ML051220543
| ML051220543 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/31/2004 |
| From: | Doebler R, Hickey F, Rhoads B Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051220543 (134) | |
Text
Susquehanna Steam Electric Stati on..
Units 1 & 2- :-
Radioactive Effluent Release Report 2004 Annual
~
.49 4
, -r ig"MEN'
SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE EFFLUENT RELEASE REPORT REPORT PERIOD: 01/01/04 - 12/31/04 Prepared by:
Health Physicist Reviewed by:
Rayfond E. Doebler Chemistry Support Supervisor- SSES Approved by:
1I 244 Bruce E. Rhoads 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 Technical Requirements Manual (TRM) and the Solid Radioactive Waste Process Control Program
- 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 8-1 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 Waterborne 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 Waste Disposition 2-16 Table 2-7 Condensate Demineralizer/Radwaste Demineralizer 2-17 Class A HIC (Dewatered)
Table 2-8 Condensate Demineralizer/Radwaste Demineralizer 2-18 Class A Liner (Dewatered)
Table 2-9 Liquid Radwaste Filter Media 2-19 Class A HIC (Dewatered)
Table 2-10 RWCU Filter Media 2-20 Class A HIC (Dewatered)
Table 2-11 CFS Backwash Media 2-21 Class A HIC (Pyrolysis)
Table 2-12 CFS Backwash Media 2-22 Class A Strong Tight Container (Compacted)
Table 2-13 Chem - Decon Resin 2-23 Class A HIC (Pyrolysis)
Table 2-14 Contaminated Waste Oil - Class A 2-24 (Fuel Blending for Co-Generation)
LIST OF TABLES (cont.)
PAGE Table 2-15 Incinerated DAW - Class A 2-25 Strong Tight Container (Incineration)
Table 2-16 Liquid Radwaste Filter Media - Class A 2-26 HIC (Pyrolysis)
Table 2-17 Mixed Waste - Class A 2-27 (Incineration)
Table 2-18 Mixed Waste - Class A 2-28 Strong Tight Container (Compacted)
Table 2-19 Processed DAW - Class A 2-29 Strong Tight Container (Compacted)
Table 2-20 Cartridge Filters - Class B 2-30 HIC (Dewatered)
Table 2-21 Non-Processed DAW - Class B 2-31 HIC (Non-Processed)
Table 2-22 RWCU Filter Media - Class B 2-32 HIC (Dewatered)
Table 2-23 Chem - Decon Resin 2-33 Class B HIC (Pyrolysis)
Table 2-24 Liquid Radwaste Filter Media - Class B 2-34 HIC (Pyrolysis)
Table 2-25 CFS Backwash Media - Class C 2-35 HIC (Pyrolysis)
Table 2-26 Chem - Decon Resin 2-36 Class C HIC (Pyrolysis)
Table 2-27 Liquid Radwaste Filter Media - Class C 2-37 HIC (Pyrolysis)
Table 2-28 Condensate Demineralizer/Radwaste Demineralizer 2-38 Class A HIC (Pyrolysis)
LIST OF TABLES (cont.) PAGE Table 3-1 SSES Meteorological Data Recovery for 2004 3-3 Table 3-2 SSES Joint Frequency Distribution of Wind Speed and 3-4 Direction 1Om versus Delta Temperature 60-1 Om for the Period of January 1, 2004 through December 31, 2004 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, 2004 through December 31, 2004 Table 3-4 2004 SSES Annual Relative Concentrations No Decay, 3-20 Undepleted X/Q (sec/M 3 )
Table 3-5 2004 SSES Annual Relative Concentrations 2.26-Day 3-21 Decay, Undepleted X/Q (sec/M 3 )
Table 3-6 2004 SSES Annual Relative Concentrations 8-Day 3-22 Decay, Depleted X/Q (sec/M 3 )
Table 3-7 2004 SSES Annual Relative Deposition (D/Q meters )2 3-23 Table 3-8 2004 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 2004 Table 4-2 Summary of Maximum Individual Doses to Members 4-4 of the Public Data Period: 1/1/04 to 12/31/04 Table 4-3 Calculated Collective Doses to Members of the 4-5 Public Within the Riverlands/lnformation Center Complex Data Period: 1/1/04 to 12/31/04 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
LIST OF FIGURES PAGE Figure 1-1 SSES Airborne Effluent Release Points 1-6 Figure 1-2 SSES Waterborne Effluent Pathway 1-7 Figure 2-1 Susquehanna River Monthly Average Flow Rates 2-10 Data Period: 2004 Figure 2-2 SSES Monthly Liquid Radwaste Discharge Totals 2-11 Figure 3-1 SSES 2004 Annual Wind Rose 1OM Level - 3-26 Primary Tower Figure 3-2 SSES 2004 Annual Wind Rose 60M Level - 3-27 Primary Tower Figure 3-3 SSES Pasquil Stability Class Prevalences 3-28 Data Period: 2004 Figure 4-1 Airborne - Dose Calculation Locations 4-7
SECTION 1 INTRODUCTION,
SUMMARY
AND SUPPLEMENTAL INFORMATION 1-1
INTRODUCTION The submittal of the 2004 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 2004 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, Luzerne County, Pennsylvania. It is on the west bank of the Susquehanna River, 8 km northeast of Berwick. The Station consists of two boiling water reactor generating units, each with about 1,200 MW net electrical capacity. The reactor and generating units were supplied by General Electric, while the Bechtel Corporation served as architect-engineer and constructor.
Construction of the Station began in the early 1970s. Fuel load began in Unit 1 in July of 1982. Initial criticality was achieved in the Unit 1 reactor on September 10, 1982.
The reactor reached 100% power for the first time on February 4, 1983. Commercial operation of Unit 1 was declared on June 8, 1983. Initial criticality of Unit 2 occurred on May 8, 1984. Unit 2 was declared commercial on February 12, 1985.
Airborne effluents are released from the Susquehanna Station via five rooftop vents on the reactor building (see Figure 1-1). Each vent is continuously monitored for Noble Gases, and a program of periodic sampling and analysis for Particulates, Iodine, Tritium and 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. Waterborne effluents from the site are released into the cooling tower blowdown line for dilution prior to release to the Susquehanna River (see Figure 1-2).
Blowdown line flow rates are at least 5,000 gpm during periods of liquid radwaste release. The diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed. The diffuser serves to rapidly and uniformly mix the station discharge with the main flow of the river.
This report presents a summary of the quantities of radioactive materials which were released from the Susquehanna Steam Electric Station during the period from January 1, 2004 to December 31, 2004. In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to the SSES Offsite Dose Calculation Manual (ODCM) and Solid Radioactive Waste Process Control Program (PCP) and documentation of any exceptions to the SSES effluent monitoring program which must be reported per Technical Requirements.
Airborne and waterborne radioactive effluent releases to the environment during the report period were sampled and analyzed in accordance with the Technical Requirements. All radioactive effluent releases were within the concentration and 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 waterborne effluents over the report period.
Figures 2-1 and 2-2 present the Susquehanna River Monthly Average Flow Rates for 2004 and the SSES Monthly Liquid Radwaste Discharge Totals for 2004 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 waterborne 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 2004 including data recovery, joint frequency distribution of wind speed and direction, stability class distribution, and atmospheric dispersion estimates for selected locations.
Section 4 of this report contains an assessment of the calculated doses attributed to the reported radiological effluents for the calendar year. The Radioactive Effluent Tracking and Dose Assessment Software (RETDAS) computer code was used for calculation of doses from waterborne effluents. Site-specific parameters used in the calculations for the Danville receiver are shown in Table 4-1. The RETDAS code was also used for calculation of doses from airborne effluents. The calculated doses and direct radiation estimates can be used to estimate the doses to maximally exposed members of the public. Table 4-2 summarizes maximum calculated doses and dose commitments to members of the public from airborne and waterborne effluents. Table 4-3 presents
) g calculated collective doses to members of the public within the Riverlands/Information 1-3
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 (if any) in which airborne or waterborne effluent monitoring instrumentation was declared inoperable and was not restored to operability within the time period specified in Technical Requirements 3.11.1.4, 3.11.1.5 and 3.11.2.6 Action Statements. In addition, this section presents issues (if any) with the collection of milk or fresh leafy vegetables per Technical Requirement 3.11.4.1 and changes due to the land use census per Technical Requirement 3.11.4.2.
Section 7 contains corrections (if any) to doses reported in previous 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 2004 were similar to those of previous years.
During 2004 there were seventy nine (79) liquid batch releases resulting in a total release volume of nine-hundred-seventeen thousand five hundred (917,500) gallons.
The total number of liquid batch releases and total volume released in 2004 was lower than the corresponding values for 2003 (107 releases resulting in 1,036,000 gallons released in 2003). The predominant radionuclide released in liquid effluents during 2004 was tritium. Approximately sixty two (62) curies of tritium were released in liquid effluents in 2004, compared to seventy (70) curies released in 2003. When compared with all radionuclides released in liquid effluents in 2004, tritium was the main contributor to the resultant offsite dose. Consistent with previous years, the offsite dose from liquid releases in 2004 was less than one percent (1%) of the annual limits for both organ and whole body dose.
Gaseous effluents for 2004 were also comparable to those of previous years. Similar to liquid effluents in 2004, the predominant radionuclide released in gaseous effluents was tritium. When compared with all radionuclides released in gaseous effluents in 2004, tritium was the main contributor to the resultant offsite dose. The resultant maximum offsite organ dose due to gaseous effluents from Susquehanna Steam Electric Station Unit-1 for 2004 was 6.63E-01 mrem, which is 4.4 percent (4.4%) of the per unit annual limit of fifteen (15) mrem. The resultant maximum offsite organ dose due to gaseous effluents from Susquehanna Steam Electric Station Unit-2 for 2004 was 5.20E-01 mrem, which is 3.5 percent (3.5%) 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 UNI I NTI lI REACTOR REACTOR l BUILDING BUILDING
£XNAUST EXHAUST
- .. } VEN VN 160,770CFM 157,350 CFM 0 0 AT 600 F-110 F AT 60°F-.I 10 F 302.959 CFM 17.500 CfM 227.034 CFM0 0
AT 100°F-120°f AT 120°F AT IDO F-120 F OUTSIDE AIR INTAKE REACTOR BUILDING UNIT I GTUNIT II lURBINE TURBINE EXHAUSTSTACKS BUILDING BUILDING DIESEL EXHAUST PLENUM is EXHAUST EXHAUST BUILDING VEVATTR E VENT ROL BUILDINDI 7 2t'4"- i
-21'46 1-6
FIGURE 1-2 SSES WATERBORNE EFFLUENT PATHWAY
\
/
) I FROM EVAPORATOR HEATING STEAM CONDENSATE RETURN TANK REACTOR WELL SEAL LEAK DRAIN . l REACTOR BUILDING DRAINS FROM PHASE SEPARATORS (DECANT)N DRYWELL DRAINS [ SSES LIQUID EFFLUENT RELEASE FLOWPATH I I FROM RHR SYSTEM I(SUPPRESSION POOL TRANSFERS) TURBINE BUILDING DRAINS 1 IM-161. M-162. M-163 AND M-1641 I RADWASTE BUILDING DRAINS RADWASTE BUILDING DRAINS l
_ LIQUIL) RADWASTE RECYCLE r - ',-- I LIQUIDRDAT COLLECTION AND P SURGITANKS S RITK 0T-302A THRU F__
OT-304A THRU D LQI IUDl LQI
_RADWASTE _RADWASTE RADAT h_ ) _ FILTERS DEMINERALIZER SAMPL AK LIQUID RADWASTE OF-302A & B 0-301 OT-30ATRF COLLECTION TANK PUMP LWIQIUIDRAWAT CONDENSATE 0P-301A, B bC STORAGE TANKS 0T-522A & B I SAMPLE TANK PUMPS
_ _ wes OP-522A, B & C RADWASTE BUILDING FUEL POOL CLEANUP SAMPLE STATION SYSTEM CHEMICAL DECON RWCU CHEMICAL DECON. CHEMICAL DECON LAB & DECON DRAINS l AUX. BOILER BLOWDOWNS r---EMCA-RAN-AN-
____4;_ ---- ___
ICI WAS I TNK OT-314 KADWIASTE DISTILLATE EVAPORATORS SAMPLE TANK l HMICAL WASTE TANK OF-302A, I I1 OT-321 1
'PTUMPSOP32A B___ ------------
1(2) CONDENSATEDMNI, t , l I-EVAPORATOR I S TN CONCENTRATE _
STORAGE TANK I DISTILLATE NEUTRALZN PUMPS l T-130A, B ltl l 0-2A 2T-130A, B 8F J -
NEUTRALIZNG TAN" UP CONOENSATE STORAGE TANKl DISCHARGIE PUM OP32 lPERSONNEL DECONTAMINATION _
l (DETERGENTS) -
l FLOOR DECON (SOLUTIONS) K LANN DAN l REGULATED SHOP DRAINS LANR DRIN (3 IL TANDRYDR LANR FITRSAI LAUNDRY DRAINl l 0-11,B TNK PUMPS ANR RIN' l P-318A, B SAMPLE TANK PUMPS L. I (1) RADWASTE EVAPORATORS (2) COND DEMIN RESINS CURRENTLY (3) CONTAMINATED CLOTHING CURRENTLY ARE NOT USED NOT REGENERATED NOT LAUNDERED ONSITE SUSQUEHANNA RIVER 1-7
SUPPLEMENTAL INFORMATION
- 1. Regulatory Limits Technical Requirements 3.11.1 and 3.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively. Concentration of radioactive materials released in liquid effluents and dose or dose commitment resultant thereof are limited in unrestricted areas, Dose and dose rate due to radioactive materials released in gaseous effluents are limited in areas at or beyond the site boundary. Technical Requirement limits are listed in Table 1-1.
- 2. Maximum Permissible Concentrations in Waterborne Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas is limited to 10 times the concentrations specified in 10 CFR Part 20 Appendix B Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration is limited to 2.OE-04 pCi/ml 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 2004 resulted in an Annual E-Bar Beta value of 4.27E-01 mev and an E-Bar Gamma value of 1.15 mev.
- 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: Airborne tritium is collected monthly via bubbler sampler. The sample is collected for one hour at a flow rate of approximately 1000 cc/min.
Tritium activity in the bubbler sample is determined by liquid scintillation counting. The liquid sample tritium concentration is then converted to air concentration by volume proportion.
- 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. A monthly composite is sent to a vendor laboratory for gross alpha analysis. A quarterly composite is sent to a vendor laboratory for iron-55, strontium-89 and-90 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 in 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 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 mrem/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 3.11.2.1.1.A) limit of 500 mrem/yr was calculated from the expected mix of noble gas radionuclides presented in Attachment A of ODCM-QA-003, Effluent Monitor Setpoints. The limit is 1.00E+06 pCi/min (1.67E+04 pCi/sec).
Iodine-131 A derived release rate limit for 1-131 based on the Technical Requirement (TRO 3.11.2.1.1l.A) limit of 1500 mrem/yr from 1-131, 1-133, tritium and particulates with half-lives greater than 8 days was calculated based on the ratio of the expected annual release quantities of 1-131 and 1-133 provided in Attachment E of ODCM-QA-004, Airborne Effluent Dose Calculations. The limit is 1.04E+02 pCi/min 1-131 (1.73E+00 pCi/sec).
Particulates A derived release rate limit for particulate activity other than iodines based on the Technical Requirement (TRO 3.11.2.1.1l.A) limit of 1500 mrem/yr from I-131,1-133, tritium and particulates with half-lives greater than 8 days was calculated based on the expected annual release quanities of particulate radionuclides provided in Attachment E of ODCM-QA-004, Airborne Effluent Dose Calculations. The limit is 3.OOE+03 pCi/min (5.OOE+01 pCi/sec).
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 pCi/cc) to unrestricted areas. A relative concentration of 4.1 E-05 sec/m 3 was assumed (PPL calculation EC-ENVR-1040). The limit is 1.46E+05 pCi/min (2.44E+03 pCi/sec).
1-11
E. WATERBORNE EFFLUENT: BASES FOR 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 pCi/ml 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 2.0E-04 pCi/ml.
(TRO 3.11.1.1)
Radionuclide Fractional Summation 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. 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, the measurement laboratory LLDs were less than the levels required by Technical Requirements.
- 1. Number of Batch Releases: 0
- 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 1*
- 2. Total Activity Released NA
- Historically, monitoring of NRC I/E Bulletin 80-10 applicable systems at the SSES did not include analysis for tritium. Peer facilities were benchmarked in September 2004 regarding tritium analysis of 80-10 systems. The majority of benchmarked facilities analyze for tritium in 80-10 systems. Based on the benchmarking feedback and additional evaluation by the SSES Chemistry group, tritium analysis was added to the auxiliary steam system 80-10 monitoring program. In October 2004 the auxiliary steam system was identified as contaminated with low levels of tritium (-1 E-5 uCi/cc). The auxiliary steam system was assumed contaminated at identified concentrations for all of 2004. Conservative assumptions were used in support of the calculation of total radioactive effluent from operation of the auxiliary steam system during 2004. The radioactive effluent due to auxiliary steam system operation in 2004 is a small fraction
(<0.001 %) of the total releases due to station operation in 2004. Additional details on this release are outlined in Section 8.
2-2
TVpical LLDs Radionuclide LLD (pGCVcc)
Kr-87 4.6 E-08 Kr-88 5.3 E-08 Xe-1 33 5.4 E-08 Xe-133m 1.3 E-07 Xe-135 1.5 E-08 Xe-135m 5.OE-08 Xe-138 1.2 E-07 Mn-54 2.9 E-13 Fe-59 2.8 E-13 Co-58 1.8 E-13 Co-60 3.8 E-13 Zn-65 4.4 E-13 Mo-99 3.3 E-12 Cs-1 34 2.4 E-13 Cs-1 37 2.1 E-14 Ce-1 41 1.5 E-14 Ce-1 44 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 I Second Third Fourth A. Fission and Activation Gas Unit . Quarter Quarter Quarter Quarter Total Release Ci 1.40E+00 5.74E+00 2.38E+00 0 Average Release Rate for Period pCi/sec 1.78E-01 7.30E-01 3.OOE-01 0 Percent of Applicable Limit I 1.07E-03 4.37E-03 1 .80E-03 0 (1.67E+04 pCVsec)
B. lodines Total 1-131 Ci 0 0 0 0 Total 1-133 Ci 0 0 0 0 Average Release Rate for Period pCilsec 0 0 0 0 Percent of Applicable Limit 0 0 0 0 (1.73E+00 pCi/sec)
C. Particulate Particulate with Half-Life >8 Days Ci 2.12E-04 4.28E-04 7.78E-05 7.49E-07 Average Release Rate for Period pCi/sec 2.70E-05 5.44E-05 9.79E-06 9.43E-08 yPercent of Applicable Limit % 5.39E-05 1.09E-04 1.96E-05 1.89E-07 (5.00E+01 pCi/sec) _
Gross Alpha Radioactivity Ci 0 0 0 0 D.. Tritium Total Release Ci 4.59E+01 2.53E+01 3.29E+01 5.59E+01 Average Release Rate for Period pCi/sec 5.84E+00 3.22E+00 4.14E+00 7.04E+00 Percent of Applicable Limit 2.39E-01 1.32E-01 1.70E-01 2.88E-01 (2.44E+03 pCi/sec) 2-4
TABLE 2-2 AIRBORNE EFFLUENT - RADIONUCLIDES RELEASED I Releases in Continuous Mode I First Second Third Fourth Nuclides Released I Unit Quarter Quarter Quarter Quarter A. Fission and Activation Gases Ar-41 Ci 1.20E+00 4.90E+00 1.97E+00 0 Kr-85 Ci 0 0 0 0 Kr-85m Ci 8.59E-02 3.51 E-01 1.65E-01 0 Kr-87 Ci 0 0 0 0 Kr-88 Ci 2.80E-02 1.14E-01 1.06E-01 0 Kr-89 Ci 0 0 0 0 Xe-133 Ci 9.1 OE-02 3.72E-01 1.41 E-01 0 Xe-133m Ci 0 0 0 0 Xe-135 Ci 0 0 0 0 Xe-135m Ci 0 0 0 0 Xe-137 Ci 0 0 0 0 Xe-138 Ci 0 0 0 0 Total for Period Ci 1.40E+00 5.74E+00 2.38E+00 0 B. lodines 1-131 Ci 0 0 O O 1-133 1 Ci 01 0 0 1-135 Ci O 0 0 0 Total for Period Ci 0 0 0 0 C. Particulate Cr-51 Ci 1.20E-04 1.32E-04 0 0 Mn-54 Ci 3.64E-05 1.87E-04 5.01 E-05 0 Fe-59 Ci 0 0 0 0 Co-58 Ci 9.56E-07 8.97E-06 0 0 Co-60 Ci 5.44E-05 9.62E-05 2.78E-05 7.49E-07 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-144 Ci 0 0 0 0 Ag-11OM Ci 0 0 0 0 Nb-95 Ci 0 4.11 E-06 0 0 Ba-La-140 Ci 0 0 0 0 Total for Period Ci 2.12E-04 4.28E-04 7.79E-05 7.49E-07 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. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual
- 1. Number of Batch Releases 29 23 17 10 79
- 2. Total Time Period for a Batch Release 3.59E+03 4.44E+03 2.90E+03 6.17E+02 1.1 5E+04
- 3. Maximum Time Period for a Batch Release 2.97E+02 2.96E+02 2.98E+02 7.70E+01 2.98E+02
- 4. Average Time Period for a Batch Release 1.24E+02 1.93E+02 1.70E+02 6.17E+01 1.46E+02
- 5. Minimum Time Period for a Batch Release 2.80E+01 2.50E+01 2.20E+01 2.90E+01 2.20E+01
- 6. Average Cooling Tower Blowdown 7.76E+03 9.22E+03 1.08E+04 9.39E+03 9.16E+03 Flow Rate During Periods of Release
- 7. Susquehanna River Flow Rate 8.79E+06 8.87E+06 1.05E+07 8.44E+06 9.15E+06
- Units of time and flow are expressed in minutes and gallons per minute (gpm),
respectively.
Abnormal Releases
- 1. Number of releases 0 0 0 0
- 2. Volume Released N/A N/A N/A N/A
- 3. Total Activity Released N/A N/A N/A NIA 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 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. In all cases, the measurement laboratory LLDs were less than the levels required by Technical Requirements. The following are typical measurement laboratory LLDs.
Radionuclide LLD (IiCVml)
Mn-54 4.5 E-08 Fe-59 5.0 E-08 Co-58 2.4 E-08 Co-60 5.4 E-08 Zn-65 4.9 E-08 Mo-99 1.7 E-07 1-131 2.0 E-08 Cs-1 34 2.2 E-08 2-6
Radionuclide LLD (WCi/ml)
Cs-1 37 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 5.3E-07 Gross Alpha 3.0 E-08 2-7
TABLE 2-3 WATERBORNE EFLUENT - SUMMATION OF ALL RELEASES First Second Third Fourth A Me~cinn nnrl Arflut;ionn Prnrhimrfc Unit (Ii nrt-fr f) i in rtgr nimrfar fli inrfgr A. * -..- va u -wala
>W~ -uuglv
s -Lusa-ka----
- 1. Total Release (excluding: Tritium, Ent.
Gases, Alpha) Ci 2.35E-02 5.79E-04 2.68E-04 6.89E-04
- 2. Average Diluted Concentration During Period PCi/l 2.22E-07 3.74E-09 2.27E-09 3.14E-08
- 3. Sum of Average Diluted Cr/L, Ratio During Period Unitless 4.84E-04 3.99E-05 4.03E-05 3.61 E-04
- 4. Percent of Applicable Limit (Ratio < 1.0) % 0.05 0.004 0.004 0.04 B. Tritium
- 1. Total Release Ci 2.29E+01 2.53E+01 1.31 E+01 7.56E-01
- 2. Average Diluted Concentration During Period ijCi/ml 2.17E-04 1.63E-04 1.11 E-04 3.45E-05
- 3. Percent of Applicable Limit (1.OE-2 pCi/ml) % 2.17 1.63 1.11 0.35 C. Dissolved and Entrained Gases
- 1. Total Release Ci 4.97E-05 1.68E-05 2.72E-05 0
- 2. Average Diluted Concentration pCi/ml 4.72E-10 1.09E-10 2.31E-10 0 During Period
- 3. Percent of Applicable Limit (2.OE-4 pCi/ml) _ 2.36E-04 5.43E-05 1.15E-04 0 K> D. Radionuclide Fractional Summation
- 1. Sum of Percentages/Percent of Applicable l Limit During Period (Limit = 100%) % 1 2.22 1 1.63 1 1.11 1 0.39 I E.. Gross Alpha Radioactivity l1. Total Release I Ci I 5.06E-08 I 0 l 0 0° F. Volume of Water Released I Gallons I 2.77E+05 1 3.65E+05 1 2.34E+05 1 4.15E+04 1 (Prior to Dilution) Liters I .05E+06 1 .38E+06 8.87E+05 I 1.57E+05 1 G. Volume of Dilution Water l Gallons l 2.75E+07 l 4.07E+07 l 3.09E+07 l 5.76E+06 l Used During Period of Release Liters 1.04E+08 1.54E+08 1.17E+08 2.18E+07 H. Volume of Dilution Water I Gallons l 9.58E+08 l 7.08E+08 l 1.48E+09 l 1.06E+09 l Used Over Entire Period Liters 3.63E+09 2.68E+09 5.62E+09 4.02E+09E l 2-8
TABLE 2-4 WATERBORNE EFFLUENT - RADIONUCLIDES RELEASED Releases in Batch Mode Nuclides Unit First Second Third Fourth Released Quarter Quarter Quarter Quarter A. Fission and Activation Products F-18 Ci 0 1.96E-07 0 0 Na-24 Ci 0 0 0 0 Cr-51 Ci 2.09E-03 2.70E-04 7.37E-06 2.98E-04 Mn-54 Ci 9.00E-04 1.19E-04 1.28E-04 1.42E-04 Fe-55 Ci 1.95E-02 0 0 0 Co-58 Ci 1.56E-04 1.60E-05 2.81 E-06 2.82E-05 Fe-59 Ci 3.78E-05 6.98E-06 0 4.23E-06 Co-60 Ci 8.09E-04 1.68E-04 1.29E-04 2.12E-04 Zn-65 Ci 0 0 0 3.61 E-06 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 2.66E-06 0 0 0 Cs-137 Ci 0 0 0 6.57E-07 Sb-124 Ci 0 0 0 9.12E-07 Hf-181 Ci 2.30E-06 0 0 0 Total for Period Cl 2.35E-02 5.80E-04 2.67E-04 6.90E-04 B Tritium Total for Period lCi 2.29E+01 l 2.53E+01 J 1.31 E+01 J 7.56E-01 C. Dissolved and Entrained Gases Ar-41 Ci 0 0 0 0 Kr-85 Ci 0 0 0 0 Kr-86m Ci 0 0 0 0 Kr-87 Ci 0 0 0 0 Kr-88 Ci 0 0 0 0 Xe-131m Ci 0 0 0 0 Xe-133m Ci 0 0 0 0 Xe-133 Ci 2.23E-05 4.69E-06. 1.94E-05 0 Xe-135m Ci 0 0 0 0 Xe-135 Ci 2.75E-05 1.21 E-05 7.75E-06 0 Total for Period Ci 4.98E-05 1.68E-05 2.72E-05 0 2-9
Figure 2-1 Susquehanna River Monthly Average Flow Rates Data Period: 2004 20.0 18.0 16.0 0) 0 14.0 r-0)
- 0. 12.0 0
-W 10.0 0)
K> 8.0 a: 6.0 0) 4.0 2.0 0.0 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC I
- 20047 2-10
Figure 2-2 SSES Monthly Liquid Radwaste Discharge Totals 300 250 200 a)
On a,
.s U- C0 mCZ
.8 a 0= 1 50 EA 0o 0
100 50 0
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2004 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. Condensate Demineralizer/Radwaste Demineralizer - +/-25%
Class A HIC (Dewatered)
- b. Condensate Demineralizer/Radwaste Demineralizer - +/-25%
Class A Steel Liner (Dewatered)
- c. Liquid Radwaste Filter Media - Class A HIC (Dewatered) +/-25%
- e. CFS Backwash Media - Class A (Pyrolysis) +/-25%
- f. CFS Backwash Media - Class A Strong Tight +/-25%
Container (Compacted)
- g. Chem - Decon Resin - Class A HIC (Pyrolysis) +/-25%
- h. Contaminated Waste Oil - Class A +/-25%
(Fuel Blending for Co-Generation)
- i. Incinerated DAW - Class A Strong Tight Container +/-25%
(Incineration) 2-12
ESTIMATED MAXIMUM MEASUREMENT MEASUREMENT ERROR
- 3. Solid Wastes (cont.)
- j. Liquid Radwaste Filter Media - Class A HIC +/-25%
(Pyrolysis)
- k. Mixed Waste - Class A (Incineration) +/-25%
I. Mixed Waste - Class A Strong Tight Container +/-25%
(Compacted)
- m. Processed DAW - Class A Strong Tight Container +/-25%
(Compacted)
- n. Cartridge Filters - Class B HIC (Dewatered) +/-25%
Processed)
- q. Chem-Decon Resin - Class B HIC (Pyrolysis) +/-25%
- r. Liquid Radwaste Filter Media - Class B HIC i25%
(Pyrolysis)
- t. Chem-Decon Resin - Class C HIC (Pyrolysis) i25%
- u. Liquid Radwaste Filter Media - Class C HIC (Pyrolysis) i25%
- v. Condensate Demineralizer/Radwaste Demineralizer - +/-25%
Class A HIC (Pyrolysis) 2-13
SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE DATA PERIOD: JANUARY 1. 2004 - DECEMBER 31. 2004 PREPARED BY:
MICHAEL C. MICCA HEALTH PHYSICIST APPROVED BY:
RAY T. HOCK RADIOLOGICAL OPERATIONS SUPERVISOR 2-14
SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE DATA PERIOD: JANUARY 1.2004 - DECEMBER 31. 2004 PREPARED BY.:
-MICHAEL C. MICCA HEALTH PHYSICIST APPROVED BY:
RAI 0L C . H OCK S RJ RADIOLOGICAL ORE ATIONS SUPERVISOR
- 2-14
REPORT NOTES
- 1. All activities reported in Milli-Curies (mCi) unless otherwise noted.
- 2. Reported activities, as indicated with the (<) sign, are comprised in whole or part of MDL values.
- 3. Estimated maximum measurement error is +25%.
2-15
TABLE 2-6 WASTE DISPOSITION Data Period: January 1, 2004 - December 31, 2004 A. SOLID WASTE SHIPPED OFF-SITE FOR BURIAL OR DISPOSAL Number of Shipments Mode of Transportation Destination 8 Truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS Number of Shipments Mode of Transportation Destination NONE 2-16
Table 2-7 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: No Source: Condensate Demineralizer / Radwaste Demineralizer Container: HIC (High Integrity Container)
..Process: Dewatered Nuclides Activity (mCi)
- of Total C-14 1.120E+02 48.67 t CO-58 1.060E+00 0.46 t CO-60 2.400E+01 10.43 t CS-137 4.160E-01 0.18 t FE-55 4.550E+01 19.77 %
H-3 2.970E+01 12.91 %
I-129 4.OOOE-06 0.00 %
MN-54 1.720E+01 7.47 %
NI-63 2.630E-01 0.11 %
TC-99 < 5.230E-06 0.00 %
Total Activity (Ci) 0.230 100.00 %
Container Volume 84.250 ft3 2.386 m3 2-17
Table 2-8 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: No Source: Condensate Demineralizer / Radwaste Demineralizer Container: Liner Process: Dewatered Nuclides Activity (mCi) % of Total C-14 1.759E+02 7.62 %
CO-58 2.166E+01 0.94 %
CO-60 2.326E+02 10.08 %
CR-51 1.814E+02 7.86 %
CS-137 4.131E-01 0.02 %
FE-55 1.211E+03 52.47 %
FE-59 2.091E+01 0.91 %
H-3 2.357E+02 10.21 %
I-129 < 2.580E-06 0.00 %
I-131 9.360E-01 0.04 %
MN-54 1.854E+02 8.03 %
NB-95 1.931E+01 0.84 %
NI-63 7.630E+00 0.33 %
TC-99 < 7.800E-06 0.00 %
ZN-65 2.580E-01 0.01 %
ZR-95 1.478E+01 0.64 %
Total Activity (Ci) 2.308 100.00 %
Container Volume 598.200 ft3 16.939 m3 2-18
Table 2-9 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: No Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides Activity (mCi) % of Total
________ ______________ 0.00______
C-14 8.350E-02 0.00 %
CE-144 4.730E+0l 0.02 %
CM-242 3.450E-03 0.00 %-
CO-58 1.080E+03 0.56 %
CO-60 6.670E+03 3.45 %
CR-51 1.250E+04 6.47 %
CS-137 1.120E+01 0.01 %
FE-55 1.590E+05 82.24 %
FE-59 1.720E+03 0.89 %
H-3 4.670E+0l 0.02 %
I-129 < 2.OOOE-04 0.00 %
MN-54 1.130E+04 5.84 %
NB-95 1.900E+02 0.10 %
NI-59 1.350E+00 0.00 %
NI-63 9.670E+01 0.05 %
SB-124 1.200E+02 0.06 %
SB-125 7.310E+01 0.04 %
SR-90 1.280E+01 0.01 %
TA-182 1.630E+02 0.08 %
TC-99 < 3.160E-05 0.00 %
ZN-65 1.790E+02 0.09 %
ZR-95 1.320E+02 0.07 %
Total Activity (Ci) 193.343 100.00 %
Container Volume 132.400 ft3 3.749 m3 2-19
Table 2-10 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: No Source: RWCU Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides Activity (mCi) % of Total AM-241 1.345E-0l 0.00 %
C-14 < 4.340E-05 0.00 %
CE-144 8.980E+02 0.08 %
CM-242 1.585E-Ol 0.00 %
CM-243 1.259E+00 0.00 %
CO-58 9.980E+02 0.09 %
CO-60 2.647E+05 23.39 %
CS-137 3.181E+02 0.03 %
FE-55 5.570E+05 49.21 t H-3 < 6.050E-04 0.00 %
I-129 < 2.500E-05 0.00 %
MN-54 2.823E+05 24.94 t NB-95 5.175E+02 0.05 %
NI-63 3.860E+03 0.34 %
PU-238 1.444E-0l 0.00 %
PU-239 3.506E-02 0.00 %
PU-241 1.285E+Ol 0.00 %
SB-125 1.991E+04 1.76 %
SR-89 3.568E+01 0.00 %
SR-90 7.870E+0O 0.00 %
TC-99 < 3.490E-05 0.00 %
ZN-65 1.312E+03 0.12 %
Total Activity (Ci) 1131.872 100.00 %
Container Volume 180.550 ft3 5.113 m3 2-20
Table 2-11 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: CFS Backwash Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) t of Total
________ ______________ 0.00______
C-14 8.372E+00 0.00 %
CE-144 1.520E+01 0.00 t CM-244 1.460E-03 0.00 %
CO-58 7.335E+01 0.01 %
CO-60 4.547E+04 5.40 t CR-51 6.737E+01 0.01 t CS-137 2.502E+02 0.03 t FE-55 7.541E+05 89.55 %
FE-59 2.100E+01 0.00 t H-3 9.312E+01 0.01 %
I-129 5.615E-01 0.00 %
MN-54 4.169E+04 4.95 %
NB-95 8.500E+00 0.00 %
NI-59 1.770E-01 0.00 %
NI-63 3.362E+02 0.04 %
PU-241 7.950E-02 0.00 t 11-J SR-90 9.620E-02 0.00 %
TC-99 4.026E-01 0.00 %
Total Activity (Ci) 842.101 100.00 %
Container Volume 68.010 ft3 1.926 m3 2-21
Table 2-12 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: CFS Backwash Media Container: Strong Tight Container Process: Compacted Nuclides Activity (mCi) % of Total C-14 2.434E+00 0.00 %
CO-60 1.464E+04 4.76 t CS-137 9.363E+01 0.03 t FE-55 2.741E+05 89.03 t H-3 2.154E+01 0.01 t I-129 O.OOOE+00 0.00 t MN-54 1.890E+04 6.14 %
NI-63 1.047E+02 0.03 t TC-99 O.OOOE+00 0.00 %
Total Activity (Ci) 307.862 100.00 %
Container Volume 27.790 ft3 0.787 m3 2-22
Table 2-13 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: Chem-Decon Resin Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) t of Total C-14 1.380E+0l 0.04 %
CO-58 1.881E+03 5.63 %
CO-60 2.092E+04 62.61 %
CR-51 2.898E+02 0.87 %
CS-137 1.083E+0l 0.03 t FE-55 6.600E+03 19.75 t FE-59 4 .340E+0l 0.13 %
H-3 1.940E+0l 0.06 %
I-129 3 .346E-03 0.00 %
MN-54 3 .249E+03 9.73 t NB-95 2.060E-Ol 0.00 %
NI-59 6.160E-01 0.00 %
NI-63 1.236E+02 0.37 %
SB-124 1.200E-05 *O.00 %
SR-89 1.500E-0l 0.00 %
SR-90 2.230E-04 0.00 %
TC-99 1.020E-02 0.00 %
ZN-65 2.580E+02 0.77 %
ZR-95 3.780E-01 0.00 t Total Activity (Ci) 33.408 100.00 %
Container Volume 48.820 ft3 1.382 m3 2-23
Table 2-14 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: Contaminated Waste Oil Container: None Process: Fuel Blending for Co-Generation Nuclides Activity (mCi) % of Total C-14 3.230E-05 0.00 %
CO-60 9.310E-02 2.51 %
CS-137 8.830E-05 0.00 %
FE-55 7.020E-01 18.96 %
H-3 1.890E+00 51.03 %
I-129 < 9.870E-09 0.00 %
MN-54 5.410E-03 0.15 %
NB-95 1.340E-03 0.04 %
NI-59 1.580E-05 0.00 %
NI-63 1.830E-03 0.05 %
RA-226 8.380E-02 2.26 %
TC-99 < 2.020E-09 0.00 %
TH-234 3.150E-01 8.51 %
U-235 4.740E-03 0.13 t U-238 6.060E-01 16.36 %
Total Activity (Ci) 0.004 100.00 9 Container Volume 0.000 ft3 0.000 m3 2-24
Table 2-15 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: Incinerated DAW Container: Strong Tight Container Process: Incineration Nuclides Activity (mCi) W of Total
________ ____ _________ 0.00______
C-14 1.287E-01 0.00 %
CO-57 5.648E-01 0.00 %
CO-58 1.560E+01 0.09 %
CO-60 7.827E+02 4.47 %
CS-137 1.023E+00 0.01 %
FE-55 1.476E+04 84.22 %
FE-59 2.534E+01 0.14 %
H-3 4.822E+01 0.28 %
I-129 O.OOOE+00 0.00 %
MN-54 1.873E+03 10.69 %
NB-95 1.701E+00 0.01 %
NI-63 5.523E+00 0.03 %
SB-124 2.012E+00 0.01 %
SB-125 1.332E+00 0.01 t TC-99 O.OOOE+00 0.00 t ZN-65 8.117E+00 0.05 t Total Activity (Ci) 17.525 100.00 t Container Volume 14.500 ft3 0.411 m3 2-25
Table 2-16 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) t of Total
________ ______________ 0.00______
C-14 1.11OE-08 0.00 %
CE-144 3.120E-06 0.02 %
CM-242 1.360E-10 0.00 %
CO-58 1.340E-05 0.07 %
CO-60 7.990E-04 4.10 %
CR-51 3.670E-06 0.02 %
CS-137 1.470E-06 0.01 %
FE-55 1.730E-02 88.79 %
FE-59 5.010E-06 0.03 %
H-3 4.020E-06 0.02 %
I-129 9.010E-09 0.00 %
MN-54 1.340E-03 6.88 %
NB-95 6.090E-08 0.00t NI-59 1.800E-07 *0.00 %
NI-63 1.280E-05 0.07 t SB-124 7.810E-07 0.00 %
SR-90 1.670E-06 0.01 %
TC-99 1.430E-09 0.00 %
Total Activity (Ci) <0.001 100.00 %
Container Volume 16.000 ft3 0.453 m3 2-26
Table 2-17 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: Mixed Waste Container: None Process: Incineration Nuclides Activity (mCi) % of Total C-14 c 2.840E-07 0.00 %
CE-144 5.720E-05 0.00 %
CM-244 1.294E-07 0.00 %
CO-58 1.223E-04 0.01 %
CO-60 1.845E-02 0.85 %
CS-137 2.640E-05 0.00 %
FE-55 3.030E-0l 13.96 %
H-3 1.835E+00 84.52 %
I-129 < 3.630E-07 0.00 %
MN-54 1.317E-02 0.61 %
NB-95 7.180E-05 0.00 %
NI-59 4.400E-05 0.00 %
NI-63 9.410E-04 0.04 %
PU-238 7.980E-08 0.00 t TC-99 4.020E-05 0.00 %
ZN-65 1.459E-04 0.01 %
Total Activity (Ci) 0.002 100.00 %
Container Volume 0.000 ft3 0.000 m3 2-27
Table 2-18 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: Mixed Waste Container: Strong Tight Container Process: Compacted Nuclides Activity (mCi) % of Total
________ ______________ 0.00______
- 5.890E-07 0.00 %
CE-144 4.430E-04 0.00 %
CM-244 1.003E-06 0.00 %
CO-58 9.480E-04 0.00 %
CO-60 1.427E-O1 0.70 %
CS-137 2.051E-04 0.00 %
FE-55 2.355E+00 11.60 %
H-3 1.769E+0l 87.14 %
I-129
- 7.520E-07 0.00 %
MN-54 1.022E-0l 0.50 %
NB-95 5.560E-04 0.00 %
NI-59 3.415E-04 0.00 %
NI-63 7.290E-03 0.04 %
PU-238 6.180E-07 0.00 %
TC-99 3.114E-04 0.00 %
ZN-65 1.130E-03 0.01 %
Total Activity (Ci) 0.020 100.00 %
Container Volume 81.070 ft3 2.296 m3 2-28
Table 2-19 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reeduction Vendor: Yes Source: Processed DAW Container: Strong Tight Container Process: Compacted Nuclides Activity (mCi) % of Total
______________ 0.00______
AG-110M 3.279E-03 0.00 %
AM-241 2.101E-01 0.00 %
C-14 2.212E+O0 0.00 %
CD-109 6.417E-02 0.00 %
CE-139 1.127E-06 0.00 %
CE-144 4.808E-01 0.00 %
CM-244 1.280E-03 0.00 %
CO-57 7.819E+00 0.00 CO-58 2.183E+02 0.07 %
CO-60 1.360E+04 4.54 %
CR-51 4.147E+01 0.01 %
CS-137 3.095E+01 0.01 %
FE-55 2.554E+05 85.31 %
FE-59 3.532E+02 0.12 %
H-3 5.317E+01 0.02 %
HF-181 3.720E-02 0.00 %
HG-203 1.171E-03 0.00 %
I-129 5.750E-01 0.00 %
MN-54 2.937E+04 9.81 %
NB-95 2.379E+01 0.01 %
NI-59 4.104E-01 0.00 %
NI-63 1.039E+02 0.03 %
PU-238 7.422E-04 0.00 %
SB-124 2.787E+01 0.01 %
SB-125 1.844E+01 0.01 %
SN-113 3.663E-07 0.00 %
SR-85 4.351E-11 0.00 %
SR-90 4.OOOE-04 0.00 %
TC-99 3.903E-Ol 0.00 %
Y-88 3.225E-07 0.00 %
ZN-65 1.139E+02 0.04 %
ZR-95 8.162E-04 0.00 %
Total Activity (Ci) 299.351 100.00 %
Container Volume 4274.109 ft3 121.032 m3 2-29
Table 2-20 Annual Waste Release Summary Report Year: 2004 Class: B Volume Reduction Vendor: No Source: Cartridge Filters Container: HIC (High Integrity Container)
Process: Dewatered Nuclides Activity (mCi) % of Total 0.00______
C-14 < 1.600E-0l 0.00 %
CE-144 3.220E+00 0.00 %
CM-244 2.200E-02 0.00 %
CO-58 4.830E+01 0.02 %
CO-60 1.440E+04 5.54 %
CR-51 4.280E+01 0.02 %
CS-137 1.631E+01 0.01 %
FE-55 2.410E+05 92.65 %
FE-59 2.150E+00 0.00 %
H-3 1.736E+00 0.00 %
I-129 < 2.730E+00 0.00 %
MN-54 3.139E+03 1.21 %
NB-95 2.271E+01 0.01 %
NI-59 1.510E+01 0.01 %
NI-63 1.278E+03 0.49 %
PU-238 5.410E-05 0.00 %
SB-125 6.950E+01 0.03 %
SN-113 1.190E+00 0.00 %
SR-90 4.240E+01 0.02 %
TC-99 3.420E+00 0.00 %
ZN-65 2.200E+01 0.01 %
ZR-95 1.884E+01 0.01 %
Total Activity (Ci) 260.087 100.00 %
Container Volume 22.770 ft3 0.645 2-30
Table 2-21 Annual Waste Release Summary Report Year: 2004 Class: B Volume Reduction Vendor: No Source: Non-Processed DAW Container: HIC (High Integrity Container)
Process: Non-Processed Nuclides Activity (mCi) % of Total C-14 < 2.270E+O0 0.01 %
CE-144 1.050E+00 0.00 t CM-244 2.950E-03 0.00 %
CO-S8 2.700E+00 0.01 %
CO-60 1.860E+03 6.82 %
CR-51 1.090E-04 0.00 t CS-137 2.680E+00 0.01 t FE-55 2.460E+04 90.25 t H-3 4.870E-01 0.00 %
I-129 < 3.880E+01 0.14 %
MN-54 4.440E+02 1.63 %
NB-95 6.920E+00 0.03 %
NI-59 1.280E+00 0.00 %
NI-63 2.150E+02 0.79 %
PU-238 1.840E-03 0.00 %
SB-125 6.900E+01 0.25
- SN-113 9.830E-01 0.00 %
TC-99 2.210E+00 0.01 %
ZN-65 2.620E+0O 0.01 %
ZR-95 7.730E+00 0.03 %
Total Activity (Ci) 27.258 100.00 %
Container Volume 109.600 ft3 3.104 m3 2-31
Table 2-22 Annual Waste Release Summary Report Year: 2004 Class: B Volume Reduction Vendor: No Source: RWCU Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides Activity (mCi) % of Total
______________ 0.00______
AM-241 1.650E-02 0.00 %
C-14 < 5.020E-05 0.00%
CE-144 5.970E+02 0.03 %
CM-242 1.160E-02 0.00 %
CM-244 5.420E-02 0.00 %
CO-58 8.640E+02 0.04 %
CO-60 2.500E+05 11.68 %
CR-51 4.110E+02 0.02 %
CS-137 8.040E+02 0.04 %
FE-55 1.630E+06 76.15 %
H-3 < 9.810E-04 0.00 %
I-129 < 8.910E-05 0.00 %
MN-54 2.450E+05 11.45 %
NB-95 1.910E+03 0.09 %
NI-63 5.470E+03 0.26 t SB-125 2.160E+03 0.10 %
SN-113 3.770E+02 0.02 %
SR-89 1.790E+0l 0.00 %
TC-99 1.020E+0l 0.00 %
ZN-65 6.690E+02 0.03 %
ZR-95 2.170E+03 0.10 %
Total Activity (Ci) 2140.460 100.00 %
Container Volume 132.400 ft3 3.749 m3 2-32
Table 2-23 Annual Waste Release Summary Report Year: 2004 Class: B Volume Reduction Vendor: Yes Source: Chem-Decon Resin Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 3.580E-0l 0.18 %
CO-58 2.110E+00 1.09 %
CO-60 2.660E+0l 13.68 %
CR-51 1.43OE+02 73.55 %
CS-137 8.150E-0l 0.42 %
FE-55 3.080E+00 1.58 %
H-3 8.560E+00 4.40 %
1-129 3.060E-03 0.00 %
MN-54 9.260E-01 0.48 %
NB-95 1.120E-01 0.06 %
NI-63 1.290E+00 0.66 %
SB-124 2.200E-01 0.11 %
SR-90 6.780E+O0 3.49 %
TC-99 4.540E-03 0.00 %
ZN-65 4.630E-01 0.24 %
ZR-95 1.OlOE-01 0.05 %
Total Activity (Ci) 0.194 100.00 %
Container Volume 3.580 ft3 0.101 m3 2-33
Table 2-24 Annual Waste Release Summary Report Year: 2004 Class: B Volume Reduction Vendor: Yes Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) t of Total
________ ______________ 0.00______
C-14 7.260E-02 0.00 %
CE-144 1.960E+01 0.02 %
CM-244 8.270E-04 0.00 %
CO-58 7.350E+01 0.06 t CO-60 5.210E+03 4.14 CR-51 1.530E+01 0.01 %
CS-137 9.610E+00 .0.01
!6 FE-55 1.120E+05 88.95 FE-59 2.490E+01 0.02 H-3 2.630E+01 0.02 1-129 4.060E-01 0.00 MN-54 8.430E+03 6.70 NB-95 2.800E-01 0.00 NI-59 1.180E+00 0.00 NI-63 8.370E+01 0.07 SB-124 4.170E+00 0.00 SR-90 1.100E+01 0.01 TC-99 6.430E-02 0.00 Total Activity (Ci) 125.910 100.00 %
Container Volume 14.740 ft3 0.417 m3 2-34
Table 2-25 Annual Waste Release Summary Report Year: 2004 Class: C Volume Reduction Vendor: Yes Source: CFS Backwash Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 2.290E-06 0.00 %
CO-58 2.530E-05 0.01 %
CO-60 1.330E-02 5.02 %
CR-51 7.750E-06 0.00 %
CS-137 1.810E-05 0.01 %
FE-55 2.400E-01 90.64 t H-3 4.490E-05 0.02 %
MN-54 1.130E-02 4.27 %
NI-63 9.780E-05 0.04 %
Total Activity (Ci) <0.001 100.00 t Container Volume 14.750 ft3 0.418 m3 2-35
Table 2-26 Annual Waste Release Summary Report Year: 2004 Class: C Volume Reduction Vendor: Yes Source: Chem-Decon Resin Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 2.200E+00 0.13 %
CO-58 1.550E+0l 0.92 %
CO-60 1.640E+02 9.70 %
CR-51 1.370E+03 81.03 %
CS-137 5.010E+00 0.30 %
FE-55 1.920E+0l 1.14 %
H-3 5.280E+0l 3.12 %
I-129 1.880E-02 0.00 %
MN-54 5.920E+00 0.35 %
NB-95 9.830E-Ol 0.06 %
NI-63 7.900E+00 0.47 %
SB-124 1.660E+00 0.10 %
SR-90 4.170E+01 2.47 %
TC-99 2.790E-02 0.00 %
ZN-65 3.OOOE+00 0.18 %
ZR-95 7.510E-01 0.04 %
Total Activity (Ci) 1.691 100.00 %
Container Volume 19.600 ft3 0.555 m3 2-36
Table 2-27 Annual Waste Release Summary Report Year: 2004 Class: C Volume Reduction Vendor: Yes Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 5.046E-02 0.00 %
CE-144 1.282E+0l 0.01 %
CM-242 5.161E-04 0.00 %
CO-58 4. 011E+01 0.05 %
CO-60 3.590E+03 4.18 t CR-51 5.880E+00 0.01 %
CS-137 6.663E+00 0.01 t FE-55 7.664E+04 89.19 t FE-59 1. 187E+0l 0.01 %
H-3 1.818E+Ol 0.02 %
1-129 2.818E-0l 0.00 %
MN-54 5.537E+03 6.44 %
NB-95 1.212E-0l 0.00 *%
NI-59 8.200E-0l 0.00 %
NI-63 5.813E+0l 0.07 %
SB-124 2.183E+00 0.00 %
SR-90 7.599E+00 0.01 %
TC-99 4.468E-02 0.00 %
Total Activity (Ci) 85.932 100.00 %
Container Volume 7.860 ft3 0.223 m3 2-37
Table 2-28 Annual Waste Release Summary Report Year: 2004 Class: A Volume Reduction Vendor: Yes Source: Condensate Demineralizer / Radwaste Demineralizer Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 1.340E+02 0.33 %
CE-144 9.203E-51 0.00 %
CO-58 1.952E+03 4.86 %
CO-60 2.457E+04 61.15 %
CR-51 2.761E+02 0.69 %
CS-137 1.301E+0l 0.03 %
FE-55 8.460E+03 21.05 %
FE-59 4.417E+01 0.11 %
H-3 4.483E+02 1.12 %
I-129 6.608E-02 0.00 %
I-131 1.185E-02 0.00 %
MN-54 3.840E+03 9.56 t NB-95 1.077E+00 0.00 '%
NI-59 - 7.240E-0l 0.00 %
NI-63 1.508E+Ok 0.38
- SR-89 1.470E-01 0.00 %
TC-99 1.999E-0l 0.00 %
ZN-65 2.920E+02 0.73 %
ZR-95 1.525E+00 0.00 %
Total Activity (Ci) 40.188 100.00 %
Container Volume 233.630 ft3 6.616 m3 2-38
SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 3-1
METEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the Susquehanna SES (SSES) site since the early 1970s. At the present time, the meteorological system is based on a 300-foot high tower located approximately 1,000 feet to the southeast of the plant. Wind sensors are mounted at the 10m and 60m elevations on this tower.
Vertical temperature differential is measured with redundant sensor pairs between the 10m and 60m levels. Sigma theta (the standard deviation of horizontal wind direction) is calculated from wind direction at both levels. Dew point and ambient temperature sensors are present at the 10m level. Precipitation is measured at ground level.
A back-up meteorological tower was erected in 1982. It is a 1lOm tower providing alternate measurements of wind speed, wind direction, and sigma theta. A 10m supplemental downriver meteorological tower is also available. This tower measures wind speed, wind direction, sigma theta, temperature and dew point.
SSES meteorological data are transmitted to the plant Control Room, Technical Support Center, Emergency Operations Facility for emergency response availability, and ABSG Consulting, Inc. ABSG Consulting, Inc., located in Rockville, Maryland, provides meteorological consulting services to PPL Susquehanna, LLC.
Dispersion modeling for effluents from normal operation of SSES is done using the MIDAS system XDCALC program, a straight-line Gaussian plume model designed to estimate average relative concentration. The model was developed in accordance with Regulatory Guide 1.111. For periods when the wind speed is calm, the actual wind direction that 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 3-1 SSES METEOROLOGICAL DATA RECOVERY FOR 2004 PERCENT VALID PARAMETER DATA RECOVERY Wind Speed 1Om - Primary (y)99.0 Wind Speed 60m - Primary 99.1 Wind Speed lOm - Backup(2) 99.9 Wind Speed I Om - Downriver(3) 99.8 Wind Direction IOm - Primary 99.1 Wind Direction 60m - Primary 99.1 Wind Direction lOmi- Backup 100.0 Wind Direction lOm - Downriver 99.8 Temperature I Om -Primary 99.0 Dew Point I Om - Primary 98.8 Delta Temperature 60m - Primar 99.0 Sigma Theta lOm -Primary 99.1 Sigma Theta 60m - Primary 99.1 Sigma Theta 1Om- Backup 100.0 Sigma Theta I Om - Downriver 99.8 Precipitation - Primary 96.3 Composite Parameters Wind Speed and Direction 1Om, 98.9 Delta Temperature 60-lOm Wind Speed and Direction 60m, 99.0 Delta Temperature 60-lOm
"'SSES "Primary" meteorological tower (2)SSES "Backup" meteorological tower (3)SSES "Downriver" meteorological tower 3-3
TABLE 3-2 SSES Joint Frequency Distribution of Wind Speed and Direction lOm Versus Delta Temperature 60-lOm for the Period of January 1,2004 through December 31, 2004 SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:10M - Direction:lOM Lapse:DT60-10 Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19 -25 >25 Total N 0 1 2 1 0 0 4 NNE 2 3 4 0 0 0 9 NE 2 11 4 0 0 0 17 ENE 4 4 0 0 0 0 8 E 5 2 0 0 0 0 7 ESE 2 3 0 0 0 0 5 SE 2 5 13 1 0 0 21 SSE 0 1 3 0 0 0 4 S 0 10 17 0 0 0 27 SSW 1 24 9 0 0 0 34 SW 3 45 62 11 0 0 121 WSW 2 9 17 7 0 0 35 W 0 1 5 0 0 0 6 WNW 0 1 3 0 0 0 4 NW 0 1 0 1 0 0 2 NNW 0 0 0 1 0 0 1 Total 23 121 139 22 0 0 305 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 305 Total Hours for the Period 8783 3-4
TABLE 3-2 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:1OM Direction:1OM Lapse:DT60-10 Stability Class B Delta Temperature Moderately Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 1 6 7 0 0 0 14 NNE 0 6 13 1 0 0 20 NE 5 17 4 0 0 0 26 ENE 3 1 0 0 0 0 4 E 2 1 1 0 0 0 4 ESE 2 0 0 0 0 0 2 SE 3 1 4 0 0 0 8 SSE 1 2 5 0 0 0 8 S 2 2 1 0 0 0 5 SSW 2 25 1 0 0 O 28 SW 1 54 47 6 0 0 108 WSW 1 7 15 3 0 0 26 W 0 1 5 0 0 0 6 WNW 0 1 4 0 0 0 5 NW 0 0 7 5 0 0 12 NNW 0 3 5 3 0 0 11 Total 23 127 119 18 0 0 287 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 287 Total Hours for the Period 8783 3-5
TABLE 3-2 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:lOM Direction:1OM Lapse:DT60-10 Stability Class C Delta Temperature Slightly Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 3 9 14 1 0 0 27 NNE 6 23 7 0 0 0 36 NE 6 18 1 0 0 0 25 ENE 8 6 0 0 0 0 14 E 5 1 0 0 0 0 6 ESE 3 1 1 0 0 0 5 SE 5 6 7 2 0 0 20 SSE 5 4 3 0 0 0 12 S 5 13 8 0 0 0 26 SSW 7 31 4 0 0 0 42 SW 3 75 39 11 0 0 128 WSW 0 22 30 5 1 0 58 W 0 0 7 3 0 0 10 WNW 1 4 4 0 0 0 9 NW 1 4 14 1 0 0 20 NNW 0 3 13 1 0 0 17 Total 58 220 152 24 1 0 455 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 455 Total Hours for the Period 8783 3-6
TABLE 3-2 (continued)
SITE: SSES Hours at Each Wind Speed and Direction*
Period of Record 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:1OM Direction:lOM Lapse:DT60-10 Stability Class D Delta Temperature Neutral Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 27 122 85 1 0 0 235 NNE 88 221 50 0 0 0 359 NE 108 152 19 0 0 0 279 ENE 88 32 5 0 0 0 125 E 98 32 2 0 0 0 132 ESE 93 36 5 0 0 0 134 SE 92. 70 16 0 0 0 178 SSE 66 79 6 1 0 0 152 S 70 100 14 0 0 0 184 SSW 71 133 13 0 0 0 217 SW 56 186 144 17 1 0 404 WSW 14 82 89 47 3 0 235 W 11 34 59 23 0 0 127 WNW 6 42 62 14 0 0 124 NW 9 49 173 40 0 0 271 NNW 6 91 158 15 0 0 270 Total 903 1461 900 158 4 0 3426 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 3426 Total Hours for the Period 8783 3-7
TABLE 3-2 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:1OM Direction:1OM Lapse:DT60-10 Stability Class E Delta Temperature Slightly Stable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 38 94 6 0 0 0 138 NNE 174 150 12 3 1 0 340 NE 319 80 7 0 0 0 406 ENE 318 23 3 0 0 0 346 E 215 13 4 0 0 0 233 ESE 133 19 5 5 0 0 162 SE 134 22 7 1 0 0 164 SSE 107 34 10 3 0 0 154 S 134 88 17 1 0 0 240 SSW 97 114 3 0 0 0 214 SW 61 98 23 3 0 0 185 WSW 18 39 11 1 0 1 70 W 17 20 1 0 0 0 38 WNW 7 13 1 0 0 0 21 NW 13 17 5 0 0 0 35 NNW 11 43 13 1 0 0 68 Total 1796 867 128 18 1 1 2814 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 2811 Total Hours for the Period 8783 3-8
TABLE 3-2 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:lOM Direction:10M Lapse:DT60-10 Stability Class F Delta Temperature Moderately Stable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 4 3 0 0 0 0 7 NNE 23 10. 0 0 0 0 33 NE 147 4 0 0 0 0 151 ENE 457 5 0 0 0 0 462 E 126 0 0 0 0 0 126 ESE 52 0 0 0 0 0 52 SE 32 0 0 0 0 0 32-SSE 25 4 0 0 0 0 29 S 44 3 0 0 0 0 47 SSW 15 4 0 0 0 0 19 SW 4 7 0 0 0 0 11 WSW 1 1 0 0 0 0 2 W 0 1 0 0 0 0 1 WNW 0 1 0 0 0 0 1 NW 2 1 0 0 0 0 3 NNW 2 1 0 0 0 0 3 Total 934 45 0 0 0 0 979 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 979 Total Hours for the Period 8783 3-9
TABLE 3-2 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:lOM Direction:1OM Lapse:DT60-10 Stability Class G Delta Temperature Extremely Stable Wind Speed (mph)
Wind Direction 1-4 4-8 B-13 13-19 19-25 >25 Total N 1 0 0 0 0 0 1 NNE 3 2 0 0 0 0 5 NE 84 2 0 0 0 0 86 ENE 222 1 0 0 0 0 223 E 57 0 0 0 0 0 57 ESE 25 0 0 0 0 0 25 SE 11 0 0 0 0 0 11 SSE 7 0 0 0 0 0 7 S 7 0 0 0 0 0 7 SSW 1 0 0 0 0 0 1 SW 1 0 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 Total 420 5 0 0 0 0 425 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 425 Total Hours for the Period 8783 3-10
TABLE 3-2 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:lOM Direction:lOM Lapse:DT60-10 Summary of All Stability Classes Delta Temperature Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 74 235 114 3 0 0 426 NNE -296 415 86 4 1 0 802 NE 671 284 35 0 0 0 990 ENE 1100 72 8 0 0 0 1182 E 508 49 7 0 0 0 565 ESE 310 59 *11 5 0 0 385 SE 279 104 47 4 0 0 434 SSE 211 124 27 4 0 0 366 S 262 216 57 1 0 0 536 SSW 194 331 30 0 0 0 555 SW 129 465. 315 48 1 0 958 WSW 36 160 162 63 4 1 426 W 28 57 77 26 0 0 188 WNW 14 62 74 14 0 0 164 NW 26 72 199 .47 0 0 344 NTt 19 141 189 21 0 0 370 Total 4157 2846 .1438 240 6 1 8691 Number of Calm Hours for this Table 3 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 92 Number of Valid Hours for this Table 8688 Total Hours for the Period 8783 3-11
TABLE 3-3 SSES Joint Frequency Distribution of Wind Speed and Direction 60m Versus Delta Temperature 60-1 Om for the Period of January 1, 2004 through December 31, 2004 SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 0 0 0 ' 2 0 0 2 NNE 0 7 6 1 0 0 14 NE 2 7 8 2 0 0 19 ENE 5 3. 1 0 0 0 9 E 1 1 0 0 0 0 2 ESE 0 1 0 0 0 0 1 SE 3 3 9 2 0 0 17 SSE 0 1 7 1 1 0 10 S 0 0 3 3 0 0 6 SSW 1 13 11 16 2 0 43 SW 5 30 48 21 1 0 105 WSW 1 5 12 36 6 1 61 W 0 0 4 6 0 0 10 WNW 0 0 2 1 0 0 3 NW 0 0 0 2 0 0 2 NNW 0 1 o 0 0 0 1 Total 18 72 111 93 10 1 305 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 305 Total Hours for the Period 8783 3-12
TABLE 3-3 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Stability Class B Delta Temperature Moderately Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 0 2 8 2 0 0 12 NNE 2 6 16 3 0 0 27 NE 3 6 12 2 0 0 23 ENE 4 0 1 0 0 0 5 E 1 0 2 0 0 0 3 ESE 0 0 0 0 0 0 0 SE 2 0 3 1 0 0 6 SSE 0 2 2 2 0 0 6 S 1 2 1 2 0 0 6 SSW 4 8 5. 4 0 0 21 SW 0 17 63 14 0 1 95 WSW 0 5 17 24 2 0 48 W 0 0 1 6 1 0 8 WNW 0 0 5 1 0 0 6 NW 0 0 2 7 2 0 11 NNW 0 2 4 4 0 0 10 Total 17 50 142 72 5 1 287 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 287 Total Hours for the Period 8783 3-13
TABLE 3-3 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record 01/01/04 .1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Stability Class C Delta Temperature Slightly Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 1 9 12 5 0 0 27 NNE 3 17 16 4 0 0 40 NE 2 20 6 1 0 0 29 ENE 3 5 0 0 0 0 8 E 3 3 0 0 0 0 6 ESE 0 1 1 0 0 0 2 SE 1 2 6 0 2 0 11 SSE 3 1 4 3 0 0 11 S 7 4 8 4 0 0 23 SSW 5 17 11 8 0 0 41 SW 2 30 58 12 0 0 102 WSW 0 9 37 41 9 2 98 W 1 1 5 9 1 0 17 WNW 0 1 4 2 0 0 7 NW 0 2 4 9 0 0 15 NNW 1 4 9 5 0 0 19 Total 32 126 181 103 12 2 456 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 456 Total Hours for the Period 8783 3-14
TABLE 3-3 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record
- 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Stability Class D Delta Temperature Neutral Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 15 65 90 28 0 0 198 NNE
- 51 117 166 37 1 0 372 NE 63 97 118 18 2 0 298 ENE 64 38 12 2 0 0 116 E 48 37 18 0 0 0 103 ESE 42 28 26 3 0 0 99 SE 34 52 37 10 0 0 133 SSE 32 58 36 2 2 0 130 S 39 44 61 18 4 0 166 SSW 41 74 54 20 4 0 193 SW 40 135 121 38 6 0 340 WSW 18 67 124 161 47 4 421 W 6 18 62 84 20 2 192 WNW 4 24 73 .52 5 0 158 NW 3 24 127 109 4 0 267 TNW 9 26 136 69 1 0 241 Total 509 904 1261 651 96 6 3427 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 3427 Total Hours for the Period 8783 3-15
TABLE 3-3 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Stability Class E Delta Temperature Slightly Stable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 38 110 39 1 0 0 188 NNE 115 271 71 17 1 4 479 NE 151 151. 93 6 1 0 402 ENE 68 55 13 1 0 0 137 E 71 35 10 4 0 0 120 ESE 51 29 9 5 5 0 99 SE 46 35 17 8 2 0 108 SSE 51 48 20 6 4 0 129 S 60 53 49 22 5 2 191 SSW 60 73 87 16 1 0 237 SW 37 132 104 11 1 0 285 WSW 17 46 101 59 4 1 228 W 7 28 19 5 0 0 59 WNW 3 14 11 1 0 0 29 NW 4 14 31 3 0 0 52 NNW 10 21 36 4 0 0 71 Total 789 1115 710 169 24 7 2814 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 2814 Total Hours for the Period 8783 3-16
TABLE 3-3 (continued)
SITE: SSES Hours at Each Wind Speed and Direction*
Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Stability Class F Delta Temperature Moderately Stable Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >.25 Total N 22 60 4 0 0 0 86 NNE 95 244 11 0 0 0 350 NE 87 64 3 0 0 0 154 ENE 42 8 0 0 0 0 50 E 31 8 0 0 0 0 39 ESE 23 4 0 0 0 0 27 SE 20 6 0 0 0 0 26 SSE 16 5 0 0 0 0 21 S 13 20 2 0 0 0 35 SSW 17 33 10 0 0 0 60 SW 3 41 14 0 0 0 *58 WSW 0 9 41 5 0 0 55 W 1 2 1 0 0 0 4 WNW 0 4 1 0 0 0 5 NW 0 2 2 0 0 0 4 NNW 2 2 1 0 0 0 5 Total 372 512 90 5 0 0 979 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 979 Total Hours for the Period 8783 3-17
TABLE 3-3 (continued)
SITE: SSES Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Stability Class G Delta Temperature Extremely Stable Wind Speed (mph)
Wind Direction 1-4 4- 8 8 - 13 13 - 1919 - 25 >2s Total N 13 28 1 0 0 0 42 NNE 38 58 2 0 0 0 98 NE 57 23 0 0 0 0 80
.ENE 30 .5.. 0 0 0 35 E 22 2 0 0 0 0 24 ESE 16 1 0 0 0 0 17 0
SE 10 5 0 0 0 15 0
SSE 10 3 0 0 0 13 0
S 11 9 1 0 0 21 0
SSW 8 21 9 0 0 38 0
SW 6 16 .5 0 0 27 0
WSW 0 2 7 0 0 9 0
W 0 0 0 0 0 0 0
0o WNW 0 0 0 0 0 0 0
NW 0 2 1 0 0 3 0
NNW 1 2 0 0 0 3 0
Total 222 177 26 0 0 425 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 425 Total Hours for the Period 8783 3-18
TABLE 3-3 (continued)
SITE: SSES
- Hours at Each Wind Speed and Direction Period of Record = 01/01/04 1:00 12/31/04 23:00 Total Period Elevation: Speed:60M Direction:60M Lapse:DT60-10 Summary of All Stability Classes Delta Temperature Wind Speed (mph)
Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 89 274 154 38 0 0 555 NNE 304 720 288 62 2 4 1380 NE 365 368 240 ~29 3 0 1005 ENE 216 114 27 3 0 0 360 E 177 86
- 30 4 0 0 297 ESE 132 64 36 8 5 0 245 SE 116 103 72 21 4 0 316 SSE 112 118 69 14 7 0 320 S 131 132 125 49 9 2 448 SSW 136 239 187 64 7 0 633 SW 93 401 413 96 8 1 1012 WSW 36 143 339 326 68 8 920 W 15 49 92 110 22 2 290 WNW 7 43 96 57 5 0 208 NW 7 44 167 130 6 0 354 NNW 23 58 186 82 1 0 350 Total 1959 2956 2521 1093 147 17 8693 Number of Calm Hours for this Table 0 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 90 Number of Valid Hours for this Table 8693 Total Hours for the Period . 8783 3-19
C (. (
TABLE 34 2004 SSES ANNUAL RELATIVE CONCENTRATIONS NO DECAY, UNDEPLETED X/Q (sec/mr3 )
DATES OF LAST X/Q ACCUMULATION ARE FROM 4 1 1 1 0 TO 4123124 0 X/Q ACCUMULATION FOR GROUND AVERAGE 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
- DIRECTION FROM N 4.1804E-06 8.1592E-07 3.3904E-07 1.7797E-07 1.1451E-07 4.2651E-08 1.1707E-08 5.6727E-09 3.5709E-09 2.5283E-09
- DIRECTION FROM NNE 9.8064E-06 2.0458E-06 9.1022E-07 4.8328E-07 3.1157E-07 1.1546E-07 3.1429E-08 1.5379E-08 9.7423E-09 6.9408E-09
- DIRECTION FROM NE 2.0463E-05 3.9284E-06 1.7818E-06 1.0064E-06 6.6693E-07 2.6403E-07 7.9892E-08 4.0190E-08 2.5861E-08 1.8792E-08
- DIRECTION FROM ENE 4.1915E-05 7.9631E-06 3.8761E-06 2.2807E-06 1.5198E-06 5.9915E-07 1.7331E-07 8.4233E-08 5.4647E-08 4.0038E-08
- DIRECTION FROM E 1.8881E-05 3.5034E-06 1.5280E-06 8.5667E-07 5.7179E-07 2.3210E-07 7.2936E-08 3.6810E-08 2.3733E-08 1.7266E-08
- DIRECTION FROM ESE 1.1927E-05 2.3312E-06 1.0478E-06 5.8436E-07 3.8795E-07 1.5664E-07 4.3348E-08 1.9002E-08 1.2181E-08 8.8067E-09
- DIRECTION FROM SE 1.1598E-05 2.3236E-06 1.0545E-06 5.9071E-07 3.9079E-07 1.5861E-07 3.9302E-08 1.4445E-08 9.2056E-09 6.6049E-09
- DIRECTION FROM S 7.2604E-06 1.5494E-06 7.5884E-07 4.4213E-07 3.0372E-07 1.4128E-07 3.9301E-08 1.3562E-08 8.6575E-09 6.2148E-09
- DIRECTION FROM SSW 6.9240E-06 1.4035E-06 6.4246E-07 3.6190E-07 2.3926E-07 9.8772E-08 2.5463E-08 9. 6434E-09 6.1080E-09 4.3476E-09
- DIRECTION FROM SW 6.1553E-06 1.2352E-06 5.8338E-07 3.3312E-07 2.2310E-07 9.7702E-08 2.5121E-08 8.4395E-09 5.3318E-09 3.7811E-09
- DIRECTION FROM WSW 2.7911E-06 5.4621E-07 2.5496E-07 1.4999E-07 1.0287E-07 4.8883E-08 1.5408E-08 5.8092E-09 2.9882E-09 1.6424E-09
- DIRECTION FROM W 1.2573E-06 2.4999E-07 1.0862E-07 5.9533E-08 3.9272E-08 1.6322E-08 4.4815E-09 1.8260E-09 1.1397E-09 7.9953E-10
- DIRECTION FROM WNW 1.0642E-06 1.9703E-07 7.9001E-08 4.1305E-08 2.6350E-08 9.7243E-09 2.6404E-09 1.2491E-09 7.7341E-10 5.3768E-10
- DIRECTION FROM NW 2.2284E-06 4.1368E-07 1.6606E-07 8.5342E-08 5.4402E-08 1.9809E-08 5.2971E-09 2.5246E-09 1.5698E-09 1.0976E-09
- DIRECTION FROM NNW 2.5207E-06 4.8608E-07 2.0582E-07 1.0934E-07 6.9049E-08 2.4188E-08 6.0600E-09 2.8860E-09 1.7943E-09 1.2530E-09 3-20
( ( (
TABLE 3-5 2004 SSES ANNUAL RELATIVE CONCENTRATIONS 2.26-DAY DECAY, UNDEPLETED X/Q (sec/M3 )
DATES OF LAST X/Q ACCUMULATION ARE FROM 4 1 1 1 0 TO 4123124 0 X/Q ACCUMULATION FOR GROUND DECAYED S.AVG 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
- DIRECTION FROM N 4.1727E-06 8.1140E-07 3.3589E-07 1.7564E-07 1.1258E-07 4.1446E-08 1.1046E-08 5.1478E-09 3.1171E-09 2.1227E-09
- DIRECTION FROM NNE 9.7854E-06 2.0326E-06 9.0040E-07 4.7596E-07 3.0550E-07 1.1172E-07 2.9408E-08 1.3764E-08 8.3417E-09 5.6859E-09
- DIRECTION FROM NE 2.0403E-05 3.8940E-06 1.7558E-06 9.8580E-07 6.4938E-07 2.5252E-07 7.3044E-08 3.4614E-08 2.0988E-08 1.4371E-08
- DIRECTION FROM ENE 4.1776E-05 7.8836E-06 3.8119E-06 2.2281E-06 1.4749E-06 5.6996E-07 1.5686E-07 7.1371E-08 4.3358E-08 2.9756E-08
- DIRECTION FROM E 1.8806E-05 3.4617E-06 1.4978E-06 8.3304E-07 5.5158E-07 2.1858E-07 6.4675E-08 3 .0133E-08 1.7941E-08 1.2055E-08
- DIRECTION FROM ESE 1.1882E-05 2.3050E-06 1.0282E-06 5.6909E-07 3.7494E-07 1.4796E-07 3.8667E-08 1.5707E-08 9.3331E-09 6.2558E-09
- DIRECTION FROM SE 1.1559E-05 2.2998E-06 1.0366E-06 5.7663E-07 3.7883E-07 1.5057E-07 3.5409E-08 1.2142E-08 7.2215E-09 4.8368E-09
- DIRECTION FROM SSE 8.3147E-06 1.6377E-06 7.2025E-07 4.0016E-07 2.6699E-07 1.1264E-07 2.8037E-08 9.3995E-09 5.6309E-09 3.7972E-09
- DIRECTION FROM S 7.2418E-06 1.5375E-06 7.4910E-07 4.3417E-07 2.9669E-07 1.3586E-07 3.6330E-08 1.1898E-08 7.2116E-09 4. 9163E-09
- DIRECTION FROM SSW 6.9090E-06 1.3943E-06 6.3546E-07 3.5638E-07 2.3457E-07 9.5567E-08 *2.3836E-08 8.6415E-09 5.2416E-09 3.5739E-09
- DIRECTION FROM SW 6.1450E-06 1.2288E-06 5.7833E-07 3.2908E-07 2.1962E-07 9.5163E-08 2.3828E-08 7.7311E-09 4.7193E-09 3.2347E-09
- DIRECTION FROM WSW 2.7870E-06 5.4377E-07 2.5304E-07 1.4840E-07 1.0146E-07 4.7761E-08 1.4699E-08 5.3698E-09 2.6770E-09 1.4261E-09
- DIRECTION FROM W 1.2552E-06 2.4869E-07 1.0767E-07 5.8805E-08 3.8651E-08 1.5888E'08 4.2432E-09 1.6667E-09 1.0029E-09 6.7819E-10
- DIRECTION FROM WNW 1.0628E-06 1.9621E-07 7.8451E-08 4.0903E-08 2.6018E-08 9.5185E-09 .2.5282E-09 1.1615E-09 6.9837E-10 4.7135E-10
- DIRECTION FROM NW 2.2254E-06 4.1196E-07 1.6490E-07 8.4491E-08 5.3696E-08 1.9371E-08 5.0566E-09 2.3336E-09 1.4049E-09 9.5028E-10
- DIRECTION FROM NNW 2.5177E-06 4.8431E-07 2.0456E-07 1.0840E-07 6.8282E-08 2.3735E-08 5.8309E-09 2.7049E-09 1.6380E-09 1.1137E-09 3-21
C C (
TABLE 3-6 2004 SSES ANNUAL RELATIVE CONCENTRATIONS 8-DAY DECAY, DEPLETED X/Q (sec/mr3 )
DATES OF LAST X/Q ACCUMULATION ARE FROM 4 1 1 1 0 TO 4123124 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
- DIRECTION FROM N 3.8194E-06 6.9110E-07 2.7419E-07 1.3788E-07 8.5772E-08 2.9665E-08 7.2131E-09 3.0497E-09 1.7201E-09 1.1048E-09
- DIRECTION FROM NNE 8.9587E-06 1.7324E-06 7.3582E-07 3.7418E-07 2.3320E-07 8.0211E-08 1.9319E-08 8.2361E-09 4.6680E-09 3.0127E-09
- DIRECTION FROM NE 1.8690E-05 3.3244E-06 1.4389E-06 7.7803E-07 4.9820E-07 1.8282E-07 4.8789E-08 2. 1292E-08 1.2205E-08 8.0004E-09
- DIRECTION FROM ENE 3.8279E-05 6.7365E-06 3.1283E-06 1.7619E-06 1.1343E-06 4.1424E-07 1.0554E-07 4.4422E-08 2.5630E-08 1.6911E-08
- DIRECTION FROM E 1.7240E-05 2.9621E-06 1.2321E-06 6.6092E-07 4.2600E-07 1.6001E-07 4.4160E-08 1.9224E-08 1.0980E-08 7.1649E-09
- DIRECTION FROM ESE 1.0891E-05 1.9714E-06 8.4511E-07 4.5103E-07 2.8919E-07 1.0808E-07 2.6289E-08 9.9509E-09 5.6561E-09 3.6717E-09
- DIRECTION FROM SE 1.0592E-05 1.9655E-06 8.5096E-07 4.5622E-07 2.9156E-07 1.0959E-07 2.3901E-08 7.5998E-09 4.3026E-09 2.'7770E-09
- DIRECTION FROM SSE 7.6170E-06 1.3984E-06 5.9043E-07 3.1596E-07 2.0496E-07 8.1634E-08 1.8767E-08 5.8021E-09 3.2906E-09 2.1268E-09
- DIRECTION FROM S 6.6320E-06 1.3116E-06 6.1309E-07 3.4205E-07 2.2709E-07 9.7976E-08 2.4075E-08 7.2219E-09 4. 1155E-09 2.6705E-09
- DIRECTION FROM SSW 6.3255E-06 1.1885E-06 5.1935E-07 2.8020E-07 1.7907E-07 6.8615E-08 1.5654E-08 5.1662E-09 2.9284E-09 1.8890E-09
- DIRECTION FROM SW 5.6240E-06 1.0464E-06 4.7189E-07 2.5814E-07 1.6717E-07 6.8000E-08 1.5501E-08 4.5495E-09 2.5787E-09 1.6614E-09
- DIRECTION FROM WSW 2.5503E-06 4.6279E-07 2.0630E-07 1.1628E-07 7.7126E-08 3.4052E-08 9.5230E-09 3. 1396E-09 1.4502E-09 7.2473E-10
- DIRECTION FROM W 1.1488E-06 2.1177E-07 8.7863E-08 4.6133E-08 2.9425E-08 1.1358E-08 2.7639E-09 9.8328E-10 5.5021E-10 3.5039E-10
- DIRECTION FROM WNW 9.7247E-07 1.6696E-07 6.3934E-08 3.2031E-08 1.9761E-08 6.7774E-09 1.6336E-09 6.7620E-10 3.7618E-10 2.3789E-10
- DIRECTION FROM NW 2.0362E-06 3.5053E-07 1.3439E-07 6.6175E-08 4.0794E-08 1.3802E-08 3.2744E-09 1.3643E-09 7.6149E-10 4.8380E-10
- DIRECTION FROM NNW 2.3035E-06 4.1194E-07 1.6660E-07 8.4813E-08 5.1806E-08 1.6870E-08 3.7546E-09 1.5659E-09 8.7557E-10 5.5671E-10 3-22
C (.
TABLE 3-7 2004 SSES ANNUAL RELATIVE DEPOSITION (D/Q metcrs-2)
DATES OF LAST X/Q ACCUMULATION ARE FROM 4 1 1 1 0 TO 4123124 0 X/Q ACCUMULATION FOR DEPOSITION 1/M2 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
- "DIRECTION FROM N 2.4507E-08 3.6110E-09 1.4810E-09 7.0194E-10 4.1483E-10 1.3147E-10 3.1451E-11 1.1580E-11 6. 1806E-12 3.8829E-12
- DIRECTION FROM NNE 4.3324E-08 6.7129E-09 2.9116E-09 1.3848E-09 8.1520E-10 2.5400E-10 5.9211E-11 2.1801E-ll 1.1636E-11 7.3100E-12
- DIRECTION FROM NE 5.0007E-08 7.5424E-09 3.2250E-09 1.5609E-09 9.2604E-10 2.9830E-10 7.3091E-11 2.6911E-11 1.4363E-11 9. 0237E-12
- DIRECTION FROM ENE 6.3576E-08 9.8723E-09 4.3962E-09 2.1508E-09 1.2706E-09 4.0212E-10 9. 1633E-11 3.2130E-11 1.7149E-11 1.0774E-11
- DIRECTION FROM E 2.9465E-08 4.3041E-09 1.7536E-09 8.3729E-10 4.9957E-10 1.6475E-10 4.1714E-11 1.5358E-11 8.1973E-12 5.1498E-12
- DIRECTION FROM ESE 2.3139E-08 3.4977E-09 1.4913E-09 7.1997E-10 4.3014E-10 1.4264E-10 3.2406E-11 1.0465E-11 5.5858E-12 3.5092E-12
- DIRECTION FROM SE 3.1230E-08 4.7456E-09 2.0726E-09 1.0235E-09 6.1438E-10 2.0759E-10 4.3203E-11 1.1825E-11 6.3112E-12 3.9649E-12
- DIRECTION FROM SSE 2.4907E-08 3.7177E-09 1.5837E-09 7.8201E-10 4.7661E-10 1.7063E-10 3.7432E-11 9.9489E-12 5.3101E-12 3.3360E-12
- DIRECTION FROM S 2.6072E-08 4.1800E-09 1.9631E-09 1.0088E-09 6.2875E-10 2.4335E-10 5.6798E-11 1.4570E-11 7.7765E-12 4.8855E-12
- DIRECTION FROM SSW 3.2447E-08 4.9629E-09 2.2260E-09 1. 1269E-09 6.8205E-10 2.3797E-10 5.2865E-11 1.5086E-11 8.0522E-12 5.0587E-12
- DIRECTION FROM SW 5.0407E-08 8.0019E-09 3.7648E-09 1.9480E-09 1.2036E-09 4.5249E-10 1.0222E-10 2.6041E-11 1.3899E-11 8.7320E-12
- DIRECTION FROM WSW 2.5603E-08 3.9466E-09 1.8432E-09 9.8678E-10 6.2740E-10 2.5875E-10 7.2817E-11 2.1039E-11 9.2106E-12 4.5183E-12
- DIRECTION FROM W 9.4524E-09 1.4188E-09 6.1392E-10 3. 0635E-10 1.8671E-10 6.6845E-11 1.6311E-ll 5.1104E-12 2.7276E-12 1.7136E-12
- DIRECTION FROM WNW 9.1661E-09 1.3226E-09 5.3292E-10 2.5469E-10 1.5131E-10 4.9017E-11 1.2108E-11 4.4580E-12 2.3794E-12 1.4948E-12
- DIRECTION FROM NW 2.0735E-08 3.0353E-09 1.2162E-09 5.6575E-10 3.3449E-10 1.0619E-10 2.5471E-11 9.3781E-12 5.0054E-12 3.1446E-12
- DIRECTION FROM NNW 2.2471E-08 3.3372E-09 1.4100E-09 6.8162E-10 3.9927E-10 1.2171E-10 2.7391E-11 1.0085E-11 5.3826E-12 3.3816E-12 3-23
TABLE 3-8 2004 ATM16SPHERIC DISPERSION ESTIMATES FOR RETDAS INPUT AT SELECTED LOCATIONS AFFECTED LOCATION MILES X/Q( ) X/Q DEC(2) X/Q DEC+DEP(3)- DEPOSITION(4 )
SECTOR _ _ _ _ _ _ _ _ _ _ Q__
_ _ X___DEC_____D 1I/SW Maximum (X/Q) Site Boundary 0.6 1.46E-05 1.46E-0S 1.32E-05 3.38E-08 9/S Closest (X/Q) Site Boundary 0.38 6.05E-06 6.05E-06 5.64E-06 3.71 E-08 12/WSW Maximum (X/Q) Residence 1.3 9.97E-06 9.88E-06 8.52E-06 1.25E-08 7/SE Maximum (D/Q) Residence 0.5 2.15E-06 2.14E-06 1.96E-06 1.96E-08 7/SE Maximum (DIQ) Garden 0.6 1.64E-06 1.64E-06 1.48E-06 1.44E-08 12/WSW Maximum (D/Q) Dairy 1.7 6.84E-06 6.76E-06 5.72E-06 8.17E-09 12/VSW Maximum (DIQ) Meat Producer 1.7 6.84E-06 6.76E-06 5.72E-06 8.17E-09 3/NE Riverlands / EIC 0.7 3.89E-06 3.88E-06 3.47E-06 2.91 E-08 12/WSW Tower's Club 0.5 3.34E-05 3.32E-05 3.05E-05 5.02E-08 5/E East Gate 0.5 1.39E-06 I 1.39E-06 1.27E-06 I1.02E-08 NEAREST RESIDENCE WITHIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES XIQ X/Q DEC DC E DEPOSITION NUMBER SECTOR DEC+DEP _____
I N H.Burd 1.3 1.90E-06 1.89E-06 1.63E-06 5.26E-09 2 NNE E.Ashbridge III 1 2.57E-06 2.56E-06 2.24E-06 9.92E-09 3 NE W.Tuggle 0.9 2.68E-06 2.68E-06 2.36E-06 1.91 E-08 4 ENE D.Barberi 2.1 3.32E-07 3.29E-07 2.73E-07 2.38E-09 5 E L.Kozlowski 1.4 2.77E-07 2.76E-07 2.36E-07 1.59E-09 6 ESE R.Panetta 0.5 1.17E-06 1.17E-06 1.07E-06 9.88E-09 7 SE J.Futoma 0.5 2.15E-06 2.14E-06 1.96E-06 1.96E-08 8 SSE J.Naunczek 0.6 2.06E-06 2.05E-06 1.85E-06 1.72E-08 9 S S.Slusser I 1.55E-06 1.54E-06 1.35E-06 7.49E-09 10 SSW S.Molnar 0.9 4.43E-06 4.41 E-06 3.88E-06 1.64E-08 1 SW F.Michael 1.5 4.OOE-06 3.97E-06 3.39E-06 7.59E-09 12 WSW F.Michael 1.3 9.97E-06 9.88E-06 8.52E-06 1.25E-08 13 W F. Hummel 1.2 5.07E-06 5.01 E-06 4.35E-06 6.45E-09 14 WNW R.Orlando 0.8 6.44E-06 6.40E-06 5.69E-06 1.IOE-08 15 NW H.Long 0.8 6.38E-06 6.34E-06 5.64E-06 1.50E-08 16 NNW W.Metzler 0.6 5.66E-06 5.64E-06 5.11 E-06 1.58E-08 NEAREST GARDEN WITHIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES X/Q X/Q DEC DC E DEPOSITION NUMBER SECTOR ________DEC+DEP I N J.Wojcik 3.2 5.06E-07 4.97E-07 3.96E-07 1.18E-09 2 NNE R.Chapin 2.3 7.56E-07 7.48E-07 6.16E-07 2.61 E-09 3 NE Yokum 2.7 5.27E-07 5.22E-07 4.22E-07 3.31 E-09 4 ENE G.Dennis 2.4 2.76E-07 2.74E-07 2.24E-07 1.99E-09 5 E W.Daily 1.8 1.87E-07 1.86E-07 1.56E-07 1.05E-09 6 ESE L.Travelpiece 2.5 7.91 E-08 7.86E-08 6.40E-08 5.31E-10 7 SE F.Scholl 0.6 1.64E-06 1.64E-06 1.48E-06 1.44E-08 8 SSE M.Zaletko 1.6 4.31 E-07 4.29E-07 3.63E-07 2.93E-09 9 S M.Cope 1.1 1.33E-06 1.33E-06 1.15E-06 6.30E-09 10 SSW S.Bodnar 1.2 2.87E-06 2.86E-06 2.47E-06 9.88E-09 II SW H.Schultz 1.9 2.81 E-06 2.78E-06 2.32E-06 5.18E-09 12 WSW F.Michael 1.3 9.97E-06 9.88E-06 8.52E-06 1.25E-08 13 W F.Hummel 1.2 5.07E-06 5.01 E-06 4.35E-06 6.45E-09 14 WNW P.Moskaluk 1.3 2.97E-06 2.94E-06 2.54E-06 4.55E-09 15 NW D.Goff 1.8 1.80E-06 1.78E-06 1.50E-06 3.58E-09 16 NNW P.Culver 4 3.25E-07 3.17E-07 2.47E-07 5.87E-10 3-24
TABLE 3-8 (continued)
NEAREST ANIMAL RAISED FOR MEAT CONSUMPTION WITHIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES l Q XIQ DEC l E P DEPOSITION NUMBER SECTOR ___________ ____DEC+DEP DPSTO 2 NNE R.Chapin 2.3 7.56E-07 7.48E-07 6.16E-07 2.61 E-09 4 ENE G.Dennis 2.4 2.76E-07 2.74E-07 2.24E-07 1.99E-09 5 E W.Daily 1.8 1.87E-07 1.86E-07 1.56E-07 1.05E-09 10 SSW R. & C. Ryman 3 6.44E-07 6.35E-07 5.08E-07 1.93E-09 10 SSW C.K.Drasher 3.5 4.50E-07 4.43E-07 3.48E-07 1.28E-09 12 WSW T. & M. Berger 1.7 6.84E-06 6.76E-06 5.72E-06 8.17E-09 ALL DAIRY LOCATIONS NEAR SSES SECTOR AFFECTED NAME MILES XIQ X/Q DEC X/Q DEPOSITION NUMBER SECTOR DEC+DEP 5 E W.Bloss 4.5 3.87E-08 3.81 E-08 2.90E-08 1.84E-10 6 ESE D.Moyer 2.7 6.81 E-08 6.76E-08 5.46E-08 4.48E-10 6 ESE F.Rinehimer 4.2 2.73E-08 2.70E-08 2.07E-08 1.59E-10 10 SSW R. & C. Ryman 3 6.44E-07 6.35E-07 5.08E-07 1.93E-09 10 SSW R.Ryman 3.1 5.98E-07 5.90E-07 4.70E-07 1.77E-09 10 SSW C.K.Drasher 3.5 4.50E-07 4.43E-07 3.48E-07 1.28E-09 10 SSW K.Davis 14.01 3.58E-08 3.36E-08 2.23E-08 6.84E-II 12 WSW T . & M. Berger 1.7 6.84E-06 6.76E-06 5.72E-06 8.17E-09 13 W J. & N. Dent 5 4.50E-07 4.32E-07 3.30E-07 3.72E-10 16 NNW H.Shoemaker 4.2 3.04E-07 2.97E-07 2.30E-07 5.39E-10 1 X/Q RELATIVE CONCENTRATION (SEC/M3 )
3 2 X/Q DEC DECAYED AND UNDEPLETED, HALF-LIFE 2.26 DAYS (SEC/M )
3 3 X/Q DEC+DEP DECAYED AND DEPLETED, HALF-LIFE 8 DAYS (SEC/M )
2 4 DEPOSITION RELATIVE DEPOSITION RATE (1/H )
3-25
FIGURE 3-1 SSES 2004 ANNUAL WVIND ROSE 10M LEVEL - PRIMARY TOWER all WIND ROSE CWINDS FROM)
N
- 1. .,.
0.02% PERCENT CALMS (NOT INCLUDED INPLOT A6 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 2004, the predominant wind direction occurred 13.6% 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 2.3 mph. The sector with the highest average wind speed was NW (9.2 mph.).
3-26
FIGURE 3-2 SSES 2004 ANNUAL WIND ROSE 60M LEVEL - PRIMIARY TOWER 12 WIND ROSE XlMNDS FROM)
N 0O.00% PERCENT CALMS (NOT INCLUDED INPLOT)
WIND SPEED LESS THAN 3.5 MPH
- WIND SPEED LESS THAN 7.5 MPH o VWND SPEED LESS THAN 12.5 MPH WIVND SPEED GREATERTHAN 12.5 MPH This wind rose displays the frequency of hourly average wind direction from a given sector. In 2004, the predominant wind direction occurred 15.9% 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 6.1 mph. The sector with the highest average wind speed wavs WSW ( 1.9 mph.).
3-27
FIGURE 3-3 SSES PASQUIL STABILITY CLASS PREVALENCES DATA Period: 2004 SSES Joint Frequency Distributions at 10 Meters Wind Speed and Direction 1OM vs. Delta Temperature 60-1 OM
. (Based on 8,676 Valid Hours)
A G 3.5% B 4.9% 3.3%
.. F3%
11 .3% ist E D 32.4% 39.4%
3-28
SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 4-1
Radiological Impact on Man Sampling and analysis of airborne and waterborne effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (LLD) outlined in the SSES Technical Requirements.
Radioactive material was detected in some of the airborne and waterborne effluent samples analyzed. Dose calculations using measured effluent activity levels, meteorological data from the current reporting period and average river flow dilution factors resulted in estimated doses to individuals at levels below 10 CFR 20 and 10 CFR 50, Appendix I limits. Direct radiation resulting from plant operation (reported in the 2004 Annual Radiological Environmental Operating Report) contributed a maximum of 3.88E-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 1.18E0 mrem (CHILD, LUNG Table 4-4). The maximum organ/total body dose from all liquid effluent is 2.07E-3 mrem (ADULT, GI-LLI Table 4-4). 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 (1.22E0 mrem) is 4.9% of the 40CFR1 90 limit of 25 mrem to total body/organ (except thyroid) and 1.6% of the 40CFR1 90 limit of 75 mrem to the thyroid.
Doses to a maximally exposed member of the public from waterborne effluents are calculated for fish ingestion and shoreline exposure at the plant outfall, and drinking water ingestion at Danville, PA. Site specific parameters used in the calculations for the Danville receiver, specific for actual average blowdown and river level for the entire year are shown in Table 4-1.
TABLE 4-1 SITE-SPECIFIC PARAMETERS USED FOR RETDAS CALCULATIONS (DANVILLE RECEIVER)
FOR 2004 PARAMETER ENTIRE YEAR Cooling Tower Blowdown (CFS) 19.6 Average Net River Level (ft.) 8.0 Dilution Factor at Danville(') 869.6 Transit time to Danville (hr.)(') 16.5
(')From ODCM-QA-005, Att. E 4-2
Summaries of maximum individual doses resulting from airborne and waterborne radioactive effluent releases are given in Table 4-2. Meteorological data from Section 3 were used to calculate the dose from airborne effluents.
The Radioactive Effluent Release Report includes 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. There are no significant exposure pathways from waterborne effluents in these areas. 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 residence and garden with the maximum X/Q and D/Q value, the dairy and meat producing farm with the maximum D/Q value, and the site boundary with the maximum X/Q value.
Summaries of the calculated maximum doses within the site boundary and selected locations resulting from airborne effluents are presented in Tables 4-3 and 4-4. The above referenced locations are shown on Figure 4-1.
In the area comprising the Riverlands recreation area, which surrounds the Energy Information Center, three pathways of radiation exposure can be identified: plume, ground, and inhalation. There are no significant exposure pathways from waterborne effluents in this area. There are approximately 100,000 visitors to the Riverlands/Information Center complex each year. For dose calculations, it is assumed the visitor stays in the area for one hour.
Use of the RETDAS code yields calculated doses for the Riverlands area for the report period. These doses are the total doses at the location from gaseous effluents during the report period.
4-3
TABLE 4-2
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES TO MEMBERS OF THE PUBLIC DATA PERIOD: 1/1/04 TO 12/31/04 ESTIMATED MAAXINMUNM LIMIT AGE APPLICABLE DOSE PERCENT (NIRENI/
UNIT EFFLUENT GROUP ORGAN (MIRENMIIRAD) LOCATION OF LIMIT MIRAD)t 2 )
DIST AFFECTED
(_MILES) SECTOR I Liquid(X) Child Total Body 4.87E-4 (3) 0.02 3 I Liquid(" Adult GI-LLI 1.04E-3 (3) 0.01 10 I Noble Gas N/A Air Dose 6.31 E-2 0.5 WSW 0.63 10 (Gamma-MRAD)
I Noble Gas N/A Air Dose 2.31E-2 0.5 WSW 0.12 20 (Beta-MRAD)
I Airborne Child Lung 6.63E-1 0.5 WSW 4.4 15 Iodine, Tritium and Particulates __
2 Liquid(l) Child Total Body 4.87E-4 (3) 0.02 3 Liquid(l)
- Adult +
GI-LLI 4-1.04E-3 t (3) 4 0.01 4 10 2 Noble Gas N/A Air Dose 2.14E-2 0.5 WSW 0.21 10 (Gamma-MRAD) 2 Noble Gas N/A Air Dose 7.68E-3 0.5 WSW 0.04 20 (Beta-MRAD) 2 Airborne Child Lung 5.20E-1 0.5 WSW 3.5 15 Iodine, Tritium and I Particulates I I I I I I
(')Estimated dose is based on a site total activity release equally divided between Unit 1 and Unit 2.
(2)10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year for airborne and waterborne effluent from each unit.
3b 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.
4-4
TABLE 4-3 CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/INFORMATION CENTER COMPLEX DATA PERIOD: 1/1/04 TO 12/31/04 COLLECTIVE APPLICABLE DOSE RATE(') DOSE( 2' EFFLUENT AGE GROUP ORGAN (MIREMMHR) (PERSON-REM)
Noble Gas N/A Total Body 1.12E-06 1.12E-04 Noble Gas NIA Skin 4.09E-07 4.09E-05 Iodine, Tritium and Child Total Body 1.61 E-05 1.61 E-03 Particulates I I I
(')Estimated dose and dose rate is based on annual site total activity release.
(2)Collective 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. Maximum site boundary XI T Total (All) 5.15E-01 (CHILD) 5.1 9E-01 (CHILD, LUNG) 5.18E-01 (CHILD)
- 2. Maximum X/Q Residence 4__Maximum_____Dairy___Meat Total (All) 3.53E-01 (CHILD) 3.53E-01 (CHILD, LUNG) 3.53E-01 (CHILD)
- 3. Maximum DIQ Garden
_______________Total (All) 5.98E-02 (CHILD) 6.00E.02 (CHILD, GI-LLI) 5.96E-02 (CHILD)
- 4. Maximum DIQ Dairy & Meat
_______________Total (All) 2.42E.O1 (CHILD) 2.42E-O1 (CHILD, LUNG) 2.42E.O1 (CHILD)
- 5. Towers Club Total (All) 1.18E 00 (CHILD) 1.18E 00 (CHILD, LUNG) 1.18E 00 (CHILD)
- 6. Riverland/EIC Total (All) 1.41E-01 (CHILD) 1.41 E-01 (CHILD, GI-LLI) 1.41 E-01 (CHILD)
- 7. Gate No. 10 Guard House Total (All) 5.04E-02 CHILD 5.05E-02 (CHILD, GI-LLI) 5.03E-02 (CHILD)
Note: The doses shown above are based on 100% occupancy at the indicated locations.
Note: The doses shown above are based on a composite of all applicable pathways resulting in a total dose to the maximally exposed individual due to airborne effluents from both Unit-1 and Unit-2 operations.
4-6
FIGURE 4-1 AIRBORNE-DOSE CALCULATION LOCATIONS
- Indicates airborne-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) individual procedures.
The following ODCM procedures were revised during 2004 (effective dates in parentheses) to update position titles, revise "Annual Effluent and Waste Disposal Report" title to "Radioactive Effluent Release Report" and to add applicable 'Adherence Level" to each procedure cover page:
ODCM-QA-001, ODCM Introduction (November 18, 2004); ODCM-QA-002, ODCM Review and Revision Control (December 30, 2004).
ODCM-QA-003, Effluent Monitor Setpoints, was revised January 28, 2004. The revision: 1) deleted references to particulate and iodine gaseous effluent monitor setpoints; 2) revised references 3.12 and 3.13; 3) relocated sections 6.3 and 6.4 to ODCM-QA-004 Airborne Effluent Dose Calculations. Additionally, ODCM-QA-003 was revised September 30, 2004 to update position titles.
ODCM-QA-004, Airborne Effluent Dose Calculations, was revised January 28, 2004.
The revision: 1) added section 6.3 which outlines methodology for determination of particulate/iodine limiting release rates and limiting release concentrations; 2) added section 6.4 which incorporates line loss correction factors to support gaseous effluent release concentration calculations; 3) added Attachment E to support determination of particulate/iodine limiting release rate calculations; 4) revised "Annual Effluent and Waste Disposal Report" title to "Radioactive Effluent Release Report". Additionally, ODCM-QA-004 was revised October 11, 2004 to update position titles.
ODCM-QA-008, Radiological Environmental Monitoring Program, was revised January 28, 2004. The revision: 1) updated Attachment C to incorporate a complete list of TLD locations; 2) updated Attachments A, B and the reference section to correspond with revised Attachment C; 3) clarified the requirements of the Interlaboratory Comparison Program; 4) made minor typographical corrections.
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 following Unit-1 and Unit-2 TRM sections were revised December .3, 2004 to update the "Annual Effluent and Waste Disposal Report" title to "Radioactive Effluent Release Report": 3.11.1.4, 3.11.1.5, 3.11.2.6, 3.11.4.1, 3.11.4.2, B3.11.2.1 and B3.11.4.1.
5-2
Unit-1 and Unit-2 TRM Table 3.11.2.1-1 was revised January 21, 2004 to clarify gaseous effluent sampling in support of start-up, shutdown and thermal power changes greater than 15% of rated thermal power within a one hour period. This TRM revision is a result of the deletion of the requirements for particulate and iodine gaseous effluent monitoring from Unit-1 and Unit-2 TRM section 3.11.2.6.
Unit-1 TRM section B3.11.2.5 revised October 15, 2004 to delete references to Unit-2 filtered exhaust system filters.
Unit-2 TRM section B3.11.2.5 revised October 15, 2004 to delete references to Unit-1 filtered exhaust system filters.
Unit-1 and Unit-2 TRM sections 3.11.2.6, B3.11.2.5, B3.11.2.6 and Table 3.11.2.6-1 were revised January 21, 2004 to reflect deletion of the requirements for particulate and iodine gaseous effluent monitors.
There were no changes to the Unit-I or Unit-2 TRM Section 3.6.1 during 2004.
5-3
PROCESS CONTROL PROGRAM CHANGES The following changes were made to the Process Control Program and implementing procedures during 2004. 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 (as necessary) as documented on the attached summary of procedure changes. The following procedures were changed:
- 1. NDAP-QA-0646, Process Control Program
- 2. CH-RC-075, Sample Preparation and Analysis of Dewatered Radwaste
- 3. WM-PS-1 00, Shipment of Radioactive Waste
- 4. WM-PS-110, General Shipment of Radioactive Material
- 5. WM-PS-180, Advanced Notification of Applicable States
- 6. WM-PS-210, Packaging and Loading of DAW and Radioactive Material
- 7. WM-PS-230, Receipt, Use, Storage and Shipment of High Integrity Containers
- 8. WM-PS-250, Use of RADMAN and RAMSHP Computer Programs
- 9. WM-PS-310, Use of the 10-142B (USA/92081B) Shipping Cask
- 10. WM-PS-311, Use of the 10-142A Shipping Package
- 11. WM-PS-318, Use of Tandem Container Transport (TCT)
- 12. WM-PS-351, Use of the CNS 21-200 (USA9096/A)
- 13. WM-PS-354, Use of the CNSI 14-215H Series A, NUCPAC 14/210L, and NUPAC 14/210H Shipping Packages
- 14. WM-PS-356, Use of the CNSI 8-120 (USA/9168/B(u)) Shipping Package
- 15. WM-RP-009, Combustible Gas Check and Closure of Processing Liners and High Integrity Containers
- 16. WM-RP-010, Liner Decanting
- 17. WM-RP-011, Waste Sluicing
- 18. WM-RP-012, Handling and Use of Steel Liners and High Integrity Containers
- 19. WM-RP-104, Gross Dewatering 5-4
- 20. WM-RP-105, Cartridge Filter Processing and Packaging
- 21. WM-RP-106, Transfer and Dewatering Bead Resin
- 22. WM-RP-107, Transfer and Dewater A (B) RWCU Phase Separator
- 23. WM-RP-109, Transfer and Dewater of Waste Sludge Phase Separator
- 24. WM-RP-1 10, Transfer and Dewatering of Waste Mix Tanks
- 25. WM-RP-111, Drying Waste
- 26. ME-ORF-165, Fuel Pool Cleanout - Duratek - Handling Procedure for 3-55 Cask C of C #5805 at PPL Susquehanna LLC NDAP-QA-0646 continues to fully implement the requirements and intent of the following:
- 1. Sections 11.4 and 13.5 of the FSAR
- 2. Section 3.7.4 of the Technical Requirements Manual
- 3. 10 CFR 20,10 CFR 61,10 CFR 71,49 CFR 100-177, and 40 CFR 261-Compliance with all applicable regulatory requirements listed above continues to be met as the result of these changes to the program. These changes to the Process Control Program will not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.
5-5
PROCEDURE REVISION
SUMMARY
NDAP-QA-0646, Revision 9
- 1. Revised Responsibility Section to reflect current staffing.
- 2. Add responsibilities of Supervising Quality Control Specialist to describe Quality control Inspection function relative to radioactive waste/material processing, packaging and shipping.
- 3. Add "Transition" section to describe implementation of Quality Control function, based on LDCN 3741.
5-6
PROCEDURE REVISION
SUMMARY
CH-RC-075, Revision 7
- 1. Procedure CH-RC-075 is being revised to reflect changes in NDAP-QA-0646, Solid Radwaste Process Procedure. Part of the NDAP-QA-0646 revision added steps for Effluents personnel to request the specific analyses required to each sample provided to the Chemistry laboratory for analyses.
- 2. PCAF-2003-1744 is being incorporated, as this PCAF is identical except for the FUM Approval signature. The main focus of this PCAF remains elimination of specific sample analysis requirements for sample types. Since sample analysis frequency vary, NDAP-QA-0646 has been revised to require that required sample analyses for each sample be provided by Effluents Management.
- 3. Procedure Cover Sheet titles have been revised.
- 4. Added Applicability Number A-01-161 1 to Reference (section 2.5).
- 5. Added clarification for Step 3.1.
- 6. Added step 3.2.3 to state sample analyses and composite requirements will be delineated by Effluents personnel.
- 7. Added step 6.3
- 8. Revised step 7.1.2 to state that sample analyses and composite requirements will be delineated by Effluents personnel on Form NDAP-QA-0646-2.
- 9. Revised step 7.2.1.a to add volume of waste proportional to what is in liner or transfer volume specified on sample request paperwork for multiple samples for a single batch or liner.
- 10. Reworded step 7.2.6 to clarify steps if there is more than one sample and mixing is required.
- 11. Revised steps 7.2.7 and separated some actions to a new step 7.2.8.
- 12. Revised step 7.2.8 and renumbered remaining steps.
- 13. Revised steps 7.2.10 and 7.2.11.
- 14. Existing NOTE revised and a new NOTE was added to section 7.3 to clarify isotopic analysis requirements.
- 15. Reworded steps 7.3.1 and 7.3.2 (editorial) 5-7
- 16. Added subsection 7.3.4.c AND NOTE to step 7.3.4 as there may be situations where two separate gamma isotopic analyses are required. Effluents personnel may need a gamma spectroscopy analysis on a smaller sample for shipping purposes (e.g. a separate smaller sample to meet deadline requirements).
A second gamma spectroscopy analysis of the actual sample being shipped may be required for Effluents personnel to compare vendor gamma isotopic results with. The gamma spectroscopy analysis for the actual sample sent to vendor does not need to meet deadtime requirements.
- 17. Deleted Note (2) in step 7.3.5. Effluents personnel will delineate analysis steps required.
- 18. Deleted Note (1) designation and designated as "Note". Revised Note to skip steps 7.3.6 and 7.3.7 if a compositing is not required.
- 19. Revised step 7.3.6 to eliminate nominal sample volumes to be composited.
Effluents personnel will delineate volumes to be composited.
- 20. Revised step 7.3.8 to transfer and store unused sample with radwaste services vendor.
5-8
PROCEDURE REVISION
SUMMARY
WM-PS-100, Revision 9
- 1. Incorporated several changes throughout the procedure to comply with new requirements in 49 CFR which take effect on October 1, 2004.
- 2. Modified several definitions due to the changes in 49 CFR.
- 3. Modified changes to the requirements for shipping papers. Allowed the use of a manifest for the shipping paper. Made a Bill of Lading optional and changed what is required to be on the Bill of Lading.
- 4. Clarified the requirements to track a shipment until it reaches the final destination.
- 5. Incorporated several minor enhancements and administrative changes throughout the procedure.
5-9
PROCEDURE REVISION
SUMMARY
WM-PS-110, Revision 5
- 1. Incorporated several changes throughout the procedure to comply with new requirements in 40 CFR which take effect on October 1, 2004.
- 2. Modified several definitions due to the changes in 49 CRF.
- 3. Modified changes to the requirements for shipping papers. Allowed the use of a manifest for the shipping paper. Made a Bill of Lading optional and clarified what is required to be on the Bill of Lading.
- 4. Incorporated several minor enhancements and administrative changes throughout the procedure.
- 5. Updated Form WM-PS-1 10-2 due to new method of determining if a material is radioactive.
5-10
PROCEDURE REVISION
SUMMARY
WM-PS-180, Revision 7
- 1. Changed adherence level to reference use.
- 2. Added PPL contact to Form WM-PS-180-3 in response to CR 519365.
- 3. Added requirement to contact the Nebraska Dept. of Health and Human Services prior to shipping high level radioactive waste or transuranic waste through Nebraska.
5-11
PROCEDURE REVISION
SUMMARY
WM-PS-210, Revision 7
- 1. Changed marking requirements in section 6.1.7 and added Attachment K and miscellaneous sections to comply with the new DOT package marking requirements.
- 2. Added requirement to document the loading of non-friable asbestos on Form WM-PS-21 0-1. Made other minor changes to the form requirements.
- 3. Updated the Air Transport Packaging Data Sheet, Form WM-PS-210-2.
5-12
PROCEDURE REVISION
SUMMARY
WM-PS-230, Revision 1
- 1. Updated procedure adherence level.
5-13
PROCEDURE REVISION
SUMMARY
WM-PS-250, Revision 4
- 1. Changed procedure adherence level to comply with NDAP-QA-0029.
- 2. Changed prerequisite for control of passwords lAW NDAP-QA-0801. (CRA 571633).
5-14
PROCEDURE REVISION
SUMMARY
WM-PS-310, Revision 3
- 1. Change to section 6.3 due to change in the vendor's procedure change (OM-101-WS).
5-15
PROCEDURE REVISION
SUMMARY
WM-PS-311, Revision 3
- 1. Updated procedure adherence level.
5-16
PROCEDURE REVISION
SUMMARY
WM-PS-318, Revision 3
- 1. Updated procedure adherence level.
5-17
PROCEDURE REVISION
SUMMARY
WM-PS-351, Revision 1
- 1. Updated procedure adherence level.
5-18
PROCEDURE REVISION
SUMMARY
WM-PS-354, Revision 3
- 1. Incorporated PCAF's 99-6532 and 2000-3339 into this PCAF. NRC Specification Package certifications have expired on 4/1/99. All references to the NRC specification packaging have been deleted. Procedure has been updated so that the cask can be used as a Type A, IP-I, IP-Il, IP-Ill, modified Type A package or a strong tight package. Steps specific to the use of the cask as an NRC specification package have been deleted or updated. Various administrative changes have been made throughout the procedure.
5-19
PROCEDURE REVISION
SUMMARY
WM-PS-354, Revision 4
- 1. Incorporated PCAF 2004-1327.
- 2. Added NUPAC 14-215 cask to this procedure.
- 3. Changed "strong, tight" package to "general design" package throughout this procedure.
- 4. Incorporated high intensity light inspection on cask upon receipt and prior to installing the primary lid per CR 613944 and updated the cask checklist (Form WM-PS-354-1).
5-20
PROCEDURE REVISION
SUMMARY
WM-PS-356, Revision 1
- 1. Updated procedure adherence level.
5-21
PROCEDURE REVISION
SUMMARY
WM-RP-009, Revision 4
- 1. Added container closure to this procedure. This includes instruction and form for documentation. This was done to consolidate the instruction for these two related evolutions into a single procedure.
5-22
PROCEDURE REVISION
SUMMARY
WM-RP-010, Revision 3
- 1. Updated procedure adherence level.
- 2. Added Operations interface section.
- 3. Deleted settling time determination.
- 4. Defined settling time as: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for bead resin, grit and sand, 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> for all other wastes.
- 5. Improved procedural instruction for establishing and securing dewatering flowpath.
- 6. Established criteria for when a container is properly decanted.
- 7. Add form to document decanting.
- 8. Incorporated Human Performance formatting.
5-23
PROCEDURE REVISION
SUMMARY
WM-RP-010, Revision 4
- 1. Added provisions for container sampling to the procedure to keep procedures consistent.
5-24
PROCEDURE REVISION
SUMMARY
WM-RP-011, Revision 3
- 1. Incorporated Human Performance formatting.
- 2. Updated procedure adherence level and cover page.
- 3. Deleted instructions for liner overfill that were incorporated under PCAF 1 1081.
- 4. Changed "Dewatering Pump" to "Transfer Pump" where appropriate.
- 5. Added reference to "Gross Dewatering" procedure.
- 6. Deleted reference to WM-RP-001, "Dewatering Pump Skid Operation".
5-25
PROCEDURE REVISION
SUMMARY
WM-RP-012, Revision 6
- 1. Incorporated Human Performance format.
- 2. Deleted inspection form for EL-1 90/EL-210 Liner and all related procedure steps.
- 3. Updated or deleted vendor names as appropriate.
- 4. Added ability to use powdered resin or sludge internals for processing LRWF or RWCU media.
5-26
PROCEDURE REVISION
SUMMARY
WM-RP-104, Revision 5
- 1. Title change to more accurately reflect content of procedure.
- 2. Incorporated Human Performance Enhancements into procedure.
- 3. Added drawings of plant valves and vendor skid for reference.
- 4. Major editorial changes throughout procedure.
- 5. Made procedure specific to Gross Dewatering and Liner sampling.
5-27
PROCEDURE REVISION
SUMMARY
WM-RP-105, Revision 5
- 1. Incorporated Human Performance formatting.
- 2. Updated cover sheet.
- 3. Moved gas check and closure to WM-RP-009.
- 4. Replaced "Effluents Management Shipping Specialist" to "Health Physicist-Radwaste or Designee"
- 5. Improved documentation on form WM-RP-105-1.
5-28
PROCEDURE REVISION
SUMMARY
WM-RP-106, Revision 5
- 1. Incorporated Human Performance enhancements into procedure.
- 2. Added operations interface section to specify discussions that must take place between Effluents and operations prior to and during transfers.
- 3. Added drawings of plant valves and vendor skid for reference.
- 4. Major editorial changes throughout procedure.
- 5. Made procedures specific to Transfer and Dewatering, drying, decanting and closure have been moved to other procedures.
5-29
PROCEDURE REVISION
SUMMARY
WM-RP-107, Revision 7
- 1. Procedure now specific to transfer and dewatering of RWCU.
- 2. Instructions for sampling and drying have been moved to another procedure.
- 3. Instructions for container closure, combustible gas and waste on top of the container, have been moved to other procedures.
5-30
PROCEDURE REVISION
SUMMARY
WM-RP-109, Revision 0
- 1. Procedure is now specific to transfer and dewatering waste sludge.
- 2. Drying and transfer of other waste streams are now in other procedures.
- 3. Instruction for container closure has been moved to another procedure.
5-31
PROCEDURE REVISION
SUMMARY
WM-RP-110, Revision 0
- 1. Procedure now specific to transfer and dewatering of waste mix.
- 2. Instructions for drying have been moved to another procedure.
- 3. Instruction for container closure has been moved to another procedure.
5-32
PROCEDURE REVISION
SUMMARY
WM-RP-111, Revision 0
- 1. New procedure specific to drying waste in liners and high integrity containers.
- 2. Instruction was previously contained in WM-RP-106 and WM-RP-107.
5-33
PROCEDURE REVISION
SUMMARY
ME-ORF-165, Revision I
- 1. A copy of the current revision of Certificate of Compliance NO. 5805 shall be available on site prior to use of shipping package.
- 2. PPL shall be a registered use of the model CNS 3-55 shipping package with the Nuclear Regulatory Commission.
- 3. A copy of all documents referenced in the current revision of the certificate of compliance to the use and maintenance of the packaging and to the actions taken prior, shall be available on site prior to use of the shipping package, (i.e.
applicable drawing and/or safety and design evaluations).
5-34
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 manner.
None to report for 2004.
- 2. TRM Action 3.11.1.5.C.1 requires the reporting of Radioactive Liquid Process Effluent Monitoring Instrumentation inoperability not corrected in a timely manner.
None to report for 2004.
- 3. TRM Action 3.11.2.6.K requires an explanation for Radioactive Gaseous Effluent Monitoring Instrumentation required actions and completion times not met.
None to report for 2004.
- 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 2004.
- 5. TRM Action 3.11.4.2.A requires reporting when land use census identifies a new location which yields a calculated dose or dose commitment greater than the values currently being calculated in Requirement 3.11.2.3 (Gaseous Effluent Dose due to Iodine, Tritium, and Radionuclides in Particulate Form).
None to report for 2004.
- 6. TRM Action 3.11.4.2.B requires reporting when land use census identifies locations that yield 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 2004.
- 7. The 40CFR1 90.10 standard for normal operation for the uranium fuel cycle including annual dose equivalent and total quantities of radioactive material limits was 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 2004.
6-2
SECTION 7 CORRECTIONS TO DOSES REPORTED IN PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS 7-1
CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENT AND WASTE DISPOSAL REPORTS No corrections to previous Radioactive Effluent Release Reports are submitted for this report period.
7-2
SECTION 8 EFFL UENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS 8-1
EFFLUENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS Insignificant Effluent Pathways are: 1) evaporation from the Unit 1 and Unit 2 Condensate Storage Tanks (CST's); 2) evaporation from the common Refueling Water Storage Tank (RWST); 3) gaseous effluent from the Hydrogen Seal Oil, 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. Additionally, in October 2004 the auxiliary steam system was identified as contaminated with low levels of tritium (-1 E-5 pC/cc).
Airborne release to the environment from auxiliary steam system operation during 2004 is estimated based on conservative assumptions of system maximum vent flow rates and maximum identified tritium concentration levels. Offsite dose due to the release of 4.58E-4 Ci tritium from the auxiliary steam system operation during 2004 is included in the maximum dose to the public from insignificant effluents. 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, except for tritium, released from insignificant effluent pathways are negligible compared to the airborne release data shown in Tables 2-1 and 2-2. The maximum dose to the public from a release of 33.6 Ci of tritium is calculated to be 2.48-01 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 U2-CST and Main Turbine/RFPT Main Turbine/RFPT Nuclide RNN'ST Lube Oil Systems Lube Oil Svstems Aux. Steam System Total (Ci) (Ci) (Ci) (Ci) (Ci)
H-3 8.347E-02 1.609E+01 1.739E+01 4.58E-04 3.357E+Ol Mn-54 3.050E-09 3.313E-08 1.653E-07 2.015E-07 Co-60 8.822E-09 1.490E-07 2.339E-07 3.917E-07 Cs-137 3.452E-10 O.OOOE+OO -O.OOOE+OO 3.452E-lO Xe-135 O.OOOE+OO 2.238E-06 1.127E-05 1.351 E-05 Co-58 3.311 E-1 O O.OOOE+OO 7.254E-09 7.585E-09 Y-91m 1.809E-10 O.OOOE+OO O.OOOE+OO 1.809E-10 Sb-125 4.346E-09 O.OOOE+OO O.OOOE+OO 4.346E-09 Cr-51 1.276E-09 3.822E-08 5.902E-08 9.851 E-08 Fe-S9 O.OOOE+OO O.OOOE+OO 1.469E-08 1.469E-08 Xe-133 O.OOOE+OO 2.740E-06 3.081E-06 5.822E-06 8-3