ML071290153
| ML071290153 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/30/2007 |
| From: | Doebler R, Hickey F, Rhoads B Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML071290153 (101) | |
Text
Susquehanna Steam Electric Station Units 1 & 2 Radioactive Effluent Release Report 2006 Annual Report
- i-, ,*; Al...
RADIOACTIVE EFFLUENT RELEASE REPORT REPORT PERIOD: 01/01/06 - 12/31/06 Prepared by:
Francis J. HickW Health Physicist Reviewed by:
Raymor( E. Doebler-Chemistry Support Supervisor Approved by:
Manager - Plant Chemistry PPL Susquehanna, LLC 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 Radioactive Effluent 7-1 Release Reports
- 8. Effluent from Systems Classified as Insignificant Effluent Pathways 8-1 Appendix A ODCM/TRM
LIST OF TABLES PAGE Table 1-1 Technical Requirement Limits 1-10 Table 2-1 Airborne Effluent - Summation of All Releases 2-3 Table 2-2 Airborne Effluent - Radionuclides Released 2-4 Table 2-3 Waterborne Effluent - Summation of All Releases 2-7 Table 2-4 Waterborne Effluent- Radionuclides Released 2-8 Table 2-5 Estimated Total Errors Associated with 2-11 Effluents Measurements Table 2-6 Waste Disposition 2-15 Table 2-7 Condensate Demineralizer/Radwaste Demineralizer - 2-16 Class A Steel Liner (Dewatered)
Table 2-8 Liquid Radwaste Filter Media - Class A HIC (Dewatered) 2-17 Table 2-9 Non-Processed DAW - Class A Steel Liner (Non-Processed) 2-18 Table 2-10 RWCU Filter Media - Class A HIC (Dewatered) 2-19 Table 2-11 Ash- Class A Strong Tight Container (Incineration) 2-20 Table 2-12 CFS Backwash Media - Class A HIC (Pyrolysis) 2-21 Table 2-13 Condensate Demineralizer/Radwaste Demineralizer - 2-22 Class A HIC (Pyrolysis)
Table 2-14 Contaminated Waste Oil - Class A (Fuel Blending for 2-23 Co-Generation)
Table 2-15 Liquid Radwaste Filter Media - Class A HIC (Pyrolysis) 2-24 Table 2-16 Processed DAW - Class A Strong Tight Container 2-25 (Compacted)
Table 2-17 Sump Sludge - Class A HIC (Pyrolysis) 2-26 Table 2-18 Irradiated Components - Class B Steel Liner 2-27
LIST OF TABLES (cont.) PAGE Table 2-19 CFS Backwash Media - Class B HIC (Pyrolysis) 2-28 Table 2-20 Condensate Demineralizer/Radwaste Demineralizer- 2-29 Class B HIC (Pyrolysis)
Table 2-21 Irradiated Components - Class C Steel Liner 2-30 Table 2-22 Condensate Demineralizer/Radwaste Demineralizer - 2-31 Class C HIC (Pyrolysis)
Table 3-1 Meteorological Data Recovery for 2006 3-3 Table 3-2 Joint Frequency Distribution of Wind Speed and 3-4 Direction 1Om versus Delta Temperature 60-1Om for the Period of January 1, 2006 through December 31, 2006 Table 3-3 Joint Frequency Distribution of Wind Speed and 3-12 Direction 60m versus Delta Temperature 60-1 Om for the Period of January 1, 2006 through December 31, 2006 Table 3-4 2006 Annual Relative Concentrations No Decay, 3-20 Undepleted X/Q (sec/m 3 )
Table 3-5 2006 Annual Relative Concentrations 2.26-Day 3-21 Decay, Undepleted X/Q (sec/mi3 )
Table 3-6 2006 Annual Relative Concentrations 8-Day 3-22 Decay, Depleted X/Q (sec/m 3 )
Table 3-7 2006 Annual Relative Deposition (D/Q meters-2 ) 3-23 Table 3-8 2006 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 2006 Table 4-2 Summary of Maximum Individual Doses to Members 4-4 of the Public Data Period: 1/1/06 to 12/31/06 Table 4-3 Calculated Collective Doses to Members of the 4-5 Public Within the Riverlands/Energy Information Center Complex Data Period: 1/1/06 to 12/31/06
LIST OF TABLES (cont.) PAGE 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 Airborne Effluent Release Points 1-6 Figure 1-2 Waterborne Effluent Pathway 1-7 Figure 2-1 Susquehanna River Monthly Average Flow Rates 2-9 Data Period: 2006 Figure 2-2 Monthly Liquid Radwaste Discharge Totals 2-10 Figure 3-1 2006 Annual Wind Rose 1OM Level - 3-26 Primary Tower Figure 3-2 2006 Annual Wind Rose 60M Level - 3-27 Primary Tower Pasquil Stability Class Prevalences Figure 3-3 3-28 Data Period: 2006 Figure 4-1 Airborne-Dose Calculation Locations 4-7
SECTION 1 INTRODUCTION,
SUMMARY
AND SUPPLEMENTAL INFORMATION 1-1
INTRODUCTION The submittal of the 2006 Radioactive Effluent Release Report is in accordance with PPL Susquehanna, LLC Tech Spec. 5.6.3. The enclosed information is consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP). The 2006 Radioactive Effluent Release Report is in conformance with 100FR50.36a and 10CFR50, Appendix I, Section IV.B.1.
PPL Susquehanna, LLC 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 Station via five rooftop vents on the reactor building (see Figure 1-1). Continuous sampling for particulates and iodines is performed at each vent as well as continuous monitoring for noble gases. A program of periodic sampling and analysis for tritium and noble gases along with periodic analysis of particulate and iodine samples 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 Station during the period from January 1, 2006 to December 31, 2006. In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to the ODCM, PCP and documentation of any exceptions to the effluent monitoring program which must be reported per Technical Requirements.
Airborne and waterborne radioactive effluent releases to the environment during the report period were sampled and analyzed in accordance with the Technical Requirements. All radioactive effluent releases were within the concentration and release limits specified in the Technical Requirements. Calculations and terms utilized in this report are those outlined in the ODCM.
1-2
Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant. Included are regulatory limits (Table 1-1), sampling and analysis methods, characterization of the number and duration of batch and abnormal releases and a brief summary of the applicable year's 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 2006 and the Monthly Liquid Radwaste Discharge Totals for 2006, 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 2-22 present a characterization of the solid radioactive waste shipped offsite during the report period. An estimate of major nuclide composition is presented for each waste type. Also included are the volumes and curie contents associated with each type of solid waste. The number of waste shipments from the site transported directly for burial or disposal are listed in Table 2-6.
Section 3 presents meteorological data for 2006, 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 to members of the public from airborne and waterborne effluents. Table 4-3 presents calculated collective doses to members of the public within the Riverlands/Energy Information Center Complex.
Table 4-4 summarizes the calculated doses for residences and other occupied areas within the site boundary and the nearest dairy.
1-3
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 2006 were similar to those of previous years.
During 2006 there were one hundred three (103) liquid batch releases resulting in a total release volume of one million five hundred thirty thousand (1,530,000) gallons.
The total number of liquid batch releases and total volume released in 2006 was higher than the corresponding values for 2005 (96 releases resulting in 1,470,000 gallons released in 2005). The predominant radionuclide released in liquid effluents during 2006 was tritium. Approximately eighty-nine (89) curies of tritium were released in liquid effluents in 2006, compared to seventy-four (74) curies released in 2005. When compared with all radionuclides released in liquid effluents in 2006, tritium was the main contributor to the resultant offsite dose. Consistent with previous years, the offsite dose from liquid releases in 2006 was less than one percent (1%) of the annual limits for both organ and whole body dose.
Gaseous effluents for 2006 were also comparable to those of previous years. Similar to liquid effluents in 2006, the predominant radionuclide released in gaseous effluents was tritium. When compared with all radionuclides released in gaseous effluents in 2006, tritium was the main contributor to the resultant offsite dose. Approximately fifty-nine (59) curies of tritium were released in gaseous effluents in 2006. The resultant maximum offsite organ dose due to gaseous effluents from Unit-1 for 2006 was 1.62E-01 mrem, which is 1.1 percent (1.1%) of the per unit annual limit of fifteen (15) mrem.
The resultant maximum offsite organ dose due to gaseous effluents from Unit-2 for 2006 was 3.31 E-01 mrem, which is 2.2 percent (2.2%) 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 AIRBORNE EFFLUENT RELEASE POINTS f
NIT 11 REACTOR BUILDING EXHAUST VENT 160,770 CFM 157.350 CFM 0
AT 600 F- 110°F AT 60OF-I10 F 302,959 CFM AT iOOOF-120°F UNIT TURAINE EXHAUST STACKS.
BUILDING DIESEL EXHAUST PLENUM-_ EXHAUST VENT 7-.6"----ý k3'o'4+ 3--6.--ý-5'-6 I
1-6
FIGURE 1-2 WATERBORNE EFFLUENT PATHWAY
[FROM EVAPORATOR HEATING STEAM CONDENSATE RETURN TANK i
REACTOR WELL SEAL LEAK DRAIN l
[
FROM PHASE SEPARATORS DEC ANT )
FROM RHR SYSTEM Of 4l REACTOR BUILDING DRAINS DRYWELL DRAINS 'I'll I LIQUID EFFLUENT RELEASE FLOWPATH I (M-181, M-162, M-163 AND M-164)
(SUPPRESSION POOL TRANSFERS) 44 TURBINE BUILDING DRAINS -J i
[ RADWASTE BUILDING DRAINS I* RADWASTE BUILDING DRAINS
__ I ILIUUIU RADWASTE RECYCLE LIQ UID RADWASTEI COLLECTION AND SURGE TANKS OT-302A THRUF II F1 t ,l tALIwUID OT-304A THRU D RADWASTE RADWASTE RADASE FILTERS DEMINERALIZER SAMPLE TANKS S
LIQUID RADWASTE i. OF-302A & B 0-301 0IT-303A THRU F TANKS SAPL TANK PUMPS T522A & B STATION CAPL N TANK PUMP S ST M C E I A DE O CLm H E M IC TA AK E - 02 , LIQ U ID2 A1STT-RESINS R TATO N SU A PL TANKN MAO RADWASTE~~TOAG OLCLAU BULINANK SA PESAINSSE CHEMICAL WAS E I r ~ ~~ ~ ~HEIA ~ E.NLB.DC.~ ~
CHMTANKDCN ~~CNEST RI STORAG
[- -- 7; .1E
.*E UTR EMALZNG TANK N -PUMPS-MOBILEWN L-S YS TE M IRREN REG U ATE SLOAD D A T TANVAPOILTE R S AMP LE TANKS CHEMIC LWAST TAN 0F-3 3A1 A3 B01)OT-3 212 (2) CONDENSATEDRAIN TANANK PUMPS NEUTRALIZING TANK PUMPSDICAG PUPO 32 (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 resulting dose 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 2006 resulted in an annual E-Bar Beta value of 3.62E-01 MeV and an E-Bar Gamma value of 1.86 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 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 grab 1-8
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 from alternate sampling ports available on the sample lines or directly from the affected rooftop vent(s).
- 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 from alternate sampling ports available on the sample lines or directly from the affected rooftop vent(s).
- 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 3.11.2.1.1)
- 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 .Il.A)
- 2. -<7.5 mrem - ORGAN
- quarterly dose limit per reactor unit at and beyond the site boundary (TRO 3.11.2.3.a)
- 3. *<15 mrem-ORGAN
- annual dose limit per reactor unit at and beyond the site boundary (TRO 3.11.2.3.b) 1-10
C. LIQUID EFFLUENTS:
- 1. *1.5 mrem - TOTAL BODY
- 5.0 mrem - ORGAN
- quarterly dose limits per unit (TRO 3.11.1.2.a)
- 2. *3.0 mrem - TOTAL BODY
- 10.0 mrem - ORGAN
- annual dose limits per 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 Derived release rate limits based on the Technical Requirement (TRO 3.11.2.1 .1.A and B) limits of 500 mrem/yr to the total body and 3000 mrem/yr to the skin were calculated from the expected mix of noble gas radionuclides presented in Attachment A of ODCM-QA-003, Effluent Monitor Setpoints. The lower limit of 1.OOE+06 pCi/min (1.67E+04 pCi/sec) based on total body dose rate is used.
Iodine-131 A derived release rate limit for 1-131 based on the Technical Requirement (TRO 3.11.2.1.II.A) limit of 1500 mrem/yr from 1-131, 1-133, tritium and particulates with half-lives greater than 8 days was calculated 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 .Il.A) limit of 1500 mrem/yr from I-131, 1-133, tritium and particulates with half-lives greater than 8 days was calculated (PPL calculation EC-ENVR-1041) 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 3.02E+03 pCi/min (5.03E+01 pCi/sec).
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Tritium A derived release rate was calculated based on the 10 CFR 20, Appendix B, Table 2, Column 1, Effluent Concentration Limit for tritium (1.0E-07 pCi/cc) to unrestricted areas. A relative concentration of 4.1 E-05 sec/m 3 was assumed (PPL calculation EC-ENVR-1 040). The limit is 1.46E+05 pCi/min (2.44E+03 pCi/sec).
Radionuclide Fractional Summation The sum of the percents of applicable limits for particulates, iodine and tritium must be less than 100%.
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 (TRO 3.11.1.1).
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.OE-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%.
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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 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. The following are typical measurement laboratory LLDs.
Typical LLDs Radionuclide LLD (pCi/cc)
Kr-87 4.3 E-08 Kr-88 4.6 E-08 Xe-1 33 3.0 E-08 Xe-1 33m 1.1 E-07 Xe-135 1.5 E-08 Xe-135m 8.0 E-08 Xe-138 1.5 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 1.0 E-13 Mo-99 1.0 E-12 Cs-134 2.4 E-13 Cs-137 1.1 E-13 Ce-141 1.0 E-13 Ce-144 5.0 E-13 1-131 4.4 E-14 Sr-89 1.1 E-13 Sr-90 1.3 E-14 H-3 1.5 E-08 Gross Alpha 2.3 E-14 Batch Releases
- 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 0
- 2. Total Activity Released NA 2-2
TABLE 2-1 AIRBORNE EFFLUENT - SUMMATION OF ALL RELEASES First Second Third Fourth A. Fission and Activation Gas Unit I Quarter I Quarter Quarter Quarter Total Release Ci 6.94E-01 0 4.13E-02 0 Average Release Rate for Period pCi/sec 8.93E-02 0 5.20E-03 0 Percent of Applicable Limit (1.67E+04 % 5.35E-04 0 3.11E-05 0 pCi/sec)
B. lodines Total 1-131 Ci 0 5.02E-06 3.99E-06 5.13E-06 Average Release Rate for Period pCi/sec 0 6.39E-07 5.02E-07 6.45E-07 Percent of Applicable Limit (1.73E+00 % 0 3.69E-05 2.90E-05 3.73E-05 pCi/sec)
Particulate Particulate with Half-Life >8 Days Ci 3.83E-04 9.46E-05 4.21 E-05 2.74E-04 Average Release Rate for Period pCi/sec 4.92E-05 1.20E-05 5.30E-06 3.44E-05 Percent of Applicable Limit (5.03E+01 % 9.85E-05 2.41 E-05 1.06E-05 6.89E-05 IJCi/sec)
Gross Alpha Radioactivity Ci 0 0 0 0 D. Tritium Total Release Ci 9.32E+00 2.06E+01 2.81 E+01 6.38E-01 Average Release Rate for Period pCi/sec 1.20E+00 2.61 E+00 3.54E+00 8.03E-02 Percent of Applicable Limit (2.44E+03 % 4.91 E-02 1.07E-01 1.45E-01 3.29E-03 pCi/sec)
I E. Radionuclide Fractional Summation Sum of Percent of Applicable Limit 0.05 0.11 0.15 0.003 During Period for B, C and D (Limit 100%)
2-3
TABLE 2-2 AIRBORNE EFFLUENT - RADIONUCLIDES RELEASED
_ _ _ __ IReleases in Continuous Mode First Second Third Fourth Nuclides Released Unit Quarter Quarter Quarter Quarter A. Fission and Activation Gases Ar-41 Ci 0 0 0 0 Kr-85 Ci 0 0 0 0 Kr-85m Ci 0 0 0 0 Kr-87 Ci 0 0 0 0 Kr-88 Ci 6.94E-01 0 0 0 Kr-89 Ci 0 0 0 0 Xe-133 Ci 0 0 0 0 Xe-133m Ci 0 0 0 0 Xe-135 Ci 0 0 4.13E-02 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 6.94E-01 0 4.13E-02 0 B. lodines 1-131 Ci 0 5.02E-06 3.99E-06 5.13E-06 1-133 Ci 0 0 0 0 1-135 Ci 0 0 0 0 Total for Period Ci 0 5.02E-06 3.99E-06 5.13E-06 C. Particulate Cr-51 Ci 1.39E-04 0 0 6.76E-05 Mn-54 Ci 1.08E-04 4.03E-05 8.16E-06 3.70E-05 Fe-59 Ci 0 0 0 0 Co-57 Ci 0 0 0 0 Co-58 Ci 6.79E-06 0 0 4.14E-06 Co-60 Ci 1.29E-04 5.43E-05 3.40E-05 1.65E-04 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 Nb-95 Ci 0 0 0 0 Ba-La-140 Ci 0 0 0 0 Total for Period Ci 3.83E-04 9.46E-05 4.21 E-05 2.74E-04 2-4
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 31 19 16 37 - 103
- 2. Total Time Period for a Batch Release 5.16E+03 3.58E+03 2.20E+03 7.83E+03 1.88E+04
- 3. Maximum Time Period for a Batch Release 3.04E+02 2.94E+02 3.OOE+02 3.1OE+02 3.1OE+02
- 4. Average Time Period for a Batch Release 1.66E+02 1.89E+02 1.38E+02 2.12E+02 1.82E+02
- 5. Minimum Time Period for a Batch Release 2.50E+01 3.1OE+01 3.OOE+01 2.50E+01 2.50E+01
- 6. Average Cooling Tower Blowdown 7.41E+03 7.71E+03 1.17E+04 8.95E+03 8.61 E+03 Flow Rate During Periods of Release
- 7. Susquehanna River Flow Rate 1.12E+07 8.23E+06 6.96E+06 9.96E+06 9.1OE+06
- Units of time and flow are expressed in minutes and gallons per minute (gpm),
respectively.
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 Technical Requirement 3.11.1.1 -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 (uCi/ml)
Mn-54 4.5 E-08 Fe-59 5.0 E-08 Co-58 4.0 E-08 Co-60 5.4 E-08 Zn-65 4.9 E-08 Mo-99 1.7 E-07 1-131 2.0 E-08 Cs-134 2.2 E-08 Cs-137 2.6 E-08 Ce-141 3.2 E-08 Ce-1 44 1.3 E-07 Sr-89 4.4 E-08 Sr-90 1.6 E-08 Fe-55 8.2 E-07 H-3 3.6 E-06 Gross Alpha 3.7 E-09 2-5
Abnormal Releases
- 1. Number of releases 0 0 0 0
- 2. Volume Released N/A N/A N/A N/A
- 3. Total Activity Released N/A N/A N/A N/A 2-6
TABLE 2-3 WATERBORNE EFFLUENT - SUMMATION OF ALL RELEASES First Second Third Fourth A. Fission and Activation Products Unit Quarter Quarter Quarter Quarter
- 1. Total Release (excluding: Tritium, Ent.
Gases, Alpha) Ci 5.26E-04 5.55E-05 7.20E-05 6.68E-04
- 2. Average Diluted Concentration During Period PCi/ml 3.64E-09 5.31E-10 7.38E-10 2.52E-09
- 3. Sum of Average Diluted CJLn Ratio During Period Unitless 5.10E-05 1.36E-05 2.80E-05 1.84E-05
- 4. Percent of Applicable Limit (Ratio < 1.0) % 0.005 0.001 0.003 0.002 B. Tritium
- 1. Total Release Ci 2.52E+01 1.56E+01 8.17E+00 4.02E+01
- 2. Average Diluted Concentration During Period PCi/ml 1.75E-04 1.49E-04 8.38E-05 1.52E-04
- 3. Percent of Applicable Limit (1.OE-2 pCi/ml) % 1.75 1.49 0.838 1.52 C. Dissolved and Entrained Gases
- 1. Total Release Ci 3.26E-05 9.88E-06 2.42E-05 6.31 E-05
- 2. Average Diluted Concentration pCi/ml 2.26E-10 9.44E-11 2.48E-10 2.38E-10 During Period
- 3. Percent of Applicable Limit (2.OE-4 pCi/ml) % 1.13E-04 4.72E-05 1.24E-04 1._1_9E-04 D. Radionuclide Fractional Summation
- 1. Sum of Percent of Applicable Limit During Period for A, B and C (Limit = 100%) % 1.76 1.49 0.84 1.52 E. Gross Alpha Radioactivity r 1. Total Release I Ci I 0 1 0 1 o0 F. Volume of Water Released IGallons 4.17E+05 I2.93E+05 1.74E+05 6.45E+05 (Prior to Dilution) Liters 1.58E+06 1.11E+06 6.59E+05 2.44E+06 G. Volume of Dilution Water i Gallons I 3.78E+07 I 2.72E+07 I 2.56E+07 6.95E+07 Used During Period of Release Liters 1.43E+08 1.03E+08 9.69E+07 2.63E+08 H. Volume of Dilution Water i Gallons I 8.12E+08 I 1. 3E+09 I 1.52E+09 1.13E+09 Used Over Entire Period Liters 3.07E+09 4.28E+09 5.75E+09 4.27E+09 2-7
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 0 0 0 Na-24 Ci 0 0 0 0 Cr-51 Ci 1.68E-04 2.81 E-06 0 5.37E-04 Mn-54 Ci 1.01 E-04 1.65E-05 1.41 E-05 8.26E-06 Fe-55 Ci 0 0 0 0 0o-58 Ci 2.47E-05 1.19E-06 0 6.62E-06 Fe-59 Ci 1.16E-05 7.74E-07 0 0 Co-60 Ci 1.73E-04 2.65E-05 3.1OE-05 3.68E-05 Zn-65 Ci 4.19E-05 1.88E-06 1.30E-05 4.09E-05 Sr-89 Ci 0 0 0 0 Sr-90 Ci 0 0 0 0 Tc-99m Ci 0 0 0 1.17E-06 Sb-124 Ci 0 0 0 1.22E-05 Cs-137 Ci 1.32E-06 4.23E-06 1.39E-05 2.50E-05 Ce-141 Ci 0 1.61 E-06 0 0 Ta-1 82 Ci 4.38E-06 0 0 0 Total for Period Ci 5.26E-04 5.55E-05 7.20E-05 6.68E-04 B. Tritium Total for Period Ci 2.52E+01 1.56E+01 8.17E+00 4.02E+01 C. Dissolved and Entrained Gases Ar-41 Ci 0 0 0 0 Kr-85 Ci 0 0 0 0 Kr-85m 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 8.11E-06 0 4.74E-06 1.74E-05 Xe-135m Ci 0 0 0 0 Xe-135 Ci 2.45E-05 9.88E-06 1.95E-05 4.57E-05 Total for Period Ci 3.26E-05 9.88E-06 2.42E-05 6.31 E-05 2-8
Figure 2-1 Susquehanna River Monthh VAverage Flow Rates Data Period : 2006 20.0 18.0 16.0 oL 14.0 cm 0
12.0 I 10.0 0
8.0 6.0 -
4.0 2.0 0.0 AN 2-9
Figure 2-2 Monthly Liquid Radwaste Discharge Totals 350 300 250 4) 200 0
0 E=*1o ZO 100 50 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
-.- 2006 2-10
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 (incl. 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/RadwasteDemineralizer- +/-25%
Class A Steel Liner HIC (Dewatered)
- b. Liquid Radwaste Filter Media- +/-25%
Class A HIC (Dewatered)
- c. Non-Processed DAW - Class A Steel Liner +/-25%
(Non-Processed)
- e. Ash - Class A Strong Tight Container (Incineration) +/-25%
- g. Condensate Demineralizer/Radwaste Demineralizer- +/-25%
Class A HIC (Pyrolysis)
- h. Contaminated Waste Oil - Class A (Fuel Blending for +/-25%
Co-Generation)
- i. Liquid Radwaste Filter Media - Class A HIC (Pyrolysis) +/-25%
2-11
ESTIMATED MAXIMUM MEASUREMENT ERROR
- 3. Solid Wastes (cont.)
- j. Processed DAW - Class A Strong Tight Container +/-25%
(Corn pacted)
I. Irradiated Components - Class B Steel Liner +/-25%
- n. Condensate Demineralizer/Radwaste Demineralizer - +/-25%
Class B HIC (Pyrolysis)
- o. Irradiated Components - Class C Steel Liner +/-25%
- p. Condensate Demineralizer/Radwaste Demineralizer - +/-25%
Class C HIC (Pyrolysis) 2-12
SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE DATA PERIOD: JANUARY 1. 2006 - DECEMBER 31, 2006 PREPARED BY:
MICHAEL C. MICCA HEALTH PHYSICIST APPROVED BY: ;I~
RADIOLOGICAL OEFOONS SUPERVISOR 2-13
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%.
2-14
TABLE 2-6 WASTE DISPOSITION Data Period: January 1, 2006 - December 31, 2006 A. SOLID WASTE SHIPPED OFF-SITE FOR BURIAL OR DISPOSAL Number of Shipments Mode of Transportation Destination 11 Truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS Number of Shipments Mode of Transportation Destination NONE NOTE: The number of shipments listed in A include only the shipments from PPL Susquehanna, LLC to a disposal site. It does not include shipments made to or from volume reduction vendors.
2-15
Table 2-7 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: No Source: Condensate Demineralizer / Radwaste Demineralizer Container: Steel Liner Process: Dewatered Nuclides Activity (mCi) % of Total C-14 1.510E+02 16.60 %
CO-58 5.780E+01 6.35 %
CO-60 1.750E+02 19.23 %
CR-51 1.570E+01 1.73 %
CS-137 1.860E-01 0.02 %
FE-55 2.010E+02 22.09 %
FE-59 8.750E+00 0.96 %
H-3 7. 840E+01 8.62 %
1-129 < 4.640E-06 0.00 %
MN-54 1. 770E+02 19.45 %
NB-95 1. 580E+00 0.17 %
TC-99 < 1.370E-04 0.00 %
ZN-65 4.310E+01 4.74 %
Total Activity (Ci) 0.910 100.00 %
Container Volume 199.400 ft3 5.646 m3 2-16
Table 2-8 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: No Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides Activity (mCi) % of Total 0.04 %
BA-131 4. 050E+01 0.00 %
C-14 2. 840E-01 CE-144 7. 160E+00 0.01 %
CO-58 8. 060E+02 0.75 %
CO-60 5 070E+03 4.73 %
CR-51 2. 990E+03 2.79 %
CS-137 2. 360E+00 0.00 %
FE-55 9. 240E+04 86.25 %
FE-59 4 .880E+02 0.46 %
H-3 4. 670E+01 0.04 %
1-129 < 2.080E-06 0.00 %
MN-54 4 .OOOE+03 3.73 %
NB-95 6. 390E+01 0.06 %
NI-63 2. 750E+02 0.26 %
PU-241 1 .1OE+01 0.01 %
SB-124 5. 050E+01 0.05 %
SB-125 8. 630E+00 0.01 %
SR-89 2. 020E+00 0.00 %
ZN-65 8. 540E+02 0.80 %
ZR-95 1 .040E+01 0.01 %
Total Activity (Ci) 107.127 100.00 %
Container Volume 132.400 ft3 3.749 m3 2-17
Table 2-9 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: No Source: Non-Processed DAW Container: Steel Liner Process: Non-Processed Nuclides Activity (mCi) % of Total C-14 2.730E+00 0.01 %
CE-144 3.420E+00 0.01 %
CO-58 4.600E+01 0.18 %
CO-60 1.050E+03 4.22 %
CR-51 1.190E+02 0.48 %
CS-137 9.880E-01 0.00 %
FE-55 2.270E+04 91.23 %
FE-59 2.910E+01 0.12 %
H-3 1.980E+00 0.01 %
1-129 < 4.900E-05 0.00 %
MN-54 7.770E+02 3.12 %
NB-95 8.140E+00 0.03 %
NI-63 7.050E+01 0.28 %
PU-241 3.230E+00 0.01 %
SB-124 1.870E+00 0.01 %
SB-125 6.260E+00 0.03 %
TC-99 < 1.030E-04 0.00 %
ZN-65 6.180E+01 0.25 %
Total Activity (Ci) 24.882 100.00 %
Container Volume 170.200 ft3 4.820 m3 2-18
Table 2-10 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: No Source: RWCU Filter Media Container: HIC (High Integrity Container)
Process: Dewatered Nuclides Activity (mCi) % of Total AM-241 3.610E-03 0.00 %
C-14 1.852E+03 0.20 %
CE-144 3.671E+02 0.04 %
CM-242 3.510E-03 0.00 %
CM-244 5.700E-03 0.00 %
CO-57 5.160E+01 0.01 %
CO-58 2.388E+04 2.64 %
CO-60 1.992E+05 22.01 %
CR-51 4.909E+04 5.42 %
CS-137 4. 626E+02 0.05 %
FE-55 4. 550E+05 50.28 %
FE-59 3 .910E+03 0.43 %
H-3 8. 494E+02 0.09 %
1-129 < 8.530E-06 0.00 %
MN-54 1. 020E+05 11.27 %
NB-95 6. 591E+03 0.73 %
NI-63 3. 500E+03 0.39 %
SB-124 2 .800E+02 0.03 %
SR-89 6. 233E+02 0.07 %
SR-90 5 .810E+00 0.00 %
TC-99 5. 860E+00 0.00 %
ZN-65 5. 430E+04 6.00 %
ZR-95 2. 978E+03 0.33 %
Total Activity (Ci) 904.946 100.00 %
Container Volume 264.800 ft3 7.498 m3 2-19
Table 2-11 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: Yes Source: Ash Container: Strong Tight Container Process: Incineration Nuclides Activity (mCi) % of Total 0.00 %
CE-141 4. 836E-01 0.01 %
CE-144 1. 125E+00 0.00 %
CO-58 9. 690E-01 CO-60 1. 229E+03 5.99 %
CS-137 2. 072E+00 0.01 %
FE-55 1 .862E+04 90.81 %
H-3 0. 000E+00 0.00 %
1-129 0. 000E+00 0.00 %
MN-54 5. 747E+02 2.80 %
NI-63 6 .811E+01 0.33 %
PU-241 1. 740E+00 0.01 %
SR-89 9. 350E-02 0.00 %
ZN-65 7. 082E+00 0.03 %
Total Activity (Ci) 20.505 100.00 %
Container Volume 21.630 ft3 0.613 m3 2-20
Table 2-12 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: Yes Source: CFS Backwash Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 5.990E-02 0.00 %
CE-144 5.530E-01 0.05 %
CM-244 7.780E-05 0.00 %
CO-58 1.170E+00 0.10 %
CO-60 2.050E+02 16.85 %
CR-51 1.140E-01 0.01 %
CS-137 5.670E-01 0.05 %
FE-55 8.860E+02 72.83 %
FE-59 4.490E-01 0.04 %
H-3 2. 470E+00 0.20 %
1-129 5. 570E-04 0.00 %
MN-54 1 .140E+02 9.37 %
NB-95 9. 630E-02 0.01 %
NI-59 9. 540E-03 0.00 %
NI-63 1. 420E+00 0.12 %
PU-241 4. 210E-03 0.00 %
SB-124 8. 790E-02 0.01 %
TC-99 6.590E-03 0.00 %
ZN-65 4. 280E+00 0.35 %
ZR-95 3. 140E-01 0.03 %
Total Activity (Ci) 1.217 100.00 %
Container Volume 1.450 ft3 0.041 m3 2-21
Table 2-13 Annual Waste Release Summary Report Year: 2006 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 4.621E+02 19.53 %
CO-58 5.614E+01 2.37 %
CO-60 5.039E+02 21.29 %
CR-51 2.847E+01 1.20 %
CS-137 5.495E-01 0.02 %
FE-55 5.792E+02 24.48 %
FE-59 9.140E+00 0.39 %
H-3 2.381E+02 10.06 %
1-129 1.133E-01 0.00 %
MN-54 3.270E+02 13.82 %
NB-95 2.180E+01 0.92 %
NI-63 6.530E-02 0.00 %
SR-90 1.134E+00 0.05 %
TC-99 3.071E+00 0.13 %
ZN-65 1.188E+02 5.02 %
ZR-95 1.682E+01 0.71 %
Total Activity (Ci) 2.366 100.00 %
Container Volume 90.280 ft3 2.556 m3 2-22
Table 2-14 Annual Waste Release Summary Report Year: 2006 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 7.480E-05 0.00 %
CE-144 9.330E-05 0.00 %
CO-58 1.240E-03 0.05 %
CR-51 3. 1OE-03 0.14 %
H-3 1. 600E+00 70.79 %
1-129 < 2.290E-09 0.00 %
NB-95 2. 150E-04 0.01 %
PU-241 8. 840E-05 0.00 %
SB-124 5. 000E-05 0.00 %
SB-125 1. 710E-04 0.01 %
TC-99 < 4.800E-09 0.00 %
ZN-65 1. 690E-03 0.07 %
Total Activity (Ci) 0.002 100.00 %
Container Volume 0.000 ft3 0.000 m3 2-23
Table 2-15 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: Yes Source: Liquid Radwaste Filter Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 8.390E-01 0.00 %-
CE-144 1.938E+01 0 .01 %-
CO-58 6.880E+02 0.23 CO-60 1.476E+04 5 .02 CR-51 9.650E+02 0.33 CS-137 6.960E+00 0.00 FE-55 2.660E+05 90.50 9-FE-59 4.490E+02 0.15 H-3 5.050E+01 0.02 1-129 1.356E-01 0.00 MN-54 7. 930E+03 2.70 NB-95 6.250E+01 0 .02 NI-63 8.120E+02 0.28 PU-241 3.260E+01 0 .01 SB-124 5.120E+01 0 .02 SR-90 1.375E-01 0.00 TC-99 8.850E-01 0.00 ZN-65 2.060E+03 0.70 ZR-95 4.970E+01 0 .02 Total Activity (Ci) 293.939 100.00 %
Container Volume 29.320 ft3 0.830 m3 2-24
Table 2-16 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: Yes Source: Processed DAW Container: Strong Tight Container Process: Compacted Nuclides Activity (mCi) % of Total AG-11OM 0 . OOOE+00 0.00 %
AM-241 7.150E-03 0.00 %
BA-133 1 .220E-01 0.00 %
CD-109 1.340E-02 0.00 %
CE-139 6.500E-06 0.00 %
CE-141 1. 775E+00 0.00 %
CE-144 4 .673E+00 0.01 %
CM-244 0 . OOOE+00 0.00 %
CO-58 2 . 042E+01 0.03 %
CO-60 4 552E+03 5.82 %
CR-51 1. 758E+01 0.02 %
CS-134 2. 930E-04 0.00 %
CS-137 7. 917E+00 0.01 %
FE-55 7 108E+04 90.85 %
FE-59 8. 330E+00 0.01 %
H-3 2. 465E+01 0.03 %
HG-203 4. 770E-10 0.00 %
1-129 2.241E-03 0.00 %
1-131 1.400E-10 0.00 %
MN-54 2. 175E+03 2.78 %
NB-95 2 . 049E+00 0.00 %
NI-59 0. 000E+00 0.00 %
NI-63 2. 546E+02 0.33 %
PU-238 4 610E-04 0.00 %
PU-241 6 . 919E+00 0.01 %
SB-124 8. 990E-01 0.00 %
SB-125 1 230E+00 0.00 %
SN-113 3. 780E-06 0.00 %
SR-89 3. 187E-01 0.00 %
Y-88 3. 960E-06 0.00 %
ZN-65 7 561E+01 0.10 %
ZR-95 7. 456E-01 0.00 %
Total Activity (Ci) 78.236 100.00 %
Container Volume 6827.700 f t3 193.343 m3 2-25
Table 2-17 Annual Waste Release Summary Report Year: 2006 Class: A Volume Reduction Vendor: Yes Source: Sump Sludge Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 5.780E+02 1.92 %
CO-60 1.720E+03 5.72 %
CS-137 1.200E+01 0.04 %
FE-55 2.750E+04 91.38 %
H-3 4.270E+00 0.01 %
1-129 6.610E-03 0.00 %
MN-54 2.050E+02 0.68 %
NI-63 7.590E+01 0.25 %
TC-99 4.860E-02 0.00 %
Total Activity (Ci) 30.095 100.00 %
Container Volume 12.160 ft3 0.344 m3 2-26
Table 2-18 Annual Waste Release Summary Report Year: 2006 Class: B Volume Reduction Vendor: No Source: Irradiated Components Container: Steel Liner Process: N/A Nuclides Activity (mCi) % of Total AM-241 1.070E-06 0.00 %
0.00 %
AM-243 7.640E-11 0.00 %
C-14 1.400E+01 0.00 %
CM-242 9.840E-08 0.00 %
CM-243 8.490E-12 0.00 %
CM-244 1. 710E-05 CO-60 1. 430E+05 47.03 %
FE-55 1. 460E+05 48.02 %
H-3 2. 020E+01 0.01 %
1-129 < 4.340E-06 0.00 %
MN-54 4. 880E+03 1.60 %
NB-94 2. 700E-01 0.00 %
NI-59 5. 280E+01 0.02 %
NI-63 1. 010E+04 3.32 %
NP-237 8. 810E-07 0.00 %
PU-238 1. 980E-04 0.00 %
PU-239 9. 790E-05 0.00 %
PU-240 1. 100E-05 0.00 %
PU-241 3. 980E-04 0.00 %
TC-99 6.210E-02 0.00 %
U-235 6.500E-05 0.00 %
Total Activity (Ci) 304.067 100.00 %
Container Volume 125.200 ft3 3.545 m3 2-27
Table 2-19 Annual Waste Release Summary Report Year: 2006 Class: B Volume Reduction Vendor: Yes Source: CFS Backwash Media Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 6.470E-01 0.00 %
CE-141 1.799E+01 0.02 %
CE-144 4 .850E+00 0.01 %
CO-58 1. 472E+02 0.16 %
CO-60 5. 300E+03 5.89 %
CR-51 2 .480E+02 0.28 %
CS-137 8. 970E+00 0.01 %
FE-55 8. 050E+04 89.48 %
FE-59 1. 324E+02 0.15 %
H-3 3. 860E+01 0.04 %
1-129 4. 500E-02 0.00 %
MN-54 2. 899E+03 3.22 %
NB-95 1 .880E+01 0.02 %
NI-63 2. 950E+02 0.33 %
PU-241 7. 510E+00 0.01 %
SB-124 9. 670E+00 0.01 %
TC-99 4 .280E-01 0.00 %
ZN-65 3 .401E+02 0.38 %
Total Activity (Ci) 89.969 100.00 %
Container Volume 43.830 ft3 1.241 m3 2-28
Table 2-20 Annual Waste Release Summary Report Year: 2006 Class: B Volume Reduction Vendor: Yes Source: Condensate Demineralizer / Radwaste Demineralizer Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 6. 495E+02 19.82 %
CO-58 9. 347E+01 2.85 %
CO-60 6. 726E+02 20.52 %
CR-51 2. 321E+01 0.71 %
FE-55 7. 723E+02 23.56 %
FE-59 1. 820E+01 0.56 %
H-3 2 .603E+02 7.94 %
1-129 1. 017E-01 0.00 %
LA-140 7. 514E-07 0.00 %
MN-54 5 .15E+02 15.61 %
NA-24 0. 000E+00 0.00 %
NB-95 8. 410E+00 0.26 %
SB-124 1. 049E+00 0.03 %
SB-125 4. 658E+00 0.14 %
SR-90 1. 502E+00 0.05 %
TC-99 2. 241E+00 0.07 %
ZN-65 2. 475E+02 7.55 %
ZR-95 9. 600E+00 0.29 %
Total Activity (Ci) 3.278 100.00 %
Container Volume 121.640 ft3 3.445 m3 2-29
Table 2-21 Annual Waste Release Summary Report Year: 2006 Class: C Volume Reduction Vendor: No Source: Irradiated Components Container: Steel Liner Process: N/A Nuclides Activity (mCi) % of Total AM-241 1.472E-02 0.00 AM-243 6. 860E-04 0.00 C-14 4. 502E+03 0 .01 CM-242 2.629E-01 0.00 CM-243 7.260E-04 0.00 CM-244 1.356E-01 0.00 CO-58 2 . 040E+05 0.23 CO-60 3.460E+07 39.02 CR-51 1. 237E+05 0.14 FE-55 3. 423E+07 38.60 FE-59 1. 986E+04 0. 02 H-3 5 . 097E+03 0.01 HF-181 7 . 800E+05 0.88 1-129 7.370E-06 0.00 MN-5 4 1.261E+06 1 .42 NB-94 1. 043E+02 0.00 NB-95 2 .239E+06 2 .52 NI-59 1.302E+04 0.01 NI-63 2.529E+06 2 .85 NP-237 1. 935E-03 0.00 PU-238 2. 428E+01 0.00 PU-239 1. 775E-02 0.00 PU-240 2. 413E-02 0.00 PU-241 3 .282E+00 0.00 SB-125 3. 033E+06 3 .42 SN-113 1. 841E+05 0.21 SN-119M 4 . 483E+06 5.06 SN-123 8. 761E+04 0.10 TA-182 2. 767E+06 3 .12 TC-99 1. 437E+01 0.00 U-235 8.710E-05 0.00 ZR-95 2. 118E+06 2.39 Total Activity (Ci) 88682.036 100.00 %
Container Volume 287.000 ft3 8.127 m3 2-30
Table 2-22 Annual Waste Release Summary Report Year: 2006 Class: C Volume Reduction Vendor: Yes Source: Condensate Demineralizer / Radwaste Demineralizer Container: HIC (High Integrity Container)
Process: Pyrolysis Nuclides Activity (mCi) % of Total C-14 1. 298E+02 16.57 %
CO-58 2. 291E+01 2.92 %
CO-60 1. 496E+02 19.10 %
CR-51 2. 380E+01 3.04 %
FE-55 1. 706E+02 21.78 %
FE-59 6 .040E+00 0.77 %
H-3 9. 220E+01 11.77 %
1-129 5 310E-02 0.01 %
MN-54 9. 621E+01 12.28 %
NB-95 1. 330E+00 0.17 %
TC-99 1. 566E+00 0.20 %
ZN-65 8. 866E+01 11.32 %
Total Activity (Ci) 0.783 100.00 %
Container Volume 54.470 ft3 1.542 m3 2-31
SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 3-1
METEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the PPL Susquehanna, LLC 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 1Om 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 10m 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.
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.
Regulatory Guide 1.23 (Safety Guide 23) requires at least 90% data recovery for meteorological instrumentation. During 2006, all meteorological instrumentation met the 90% data recovery requirement. Table 3-1 lists the percent valid data recovery values for the parameters monitored as part of the PPL Susquehanna Meteorological Monitoring Program.
Dispersion modeling for effluents from normal operation 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 terrain correction factors were taken from FSAR Table 2.3-128.
Tables 3-2 and 3-3 provide the joint frequency distribution of wind speed and direction (as a function of delta temperature) at the 10 and 60 meter elevations of the primary meteorological tower. Table 3-4 lists no decay, undepleted X/Q values at various distances from the site. Table 3-5 lists 2.26 day decay, undepleted X/Q values at various distances from the site. Table 3-6 lists 8-day decay, undepleted X/Q values at various distances from the site and Table 3-7 is a listing of D/Q (relative deposition) values at various distances from the site.
3-2
TABLE 3-1 METEOROLOGICAL DATA RECOVERY FOR 2006 PERCENT VALID PARAMETER DATA RECOVERY Wind Speed lOim - Primary < 99.6 Wind Speed 60m - Primary 99.5 Wind Speed IOm - Backup(2 ) 99.9 Wind Speed 1Om - Downriver(3) 99.8 Wind Direction lOim - Primary 99.6 Wind Direction 60m - Primary 99.6 Wind Direction lOim - Backup 99.9 Wind Direction 10m - Downriver 99.5 Temperature lOim - Primary 99.5 Dew Point lOim - Primary 98.6 Delta Temperature 60m - Primary 99.3 Sigma Theta lOim - Primary 99.6 Sigma Theta 60m - Primary 99.6 Sigma Theta 1Oin- Backup 99.9 Sigma Theta lOim - Downriver 99.5 Precipitation - Primary 100.0(4)
Composite Parameters Wind Speed and Direction lOin, 99.3 Delta Temperature 60-1 Om Wind Speed and Direction 60m, 99.3 Delta Temperature 60-1 Om (I""Primary" meteorological tower (2) "Backup" meteorological tower (3) "Downriver" meteorological tower (4) "Data supplemented with data from the National Weather Service for the period of September 5 through October 31, 2006 3-3
TABLE 3-2 Joint Frequency Distribution of Wind Speed and Direction 10m Versus Delta Temperature 60-10m for the Period of January 1, 2006 through December 31, 2006 Hours it Each Wind Speed and Direction Period of Record = )1/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD Direction: 1OMWD Lapse:DT60-10 Stability Class A Delta Tempera ture Extremely Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8 -13 13-19 1 9 - 25 > 25 Total N 1 17 11 0 0 0 29 NNE 4 31 7 0 0 0 42 NE II 17 0 0 0 0 28 ENE 15 3 0 0 0 0 18 E 11 8 0 0 0 0 19 ESE 12 3 1 0 0 0 16 SE 10 13 0 0 0 24 SSE 13 3 0 0 0 17 S 16 11 4 0 0 0 31 SSW 11 51 6 0 0 0 68 SW 10 106 85 2 0 0 203 WSW 4 22 33 0 0 0 59 W 1 4 5 0 0 0 10 WNW 0 2 1 0 0 0 3 NW 1 1 5 0 0 0 7 NNW 1 9 5 0 0 0 15 Total 121 301 165 2 0 0 589 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 589 Total Hours for the Period 8760 3-4
TABLE 3-2 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD Direction: 1OM WD 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 5 5 9 0 0 0 19 NNE 0 15 6 0 0 0 21 NE 1 6 2 0 0 0 9 ENE 6 4 1 0 0 0 11 E 5 1 3 0 0 0 9 ESE 2 0 1 0 0 0 3 SE 2 3 2 0 0 0 7 SSE 5 2 0 0 0 0 7 S 1 4 3 0 0 0 8 SSW 5 7 4 0 0 0 16 SW 4 29 31 3 0 0 67 WSW 0 4 8 1 0 0 13 W 0 3 5 0 0 0 8 WNW 1 2 8 0 0 0 11 NW 0 2 1 0 0 0 3 NNW 0 2 8 0 0 0 10 Total 37 89 92 4 0 0 222 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 222 Total Hours for the Period 8760 3-5
TABLE 3-2 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD Direc tion: 10M WD La pse: 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 2 20 20 2 0 0 44 NNE 3 20 6 0 0 0 29 NE 2 13 0 0 0 0 15 ENE 0 4 1 0 0 0 5 E 5 2 0 0 0 0 7 ESE 8 1 2 0 0 0 11 SE 4 4 2 0 0 0 10 SSE 2 5 0 0 0 0 7 S 4 7 7 0 0 0 18 SSW 5 10 7 0 0 0 22 SW 0 24 33 5 0 0 62 WSW 0 15 19 2 0 0 36 W 0 7 4 1 0 0 12 WNW 1 1 2 0 0 0 4 NW 0 1 9 0 0 0 10 NNW 0 2 12 3 0 0 17 Total 36 136 124 13 0 0 309 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 309 Total Hours for the Period 8760 3-6
TABLE 3-2 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD Direction: IOM WD 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 20 158 79 2 0 0 259 NNE 47 192 46 0 0 0 285 NE 71 116 2 0 0 0 189 ENE 59 33 8 0 0 0 100 E 56 34 10 2 0 0 102 ESE 68 59 21 4 0 0 152 SE 70 63 19 5 1 0 158 SSE 55 46 10 1 0 0 112 S 60 74 29 2 2 0 167 SSW 71 160 18 2 0 0 251 SW 35 188 157 50 1 0 431 WSW 14 70 112 50 13 0 259 W 8 74 88 30 1 0 201 WNW 8 86 135 34 0 0 263 NW 8 99 180 43 0 0 330 NNW 3 111 145 40 0 0 299 Total 653 1563 )59 265 18 0 3558 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 3558 Total Hours for the Period 8760 3-7
TABLE 3-2 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD Direction: IOM WD 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 53 60 2 0 0 0 115 NNE 136 96 10 0 0 0 242 NE 214 54 7 0 0 0 275 ENE 296 14 6 0 0 0 316 E 170 7 4 0 0 0 181 ESE 130 11 4 0 0 0 145 SE 119 17 3 2 0 0 141 SSE 132 21 7 1 0 0 161 S 164 68 17 2 0 0 251 SSW 105 139 10 0 0 255 SW 50 84 20 0 0 155 WSW 12 30 5 0 0 48 W 11 16 3 0 0 0 30 WNW 3 8 1 0 0 0 12 NW 9 12 4 0 0 0 25 NNW 8 20 7 0 0 0 35 Total 1612 657 110 8 0 0 2387 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 2387 Total Hours for the Period 8760 3-8
TABLE 3-2 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD Direction: IOM WD 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 8 1 0 0 0 0 9 NNE 46 8 0 0 0 0 55 NE 174 9 0 0 0 0 183 ENE 407 6 0 0 0 0 413 E 148 1 0 0 0 0 149 ESE 48 0 0 0 0 0 48 SE 42 0 0 0 0 0 42 SSE 44 0 0 0 0 0 44 S 37 3 0 0 0 0 40 SSW 17 5 0 0 0 0 22 SW 3 0 0 0 0 4 WSW 2 0 0 0 0 3 W 0 0 0 0 0 0 0 WNW 2 0 0 0 0 0 2 NW 3 0 0 0 0 0 3 NNW 1 0 0 0 0 0 1 Total 982 35 0 0 0 0 1018 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 1017 Total Hours for the Period 8760 3-9
TABLE 3-2 (continued)
Hours at Each Wind Speed and Direction Period of Record 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD irection: OM WD Lapse: DT60-10 Stability Class C Delta Temperature Extremely Stable Wind Speed (mph)
Wind Direction 1-4 4-8 8- 13 13 - 19 19 - 25 > 25 Total N 2 1 0 0 0 0 3 NNE 11 0 0 0 0 0 11 NE 137 7 0 0 0 0 144 ENE 345 6 0 0 0 0 351 E 61 0 0 0 0 0 61 ESE 25 0 0 0 0 0 25 SE 10 1 0 0 0 0 11 SSE 6 0 0 0 0 0 6 S 5 0 0 0 0 0 5 SSW 0 0 0 0 0 0 0 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 0 0 0 0 0 0 0 NNW 1 0 0 0 0 0 1 Total 604 15 0 0 0 0 619 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 619 Total Hours for the Period 8760 3-10
TABLE 3-2 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: IOM SPD Direction: 10M WD 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 91 262 121 4 0 0 478 NNE 247 .362 75 0 0 0 685 NE 610 222 11 0 0 0 843 ENE 1128 70 16 0 0 0 1214 E 456 53 17 2 0 0 528 ESE 293 74 29 4 0 0 400 SE 257 101 27 7 1 0 393 SSE 257 77 18 2 0 0 354 S 287 167 60 4 2 0 520 SSW 214 372 45 3 0 0 634 SW 103 432 326 61 1 0 923 WSW 32 142 177 54 13 0 418 W 20 104 105 31 1 0 261 WNW 15 99 147 34 0 0 295 NW 21 115 199 43 0 0 378 NNW 14 144 177 43 0 0 378 Total 4045 2796 1550 292 18 0 8702 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 58 Number of Valid Hours for this Table 8701 Total Hours for the Period 8760 3-1.1
TABLE 3-3 Joint Frequency Distribution of Wind Speed and Direction 60m Versus Delta Temperature 60-10m for the Period of January 1, 2006 through December 31, 2006 Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: 60M SPD Direction: 60M WD 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 14 24 0 0 0 38 NNE 3 16 15 5 0 0 39 NE 9 21 5 0 0 0 35 ENE 10 10 0 0 0 0 20 E 12 7 0 0 0 0 19 ESE 3 7 0 1 0 0 11 SE 3 5 0 1 0 0 9 SSE 1 10 2 1 0 0 14 S 11 9 4 3 0 0 27 SSW 16 21 14 3 0 0 54 SW 5 58 93 33 0 0 189 WSW 0 15 53 32 1 0 101 W 0 1 10 1 0 0 12 WNW 0 0 6 0 0 0 6 NW 1 2 3 1 0 0 7 NNW 0 1 6 1 0 0 8 Total 74 197 135 82 1 0 589 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 589 Total Hours for the Period 8760 3-12
TABLE 3-3 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: 60M SPD Direction: 60M WD Lapse: DT60-10 Stability Class B Delta Temperrature Moderately Unstable Wind Speed (mph)
Wind Direction 1-4 4-8 8 - 13 13 - 19 19 - 25 > 25 Total N 2 4 9 0 0 16 NNE 10 13 0 0 25 NE 4 7 01 0 0 12 ENE 2 3 1 0 0 0 6 E 2 1 1 2 0 0 6 ESE 3 1 0 0 0 5 SE 0 1 1 2 0 0 4 SSE 2 2 1 0 0 0 5 S 3 1 3 0 0 0 7 SSW 2 3 4 4 0 0 13 SW 2 9 22 13 0 0 46 WSW 2 3 15 22 2 0 44 W 0 1 9 0 13 0 0 10 WNW 0 1 9 0 0 0 10 NW 0 0 1 0 0 0 1 NNW 0 2 9 0 0 12 Total 22 46 105 47 2 0 222 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 222 Total Hours for the Period 8760 3-13
TABLE 3-3 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: 60M SPD Dire( tion: 60M WD La pse: 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 6 19 8 0 0 36 NNE 0 13 22 2 0 0 37 NE 1 8 6 0 0 0 15 ENE 3 3 0 1 0 0 7 E 5 1 1 0 0 0 7 ESE 4 0 2 1 0 0 7 SE 1 0 2 1 0 0 4 SSE 0 2 3 0 0 0 5 S 5 3 1 3 0 0 12 SSW 2 4 6 6 1 0 19 SW 2 8 26 13 0 0 49 WSW 0 9 27 21 3 2 62 W 0 1 12 2 0 0 15 WNW 0 2 3 1 0 0 6 NW 0 1 2 4 0 0 7 NNW 1 1 15 4 0 0 21 Total 27 62 147 67 4 2 309 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 309 Total Hours for the Period 8760 3-14
TABLE 3-3 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: 60M SPD Direction: 60M WD Lapse: DT60-10 Stability Class D Delta Temperature Neutral Wind Speed (mph)
Wind Direction 1-4 4-8 8. -13 13-19 1 9- 25 > 25 Total N 11 67 47 22 1 0 248 NNE 33 93 55 37 0 319 NE 41 63 69 9 0 0 182 ENE 32 31 21 4 1 0 89 E 16 21 26 5 0 69 ESE 17 26 41 25 2 116 SE 21 40 30 16 5 1 113 SSE 32 21 33 10 1 0 97 S 25 36 25 16 0 2 104 SSW 30 62 48 29 10 2 181 SW 33 162 38 65 4 2 404 WSW 10 79 38 170 75 19 491 W 2 39 23 87 25 9 285 WNW 1 39 25 100 11 0 276 NW 0 44 75 92 8 0 319 NNW 2 24 60 67 12 0 265 Total 306 847 14l354 754 160 37 3558 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 3558 Total Hours for the Period 8760 3-15
TABLE 3-3 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:()0 12/31/06 23:00 Total Period Elevation: S peed: 60M SPD Direction: 60M WD Lapse: DT60-10 Stability Class E Delta Tempe rature Slightly Stable Wind Speed (mph)
Wind Direction 1-4 4-8 8 - 13 13 - 19 19 - 25 > 25 Total N 37 86 21 0 0 0 144 NNE 104 212 68 3 0 0 387 NE 123 108 33 10 9 0 283 ENE 55 41 14 4 2 0 116 E 54 26 5 2 0 0 87 ESE 38 20 7 5 0 0 70 SE 47 27 22 2 1 1 100 SSE 62 33 14 7 2 1 119 S 50 46 33 11 3 0 143 SSW 49 90 100 28 7 2 276 SW 38 132 100 12 1 0 283 WSW 17 53 114 38 2 0 224 W 6 30 10 3 0 0 49 WNW 4 15 6 1 0 0 26 NW 2 11 19 5 0 0 37 NNW 15 14 11 3 0 0 43 Total 701 944 577 134 27 4 2387 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 2387 Total Hours for the Period 8760 3-16
TABLE 3-3 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: SI )eed: 60M SPD Direc:tion: 60M WD 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 26 78 6 0 0 0 110 NNE 77 199 13 0 0 0 289 NE 119 57 4 0 0 0 181 ENE 44 5 0 0 0 0 49 E 46 7 0 0 0 0 53 ESE 36 2 1 0 0 0 39 SE 34 7 1 0 0 0 42 SSE 19 3 0 0 0 0 22 S 17 17 4 0 0 0 38 SSW 11 38 9 0 0 0 58 SW 5 31 25 0 0 62 WSW 2 12 35 0 0 50 W 3 2 0 0 0 0 5 WNW 0 2 0 0 0 0 2 NW 2 7 1 0 0 0 10 NNW 4 2 1 0 0 0 7 Total 445 469 100 2 0 0 1017 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 1016 Total Hours for the Period 8760 3-17
TABLE 3-3 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: S peed: 60M SPD Direction: 60M WD Lapse: DT60-10 Stability Class G Delta Temperature Extremely Stable Wind Speed (mlph)
Wind Direction 1-4 4-8 8 -13 13-19 19 - 25 > 25 Total N 12 60 3 0 0 0 75 NNE 53 134 0 0 0 0 187 NE 65 54 0 0 0 0 119 ENE 39 7 0 0 0 0 46 E 29 5 0 0 0 0 34 ESE 13 4 0 0 0 0 17 SE 13 5 0 0 0 0 18 SSE 12 4 2 0 0 0 18 S 9 14 1 0 0 0 24 SSW 5 21 7 0 0 0 33 SW 1 21 4 0 0 0 26 WSW 1 6 5 0 0 0 12 W 0 2 0 0 0 0 2 WNW 2 1 0 0 0 0 3 NW 2 2 0 0 0 0 4 NNW 0 1 0 0 0 0 1 Total 256 341 22 0 0 0 619 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 619 Total Hours for the Period 8760 3-18
TABLE 3-3 (continued)
Hours at Each Wind Speed and Direction Period of Record = 01/01/06 0:00 12/31/06 23:00 Total Period Elevation: Speed: 60M SPD Direction: 60M WD 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 91 315 229 31 1 0 667 NNE 271 677 286 48 1 0 1283 NE 359 315 124 19 9 0 827 ENE 185 100 36 9 3 0 333 E 164 68 33 9 1 0 275 ESE 114 60 51 33 5 2 265 SE 119 85 56 22 6 2 290 SSE 128 75 55 18 3 1 280 S 120 126 71 33 3 2 355 SSW 115 239 188 70 18 4 634 SW 86 421 408 137 5 2 1059 WSW 32 177 387 284 83 21 984 W 11 76 164 93 25 9 378 WNW 7 60 149 102 11 0 329 NW 7 67 201 102 8 0 385 NNW 22 45 202 76 12 0 357 Total 1831 2906 2640 1086 194 43 8701 Number of Calm Hours for this Table I Number of Variable Direction Hours for this Table 0 Number of Invalid Hours 59 Number of Valid Hours for this Table 8700 Total Hours for the Period 8760 3-19
TABLE 3-4 2006 SSES ANNUAL RELATIVE CONCENTRATIONS 3
NO DECAY, UNDEPLETED X/Q (sec/m )
MILES DIRECTION FROM 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N 1.91 E-06 3.76E-07 1.73E-07 1.01 E-07 7.01 E-08 3.45E-08 1.29E-08 6.30E-09 3.98E-09 2.83E-09 NNE 3.86E-06 7.71E-07 3.64E-07 2.16E-07 1.52E-07 7.63E-08 2.96E-08 1.47E-08 9.36E-09 6.72E-09 NE 1.0OE-05 1.88E-06 9.20E-07 5.75E-07 4.13E-07 2.14E-07 8.76E-08 4.44E-08 2.87E-08 2.1OE-08 ENE 2.01 E-05 3.69E-06 1.84E-06 1.17E-06 8.42E-07 4.41 E-07 1.83E-07 9.36E-08 6.07E-08 4.46E-08 E 8.03E-06 1.55E-06 7.62E-07 4.73E-07 3.39E-07 1.75E-07 7.11E-08 3.61E-08 2.33E-08 1.70E-08 ESE 4.40E-06 8.65E-07 4.14E-07 2.50E-07 1.78E-07 9.02E-08 3.58E-08 1.79E-08 1.15E-08 8.30E-09 SE 3.55E-06 7.13E-07 3.39E-07 2.03E-07 1.43E-07 7.21E-08 2.82E-08 1.41 E-08 8.99E-09 6.48E-09 SSE 3.07E-06 6.23E-07 2.97E-07 1.78E-07 1.25E-07 6.32E-08 2.48E-08 1.23E-08 7.91E-09 5.69E-09 S 3.53E-06 7.25E-07 3.41E-07 2.02E-07 1.42E-07 7.15E-08 2.77E-08 1.37E-08 8.78E-09 6.31E-09 SSW 3.09E-06 6.30E-07 2.91 E-07 1.70E-07 1.18E-07 5.87E-08 2.23E-08 1.09E-08 6.91 E-09 4.92E-09 SW 2.34E-06 4.51 E-07 2.05E-07 1.1 9E-07 8.24E-08 4.02E-08 1.49E-08 7.27E-09 4.59E-09 3.25E-09 WSW 9.65E-07 1.85E-07 8.38E-08 4.83E-08 3.32E-08 1.59E-08 5.79E-09 2.78E-09 1.74E-09 1.22E-09 W 7.OOE-07 1.36E-07 6.09E-08 3.48E-08 2.39E-08 1.13E-08 4.05E-09 1.91 E-09 1.18E-09 8.21E-10 WNW 7.24E-07 1.37E-07 6.14E-08 3.52E-08 2.40E-08 1.12E-08 3.94E-09 1.84E-09 1.12E-09 7.71E-10 NW 9.65E-07 1.86E-07 8.37E-08 4.82E-08 3.29E-08 1.55E-08 5.50E-09 2.58E-09 1.59E-09 1.10E-09 NNW 9.48E-07 1.81 E-07 8.17E-08 4.71E-08 3.23E-08 1.53E-08 5.51E-09 2.61E-09 1.61 E-09 1.12E-09 3-20
0 TABLE 3-5 2006 SSES ANNUAL RELATIVE CONCENTRATIONS 3
2.26-DAY DECAY, UNDEPLETED X/Q (sec/m )
MILES DIRECTION FROM 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N 1.90E-06 3.74E-07 1.71E-07 9.93E-08 6.88E-08 3.34E-08 1.21E-08 5.66E-09 3.42E-09 2.33E-09 NNE 3.85E-06 7.66E-07 3.59E-07 2.13E-07 1.49E-07 7.36E-08 2.76E-08 1.30E-08 7.92E-09 5.43E-09 NE 1.OOE-05 1.86E-06 9.06E-07 5.63E-07 4.01 E-07 2.04E-07 8.OOE-08 3.81 E-08 2.32E-08 1.59E-08 ENE 2.OOE-05 3.65E-06 1.81 E-06 1.14E-06 8.17E-07 4.19E-07 1.66E-07 7.94E-08 4.82E-08 3.32E-08 E 8.OOE-06 1.53E-06 7.47E-07 4.60E-07 3.27E-07 1.64E-07 6.31 E-08 2.96E-08 1.77E-08 1.19E-08 ESE 4.38E-06 8.56E-07 4.06E-07 2.44E-07 1.72E-07 8.52E-08 3.19E-08 1.48E-08 8.80E-09 5.90E-09 SE 3.54E-06 7.05E-07 3.33E-07 1.98E-07 1.39E-07 6.84E-08 2.54E-08 1.18E-08 7.01E-09 4.70E-09 SSE 3.06E-06 6.17E-07 2.92E-07 1.74E-07 1.22E-07 6.02E-08 2.25E-08 1.05E-08 6.32E-09 4.28E-09 S 3.52E-06 7.19E-07 3.37E-07 1.98E-07 1.39E-07 6.86E-08 2.55E-08 1.20E-08 7.24E-09 4.92E-09 SSW 3.08E-06 6.26E-07 2.88E-07 1.67E-07 1.16E-07 5.69E-08 2.09E-08 9.79E-09 5.94E-09 4.06E-09 SW 2.33E-06 4.49E-07 2.04E-07 1.18E-07 8.12E-08 3.92E-08 1.42E-08 6.68E-09 4.08E-09 2.80E-09 WSW 9.63E-07 1.85E-07 8.32E-08 4.78E-08 3.28E-08 1.56E-08 5.55E-09 2.59E-09 1.57E-09 1.07E-09 W 6.99E-07 1.35E-07 6.04E-08 3.45E-08 2.36E-08 1.11E-08 3.88E-09 1.78E-09 1.07E-09 7.17E-10 WNW 7.23E-07 1.37E-07 6.11E-08 3.49E-08 2.37E-08 1.10E-08 3.80E-09 1.73E-09 1.03E-09 6.90E-10 NW 9.64E-07 1.85E-07 8.32E-08 4.77E-08 3.25E-08 1.52E-08 5.28E-09 2.41E-09 1.44E-09 9.65E-10 NNW 9.46E-07 1.80E-07 8.11E-08 4.67E-08 3.19E-08 1.50E-08 5.27E-09 2.42E-09 1.45E-09 9.79E-10 3-21
0 TABLE 3-6 2006 SSES ANNUAL RELATIVE CONCENTRATIONS 3
8-DAY DECAY, DEPLETED X/Q (secdm )
MILES DIRECTION FROM 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N 1.74E-06 3.19E-07 1.40E-07 7.80E-08 5.25E-08 2.39E-08 7.96E-09 3.38E-09 1.91 E-09 1.23E-09 NNE 3.52E-06 6.53E-07 2.94E-07 1.67E-07 1.14E-07 5.30E-08 1.82E-08 7.84E-09 4.47E-09 2.91E-09 NE 9.16E-06 1.59E-06 7.43E-07 4.44E-07 3.08E-07 1.48E-07 5.35E-08 2.35E-08 1.35E-08 8.92E-09 ENE 1.84E-05 3.12E-06 1.48E-06 9.01E-07 6.29E-07 3.05E-07 1.12E-07 4.94E-08 2.85E-08 1.88E-08 E 7.33E-06 1.31 E-06 6.14E-07 3.65E-07 2.52E-07 1.20E-07 4.31E-08 1.88E-08 1.08E-08 7.07E-09 ESE 4.02E-06 7.32E-07 3.34E-07 1.93E-07 1.32E-07 6.22E-08 2.17E-08 9.37E-09 5.33E-09 3.46E-09 SE 3.24E-06 6.03E-07 2.73E-07 1.57E-07 1.07E-07 4.98E-08 1.72E-08 7.38E-09 4.19E-09 2.72E-09 SSE 2.80E-06 5.27E-07 2.40E-07 1.37E-07 9.35E-08 4.37E-08 1.51 E-08 6.52E-09 3.72E-09 2.41 E-09 S 3.23E-06 6.13E-07 2.76E-07 1.56E-07 1.06E-07 4.95E-08 1.70E-08 7.30E-09 4.16E-09 2.70E-09 SSW 2.82E-06 5.34E-07 2.35E-07 1.31E-07 8.87E-08 4.08E-08 1.37E-08 5.84E-09 3.31E-09 2.14E-09 SW 2.14E-06 3.82E-07 1.66E-07 9.21 E-08 6.17E-08 2.80E-08 9.23E-09 3.92E-09 2.22E-09 1.43E-09 WSW 8.82E-07 1.57E-07 6.78E-08 3.74E-08 2.49E-08 1.11E-08 3.58E-09 1.50E-09 8.46E-10 5.41E-10 W 6.39E-07 1.15E-07 4.93E-08 2.70E-08 1.79E-08 7.91E-09 2.51E-09 1.04E-09 5.75E-10 3.63E-10 WNW 6.61E-07 1.16E-07 4.97E-08 2.73E-08 1.80E-08 7.83E-09 2.44E-09 9.98E-10 5.49E-10 3.43E-10 NW 8.82E-07 1.57E-07 6.78E-08 3.74E-08 2.47E-08 1.08E-08 3.40E-09 1.40E-09 7.74E-10 4.86E-10 NNW 8.66E-07 1.53E-07 6.61E-08 3.65E-08 2.42E-08 1.07E-08 3.41E-09 1.41E-09 7.83E-10 4.95E-10 3-22
TABLE 3-7 2006 SSES ANNUAL RELATIVE DEPOSITION D/Q (meters"2)
MILES DIRECTION FROM 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N 1.12E-08 1.71E-09 7.77E-10 4.07E-10 2.60E-10 1.09E-10 3.54E-11 1.30E-11 6.95E-12 4.37E-12 NNE 1.60E-08 2.45E-09 1.11E-09 5.82E-10 3.72E-10 1.55E-10 5.06E-11 1.86E-11 9.94E-12 6.24E-12 NE 1.97E-08 3.01E-09 1.37E-09 7.16E-10 4.57E-10 1.91E-10 6.22E-11 2.29E-11 1.22E-11 7.68E-12 ENE 2.83E-08 4.34E-09 1.96E-09 1.03E-09 6.58E-10 2.75E-10 8.95E-11 3.29E-11 1.76E-11 1.10E-11 E 1.23E-08 1.89E-09 8.54E-10 4.48E-10 2.86E-10 1.20E-10 3.89E-11 1.43E-11 7.65E-12 4.80E-12 ESE 9.34E-09 1.43E-09 6.47E-10 3.40E-10 2.17E-10 9.06E-11 2.95E-11 1.09E-11 5.79E-12 3.64E-12 SE 9.18E-09 1.40E-09 6.36E-10 3.34E-10 2.13E-10 8.90E-11 2.90E-11 1.07E-11 5.69E-12 3.58E-12 SSE 8.27E-09 1.26E-09 5.73E-10 3.01E-10 1.92E-10 8.01E-11 2.61E-11 9.61E-12 5.13E-12 3.22E-12 S 1.21E-08 1.86E-09 8.41E-10 4.41E-10 2.82E-10 1.18E-10 3.83E-11 1.41E-11 7.53E-12 4.73E-12 SSW 1.48E-08 2.26E-09 1.03E-09 5.38E-10 3.44E-10 1.44E-10 4.67E-11 1.72E-11 9.18E-12 5.77E-12 SW 2.16E-08 3.30E-09 1.49E-09 7.84E-10 5.OOE-10 2.09E-10 6.80E-11 2.50E-11 1.34E-11 8.40E-12 WSW 9.76E-09 1.49E-09 6.76E-10 3.55E-10 2.27E-10 9.46E-11 3.08E-11 1.13E-11 6.05E-12 3.80E-12 W 6.09E-09 9.32E-10 4.22E-10 2.22E-10 1.41E-10 5.91E-11 1.92E-11 7.08E-12 3.78E-12 2.38E-12 WNW 6.89E-09 1.05E-09 4.77E-10 2.50E-10 1.60E-10 6.68E-11 2.17E-11 8.01E-12 4.27E-12 2.68E-12 NW 8.85E-09 1.35E-09 6.13E-10 3.22E-10 2.05E-10 8.58E-11 2.79E-11 1.03E-11 5.49E-12 3.45E-12 NNW 8.85E-09 1.35E-09 6.13E-10 3.22E-10 2.05E-10 8.58E-11 2.79E-11 1.03E-11 5.49E-12 3.45E-12 3-23
TABLE 3-8 2006 ATMOSPHERIC DISPERSION ESTIMATES FOR RETDAS INPUT AT SELECTED LOCATIONS AFFECTED LOCATION MILES X/Q(1) X/Q DEC(2) X/Q DEC+DEP(3) DEPOSITION(4)
SECTOR I 1/SW Maximum (X/Q) Site Boundary 0.61 1.52E-05 1.5 1E-05 1.37E-05 2.88E-08 9/S Closest (X/Q) Site Boundary 0.38 6.67E-06 6.66E-06 6.2 1E-06 4.18E-08 12 / WSW Maximum (X/Q) Residence 1.3 1.07E-05 1.06E-05 9.12E-06 1.28E-08 7 / SE Maximum (D/Q) Residence 0.5 2.34E-06 2.34E-06 2.14E-06 2.15E-08 7/SE Maximum (D/Q) Garden 0.6 1.79E-06 1.79E-06 1.61E-06 1.58E-08 12 / WSW Maximum (D/Q) Dairy 1.7 7.30E-06 7.22E-06 6.11 E-06 8.38E-09 12/ WSW Maximum (D/Q) Meat Producer 1.7 7.30E-06 7.22E-06 6.11 E-06 8.38E-09 3/NE Riverlands / EIC 0.7 3.26E-06 3.25E-06 2.9 1E-06 2.80E-08 12/WSW Tower's Club 0.5 3.66E-05 3.64E-05 3.34E-05 5.15E-08 5/E East Gate 0.5 1.62E-06 1.62E-06 1.48E-06 1.41E-08 NEAREST RESIDENCE WITHIN A 5-MILE RADIUS BY SECTOR SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q NUMBER SECTOR NAMEMILESX/Q X/QDEC DEC+DEP DEPOSITION 1 N H.Burd 1.3 1.91E-06 1.90E-06 1.64E-06 5.09E-09 2 NNE E.Ashbridge III 1 2.83E-06 2.82E-06 2.47E-06 1.13E-08 3 NE W.Tuggle 0.9 2.26E-06 2.25E-06 1.98E-06 1.84E-08 4 ENE D.Barberi 2.1 2.89E-07 2.87E-07 2.38E-07 2.33E-09 5 E L.Kozlowski/W. Witts 1.4 3.15E-07 3.14E-07 2.68E-07 2.20E-09 6 ESE R.Panetta 0.5 1.86E-06 1.86E-06 1.70E-06 1.77E-08 7 SE J.Futoma 0.5 2.34E-06 2.34E-06 2.14E-06 2.15E-08 8 SSE J.Naunczek 0.6 1.95E-06 1.95E-06 1.76E-06 1.75E-08 9 S S.Slusser I 1.69E-06 1.68E-06 1.47E-06 8.43E-09 10 SSW S.Molnar 0.9 3.89E-06 3.88E-06 3.42E-06 1.40E-08 S1I SW F.Michael 1.5 4.02E-06 3.99E-06 3.40E-06 6.46E-09 12 WSW F.Michael 1.3 1.07E-05 1.06E-05 9.12E-06 1.28E-08 13 W F. Hummel 1.2 4.71E-06 4.66E-06 4.04E-06 6.02E-09 14 WNW R.Orlando 0.8 6.01E-06 5.97E-06 5.31E-06 1.15E-08 15 NW B. Kramer 0.8 5.89E-06 5.85E-06 5.21E-06 1.36E-08 16 NNW G. John 0.6 5.96E-06 5.93E-06 5.37E-06 1.53E-08 NEAREST GARDEN WITHIN A 5-MILE RADIUS BY SECTOR SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSITION NUMBER SECTOR DEC+DEP I N J.Wojcik 3.2 5.08E-07 4.99E-07 3.98E-07 I. 15E-09 2 NNE R.Chapin 2.3 8.41E-07 8.33E-07 6.85E-07 2.97E-09 3 NE F. Kremski 2.6 4.79E-07 4.74E-07 3.85E-07 3.44E-09 4 ENE G.Dennis 2.4 2.41E-07 2.39E-07 1.96E-07 1.95E-09 5 E W.Daily 1.8 2.IIE-07 2.10E-07 1.76E-07 1.46E-09 6 ESE L.Travelpiece 2.5 1.23E-07 1.22E-07 9.93E-08 9.53E-10 7 SE F.Scholl 0.6 1.79E-06 1.79E-06 1.61E-06 1.58E-08 8 SSE H.Roinick 2.9 1.47E-07 1.46E-07 1.17E-07 1.06E-09 9 S T. Stemrich 2.5 3.80E-07 3.76E-07 3.07E-07 1.71E-09 10 SSW S.Bodnar 1.2 2.5 1E-06 2.50E-06 2.16E-06 8.43E-09 11 SW R. Broody 1.9 2.85E-06 2.81E-06 2.36E-06 4.41E-09 12 WSW F.Michael 1.3 1.07E-05 1.06E-05 9.12E-06 1.28E-08 13 W F.Hummel 1.2 4.7 1E-06 4.66E-06 4.04E-06 6.02E-09 14 WNW P.Moskaluk 1.3 2.77E-06 2.74E-06 2.37E-06 4.72E-09 15 NW R.Reider 4.5 3.66E-07 3.55E-07 2.73E-07 5.45E-10 16 NNW P.Culver 4 3.53E-07 3.44E-07 2.68E-07 5.67E-10 3-24
TABLE 3-8 (continued)
NEAREST ANIMAL RAISED FOR MEAT CONSUMPTION WITHIN A 5-MILE RADIUS BY SECTOR SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSITION NUMBER SECTOR DEC+DEP 2 NNE R.Chapin 2.3 8.41E-07 8.33E-07 6.85E-07 2.97E-09 4 ENE G.Dennis 2.4 2.41E-07 2.39E-07 1.96E-07 1.95E-09 5 E W.Daily 1.8 2.I E-07 2.10E-07 1.76E-07 1.46E-09 10 SSW R. & C. Ryman 3 5.77E-07 5.69E-07 4.56E-07 1.65E-09 12 WSW T. & M Berger 1.7 7.30E-06 7.22E-06 6.1 IE-06 8.38E-09 ALL DAIRY LOCATIONS SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSITION NUMBER SECTOR DEC+DEP 5 E W.Bloss 4.5 4.29E-08 4.24E-08 3.22E-08 2.54E-10 6 ESE F.Rinehimer 4.2 4.22E-08 4.18E-08 3.19E-08 2.86E-10 10 SSW R. & C. Ryman 3 5.77E-07 5.69E-07 4.56E-07 1.65E-09 10 SSW R.Ryman 3.1 5.37E-07 5.29E-07 4.22E-07 1.5 1E-09 10 SSW K.Davis 14.0 3.36E-08 3.14E-08 2.09E-08 5.84E- 11 12 WSW T. & M. Berger 1.7 7.30E-06 7.22E-06 6.11E-06 8.38E-09 13 W J. Dent 5 4.29E-07 4.12E-07 3.15E-07 3.47E-10 16 NNW H.Shoemaker 4.2 3.31E-07 3.22E-07 2.49E-07 5.21E-10 3
1 X/Q RELATIVE CONCENTRATION (SEC/M )
2 T DECAYED AND UNDEPLETED, HALF-LIFE 2.26 DAYS 3
X/Q DEC (SEC/M )
3 3 X/Q DEC+DEP DECAYED AND DEPLETED, HALF-LIFE 8 DAYS (SEC/M )
4 DEPOSITION 2 RELATIVE DEPOSITION RATE (1/N )
3-25
FIGURE 3-1 2006 ANNUAL WIND ROSE 10M LEVEL - PRIMARY TOWER WIND ROSE
('WINDS FROM) 16% N 0.01% PERCENT CALMS (NOT INCLUDED IN PLOT, WIND SPEED LESS THAN 3.5 MPH
, WIND SPEED LESS THAN 7.5 MPH Eo WIND SPEED LESS THAN 12.5 MPH x WIND SPEED GREATER THAN 12.5 MPH This wind rose displays the frequency of hourly average wind direction from a given sector. In 2006, the predominant wind direction occurred 14 % of the time from the ENE sector. The average wind speed was 5.0 mph and the average wind speed for the predominant sector (ENE) was 2.4 mph. The sector with the highest average wind speed was WSW (8.8 mph).
3-26
FIGURE 3-2 2006 ANNUAL WIND ROSE 60M LEVEL - PRIMARY TOWER WIND ROSE (WINDS FROM)
N 0.01% PERCENT CALMS (NOT INCLUDED IN PLOT)
, 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 GREATER THAN 12.5 MPH This wind rose displays the frequency of hourly average wind direction from a given sector. In 2006, the predominant wind direction occurred 14.7% of the time from the NNE sector. The average wind speed was 7.8 mph and the average wind speed for the predominant sector (NNE) was 6.0 mph. The sector with the highest average wind speed was WSW (11.8 mph.).
3-27
FIGURE 3-3 PASQUIL STABILITY CLASS PREVALENCES DATA Period: 2006 Joint Frequency Distributions at 10 Meters Wind Speed and Direction IOM vs. Delta Temperature 60-10M (Based on 8,702 Valid Hours)
A G 6.8%
7.1%-
F C 11.7% 3.6%
E 27.4% D 40.8%
3-28
SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 4-1
Radioloqical 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 PPL Susquehanna, LLC Technical Requirements Manual.
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 2006 Annual Radiological Environmental Operating Report) contributed a maximum of 3.28E-2 mrem (measured at TLD Location 9S2) at the Protected Area Boundary south of the plant. The maximum organ (including thyroid)/total body dose from all airborne effluent is 4.92E-1 mrem (CHILD, THYROID Table 4-4). The maximum organ/total body dose from all liquid effluent is 2.14E-3 mrem (ADULT, Liver Table 4-2). Conservatively adding the maximum organ (including thyroid)/total body 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 station operations. The result (5.27E-1 mrem) is 2.1% of the 40CFR190 limit of 25 mrem to total body/organ (except thyroid) and 0.7% of the 40CFR190 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 2006 PARAMETER ENTIRE YEAR Cooling Tower Blowdown (CFS) 19.5 Average Net River Level (ft.) 7.9 Dilution Factor at Danville(1 ) 813.3 Transit time to Danville (hr.)(1 ) 17.2
(')From ODCM-QA-005, Att. E 4-2
Summaries of maximum individual doses resulting from airborne and waterborne radioactive effluent releases from each unit 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 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: Riverlands Energy Information Center, the Towers Club, and residence with the maximum X/Q value; the garden, 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 Table 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/Energy Information Center complex each year. For dose calculations, it is assumed the visitor stays in the area for one hour. The calculated dose rate and collective dose for visitors to the Riverlands/Energy Information Center during 2006 are shown on Table 4-3.
Use of the RETDAS code yields calculated doses for the Riverlands area for the report period. These doses assume an occupancy factor of 100% for a member of the public during 2006. These calculated dose values are shown on Table 4-4.
4-3
TABLE 4-2
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES TO MEMBERS OF THE PUBLIC DATA PERIOD: 1/1/06 TO 12/31/06 ESTIMATED MAXIMUM LIMIT AGE APPLICABLE DOSE PERCENT (MREM/
(MREM/MRAD) LOCATION OF LIMIT MRAD)(2)
UNIT EFFLUENT GROUP ORGANý DIST AFFECTED (MILES) SECTOR 1 Liquid"l) Adult Total Body 8.80E-04 (3) 0.03 3 1
1 Liquid( ) Adult Liver 1.07E-03 (3) 0.01 10 1 Noble Gas N/A Air Dose 1.22E-02 0.5 WSW 0.12 10 (Gamma-MRAD)
I Noble Gas N/A Air Dose 2.36E-03 0.5 WSW 0.01 20 (Beta-MRAD)
I Airborne Child Thyroid 1.62E-01 0.5 WSW 1.1 15 Iodine, Tritium and Particulates 2 Liquid") Adult Total Body 8.80E-04 (3) 0.03 3 2 Liquid(') Adult Liver 1.07E-03 (3) 0.01 10 2 Noble Gas N/A Air Dose 9.20E-05 0.5 WSW 0.001 10 (Gamma-MRAD) 2 Noble Gas N/A Air Dose 1.18E-04 0.5 WSW 0.001 20 (Beta-MRAD) 2 Airborne Child Thyroid 3.31E-01 0.5 WSW 2.2 15 Iodine, Tritium and Particulates (1 )Estimated dose is based on a site total activity release equally divided between Unit 1 and Unit 2.
(2)10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year for airborne and waterborne effluent from each unit.
(3)Doses from liquid effluent are estimated from fish ingestion and shoreline exposure at the site outfall and from the drinking water pathway at Danville, PA.
4-4
TABLE 4-3 CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/ENERGY INFORMATION CENTER COMPLEX DATA PERIOD: 1/1/06 TO 12/31/06 COLLECTIVE APPLICABLE DOSE RATE(1 ) DOSE(2 )
EFFLUENT AGE GROUP ORGAN (MREM/HR) (PERSON-REM)
Noble Gas N/A Total Body 1.26E-07 1.26E-05 Noble Gas N/A Skin 2.50E-08 2.50E-06 Iodine, Tritium and Child Thyroid 6.02E-06 6.02E-04 Particulates (1)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 X/Q Total (All) 2.04E-01 (CHILD) 2.07E-01 (CHILD, THYROID) 2.07E-01 (CHILD)
- 2. Maximum X/Q Residence Total (All) 1.42E-01 (CHILD) 1.43E-01 (CHILD, THYROID) 1.43E-01 (CHILD)
- 3. Maximum D/Q Dairy +
Maximum D/Q Meat Total (All) 9.66E-02 (CHILD) 9.74E-02 (CHILD, THYROID) 9.74E-02 (CHILD)
- 4. Maximum D/Q Garden Total (All) 2.76E-02 (CHILD) 2.91 E-02 (CHILD, THYROID) 2.91 E-02 (CHILD)
- 5. Tower's Club Total (All) 4.87E-01 (CHILD) 4.92E-01 (CHILD, THYROID) 4.92E-01 (CHILD)
- 6. Riverland/EIC 6._______________ Total (All) 5.01 E-02 (CHILD) 5.27E-02 (CHILD, THYROID) 5.27E-02 (CHILD)
Note: The doses shown above are based on 100% occupancy at the indicated locations. They 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 16-WNW 1E 1
- Indicates airborne-dose calculation location per Table 4-4 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 PPL Susquehanna, LLC ODCM consists of nine (9) individual procedures.
ODCM-QA-007, Radioactive Waste Treatment Systems, was revised on October 30, 2006. The revision deleted reference to performing vent evaluations in connection with inoperable ventilation exhaust treatment systems.
ODCM-QA-008, Radiological Environmental Monitoring Program, was revised on May 3 (revision 8) and July 12 (revision 9) 2006. The revisions: 1) added monitoring locations for surface water, groundwater and food product sampling; 2) clarified direct radiation monitoring location "Special Interest Areas"; 3) added guidance to clarify that some REMP monitoring locations may represent multiple exposure pathways; 4) updated milk sampling locations due to changes in dairy farm participation in the REMP and added guidance to clarify the requirements for milk sampling 5-2
CHANGES TO THE TECHNICAL REQUIREMENTS MANUAL Section 3.11 and 3.6.1 of the 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.
Unit-1 and Unit-2 TRM sections 3.11.1.1, 3.11.1.2, 3.11.1.3, 3.11.2.1, 3.11.2.2, 3.11.3, 3.11.4.1, 3.11.4.2 and 3.11.4.3 were revised March 31, 2006 to add a clarifying note to requirements which are applicable at all times.
Unit-1 and Unit-2 TRM section 3.11.2.5 Condition B was revised on November 14, 2006 to clarify the dose projection limit described by the referenced Condition.
There were no changes to the Unit-1 or Unit-2 TRM Section 3.6.1 during 2006.
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PROCESS CONTROL PROGRAM CHANGES The following changes were made to the Process Control Program and implementing procedures during 2006. 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
Sample Collection and Preparation
- 3. WM-PS-1 00, Shipment of Radioactive Waste
- 4. WM-PS-1 10, General Shipment of Radioactive Material
- 5. WM-PS-155, 10CFR61 Sample Shipping and Correlation Factor Determination
- 6. WM-PS-160, Radwaste Curie Calculations
- 7. WM-PS-180, Advanced Notification of Applicable States
- 8. WM-RP-012, Handling and use of Steel Liners and High Integrity Containers
- 9. WM-RP-1 05, Cartridge Filter Processing and Packaging
- 10. ME-EO-051, Fuel Pool Cleanout of Duratek Shielded Transfer Bell and Verification of NO FREE Standing Water IN FEXM High Integrity Container
- 11. ME-ORF-1 65, 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.
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PROCEDURE REVISION
SUMMARY
NDAP-OA-0646, Revision 11
- 1. Added CR 613944 to the reference section and added additional responsibilities to the Health Physicist - Radwaste and Solidification/Dewatering/Services Vendor in the Responsibilities Section.
- 2. Clarified Part 4, Step 6 of FORM NDAP-QA-0646-2.
- 3. Added procedure WM-RP-301 to Attachment C.
- 4. Various minor administrative changes.
PROCEDURE REVISION
SUMMARY
CH-TP-055, Revision 5
- 1. Correct typo error on page 4 of 10.
- 2. Deleted specific waste type information and reference NDAP-QA-0646 for information on page 5 of 10.
- 3. Deleted prerequisite and changed to None on page 5 of 10. Procedure adherence is now on Title page.
- 4. Added clarification about performing isotopic analyses based on deadtime criteria in section 7.1.
- 5. Updated sample frequency and quantity requirements in section 7.1.
- 6. Step 7.1.6 now requires saving remaining original composite until vendor results are evaluated.
- 7. Revised Attachment A to correct waste types and specify how dose rate is to be performed.
- 8. Added Form Number in step 7.1.11.
- 9. All these changes are administrative corrections.
PROCEDURE REVISION
SUMMARY
WM-PS-1100, Revision 10
- 1. Modified the procedure to require compliance with WM-PS-180 if transporting RAMQC in accordance with NRC Additional Security Measures for Transportation of Radioactive Material Quantities of Concern.
- 2. Updated Form WM-PS-100-1.
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PROCEDURE REVISION
SUMMARY
WM-PS-1 10, Revision 6
- 1. Added note to allow the Designated Radioactive Material Shipper to determine what procedure steps (Section 6) are required to transship a radioactive material package from Susquehanna. 49CFR171.2(b) allows transshippers use of information provided by another offeror.
- 2. Minor administrative enhancements.
- 3. Modified the procedure to require compliance with WM-PS-1 80 if transporting RAMQC in accordance with NRC Additional Security Measures for Transportation of Radioactive Material Quantities of Concern.
PROCEDURE REVISION
SUMMARY
WM-PS-1155, Revision 4
- 1. Added AR 733318733318to the Reference Section.
- 2. Added requirement to compare the reported minimum detectable activities of nuclides in 10CFR61 samples with the nuclide activities listed in 10CRF61.55 to ensure compliance.
- 3. Added Attachment G, Isotopic Data Screening, to provide guidance for screening the isotopic data.
- 4. Added Adherence Level to the Procedure Coversheet.
- 5. Made miscellaneous administrative changes.
PROCEDURE REVISION
SUMMARY
WM-PS-1160, Revision 4
- 1. Several minor administrative changes were made.
- 2. AR 713346713346was referenced.
- 3. Described the normal method (by utilizing the Radman computer program) for characterizing radioactive material for shipment.
- 4. Deleted Attachment B Current Correlation Factors since the factors are incorporated into the Radman computer program. Attachment B had a PCAF (2002-1093) which was not incorporated due to the factors being incorporated into the Radman Computer Program.
PROCEDURE REVISION
SUMMARY
WM-PS-1180, Revision 8
- 1. Modified the procedure to comply with EA-05-007, NRC Additional Security Measures for Transportation of Radioactive Material Quantities of Concern.
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PROCEDURE REVISION
SUMMARY
WM-RP-012, Revision 7
- 1. Incorporated PCAF 2006-1051 and made administrative changes. The PCAF changed the following.
- a. Added reference to CR 721330.
- b. Updated steel liner inspection to account for reusable containers.
- c. Added inspection for water in open top liners being returned from a waste processing vendor.
- d. Updated FORM WM-RP-012-1 and FORM WM-RP-012-2 and generated new FORM WM-RP-012-4.
PROCEDURE REVISION
SUMMARY
WM-RP-105, Revision 6
- 1. Clarified what information is needed on Form WM-RP-105-1.
- 2. Added requirement to weigh filters that are surveyed.
PROCEDURE REVISION
SUMMARY
MT-EO-051, Revision 2
- 2. Changed additional verification steps and QC sign off's to body of procedure.
- 3. Added additional verification steps and QC sign off's to body of procedure.
- 4. Performed required administrative changes.
PROCEDURE REVISION
SUMMARY
ME-ORF-165, Revision 2
- 1. Corrected ME-ORD number in step 8.21.4.
- 2. Incorporate 3-55 Cask Loading Verification Checklist per new Attachment G.
Attachment G also referenced in the body of the procedure.
- 3. Various administrative changes.
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SECTION 6 MISCELLANEOUS TECHNICAL REQUIREMENTS MANUAL (TRM),
FSAR, 40CFR190 AND NEI GROUNDWATER PROTECTION INITIATIVE 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 2006.
- 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 2006.
- 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 2006.
- 4. TRM Action 3.11.4.1 .F.2 requires reporting the cause of the unavailability of milk or fresh leafy vegetable samples and identify the new locations for obtaining replacements.
4/3/06 - Milk sample not available from Berger Farm (location 122B2, 1.7 miles WSW) due to owner no longer participating in Radiological Environmental Monitoring Program (REMP) milk sampling program. The Shoemaker Farm (location 16E1, 4.2 miles NNW) had the next highest relative deposition rate for the remaining dairy farms but they were not willing to participate in the REMP milk sampling program. The Berger Farm was replaced with the Moyer Farm (location 6C1, 2.7 miles ESE). The first milk sample was taken from the Moyer Farm on 4/17/06. The Berger Farm is an operating dairy farm (per 2006 Land Use Census) but not an active participant in the REMP milk sampling program.
6/12/06 - Milk sample not available from Moyer Farm (location 6C1, 2.7 miles ESE) due to owner no longer participating in milk sampling program. The Moyer Farm was replaced with the Dent Farm (location 13E3, 5.0 miles W).
The first milk sample was taken from the Dent Farm on 6/12/06. The Moyer Farm is no longer an operating dairy farm (all dairy cows sold by owner).
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- 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 2006.
- 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 2006.
- 7. The 40CFR190.10 standard for normal operation for the uranium fuel cycle including annual dose equivalent and total quantities of radioactive material limits was not exceeded by Station 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 2006.
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q9. The PPL Susquehanna station has implemented an Action Plan in response to the NEI Initiative on Groundwater Protection. Part of the Action Plan includes the assessment of the current groundwater monitoring program.
Groundwater is sampled and analyzed quarterly as part of the Radiological Environmental Monitoring Program (REMP). REMP groundwater sampling locations are defined in ODCM-QA-008 Attachment G. In August 2006, additional groundwater sampling was initiated at locations which are not listed in the ODCM. The additional locations are three manholes which collect water from a perimeter drain system. The perimeter drain system consists of perforated piping installed just above the footing along the exterior base of the vertical walls of the reactor, turbine and radwaste buildings. Outlined below are the tritium analysis results for the perimeter drain manhole sampling during 2006. No gamma emitting radionuclides were identified above analysis LLD's for the perimeter drain manhole samples. The tritium results reported below did not exceed any Reporting Level thresholds in the PPL Susquehanna Technical Requirements Manual or any reporting criteria established in response to the NEI Groundwater Protection Initiative.
PERIMETER DRAIN SAMPLING 2006 TRITIUM RESULTS I MPLE DATE MANHOLE LOCATION CODE (PCi/L) 8/23/2006 FD-1 7S9 (E of U2 CST) 424 8/23/2006 FD-2 16S3 (NW corner of RW Bldg.) 358 8/23/2006 FD-3 9S3 (inside U2 TB Bldg.) 328 11/13/2006 FD-1 7S9 (E of U2 CST) 179 11/13/2006 FD-2 16S3 (NW corner of RW Bldg.) 410 11/13/2006 FD-3 9S3 (inside U2 TB Bldg.) 344 6-4
SECTION 7 CORRECTIONS TO DOSES REPORTED IN PREVIOUS RADIOACTIVE EFFLUENTRELEASE REPORTS 7-1
CORRECTIONS TO DOSES REPORTED IN PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS No corrections to previous Radioactive Effluent Release Reports are submitted for this report period.
7-2
SECTION 8 EFFLUENTFROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENTPA THWA YS 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 moisture (condensate) concentration of the lubrication oil as measured via sampling during 2006. The calculation also assumes immediate removal of 100% of the water by the oil mist eliminators as it passes through the turbines. 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 2.81 Ci of tritium is calculated to be 2.26E-2 mrem (child). This is a small 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 U1-CST and U2-CST and Main Turbine/RFPT Main Turbine/RFPT Nuclide RWST Lube Oil Systems Lube Oil Systems Total (Ci) (Ci) (Ci) (Ci)
H-3 6.47E-02 1.35E+00 1.39E+00 2.8 1E+00 Mn-54 3.60E-08 6.42E-08 1.05E-07 2.05E-07 Co-60 1.2 1 E-07 1.50E-07 1.61E-07 4.30E-07 Cs- 137 0.OOE+00 1.38E-09 0.OOE+00 1.38E-09 Xe- 135 0.00E+00 6.29E-07 2.36E-06 3.16E-06 Co-58 4.80E-09 4.38E-08 5.17 E-08 1.00E-07 Zn-65 3.02E-09 1.84E-08 2.25E-08 4.39E-08 Xe- 135m 0.OOE+00 0.OOE+00 7.67E- 10 7.67E-10 Cr-51 1.3 IE-08 1.08E-08 0.OOE+00 2.38E-08 Fe-59 3.56E-09 0.OOE+00 0.OOE+00 3.56E-09 Sb- 124 9.39E-I I 0.OOE+00 0.OOE+00 9.39E- II Ba-131 1.12E-10 1.38E-09 6.13E-09 7.62E-09 Nb-95 4.90E- 10 0.OOE+00 0.00E+00 4.90E- 10 Zr-95 4.52E-10 0.OOE+00 0.OOE+00 4.52E-10 8-3