 2002 E
0o 0.
3 IL C) 0)
0) 16.0 14.0 12.0 10.0 8.0 6.0 4.0 2.0 0.0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
-.-- 2002 2-10
Figure 2-2 SSES Monthly Liquid Radwaste Discharge Totals Data Period: 2002 300 250 200 la D,,, 150 L.
Co
.=
0 X =
Eo 0 m CD ° 50 M=- 100 0
-50 I
A Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec I _ 2002 !
I 2-11
TABLE 2-5 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT ESTIMATED TOTAL ERRORS ASSOCIATED WITH EFFLUENTS MEASUREMENTS DATA PERIOD: JANUARY 1, 2002 - DECEMBER 31, 2002 ESTIMATED MEASUREMENT TOTAL ERROR
- 1.
Airborne Effluents
- a.
Fission and Activation Gases 15.9%
- b.
1-131 13.3%
- c.
Particulates (inc. Gross Alpha) 15.8%
- d.
Tritium 13.6%
- 2.
Waterborne Effluents
- a.
Fission and Activation Products 5.0%
- b.
Tritium 33%
- c.
Dissolved and Entrained Gases 8.4%
- d.
Gross Alpha Activity 6.0%
- e.
Volume of Waste Released 5.0%
(Prior to Dilution)
- f.
Volume of Dilution Water Used During Period 15.0%
ESTIMATED MAXIMUM MEASUREMENT ERROR
- 3.
Solid Wastes
- a.
Dry Active Waste (DAW) -
+95%
Class A Strong Tight Container (Compacted)
- b.
Bead Resin/Charcoal - Class A HIC (Pyrolysis)
+25%
- c.
Condensate Filtration System (CFS) Filters -
+/-25%
Class A Strong Tight Container (compacted)
- d.
Waste Oil - Class A
+25%
(Fuel Blending for Co-Generation)
- e.
RWCU Filter Media - Class A HIC (Dewatered)
+25%
- f.
Condensate Demineralizer/Radwaste Demineralizer -
+/-25%
Class A HIC (Pyrolysis) 2-12
ESTIMATED MAXIMUM MEASUREMENT MEASUREMENT ERROR
- 3.
Solid Wastes (cont.)
- g.
LRW Filter Media - Class A HIC (Dewatered)
+25%
- h.
Condensate Dermineralizer/Radwaste Demineralizer -
+95%
Class B HIC (Pyrolysis)
- i.
Cartridge Filters - Class C HIC (non-processed)
+25%
- j.
Dry Active Waste (DAW) - Class C HIC
+25%
(Non-Processed)
- k.
RWCU Filter Media - Class B HIC (Dewatered)
+95%
- 1.
Asbestos - Class A Strong Tight Container
+25%
(compacted)
- m.
Ash-Class A Strong Tight Container (Incineration)
+/-25%
- n.
LRW Filter Media - Class A HIC (Pyrolysis)
++/-5%
- o.
LRW Filter Media - Class B HIC (Pyrolysis)
+95%
- p.
Phosphoric Acid - Class A Drums (Incineration)
+25%
- q.
LRW Filter Media - Class C HIC (Pyrolysis)
+25%
2-13
SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT SOLID RADIOACTIVE WASTE DATA PERIOD:
JANUARY 1, 2002 - DECEMBER 31, 2002 PREPARED BY:
APPROVED BY:
MICHAEL C. MICCA - HEALTH PHYSICIST JEFFREY F.
OPERATIONS 2-14
REPORT NOTES
- 1.
All activities reported in millicuries (mCi) unless otherwise noted.
- 2.
Reported activities, as indicated with the (<) sign, are comprised in whole or part of MDL values.
- 3.
Estimated maximum measurement error is +/-25%.
2-15
TABLE 2-6 WASTE DISPOSITIONS Data Period: January 1, 2002 - December 31, 2002 A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Number of Shipments Mode of Transportation Destination 4
Truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS Number of Shipments Mode of Transportation None Destination 2-16
TABLE 2-7 Annual Waste Release Summary Report Year: 2002 Class: A Volume Reduction Vendor: No Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides C-14 CE-144 CO-58 C0-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-63 SB-124 SR-90 TC-99 ZN-65 Total Activity (Ci)
Container Volume Activity (mCi) 1.030E+01 1.100E+01 1.630E+04 5.490E+04 1.160E+05 1.140E+01 1.020E+06 9.120E+04 3.110E+01
< 1.270E-04 3.460E+05 1.390E+03 9.910E+02 2.990E+03 1.060E+00
< 4.170E-06 3.130E+02 1650.149 132.400 ft3
% of Total 0.00 %
0.00 %
0.99 %
3.33 %
7.03 %
0.00 %
61.81 %
5.53 %
0.00 %
0.00 %
20.97 %
0.08 %
0.06 %
0.18 %
0.00 %
0.00 %
0.02 %
100.00 %
3.749 m3 2-17
TABLE 2-8 Annual Waste Release Summary Report Year: 2002 Class: A Volume Reduction Vendor: No Source: RWCU Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides C-14 CE-144 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-63 PU-241 SB-125 SR-90 TC-99 ZN-65 Total Activity (Ci)
Container Volume Activity (mCi) 1.310E+02 4.700E+01 7.290E+03 2.180E+05 2.330E+04 2.390E+02 6.690E+04 1.410E+04 2.770E+01
< 4.740E-05 3.950E+05 2.640E+03 1.230E+03 4.280E+02 1.640E+05 5.280E+0O
< 1.800E-04 5.360E+03 898.698 132.400 ft3
% of Total 0.01______
0.01 %
0.01 %
0.81 %
24.26 %
2.59 %
0.03 %
7.44 %
1.57 %
0.00 %
0.00 %
43.95 %
0.29 %
0.14 %
0.05 %
18.25 %
0.00 %
0.00 %
0.60 %
100.00 %
3.749 m3 2-18
TABLE 2-9 Annual Waste Release Summary Report Year: 2002 Class: A Source: Asbe Container: Stro:
Process: Comp, Volume Reduction Vendor: Yes stos rng Tight Container acted Nuclides C-14 CE-144 CO-58 CO-60 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NI-59 NI-63 SB-125 SR-89 SR-90 TC-99 Total Activity (Ci)
Container Volume Activity (mCi) 7.OOOE-04 1.260E-02 4.100E-02 2.140E+00 4.600E-03 1.503E+01 7.460E-02 5.200E-03 4.OOOE-04 3.148E+00 3.100E-03 3.960E-02 7.900E-03 1.OOOE-04 2.OOOE-04
< O.OOOE+00 0.021 3.600 ft3
% of Total 0 0 0.00 %
0.06 %
0.20 %
10.43 %
0.02 %
73.29 %
0.36 %
0.03 %
0.00 %
15.35 %
0.02 %
0.19 %
0.04 %
0.00 %
0.00 %
0.00 %
100.00 %
0.102 m3 2-19
TABLE 2-10 Annual Waste Release Summary Report Year: 2002 Class: A Source: Ash Container: Stroi Process: Incii Volume Reduction Vendor: Yes ng Tight Container neration Nuclides AG-llOM C-14 CE-144 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NI-59 NI-63 K..-'PU-238 PU-239 PU-241 SB-125 SR-89 SR-90 TC-99 ZN-65 Total Activity (Ci)
Container Volume Activity (mCi) 6.100E-03 1.11OE-01 1.627E+00 5.597E+00 3.347E+02 1.580E-02 6.563E-01 2.063E+03 7.202E+00 3.763E+00 6.510E-02 4.113E+02 4.795E-01 5.819E+00
< O.OOOE+00
< O.OOOE+00 3.060E-02 9.832E-01 1.060E-02 2.900E-02 1.040E-02 3.923E+00
% of Total 0 0 0.00 %
0.00 %
0.06 %
0.20 %
11.79 %
0.00 %
0.02 %
72.65 %
0.25 %
0.13 %
0.00 %
14.49 %
0.02 %
0.20 %
0.00 %
0.00 %
0.00 %
0.03 %
0.00 %
0.00 %
0.00 %
0.14 %
2.839 38.431 ft3 100.00 %
1.088 m3 2-20
TABLE 2-11 Annual Waste Release Summary Report Year: 2002 Class: A Volume Reduction Vendor: Yes Source: Bead Resin/Charcoal Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides C-14 CE-144 CO-58 CO-60 CS-137 FE-55 H-3 I-129 MN-54 NI-59 NI-63 PU-239 PU-241 SR-89 SR-90 TC-99 Total Activity (Ci)
Container Volume Activity (mCi) 3.237E-02 1.734E-02 5.167E+00 1.212E+02 2.434E-02 1.453E+02 7.762E+01 8.479E-03 6.125E+01 8.330E-03 2.373E+00 1.100E-05 3.120E-03 1.020E-01 4.490E-04 3.405E-03 0.413 31.990 ft3
% of Total 0.01______
0.01 %
0.00 %
1.25 %
29.35 %
0.01 %
35.16 %
18.79 %
0.00 %
14.83 %
0.00 %
0.57 %
0.00 %
0.00 %
0.02 %
0.00 %
0.00 %
100.00 %
0.906 m3 2-21
TABLE 2-12 Annual Waste Release Summary Report Year: 2002 Class: A Source: CFS I Container: Stror Process: Compi Volume Reduction Vendor: Yes Filters pig Tight Container acted Nuclides C-14 CE-144 CM-244 CO-58 CO-60 CS-134 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NI-59 NI-63 PU-238 PU-239 PU-241 SB-125 SR-89 SR-90 TC-99 Total Activity (Ci)
Container Volume Activity (mCi) 1.559E+00 3.120E-02
< O.OOOE+00 5.313E-01 3.423E+02 4.076E-01 4.693E-01 4.435E+03 1.870E-02 3.366E+00 1.OOOE-04 2.474E+02 7.OOOE-04 6.528E+00
< O.OOOE+00
< O.OOOE+00 4.990E-02 1.900E-03 1.700E-03 1.220E-02
< O.OOOE+00 5.037 61.700 ft3
% of Total 0.03______
0.03 %
0.00 %
0.00 %
0.01 %
6.80 %
0.01 %
0.01 %
88.04 %
0.00 %
0.07 %
0.00 %
4.91 %
0.00 %
0.13 %
0.00 %
0.00 %
0.00 %
0.00 %
0.00 %
0.00 %
0.00 %
100.00 %
1.747 m3 2-22
TABLE 2-13 Annual Waste Release Summary Report Year: 2002 Class: A Volume Reduction Vendor: Yes Source: Condensate Demineralizer / Radwaste Demineralizer Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides AM-241 C-14 CE-144 CM-244 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 I-131 MN-54 NB-95 NI-59 NI-63 PU-241 SB-124 SR-90 TC-99 ZN-65 ZR-95 Total Activity (Ci)
Container Volume Activity (mCi) 1.620E-04 1.070E+02 3.081E-01 1.406E-03 1.055E+02 2.386E+03 3.248E+02 2.150E+00 1.813E+04 7.203E+01 4.201E+02 5.626E-01 1.056E-02 2.268E+03 2.882E+01 4.346E-01 3.647E+01 4.140E-02 1.107E+00 1.198E-01 1.498E-02 6.172E+00 3.150E+01 23.917 205.670 ft3
% of Total 0.00 %
0.45 %
0.00 %
0.00 %
0.44 %
9.97 %
1.36 %
0.01 %
75.79 %
0.30 %
1.76 %
0.00 %
0.00 %
9.48 %
0.12 %
0.00 %
0.15 %
0.00 %
0.00 %
0.00 %
0.00 %
0.03 %
0.13 %
100.00 %
5.824 m3 2-23
TABLE 2-14 Annual Waste Release Summary Report Year: 2002 1
Class: A Volume Reduction Vendor: Yes Source: Contaminated Waste Oil Container: None Process: Fuel Blending for Co-Generation Nuclides AM-241 C-14 CE-144 CM-242 CM-244 CO-60 CS-137 FE-55 H-3 1-129 MN-54 NI-63 PU-238 PU-239 PU-241 SR-90 TC-99 Total Activity (Ci)
Container Volume Activity (mCi) 5.670E-09 1.680E-07 3.470E-07 6.640E-09 4.660E-09 4.360E-04 7.630E-08 1.980E-03 4.300E-04
< 8.210E-12 1.100E-04 4.150E-06 1.290E-08 7.800E-09 1.560E-06 5.880E-08
< 4.050E-13 0.000 0.000 ft3
% of Total 0.00 %
0.01 %
0.01 %
0.00 %
0.00 %
14.72 %
0.00 %
66.84 %
14.52 %
0.00 %
3.71 %
0.14 %
0.00 %
0.00 %
0.05 %
0.00 %
0.00 %
100.00 %
0.000 m3 2-24
TABLE 2-15 Annual Waste Release Summary Report Year:
Class:
Source:
Container:
Process:
2002 A
Volume Reduction Vendor: Yes Liquid Radwaste Filter Media HIC (High Integrity Container)
Pyrolysis Nuclides C-14 CE-144 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 MN-54 NB-95 NI-63 SB-124 SR-90 ZN-65 ZR-95 Total Activity (Ci)
Container Volume Activity (mCi) 1.580E-04 7.500E-05 5.670E-03 7.450E-01 9.470E-05 1.710E-04 1.240E+0l 3.450E-03 7.860E-04 2.080E+00 1.130E-05 1.510E-02 5.600E-04 1.580E-05 7.360E-03 1.510E-04 0.015 5.980 ft3
% of Total 0.00______
0.00 %
0.00 %
0.04 %
4.88 %
0.00 %
0.00 %
81.27 %
0.02 %
0.01 %
13.63 %
0.00 %
0.10 %
0.00 %
0.00 %
0.05 %
0.00 %
100.00 %
0.169 m3 2-25
TABLE 2-16 Annual Waste Release Summary Report Year:
Class:
Source:
Container:
Process:
2002 A
Volume Reduction Vendor: Yes Phosphoric Acid Drums Incineration Nuclides AG-liOM AM-241 CE-144 CM-242 CM-244 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 MN-54 NI-59 NI-63 PU-238 PU-239 PU-241 SR-90 TC-99 ZN-65 Total Activity (Ci)
Container Volume Activity (mCi) 1.700E-02 1.620E-06 5.830E-05 1.83OE-06 1.170E-06 3.490E-03 1.940E-01 1.22OE-02 9.360E-05 7.450E-02 1.760E-02 1.210E-01 2.720E-01 8.630E-04 3.980E-03 1.980E-06 2.000E-06 5.710E-04 4.540E-05 1.500E-04 9.540E-03
% of Total 2.34 %
0.00 %
0.01 %
0.00 %
0.00 %
0.48 %
26.68 %
1.68 %
0.01 %
10.25 %
2.42 %
16.64 %
37.41 %
0.12 %
0.55 %
0.00 %
0.00 %
0.08 %
0.01 %
0.02 %
1.31 %
0.001 15.450 ft3 100.00 %
0.438 m3 2-26
TABLE 2-17 Annual Waste Release Summary Report Year:
Class:
Source:
Container:
Process:
2002 A
Volume Reduction Vendor: Yes Processed DAW Strong Tight Container Compacted Nuclides AG-llOM AM-241 C-14 CE-144 CM-242 CM-244 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-59 NI-63 PU-238 PU-239 PU-241 SB-124 SB-125 SR-89 SR-90 TC-99 ZN-65 ZR-95 Total Activity (Ci)
Container Volume Activity (mCi) 2.127E+00 2.299E-03 1.816E-01 3.772E+00 2.286E-03 1.809E-03 1.026E+01 5.178E+02 7.261E+00 2.742E+00 2.648E+03 5.237E+01 4.216E+00 6.260E-02 8.013E+02 2.453E-0l 7.105E-0l 9.541E+00 5.672E-03 3.336E-03 6.848E-01 1.432E-0l 1.236E+00 2.864E-02 2.423E-02
< 1.360E-05 7.111E+00 1.235E-0l 4.070 1538.130 ft3
% of Total 0.05______
0.05 %
0.00 %
0.00%
0.09 %
0.00 %
0.00 %
0.25 %
12.72 %
0.18 %
0.07 %
65.06 %
1.29 %
0.10 %
0.00 %
19.69 %
0.01 %
0.02 %
0.23 %
0.00 %
0.00 %
0.02 %
0.00 %
0.03 %
0.00 %
0.00 %
0.00 %
0.17 %
0.00 %
100.00 %
43.556 m3 2-27
TABLE 2-18 Annual Waste Release Summary Report Year:
Class:
Source:
Container:
Process:
2002 B
Volume Reduction Vendor: No RWCU Filter Media HIC (High Integrity Container)
Dewatered Nuclides C-14 CE-144 CM-242 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-59 NI-63 PU-238 PU-239 PU-241 SB-124 SB-125 SR-89 TC-99 ZN-65 ZR-95 Total Activity (Ci)
Container Volume Activity (mCi)
- 2. 220E+02 2.690E+02 3.090E-02 3.020E+03 2.390E+05 2.850E+03 3.810E+02 1.180E+06 2.060E+03 1.380E+03
< 1.080E-04 1.870E+05 9.600E+03 2.530E+01 3.840E+03 1.300E-02 4.490E-03 1.040E+00 1.020E+02 8.190E+03 8.450E+01 7.OOOE+01 2.470E+03 8.890E+03 1649.455 132.000 ft3
% of Total 0.01______
0.01 %
0.02 %
0.00 %
0.18 %
14.49 %
0.17 %
0.02 %
71.54 %
0.12 %
0.08 %
0.00 %
11.34 %
0.58 %
0.00 %
0.23 %
0.00 %
0.00 %
0.00 %
0.01 %
0.50 %
0.01 %
0.00 %
0.15 %
0.54 %
100.00 %
3.738 m3 2-28
TABLE 2-19 Annual Waste Release Summary Report Year:
Class:
Source:
Container:
Process:
2002 B
Volume Reduction Vendor: Yes Condensate Demineralizer / Radwaste Demineralizer HIC (High Integrity Container)
Pyrolysis Nuclides C-14 CO-57 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NI-59 NI-63 SR-89 SR-90 TC-99 ZN-65 Total Activity (Ci)
Container Volume Activity (mCi) 1.843E+00 7.150E+01 9.600E+03 7.750E+04 5.673E+03 6.244E+01 1.874E+04 7.140E+01 7.880E+00 5.583E-01 5.180E+03 9.460E-01 2.791E+02 1.400E+01 3.840E+00 4.304E-01 2.630E+03 119.837 22.000 ft3
% of Total 0.00______
0.00 %
0.06 %
8.01 %
64.67 %
4.73 %
0.05 %
15.64 %
0.06 %
0.01 %
0.00 %
4.32 %
0.00 %
0.23 %
0.01 %
0.00 %
0.00 %
2.19 %
100.00 %
0.623 m3 2-29
TABLE 2-20 Annual Waste Release Summary Report Year: 2002 Class: B Volume Reduction Vendor: Yes Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides C-14 CE-144 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 HF-181 I-129 MN-54 NB-95 NI-63 SB-124 SR-90 TC-99 ZN-65 ZR-95 Total Activity (Ci)
Container Volume Activity (mCi) 4.726E+00 4.119E+00 1.611E+03 2.438E+04 2.246E+04 5.219E+00 4.408E+05 2.876E+03 2.644E+01 2.407E+01 3.805E-01 6.982E+04 7.417E+01 4.537E+02 1.309E+02 4.833E-01 1.254E-02 2.647E+02 4.060E-01 562.931 18.400 ft3
% of Total 0.00______
0.00 %
0.00 %
0.29 %
4.33 %
3.99 %
0.00 %
78.30 %
0.51 %
0.00 %
0.00 %
0.00 %
12.40 %
0.01 %
0.08 %
0.02 %
0.00 %
0.00 %
0.05 %
0.00 %
100.00 %
0.521 m3 2-30
TABLE 2-21 Annual Waste Release Summary Report Year:
Class:
Source:
Container:
Process:
2002 C
Volume Reduction Vendor: No Cartridge Filters HIC (High Integrity Container)
Non-Processed Nuclides AG-liOM C-14 CE-144 CM-242 CM-244 CO-57 CO-58 CO-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-59 NI-63 PU-238 PU-239 PU-241 SB-125 SR-89 SR-90 TC-99 ZN-65 Activity (mCi) 1.540E+00 5.890E-01 1.071E+01 5.070E-03 5.770E-05 4.540E+00 7.220E+02 1.048E+04 3.240E+02 8.920E-02 1.673E+01 3.460E+03 6.890E+00 1.407E+00 7.210E-01 8.267E+02 4.592E-03 1.060E+00 5.463E+01 1.160E-04 3.980E-05 1.172E+01 7.050E-01 4.860E-02 2.050E-02 1.340E+01 6.143E+02 16.555 41.980 ft3
% of Total 0.01______
0.01 %
0.00 %
0.06 %
0.00 %
0.00 %
0.03 %
4.36 %
63.32 %
1.96 %
0.00 %
0.10 %
20.90 %
0.04 %
0.01 %
0.00 %
4.99 %
0.00 %
0.01 %
0.33 %
0.00 %
0.00 %
0.07 %
0.00 %
0.00 %
0.00 %
0.08 %
3.71 %
100.00 %
1.189 m3 Total Activity (Ci)
Container Volume 2-31
TABLE 2-22 Annual Waste Release Summary Report Year:
Class:
Source:
Container:
Process:
2002 C
Volume Reduction Vendor: No Non-Processed DAW HIC (High Integrity Container)
Non-Processed Nuclides C-14 CE-144 CM-242 CO-58 CO-60 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-95 NI-59 NI-63 PU-241 SB-125 SR-89 SR-90 TC-99 ZN-65 Total Activity (Ci)
Container Volume Activity (mCi) 8.300E-02 1.610E+00 5.320E-02 4.630E+00 3.430E+03 8.830E+00 1.360E+03 7.890E-02 3.780E+00 4.630E-02 4.730E+02 4.250E+00 3.450E-01 5.830E+01 3.680E+01 7.130E-01 1.210E-04 1.750E-02
< 1.440E-01 2.820E+01
% of Total 0 0 0.00 %
0.03 %
0.00 %
0.09 %
63.39 %
0.16 %
25.13 %
0.00 %
0.07 %
0.00 %
8.74 %
0.08 %
0.01 %
1.08 %
0.68 %
0.01 %
0.00 %
0.00 %
0.00 %
0.52 %
5.411 90.430 ft3 100.00 %
2.561 m3 2-32
TABLE 2-23 Annual Waste Release Summary Report Year: 2002 Class: C Volume Reduction Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Pyrolysis Vendor: Yes Nuclides Activity (mCi)
C-14 CE-144 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 HF-181 I-129 MN-54 NB-95 NI-63 SB-124 SR-90 TC-99 ZN-65 ZR-95
- 6. 640E+00 6.120E+00 3.214E+03 3.455E+04 1.203E+04 7.350E+00 6.330E+05
- 8. 640E+03 3.511E+01 8.960E+00 4.870E-O1 1.485E+05 1.060E+02 6.380E+02 4.641E+02 6.820E-0l
- 1. 607E-02 6.129E+02 9.380E+01
% of Total 0___00____
0.00 %
0.00 %
0.38 %
4.10 %
1.43 %
0.00 %
75.19 %
1.03 %
0.00 %
0.00 %
0.00 %
17.64 %
0.01 %
0.08 %
0.06 %
0.00 %
0.00 %
0.07 %
0.01 %
Total Activity (Ci)
Container Volume 841.914 22.820 ft3 100.00 %
0.646 m3 2-33
SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 3-1
METEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the Susquehanna SES (SSES) site since the early 1970s. At the present time, the meteorological system is based on a 300-foot high tower located approximately 1,000 feet to the southeast of the plant. Wind sensors are mounted at the 10m and 60m elevations on this tower.
Vertical temperature differential is measured with redundant sensor pairs between the 10m and 60m levels. Sigma theta (the standard deviation of horizontal wind direction) is calculated from wind direction at both levels. Dew point and ambient temperature sensors are present at the 10m level. Precipitation is measured at ground level.
A back-up meteorological tower was erected in 1982. It is a 1Gm tower providing alternate measurements of wind speed, wind direction, and sigma theta. A 10m supplemental downriver meteorological tower is also available. This tower measures wind speed, wind direction, sigma theta, temperature and dew point.
SSES meteorological data are transmitted to the plant Control Room, Technical Support Center, Emergency Operations Facility for emergency response availability, and ABSG Consulting, Inc.
ABSG Consulting, Inc., located in Rockville, Maryland, provides meteorological consulting services to PPL Susquehanna, LLC.
Dispersion modeling for effluents from normal operation of SSES is done using the MIDAS system XDCALC program, a straight-line Gaussian plume model designed to estimate average relative concentration.
The model was developed in accordance with Regulatory Guide 1.111. For periods when the wind speed is calm, the actual wind direction that occurred is used.
XDCALC and the XQINTR program that interpolates X/Q values to exact locations both use terrain correction factors to account for the temporal and spatial variations in the airflow in the region. A straight-line trajectory model assumes that a constant mean wind transports and diffuses effluents in the direction of airflow at the release point within the entire region of interest. The SSES terrain correction factors were taken from SSES FSAR Table 2.3-128.
3-2
TABLE 3-1 SSES METEOROLOGICAL DATA RECOVERY FOR 2002 PERCENT VALID PARAMETER DATA RECOVERY Wind Speed I Om - Primaryt (i 99.5 Wind Speed 60m - Primary 99.5 Wind Speed lOm - Backup(2) 99.9 Wind Speed lOm - Downriver( 3) 99.9 Wind Direction IOm -Primary 99.4 Wind Direction 60m - Primary 99.5 Wind Direction I Om - Backup 99.9 Wind Direction 1 Om - Downriver 100.0 Temperature lOm -Primary 99.6 Dew Point lOm - Primary 98.6 Delta Temperature 60m - Primary 99.0 Sigma Theta I Om - Primary 99.4 Sigma Theta 60m - Primary 99.5 Sigma Theta lOm-Backup 99.9 Sigma Theta lOm - Downriver 100.0 Precipitation - Primary 100.0 Composite Parameters Wind Speed and Direction I Om, 99.0 Delta Temperature 60-lOm Wind Speed and Direction 60m, 99.0 Delta Temperature 60-lOnm
"'SSES "Primary" meteorological tower (2)SSES "Backup" meteorological tower (3)SSES "Downriver" meteorological tower 3-3
TABLE 3-2 Table 2. SSES Joint Frequency Distribution of Wind Speed and Direction lOm Versus Delta Temperature 60-lOm for the Period of January 1, 2002 through December 31, 2002 SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
A DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 3
12 2
0 0
17 NNE 1
2 11 1
0 0
15 NE 2
9 0
0 0
0 11 ENE 1
3 0
0 0
0 4
E 2
2 0
0 0
0 4
ESE 0
2 2
0 0
0 4
SE 1
1 4
0 0
0 6
SSE 1
4 5
0 0
0 10 S
2 10 11 0
0 0
23 SSW 3
26 26 0
0 0
55 SW 2
40 46 6
0 0
94 WSW 0
6 21 2
0 0
29 W
0 0
1 0
0 0
1 WNW 1
0 0
0 0
0 1
NW 0
0 1
0 0
0 1
NNW 0
0 3
0 0
0 3
TOTAL 16 108 143 11 0
0 278 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-4
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
B DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A
-WIND SPEED(MPH)
WIND DIRECTION N
NNE NE ENE E
WNW NW NNW 1-3 4-7 0
8 2
15 3
10 4
2
.4 3
2 1
2 4
1 2
3 6
3 27 2
43 0
10 0
1 0
0 0
0 0
2 8-12 13 6
0 0
0 1
0 0
7 10 67 27 5
0 1
7 13-18 1
0 0
0 0
0 0
0 0
1 8
5 0
0 0
2 19-24 0
0 0
0 0
0 0
0 0
0 1
0 0
0 0
0
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 TOTAL 22 23 13 6
7 4
6 3
16 41 121 42 6
0 1
11 TOTAL 26 134 144 17 1
0 322 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION O
HOURS OF MISSING DATA:
85 3-5
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
C DT/DZ ELEVATION:
SPEED:10M SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 10 17 0
0 0
27 NNE 1
25 9
0 0
0 35 NE 2
16 1
0 0
0 19 ENE 6
5 0
0 0
0 11 E
7 3
0 0
0 0
10 ESE 7
5 0
0 0
0 12 SE 3
7 0
0 0
0 10 SSE 4
8 2
0 0
0 14 S
7 12 8
0 0
0 27 SSW 0
27 5
0 0
0 32 SW 2
72 47 6
0 0
127 WSW 1
12 32 12 1
0 58 W
2 4
5 3
0 0
14 WNW 0
1 3
0 0
0 4
NW 0
2 4
2 0
0 8
NNW 0
5 11 4
0 0
20 TOTAL 42 214 144 27 1
0 428 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-6
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
D DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:10M WD LAPSE:DT.A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL NN NNE ENE E
WNW NWr NNW 16 138 63 177 73 143 70 51 82 36 73 60 78 86 52 98 60 99 57 151 42 209 25 101 10 75 5
50 8
62 14 82 85 26 8
1 2
9 11 22 38
,33 162 165 94 69 124 136 1_
0--
0-1 0
0 0
0 0
0 0
0 0
0 0
1 0
0 0
0 0
0 0
0 1
0 0
0 0
0 8
0 0
51 0
0 33 5
0 27 0
0 20 0
0 30 0
0 240 266 224 124 121 143 175 172.
198 241 421 342 217 151 214 262 TOTAL 728 1618 985 172 5
0 3511 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-7
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
E DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
38 71 5
0 0
0 114 NNE 94 127 12 0
0 0
233 NE 175 58 4
0 0
0 239 ENE 186 3
1 0
0 0
192 E
171 7
0 0
0 0
180 ESE 111 4
0 0
0 0
116 SE 99 9
0 1
0 0
109 SSE 94 35 2
0 0
0 131 S
158 80 18 3
0 0
259 SSW 119 163 25 0
0 0
308 SW 44 149 21 0
1 0
215 WSW 19 39 13 0
0 0
71 W
13 15 4
0 0
0 32 WNW 8
11 0
0 0
0 19 NW 7
14 10 0
0 0
31 NNW 7
28 9
-0 0
0 44 TOTAL 1343 813 124 4
1 0
2293 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-8
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
F DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
7 5
0 0
0 0
12 NNE 33 6
0 0
0 0
39 NE 114 5
0 0
0 0
119 ENE 471 7
0 0
0 0
479 E
194 0
0 0
0 0
195 ESE 83 0
0 0
0 0
83 SE 44 0
0 0
0 0
44 SSE 56 3
0 0
0 0
59 S
56 5
0 0
0 0
61 SSW 27 6
0 0
0 0
33 SW 9
7 0
0 0
0 16 WSW 2
0 0
0 0
0 2
W 1
1 0
0 0
0 2
WNW 2
0 0
0 0
0 2
NW 1
1 0
0 0
0 2
NNW 2
2 0
0 0
0 4
TOTAL 1102 48 0
0 0
0 1152 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-9
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
G DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 0
0 0
0 0
1 NNE 13 1
0 0
0 0
14 NE 88 4
0 0
0 0
92 ENE 425 13 0
0 0
0 438 E
69 0
.0 0
0 0
69 ESE 29 0
0 0
0 0
29 SE 18 0
0 0
0 0
18 SSE 13 0
0 0
0 0
13 S
4 0
0 0
0 0
4 SSW 7
3 0
0 0
0 10 SW 1
0 0
0 0
0 1
WSW 1
0 0
0 0
0 1
W 0
0 0
0 0
0 0
WNW 0
0 0
0 0
0 0
NW 0
0 0
0 0
0 0
NNW 1
0 0
0 0
0 1
TOTAL 670 21 0
0 0
0 691 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-10
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF.RECORD =
02010101-02123124 STABILITY CLASS:
ALL DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:10M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
62 235 132 4
0 0
433 NNE 207 353 64 1
0 0
625 NE 457 245 13 0
0 0
717 ENE 1163 84
- 2.
0 0
0 1254 E
529 51 2
0 0
0 586 ESE 305 72 12 1
0 0
391 SE 245 107 15 1
0 0
368 SSE 221 150 31 0
0 0
402 S
290 212 82 4
0 0
588 SSW 216 403 99 1
0 0
720 SW 102 520 343 28 2
0 995 WSW 48 168 258 70 1
0 545 W
26 96 109 36 5
0 272 WNW 16 62 72 27 0
0 177 NW 16 79 140 22 0
0 257 NNW 24 119 166 36 0
0 345 TOTAL 3927 2956 1540 231 8
0 8675 PERIODS OF CALM(HOURS):
13 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-11
TABLE 3-3 Table 3. SSES Joint Frequency Distribution of Wind Speed and Direction 60m Versus Delta Temperature 60-1 Om for the Period of January 1, 2002 through December 31, 2002 SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
A DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 1
15 3
0 0
19 NNE 0
3 6
6 0
0 15 NE 4
7 2
0 0
0 13 ENE 1
3 0
0 0
0 4
E 0
1 0
0 0
0 1
ESE 1
1 0
3 0
0 5
SE 2
1 0
4 0
0 7
SSE 0
0 1
1 0
0 2
S 0
5 3
10 0
0 18 SSW 1
13 23 8
3 0
48 SW 1
14 55 30 1
1 102 WSW 0
3 15 20 0
0 38 W
0 0
1 1
0 0
2 WNW 0
1 0
0 0
0 1
NW 0
0 0
1 0
0 1
NNW 0
0 1
1 0
0 2
TOTAL 10 53 122 88 4
1 278 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-12
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
B DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 3
14 6
0 0
24 NNE 2
12 10 2
0 0
26 NE 3
7 4
0 0
0 14 ENE 2
3 1
0 0
0 6
E 3
0 1
0 0
0 4
ESE 2
2 0
1 0
0 5
SE 0
2 0
0 0
0 2
SSE 0
0 1
0 0
0 1
S 1
2 5
3 0
0 11 SSW 2
9 12 6
4 0
33 SW 0
21 63 27 2
4 117 WSW 0
3 27 28 2
0 60 W
0 0
8 0
0 0
8 WNW 0
0 0
0 0
0 0
NW 0
2 2
0 1
0 5
NNW 0
0 4
1 1
0 6
TOTAL 16 66 152 74 10 4
322 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-13
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
C DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 4
21 1
0 0
27 NNE 1
15 17 6
0 0
39 NE 5
15 1
1 0
0 22 ENE 5
7 0
0 0
0 12 E
4 2
0
-0 0
0 6
ESE 1
6 0
0 0
0 7
SE 3
3 4
0 0
0 10 SSE 0
1 0
1 0
0 2
S 4
10 11 7
0 0
32 SSW 2
9 13 5
2 0
31 SW 2
31 54 19 3
0 109 WSW 0
7 37 30 10 1
85 W
1 1
3 7
1 0
13 WNW 2
0 4
0 0
0 6
NW 0
2 4
5 0
0 11 NNW 0
4 7
3 2
0 16 TOTAL 31 117 176 85 18 1
428 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-14
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
D DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
8 44 127 18 0
0 197 NNE 25 90 140 27 0
0 282 NE 48 82 91 10 0
0 231 ENE 43 46 15 0
0 0
104 E
29 63 14 3
0 0
109 ESE 25 42 22 7
2 0
,98 SE 27 61 37 10 0
0 135 SSE 34 46 66 14 1
0 161 S
29 44 60 35 5
0 173 SSW 24 80 70 42 4
0 220 SW 26 127 148 68 6
0 375 WSW 11 71 184 214 43 2
525 W
2 31 107 116 29 7
292 WNW 4
13 79 49 11 0
156 NW 3
17 115 72 3
0 210 NNW 8
36 137 60 2
0 243 TOTAL 346 893 1412 745 106 9
3511 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0.
HOURS OF MISSING DATA 85 3-15
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
E DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
17 84 33 2
0 0
136 NNE 60 148 69 18 0
0 295 NE 102 89 51 7
0 0
249 ENE 63 34 4
1 0
0 102 E
37 22 9
0 0
0 68 ESE 38 16 3
0 0
0 57 SE 39 15 8
2 1
0 65 SSE 38 33 20 3
0 0
94 S
54 59 54 19 7
3 196 SSW 37 87 104 43 5
0 276 SW 35 104 121 27 0
1 288 WSW 14 64 128 56 1
0 263 W
10 29 13 5
1 0
58 WNW 2
19 7
0 0
0 28 NW 4
12 22 11 0
0 49 NNW 10 27 30 2
0 0
69 TOTAL 560 842 676 196 15 4
2293 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-16
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
F DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
18 69 5
0 0
0 92 NNE 84 226 6
0 0
0 316 NE 115 52 1
0 0
0 168 ENE 51 5
0 0
0 0
56 E
32 5
0 0
0 0
37 ESE 36 6
0 0
0 0
42 SE 34 5
1 0
0 0
40 SSE 32 7
0 0
0 0
39 S
42 34 6
1 0
0 83 SSW 21 50 10 0
0 0
81 SW 10 52 27 0
0 0
89 WSW 8
11 50 5
0 0
74 W
- 2 4
0 0
0 0
6 WNW 1
4 0
0 0
0 5
NW 2
6 2
0 0
0 10 NNW 3
8 3
0 0
0 14 TOTAL 491 544 111 6
0 0
1152 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:.
85 3-17
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
G DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
6 44 4
0 0
0 54 NNE 55 141 0
0 0
0 196 NE 78 36 1
0 0
0 115 ENE 36 13 0
0 0
0 49 E
28 4
0 0
0 0
32 ESE 21 5
0 0
0 0
26 SE 25 1
1 0
0 0
27 SSE 20 5
0 0
0 0
25 S
15 26 2
0 0
0 43 SSW 6
38 3
0 0
0 47 SW 7
24 6
1 0
0 38 WSW 2
6 13 6
0 0
27 W
0 1
0 0
0 0
1 WNW 1
1 0
0 0
0 2
NW 1
2 3
0 0
0 6
NNW 0
3 0
0 0
0 3
TOTAL 301 350 33 7
0 0
691 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-18
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
02010101-02123124 STABILITY CLASS:
ALL DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
51 249 219 30 0
0 549 NNE 227 635 248 59 0
0 1169 NE 355 288 151 18 0
0 812 ENE 201 111 20 1
0 0
333 E
133 97 24 3
0 0
257 ESE 124 78 25 11 2
0 240 SE 130 88 51 16 1
0 286 SSE 124 92 88 19 1
0 324 S
145 180 141 75 12 3
556 SSW 93 286 235 104 18 0
736 SW 81 373 474 172 12 6
1118 WSW 35 165 454 359 56 3
1072 W
15 66 132 129 31 7
380 WNW 10 38 90 49 11 0
198 NW 10 41 148 89 4
0 292 NNW 21 78 182 67 5
0 353 TOTAL 1755 2865 2682 1201 153 19 8675 PERIODS OF CALM(HOURS):
0 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
85 3-19
(
TABLE 34 2002 SSES ANNUAL RELATIVE CONCENTRATIONS NO DECAY, UNDEPLETED X/Q (sec/m3)
(I DATES OF LAST X/Q ACCUMULATION ARE FROM 2 1 1 1 0 TO 2123124 0 X/Q ACCUMULATION FOR GROUND AVERAGE SEC/M3 FOR RELEASE POINT 1
MILES 5-10 0.5-1
- DIRECTIONI 3.9379E-06
- DIRECTION I 8.4537E-06
- DIRECTION I 1.5953E-05
- DIRECTION I 5.0106E-05
- DIRECTION 2.0427E-05
- DIRECTION 1.3100E-05
- DIRECTION 1.0910E-05
- DIRECTION 9.6156E-06
- DIRECTION 7.8065E-06
- DIRECTION 8.7781E-06
- DIRECTION 6.3793E-06
- DIRECTION 3.5508E-06
- DIRECTION 1.6539E-06
- DIRECTION 1.1817E-06
- DIRECTION 1.7326E-06
- DIRECTION 2.4100E-06 I
1-2 FROM N
7.6082E-07 FROM NNE 1.6986E-06 FROM NE 2.9766E-06 FROM ENE 9.0704E-06 FROM E 3.7301E-06 FROM ESE 2.5055E-06 FROM SE 2.1229E-06 FROM SSE 1.8520E-06 FROM S 1.6745E-06 FROM SSW 1.7834E-06 FROM SW 1.2807E-06 FROM WSW 6.8882E-07 FROM W 3.1928E-07 FROM WNW 2.2083E-07 FROM NW 3.2640E-07 FROM NNW 4.5501E-07 2-3 3-4 4-5 10-20 20-30 30-40 40-50 3.1798E-07 7.6559E-07 1.3543E-06 4.4188E-06 1.6598E-06 1.1464E-06 9.7689E-07 8.3697E-07 8.2542E-07 8.2504E-07 6.0772E-07 3.2088E-07 1.3771E-07 8.9351E-08 1.3054E-07 1.9232E-07 1.6784E-07 4.1443E-07 7.7327E-07 2.6459E-06 9.4409E-07 6.4959E-07 5.5702E-07 4.7779E-07 4.8206E-07 4.6985E-07 3.4847E-07 1.8911E-07 7.5264E-08 4.7012E-08 6.6585E-08 1.0242E-07 1.0808E-07 2.6897E-07
- 5. 1429E-07 1.7763E-06 6.3202E-07 4.3301E-07 3.7062E-07 3.2270E-07 3.3147E-07 3.1292E-07 2.3390E-07 1.2965E-07 4.9263E-08 3.0058E-08 4.2229E-08 6.4534E-08 4.0255E-08 1.0065E-07 2.0460E-07 7.0835E-07 2.5725E-07 1.7568E-07 1.5162E-07 1.3976E-07 1.5446E-07 1.3103E-07 1.0287E-07 6.1466E-08 2.0085E-08 1.1127E-08 1.5208E-08 2.2452E-08 1.1095E-08 2.7988E-08 6.2481E-08 2.0817E-07 8.1744E-08 4.9303E-08 3.8241E-08 3.7189E-08 4.3137E-08 3.4478E-08 2.6641E-08 1.9317E-08 5.3873E-09 3.0426E-09 3.9918E-09 5.5906E-09 5.3949E-09 1.3854E-08 3.1536E-08 1.0163E-07 4.1578E-08 2.1806E-08 1.4184E-08 1.3424E-08 1.4937E-08 1.3187E-08 8.9831E-09 7.2503E-09 2.1671E-09 1.4433E-09 1.8798E-09 2.6531E-09 3.4030E-09 8.8342E-09 2.0317E-08 6.6014E-08 2.6941E-08 1.4056E-08 9.0846E-09 8.6133E-09 9.5594E-09 8.3986E-09 5.6881E-09 3.7117E-09 1.3405E-09
- 8. 9416E-10 1.1585E-09 1.6446E-09 2.4127E-09 6.3454E-09 1.4810E-08 4.8625E-08 1.9662E-08 1.0209E-08 6.5577E-09 6.2179E-09 6.8711E-09 6.0193E-09 4.0439E-09 2.0332E-09 9.3094E-10 6.2184E-10 8.0130E-10 1.1452E-09 3-20
C
(
TABLE 3-5 2002 SSES ANNUAL RELATIVE CONCENTRATIONS 2.26-DAY DECAY, UNDEPLETED X/Q (sec/m3)
DATES OF LAST X/Q ACCUMULATION ARE FROM 2 1 1 1 0 TO 2123124 0 X/Q ACCUMULATION FOR GROUND DECAYED S.AVG SEC/M3 FOR RELEASE POINT 1
0.5-1
- DIRECTION 3.9307E-06
- DIRECTION 8.4327E-06
- DIRECTION 1.5906E-05
- DIRECTION 4.9946E-05
- DIRECTION 2.0348E-05
- DIRECTION 1.30SOE-05
- DIRECTION 1.0873E-05
- DIRECTION 9.5873E-06
- DIRECTION 7.7871E-06
- DIRECTION 8.7601E-06
- DIRECTION 6.3693E-06
- DIRECTION 3.5457E-06
- DIRECTION 1.6516E-06
- DIRECTION 1.1800E-06
- DIRECTION 1.7305E-06
- DIRECTION 1-2 FROM N 7.5660E-07 FROM NNE 1.6861E-06 FROM NE 2.9502E-06 FROM ENE 8.9827E-06 FROM E
3.6872E-06 FROM ESE 2.4767E-06 FROM SE 2.1016E-06 FROM SSE 1.8358E-06 FROM S 1.6619E-06 FROM SSW 1.7724E-06 FROM SW 1.2745E-06 FROM WSW 6.8578E-07 FROM W 3.1792E-07 FROM WNW 2.1987E-07 FROM NW 3.2520E-07 FROM NNW 2-3 3-4 4-5 MILES 5-10 10-20 20-30 30-40 40-50 10-2 0 20-30 30-40 An-n 3.1501E-07 7.5608E-07 1.3342E-06 4.3477E-06 1.6280E-06
- 1. 1244E-06 9.6045E-07 8.2463E-07 8.1505E-07 8.1649E-07 6.0279E-07
- 3. 1850E-07 1.3673E-07 8.8692E-08 1.2974E-07 1.9101E-07 1.6562E-07 4.0713E-07 7.5723E-07 2.5866E-06 9.1880E-07 6.3211E-07 5.4383E-07 4.6787E-07 4.7355E-07 4.6302E-07 3.4448E-07 1.8712E-07 7.4514E-08 4.6523E-08 6.6009E-08 1.0143E-07 1.0623E-07 2.6285E-07 5.0058E-07 1.7253E-06 6.1032E-07 4.1805E-07 3.5934E-07 3.1408E-07 3.2395E-07 3.0706E-07 2.3045E-07 1.2789E-07 4.8630E-08 2.9654E-08 4.1757E-08 6.3733E-08 3.9107E-08 9.6829E-08 1.9556E-07 6.7488E-07 2.4270E-07 1.6563E-07 1.4395E-07 1.3355E-07 1.4864E-07 1.2695E-07 1.0033E-07 6.0051E-08 1.9651E-08 1.0874E-08 1.4922E-08 2.1985E-08 1.0462E-08 2.5873E-08 5.7060E-08 1.8901E-07 7.2746E-08 4.3792E-08 3.4432E-08 3.3930E-08 3.9926E-08 3.2355E-08 2.5326E-08 1.8417E-08 5.1531E-09 2.9024E-09 3.8406E-09 5.3579E-09 4.8900E-09 1.2148E-08 2.7112E-08 8.6561E-08 3.4236E-08 1.7891E-08 1.1902E-08 1.1517E-08 1.3128E-08 1.1862E-08 8.2561E-09 6.6923E-09 2.0114E-09 1.3330E-09 1.7616E-09 2.4710E-09 2.9659E-09 7.3509E-09 1.6448E-08 5.2757E-08 2.0531E-08 1.0655E-08 7.1046E-09 6.9503E-09 7.9802E-09 7.2438E-09 5.0561E-09 3.3179E-09 1.2071E-09 7.9942E-10 1.0573E-09 1.4888E-09 2.0218E-09
- 5. O100E-09 1.1292E-08 3.6479E-08 1.3873E-08 7.1498E-09 4.7791E-09 4.7189E-09 5.4489E-09 4.9786E-09 3.4766E-09 1.7592E-09 8.1300E-10 5.3792E-10 7.1209E-10 1.0075E-09 2.4068E-06 4.5315E-07 3-21
(
TABLE 3-6 2002 SSES ANNUAL RELATIVE CONCENTRATIONS 8-DAY DECAY, DEPLETED X/Q (sec/m3)
(
DATES OF LAST X/Q ACCUMULATION ARE FROM 2 1 1 1 0 TO 2123124 0 X/Q ACCUMULATION FOR DECAYED DEPLETION SEC/M3 FOR RELEASE POINT 1
0.5-1
- DIRECTION 3.5978E-06
- DIRECTION 7.7222E-06
- DIRECTION 1.4571E-05
- DIRECTION 4.5761E-05
- DIRECTION 1.8652E-05
- DIRECTION 1.1962E-05
- DIRECTION 9.9631E-06
- DIRECTION 8.7825E-06
- DIRECTION 7.1310E-06
- DIRECTION 8.0195E-06
- DIRECTION 5.8288E-06
- DIRECTION 3.2445E-06
- DIRECTION 1.5112E-06
- DIRECTION 1.0797E-06
- DIRECTION 1.5833E-06
1.4175E-06 FROM SSW 1.5103E-06 FROM SW 1.0850E-06 FROM WSW 5.8363E-07 FROM W 2.7054E-07 FROM WNW 1.8711E-07 FROM NW 2.7661E-07 FROM NNW 3.8556E-07 2-3 3-4 4-5 MILES 5-10 10-20 20-30 30-40 40-50n 10-20 20-3 0 30-40 4fl-!fl 2.5716E-07 6.1862E-07 1.0935E-06 3.5668E-06 1.3386E-06 9.2451E-07 7.8836E-07 6.7585E-07 6.6693E-07 6.6704E-07 4.9166E-07 2.5965E-07 1.1144E-07 7.2302E-08 1.0567E-07 1.5565E-07 1.3002E-07 3.206SE-07 5.9776E-07 2.0443E-06 7.2853E-07 5.0125E-07 4.3023E-07 3.6934E-07 3.7298E-07 3.6385E-07 2.7009E-07 1.4661E-07 5.8361E-08 3.6449E-08 5.1650E-08 7.9421E-08 8.0948E-08 2.0113E-07 3.8414E-07 1.3260E-06 4.7102E-07 3.2269E-07 2.7652E-07 2.4103E-07 2.4787E-07 2.3426E-07 1.7531E-07 9.7203E-08 3.6942E-08 2.2537E-08 3.1683E-08 4.8400E-08 2.7996E-08 6.9806E-08 1.4165E-07 4.8995E-07 1.7744E-07 1.2116E-07 1.0477E-07 9.6748E-08 1.0714E-07 9.1058E-08 7.1621E-08 4.2816E-08 1.3997E-08 7.7514E-09 1.0607E-08 1.5650E-08 6.8348E-09 1.7144E-08 3.8144E-08 1.2688E-07 4.9543E-08 2.9865E-08 2.3252E-08 2.2697E-08 2.6434E-08 2.1211E-08 1.6449E-08 1.1937E-08 3.3322E-09 1.8804E-09 2.4731E-09 3.4598E-09 2.8992E-09 7.3753E-09 1.6698E-08 5.3675E-08 2.1750E-08 1.1395E-08 7.4589E-09
- 7. 1034E-09 7.9583E-09 7.0722E-09 4.8469E-09 3.9166E-09 1.1726E-09 7.7980E-10 1.0199E-09 1.4369E-09 1.6383E-09 4.1972E-09 9.5818E-09 3.1024E-08 1.2492E-08 6.5075E-09 4.2424E-09 4.0580E-09 4.5475E-09 4.0325E-09 2.7542E-09 1.7999E-09 6.5157E-10 4.3363E-10 5.6525E-10 8.0052E-10 1.0535E-09 2.7240E-09 6.2992E-09 2.0592E-08 8.1831E-09 4.2398E-09 2.7535E-09 2.6408E-09 2.9550E-09 2.6199E-09 1.7792E-09
- 8. 9604E-10 4.1154E-10 2.7403E-10 3.5598E-10 5.0724E-10 3-22
(
TABLE 3-7 2002 SSES ANNUAL RELATIVE DEPOSITION (D/Q meters-2)
(
DATES OF LAST X/Q ACCUMULATION ARE FROM 2 1 1 1 0 X/O ACCUMULATION FOR DEPOSITION 1/M2 TO 2123124 0 FOR RELEASE POINT 1
0.5-1
- "DIRECTION 2.4958E-08
- DIRECTION 3.3829E-08
- DIRECTION 3.6288E-08
- 'DIRECTION 6.75S81E-08
- DIRECTION 3.0620E-08
- DIRECTION 2.3545E-08
- DIRECTION 2.6544E-08
- DIRECTION 2.7410E-08
- DIRECTION 2.8706E-08
- DIRECTION 4.2176E-08
- DIRECTION 5.2457E-08
- DIRECTION 3.2819E-08
- DIRECTION 1.3703E-08
- DIRECTION 9.9121E-09
- DIRECTION 1.5476E-08
- DIRECTION 2.0937E-08 MILES a _tfn 1-2 2-1 3-A 4_ c I A_<
orarz I An
&t
.LUzU
£UJU3
.3U"Av qU-bU FROM N 3.67752-09 FROM NNE 5.2416E-09 FROM NE 5.4732E-09 FROM ENE 1.0494E-08 FROM E
4.4728E-09 FROM ESE 3.5592E-09 FROM SE 4.0334E-09 FROM SSE 4.0914E-09 FROM S
4.6023E-09 FROM SSW 6.4510E-09 FROM SW 8.3273E-09 FROM WSW 5.0589E-09 FROM W 2.0568E-09 FROM WNW 1.4302E-09 FROM NW 2.2656E-09 FROM NNW 3.1094E-09 1.5082E-09 2.2734E-09 2.3402E-09 4.6732E-09 1.8223E-09 1.5175E-09 1.7616E-09 1.7429E-09 2.1614E-09 2.8935E-09 3.9178E-09 2.3627E-09 8.8997E-10 5.7629E-10 9.0774E-10 1.3137E-09 7.1487E-10 1.0813E-09 1.1327E-09 2.2863E-09 8.7011E-10 7.3262E-10 8.6991E-10 8.6061E-10 1.1108E-09 1.4647E-09 2.0272E-09 1.2649E-09 4.4410E-10 2.7542E-10 4.2227E-10 6.3510E-10 4.2248E-10 6.3653E-10 6.7199E-10 1.3507E-09 5.1915E-10 4.3770E-10 S.2218E-10 5.2451E-10 6.9228E-10 8.8656E-10 1.2526E-09 8.0423E-10 2.7066E-10 1.6362E-10 2.4966E-10 3.7201E-10 1.3389E-10 1.9833E-10 2.1647E-10 4.2745E-10 1.7121E-10 1.4514E-10 1.7644E-10 1.8778E-10 2.6794E-10 3.0933E-10 4.7089E-10 3.3167E-10 9.6901E-11 5.3006E-11 7.9260E-11 1.1340E-10 3.2031E-11 4.6234E-11 5.3040E-11 9.7405E-11 4.3349E-11 3.2976E-11 3.6720E-11 4.1194E-11 6.2536E-11 6.8717E-11 1.0638E-10 9.3340E-11 2.3644E-11 1.3093E-11 1.9011E-11 2.5521E-11 1.1793E-11 1.7023E-11
- 1. 9528E-11 3.4154E-11 1.5960E-11 1.0649E-11 1.0050E-11 1.0949E-11 1.6042E-11
- 1. 9610E-11 2.7100E-11 2.6969E-11 7.4082E-12 4.8208E-12 6.9997E-12 9.3964E-12 6.2945E-12 9.0855E-12 1.0423E-11 1.8229E-11 8.5186E-12 5.6839E-12 5.3641E-12 5.8438E-12 8.5622E-12 1.0467E-11 1.4464E-11 1.1807E-11 3.9540E-12 2.5730E-12 3.7360E-12 5.0152E-12 3.9544E-12 5.7079E-12 6.5481E-12 1.1452E-11 5.3517E-12 3.5708E-12 3.3699E-12 3.6713E-12 5.3791E-12 6.57552-12 9.0870E-12 5.7918E-12 2.4841E-12 1.6165E-12 2.3471E-12 3.1507E-12 3-23
TABLE 3-8 2002 ATMOSPHERIC DISPERSION ESTIMATES FOR RETDAS INPUT AT SELECTED LOCATIONS AFECE
()
X/Q XIQ SECTOR LOCATION MILES X/Q DE DEC+DE)(3)
DEPOSrrION(4 12/WSW Maximum (X/Q) Site Boundary 1.22 1.244E-05 1.234E-05 1.068E-05 1.482E-08 9/S Closest (X/Q) Site Boundary 0.38 5.573E-06 5.568E-06 5.189E-06 3.779E-08 121WSW Maximum (X/Q) Residence 1.1 1.458E-05 1.446E-05 1.260E-05 1.761E-08 31NE Maximum (D/Q) Residence 0.9 2.742E-06 2.733E-06 2.406E-06 1.988E-08 121WSW Maximum (DIQ) Garden 1.1 1.458E-05 1.446E-05 1.260E-05 1.761E-08 10/SSW Maximum (DIQ) Dairy 3.0 5.435E-07 5.352E-07 4.289E-07 1.504E-09 2/NNE Maximum (D/Q) Meat Producer 2 3 9.612E-07 9.519E-07 7.830E-07 3.388E-09 3/NE Riverlands / EIC 0.7 3.959E-06 3.949E-06 3.535E-06 3.030E-08 121WSW I Tower's Club 0.5 3.959E-05 3.947E-05 3.616E-05 5.339E-08 5/E I East Gate 05 1.785E-06 1.782E-06 1.631E-06 1.479E-08 NEAREST RESIDENCE WITHIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES X/Qt )
D (2)
DEC+DEP(3)
DEPOSITION")
NUMBER SECTOR
______DEC(
DEC+DEPt3 EOIIN 1
N H. Burd 1.3 2.028E-06 2.014E-06 1.734E-06 5.789E-09 2
NNE E. Ashbndge III 1.0 3.211E-06 3.196E-06 2.797E-06 1.290E-08 3
NE W. Tuggle 0.9 2.742E-06 2.733E-06 2.406E-06 1.988E-08 4
ENE D. Barberi 2.1 4.147E-07 4.126E-07 3.409E-07 3.051 E-09 5
E L Kozlowski 1.4 3.512E-07 3.497E-07 2.990E-07 2.298E-09 6
ESE R. Panetta 05 1.274E-06 1.272E-06 1.164E-06 1.068E-08 7
SE J. Futoma 05 1.636E-06 1.634E-06 1.494E-06 1.461E-08 8
SSE J. Naunczek 06 1.919E-06 1.916E-06 1.732E-06 1.602E-08 9
5 S. Slusser 1.0 1.429E-06 1.423E-06 1.244E-06 7.632E-09 10 SSW S. Molnar 0 9 3.679E-06 3.660E-06 3.227E-06 1.281E-08 11 SW F. Michael 1.5 2.993E-06 2.967E-06 2 533E-06 5.504E-09 12 WSW W. Kisner 1.1 1.458E-05 1.446E-05 1.260E-05 1.761E-08 13 W
E. Seely/F. Hummel 1.2 5.340E-06 5.286E-06 4.586E-06 6.700E-09 14 WNW R. Orlando 0.8 6 914E-06 6.864E-06 6.109E-06 1.124E-08 15 NW L. Hidlay 0.8 5.834E-06 5.798E-06 5.156E-06 1.277E-08 16 NNW W. Metzler 0.6 6.380E-06 6.355E-06 5.754E-06 1.743E-08 NEAREST GARDEN WIT1HN A 5-MILE RADIUS OF SSES BY SECTOR NUMBER SECTOR NAME MILES xi/
DEC(2)
DEC+DEPX/ )
DEPOSITION")
I N
J. Wojcik 3.2 5.464E-07 5.375E-07 4.276E-07 1.302E-09 2
NNE R. Chapin 2.3 9.612E-07 9.519E-07 7.830E-07 3.388E-09 3
NE Yokum 2.7 5.468E-07 5.419E-07 4.380E-07 3.442E-09 4
ENE G. Dennis 2.4 3.456E-07 3 432E-07 2.807E-07 2.544E-09 5
E L.KozlowskilW.Witts 1.4 3.512E-07 3.497E-07 2.990E-07 2.298E-09 6
ESE L. Travelpiece 2.5 8.902E-08 8.836E-08 7.203E-08 5.741E-10 7
SE F. Scholl 0.6 1.254E-06 1.252E-06 1.132E-06 1.074E-08 8
SSE D. Dawson 1.5 4.422E-07 4.404E-07 3.747E-07 3 022E-09 9
S M. Cope 1.1 1.230E-06 1.225E-06 1.064E-06 6 419E-09 10 SSW S. Bodnar 1.2 2.370E-06 2.355E-06 2.038E-06 7.71 1E-09 I
SW H. Schultz 1.9 2.102E-06 2.077E-06 1.740E-06 3.755E-09 12 WSW W. Kisner 1.1 1.458E-05 1.446E-05 1.260E-05 1.761E-08 13 W
E. Seely/F. Hummel 1.2 5.340E-06 5.286E-06 4.586E-06 6.700E-09 14 WNW P. Moskaluk, Jr.
1.3 3.164E-06 3.130E-06 2.702E-06 4.634E-09 15 NW D. Goff 1.8 1.633E-06 1.613E-06 1.359E-06 3.046E-09 16 NNW P. Culver 4.0 3.787E-07 3.696E-07 2.874E-07 6.457E-10 3-24
TABLE 3-8 (continued)
NEAREST ANIMAL RAISED FOR MEAT CONSUMPTION WITHIN A 5-MILE RADIUS OF SSES BY SECTOR NUMBER SECTOR NAME MILES XIQ DEC(
DEC+DEP/
l DEPOSITION" 4 '
2 NNE R. Chapin 2.3 9.612E-07 9.519E-07 7.830E-07 3.388E-09 4
ENE G Dennis 2.4 3 453E-07 3 428E-07 2 804E-07 2.542E-09 5
E K. Kozlowskil 1.4 3.512E-07 3 498E-07 2.990E-07 2.299E-09 W. W itts 10 SSW R. & C. Ryman 3.0 5.435E-07 5.352E-07 4.289E-07 1.504E-09 C. K. Drasher 3.5 3.834E-07 3.766E-07 2.966E-07 1.000E-09 15 NW D. Goff 1.8 1.633E-06 1.613E-06 1.359E-06 3.046E-09 ALL DAIRY LOCATIONS NEAR SSES SECTOR AFFECTED NA E MIE XQ)
(2)X/
NUMBER SECTOR NAME MILES XIQ DEC(2)
DEC+DEP(3)
DEPOSITION(4) 5 E
W. Bloss 4.5 4 843E-08 4 781E-08 3 632E-08 2 661E-10 6
ESE D. Moyer 2.7 7.680E-08 7.618E-08 6.154E-08 4 845E-10 F. Rinehimer 4.2 3.102E-08 3 063E-08 2.347E-08 1.723E-10 10 SSW R. & C. Ryman 3.0 5.435E-07 5.352E-07 4.289E-07 1.504E-09 R. Ryman 3.1 5.059E-07 4 979E-07 3.975E-07 1.383E-09 C. K. Drasher 3.5 3.834E-07 3.766E-07 2.966E-07 1.000E-09 K. Davis 14.0 3.175E-08 2.947E-08 1.969E-08 5.337E-1I W
J. & N. Dent 5.0 4.921E-07 4.729E-07 3.609E-07 3.869E-10 16 NNW H. Shoemaker 4.2 3.550E-07 3.460E-07 2.676E-07 5.933E-10 1
X/Q RELATIVE CONCENTRATION (SECIM 3) 2 X/Q DEC DECAYED AND UNDEPLETED, IIALF-LIFE 2.26 DAYS (SEC/M3 )
3 X/Q DEC+DEP DECAYED AND DEPLETED, HALF-LIFE 8 DAYS (SECIM 3) 4 DEPOSITION RELATIVE DEPOSITION RATE (1/M 2 )
3-25
(:
(I
(
SSES 2002 ANNUAL WIND ROSE 9291910109 0212312409 SPEED SENSOR HEIGHT = 33.0 10M LEVEL - PRIMARY TOWER k) 0a WIND ROSE CWINDS FROM)
N
.t C.T ANIND SPEED
+WIND SPEED XWIND SPEED
- RIND SPEED LESS THAN 3.5 MPH LESS THAN 7.5 MPH LESS THAN 12. 5 MPH GREATER THAN 12.5 MPH 9.1 PERCENT CALMS (NOT INCLUDED IN PLOT)
This wind rose displays the frequency of hourly average wind direction from a given sector.
In 2002, the predominant wind direction occurred 14.5% of the time from the ENE sector.
The average wind speed was 4.9 mph. The peak sector wind speed was 8.5 mph from the WSW.
(
C C
SSES 2002 ANNUAL WIND ROSE 92e10101gi 0212312408 SPEED SENSOR HEIGHT = 197.0 60M LEVEL - PRIMARY TOWER
£6 v
-i MIND ROSE (WINDS FROM)
N At
,Id 0-4 0
(.11, A
,WIND SPEED
+WIND SPEED XWIND SPEED oWIND SPEED LESS THAN 3.5 MPH LESS THAN 7.5 MPH LESS THAN 12.5 MPH GREATER THAN 12.5 MPH 0.0 PERCENT CALMS CNOT INCLUDED IN PLOT)
This wind rose displays the frequency of hourly average wind direction from a given sector.
In 2002, the predominant wind direction occurred 13.5% of the time from the NNE sector.
The average wind speed was 7.8 mph. The peak sector wind speed was 12.0 mph from the W.
FIGURE 3-3 SSES PASQUIL STABILITY CLASS PREVALENCES DATA Period: 2002 SSES Joint Frequency Distributions at 10 Meters Wind Speed and Direction IOM vs. Delta Temperature 60-IOM (Based on 8,675 Valid Hours)
G 8.0%
A 3.2%
)
I'7A-M B
3.70/
F 13.3%
E 26.4%
C 4.9%
D 40.5%
3-28
SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 4-1
Radiological Impact on Man Sampling and analysis of airborne and waterborne effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (LLD) outlined in the SSES Technical Requirements.
Radioactive material was detected in some of the airborne and waterborne effluent samples analyzed. Dose calculations using measured effluent activity levels, meteorological data from the current reporting period and average river flow dilution factors resulted in estimated doses to individuals at levels below 10 CFR 20 and 10 CFR 50, Appendix I limits. Direct radiation resulting from plant operation, as measured by environmental thermoluminescent dosimeters located around the plant contributed a maximum of 2.99E-2 mrem (measured at TLD Location 9S2) at the Protected Area Boundary south of the plant. The maximum organ/total body dose including thyroid from all airborne effluent is 1.27E0 mrem (CHILD, LUNG Table 4-4). The maximum organ/total body dose from liquid effluent is 6.06E-3 mrem (ADULT, GI-LLI: two times the unit dose shown Table 4-2).
Conservatively adding the maximum total body/organ dose from liquid and gaseous effluent (even though different age groups) and the maximum total body dose determined from direct radiation bounds the dose that any member of the public receives from operation of SSES. The result (1.31 E 00 mrem) is 5.2% of the 40CFR1 90 limit of 25 mrem to total body/organ (except thyroid) and 1.7% of the 40CFR1 90 limit of 75 mrem to the thyroid.
Doses to a maximally exposed member of the public from waterborne effluents are calculated for fish ingestion and shoreline exposure at the plant outfall, and drinking water ingestion at Danville, PA. Site specific parameters used in the calculations for the Danville receiver, specific for actual average blowdown and river level for the entire year are shown in Table 4-1.
TABLE 4-1 SITE-SPECIFIC PARAMETERS USED FOR RETDAS CALCULATIONS (DANVILLE RECEIVER)
FOR 2002 PARAMETER ENTIRE YEAR Cooling Tower Blowdown (CFS) 17.5 Average Net River Level (ft.)
6.8 Dilution Factor at Danville(')
413.2 Transit time to Danville (hr.)(')
24.7
(')From ODCM-QA-005, Att. D 4-2
Summaries of maximum individual doses resulting from airborne and waterborne radioactive effluent releases are given in Table 4-2. Meteorological data from Section 3 were used to calculate the dose from airborne effluents.
Technical Specifications 5.5.4 require assessment of radiation doses from radioactive airborne and waterborne effluent to members of the public within the site boundary. There are no significant exposure pathways from waterborne effluents in these areas. Onsite doses are assessed relative to offsite dose values and are adjusted for appropriate dispersion and occupancy factors. Summaries of the calculated maximum doses within the site boundary and selected locations resulting from airborne effluents are presented in Tables 4-3 through 4-4.
SSES Technical Specification 5.5.4 requires that the Annual Radioactive Effluent and Waste Disposal Report include an assessment of the radiation dose from radioactive effluents to members of the public within the site boundary. Within the SSES Site Boundary there are several areas frequented by members of the public.
Doses from airborne effluent are calculated for members of the public for the following locations: SSES Riverlands Energy Information Center, the Guard House at access Gate No. 10, the Towers Club, the Kisner Farm and the site boundary with the maximum X/Q value. The above referenced locations are shown on Figure 4-1.
In the area comprising the Riverlands recreation area, which surrounds the Energy Information Center, three pathways of radiation exposure can be identified: plume, ground, and inhalation. There are no significant exposure pathways from waterborne effluents in this area. There are approximately 100,000 visitors to the Riverlands/Information Center complex each year. For dose calculations, it is assumed the visitor stays in the area for one hour.
Use of the RETDAS code yields calculated doses for the Riverlands area for the report period. These doses are the total doses at the location from gaseous effluents during the report period.
4-3
TABLE 4-2
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES TO MEMBERS OF THE PUBLIC DATA PERIOD: 1/1/02 TO 12/31/02 ESTIMATED MAXIMUM AGE APPLICABLE DOSE PERCENT LIMIT EFFLUENT GROUP ORGAN (MREM)
LOCATION OF LIMIT (MREM)~2 DIST AFFECTED (MILES)
SECTOR Liquid"l)
Child Total Body 1.05E-3 (3) 0.04 3
Liquid('"
Adult GI-LLI 3.03E-3 (3) 0.03 10 Noble Gas 4)
N/A Air Dose 1.13E-1 0.5 WSW 1.13 10 (Gamma-MRAD)
Noble Gas(4)
N/A Air Dose 3.99E-2 0.5 WSW 0.2 20 (Beta-MRAD)
Airborne Child Lung 1.27E 0 0.5 WSW 8.5 15
(1)Estimated dose is based on a site total activity release equally divided between Unit 1 and Unit 2.
(2)10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year for airborne effluent and mrem per year for waterborne effluent from each unit.
(3)Doses from liquid effluent are estimated from fish ingestion and shoreline exposure at the site outfall and from the drinking water pathway at Danville, PA.
(4)Estimated dose is based on the site total activity release.
4-4
TABLE 4-3 CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/INFORMATION CENTER COMPLEX DATA PERIOD: 1/1102 TO 12/31/02 COLLECTIVE APPLICABLE, DOSE RATE"1 '
DOSE(2)
- EFFLUENT AGE GROUP ORGAN (MREM/HR)
(PERSON-REM)
Noble Gas N/A Total Body 1.29E-06 1.29E-04 Noble Gas N/A Skin 4.55E-07 4.55E-05 Iodine, Tritium and Child Total Body 1.87E-05 1.87E-03 Particulates I
I I
('Estimated dose and dose rate is based on annual site total activity release.
(2)Collective dose is based on occupancy of 100,000 person-hours.
4-5
TABLE 4-4
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES FROM AIRBORNE EFFLUENT MAXIMUM MAXIMUM MAXIMUM TOTAL BODY ORGAN THYROID DOSE DOSE DOSE LOCATION PATHWAY (MREM)
(MREM)
(MREM)
- 1.
Maximum site boundary X/O Total (All) 3.96E-01 (CHILD) 3.96E-01 (CHILD, LUNG) 3.90E-01 (CHILD)
- 2.
Maximum X/Q Residence &
Maximum D/Q Garden Total (All) 4.65E-01 (CHILD) 4.64E-01 (CHILD, LUNG) 4.58E-01 (CHILD)
- 3.
Maximum DIQ Dairy Total (All) 1.86E-02 (CHILD) 1.82E-02 (CHILD, GI-LLI) 1.80E-02 (CHILD)
Total (All) 3.39E-02 (CHILD) 3.32E-02 (CHILD, GI-LLI) 3.25E-02 (CHILD)
- 5.
Towerss Club Total (All) 1.27E 00 (CHILD) 1.27E 00 (CHILD, LUNG) 1.25E 00 (CHILD)
- 6.
Riverand/EIO Total (All) 1.64E-01 (CHILD) 1.57E-01 (CHILD, GI-LLI) 1.51E-01 (CHILD)
- 7.
Gate No. 10 Guard House Total (All) 7.55E-02 (CHILD) 7.22E-02 (CHILD, GI-LLI) 6.95E-02 (CHILD)
Note: The doses shown above are based on 100% occupancy at the indicated locations.
Note: The doses shown above are based on a composite of all applicable pathways resulting in a total dose to the maximally exposed individual.
4-6
FIGU
FIGUI
.~
Z DMRU MODAL f A
NW ENE SE SW SUSOUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN BOUNDARY DISTANCES IDISTANCES IN FEET)
PENNSYLVANIA POWER & LIGHT
zI
.0, q
- LEGOBO wPP&L roperlr soundwy e/
So~
WVoeel 122.S-dogreW Rands
) Lziceti~m tsrmaionie doe. al.ciasoce scale In Feet 0
50W 000 2000 4-7
SECTION 5 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM),
TECHNICAL REQUIREMENTS MANUAL (TRM)
AND THE SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM 5-1
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The SSES ODCM consists of nine (9) individual procedures. Revision 1 to ODCM-QA-001, "ODCM Introduction" became effective on April 14, 2002. This revision incorporated the following changes:
- 1.
Updated position titles and responsibilities.
- 2.
Updated the reference section.
- 3.
Removed "Gray Shading" from ITS implementation.
- 4.
Additional changes of a minor editorial nature were made to Sections 2.1 and 2.4.
A change was made to Revision 1 of ODCM-QA-002, UODCM Review and Revision Control" on June 6, 2002. This change provided clarification that 10CFR50.59 and 10CFR72.48 screens are not needed for ODCM changes. This change is in conjunction with guidance provided in SSES Technical Specifications section 5.5.1.
Additionally, position titles and responsibilities were updated as part of the change to ODCM-QA-002.
The following ODCM procedures (with corresponding revision numbers) were revised and effective on September 20, 2002; ODCM-QA-003 Rev. 1, ODCM-QA-004 Rev. 2, ODCM-QA-005 Rev. 2, ODCM-QA-006 Rev. 1, ODCM-QA-007 Rev. 1. Outlined below is a summary of the changes to the above referenced ODCM revisions:
- 1.
Revised liquid effluent dose calculation methodology to reflect the actual methodology of Regulatory Guide 1.109. Provided a consolidated version of the referenced methodology for liquid effluent dose calculation, which reflects the methodology, utilized by a newly implemented offsite dose computer program (RETDAS).
- 2.
Revised gaseous effluent noble gas dose calculation methodology to reflect the actual methodology of NUREG-0133. Revised methodology is more conservative and reflects the methodology utilized in the RETDAS program.
- 3.
Gaseous effluent dose factors revised. Minor differences between the current gaseous effluent dose factors and the RETDAS gaseous effluent dose factors.
Minor differences due to use of default values in Reg. Guide 1.109 in lieu of site specific values currently utilized.
5-2
- 4.
Revised the liquid effluent dose factors. The river dilution factor and transit time are values in current ODCM dose factor calculation. These parameters are part of the RETDAS liquid effluent dose calculation, not part of the derivation of the dose factor value.
- 5.
Added system flow-paths for liquid and gaseous effluents per NRC Effluent Inspection 2002-02.
- 6.
The RETDAS program utilizes a larger isotopic library than that which is listed in the current SSES ODCM. The additional isotopes and corresponding dose factor values have been incorporated into the ODCM revision.
- 7.
Incorporated Insignificant Effluent Pathway dose calculation methodology.
- 8.
Revised liquid effluent dose factor for P-32 (Phosphorous 32) and deleted reference to analyze for P-32 in liquid effluent composite samples. Technical justification (which includes NRC Technical Paper) for P-32 changes added to ODCM as supporting reference.
- 9.
Minor typographical errors, administrative title and responsibility updates and additional references incorporated.
Revision 4 to ODCM-QA-008, "Radiological Environmental Monitoring Program",
became effective on June 11, 2002. This revision incorporated the following changes:
- 1.
Incorporated explanation of regulatory basis for REMP equations I through 4.
- 2.
Deleted REMP sampling location "12G1" from Attachment B. This location has never been a required monitoring location.
- 3.
Updated the description of monitoring location "2B3" from "Durabond Corporation" To "Legett & Platt".
- 4.
Replaced milk sampling location 10D3 with location 12B2 in Attachments B and C. This change is in response to the result of an annual surveillance that evaluated the dose potentials of dairy farms in the vicinity of the SSES for any airborne activity that might be released from the SSES. This surveillance determined that location 12B2 has a significantly greater dose potential than 1 OD3.
- 5.
Additional references incorporated.
5-3
Revision 1 to ODCM-QA-009 became effective on May 24, 2002. This revision included the following changes:
- 1.
Deleted old Technical Specification statements and references and removed shading from Improved Technical Specification statements.
- 2.
Deleted Approval/date box, which is not required by Improved Technical Specifications.
- 3.
Sections 2.1.2 and 2.1.3 - Revised to reflect deletion of old Attachment A.
- 4.
Section 2.1.3 - Moved definition of 80-10 systems to Section 5.
- 5.
Section 3 - Added references to NDAP-QA-1 180, Condition Report #95876, Unit 1 and Unit 2 Technical Requirements Manual, NRC Generic Letter 91-18, and Condition Report 95876. Deleted reference to Safety Evaluation NL-90-029.
- 6.
Section 5.1 - Clarified subject definition based on TRM.
- 7.
Section 5.4 - Clarified definition of Significant Effluent Pathway.
- 8.
Section 5.5 - Added definition of 80-10 Systems.
- 9.
Section 6.0 - Changed reference to Nuclear Department to PPL Susquehanna.
- 10.
Deleted Attachment A-Systems Classified as Not an Effluent Pathway; there is no requirement to include this attachment.
- 11.
Attachment B - Systems Classified as Insignificant Effluent Pathway revised to Attachment A and updated.
- 12.
Attachments C and D revised to Attachments B and C. Systems updated and references added to Attachments C and D.
CHANGES TO THE TECHNICAL REQUIREMENTS MANUAL Section 3.11 of the SSES Technical Requirements Manual (TRM) by reference is part of the ODCM. The following limits and requirements are contained in Section 3.11:
liquid and gaseous effluent dose limits, liquid and gaseous effluent treatment system operability criteria (based on effluent dose), liquid and gaseous effluent radiation monitor operability criteria and the conduct of the Radiological Environmental Monitoring Program.
5-4
In 2002, TRM Sections 3.11.2.4 and 3.11.2.5 were revised and became effective on April 2, 2002. These revisions included the following changes:
- 1.
Editorial and administrative corrections to make the format consistent with the Writer's Guide for Standard Technical Specifications.
- 2.
The Bases to the referenced Sections has been expanded to be more reflective of the specific requirements of the TRO, Conditions, Required Actions, TRS's, and Notes, and to make format, wording, and punctuation consistent with the Writer's Guide.
- 3.
Throughout the Bases, the term "shall," is replaced with the term, "should" (or another equivalent term) because "shall" implies a requirement, and the intent of the Bases is to provide clarification.
- 4.
TRS 3.11.2.4 Bases incorrect reference to "monitoring instrumentation" is changed to "GASEOUS RADWASTE TREATMENT SYSTEM".
- 5.
TRS 3.11.2.5 Bases incorrect reference to "monitoring instrumentation" is changed to "VENTILATION EXHAUST TREATMENT SYSTEM".
5-5
PROCESS CONTROL PROGRAM CHANGES The following changes were made to the Process Controi Program and implementing procedures during 2002. None of the changes reduce the overall conformance of the solidified waste product to existing criteria for solid wastes. All changes were reviewed and approved by PORC (if necessary). The following procedures were changed:
- 1.
NDAP-QA-0646, Solid Radioactive Waste Process Control Program (Effective 04/19/2002, PORC Meeting No. 02-04-11)
- 2.
WM-PS-100, Shipment of Radioactive Waste (Effective 08/13/2002)
- 3.
WM-PS-160, Radwaste Curie Calculations (Effective 02/19/2002, PORC Meeting No. 02-02-14)
- 4.
WM-PS-21 0, Packaging and Loading of DAW and Radioactive Material (Effective 02/19/2002, PORC Meeting No. 02-03-14)
- 5.
WM-PS-345, Use of the Chem Nuclear or Vectra 14-190H (NUPAC 14/190)(USA/9159/A) Shipping Package (Effective 03/08/2002, PORC Meeting No. 02-03-07)
- 6.
WM-RP-009, Combustible Gas Detection in Processing Liners and High Integrity Containers (Effective 06/13/2002)
- 7.
WM-RP-104, Transfer and Dewatering Ion Exchange Resin for Resin Express Processing (Effective 05/13/2002)
- 8.
WM-RP-107, Transfer and Drying Powered Resin (Effective 02/19/2002, PORC Meeting No. 02-02-14)
NDAP-QA-0646 continues to fully implement the requirements and intent of the following:
- 1.
Sections 11.4 and 13.5 of the FSAR
- 2.
Section 3.7.4 of the Technical Requirements Manual
- 3.
10 CFR 20,10 CFR 61,10 CFR 71, 49 CFR 100-177, and 40 CFR 261 Compliance with all applicable regulatory requirements listed above continues to be met as the result of these changes to the program. These changes to the Process Control Program will not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.
5-6
PROCEDURE REVISION
SUMMARY
NDAP-QA-0646, Revision 6
- 1.
Add reference and clarify PCP change evaluation requirements to be in accordance with changes to NDAP-QA-0726, 10 CFR 50.59 and 10 CFR 72.48 Evaluations.
- 2.
Implement Licensing Commitment Change # 3376 to clarify that changes to PCP implementing procedures do not require PORC review consistent with the guidance in NDAP-QA-002, Nuclear Department Procedure Program, Attachment K.
- 3.
Add reference to ODCM-QA-001, ODCM introduction, change requirements to Section 6.15 and Section 6.19 to clarify requirements for completing the Annual Solid Radioactive Waste Report and changes to the PCP. This change implements corrective actions for Audit #2001-013 Finding #376192.
- 4.
These changes to the PCP do not reduce the overall conformance of the solidified waste product to existing criteria for solid radwaste. The changes are administrative in nature and are made to clarify the relationship of the PCP with other, approved procedures and to clarify requirements for reporting changes in the Annual Radwaste Report.
- 5.
Change number 1 completes implementation of the revised 10 CFR 50.59/ 10 CFR 72.48 evaluation process with regards to changes to the PCP. This change ensures the proper change mechanisms are referenced in the PCP with regard to evaluations of process or operational changes that may impact the final waste product.
- 6.
Change number 2 implements a clarification on the review requirements of PCP implementing procedures. The intent of Improved Technical Specifications was to move the Process Control Program under the administrative control of the OQA program and define the PCP as NDAP-QA-0646. This would eliminate unnecessary and burdensome Technical Specification changes when radwaste processing technology or procedures changed. The OQA program contains sufficient controls to ensure changes to the PCP and implementing procedures are adequately and appropriately reviewed. However, during the submittal of the ITS, a response to NRC questions inadvertently committed PORC to review all implementing procedures of the PCP and not only NDAP-QA-0646. This commitment was discovered during a previous submittal of this change to PORC. Regulatory Commitment Change # 3376 was approved on 3/6/02 to rescind this commitment. This change reaffirms the original intention of ITS to control NDAP-QA-0646 as the PCP which requires PORC review. Implementing procedures do not implement any new requirements and so do not require PORC review.
5-7
- 7.
Change number 3 corrects procedure deficiencies noted in Radwaste Audit 2001-013 Finding # 376192 with regards to instructions for submittal of information on the Annual Solid Radwaste Report. NDAP-QA-0646 did not contain adequate guidance to ensure the requirements of FSAR Section 13.4.4.1 were met. The change corrects this condition by inserting appropriate references to ODCM-QA-001, which is required by Technical Specification 5.6.3 to contain the guidance for this report. ODCM-QA-001 Revision 1 contains all of the requirements to ensure a proper report is made.
5-8
PROCEDURE REVISION
SUMMARY
WM-PS-100, Revision 7
- 1.
Incorporated recommendations from Audit #2001-013 (Recommendation #'s 376218 and 376219).
- 2.
Added use of RADMAN computer program to determine hydrogen generation calculation in step 6.4.7.e.
- 3.
Updated vendor's name on FORM WM-PS-100-14. Included various administrative changes.
5-9
PROCEDURE REVISION
SUMMARY
WM-PS-160, Revision 3
- 1.
Implement new scaling factors for Dry Active Waste, Condensate/Radwaste Bead Resin, Chemical Waste Processing Bead Resin/Charcoal, URC and LRW Filter Media.
5-10
PROCEDURE REVISION
SUMMARY
WM-PS-201, Revision 5
- 1.
Clarified requirements for weighing bags containing water or asbestos.
- 2.
Added new material to be used as an absorbent (AquaSorbe)
- 3.
Added item to have bags of asbestos placed in an inner metal drum due to recent industry experience.
- 4.
Revised Form WM-PS-201-1 for clarification.
5-11
PROCEDURE REVISION
SUMMARY
WM-PS-345, Revision 2
- 1.
Deleted use of cask as an NRC Type A package (NRC no longer regulates Type A packages). Procedure changed to allow cask to be used as a Type A package, Industrial Package I, Industrial Package II, or a Strong Tight Package.
- 2.
Updated vendor name from Vectra to ATG. Various administrative changes.
- 3.
Updated primary and secondary lid gasket requirements in accordance with vendor procedures.
- 4.
Changed drain port torquing requirement in accordance with vendor procedure.
- 5.
Changed cask limits to be in compliance with vendor changes.
- 6.
Updated Form WM-PS-345-1.
5-12
PROCEDURE REVISION
SUMMARY
WM-RP-009, Revision 3
- 1.
Change equipment description to allow the use of equivalent explosive gas detection devices. This is a corrective action from AR 407300407300
5-13
PROCEDURE REVISION
SUMMARY
WM-RP-104
- 1.
Clarify criteria for loss-of-suction when gross-dewatering. Original criteria were too proscriptive and did not apply to the intended purpose of this procedure. The change allows greater flexibility for determining when loss-of-suction has occurred without sacrificing any margin of safety related to meeting transportation requirements. See CRA 380089 (CR 379659).
- 2.
Clarify when confirm and verify steps must be performed and provide for the ability to document waivers.
- 3.
Add reference for CR 188042 and footnote steps required by the CR resolution in PCAF 2000-4807.
- 4.
Various administrative changes to clarify language and intentions and remove redundant signature requirements.
5-14
PROCEDURE REVISION
SUMMARY
WM-RP-107, Revision 6
- 1.
Add requirements to connect filihead flush line and flush fillhead after use in response to CR 338100. Flushing the filihead is expected to reduce the possibility of area contamination due to residual waste material on the filihead going airborne when the fillhead is removed.
- 2.
Add reference to CR 338100.
- 3.
Minor administrative corrections to procedure and Form WM-RP-107-1.
5-15
SECTION 6 MISCELLANEOUS TECHNICAL REQUIREMENTS MANUAL (TRM)
FSAR AND 40CFR190 REPORTING 6-1
- 1. TRM Action 3.11.1.4.F.2 requires the reporting of Liquid Radwaste Effluent Monitoring Instrumentation inoperability not corrected in a timely.
None to report for 2002.
- 2. TRM Action 3.11.1.5.C.1 requires the reporting of Radioactive Liquid Process Effluent Monitoring Instrumentation inoperability not corrected in a timely.
None to report for 2002.
- 3. TRM Action 3.11.2.6.K requires an explanation for Radioactive Gaseous Effluent Monitoring Instrumentation required actions and completion times not met.
None to report for 2002.
- 4. TRM Action 3.11.4.1.F.2 requires reporting the cause of the unavailability of milk or fresh leafy vegetables samples and identify the new locations for obtaining replacements.
None to report for 2002.
- 5. TRM Action 3.11.4.2.A requires reporting when land use census identifies a new location which yields a calculated dose or dose commitment greater than the values currently being calculated in Requirement 3.11.2.3 (Gaseous Effluent Dose due to Iodine, Tritium, and Radionuclides in Particulate Form).
None to report for 2002.
- 6. TRM Action 3.11.4.2.B requires reporting when land use census identifies locations that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Requirement 3.11.4.1 (Radiological Environmental Monitoring Program).
None to report for 2002. [Note: Milk sampling at the Berger farm (REMP monitoring location 12B2) began in the spring of 2002. Milk sampling at the Drasher farm (REMP monitoring location 1 OD3) was discontinued in July 2002 and replaced by the Berger farm. During the period of April through June 2002, duplicate milk sampling occurred at the Drasher and Berger farms. The Berger farm is closer to the SSES (1.7 miles) than the Drasher farm (3.5 miles).
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- 7. The 40CFR1 90.10 standard for normal operation for the uranium fuel cycle including annual dose equivalent and total quantities of radioactive material limits were not exceeded by SSES operation. Refer to Page 4-2 for specific values.
- 8. FSAR Section 11.6.11 requires the reporting of airborne radioactivity detected in the Low Level Radwaste Holding Facility. None detected in 2002.
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SECTION 7 CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENTAND WASTE DISPOSAL REPORT 7-1
CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENT AND WASTE DISPOSAL REPORTS Gross Alpha was identified (above the minimum detectable concentration) in the fourth quarter of 2001 at the Unit 1 and Unit 2 Reactor Buildings as well as the Unit 2 Turbine Building vents. Outlined below is the total gross alpha released from the referenced gaseous effluent release points (based on fourth quarter vent flow data):
Release Point uCi's Gross Alpha Released Unit 1 Reactor Vent 2.05E00 Unit 2 Reactor Vent 1.70E00 Unit 2 Turbine Vent 5.05E00 Fe-55 was identified in the fourth quarter composite for liquid effluent releases in 2001.
Based on the volume of liquid effluent released in the fourth quarter of 2001, the resultant additional dose due to the Fe-55 (based on total site release) is 1.06E-06 mrem total body dose and 6.44E-06 mrem organ dose. The above referenced additional dose is negligible based on the maximum organ/total body dose from liquid effluent of 3.16E-03 mrem reported in Section 4 of the 2001 Annual Effluent and Waste Disposal Report.
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SECTION 8 EFFL UENT FROM SYS TEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWA YS 8-1
EFFLUENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS Systems classified as Insignificant Effluent Pathways which had identified radioisotopes due to SSES operations are the following: evaporation from the Unit 1 and Unit 2 Condensate Storage Tanks (CST's), evaporation from the common Refueling Water Storage Tank (RWST) and from the Hydrogen Seal Oil and the Main Turbine and RFPT lubrication oil mist eliminators which vent to the turbine building roofs.
These pathways are not continuously monitored. The CSTs and RWST are sampled quarterly to determine the concentration of radionuclides present in these tanks.
Airborne release to the environment from the tanks is estimated based on conservative estimates of the evaporation rates from each of the tanks using a modified method established within Chapter 7 of EPA AP-42. A conservative carry-over fraction of radionuclides from the water to the evaporated liquid is then assumed. Airborne release to the environment from the demisters conservatively assumes the maximum contamination of the oil by condensate (1000 ppm) as it passes through the turbines followed by immediate removal of 100% of the water by the oil mist eliminators. The annual release of tritium, iodines and particulates with half-lives greater than 8 days was calculated based on these conservative assumptions; the calculated releases are shown in Table 8-1. All nuclides are negligible compared to the airborne release shown in Tables 2-1 and 2-2 except for tritium. The maximum dose to the public from a release of 32.6 Ci of tritium is calculated to be 1.05E-1 mrem (child). This is a fraction of the maximum dose from airborne effluent reported in Section 4.
The CST analyses showed concentrations ranging from 2.84E-8 to 5.92E-08 IICiml of Xe-135 and one sample identified a concentration of 9.45E-09 tiCi/ml of Kr-85m. This range of concentration of dissolved and entrained noble gas in water stored in tanks on site was less than 1% of the Technical Requirement limit of 2E-4 AiCVml allowed in water that may be discharged to the environment.
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TABLE 8-1 ANNUAL RELEASE FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS U1-CST and U2-CST and Main Turbine/RFPT Main Turbine/RFPT Nuclide RWST Lube Oil Systems Lube Oil Systems Total (ci)
(Ci)
(Ci)
(ci)
H-3 5.96E-02 1.52E+01 1.73E+01 3.26E+01 Mn-54 1.49E-08 1.03E-07 7.57E-08 1.94E-07 Cr-Sl 2.98E-10 7.30E-07 1.21E-08 7.43E-07 Co-58 0
5.67E-09 0
5.67E-09 Co-60 2.90E-08 1.95E-07 1.50E-07 3.74E-07 Fe-59 5.44E-11 0
0 5.44E-11 Tc-99m 0
0 5.97E-10 5.97E-10 Cs-137 1.05E-09 4.47E-08 0
4.57E-08 Ce-141 0
2.1 lE-09 0
2.1 lE-09 Xe-135 0
1.67E-06 1.06E-05 1.23E-05 Kr-85m 0
5.86E-07 0
5.86E-07 8-3