ML041280097
| ML041280097 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/31/2003 |
| From: | Hickey F Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML041280097 (109) | |
Text
SusquehIna Steatn
- Electric Station Units "I&2 Radioactive Effluent Release Report rf 2003 Annual i7.,R1,: :
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SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE EFFLUENT RELEASE REPORT REPORT PERIOD: 01/01/03 - 12131/03 Prepared by:
Francis J. Hickey t/
Health Physicist
- Reviewed by:
Raym d E. Doebler Chemistry Support Supervisor - SSES Approved by:
Manager - Plant Chemistry PPL Susquehanna, LLC Susquehanna Steam Electric Station (NUCSA3) 769 Salem Blvd.
Berwick, Pennsylvania 18603
TABLE OF CONTENTS SECTION PAGE
- 1. Introduction, Summary 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 7 Technical Requirements Manual (TRM) and the Solid Radioactive Waste Process Control Program
..4OCFR190 Reporting
.- 7. Corrections to Doses Reported in Previous 7-1 Semiannual or Annual Radioactive Effluent Release Reports
- 8. Effluent from Systems Classified as Insignificant Effluent Pathways 8-3 Appendix A SSES ODCMITRM
LIST OF TABLES PAGE Table 1-1 Technical Requirement Limits 1-10 Table 2-1 Airborne Effluent-Summation of All Releases 2-4 Table 2-2 Airborne Effluent Radionuclides Released 2-5 Table 2-3 Waterbome Effluent - Summation of All Releases 2-8 Table 2-4 Waterborne Effluent Radionuclides Released 2-9 Table 2-5 Estimated Total Errors Associated with 2-12 Effluents Measurements Table 2-6 Solid Waste and Irradiated Fuel Shipments 2-16
- Table 2-7 LRW Filter Media - Class A 2-17 HIC (Dewatered)
Table 2,8 Chem-Decon Resin - Class A HIC (Pyrolysis) 2-18 Table 2-1 Asbestos - Class A 2-19 Strong Tight Container (Compacted)
Ash - Class A 2-20 Strong Tight Container (Incineration)
Table 2-11 Bead Resin/Charcoal - Class A 2-21 HIC (Pyrolysis)
Table 2-12 Condensate Demineralizer/Radwaste Demineralizer 2-22 Class A Steel Liner (Dewatered)
Table 2-13 Condensate Demineralizer/Radwaste Demineralizer 2-23 Class A HIC (Pyrolysis)
LIST OF TABLES (cont.)
PAGE Table 2-114 Contaminated Waste Oil - Class A 2-24 (Fuel Blending for Co-Generation)
Table 2-1 15 Processed DAW - Class A 2-25 Strong right Container (Compacted)
Table 2-116 Irradiated Components - Class B 2-26 HIC Table 2-1 7 Non-Processed DAW - Class B 2-27 HIC (Non-Processed)
Table 2-1 8 RWCU Filter Media - Class B
- 2-28 HIC (Dewatered)
Table 2-2'o Irradiated Components - Class C 2-30 Steel Liner
<.1.
- -Table 2-2 1 Cartridge Filters - Class C 2-31
.HIC (Non-Processed) -
'Table 3-1 SSES Meteorological Data Recovery for 2003 3-3 Table.3-2 SSES Joint Frequency Distribution of Wind Speed and 3-4 Direction 1Om versus Delta Temperature 6G-1 Om for the Period of January 1, 2003 through December 31, 2003 Table 3-3 SSES Joint Frequency Distribution of Wind Speed and 3-12
- Direction 60m versus Delta Temperature 60-1 Om for the Period of January 1, 2003 through December 31, 2003 Table 3-4 2003 SSES Annual Relative Concentrations No Decay, 3-20
- Undepleted X/Q (sec/m 3 )
Table 3-5 2003 SSES Annual Relative Concentrations 2.26-Day 3-21 Decay, Undepleted X/Q (sec/m 3 )
LIST OF TABLES (cont.)
P.AGE Table 3-6 2003 SSES Annual Relative Concentrations 8-Day 3-22 Decay, Depleted X/Q (sectm3 )
Table 3-7 2003 SSES Annual Relative Deposition - D/Q (meters-2) 3-23 Table 3-8 2003 Atmospheric Dispersion Estimates for RETDAS 3-24 Input at Selected Locations Table 4-1 Site-Specific Parameters Used for RETDAS Calculations 4-2 (Danville Receiver): for 2003 Table 4-2 Summary of Maximum Individual Doses to Members 4-4 of the Public 71 Table 4-3 Calculated Collective Doses to Members of the 4-5 Public Within the Riverlands/Information Center Complex Table 4-4 Summary of Maximum Individual Doses from Airborne Effluent 4-6 Table 8-1 Annual Release from Systems Classified as 8-3 insignificant Effluent Pathways
' '-, j
LIST OF FIGURES PAGE Figure 1-1 SSES Airborne Effluent Release Points 1-6 Figure 1-2 SSES Waterbome Effluent Pathway 1-7 Figure 2-1 Susquehanna River Monthly Average Flow Rates 2-10 Figure 2-2 SSES Monthly Liquid Radwaste Discharge Totals 2-11 Figure 3-1 SSES 2003 Annual Wind Rose: 10-Meter Level 3-26 Primary Tower 7 Figure 3-2 SSES 2003 Annual Wind Rose: 60-Meter Level 3-27 Primary Tower Figure 3-3 SSES Pasquil Stability Class Prevalences 3-28 Figure 4-1 Locations for which Airborne Dose Calculations 4-7 are Performed
SECTION 1 INTRODUCTION,
SUMMARY
AND SUPPLEMENTAL INFORMATION 1-1
INTRODUCTION The submittal of the 2003 Radioactive Effluent Release Report is in accordance with Susquehanna Steam Electric Station (SSES) Tech Spec. 5.6.3. The enclosed information is consistent with the objectives outlined in the SSES ODCM and Process Control Program. The 2003 Radioactive Effluent Release 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, Luzeme 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 inJuly 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 for Noble Gases, and a program of periodic sampling and analysis for Particulates, Iodine, Tritium QJ.iand Noble Gases 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. Waterbome effluents from the site are released into .the cooling tower
-lowdown 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 1,2003 to December 31, 2003. 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 waterbome 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 1-2
- release limits specified in the Technical Requirements. Calculations and terms utilized in this report are those outlined in the SSES ODCM.
Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant. Included are regulatory limits (Table 1-1), sampling and analysis methods, characterization of the number and duration of batch and abnormal releases and a brief summary of the applicable years effluents.
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 waterbome effluents over the report period.
Figures 2-1 and 2-2 present the Susquehanna River Monthly Average Flow Rates for 2003 and the SSES Monthly Liquid Radwaste Discharge Totals for 2003 respectively.
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 waterbome effluents and solid wastes during the report period.
Tables 2-7 through 2-21 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 2003 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 cod6 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 memberspof the public from airborne and waterbome effluents and direct radiation.
Table 4-3 presents calculated collective doses to members of the public within the 1-3
- Riverlands/Information Center Complex. Table 4-4 summarizes the calculated doses for residences and other occupied areas within the SSES site boundary and the nearest dairy.
Section 5 of this report documents changes to the Offsite Dose Calculation Manual, Technical Requirements Manual and the Solid Radioactive Waste Process Control Program.
Section 6 presents a listing of cases (ifany) 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 (ifany) with the collection of milk or fresh leafy vegetables per Technical Requirement 3.11.4.1 and changes due to the land use census per Technical Requirement 3.11.4.2.
Section 7 contains corrections (ifany) to doses reported in previous Semiannual or Annual Radioactive Effluent Release Reports.
Section 8 contains information on effluent and offsite dose from the systems classified as insignificant effluent pathways.
1-4
SUMMARY
Liquid and gaseous effluent releases for 2003 were similar to those of previous years.
During 2003 there were one hundred seven (107) liquid batch releases resulting in a total release volume of one million thirty six thousand (1,036,000) gallons. The total number of liquid batch releases in 2003 was higher than in 2002 (83 releases in 2002),
but the total volume released in 2003 was slightly lower than in 2002 (1,063,000 gallons released in 2002). The predominant radionuclide released in liquid effluents during 2003 was tritium. Approximately seventy (70) curies of tritium were released in liquid effluents in 2003, compared to sixty-six (66) curies released in 2002. The radionuclides that had the greatest impact on offsite dose from liquid effluents during 2003 were Mn-54 and Co-60. Though the total curies released for these isotopes (0.0053 and 0.0051 respectively) was lower than tritium, the resultant offsite dose was higher due to the differences in the dose conversion factors. Consistent with previous years, the offsite dose from liquid releases in 2003 was less than one percent (1%) of the annual limits
. for both organ and whole body dose.
7.
Gaseous effluents for 2003 were also comparable to those of previous years. Similar to liquid effluents in 2003, the predominant radionuclide released in gaseous effluents was tritium. When compared with all radionuclides released in gaseous effluents in 2003,
.tritium was the main contributor to the resultant offsite dose. The resultant offsite organ dose for-the Susquehanna Steam Electric Station from gaseous effluents for 2003 was 1.17 rrem, which is 7.8 percent (7.8%) of the per unit annual limit of fifteen (15) mrem.
The main source of the tritium in liquid and gaseous effluents is from control rod blades currently in each reactor's core.
1-5
FIGURE 1-1 SSES AIRBORNE EFFLUENT RELEASE POINTS EfR A 1l RtACTOR BUIEDING I
REACTOR BLDING EXHAUST / EXHAusT 160.770 17 357OCFM 0 0 AT S( F-110 F AT 6DF-110 F 302.959 CFM 17.500 CFM 227.034 CFM AT ASOPF-120°F AT 120F AT 00OF-t2D°F OUTSIDE AIR INTAKE REACTOR BUILDING >TURBINE UNIT IITURINE UNIT It BUILDING BUILDING DIESEL EXMAUST PLENUM EXHAUST EXHAUST VENT 'VENT IESE GENERATOR L BUILDNG .
'WJ ILDINC \ *74G, b UNIT I \ \
\ ~~UNIT II\1 1-6
FIGURE 1-2 SSES WATERBORNE EFFLUENT PATHWAY FROM EVAPORATOR HEATING 44REACTOR WELL SEAL LEAK DRAIN7 ISTEAM CONDENSATE RETURN TANK FROM PHASE SEPARATORS I 4 -REACTOR BUILDING DRAINS (DECANT)
L DRYWELL DRAINS I I SSES LIOUID EFFLUENT RELEASE FLOWPATI4- -I
.11r TURBINE BUILDING DRAINS I (M.161. M-162. M.163 AND M.1641
[ RADWASTE BUILDING DRAINS 0 RADWASTE BUILDING DRAINS I I. __LIQUID RADWASTE RECYCLE COLLECTION TANKPMPS WASTEMIXNG TAKEPN RESIN TANSE AIUDW RADAST -CONDENSATE STORAGE CWMSLECSAMPE TANK PUPP TANKS OT.522A & B OP-522A, B 6, C
__ __ _ _ _ _ _ _ A -
RADWASTE DU] FUEL POOL CLEANUP SAMPLE STA SYSTEM CHEMICAL DECO I E RWCU CHEMICAL DECOM DRAE3 E- AUX. BOILER OLD CHEMICAL DRAIN TANK CHEP41CAL WASTE TANK 0 E' RASS A CHPEMICAL WASTE TANK
!%..COZOENSAT UMPS DP ED ESI REGEN.T MKS'- EVAPORATOR CONCENTRATE ILLATE H M L A .E TANK NEUTRAL ZING MPS 7_11- - TANKS 27A, 8 1T-130A, 6 2T-130A. 5 CHEMICAL WASTE PERSONNEL DECONTMNIO (DETERGENTS) zw 3
FLOOR DECON (SOLUTIONS)CS LAIG D AN REGULATED SHOP DRAINS LAUNDRY DRAINS (3) I ac I
.2 I
(1) RADWASTE EVAPORATORS (2) CONO DEMNI RESINS CURRENTLY (3) CONTAMINATED CLOTHING CURRENTLY ARE NOT USED NOT REGENERATED NOT LAUNDERED ONSITE SUSQUEHANNA RIVER
=1)
)
1-7
SUPPLEMENTAL INFORMATION
'a' 1. Reculatory 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 2.0E-04 ,uCVml 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 2003 resulted in an Annual E-Bar Beta value of 4.05E-01 and an E-Bar Gamma value of 7.09E-01.
- 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 Quantifying 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 1-8
grab samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).
- b. lodines: 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 samplers 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 samplers 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: Airbome 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 pICVcc).
- 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 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 multiplied by the volume of the batch to determine the total quantity of each nuclide released Jn each batch. The isotopic totals for each batch are summed to determine the total source term for the report period.
1-9
TABLE 1-1 s-' 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 mrern/year - ORGAN (inhalation pathways only)
- dose rate limit at and beyond the site boundary (TRO 3.11.2.1.1l.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
- 5.0 mrem ORGAN
- quarterly dose limits per SSES unit (TRO 3.11.1 .2.a)
- 2. *3.0 mrem - TOTAL BODY
- 10.0 mrem - ORGAN
- annual dose limits per SSES unit (TRO 3.11.1 .2.b)
D. AIRBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLE LIMIT VALUES IN TABLE 2-1 Fission and Activation Gases A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1 .l.A) limit of 500 mrem/yr was calculated from the expected mix of noble gas radionuclides presented in Table 11.3-1 of the SSES Final Safety Analysis Report. The limit is 1 .OOE+06 pCi/min (1.67E+04 puCVsec).
Iodines KY A derived release rate limit based on the Technical Requirement (TRO 3.1 12.1..II.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 11.3-1 of the SSES Final Safety Analysis Report. The limit is 1.04E+02 pICVmin (1.73E+00,pCVsec).
Particulates A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1.1l.A) limit of 1500 mrem/yrfrom 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 11.3-1 of the SSES Final Safety Analysis Report. The limit is 3.OOE+03 ,Ci/min (5.OOE+01 ,PCVsec).
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,uCicc) to unrestricted areas. A relative concentration of 4.1 E-05 sec/m 3 was assumed.
The limit is 1.46E+05 pCLmin (2.44E+03 pCVsec).
1-11
E. WATERBORNE EFFLUENT: BASESFOR PERCENT OF APPLICABLE LIMIT VALUES IN TABLE 2-3 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 10CFR20 Appendix B, Table 2, Column 2 Effluent Concentration Values.
Tritium Liquid effluent quarterly tritium concentrations are compared to ten times the 10 CFR 20 Appendix B, Table 2, Column 2, Effluent Concentration value of 1.OE-03 pCiml to unrestricted areas.
Dissolved and Entrained Gases Liquid effluent concentrations for dissolved and entrained gases are compared to the limiting value for total noble gas activity of 2.OE-04 uCi/ml.
Radionuclide Fractional Summation The sum of the ratios between the concentration of each radionuclide present in a batch release and ten times the effluent concentration limit in 10CFR20
-- :. Appendix B, Table 2, Column 2 or the dissolved and entrained noble gas limit.'
- of 2.0E-04 pCi/ml, may not exceed 1". The sum of the percents of applicable limits for fission and activation products, tritium and dissolved and entrained gases must be less than 100%.
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.
Radionucilde LLD (p0Ucc)
Kr-87 . 4.6 E-08 Kr-88 5.3 E-08 Xe-133 5.4 E-08 Xe-133m 1.3 E-07 Xe-135 1.5 E-08 Xe-1 35m 5.OE-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-134 2.4 E-14 2-2
Radionuclide LLD (pCUcc)
Cs-137 2.1 E-14 Ce-141 1.5 E-14 Ce-144 7.0 E-14 1-131 4.4 E-14 Sr-89 2.0 E-15 Sr-90 3.0 E-16 H-3 2.6 E-08 Gross Alpha 5.0 E-16 2-3
TABLE 2-1 AIRBORNE EFFLUENT - SUMMATION OF ALL RELEASES First Second Third Fourth A. Fission and Activation Gas Unit Quarter Quarter I Quarter Quarter Total Release Ci 3._1 E-01 0 0 0 Average Release Rate for Period ,ui/sec 4.OOE-02 0 0 O Percent of Applicable Limit 2.40E-04 0 (1.67E+04 pCVsec)
B. lodines Total 1-131 Ci0 0 0 0 Total 1-133 ci 0 0 0 0 Average Release =iCi/sec Rate for Period_ ________
O 0 1 00 O__
0 __ _ O_____
0 Percent of Applicable Umit % 0 0 0 0
- (1.73E+0O0pCVsec)
C. Particulate Particulate with Half-Life >8 Days Ci 4.22E-04 4.69E-04 5.72E-04 7.36E-05
-Average Release Rate for Period qCcsec 5.43E-05 5.96E-05 7.20E-05 9.26E-06
\,2ercent of Applicable Limit % 1.09E-04 1.1 9E-04 1.44E-04 1.85E-05
-..(5;00E*01 pCVsec).
Gross Alpha Radioactivity Ci 0 0 0 0 D. Tritium Total Release Ci l 2.88E+01 5.17E+01 4.63E+01 2.95E+01 l Average Release Rate for Period 3.71 E+00 6.58E+00 5.83E+00 3.71 E+00 Percent of Applicable Limit %
% 1.52E-01 2.70E-01 I 2.39E-01 1.52E-01 (2.44E+03 /jC/sec) 2-4
TABLE 2-2 AIRBORNE EFFLUENT - RADIONUCLIDES RELEASED Releases in Contintunou MmrIa First Second Third l Fourth Nuclides Released Unit Quarter Quarter Quarter Quarter A. Fission and Activation Gases Ar-41 Ci 3.37E-03 0 0 0 Kr-85 Ci 0 0 0 0 Kr-85m Ci 7.68E-04 0 0 0 Kr-87 Ci 5.44E-03 0 0 0 Kr-88 Ci 3.01 E-03 0 0 0 Kr-89 Ci 6.03E-02 0 0 0 Xe-133 Ci 2.36E-04 0 0 0 Xe-133m Ci 0 0 0 0 Xe-1 35 Ci 2.84E-03 0 0 0 Xe-135m Ci 1.52E-02 0 0 0 Xe-137 Ci 1.52E-01 0 0 0 Xe-1 38 Ci 6.73E-02 0 0 0 Total for Period Ci 3.10E-01 0 0 0 B. lodines 1-131 Ci 0 l 0 O0 lo]
1-133 Ci 0- 0_ 0 1 1-135 Ci 0 1 O O Total for Period Ci 0 0 0 O C. Particulate Cr-51 Ci 2.58E-04 2.66E-04 5.17E-04 I. 5.:21 E-05 l Mn-54 Ci 6.59E-05 1.58E-04 2.74E-05 9.63E-06 Fe-59 Ci 0 0 0 0 Co-58 Ci 0 3.17E-06 5.94E-06 3.1 OE-07 Co-60 Ci 1.37E-05 4.1 OE-05 2.21 E-05 1.1 5E-05 Zn-65 Ci 0 0 0 0 Sr-89 Ci 0 0 0 0 Sr-90 Ci 0 0 0 0 Cs-134 Ci 0 0 0 0 Cs-137 Ci 0 0 0 0 Ce-141 Ci 0 0 0 0 Ce-1 44 Ci 0 0 0 0 Ag-11OM Ci 0 0 0 0 Nb-95 Ci 0 0 0 0 Ba-La-140 Ci 0 0 0 0.
Total for Period Ci 3.38E-04 4.68E-04 5.72E-04 7.35E-05 2-5
Waterborne Effluents 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. I Otr. 2 Otr. 3 Otr. 4 Annual
- 1. Number of Batch Releases 29 20 33 25 107
- 2. Total Time Period for a Batch Release 3.74E+03 2.26E+03 4.83E+03 4.06E+03 1.49E+04
- 3. Maximum Time Period for a Batch Release 2.88E+02 1.05E+03 3.08E+02 2.84E+02 1.05E+03
- 4. Average Time Period for a Batch Release 1.29E+02 1.13E+02 1.46E+02 1.62E+02 1.39E+02
- 5. Minimum Time Period for a Batch Release 2.50E+01 2.70E+01 2.80E+01 2.60E+01 2.50E+01
- 6. Average Cooling Tower Blowdown 6.47E+03 7.69E+03 1.17E+04 9.04E+03 9.07E+03 Flow Rate During Periods of Release
- 7. Susquehanna River Flow Rate 1.11 E+07 1.08E+07 5.70E+06 1.20E+07 9.91 E+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 NWA
- 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 Lower Limits.of Detection (LLD) as specified in the SSES Technical Requirement 4.11A.1.11-1, 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 (uCilml)
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-134 2.2 E-08 2-6
Radionuclide LLD (uCUml)
Cs-137 2.6 E-08 Ce-141 3.2 E-08 Ce-144 1.3 E-07 Sr-89 4.0 E-08 Sr-90 4.0 E-09 Fe-55 1.0 E-06 H-3 4.6 E-06 Gross Alpha 3.0 E-08 2-7
TABLE 2-3 WATERBORNE EFLUENT - SUMMATION OF ALL RELEASES First Second Third Fourth A. Fission and Activation Products Unit Quarter Quarter Quarter Quarter
- 1. Total Release (excluding: Tritium, Ent.
Gases, Alpha) Ci 1.1 OE-02 5.21 E-03 8.24E-03 3.83E-03
- 2. Average Diluted Concentration During Period ,uCi/ml 1.20E-07 7.94E-08 3.84E-08 2.75E-08
- 3. Sum of Average Diluted CLI, Ratio During Period Unitless 8.19E-04 6.05E-04 2.94E-04 1.86E-04
- 4. Percent of Applicable Limit (Ratio < 1.0) 0.08 0.06 0.03 0.02 B. Trithim
- 1. Total Release Ci 1.96E+01 4.35E+00 2.19E+01 2.44E+01
- 2. Average Diluted Concentration
' During Period pCi/ml 2.14E-04 6.63E-05 1.02E-04 1.76E-04
- 3. Percent of Applicable Limit (1.OE-2 pCi/ml) % 2.14E+00 6.63E-01 1.02E+00 1.76E+00 C :: nicctniva~ri ~nn Fntrninpef (nacPg.
- 1. Total Releasel i [ 8.92E-05 0.OOE+00 l 4.23E-05 3.OOE-05
- 2. Average Diluted Concentration pCi/ml 9.74E-10 0.00E+00 1.97E-10 I 2.16E-10 During Period .
- 3. Percent of Applicable Limit (2.OE-4 pCi/ml) j 4.87E-04 0.00E+00 9.87E-05 1.08E-04
. Radionuclide Fractional Summation
- 1. Sum of Percentages/Percent of Applicable Limit Diuring Period (Limit = 100%) l % l 2.22 0.72 1.05 1.78 E. Gross Alpha Radioactivity
- 1. Total Release Ci 4.68E-05 1 1.60E-05 4.88E-06 5.85E-06 F. Volume of Water Released I Gallons I 2.85E+05 T 7.66E+04 I 3.49E+05 I 3.25E+05
'(Priorto Dilution) Liters 1.08E+06 2.90E+05 1.32E+06 1.23E+06l G. Volume of Dilution Water l Gallons l 2.39E+07 l 1.73E+07 l 5.63E+07 l 3.65E+07 l Used During Period of Release Liters 9.05E+07 6.54E+07 2.13E+08 1.38E+08 H. Volume of Dilution Water I Gallons I 6.67E+08 I 9.96E+08 I 1.42E+09 I 9.14E+08 I Used Over Entire Period Liters 2.53E+09 3.77E+09 5.36E+09 3.46E+098l 2-8
TABLE 24 WATERBORNE EFFLUENT - RADIONUCLIDES RELEASED
_ _ Releases in Batch Mode Nuclides Unit First Second Third Fourth Released _ auarter Quarter Quarter Quarter A. Fission and Activation Products F-1 8 Ci 0 0 0 .0 Na-24 Ci 0 . 00 0 Cr-51 Ci 6.52E-03 8.27E-04 3.52E-04 4.65E-04 Mn-54 Ci 2.24E-03 1.18E-03 1.07E-03 8.54E-04 Fe-55 Ci O.OOE+00 2.09E-03 - 5.18E-03 1.80E-03 Co-58 Ci 2.00E-04 7.85E-05 7.27E-06 5.61 E-05 Fe-59 Ci 7.87E-05 4.93E-05 9.24E-07 O.OOE+00 Co-60 Ci 1.93E-03 9.77E-04 1.63E-03 6.04E-04 Zn-65 Ci 1.06E-05 2.60E-06 O.OOE+00 3.31 E-05 As-76 Ci 0 0 0 0 Rb-86 Ci 0 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 O.OOE+00 6.81 E-07 O.OOE+00 O.OOE+00
- Sn-1 17M Ci O.OOE+00 8.93E-07 O.OOE+00 O.OOE+00 Sb-124 Ci O.OOE+00 O.OOE+00 O.OOE+00 2.96E-06 Ba-1 31 Ci O.OOE+00 O.OOE+00 O.OOE+00 1.46E-05
. Ta-i 82 Ci O.OOE+00 9.76E-06 O.OOE+00 0.00E+00 Total for Period Ci 1.1 OE-02 5.22E-03 8.24E03 3.83E03 B Tritium .-
Total for Period [Cl 1 1.96E+01 4.35E+00 2.19E+01 l 2.44E+01 C. Dissolved and Entrained Gases Ci
.Ar-41 5.682-07 0.00E+00 O.000+00 0.00+00 Kr-85 ___ __ __ __ 00 0 Kr-86m Ci O 0 0 Kr-87 Ci O O0 0 Kr-88 ci o . 0 0 Xe_1_31m Ci O O 0 0 Xe_133m Ci O O 0 0 Xe-133 Ci 6.98E-05 O.OOE+00 1.17E-05 1.31 E-05 Xe_135m Ci . 0 0 0 Xe-135 Ci 1.88E-05 O.OOE+00 3.06E-05 1.69E-05 Total for Period Ci 8.92E-05 O.OOE+00 4.23E-05 3.00E-05 2-9
Figure 2-1 Susquehanna River Monthly Average Flow Rates 25.0 20.0 a.
co C
15.0
-0 C.
. co 10.0 n.
w 5.0 0.0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1-4-2003 2-10
.- I------ ---
Figure 2-2 SSES Monthly Liquid Radwaste Discharge Totals 350 300*
250 1200 2150 00 50-0*
Jan Feb Mar Apr, May Jun Jul Aug Sep Oct Nov Dec
-50*
-42003 2-11
TABLE 2-5 ESTIMATED TOTAL ERRORS ASSOCIATED WITH EFFLUENTS MEASUREMENTS 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 3.3%
- 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. LRW Filter Media - Class A HIC (Dewatered) +/-25%
- b. Chem-Decon Resin - Class A HIC (Pyrolysis) +25%
- c. Asbestos - Class A Strong Tight Container (Compacted) +25%
- d. Ash - Class A Strong Tight Container (Incineration) +/-25%
- e. Bead Resin/Charcoal - Class A HIC (Pyrolysis) +/-25%
- f. Condensate Demineralizer/Radwaste Demineralizer - +/-25%
Class A Steel Liner (Dewatered)
- g. Condensate Demineralizer/Radwaste Demineralizer - +P5%
Class A HIC (Pyrolysis)
- h. Contaminated Waste Oil - Class A +/-25%
(Fuel Blending for Co-Generation)
I. Processed DAW +25%
Class A Strong Tight Container (Compacted)
- j. Irradiated Components ++/-5%
Class B HIC 2-12
ESTIMATED MAXIMUM MEASUREMENT- MEASUREMENT ERROR
- 3. Solid Wastes (cont)
(Non-Processed)
I. RWCU Filter Media - Class B HIC (Dewatered) +25%
Processed)
- n. Irradiated Components - Class C Steel Liner +/-25%
- a. Cartridge Filters - Class C HIC (Non-Processed) +95%
2-13
SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT
- SOLJD RADIOACTIVE WASTE
- DATA PERIOD: JANUARY 1. 2003 - DECEMBER 31 2003 PREPARED BY.
MICHAEL C. MICCA HEALTH PHYSICIST APPROVED BY:
RADIOLOGICAL OPERAIONS SUPERVISOR 2-14
REPORT NOTES
- 1. All activities reported in millicuries (mCi) unless otherwise noted.
- 2. Reported activities, as indicated with the (<)sign, are comprised inwhole or part of MDL values.
- 3. Estimated maximum measurement error is+/-25%.
2-15
TABLE 2,8 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
. Data Period: January 1, 2003 - December 31,2003 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Number of Shipments Mode of Transportation Destination 11 Truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS Number of Shipments Mode of Transportation Destination None
., I .. .
. I 2-16
Table 2-7 K Year: 2003 Class: A Volume Reduction Vendor: No.
Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Activity (mCi) % of Total Nuclides ______________ 0.00______
6.493E+00 0.00 %
C-14 0.00 %
CE-144 3.129E+01 1.790E-03 0.00 %
CM-242 0.59 %
6.185E+03 CO-58 3.63 %
CO-60 3.783E+04 1.105E+05 10.61 -
CR-51 0.00 %.
CS-137 1.292E+01 7.230E+05 69.44 %
FE-55 1.12 %
1.168E+04 FE-59 0.01 %
H-3 7.470E+01 1.11OE-04 0.00 %
1-129 14.38 %
1.498E+05 MN-54 0.05 %
NB-95 5.118E+02
- 0.00 %
6.960E-01 NI-59 0.06 %
6.697E+02 NI-6 3 0.06 %
6.272E+02 SB-124 0.00 %
SR-90 7.255E+00 3.660E-06 0.00 %
TC-99 0.03 %
ZR-95 3.275E+02 1041.233 100.00 %
- K~ Total Activity (Ci) 7.498 m3 264.800 ft3
- Container Volume 2-17
Table 2-8
<-/ Year: 2003 Class: A Volume Reduction Vendor: Yes Source: Chem-Decon Resin Container: HIC (High Integrity Container)
Process: Pyrolysis Activity (mCi) % of Total Nuclides ______________ 0.00______
AM-241 4.100E-03 0.00 %
9.327E-01 0.00 %
C-14 CE-141 6.040E+01 0.02 %
CE-144 1.070E+02 0.04 %
4.740E-03 0.00 %
CM-244 CO-58 3.362E+03 1.10 %
CO-60 6.058E+04 '19.91 %
2.186E+04 7.19 %
CR-51 3.076E+01 0.01 %
CS-137 FE-55 2.042E+05 67.10 %
4.029E+01 0.01 %
FE-59 1.603E+02 0.05 %
H-3 7.773E-01 0.00 %
- 1-129 1.146E+04 3.77 %
MN-54 8.038E+00 0.00 %
- NB-95 NI-59 2.733E+00 0.00 %
8.388E+02 0.28 %
NI-63 8.210E-03 0.00 %
PU-238 2.750E+00 0.00 %
SB-124 1.469E+01 0.00 %
SB-125 TC-99 1.202E+00 0.00 %
ZN-65 1.571E+03 0.52 %
-\
Total-Activity (Ci) 304.275 100.00 %
Container Volume 50.919 ft3 1.442 m3 2-18
Table 2-9
- Year: 2003 Class: A Volume Reduction Vendor: Yes Source: Asbestos Container: -Strong Tight Container Process: Compacted '
Nuclides Activity (mCi) % of Total C-14 1.OOOE-04
- 0.00 %
CE-144 1.700E-03 0.06 %
CO-58 5.600E-03 0.20 %
Co-60 2.955E-01 10.42 %
CS-137 6.000E-04 0.02 %
FE-55 2.079E+00 73.28 %
FE-59 1.020E-02 0.36 %
H-3 2.400E-03 0.08 %
1-129 < O.OOOE+00 0.00 %
MN-54 4.350E-01 15.33 %
NI-59 4.000E-04 0.01 %
NI-63 5.400E-03 0.19 %
SB-125 - 1. 00E-03 0.04 %
SR-89 < O.OOOE+00 0.00 %
SR-90 < 0.000E+00 '0.00 %
TC-99: < 0.000E+00 0.00 %
Total Activity (Ci) 0.003 100.00 %
Container Volume 1.500 ft3 0.042 m3 2-19
Table 2-10
- *Year
- 2003 Class: A Volume R,eduction Vendor: Yes Source: Ash Container: Stronc,gTight Container Process: Incineeration Activity (mCi) % of Total Nuclides ______________
2.980E-02 0.00 %
AG-ilOM 0.03 %
C-14 1.670E+01 7.196E-01 0.00 %
CE-144 2.OOOE-04 0.00 %
CM-242 1.600E-03 0.00 %
CM-244 2.280E+01 0.04 %
CO-58 3.893E+03 6.46 %
CO-60 3.293E-01 0.00 %
CR-51 0.01 %
CS-134 4.938E+0O 5.173E+00 0.01 %
CS-137 5.248E+04 87.16 %
FE-55 0.00 %
FE-59 1.869E+00
.7.524E+01 0.12 %
H-3 1.210E-02 0.00 %
I -129 3.642E+03 6.05 %
MN-54 1.870E-02 0.00 %
NB-95 0.00 %
NI-59 7.850E-02 7.078E+01 0.12 %
NI-63 3.90OE-03 0.00 %
PU-238 *0.00 %
PU-239 1.OOOE-03 5.452E-01 0.00 %-
PU-241 1.86BE-01 0.00 %
$fB-1 25 0.00 %
SR-89 1.458E-01
- 1.402E-01 0.00 %
SR-90_- 0.00 %
TC-99 < O.OOOE+00 5.470E-02 0.00 %
ZN-65 1.250E-02 0.00 %
ZR-95 60.219 100.00 %
Total Activity (Ci) 54.148 ft3 1.533 m3 Container Volume 2-20
Table 2-11 K)
- Year:
Class:
2003 A Volume Reduction Vendor: Yes Source: Bead Resin/Charcoal Container: -HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) *% of Total C-14 6.189E-Ol 0.26 %
CE-144 1.210E-02 ' 0.01 %
CO-58 2.460E-O1 0.10 %
CO-60 2.549E+01 10.59 %
CS-137 9.590E-02 0.04 %
FE-55 8.460E+O1 35.16 %
H-3 8.390E+01 34.87 % -
1-129 3.410E-02 0.01 %
NN-54 4.550E+0l 18.91 %
NI-63 6.570E-02 0.03 %
TC-99 2.854E-02 0.01 %
Total Activity (Ci) 0.241 100.00 %
Cbntainer Volume 40.930 ft3 1.159 m3 2-21
Table 2-12 K-i Year: 2003 Class: A Volume Reduction Vendor: No Demineralizer Source: Condensate Demineralizer. Radwaste Container: Steel Liner Process: Dewatered Activity (mCi) % of Total Nuclides ______________
< 2.320E-03 0.00 %
C-14 1.99 %
CO-58 5.920E+O1 5.300E+02 17.80 %
CO-60 3.29 %
CR-51 9.810E+0l 6.110E+00 0.21 %
CS-137 56.76 %
FE-55 1.69oE+03 7.330E+01 2.46 %
H-3 0.00 %
1-129 < 1.350E-O0 5.110E+02 17.16 %
MN-54 0.25 %
NI-63 7.480E+O0
< 3.410E-05 0.00 %
TC-99 0.08 %
- 2.450E+00 zN-65.
100.00 %
2.978 Total Activity (Ci) 5.646 m3 Container Volume 199.400 ft3 2-22
Table 2-13
.- Year: 2003 Class: A Volume Reduction Vendor: Yes Demineralizer Source: Condensate Demineralizer / Radwaste Container: HIC (High Integrity Container)
Process: Pyrolysis Activity (mCi) % of Total Nuclides ______________ __________
1.379E+02 .0.55 %
C-14 0.00 %
CE-144 4.634E-01 1.OOOE-04 0.00 %
CM-242 0.00 %
CM-244 2.022E-03 1.918E+02 0.76 %
CO-58 %
3.837E+03 15.17 CO-60 2.92 %
CR-51 7.378E+02 6.805E+00 0.03 %
CS-137 59.50 %
FE-55 1.505E+04 3.285E+01 0.13 %
FE-59 %
7.656E+02 3.03 H-3 0.00 %
I-129 7.998E-01 2.570E-02 0.00 %
1-131 %
4.467E+03 17.66 MN-54 0.00 %
NA-24 1.741E-12 4.680E+00 0.02 %
NB-95 0.00 9 NI-59 1.214E-01 5.520E+01 0.22 %
NI-63 0.01 %
SB-124 1.936E+00 1.796E-01 0.00. %
SR 0.01 %
TC-99 1.630E+00 Activity (Mi) 25.289 100.00 %
- :~
-Total 7.865 m3 Container Volume 277.755 ft3 2-23
Table 2-14 K> Year: 2003 A Volume Reduction Vendor: Yes Class:
Source: Contaminated Waste Oil Container: None Process: Fuel Blending for Co-Generation Nuclides Activity (mCi) % of Total 5.710E-06 '0.00 %
C-14 9.620E-05 0.06 %
CE-144 CO-60 1.640E-02 10.11 %
CS-137 3.570E-05 0.02 %
FE-55 1.150E-01 70.86 %
H-3 2.620E-02 16.14 %
1-129 3.190E-06 0.00 % -
MN-54 4.220E-03 2.60 %
NI-59 2.370E-05 0.01 %
3.040E-04 0.19 %
- TC-99 *c 3.460E-11 0.00 %
Total Activity (Ci) 0.000 100.00 %
- Container Volume 0.000 ft3 - 0.000 m3 2-24
Table 2-15 Year: 2003 Class: A Volume Reduction Vendor: Yes Source: Processed DAW Container: Strong Tight Container Process: Compacted Activity (mCi) % of Total Nuclides ______________ 0.06______
3.564E+00 0.06 %
AG-lIOM 2.129E-05 0.00 %
AM-241 2.052E-01 0.00%
C-14 0.01 %
CE-144 6.154E-01 2.054E-05 0.00 %
CM-242 0.00%
CM-244 1.652E-05 1.704E+01 0.27%
CO-58 6.068E+02 9.73 %
CO-60 1.85 %
CR-51 1.152E+02 7.141E-01 0.01 %
CS-137 72.33 %
FE-55 4.510E+03 3.494E+01 0.56 %
FE-59 0.07 %
H-3 4.608E+00 1.143E-01 0.00 %
1-129 14.68 %
MN-54 9.152E+02 4.672E+00 0.07 %
NB-95 0.00 %
NI-59 2.295E-01 1.179E+01 0.19 %
NI-63 0.00 %
PU-238 . 5.330E-05 3.126E-05 0.00 %
PU-239 0.00 %
PU-241 6.440E-03 1.009E-01 0.00 %
- SB-124 0.00 %
- SB-125 2.679E-01 1.400E-03 0.00 %
SR 0.00 %
SR-90 4.564E-03 2.047E-02 0.00 %
TC-99 0.11 %
'ZN-65 6.997E+00 1.949E+00 0.03 %
ZR-95 ____________
6.235 100.00 %
Total Activity (Ci) 6356.390 ft3 179.996 m3 Container Volume 2-25
Table 2-16 Year: 2003 Class: B Volume Reduction Vendor: No Source: Irradiated Components Container: HIC (High Integrity Container)
Process: N/A Nuclides Activity (mCi) % of Total C-14 3.963E+00 0.00 %
CE-144 2.233E+02 0.01 %
CM-244 4.721E-02 0.00 %
CO-58 9.823E+02 0.03 %
CO-60 1.284E+05 3.62 %
CR-S1 1.689E+03 0.05 %
CS-137 6.659E+0l 0.00 %
FE-55 3.263E+06 92.11 %
FE-59 1.682E+03 0.05 %
H-3 6.220E+02 0.02 %
1-129 1.900E-03 0.00 %
MN-54 1.358E+05 3.83 %
NB-94 3.590E-02 0.00%
-NB-95 1.645E+03 0.05 %
NI-59 3.851E+01 0.00 %
NI-63 6.057E+03 0.17 %
PU-23 8 4.291E-02 0.00 %
SB-124 8.501E+01 0.00 %
SB-125 7.400E+02 0.02 %
TC'99 4.868E+00 0.00 %
ZN-65 5.354E+02. 0.02 %
ZR-95 9.165E+02 0.03 %
Total Activity (Ci) 3542.393 100.00 %
Container Volume 240.360 ft3 6.806 m3 2-26
Table 2-17
- Year: 2003 Class: B Volume Reduction Vendor: No Source: Non-Processed DAW Container: HIC (High Integrity Container)
Process: Non-Processed Activity (mC;) % of Total Nuclides ______________
3.910E-03 .0.00 %
C-14 0.00 %
CE-144 3.860E-01 4.780E-05 0.00 %.
CM-244 1.900E+00 0.02 %
CO-58 2.90 %
CO-60 2.330E+02 4.380E+00 0.05 %
CR-51 0.00 % -
CS-137 1.200E-01 7.440E+03 92.72 %
FE-55 0.05 %
FE-59 3.970E+00 1.490E+00 0.02 %
H-3 0.00 %
1-129 < 1.OlOE-03 3.210E+02 4.00 %
MN-54 0.04 %
NB-95 2.930E+00 8.11OE-02 0.00 %
NI-59 0.13 %
NI-63 1.040E+01 1.940E-01 0.00 %
SB-124 1.690E+00 0.02 %
SB-125 0.00 %
TC-99 1.380E-02 1.290E+00 0.02 %
ZN-65 0.02 %
ZR-95 1.450E+00 ____
8.024 100.00 %
-Total Activity (Ci) 0.006 m3 Container Volumie 0.200 ft3 2-27
Table 2-18
\K> Year: 2003 Class: B Volume Reduction Vendor: No.
Source: RWCU Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides Activity (mCi) % of Total 1.270E+01 .0.00 %
C-14 5.870E+02 0.02 %
CE-144 9;330E-03 0.00 %
CM-242 CM-244 l.100E-02 0.00 %
CO-58 6.680E+03 0.23 %
CO-60 3.260E+05 11.11 %
2.700E+03 0.09 %
CR-51 7.240E+02 0.02 %
CS-137 2.280E+06 77.73 %
FE-55 FE-59 6.920E+02 0.02 %
H-3 8.970E+02 0.03 %
< 3.860E-05 0.00 %
1-129 MN-54 3.020E+05 10.30 %
NB-95 5.040E+02 0.02 %
NI-59 8.620E+01 0.00 %
NI-63 7.950E+03 0.27 %
1.460E+00 0.00 %
PU-241 1.18OE+02 0.00 %
SR-89 0.00 %
SR-90 4.600E+00 2.750E-0l 0.00 %'
TC-99 -
ZN-65 3.570E+03 0.12 %
- 1.,.f*-ZR-95 6.200E+02 0.02 %
Total Activity (Ci) 2933.147 100.00 %.
132.400 ft3 3.749 m3 Container Volume 2-28
Table 2-19 k) Year: 2003 Class: C Volume Reduction Vendor: No Source: Non-Processed DAW Container: HIC (High Integrity Container)
Process: Non-Processed Activity (mCi) % of Total Nuclides ______________ -_
0-. -00_
3.310E-0l 0.00 %
C-14 0.06 %
CE-144 4.800E+00 1.230E+01 0.14 %
CO-58 10.84 %
CO-60 9.280E+02 2.060E+00 0.02 %
CS-137 74.30 %
FE-55 6.360E+03 2.040E+O1 0.24 %- -
FE-59 0.00 %
1-129 1.850E-01 1.210E+03 14.13 %
MN-54 0.02 %
NI-59 1.370E+00 1.760E+01 0.21 %
NI-63 0.04 %
SB-125. 3.330E+00 1.850E-02 0.00 %
-SR-89 0.00 %
SR-90 7.11OE-02
< 1.920E-05 . 0.00 %
TC-99 (Ci) 8.560 100.00 %
Total Activity 2.728 m3
.Container Volume 96.320 ft3 2-29
Table 2-20 Year: 2003 Class: C Volume Reduction Vendor: No Source: Irradiated Components Container: Steel Liner Process: N/A Nuclides Activity (mCi) % of Total 1.458E-02 .0.00 %
AM-241 5.629E-04 0.00 %
AM-243 4.013E+03 0.00 %
C-14 1.339E-01 0.00 %
CM-242. %
6.187E-04 0.00 CM-243 %
9.860E-02 0.00 CM-244 %
1.550E+05 0.16 CO-58 %
4.710E+07 47.49 CO-60 %
4.840E+04 0.05 CR-51 %
4.260E+07 42.95 FE-55 %
1.160E+04 0.01 FE-59 %
6.610E+03 0.01 H-3 %
1.250E+06 1.26
-HF-181 %
5.900E-06 0.00 1-129 %
1.565E+06 1.58 MN-54 %
8.090E+01 0.00 NB-94 %
1.427E+03 0.00 NB-95 %
1.507E+04 0.02 NI-59 %
2.848E+06 2.87 NI-63 %
2.660E-03 0.00 NP-237 7 %
PU-238 2.998E+01 0.00 2.099E-02 0.00 PU-239 %
2.628E-02 0.00 PU-240 %
3.089E+0O 0.00 PU-241 %-
3.813E+02 0.00 SB-124 %
1.475E+00 0.00 SB-125. %
3.538E+06 3.57 TA-182 %
1.624E+01 0.00 TC-99 %
1.345E-04 0.00 U-235 %
3.355E+04 0.03 ZN-65 %
1.205E+03 0.00 ZR-95 Total Activity (Ci) 99178.388 100.00 %
229.600 ft3 6.502 m3 Container Volume 2-30
Table 2-21 Year: 2003 Class: C Volume Reduction Vendor: No Source: Cartridge Filters Container: HIC (High Integrity Container)
Process: Non-Processed Activity (mCi) % of Total Nuclides ______________ __________
6.730E-01 0.00 %
C-14 0.06 %
CE-144 1.203E+01 9.470E-03 0.00 %
CN-242 0.00 %
CN-244 1.690E-04 1.375E+00 0.01 %
CO-58 5.88 %
CO-60 1.242E+03 1.750E-01 0.00 %
CR-51 0.01 %
CS-137 1.962E+00 1.930E+04 91.39 %
FE-55 0.00 %
FE-59 7.770E-01 1.709E-01 0.00 %
H-3 0.00 %
HF-181 5.610E-02 8.072E-02 0.00 %
1-129 2.23 %
MNm-54 4.720E+02 2.768E+00 0.01 %
NB-95 0.00 %
NI-59 3.150E-01 1.960E+01 0.09 %
NI-63 0.00 %
PU-238 3.910E-04 6.774E+00 .0.03 %
PU-241 0.00 %
SB-124 l.1lOE-01 2.310E+01 0.11 %
SB-125 0.02 %
- -SN-113 3.350E+O0 4.300E-03 0.00.%
-SR-89 0.00 %.
SR 1.160E-02 3.120E-01 0.00 %
TC-99 0.05 %
ZN-65 1.009E+01 2.120E+01 0.10 %
ZR-95 ____________
21.119 100.00 %
Total Activity 'Ci) 1.022 m3 Container Volume* 36.080 ft3
- 2-31
SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES K-I 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 1Om 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 Ro6kville, 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 last 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 31 SSES METEOROLOGICAL DATA RECOVERY FOR 2003 PERCENT VALID PARAMETER DATA RECOVERY Wind Speed lOnm-Primary ti) 99.6 Wind Speed 60m -Primary 99.3 Wind Speed 10m-Backupa) 99.9 Wind Speed 1Om - Downriveri) 99.3 Wind Direction lOim -Primary - 99.7 Wind Direction 60m - Primary 99.7 Wind Direction lOm - Backup 99.9 Wind Direction lOm - Downriver 100.0 Temperature lOin-Primary 99.0 Dew Point lOmn-Primary 98.9 Delta Temperature 60m-Primary . 99.1 Sigma Theta 10m-Primary 99.7 Sigma Theta 60m - Primary 99.7.
Sigma Theta lOm- Backup 99.9
-Sigma Theta lOm - Downriver 100.0 Precipitation - Primary 100.0 Composite Parameters Wind Speed and Direction lOm, 99.0 Delta Temperature 60-1Om Wind Speed and Direction 60m, 98.6 Delta TeMpuature 60-10m .
(')SSES -Primary" meteorological tower (2)SSES `BackupW 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, 2003 through December 31, 2003 SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 1 2 5 1 0 0 9 NM 1 .7 6 0 0 0 14 NE 0 7 6 0 0 0 13 ENE . 3 3 0 0 0 0 6 E 8 2 0 0 0 0 10 ESE . 0 *3 1 0 0 0 4 SE
- 2 4 7 0 0. 0 13 SSE . 5 10 .5. 0 0 0 20
-S. 2 20 11 0 0 0 33
'SSW.- - 9 '39 12 0 0 0 60 SW 8 47 33 1 0.- 0 *89 WSW 3 18 24 2 0 0 47 W 1 6 6 0 0 0 13 WNW 0 6 1 0 0 0 7 NW 0 0 *6 0 0 .0 6 NNW 1 0 7 2 0 0 10 TOTAL 44 174 130 6 0 0 354 PERIODS OF CALM(HOURS).: 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 34
- TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 STABILITY CLASS: B 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 0 4 0 0 0 4
-NNE 1. 5 2 0 0 0 8 NE . 0 5 4 .0 0 0 9 ENE 3 2 0 0 0 0 5 E 1 2 2 0 0 0 5 ESE 2 1 0 0 0 0 3 SE 1 3 2 0 0 0 6 SSE 1 3 1 0 0 0 5 S .
- 2 2 3 0 0 0 7 S W -5 5 1 0 0. 0 11 SW 1 14 17 1 *0 0 33 WSW 1 7 10 3 0 0 21 W -w . 0 2. 3.0< 0 0 5
.WNW 0 1 6 0 0.. 0 7 NW 0 1 5 0 0 0 6 NNW 0 6 5 1 0 0 12 TOTAL. 18 59 65 5 0 0 147
- PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 3-5
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES
- HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 STABILITY CLASS: C 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 6 8 0 0 .0 14 NNE 2 11 3 1 0 0 17 NE 2 9 .3 0 0 0 14 ENE 6 0 1 0 0 0 7 E 4 2 1 0 0 0 7 ESE 5 3 1 0 0 0 9 SE 6 6 2 0 0 0 14 SSE 2 5 4 o 0 0 11 S 10 5 3 0 0 0 18 SSW 4 12 1 0 .0 0 17 SW 4 25 28 2 :0. 0 59 WSW 0 6 17. 4 0 0 27 1 2 3 5 0 0 11 WNW 0 2 6 1 .0 0 9 NW 0 2 6 0 0... 0 NNW 0 0 6 2 0 0 8 TOTAL 46 96 93 is 0 0 250 PERIODS OF CALM(HOURS): 0.
VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 3-6
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 03010101-03123124 STABILITY CLASS: D 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 23 115 67 4 0 0 209 NNE 95 181 50 1 0 0 327 NE 126 167 26 0 0 0 319 ENE 90 57 10 3 0 0 160 E . 104 37 14 0 0 0 155 ESE 97 67 13 0 0 0 177 SE 94 114 29 2 0 0 239 SSE 70 70 16 2 0 0 158 S 101 84 19 0 0 0 204
- SSW .
- 83 136 21 1 0 0 241 SW i50 246 209 13 1.. 0 519 WSW 28 100 149 62 12 0 351 1W 5 57 90 26 7 0 195
-WNW 9 47 52 29 1 0 138 NW .11 60 103 20 2.. 0 196 NNW 9 60 142 13 0 0 224 TOTAL 1005 1598 1010 176 23 0 3812 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 3-7
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:16M 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 29 55 12 0 0. 0 96 NNE 127 117 13 0 0 0 257 NE 244 84 12 0 0 0 340 ENE 289 26 1 3 0 0 319 7E 190 16 4 0 0 0 210 ESE 132 20 7 3 0 0 162 SE 170 30 7 7 0 0 214 SSE 119 45 15 1 0 0 180 S - 140 68 12 0 0 0 220 SSW . .103 120 9 0 .0 0 232 SW 39 89 27 2 0 0 157 WSW. 20 46 18 6. 0 0 90
- -w ,* 9 19 3 0 0 0 31 WNW 7 14 4 0 0 0 25 NW . 6 23 2 1 0 0 32 NNW 7 34 4 1 0 0 46 TOTAL 1631 806 150 24 0 0 2611 PERIODS OF CALM(HOURS): 0
- VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 3-8
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 *0 0 0 0 0 7 NNE 27 7 1 0 0 0 35 HE 140 9 °0 0 0°. 0 149 ENE 407 6 0 0 .0 0 413 E . 140 0 0 0 0 0 140 ESE 62 0 0 0 0 0 62 SE 38 0 0 0 0 0 38 SSE 27 1 0 0 0 0 28 S 38 3 0 0 0 0 41
- SSW 22 9 0 0 0 0 31
- SW 6 8 0 0 0. 0 14
. WSW . 1 2 0 0 0 0 3 w - . 3 0 0 0 0 0 3
-WNW 0 0 0 0 0 0 0 NW . 0 1 0 0 0 0 1 NNW 1 1 0 0 0 0 2 TOTAL 919 47 1 0 0 0 967 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 3-9
TABLE 3-2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 1 0 0 0 0 NNE .9 0 9 0 0 0 NE 103 4 0 0 107 0 0 ENE 309 8 0 317 0 0 0 E 57 0 0 57 0 0 0 ESE 14 0 0 0 14 0 0 SE 13 1 0 0 14 0 _ 0 SSE 9 0 0 _ 9 0 0 0 S 6 0 0 0 6 0 0 0 SSW . . 1 0 0 .0 1 0 0 SW . 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W .0 0 0 0 0 0
WNW -. 0 0 0 0 0 0 0
NW 0 0 0 0 . 0 0 0 NNW 0 0 0 0 TOTAL
- 522 13 0 0 0 0 535 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 3-10
TABLE 3:2 (continued)
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION
'PERIOD OF RECORD = 03010101-03123124 STABILITY CLASS: ALL 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 61 178 96 5 0 .0 340 NNE 262 328 75 2 0 0 667 NE 615 285 51 0 0 0 951 ENE 1107 102 12. 6 0 0 1227 E 504 59 21. 0 0 0 584
-ESE 312 94 22 3 0 0 431 SE 324 158 47 9 0 0 538 SSE 233 134 41 3 0 0 411 S 299 182 48 0 0 0 529
- SW 227 321 44 1 0 0 593
- 108 429 314 19 1 0 871 WSW 53 179 218 77 12 0 539
. 29 86 105 31 7 0 258
-WNW - 16 70 69 30 1 0 186 NW 17 87 122 21 2 0 249 NNW 18 101 164 19 0 0 302
- TOTAL
- 4185 2793 1449 226 23 0 8676 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 84 3-11
TABLE 3-3 Table 3. SSES Joint Frequency Distribution of Wind Speed and Direction 60m Versus Delta Temperature 60-10m for the Period of January 1,2003 through December 31, 2003 SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 0 0 6 1 0 0 7
-NNE 0 1 16 2 0 0 19 NE 3 9 4 1 0 0 17 ENE 3 0 0 0 0 0 3 0 1 0 0 0 0 1
- ESE . 3 3 1 0 0 0 7.
SE ,0 4 7 2 0. 0 13 SSE 2 5 3 1 0 0 11
- 7 12 10 .5 0 0 34
-SSW 4 28 15 9 1 0 57 SW 5 29 40 18 1. 0 93 WSW 2 14 21 24 2 0 63 w . 1 3 2 4 0 0 10 WNW 0 1 3 1 0 0 5 NW 1 0 3 2 0 0 6 NNW 0 0 3 5 0 0 8 TOTAL 31 110 134 75 4 0 354 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 120 3-12
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES
- HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 0 1 3 1 0 .0 5 NNE 0 1 4 3 0 0 8 NE 2 6 4 1 0 0 13 ENE 0 1 0 0 0 0 1 E1 1 1 1 0 0 4
. ESE 0 3 0 0 0 0 3 SE 2 3 .2 1 0 0 8 SSE 0 2 0 0 0 .0 2
- *2 0 3 1 0 0 6 SSW . . 2 4 1 3 1 0 11 SW 2 3 13 10 0 0 28 WSW 0 1 11 13 4 0 29 by-> w * . 0 0 6 4 0 0 10
-. 0 1 2 1 0 0 4 NW 0 2 5. 1 0 0 8 NNW 0 1 4 2 0 0 7 TOTAL 11 30 59 42 5 0 147 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION . 0 HOURS OF MISSING DATA: 120 3-13
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 03010101-03123124 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 0 3 4 3 0 0 10 NNE 3 6 11 1 1 0 22 NE 3. 5 5 2 0 0 15 ENE 2 2 2 0 0 0 6 4 4 1 0 0 0 9 ESE 0 1 1 1 0 0 3 SE 3 6 3 1 0 0 13 SSE 2 2 3 2 0 0 9 S 2 2 3 3 0 0 10 SSW .8 8 3 0 1. 0 20 SW 2 13 21 10 1 . 0 47 WSW 0 3 20 21 3 0 47
. 1 1 7 7 2.0 18 WNW - . 0 1 2 .3 0 0 6 NW 0 0 4 3 0 07 NNW 0 0 5 2 1 0 8
- TOTAL 30 57 95 59 9 0 250 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 120 3-14
TABLE 3-(continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 12 53 87 20 0 0 172 NNE 66. 111 140 37 2 0 356 NE - 86 110 110 27 1 0 334 ENE 44 54 36 4 1 2 141
- E . 31 48 16 12 3 0 110
- ESE. :33 44 48 4 0. 0 129 SE 34 55 54 .11 2 1 157
- WSW . - 13 85 175 240 53 18 584 w - . 7 34 87 .88 25 10 251
- WNW . 5 31 57 55. 19- 0 167 NW 4 23 97 57 1 1 183
- NNW - 11 33 100 62 2 0 208
- TOTAL . 543 1034 1321 747 122 .34 3801 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 120 3-15
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 24 67 21 1 0 0 113 NNE 107 219 65 22 0 0 413 NE 127 95 62 12 1 0 298' ENE 65 63 17 0 1 2 148 E 64 41 11 5 0 1 122 ESE 45 25 15 7 2 1 95 SE 56 39 21 7 4 3 130 SSE 56 56 38 10 2 1 163 S 56 68 35 17 7 0 183 SSW .64 66 72 20 3 0 225 SW 48 125 87 21 3. 0 284 WSW 20 61 102 51 5 0 239
.. 5 17 21 9 2 1 55 WNW - . 2 22
- 12 0 0 0 36 NW . 4 10 39 3 0... 0 056 NNW 6 17 21 1 0 0 45 TOTAL 749 991 639 186 30 9 2605 PERIODS OF CALM(HOURS): 1
- VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 120 3-16
TABLE 3-3 (continued)
K>
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 03010101-03123124 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 13 55 0 0 0 0 68 NNE 78 209 5 0 0 0 292 NE 96 52 7 0 0 0 155 ENE 48 11 0 0 0 0 59 E 38 4 0 0 0 0 42 ESE 34 0 0 0 0 0 34 SE 39 3 1 0 0 0 43 SSE 21 11 2 0 0 0 34 S 27 13 2 0 0 0 42 SSW . 14 28 13 0 0 0 .55 SW' 14 35 15 1 0 0 65 WSW 2 9 33. 5 0 0 49 w . 2 2 0 0 0 0 4 WNW . 3 3 0 0 0 0 6 NW 0 3 0 1 0 0 .4 NNW 1 4 0 0 0 0 5 TOTAL 430 442 78 7 0 0 957 PERIODS OF CALM(HOURS): 1*.
VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 120 3-17
TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 03010101-03123124 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 15 49 0 0 0 0 64 NNE 40 106 2 0 0 0 148 NE 42 47 0 0 0 0 89 ENE 28 13 0 0 0 0 41 E 17 2 0 0 0 0 19 ESE 17 4 1 0 0 0 22 SE. 15 2 0 0 0 0 17 SSE 16 3 0 0 0 0 19 S 15 14 3 0 0 0 32 SSW 12 16 8 1 0 0 37 SW 3 21 3 0 0. 0 27
.. -" WSW 0 0 .4 . 0 0 0 4
- .. W. , ' 1 0 0 0 0 0 1 WNW_ 1 0 1 0 0 0 2 NW 1 1 0 0 0 0 2 NNW 2 0 0 0 0 0 2 TOTAL 225 278 22 1 0 0 526 PERIODS OF CALM(HOURS): 2 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 120 3-18
- TABLE 3-3 (continued)
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 03010101-03123124 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 64 228 121 26 0 0 439 NNE 294 653 243 65 3 0 1258 NE 359 324 192 43 2 0 921 ENE 190 144 55 4 2 4 399 E 155 101 29 18 3 1 307 ESE 132 80 66 12 2 1 293 SE 149 112 88 22 6 4 381 SSE 135 128 97 35 3 3 401
- S 162 149 96 46 9 0 462 SSW .163 245 162 58 11 0 639 SW 121 395 352 123 10 0 1001 WSW . 37 173 366 354. 67 18 1015
. - W . 17 57 123 112 29 11 349
- *NW 11 59 77 60. 19 0 226 NW 10 39 148 67 1. 1 266
- NNW. 20 55 133 72 3 0 283
- TOTAL - 2019 2942 2348 1117 170 43 8640
- PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 120 3-19
( . =A.LE 3-4 ('..
2003 SSES ANNUAL RELATIVE CONCENTRATIONS NO DECAY, UNDEPLETED X/Q (sec/m 3)
DATES OF LAST X/Q ACCUMULATION ARE FROM 3 1 1 1 0 TO, '3123124 0 X/Q ACCUMULATION FOR GROUND AVERAGE SEC/M3 FOR RELEASE POINT 1 0.5-1 1-2 2-3 -- 3-4 . A-_ _W-p 6I tn _o
.aV-AU AU-a~u ensn SU-40 , ^ PX 40-50
- DIRECTION FROM N 3.2435E-06 6.3244E-07 2.6332E-07 1.3842E-07 8.8935E-08 3.2978E-08 9.0140E-09 4.3560E-09 2.7352E-09 1.9308E-09
- DIRECTION FROM NNE 8.7684E-06 1.7997E-06 8.0303E-07 4.2928E-07 2.7717E-07 1.0282E-07 2.8114E-08 1.3777E-08 8.7280E-09 6.2252E-09
- DIRECTION FROM NE 2.0428E-05 3.8436E-06 1.7466E-06 9.9371E-07 6.5969E-07 2.6161E-07 7.9521E-08 4.0052E-08 2.5772E-08 1.8753E-08
- DIRECTION FROM ENE 4.2878E-05 ' 7.9928E-06 3.8724E-06 2.2896E-06 1.5302E-06 6.0628E-07 1.7630E-07 8.5725E-08 5.5585E-08 4.0806E-08
- DIRECTION FROM E 1.8535E-05. 3.4300E-06 1.5019E-06 8.4370E-07 5.6288E-07 2.2811E-07 7.1684E-08 3.6208E-08 2.3359E-08 1.6991E-08
- DIRECTION FROM ESE 1.1657E-05 2.3011E-06 1.0372E-06 5.7616E-07 3.8111E-07 1.5277E-07 4.1948E-08 1.8354E-08 1.1760E-08 8.4772E-09
- DIRECTION FROM SE 1.3991E-05 2.8164E-06 1.2800E-06 7.1796E-07 4.7575E-07 1.9377E-07 4.8199E-08 1.7741E-08 1.1315E-08 8.1284E-09
- DIRECTION FROM SSE 8.7706E-06 1.7421E-06 7.6972E-07 4.3004E-07 2.8893E-07 1.2443E-07. 3.2494E-08 1.1591E-08 7.3841E-09 5.2971E-09
- DIRECTION FROM S 7.2101E-06 1.5361E-06 7.4824E-07 4.3415E-07 2.9754E-07 1.3782E-07 3.8075E-08 1.3089E-08 8.3354E-09 5.9694E-09
- DIRECTION FROM SSW 7.6272E-06 1.5610E-06 7.2096E-07 4.0846E-07 2.7074E-07 1.1224E-07 2.9157E-08 1.1086E-08 7.0346E-09 5.0144E-09
- DIRECTION FROM SW 5.8188E-06 1.1886E-06 5.6211E-07 3.2062E-07 2.1397E-07 9.2779E-08 2.3519E-08 7.8088E-09 4.8838E-09 3.4285E-09
- DIRECTION FROM WSW 3.5834E-06 7 .1444E-07 3.3459E-07 1.9700E-07 1.3522E-07 6.4288E-08 2.0242E-08 7.5995E-09 3.8885E-09 2.1267E-09
- DIRECTION FROM W 1.6492E-06 3.1777E-07 1.3898E-07 7.6803E-08 5.'0518E-08 2.0777E-08 5.6769E-09 2.3127E-09 1.4425E-09 1.0095E-09
- DIRECTION FROM WNW 1.2047E-06 2.2383E-07 8.9733E-08 4.6898E-08 2.9936E-08 1.1065E-08 3.0076E-09 1.4226E-09 8.8011E-10 6.1142E-10
- DIRECTION FROM NW 6.5792E-08 4.1726E-08 1.5045E-08 3.9464E-09 1.8574E-09 1.1443E-09 7.9152E-10 1.7204E-06 3.245SE-07 1.2936E-07
- DIRECTION FROM NNW 5.6126E-08 1.9628E-08 4.9080E-09 2.3339E-09 1.4486E-09 1.0095E-09 2.0586E-06 3.9538E-07 1.6735E-07 8.8919E-08 3-20
(' (.
. TABLE 3-5 2003 SSES ANNUAL RELATIVE CONCENTRATIONS 2.26-DAY DECAY, UNDEPLETED X/Q (sec/r 3 )
DATES OF LAST X/Q ACCUMULATION ARE FROM 3 1 1 1 0 TO. 3123124 0 X/Q ACCUMULATION FOR GROUND DECAYED S.AVG SEC/M3 FOR RELEASE POINT 1 MItza 0.5-1 L-2 2-3 3-4 * .4-5 5-10 10-20 20-30 30-40 40-50
- DIRECTION FROM N 3.2378E-06 6.2907E-07 2.6097E-07 1.3668E-07 8.7492E-08 3.2082E-08 8.5240E-09 3.9669E-09 2.3989E-09 1.6308E-09
- DIRECTION FROM NNE 8.7486E-06 1.7876E-06 7.9398E-07 4.2248E-07 2.7151E-07 9.9327E-08 2.6223E-08 1.2266E-08 7.4184E-09 5.0510E-09
- DIRECTION FROM NE 2.0368E-05 3.8102E-06 1.7212E-06 9.7341E-07 6.4237E-07 2.5022E-07 7.2714E-08 3.4499E-08 2.0915E-08 1.4340E-08
- DIRECTION FROM ENE 4.2744E-05 *7.9174E-06 3.8117E-06 2.2396E-06 1.4874E-06 5.7835E-07 1.6047E-07 7.3308E-08 4.4670E-08 3.0830E-08
- DIRECTION FROM E 1.8463E-05 3.3906E-06 1.4732E-06 8.2117E-07 5.4361E-07 2.1524E-07 6.3812E-08 2.9831E-08 1.7817E-08 1.2001E-08
- DIRECTION FROM ESE 1.1615E-05 2.2765E-06 1.0186E-06 5.6171E-07 3.6884E-07 1.4462E-07 3.7570E-08 1.5271E-08 9.0916E-09 6.0898E-09
- DIRECTION FROM SE 1.3945E-05 2.7881E-06 1.2585E-06 7.0104E-07 4.6133E-07 1.8401E-07 4.3431E-08 1.4910E-08 8.8711E-09 5.9454E-09
- DIRECTION FROM SSE 8.7455E-06 1.7271E-06 7.5871E-07 4.2142E-07 2.8150E-07 1.1912E-07 2.9770E-08 1.0019E-08 6.0236E-09 4.0785E-09
- DIRECTION FROM S 7.1917E-06 1.5244E-06 7.3873E-07 4.2641E-07 2.9072E-07 1.3257E-07 3.5222E-08 1.1496E-08 6.9522E-09 4.7285E-09
- DIRECTION FROM SSW 7.6106E-06 1.5507E-06 7.1307E-07 4.0219E-07 2.6540E-07 1.0857E-07 2.7273E-08 9.9182E-09 6.0214E-09 4.1072E-09
- DIRECTION FROM SW 5.8100E-06 1.1832E-06 5.5781E-07 3.1718E-07 2.1101E-07 9.0644E-08 2.2444E-08 7.2235E-09 4.3802E-09 2.9815E-09
- DIRECTION FROM WSW 3.5781E-06 7.1122E-07 3.3206E-07 1.9491E-07 1.3337E-07 6.2813E-08 1.9314E-08 7.0264E-09 3.4846E-09 1.8471E-09
- DIRECTION FROM W 7.5769E-08 4.9637E-08 2.0165E-08 5.3376E-09 2.0845E-09 1.2465E-09 8.3614E-10 1.6462E-06 3.1601E-07 1.3766E-07
- DIRECTION FROM WNW 1.2030E-06 2.2284E-07 8.9074E-08 4.6416E-08 2.9539E-08 1.0818E-08 2.8735E-09 1.3181E-09 7.9091E-10 5.3281E-10
- DIRECTION FROM NW 1.2843E-07 6.5132E-08 4.1188E-08 1.4722E-08. 3.7783E-09 1.7278E-09 1.0346E-09 6.9560E-10 1.7179E-06 3.2315E-07
- DIRECTION FROM NNW 1.9212E-08 4.6985E-09 2.1693E-09 1.3072E-09 8.8434E-10 2.0558E-06 3.9375E-07 1.6619E-07 8.8052E-08 5.5419E-08 3-21
,ILLE.
(¢ 2003 SSES ANNUAL RELATIVE CONCENTRATIONS 8-DAY DECAY, DEPLETED X/Q (sec/r 3 )
DATES OF LAST X/Q ACCUMULATION ARE FROM 3 1 1 1 0 TO 3123124 0 X/Q ACCUMULATION FOR DECAYED DEPLETION SEC/M3 '
FOR RELEASE POINT 1 MILES 0.5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 I
- DIRECTION IFROM N 2.9634E-06 5.3573E-07 2.1298E-07 1.0725E-07 6.6628E-08 2.2944E-08 5.5573E-09 2.3443E-09 1.3194E-09 8.4528E-10
- DIRECTION IFROM NNE 8.0102E-06 1.5239E-06 6.4908E-07 3.3231E-07 2.0740E-07 7.1394E-08 1.7266E-08 7.3674E-09 4.1732E-09 2.6947E-09
- DIRECTIONI FROM NE 1.8658E-05 3.2527E-06 1.4104E-06 7.6823E-07 4.9280E-07 1. 8115E-07 4.8565E-08 2.1219E-08 1.2163E-08 7.9833E-09
- DIRECTION FROM ENE 3.9160E-05 6.7626E-06 3.1261E-06 1.7693E-06 1.1425E-06 4.1950E-07 1.0753E-07 4.5327E-08 2.6165E-08 1.7316E-08
- DIRECTION FROM *E 1.6924E-05 2.9004E-06 1.2113E-06 6.5108E-07 4.1950E-07 1.5735E-07 4.3449E-08 1.8944E-08 1.0834E-08 7.0738E-09
- DIRECTION FROM ESE 1.0645E-05 1.9463E-06 8.3674E-07 4.4483E-07 2.8421E-07 1.0547E-07 2.5468E-08 9.6290E-09 5.4744E-09 3.5453E-09
- DIRECTION FROM SE 1.2778E-05 2.3825E-06 1.0330E-06 5.5455E-07 3.5498E-07 1.3390E-07 2.9313E-08 9.3327E-09 5.2870E-09 3.4157E-09
- DIRECTION FROM SSE 8.0108E-06 1.4743E-06 6.2162E-07 3.3250E-07 2.:1587E-07 8.6183E-08 1.9855E-08 6.1468E-09 3.4898E-09 2.2591E-09
- DIRECTION FROM S 6.5861E-06 1.3004E-06 6.0455E-07 3.3589E-07 2.2248E-07 9.5582E-08 2.3329E-08 6.9728E-09 3.9644E-09 2.5666E-09
- DIRECTION FROM SSW 6.9679E-06 1.3218E-06 5.8280E-07 3.1624E-07 2.0263E-07 7.7966E-08 1.7921E-08 5.9364E-09 3.3703E-09 2.1765E-09
- DIRECTION FROM SW 5.3168E-06 1.0071E-06 4.5482E-07 2.4856E-07 1.6041E-07 6.4629E-08 1.4538E-08 4.2213E-09 2.3711E-09 1.5137E-09
- DIRECTION FROM WSW 3.2742E-06 6.0533E-07 2.7073E-07 1.5273E-07 1.0138E-07 4.47835-08 1.2511E-08 4.1073E-09 1.8871E-09 9.3839E-10
- DIRECTION FROM W 2.6916E-07 1.1239E-07 5.9494E-08 3.7833E-08 1.4445E-08 3.4938E-09 1.2405E-09 6.9240E-10 4.3894E-10 1.5068E-06
- DIRECTION FROM WNW 7.2612E-08 3.6362E-08 2.2446E-08 7.7094E-09 1.8597E-09 7.6936E-10 4.2i51E-10 2.7008E-10 1.1008E-06 1.8965E-07
- DIRECTION FROM NW 3.1290E-08 1.0485E-08 2.4415E-09 1.0056E-09 5.5673E-10 3.5041E-10 1.5720E-06 2.7500E-07 1.0468E-07 5.1015E-08
- DIRECTION FROM NNW 4.2092E-08 1.3680E-08 3.0364E-09 1.2633E-09 7.0440E-10 4.4652E-10 1.8810E-06 3.3503E-07 1.3543E-07 6.8953E-08 3-22
. I
Is -
-TABLE 3-7
(, ,
2003 SSES ANNUAL RELATIVE DEPOSITION (D/Q meters 2)
DATES OF LAST X/Q ACCUMULATION ARE FROM 3 1 1 1 0 TO. 3123124 0 X/Q ACCUMULATION FOR DEPOSITION 1/M2 FUO RELEASE POINT 1 mlzs~
0.5-1 1-2 2-3-, Is A
. AE
. 5-l . 10-20 20-30 30-40 40-50
_-_J--a
- DIRECTION FROM N 1.9596E-08 2.8873E-09 1.1842E-09 5.6127E-10 3.3170E-10 1.0512E-10 2.5148E-11 9.2592E-12 4.9420E-12 3.1047E-12
- DIRECTION FROM NNE 3.6152E-08 5.6016E-09 2.4296E-09 1.1556E-09 6.8025E-10 2.1196E-10 4.9409E-11 1. 8192E-11 9.7095E-12 6.0999E-12
- DIRECTION FROM NE 4.8125E-08 7.2586E-09 3.1037E-09 1.5022E-09 8.9119E-10 2.8708E-10 7.0342E-11 2.5898E-11 1.3823E-11 8.6842E-12
- DIRECTION FROM ENE 6.6118E-08 '1.0267E-08 4.5720E-09 2.2368E-09 1.3215E-09 4.1819E-10 9.5297E-11 3.3415E-11 1.7835E-11 1.1205E-11
- DIRECTION.FROM E 3.0512E-08 4.4570E-09 1.8159E-09 8.6704E-10 5.1732E-10 1.7060E-10 4.3196E-1l 1.5904E-11 8.4885E-12 5.3328E-12
- DIRECTION FROM ESE 2.5951E-08 3.9228E-09 1.6725E-09 8.0747E-10 4.8243E-10 1.5997E-10 3.6345E-11 1.1737E-11 6.2647E-12 3.9357E-12
- DIRECTION FROM SE 3.8696E-08 5.8800E-09 2.5681E-09 1.2682E-09 7.6125E-10 2.5722E-10 5.3531E-11 1.4651E-11 7.8199E-12 4.9128E-12
- DIRECTION FROM SSE 2.8021E-08 4.1825E-09 1.7817E-09 8.7978E-10 5.3619E-10 1.9196E-10 4 .2111E-1l 1.1193E-11 5.9740E-12 3.7531E-12
- DIRECTION FROM S 2.5779E-08 4.1330E-09 1.9410E-09 9.9750E-10 6.2169E-10 2.4062E-10 5.6159E-11 1.4406E-11 7.6891E-12 4.8306E-12
- DIRECTION FROM SSW 3.4733E-08 5.3125E-09 2.3828E-09 1.2062E-09 7.3010E-10 2.5474E-10 5.6589E-11 1.6149E-11 8.6193E-12 5.4150E-12
- "DIRECTION FROM SW 4.5914E-08 7.2886E-09 3.4292E-09 1.7743E-09 1.0964E-09 4.1216E-10 9.3111E-11 2.3720E-11 1.2660E-11 7.9536E-12
- DIRECTION FROM WSW 3.2454E-08 5.0027E-09 2.3364E-09 1.2508E-09 7.9528E-10 3.2798E-10 9.2301E-11 2.6669E-11 1.167SE-11 5.7274E-12
- DIRECTION FROM W 1.3046E-08 1.9582E-09 8.4734E-10 4.2282E-10 2.5770E-10 9.2259E-11 2.2512E-11 7.0533E-12 3.7646E-12 2.3651E-12
- DIRECTION FROM WNW 1.0415E-08 1.5028E-09 6; 0552E-10 2.8939E-10 1.7192E-10 5.5695E-11 1.3758E-11 5.0653E-12. 2.7036E-12 1.6985E-12
- DIRECTION FROM NW 1.4993E-08 2.1948E-09 8.7938E-10 4.0908E-10 2.4186E-10 7.6784E-11 1.8417E-11 6.7810E-12 3.6193E-12 2.2738E-12
- DIRECTION FROM NNW 1.8325E-08 2.7215E-09 1.1498E-09 5.5588E-10 .3.2561E-10 9.9258E-11 2.2338E-11 8.2243E-12 4.3896E-12 2.7577E-12 3-23
. I
TABLE 3-8 2003 ATMOSPHERIC DISPERSION ESTIMATES FOR RETDAS INPUT AT SELECTED LOCATIONS LOCATION F-.MILES I I AFFECTED AFETED LOCAT1ON SECTOR SNLES X/Q DEC(2 I x/QDEC+DEP3) I DE~srN4)
I /SW Maximum (OUQ)Site Boundary 0.6 1.44E-05 1.43E-05 1.29E-05 3.25E-08 9/S Closest (XQ) Site Boundary 038 4.58E-06 4.58E-06 4.26E-06 2.97E-08 12/WSW Maximum (XIQ) Residence 1.1 1.27E-05 1.26E-05 1.IOE-05 1.72E-08 15/NW Maximum (D/Q) Residence 0.8 7.59E-06 7.54E-06 6.71E-06 1.86E-08 12/WSW Maximum (D/Q) Garden 1.1 1.27E-05 126E-05 1.lOE-O5 1.72E-08 12tWSW Maximum (DIQ) Dairy 1.7 6.75E-06 6.68E-06 5.65E-06 8.50E-09 121WSW Maximum (D/Q) Meat Producer 1.7 6.75E-06 6.68E-06 5.65E-06 8.50E-09 31NE Riverlands / EIC 0.7 3.63E-06 3.62E-06 3.24E-06 2.65E-08 121WSW Tower's Club 0.5 3.39E-05 338E-05 3.09E-05 5.22E408 5/E East Gate 0.5 1.78E-06 1.78E-06 1.63E-06 1.41E-08 NEAREST RESIDENCE WITHIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES X/Q DEC XDQ DEP0SFON NTJMBER SECTOR ______ ___XQDEC+DEP 1 N H.Burd 13 1.86E-06 1.85E-06 1.59E-06 5.20E-09 2 NNE E.Ashbridge Iml I 2.80E-06 2.79E-06 2.44E-06 1.06E-08 3
- NE W.Tuggle 0.9 2.52E-06 2-52E-06 2.22E-06 1.74E-08 4 ENE D.Barberi 2.1 432E-07 4.29E-07 3.55E-07 3.02E-09
. E LKozlowski IA 3.50E-07 3A.E-07 2.98E.07 2.19E-09 6 ESE R.Panetta 0.5 I.30E-06 I.30E-06 1.19E-06 1.12E-08 7 SE l.Futoma 0.5 1.62E-06 I.62E-06 1.48E-06 I.42E-08 8 SSE J.Naunczek 0.6 1.64E-06 1.64E-06 1.48E-06 1.40E-08 9
- S S.Slusser I 1.18E-06 I.18E-06 I.03E-06 5.99E-09 10 . SSW S.Molnar 0.9 3.86E-06 3.84E-06 339E-06 1.37E-08 11 SW F.Michael 1.5 3.87E-06 3.83E-06 3.27E-06 7.30E-09 12 WW.Kisner 1.1 1u27e-05 .26E-0S I.1E-05 1.72E . 13 .W IE.SeelyJP. Hurnmel 1.2 4.90E3-06 4.8SE406 4.21E-06 6.68E-O9-14 R.Orlando 0.8 6.24E-06 6.19E-06 5.51E-06 1.24E48 15 NW LHidlay 0.8 7.59E-06 7.54E-06 6.71E-06 1.86E-08 16 NNW W.Meezler 0.6 5.85E-06 5.83E-06 5.28E-06 1.78E-08 NEAREST GARDEN WITHIN A 5-MILE RADIUS OF SSES BY SECTOR MSECTOR AFECTED NAME MILES X/Q XIQ DEC XrQ DEPOSMONI NUMBER SECTOR ______ ___________DEC+DEP I N J.Wojcik 32 4.93E-07 4.85E-07 3.86E-07 1.17E-09 2 NNE R.Cbapin 2.3 8.40E-07 8.32E-07 6.84E-07 2.79E-09 3 NE Yokum 2.7 5.05E-07 5.OIE-07 4.05E-07 3.01E-09 4 ENE G.Dennis 2A 3.60E-07 3.58E-07 2.93E-07 2.52E-09 S E W.Daily 1.8 2.36E-07 2.35E-07 1.97E-07 1.45E-09 6 ESE LTravelpiece 2.5 8.94E-08 8.87E-08 7.23E-08 6.03E-10 7 SE F.Scholl 0.6 1.25E-06 1.24E-06 1.12E-06 1.04E-08 8 SSE D.Dawson 1.5 3.84E-07 3.83E-07 3.26E-07 2.65E-09 9 S I M.Cope 1.1 1.02E-06 1.02E-06 8.83E-07 5.04E-09 10 SSW S.Bodnar 1.2 2.50E-06 2.49E-06 2.15E-06 8.24E-09 11 SW HSchultz 1.9 2.71E-06 2.68E406 225E-06 4.98E-09 12 WSW W.Kisner 1.1 1.27E-05 1.26E-05 1.10D-OS 1.72E-08 13 W F.Hunmmel 1.2 4.90E-06 4.85E-06 4.21E-06 6.68E-09 14 WNW _ None -_I _ I I_
15 NW D.Goff 1.8 2.16E-06 2.13E-06 .1.80E-06 4.44E-09 16 NNW P.Culver 4 3.40E-07 3.32E-07 2:58E-07 6.60EB1O 3-24
TABLE 3-8 (continued)
NEAREST ANIMAL RAISED FOR MEAT CONSUMPTION
. WITEIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSMON NumzER SECTOR___ DEC+DEP 2 NNE R.Chapin 2.3 8.40E-07 8.32E-07 6.84E-07 2.79E-09 4 ENE G.Dennis 2.4 3.60E-07 3.58E-07 2.93E-07 2.52E.09 5 E
- K. KozlowskilW.Wims 1.4 3.50E-07 3.48E-07 2.98E-07 2.19E-09 10 SSW R. & C. Ryman 3 5.66E-07 5.58E-07 4.47E-07 1.61E-09 10 SSW C.K.Drasher 3.5 3.97E-07 3.91E-07 3.07E-07 1.07E-09 12 WSW T. & M. BEger 1.7 6.75E-06 6.68E.06 5.65E-06 8.50E-09 15 NW D.Goff 1.8 2.16E-06 2.13E-06 1.80E-06 4.44E.09 AILL DAIRY LOCATIONS NEAR SSES SECTOR AFECTED NAME M MLES XlQ XIQ DEC X/Q DEPOSMON NUMBER SECTOR ___ DEC+DEP 5 E W.Bloss 4.5 4.97E-08 4.88E-08 3.72E.08 2.53E-10 6 ESE D.Moyer 2.7 7.70E-08 7.64E-08 6.17E-08 S.09E-10 ESE F.Rinehimer 4.2 3.09E-08 3.05E-08 2.34E.08 1.81E-10 10 SSW R. & C. Ryman 3 5.66E-07 5.58E-07 4.47E.07 1.61E-09 SSW R.Ryman 3.1 5.26E-07 5.19EW07 4.14E-07 1.48E09W SSW C.K.Draser 3.5 3.97E-07 3.91E47 3.07E407 1.07E;09 SSW K.Davis 14.01 3.20E-08 2.99E-08 1.99E-08 S.70E-11 12 WSW T. & M. Berger 1.7 6.75E-06 6.68E-06 5.65E.06 8.50E-09 13 W J. & N. Dent 5 4.38E-07 4.21E-07 3.21E-07 3.86E-10 16 - .NNW H.Shoeaker 4.2 3.18E-07 3.1IE-07 2.40EW07 6.07E-10
- 1. S/Q RtELATIVE CONCENTRATION (SEC/KI) 2 S/Q DEC DECAYED AND UNDEPLETED, HALF-LIFE 2.26 DAYS (SZC/M3)
.3 X/Q DEC+DEP DECAYED AND DEPLETED, HALF-LIFZ 8 DAYS (SECIle) 4 DEPOSITION RELATIVE DEPOSITION RATE (ane) 3-25
FIGURE 3-1 SSES 2003 ANNUAL WIND ROSE 10M LEVEL - PRIMARY TOWER 16%
WIND ROSE (WINDS FROM)
N
.1, 0.00% PERCENT CALMS (NOT INCLUDED INPLOT)
A WIND SPEED LIESS THAN 3.5 MPH
- WIND SPEED LESS TI-AN 7.5 MPH o WIND SPEED LESS THAN 12.5 MPH x WIND SPEED GREATERTHAN 12.5 MPH This wind rose displays the frequency of hourly average wind direction from a given sector. In 2003, the predominant wind direction occurred 14.1% of the time from the ENE sector. The average wind speed was 4.8 mph and the average wind speed for the predominant sector (ENE) was 2.6 mph. The sector with the highest average wind speed was WSW (8.6 mph.).
3-26
FIGURE 3-2 SSES 2003 ANNUAL WIND ROSE 60M LEVEL - PRIMARY TOWER
-'12 WIND ROSE CMNDS FROM)
N I\11/ --
10/ PERCENT CALMS
~~ TINCLUDED IN PLOT)
A WIND SPEED LESS THAN 3.5 MPH
- WIND SPEED LESS THAN 7.5 MPH o WIND SPEED LESS THAN 12.5 MPH x WIND SPEED GREATERTHAN 12.5 MPH This wind rose displays the frequency of hourly average wind direction from a given sector. In 2003,.the predominant wind direction occurred 14.6% of the time from the NNE sector. The average wind speed was 7.5 mph and the average wind speed for the predominant sector (NNE) was 5.9 mph. The sector with the highest average wind speed was W (11.9mph.).
3-27
FIGURE 3-3 SSES PASQUIL STABILITY CLASS PREVALENCES DATA Period: 2003 SSES Joint Frequency Distributions at 10 Meters Wind Speed and Direction IOM vs. Delta Temperature 60-IOM (Based on 8,676 Valid Hours)
A G 4.1% B 6.20/o
) /- 1.7%C ig;-2.9%
i .
E 1 D 30.1% 43.9 3-28
SECTION 4 I DOSE MEASUREMENTS AND ASSESSMENTS 4-1
Radiological Impact on Man Sampling and analysis of airborne and waterbome 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 waterbome 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 3.14E-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 1.17E0 mrem (CHILD, LUNG Table 4-4). The maximum organ/total body dose from liquid effluent is 4.99E-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 (1.21 EO mrem) is 4.8% of the 40CFR1 90 limit of 25 mrem to total body/organ (except thyroid) and 1.6% of the 40CFR1 90 limit of 75 rnrem to the thyroid.
- Doses to a maximally exposed member of the public from waterbome 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 2003 PARAMETER ETIRE YEARl Cooling Tower Blowdown (CFS) 17.2 Average Net River Level (ft.) 8.3 Dilution Factor at Danvillez') 936.1 Transit time to Danville (hr.)() 16.0
(')From ODCM-QA-005, Aft. E 4-2
Summaries of maximum individual doses resulting from airborne and waterbome 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 waterbome effluent to members of the public within the site boundary. There are no significant exposure pathways from waterbome 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 inTables 4-3 through 4-4.
SSES Technical Specification 5.5.4 requires that the Radioactive Effluent Release 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 XIQ value.
The above referenced locations are shown on Figure 4-1.
-Inthe 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 watetbome effluents inthis area. There are approximately 100,000 visitors to the Riverlands/lnformation 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: 1/1/03 TO 12131/03
_ _ DISTj AFFECTED_ _
.. _(MISECTOR Liquid(" Child Total Body 9A5E-4 . () 0.03 3 Liquid"~) Adult GI-LU 2.50E-3 (3) 0.03 10 Noble Gas' N/A Air Dose 2.21E-3 0.5 WSW 0.02 10
_ (marnma-MRAD)
Noble Gas(4) NIA Air Dose 321E-3 0.5 WSW 0.02 20 (Beta-MRAD) . _
Airborne Child . Lung 1.17EO 0.5 WSW 7.8 15 Tridum and Particulates (4) . . .
(')Estimated dose is based on a site total actrvity release equally divided between Unit I 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 waterbome 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: 1/1/03 TO 12131/03 "CLLECTMIp>VE,
.7
. .-.-. . - P~cABL~~ OSE RAT~- ns'
'EFFLU '.AGE GROUP.: RGAi -. (MR R) PERSON-REM)
Noble Gas N/A Total Body 2.70E-08 2.70E-06 Noble Gas N/A Skin 3.90E-08 3.90E-06
. Iodine, Tritium and Child Total Body 1.45E-05 1.45E-03 Particulates_
('Estimated dose and dose rate is based on annual site total activity release.
2)ColleciyVe dose is based on 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. Maxinun site boundary XIO Total (Ai) 4.98E101 (CHILD) 4.98E-01 (CHILD, LUNG) 4.98E 0I (CHILD)
- 2. MaximunX/Q Residence &
Maidmum D10 Garden Total (AID 4.38E01 (CHILD) 4.38E-01 (CHILD, LUNG) 4.38E01 (CHILD)
- 3. Maximum D/Q Dairy & Meat 4__Tower'sClub Total (A.D 2.33EM01 (CHILD) 2.33E-01 (CHILD, Gi-LL0) 2.33E-01 (CHlD)
- 4. Tower's Cau Total _ _ _ _ 1.17E 00 (CHILD) f.17E 00 (CHILD, LUNG) 1.17E 00 (CHILD)
- 5. Rvertand/EIC.
Gteo.0Gur s Total (All) 1.27E.01 (CHILD) 1.27E-01 (CHILD, G LLI) 127E-01 (CHILD)
- 6. Gate Nl 0 House _
CGuard Tota1________
(Ar 6.23E.02 (CHI1D) 6.24E-02 (CHILD, G1-LLI) 6.22E-02 (CH1LD)
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
FIGURE 4-1 AIRBORNE-DOSE CALCULATION LOCATIONS
- . 13-I./
Indicates airbome-dose calculation location 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)ind-ivdual procedures.
The following ODCM procedures were revised and effective on March 24, 2003 to add "Nuclear Emergency Planning" to the Recommended Reviews" section of each procedure:
ODCM-QA-001, ODCM-QA-002, ODCM-QA-004, ODCM-QA-005, ODCM-QA-006, ODCM-QA-008 ODCM-QA-003 was revised and effective on March 5, 2003. The revision provided more operational flexibility regarding effluent data retrieval in order to determine the compliance status of a gaseous effluent release.
ODCM-QA-007 was revised and effective on September 9, 2003. The revision removed any reference to the 'Primary Coolant Degasifier Filter Exhaust System",
based on PPL IOCFR50.59 evaluation E-01-22.
ODCM-QA-009 was revised and effective on March 18, 2003. The revision provides guidance regarding the identification of radionuclides in the Sewage Treatment Plant waste sludge and or liquid effluent. The revision provides clarification in order to evaluate the impact of non-SSES generated isotopes identified in the Sewage Treatment Plant sludge and liquid effluent, relative to regulatory compliance and the disposition of Sewage Treatment Plant sludge.
CHANGES TO THE TECHNICAL REQUIREMENTS MANUAL Section 3.11 and 3.6.1 of the SSES Unit-1 and Unit-2 Technical Requirements Manual (TRM) by reference are 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. Section 3.6.1 contains requirements for venting or purging of primary containment. The only change to Section 3.11 of the Unit-1 and Unit-2 TRM during 2003 was in the "Bases" section for TRO 3.11.2.5. The following text was removed from the Bases section for TRO 3.11.2.5: "The Radwaste Degasifier Exhaust System, including the following filters: 0F372, OF373 and OF374."
Based on PPL 10CFR50.59 Evaluation E-01-22, the Primary Coolant Degasifier Filter Exhaust System is no longer required to perform its intended function. There were no changes to the Unit-1 or Unit-2 TRM Section 3.6.1 during 2003.
5-2
PROCESS CONTROL PROGRAM CHANGES The following changes were made to the Process Control Program and implementing
- \, procedures during 2003. 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) as documented on the attached Procedure Change Process Forms. The following procedures were changed
- 1. NDAP-QA-0646, Process Control Program
- 2. WM-PS-1 00, Shipment of Radioactive Waste
- 3. WM-PS-1 10, General Shipment of Radioactive Material
- 4. WM-PS-120, Shipment of Radioactive Material by Air Carrier
- 5. WM-PS-1 55, 10CFR61 Sample Shipping and Correlation Factor Determination
- 6. WM-PS-1 80, Advanced Notification of Applicable States
- - 7. WM-PS-21 0, Packaging and Loading of DAW and Radioactive Material
- 8. WM-PS-250, Use of RADMAN and RAMSHP Computer Programs 9.. WM-PS-31 8, Use of Tandem Container Transport (TCT)
.10. WM-RP-012, Handling and Use of Steel Liners and High Integrity Containers
- 11. _ ME-ORF-I 65, Fuel Pool Cleanout - Duratek - Handling Procedure for 3-55 Cask C of C #5805 at PPL Susquehanna LLC 12.. ME-ORF-172, Fuel Pool Cleanout - Duratek- Guidelines for Use of Polyethylene High Integrity Containers
- 13. ME-EO-051, Fuel Pool Cleanout - Operation of Duratek Shielded Transfer Bell and Verification of No Free-Standing Water.in Fexm High Integrity Container 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 10O-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.
5-3
PROCEDURE REVISION
SUMMARY
-NDAP-QA-0646, Revision 7
1. Revised procedure to implement NRC recommendations (AR#491494) (Section 6.9.4). Added several references. Changed procedure adherence level to Information Use. Updated the waste streams in section 3.5. Updated sampling frequency. Incorporated PCAF 2001-1488. Converted the Waste Stream Sample Sheet into an electronic form. Revised the SCAN users instructions, Attachment E. Made various administrative changes.
5-8
PROCEDURE REVISION
SUMMARY
WM-PS-180, Revision 6
- 1. Added requirement to contact the Iowa Department of Public Health prior to shipping radioactive waste through Iowa.
- 2. Added new advance notification requirements in accordance with the Hazardous Material Transportation Security Plan per NDAP-QA-0641, Waste Management Program.
5-9
PROCEDURE REVISION
SUMMARY
WM-PS-210, Revision 6
- 1. Incorporated PCAF2002-1092.
- 2. 'Added new 49CFR393 load securement requirements.
- 3. Added reference to Reference Section.
- 4. Updated some job titles.
- 5. Clarified what is to be documented on the Packaging Data Sheet (Form WM-PS-210-1).
- 6. Added requirement for the qualified loader to sign Form SM-PS-21 0-1.
- 7. Made various administrative changes.
5-10
PROCEDURE REVISION
SUMMARY
WM-PS-250, Revision 2
- 1. Clarified SCO shipment requirements to ensure compliance with NUREG 1608.
- 2. Administrate Correction to incorporate PCAF #s 1-98-7136 and 2003-1362.
5-11
PROCEDURE REVISION
SUMMARY
WM-PS 318, Revision 3 mr/hr to
- 1. Added clarification to allow liners with contact dose rates that exceed 300allows the be shipped in the TCT with Effluents Supervision Approval. This change dose rate, on a container to be loaded, to exceed a recommended value. If in rate Effluents Supervision judgement, the container will not cause any shipping dose limit to be exceeded, this approval may be granted.
.. :X '..
5-12
PROCEDURE REVISION
SUMMARY
WM-RP-O1Z Revision 5
- 1. Incorporated PCAF 2000-4985.
- 2. Added filter size element criteria throughout the procedure as recommended by CR #398647 (CRA# 459945).
5-13
PROCEDURE REVISION
SUMMARY
ME-ORF-165, Revision 1
\i' 1. To consolidate cask handling steps and administrative guidance from ME-ORF-164.
- 2. Incorporate changes from the current revision of the vendor originated procedure.
5-14
PROCEDURE REVISION
SUMMARY
ME-ORF4172, Revision 1 t 1. Revise vendor name throughout procedure.
- 2. Change procedure reference to recognize procedure consolidation.
k
.1 - - .
5-15
PROCEDURE REVISION
SUMMARY
MT-EO-051, Revision I
- 1. Revised Vendor name change from CNSI to DURATEK.
- 2. Updated references to latest DURATEK procedures.
- 3. Changed description of items to be loaded in HIC from "filters" to 'components."
5-16
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 2003.
- 2. TRM Action 3.11.1 .5.C.1 requires the reporting of Radioactive Uquid Process Effluent Monitoring Instrumentation inoperability not corrected in a timely.
None to report for 2003.
- 3. TRM Action 3.11 .2.6.K requires an explanation for Radioactive Gaseous Effluent Monitoring Instrumentation required actions and completion times not met.
TRO 3.1 1.2.6 Condition D (Reactor Building Ventilation Monitoring System Effluent System Flow Rate Monitor or Sampler Flow Rate Monitor Inoperable) was entered on 12/16/03 at 09:27. Required Action D.1 (Estimate Flow Rate) was required to be performed initially at 13:27.
- -Required Action D.1 was not completed until 13:40. Multiple activities created confusion and loss of focus on time of priority item (TRO Requirement). There were minimal potential consequences of the event since the vent flow channel was available and alternate sampling was setup using a calibrated external pump. The Unit-1 Reactor Building ventilation monitoring system flow rate monitor was returned to service on s121 7/03at 16:14.
- 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 2003.
- 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
- thevalues 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 2003.
- 6. TRM Action 3.1 1.4.2.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 2003.
6-2
- 7. The 40CFRI 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 2003.
6-3
SECTION 7 CORRECTIONSTODOSESREPORTEDINPREVIOUS SEMIANNUAL OR ANNUAL EFFLUENTAND WASTE DISPOSAL REPORT 7-1
CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENT AND WASTE DISPOSAL REPORTS No corrections to previous semiannual or annual Radioactive Effluent Release Reports are submitted for this report period.
7-2
SECTION 8 EFFLUENT FROM SYSTEMS CLASSIFIED AS
- INSIGNIFICANT EFFLUENT PATHWA YS 8-1
EFFLUENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS Systems classified as Insignificant Effluent Pathways are evaporation from the Unit 1 and Unit 2 Condensate Storage Tanks (CSrs), 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 monthly to determine the concentration of radionuclides present in these tanks. Tritium analysis on these samples is performed quarterly. 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 areiinegligible compared to the airborne release shown in Tables 2-1 and 2-2 except for tritium; Thermaximum dose to the public from a release of 37.9 Ci of tritium is calculated to be 2.00-01 mrem (child). This is a fraction of the maximum dose from airborne effluent reported in Section 4.
8-2
TABLE 8-1 ANNUAL RELEASE FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS Ul-CST and 1U2-CST and Main TurbineIRFPT Main Turbine/RFPI' Nudide RWST Lube Oil Systes Lube Oil Systems Total
- -iL (C) (CD) (C)
H-3 8.407E-02 1.904E+01 1.881E+01 3.793E+01 Mn-54 2.387E-08 4.064E-07 1.178E-06 1.608E.06 Co-60 8.03SE-08 7592E-07 2.176E-06 3.015E-06 Cs-137 5.0202-10 0.OOOE+00 1.693E-08 1.743E-08 Xe-135 0.OOOE+00 2.304E-05 4.269E.06 2.731E-05 8-3