Susquehanna Station Units 1 and 2 - Annual Report 2011 … · 2012. 7. 20. · Period of January 1,...

Units

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2011Annual

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Attachment I to PLA-6833

Radioactive Effluent Release Reportfor SSES Units 1 and 2

RADIOACTIVE EFFLUENTRELEASE REPORT

REPORT PERIOD: 01/01111 - 12/31111

Prepared by:

0 Francis J. HickeyHealth Physicist

Reviewed by:

Daniel W. MillerChemistry Support Supervisor

Approved by:

€,

Bruce E. RhoadsManager - Plant Chemistry / Environmental

PPL Susquehanna, LLC769 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), 5-1Technical Requirements Manual (TRM)and the Solid Radioactive Waste Process Control Program

6. Miscellaneous Technical Requirements Manual (TRM), FSAR, 6-140CFR190 and NEI Groundwater Protection Initiative Reporting

7. Corrections to Previous Radioactive Effluent Release Reports 7-1

8. Effluent from Systems Classified as Insignificant Effluent Pathways 8-1

Appendix A ODCM/TRM

LIST OF TABLES

Table 1-1

Table 2-1

Table 2-2

Table 2-3

Table 2-4

Table 2-5

Table 2-6

Table 2-7

Table 2-8

Table 2-9

Table 2-10

Table 2-11

Table 2-12

Table 2-13

Table 2-14

Table 2-15

Technical Requirement Limits

Airborne Effluent - Summation of All Releases

Airborne Effluent - Radionuclides Released

Waterborne Effluent - Summation of All Releases

Waterborne Effluent - Radionuclides Released

Estimated Total Errors Associated withEffluents Measurements

Waste Disposition

Bead Resin / Charcoal - Class A HIC (Pyrolysis)

CFS Backwash Media - Class A HIC (Pyrolysis)

CFS Filters - Class A HIC (Pyrolysis)

Condensate DemineralizerlRadwaste Demineralizer -

Class A HIC (Pyrolysis)

Contaminated Waste Oil - Class A (Fuel Blending forCo-Generation)

Liquid Radwaste Filter Media - Class A HIC (Pyrolysis)

Processed DAW - Class A HIC (Compacted)

Processed DAW - Class A Strong Tight Container(Compacted)

Sump Sludge - Class A HIC (Pyrolysis)

PAGE

1-10

2-4

2-5

2-8

2-9

2-12

2-15

2-16

2-17

2-18

2-19

2-20

2-21

2-22

2-23

2-24

LIST OF TABLES (cont.)

Table 3-1 Meteorological Data Recovery for 2011

Table 3-2 Joint Frequency Distribution of Wind Speed and WindDirection 1 Om versus Delta Temperature 60-1 Om for thePeriod of January 1, 2011 through December 31, 2011

Table 3-3 Joint Frequency Distribution of Wind Speed and WindDirection 60m versus Delta Temperature 60-1 Om for thePeriod of January 1, 2011 through December 31, 2011

Table 3-4 2011 SSES Annual Relative Concentrations No Decay,Undepleted X/Q (sec/M3)

PAGE

3-3

3-4

Table 3-5 2011 SSES Annual Relative Concentrations 2.26-DayDecay, Undepleted X/Q (sec/m3)

Table 3-6 2011 SSES Annual Relative Concentrations 8-DayDecay, Depleted X/Q (sec/m3)

3-12

3-20

3-21

3-22

3-23

3-24

4-2

4-5

Table 3-7

Table 3-8

2011 SSES Annual Relative Deposition (D/Q meters2)

2011 Atmospheric Dispersion. Estimates for RETDASInput at Selected Locations

Table 4-1 Site-Specific Parameters Used for RETDAS Calculations(Danville Receiver) for 2011

Table 4-2 Summary of Maximum Individual Doses to Membersof the PublicData Period: 1/1/11 to 12/31/11

Table 4-3

Table 4-4

Calculated Collective Doses to Members of thePublic Within the Riverlands/Energy Information CenterComplex Data Period: 1/1/11 to 12/31/11

Summary of Maximum Individual Doses from Airborne Effluent

4-6

4-6

6-4

8-3

Table 6-1 NEI Ground Water Protection Initiative Reporting

Table 8-1 Annual Release from Systems Classified asInsignificant Effluent Pathways

LIST OF FIGURES

Figure 1-1

Figure 1-2

Figure 2-1

Figure 2-2

Figure 3-1

Figure 3-2

Figure 3-3

Figure 4-1

Figure 6-1

Airborne Effluent Release Points

Waterborne Effluent Pathway

Susquehanna River Monthly Average Flow RatesData Period: 2011

Monthly Liquid Radwaste Discharge Totals

2011 Annual Wind Rose 10M Level -

Primary Tower

2011 Annual Wind Rose 60M Level -Primary Tower

Pasquil Stability Class PrevalencesData Period: 2011

Airborne-Dose Calculation Locations

SSES Tritium Effluent Releases

PAGE

1-6

1-7

2-10

2-11

3-26

3-27

3-28

4-7

6-5

SECTION 1

INTRODUCTION, SUMMARY AND SUPPLEMENTAL INFORMATION

1-1

INTRODUCTION

The submittal of the 2011 Radioactive Effluent Release Report is in accordance withPPL Susquehanna, LLC Tech Spec. 5.6.3. The enclosed information is consistent withthe objectives outlined in the Offsite Dose Calculation Manual (ODCM) and ProcessControl Program (PCP). The 2011 Radioactive Effluent Release Report is inconformance with 10CFR50.36a 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. Thestation consists of two boiling water reactor generating units. Each unit has completedan Extended Power Uprate process which has increased licensed thermal power from3489 MWt (megawatt thermal) to 3952 MWt. Unit-1 completed the power uprate in2010 and Unit 2 completed the power uprate in 2011. The reactor and generating unitswere supplied by General Electric, while the Bechtel Corporation served asarchitect-engineer and constructor.

Construction of the Station began in the early 1970s. Fuel load began in Unit 1 in Julyof 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. Commercialoperation of Unit 1 was declared on June 8, 1983. Initial criticality of Unit 2 occurred onMay 8, 1984. Unit 2 was declared commercial on February 12, 1985.

Airborne effluents are released from the Station via five rooftop vents on the reactorbuilding (see Figure 1-1). Continuous sampling for particulates and iodines isperformed at each vent as well as continuous monitoring for noble gases. A program ofperiodic sampling and analysis for tritium and noble gases along with periodic analysisof particulate and iodine samples is conducted as specified in the plant TechnicalRequirements. All waterborne effluents are released in batch mode and are sampledand analyzed prior to release. Waterborne effluents from the site are released into thecooling tower blowdown line for dilution prior to release to the Susquehanna River (seeFigure 1-2). Blowdown line flow rates are at least 5,000 gpm during periods of liquidradwaste release. The diluted effluent is introduced to the river by way of a perforateddiffuser pipe placed on the river bed. The diffuser serves to mix the station dischargewith the main flow of the river.

This report presents a summary of the quantities of radioactive materials which werereleased from the Station during the period from January 1, 2011 toDecember 31, 2011. In addition, this report serves as a medium for notifying the USNuclear Regulatory Commission staff of changes to the ODCM, PCP anddocumentation of any exceptions to the effluent monitoring program which must bereported per Technical Requirements.

Airborne and waterborne radioactive effluent releases to the environment during thereport period were sampled and analyzed in accordance with the Technical

1-2

Requirements. All radioactive effluent releases were within the concentration andrelease limits specified in the Technical Requirements. Calculations and terms utilizedin this report are those outlined in the ODCM.

Section 1 contains supplemental information pertaining to effluents from theSusquehanna plant. Included are regulatory limits (Table 1-1), sampling and analysismethods, characterization of the number and duration of batch and abnormal releasesand a brief summary of the applicable year's effluents.

Section 2 contains effluent and waste disposal data for the report period. Table 2-1contains a summation of all airborne releases, grouped into the radionuclide categoriesof gases, particulates, iodines, and tritium. Average release rates are presented andcompared to the applicable limits. Table 2-2 presents the activity totals of specificradionuclides in airborne effluents.

Waterborne effluents are summarized in Table 2-3. Average diluted concentrations arepresented and compared to the applicable limits. Table 2-4 presents the releasequantities of specific radionuclides in waterborne effluents over the report period.Figures 2-1 and 2-2 present the Susquehanna River Monthly Average Flow Rates for2011 and the Monthly Liquid Radwaste Discharge Totals for 2011, respectively.

Table 2-5 contains estimates of the errors associated with the measurements involvedin quantifying effluents. Sampling errors, counting errors, and errors associated withdetermining effluent flow rates and volumes all contribute to the total error of effluentmeasurements. Error estimates are presented for each category of radionuclidedetected in airborne and waterborne effluents and solid wastes during the report period(Error Analysis of the Radioactive Effluent Sampling and Analysis Program at theSSES, Hydro Nuclear Services; 1985).

Tables 2-7 through 2-15 present a characterization of the solid radioactive wasteshipped offsite during the report period. An estimate of major nuclide composition ispresented for each waste type. Also included are the volumes and curie contentsassociated with each type of solid waste. The number of waste shipments from the sitetransported directly for burial or disposal are listed in Table 2-6.

Section 3 presents meteorological data for 2011, including data recovery, jointfrequency distribution of wind speed and direction, stability class distribution, andatmospheric dispersion estimates for selected locations.

Section 4 of this report contains an assessment of the calculated doses attributed to thereported radiological effluents for the calendar year. The Radioactive Effluent Trackingand Dose Assessment Software (RETDAS) computer code was used for calculation ofdoses from waterborne effluents. Site-specific parameters used in the calculations forthe Danville receiver are shown in Table 4-1. The RETDAS code was also used forcalculation of doses from airborne effluents. The calculated doses and direct radiationestimates can be used to estimate the doses to maximally exposed members of the

1-3

public. Table 4-2 summarizes maximum calculated doses to members of the publicfrom airborne and waterborne effluents. Table 4-3 presents calculated collective dosesto members of the public within the Riverlands/Energy Information Center Complex.Table 4-4 summarizes the calculated doses for residences and other occupied areaswithin the site boundary and the nearest dairy. Additionally, Section 4 includes adescription of the methodology used in the calculation and resultant dose impact ofcarbon-14 released from the station.

Section 5 of this report documents changes to the Offsite Dose Calculation Manual,Technical Requirements Manual and the Solid Radioactive Waste Process ControlProgram.

Section 6 presents a listing of cases (if any) in which airborne or waterborne effluentmonitoring instrumentation was declared inoperable and was not restored to operabilitywithin the time period specified in Technical Requirements 3.11.1.4, 3.11.1.5 and3.11.2.6 Action Statements. In addition, this section presents issues (if any) with thecollection of milk or fresh leafy vegetables per Technical Requirement 3.11.4.1 andchanges due to the land use census per Technical Requirement 3.11.4.2. Section 6also includes reporting associated with the Nuclear Energy Institute (NEI) GroundwaterProtection Initiative.

Section 7 contains corrections (if any) to previous Radioactive Effluent ReleaseReports.

Section 8 contains information on effluent and offsite dose from the systems classifiedas insignificant effluent pathways.

1-4

SUMMARY

During 2011 there were one hundred forty eight (148) liquid batch releases resulting ina total release volume of one million four hundred eighty eight thousand (1,488,000)gallons. The total number of liquid batch releases and total volume released in 2011was lower than the corresponding values for 2010 (206 releases resulting in 2,702,000gallons released in 2010) due to the Unit-1 condenser area flood event (900,000gallons of water discharged in addition to water released through liquid radwastetreatment system) which occurred in 2010. The predominant radionuclide released inliquid effluents during 2011 was tritium. Approximately fifty-two (52) curies of tritiumwere released in liquid effluents in 2011, compared to fifty seven (57) curies released in2010. When compared with all radionuclides released in liquid effluents in 2011, Co-60and Zn-65 were the main contributors to the resultant offsite dose. Consistent withprevious years, the offsite dose from liquid releases in 2011 was less than one percent(1%) of the annual limits for both organ and whole body dose.

In 2010, an industry initiative (supported by EPRI and NEI) was established to evaluateand report Carbon-14 (0-14) in the Annual Radioactive Effluent Release Report. Theinitiative is rooted in Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, andReporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", inthat the NRC has recommended that U.S. nuclear power plants evaluate whether C-14is a "principal radionuclide", and if so, report the amount of C-14 released. The C-14released from the Susquehanna station in 2011 was calculated using conservativeguidance provided by the Electric Power Research Institute (EPRI Report No.1021106). Based on the EPRI methodology, approximately 23 Curies of C-14 werereleased in gaseous effluents in 2011. See section 4 for additional details on thecalculation of C-14 released in airborne effluents. Historically, tritium has been thepredominant radionuclide (both in Curies and resultant offsite dose) released ingaseous effluents from the Susquehanna station. Approximately forty-seven (47)curies of tritium were released in gaseous effluents in 2011 compared to thirty-one (31)curies in 2010. The resultant maximum offsite organ dose due to gaseous effluentsfrom Unit-1 for 2011 was 4.56E-1 mrem, which is three (3%) of the per unit annual limitof fifteen (15) mrem. The resultant maximum offsite organ dose due to gaseouseffluents from Unit-2 for 2011 was 3.34E-1 mrem, which is two percent (2%) of the perunit annual limit of fifteen (15) mrem. The maximum offsite dose from gaseouseffluents was lower in 2011 when compared with 2010 due to the dose from C-14releases being lower.

1-5

FIGURE 1-1

AIRBORNE EFFLUENT RELEASE POINTS

B

JtNJ iEATORUILDING

MHUSTVENT

UNIT 2REACTOROLqLDDINGEXHAUST

VENT

Iih

1-6

FIGURE 1-2

WATERBORNE EFFLUENT PATHWAY

FROM EVAPORATOR HEATINGSTEAM CONDENSATE RETURN TANK

FROM PHASE SEPARATORS(DECANT)

FROM RHR SYSTEM(SUPPRESSION POOL TRANSFERS)

[ RADWASTE BUILDING DRAINS

REACTOR WELL SEAL LEAK DRAIN

44! REACTOR BUILDING DRAINS I

I DRYWELL DRAINS I1 LIQUID EFFLUENT RELEASE FLOWPATH II

(M-161, M-162, M-163 AND M-164]

4-I TURBINE BUILDING DRAINS

L IO I

I RAD WASTE BUILDING DRAINS

p. LIQUID RADWASTE RECYCLE

LIQUID RADWASTECOLLECTION AND

SURGE TANKSOT-302A THRU FOT-304A THRU D LQI

RAD EARADWASTE DWASTEFILTRS EMINRALZERSAMPLE TANKS

LIQUID RADWASTE OAT-303A THRU

COLLECTION TANK PUMPS CCO0P-301A, B & C S

SOToRGTAKDSILE

LAUNDR DRAING LAUSSPNDR DRASIN LAUNDR DRAI

SLIQUID RADWASTESAMPLE TANK PUMPS

SAMPLE STATION SYSTEM CHEMICAL DECON

S RWCU CHEMICAL DECON.O CHEMICAL DECON LAB & DECON DRAB

CHMIA HWSEMALWTETN0E02,B1 0-1

I(2) CONDENSATE DEMIN vl

RESIN REGEN. TANKS I ' EVAPORATORCONCENTRATE

ISTORAGE TANK I

CHMIA WAT0T-322 DIISTILLATENNEUTRALIZING SA PMPLETN

TANKS 0PUMPSA

2T- 1 30A:2-3A B

S CHEMICAL WASTE CONDENSATE STORAGE TANKI

NEUTRALIZING TANK PUMPS DISCHARGE PUMP OP-3281P-130A, B AND 2P-130A, B

• "NI PROCESSING '

IPERSONNEL D ECONTAM INATION(ERGNS "1 YTM I

FLO DEO (SOLUTIONS) C ASK CLEANING DRAINS iREUAE SHOP -DRIN LAUNDRY DRAINS (3)

LUDYDANLAUNDRY DRAIN LAUNDRY DRAINTANKS FILTERS SMLTANKS

0T-3111A, B 0F-S13A1-A3 OT-312L ANR RITANK PUMPS 0F1B-3LAUNDRY DRAIN

0 -318, B -•SAMPLE TANK PUMPS

NDENSATESTORAG]ETANKS-522A & B

(1) RADWASTE EVAPORATORSARE NOT USED

(2) COND DEMIN RESINS CURRENTLYNOT REGENERATED

(3) CONTAMINATED CLOTHING CURRENTLYNOT LAUNDERED ONSITE

~FZ]I~I

I~I

0

SUSQUEHANNA RIVER

1-7

SUPPLEMENTAL INFORMATION

1. Regulatory Limits

Technical Requirements 3.11.1 and 3.11.2 outline requirements for release ofradioactive liquid and gaseous effluents, respectively. Concentration of radioactivematerials released in liquid effluents and resulting dose are limited in unrestrictedareas. Dose and dose rate due to radioactive materials released in gaseouseffluents are limited in areas at or beyond the site boundary. TechnicalRequirement limits are listed in Table 1-1.

2. Maximum Permissible Concentrations in Waterborne Effluents

The concentration of radioactive material released in liquid effluents to unrestrictedareas is limited to 10 times the concentrations specified in 10 CFR Part 20Appendix B Table 2, Column 2, for radionuclides other than dissolved or entrainednoble 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 Energv of Fission and Activation Gas

The Calculation of Noble Gas Effluent Average Energies E-Bar Beta and Gammawas not performed due to the fact that no noble gases were measured in StationVent Air Samples above detection limits during 2011.

4. Measurements and Approximations of Total Radioactivity

Analyses of specific radionuclides in effluent samples are used to evaluate theradioactive composition and concentration of effluents.

5. Methods of Quantifying Effluents

a. Fission and Activation Gases: Gas samples are routinely collected monthlyand analyzed with a high resolution (HPGE) detector system whichincorporates a data reduction program to determine radionuclide compositionin terms of specific activity. Data from the continuous vent monitors are usedto determine the average concentration of noble gases. The high resolution(HPGE) isotopic scan is used to convert the continuous vent monitor activityto actual activity based on the determined nuclide mixture. The vent andsample flow rates are continuously monitored and the average flow rates foreach vent are used to calculate the total activity released in a given timeperiod. When the continuous monitors are out of service, manual grabsamples are taken from each vent once every eight hours (once every four

1-8

hours for the standby gas treatment vent when standby gas treatment systemis in service).

b. lodines: Iodine is continuously collected on charcoal or silver zeolitecartridges via an isokinetic sampling assembly in each vent. Filters arenormally exchanged once per week and analyzed on a high resolution(HPGE) system. The daily average flow rates for the vents and samplepumps are averaged for the duration of the sampling period and a ratio ofvent flow rate to sample flow rate is determined. The ratio is used todetermine the total activity of each isotope released during the time period inquestion. When the continuous samplers are out of service, iodine iscontinuously collected from alternate sampling ports available on the samplelines or directly from the affected rooftop vent(s).

c. Particulates: Particulates are continuously collected via an isokineticsampling assembly in each vent. Filters are normally exchanged once perweek and analyzed on a high resolution (HPGE) system. Flow ratecorrections are performed as for iodines. When the continuous samplers areout of service, particulates are continuously collected from alternate samplingports available on the sample lines or directly from the affected rooftopvent(s).

d. Tritium: Airborne tritium is collected monthly via bubbler sampler. Thesample is collected for one hour at a flow rate of approximately 1000 cc/min.Tritium activity in the bubbler sample is determined by liquid scintillationcounting. The liquid sample tritium concentration is then converted to airconcentration by volume proportion.

e. Waterborne Effluents: Each tank of liquid radwaste is sampled andanalyzed for principal gamma emitters prior to release. Each sample tank isrecirculated for a sufficient amount of time prior to sampling to ensure that arepresentative sample is obtained. Samples are analyzed on a highresolution (HPGE) system and release permits are generated based on thevalues obtained from the isotopic analysis and the most recent values fortritium, gross alpha, iron-55, and strontium-89 and -90. An aliquot based onrelease volume is saved and added to monthly and quarterly compositecontainers. The monthly tritium analysis is done in-house. A monthlycomposite is sent to a vendor laboratory for gross alpha analysis. A quarterlycomposite is sent to a vendor laboratory for iron-55, strontium-89 and-90analyses.

The concentration of each radionuclide in each batch is multiplied by thevolume of the batch to determine the total quantity of each nuclide releasedin each batch. The isotopic totals for each batch are summed to determinethe 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 siteboundary(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 siteboundary(TRO 3.11.2.2.b)

B. AIRBORNE 1-131,1-133, TRITIUM, PARTICULATES WITHHALF-LIVES > 8 DAYS:

1. •1500 mrem/year- ORGAN(inhalation pathways only)

- dose rate limit at and beyond the site boundary

(TRO 3.11.2.1.1l.A)

2. •7.5 mrem - ORGAN

- quarterly dose limit per reactor unit at and beyond the siteboundary(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 LIMITVALUES IN TABLE 2-1

Fission and Activation Gases

Derived release rate limits based on the Technical Requirement(TRO 3.11.2.1 .I.A and B) limits of 500 mrem/yr to the total body and 3000mrem/yr to the skin were calculated (PPL calculation EC-ENVR-1 041 Rev. 2)from the expected mix of noble gas radionuclides presented in Attachment Aof ODCM-QA-003, Effluent Monitor Setpoints. The lower limit of 1.OOE+06pCi/min (1.67E+04 pCi/sec) based on total body dose rate is used.

Iodine-1 31

A derived release rate limit for 1-131 based on the Technical Requirement(TRO 3.11.2.1.11.A) limit of 1500 mrem/yr from 1-131, 1-133, tritium andparticulates with half-lives greater than 8 days was calculated (PPLcalculation EC-ENVR-1041 Rev. 2) based on the ratio of the expected annualrelease 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 i.Ci/min I-131 (1.73E+00 pCi/sec).

Particulates

A derived release rate limit for particulate activity other than iodines based onthe Technical Requirement (TRO 3.11.2.1.11.A) limit of 1500 mrem/yr from I-131, 1-133, tritium and particulates with half-lives greater than 8 days wascalculated (PPL calculation EC-ENVR-1 041 Rev. 2) based on the expectedannual release quanities of particulate radionuclides provided in AttachmentE of ODCM-QA-004, Airborne Effluent Dose Calculations. The limit is3.02E+03 pCi/min (5.03E+01 VCi/sec).

1-11

Tritium

A derived release rate was calculated based on the 10 CFR 20, Appendix B,Table 2, Column 1, Effluent Concentration Limit for tritium (1.OE-07 pCi/cc) tounrestricted areas. A relative concentration of 4.1 E-05 sec/mi3 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 tritiummust be less than 100%.

E. WATERBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLELIMIT VALUES IN TABLE 2-3

Fission and Activation Products

Concentrations of fission and activation products in liquid effluent fromradwaste effluent are determined for each batch prior to release. Eachisotope concentration is compared to ten times the 1 OCFR20 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 the10 CFR 20 Appendix B, Table 2, Column 2, Effluent Concentration value of1.OE-03 pCi/ml to unrestricted areas.

Dissolved and Entrained Gases

Liquid effluent concentrations for dissolved and entrained gases arecompared 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 activationproducts, tritium and dissolved and entrained gases must be less than 100%.

1-12

SECTION 2

EFFLUENT AND WASTE DISPOSAL DATA

2-1

Airborne Effluents

Summaries of the radionuclide total curie activities and average release rates areincluded in Tables 2-1 and 2-2. Carbon-14 (C-14) activity released is not included inTables 2-1 or 2-2. C-14 released in airborne effluents is calculated based onconservative methodology provided by the Electric Power Research Institute (EPRIReport No. 1021106). See Section 4 for additional details on the calculation of C-14released in 2011 from the Susquehanna station. If a radionuclide was not detected,zero activity was used for that isotope in dose calculations and the activity is listed as"<MDC" (less than the minimum detectable concentration) in Tables 2-1 and 2-2.<MDC indicates that no activity was positively detected in any sample when sampleswere 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, RadioactiveGaseous Effluent Sampling and Analysis Program. In all cases, the measurementlaboratory MDCs were at or below the LLD levels required by Technical Requirements.The following are typical measurement laboratory MDCs.

Typical MDCs

Radionuclide MDC (pCi/cc)

Kr-87 4.3 E-08Kr-88 4.6 E-08Xe-1 33 3.0 E-08Xe-1 33m 1.1 E-07Xe-1 35 1.5 E-08Xe-1 35m 8.0 E-08Xe-1 38 1.5 E-07

Mn-54 2.9 E-13Fe-59 2.8 E-13Co-58 1.8 E-13Co-60 3.8 E-13Zn-65 1.0 E-13Mo-99 1.0 E-12Cs-1 34 2.4 E-13Cs-137 1.1 E-13Ce-1 41 1.0 E-13Ce-1 44 5.0 E-131-131 4.4 E-14Sr-89 1.1 E-13Sr-90 1.3 E-14H-3 1.5 E-08Gross Alpha 2.3 E-14

2-2

Batch Releases

1. Number of Batch Releases: 02. Total Time Period for Batch Release: NA3. Maximum Time Period for a Batch Release: NA4. Average Time Period for a Batch Release: NA5. Minimum Time Period for a Batch Release: NA

Abnormal Releases

1. Number of Releases 02. Total Activity Released NA

2-3

TABLE 2-1

AIRBORNE EFFLUENT - SUMMATION OF ALL RELEASES

First Second Third FourthUnit Quarter I Quarter Quarter QuarterA. Fission and Activation Gas

Total Release Ci <MDC <MDC <MDC <MDCAverage Release Rate for Period pCi/sec 0 0 0 0Percent of Applicable Limit (1.67E+04 % 0 0 0 0pCi/sec)

B. lodines

Total 1-131 Ci <MDC <MDC <MDC <MDC_ Average Release Rate for Period pCi/sec 0 0 0 0

Percent of Applicable Limit (1.73E+00 % 0 0 0 0_ tCi/sec)

C. Particulate

Particulate with Half-Life >8 Days Ci <MDC 2.24E-04 7.55E-06 <MDCAverage Release Rate for Period pCi/sec 0 2.85E-05 9.50E-07 0Percent of Applicable Limit (5.03E+01 % 0 5.67E-05 1.89E-06 0, Ci/sec)Gross Alpha Radioactivity Ci <MDC <MDC <MDC <MDC

D. Tritium

Total Release Ci 8.94E+00 2.91E+00 4.69E+00 3.05E+01Average Release Rate for Period pCi/sec 1.15E+00 3.70E-01 5.90E-01 3.84E+00Percent of Applicable Limit (2.44E+03 % 4.71 E-02 1.52E-02 2.42E-02 1.57E-01_ Ci/sec)

E. Radionuclide Fractional Summation

Sum of Percent of Applicable Limit % 0.05 0.02 0.02 0.16During Period for B, C and D (Limit I100%)

0

2-4

TABLE 2-2

AIRBORNE EFFLUENT - RADIONUCLIDES RELEASED

Releases in Continuous ModeFirst Second Third Fourth

Nuclides Released Unit Quarter Quarter Quarter Quarter

A. Fission and Activation GasesN-13 Ci <MDC <MDC <MDC <MDCAr-41 Ci <MDC <MDC <MDC <MDCKr-85 Ci <MDC <MDC <MDC <MDCKr-85m Ci <MDC <MDC <MDC <MDCKr-87 Ci <MDC <MDC <MDC <MDCKr-88 Ci <MDC <MDC <MDC <MDCKr-89 Ci <MDC <MDC <MDC <MDCXe-133 Ci <MDC <MDC <MDC <MDCXe-1 35 Ci <MDC <MDC <MDC <MDCXe-1 35m Ci <MDC <MDC <MDC <MDCXe-1 37 Ci <MDC <MDC <MDC <MDCXe-138 Ci <MDC <MDC <MDC <MDCTotal for Period Ci 0 0 0 0

B. lodines1-131 Ci <MDC <MDC <MDC <MDC1-133 Ci <MDC <MDC <MDC <MDC

01-135 Ci <MDC <MDC' <MDCTotal for Period Ci 0 0 0 0

C. ParticulateCr-51 Ci <MDC 1.61 E-04 <MDC <MDCMn-54 Ci <MDC <MDC <MDC <MDCFe-59 Ci <MDC <MDC <MDC <MDCCo-57 Ci <MDC <MDC <MDC <MDCCo-58 Ci <MDC <MDC <MDC <MDCCo-60 Ci <MDC 6.32E-05 7.55E-06 <MDCZn-65 Ci <MDC <MDC <MDC <MDCSr-89 Ci <MDC <MDC <MDC <MDCSr-90 Ci <MDC <MDC <MDC <MDCCs-134 Ci <MDC <MDC <MDC <MDCCs-137 Ci <MDC <MDC <MDC <MDCCe-141 Ci <MDC <MDC <MDC <MDCCe-144 Ci <MDC <MDC <MDC <MDCNb-95 Ci <MDC <MDC <MDC <MDCBa-La-140 Ci <MDC <MDC <MDC <MDCTotal for Period Ci 0 2.24E-04 7.55E-06 0

2-5

Waterborne Effluents

Summaries of the radionuclide total curie activities, average diluted concentrations, andpercent 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 Releases2. Total Time Period for a Batch Release3. Maximum Time Period for a Batch

Release4. Average Time Period for a Batch

Release5. Minimum Time Period for a Batch

Release6. Average Cooling Tower Blowdown

Flow Rate During Periods of Release7. Susquehanna River Flow Rate

*Units of time and flow are expressed in

respectively.

283.71 E+033.OOE+02

486.58E+033.08E+02

497.59E+033.07E+02

231.74E+032.81 E+02

1481.96E+043.08E+02

1.33E+02

2.90E+01

1.33E+02 1.37E+02 1.55E+02 7.55E+01

3.OOE+01 2.90E+01 3.OOE+01 3.20E+01

1.22E+04 9.47E+03 1.12E+04 1.24E+04 1.09E+04

1.29E+07 1.76E+07 1.1OE+07 1.12E+07 1.32E+07

minutes and gallons per minute (gpm),

If a radionuclide was not detected, zero activity was used for that isotope in dosecalculations and the activity is listed as "<MDC" (less than the miniumum detectableconcentration) in Tables 2-3 and 2-4. <MDC indicates that no activity was positivelydetected in any sample when samples were analyzed with techniques which achievedthe required Lower Limits of Detection (LLD) as specified in the Technical Requirement3A11.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. In all cases, themeasurement laboratory MDCs were at or below the LLD levels required by TechnicalRequirements. The following are typical measurement laboratory MDCs.

Radionuclide

Mn-54Fe-59Co-58Co-60Zn-65Mo-991-131Cs-134Cs-137Ce-1 41Ce-1 44Sr-89Sr-90Fe-55H-3Gross Alpha

MDC (uCi/ml)

4.5 E-085.0 E-084.0 E-085.4 E-084.9 E-081.7 E-072.0 E-082.2 E-082.6 E-083.2 E-081.3 E-074.4 E-081.6 E-088.2 E-073.6 E-063.7 E-09

2-6

Abnormal Releases

1. Number of releases 0 0 0 02. Volume Released (Gallons) N/A N/A N/A N/A3. Total Activity Released (Ci) N/A N/A N/A N/A

2-7

TABLE 2-3

WATERBORNE EFFLUENT - SUMMATION OF ALL RELEASES

First Second Third FourthIln

First Secondf'% =•r

Thirde% ý* ý

FourthA C; ; A A *; #; 0 A *n.t .c[ o ,.1aV.II nIII , /•~|Va,.t, rI tI-IJ ta•pL Vil, Ui. t51 L.M,~i |t;I tMU~l It~i t, tUII .•

1. Total Release (excluding: Tritium, Ent.Gases, Alpha) Ci 2.30E-03 5.27E-03 1.00E-02 5.30E-03

2. Average Diluted ConcentrationDuring Period pCi/ml 1.34E-08 2.23E-08 3.12E-08 6.52E-08

3. Sum of Average Diluted CnLn RatioDuring Period Unitless 3.1 OE-04 5.43E-04 8.63E-04 1.90E-03

4. Percent of Applicable Limit (Ratio < 1.0) % 0.03 0.05 0.09 0.20

8. Tritium1. Total Release Ci 1.18E+01 1.78E+01 1.81 E+01 4.09E+002. Average Diluted Concentration

During Period IpCi/ml 6.89E-05 7.56E-05 5.65E-05 5.03E-053. Percent of Applicable Limit (1.OE-2 t.Ci/ml) % 0.69 0.76 0.57 0.50

C. Dissolved and Entrained Gases1. Total Release Ci <MDC <MDC 7.08E-06 5.74E-062. Average Diluted Concentration PICi/ml 0.OOE+00 0.OOE+00 2.21 E-1 1 7.06E-1 1

During Period _ I3. Percent of Applicable Limit (2.OE-4 iiCi/ml) % 0.OOE+00 0.OOE+00 1.10E-05 3.53E-O

D. Radionuclide Fractional SummationSSum of Percent of Applicable Limit During

Period for A, B and C (Limit = 100%) % 0.72 0.81 0.66 0.70

E. Gross AlDha Radioactivity1. Total Release

F. Volume of Water Released(Prior to Dilution)

G. Volume of Dilution WaterUsed During Period of Release

H. Volume of Dilution WaterUsed Over Entire Period

ci I <MDC 5.87E-06 3.91 E-05 1.46E-05

Gallons 2.79E+05 5.02E+05 I 5.93E+05 I 1.14E+05Liters 1.06E+06 1.90E+06 2.24E+06 4.31 E+05

Gallonsa 4.52E+07 6.18E+07 I 8.40E+07 I 2.14E+07Liters 1.71 E+08 2.34E+08 3.18E+08 8.09E+07

Gallons 1.45E+09 1.19E+09 I 1.78E+09 I 1.58E+09Liters 5.49E+09 4.50E+09 6.73E+09 5.97E+09

2-8

TABLE 2-4

WATERBORNE EFFLUENT - RADIONUCLIDES RELEASED

Releases in Batch ModeNuclides Unit First Second Third FourthReleased Quarter Quarter Quarter Quarter

A. Fission and Activation ProductsNa-24 Ci <MDC <MDC <MDC <MDCCr-51 Ci 2.99E-04 3.04E-04 1.04E-06 <MDCMn-54 Ci 1.47E-05 1.87E-05 3.92E-05 2.05E-06Fe-55 Ci <MDC <MDC <MDC <MDCCo-58 Ci 1.51 E-04 1.13E-03 1.78E-03 5.91 E-04Fe-59 Ci <MDC 2.06E-06 <MDC <MDCCo-60 Ci 1.18E-03 3.45E-03 7.78E-03 4.33E-03Zn-65 Ci 6.57E-04 3.63E-04 4.17E-04 3.71 E-04Sr-89 Ci <MDC <MDC <MDC <MDCSr-90 Ci <MDC <MDC <MDC <MDCNb-95 Ci <MDC 6.66E-07 <MDC <MDCTc-99m Ci <MDC <MDC <MDC <MDCSb-124 Ci <MDC <MDC <MDC <MDCCs-1 37 Ci <MDC <MDC <MDC <MDCSb-125 Ci <MDC <MDC <MDC <MDCTa-182 Ci <MDC 2.75E-06 <MDC <MDCTotal for Period Ci 2.30E-03 5.27E-03 1.OOE-02 5.30E-03

B. TritiumTotal for Period Cij 1.1 8E+01 1.78E+01 1.81 E+01 4.09E+00

C. Dissolved and Entrained GasesAr-41 Ci <MDC <MDC <MDC <MDCKr-85 Ci <MDC <MDC <MDC <MDCKr-85m Ci <MDC <MDC <MDC <MDCKr-87 Ci <MDC <MDC <MDC <MDCKr-88 Ci <MDC <MDC <MDC 5.74E-06Xe-131 m Ci <MDC <MDC <MDC <MDCXe-133m Ci <MDC <MDC <MDC <MDCXe-1 33 Ci <MDC <MDC 4.98E-06 <MDCXe-1 35m Ci <MDC <MDC <MDC <MDCXe-135 Ci <MDC <MDC 2.1OE-06 <MDCTotal for Period Ci 0 0 7.08E-06 5.74E-06

2-9

Figure 2-1

Susquehanna River Monthly Average FlowRates Data Period: 2011

0

Eu

0

0)

35.0

30.0

25.0

20.0

15.0

10.0

I I I I I I I I I I

5.0

0.0

--- • 2011

02-10

Figure 2-2

Monthly Liquid Radwaste Discharge Totals

400

350

300

250

"Im

j5 t 200

E10

0

150

100 -

50-

0 I I I I I I J I A S O

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

-.-.-- 2011!

2-11

TABLE 2-5

ESTIMATED TOTAL ERRORS ASSOCIATED WITHEFFLUENTS 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 MAXIMUMMEASUREMENT ERROR

3. Solid Wastes

a. Bead Resin / Charcoal - Class A HIC (Pyrolysis) ±25%

b. CFS Backwash Media - Class A HIC (Pyrolysis) ±25%

c. CFS Filters - Class A HIC (Pyrolysis) ±25%

d. Condensate Demineralizer / Radwaste Demineralizer - ±25%Class A HIC (Pyrolysis)

e. Contaminated Waste Oil - Class A Fuel Blending for ±25%

Co-Generation

f. Liquid Radwaste Filter Media - Class A HIC (Pyrolysis) ±25%

g. Processed DAW - Class A HIC (Compacted) ±25%

h. Processed DAW - Class A Strong Tight Container ±25%(Compacted)

i. Sump Sludge - Class A HIC (Pyrolysis) ±25%

2-12

SUSQUEHANNA STEAM ELECTRIC STATION

RADIOACTIVE WASTE REPORT

RADIOACTIVE EFFLUENT RELEASE REPORT

SOLID RADIOACTIVE WASTE

DATA PERIOD: JANUARY 1,2011 - DECEMBER 31, 2011

PREPARED BY:MICHAEL C. MICCAHEALTH PHYSICIST

APPROVED BY:RICK KESSLER

RADIOLOGICAL OPERATIONS SUPERVISOR

2-13

0REPORT 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 ofMDL values.

3. Estimated maximum measurement error is ±25%.

2-14

TABLE 2-6

WASTE DISPOSITION

Data Period: January 1, 2011 - December 31, 2011

A. SOLID WASTE SHIPPED OFF-SITE FOR BURIAL OR DISPOSAL

Number of Shipments Mode of Transportation Destination

NONE

B. IRRADIATED FUEL SHIPMENTS

Number of Shipments Mode of Transportation

NONE

Destination

NOTE: The number of shipments listed in A include only the shipments from PPLSusquehanna, LLC to a disposal site. It does not include shipments made to or fromvolume reduction vendors.

2-15

Table 2-7

Annual Waste Release Summary Report

Year: 2011Class: A Volume Reduction Vendor: Yes

Source: Bead Resin/CharcoalContainer: HIC (High Integrity Container)

Process: Pyrolysis

Nuclides Activity (mCi)

C-14 7.810E-03CO-58 5.11OE-03CO-60 1.200E+01CS-137 7.170E-01FE-55 1.250E+01H-3 5. 570E+001-129 6.970E-03MN-54 6.320E+00NI-63 1.040E+00SR-90 1.530E-02TC-99 6.180E-02ZN-65 1.180E+00

Total Activity (Ci) 0.039Container Volume 25.390 ft3

% of Total

0.02 %0.01 %

30.44 %1.82%

31.71 %14.13 %0.02 %

16.03 %2.64 %0.04 %0.16 %2.99 %

100.00 %0.719 m3

2-16

Table 2-8



Source: CFS Backwash MediaContainer: HIC (High Integrity Container)

Process: Pyrolysis


C-14 1.800E+00CO-58 7.720E+01CO-60 2.690E+03CR-51 3.560E+01CS-137 5.310E-01FE-55 9.080E+03FE-59 7.370E+00H-3 2.720E+011-129 7.100E-02MN-54 3.460E+02NB-95 4.960E+00NI-63 7.480E+01SR-90 6.520E-01TA-182 6.200E+00TC-99 6.470E-01ZN-65 1.040E+02ZR-95 4.170E+00


% of Total

0.01%0.62%

21.59 %0.29%0.00%

72.87 %0.06%0.22 %0.00 %2.78%0.04%0.60%0.01%0.05%0.01%0.83%0.03%

100.00 %0.489 m3

2-17

Table 2-9


Class: A

Container:

Year: 2011Volume Reduction Vendor: Yes

Source: CFS FiltersHIC (High Integrity Container)Process: Pyrolysis


C-14 3.970E+00CO-58 1.220E+02CO-60 5.990E+03CR-51 1.290E+02CS-137 1.180E+00FE-55 2. 020E+04FE-59 3.170E+01H-3 1.660E+011-129 1.170E-01MN-54 1.190E+03NB-95 1.680E+01NI-63 1.660E+02SR-90 1. 440E+00TC-99 1.070E+00ZN-65 3.720E+02


% of Total

0.01%0.43 %

21.21%0.46 %0.00%

71.52 %0.11%0.06%0.00%4.21%0.06%0.59%0.01%0.00%1.32%

100.00 %1.521 m3

2-18

Table 2-10


Class: ASource: Condensate

Container:


Demineralizer / Radwaste DemineralizerHIC (High Integrity Container)Process: Pyrolysis

Nuclides Activity (mCi) % of Total

C-14CO-58CO-60CR-51CS-137FE-55FE-59H-31-1291-131MN-54NB-95NI-63SB-124SB-125SN-113SR-90TC-99ZN-65ZR-95

1. 940E+037. 150E+024.470E+034. 050E+017. 130E+001. 11OE+033.740E+003. 810E+022.180E-019. 920E-021. 370E+032. 990E+011. 11OE+022.730E-011.470E+002. 020E+001.730E+001. 660E+003.700E+022.460E+01

10.580157.100 ft3

18.346 .76

42 .250.380 .07

10.490.043.600.000.00

12 .95

0.281.050.000.010 .02

0 .020.023.500.23

Total Activity (Ci)Container Volume

100.00 %4.449 m3

2-19

Table 2-11


Year: 2011Class: A Volume Reduction Vendor:

Source: Contaminated Waste OilContainer: None

Process: Fuel Blending for Co-Generation

Yes

Nuclides

C-14CO-60CS-137FE-55H-31-129MN- 54NI-63TC-99

Activity (mCi)

< 1.080E-031. 150E+001. 840E-039. 170E-019. 820E+00

< 2.380E-043. 960E-028. 140E-03

< 5.840E-03

% of Total

0.019.630.027.68

82.220.000.330.070.05 6

Total Activity (Ci)Container Volume

0.0120.000 ft3

100.00 %0.000 m3

2-20

Table 2-12



Source: Liquid Radwaste Filter MediaContainer: HIC (High Integrity Container)

Process: Pyrolysis


C-14 5.690E-02CO-58 3.240E+01CO-60 1.530E+03CR-51 1.410E+01CS-137 4.120E-01FE-55 6.790E+03H-3 2.520E+011-129 1.360E-02MN-54 2.420E+02NB-95 1.320E+00NI-63 1.020E+02SR-90 4.340E-02TA-182 7.130E+00TC-99 1.780E-01ZN-65 1.030E+.02


% of Total

0.00 %0.37 %

17.29 %0.16 %0.00 %

76.74 %0.28 %0.00 %2.74 %0.01%1.15 %0.00 %0.08 %0.00 %1.16 %

100.00 %0.461 m3

2-21

Table 2-13


Year: 2011Class: A Volume Reduction Vendor:

Source: Processed DAWContainer: HIC (High Integrity Container)

Process: Compacted

Yes


C-14 4.200E-01CO-58 1.150E+02CO-60 1.070E+03CS-137 3.700E+00FE-55 2.430E+03H-3 2. 170E-011-129 1.240E-03MN-54 1.370E+02NB-95 5.570E+00NI-63 4.950E+01SR-89 3.970E+00SR-90 2.940E-02TC-99 1. 070E-02ZN-65 4.450E+02


% of Total

0.01%2.70 %

25.11 %0.09 %

57.04 %0.01%0.00 %3.22 %0.13 %1.16 %0.09 %0.00 %0.00 %

10.44 %

100.00 %0.629 m3

2-22

Table 2-14


Class: AYear: 2011

Volume Reduction VenSource: Processed DAW

Container: Strong Tight ContainerProcess: Compacted

dor: Yes


C-14 3.592E-01CO-58 7.354E+00CO-60 2.709E+03CR-51 4.106E-01CS-137 2.364E+00FE-55 "7.445E+03FE-59 2.098E-02H-3 1.383E+02HF-181 3.820E-041-129 2.710E-02MN-54 2.229E+02NB-94 3.160E-03NB-95 6.260E-02NI-59 7.560E-01NI-63 1.563E+02SB-124 8.780E-05SB-125 3.210E-04SR-90 1.577E-02TA-182 8.890E-02TC-99 1.058E-01ZN-65 3.489E+01ZR-95 2.230E-02


% of Total

0.00 %0.07 %

25.27 %0.00 %0.02 %

69.47 %0.00 %1.29 %0.00 %0.00 %2.08 %0.00 %0.00 %0.01%1.46 %0.00 %0.00 %0.00 %0.00 %0.00 %0.33 %0.00 %

100.00 %130.298 m3

2-23

Table 2-15


Class: A

Container:


Source: Sump SludgeHIC (High Integrity Container)Process: Pyrolysis


C-14 9.900E+00CO-58 2.770E-01CO-60 2.150E+02CS-137 1.450E+00FE-55 7.480E+02H-3 1.320E+01HF-181 1.590E-011-129 1.570E-01MN-54 1.760E+01NB-95 5.150E-01NI-63 2.150E+01TC-99 4.800E-01ZN-65 2.540E+00ZR-95 6.570E-01


% of Total

0.96%0.03%

20.84 %0.14%

72.52 %1.28%0.02%0.02%1.71%0.05 %2.08 %0.05 %0.25 %0.06 %

100.00 %0.542 m3

2-24

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 theearly 1970s. At the present time, the meteorological system is based on a 300-foot hightower located approximately 1,000 feet to the southeast of the plant. Wind sensors aremounted at the 10m and 60m elevations on this tower. Vertical temperature differentialis measured with redundant sensor pairs between the 10m and 60m levels. Sigmatheta (the standard deviation of horizontal wind direction) is calculated from winddirection at both levels. Dew point and ambient temperature sensors are present at the10m level. Precipitation is measured at ground level.

A back-up meteorological tower was erected in 1982. It is a 10m tower providingalternate measurements of wind speed, wind direction, and sigma theta. A 10msupplemental downriver meteorological tower is also available. This tower measureswind speed, wind direction, sigma theta, temperature and dew point.

Meteorological data are transmitted to the plant Control Room, Technical SupportCenter, Emergency Operations Facility for emergency response availability, and ABSGConsulting, Inc. ABSG Consulting, Inc., located in Rockville, Maryland, providesmeteorological consulting services to PPL Susquehanna, LLC.

Regulatory Guide 1.23 (Safety Guide 23) requires at least 90% data recovery formeteorological instrumentation. During 2011, all meteorological instrumentation met the90% data recovery requirement. Table 3-1 lists the percent valid data recovery valuesfor the parameters monitored as part of the PPL Susquehanna MeteorologicalMonitoring Program.

Dispersion modeling for effluents from normal operation is done using the MIDASsystem XDCALC program, a straight-line Gaussian plume model designed to estimateaverage relative concentration. The model was developed in accordance withRegulatory Guide 1.111. For periods when the wind speed is calm, the actual winddirection that last occurred is used.

XDCALC and the XQINTR program that interpolates X/Q values to exact locations bothuse terrain correction factors to account for the temporal and spatial variations in theairflow in the region. A straight-line trajectory model assumes that a constant meanwind transports and diffuses effluents in the direction of airflow at the release pointwithin the entire region of interest. The terrain correction factors were taken from FSARTable 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 primarymeteorological tower. Table 3-4 lists no decay, undepleted X/Q values at variousdistances from the site. Table 3-5 lists 2.26 day decay, undepleted X/Q values atvarious distances from the site. Table 3-6 lists 8-day decay, depleted X/Q values atvarious 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 2011

Parameter Percent Valid Data Recovery

Wind Speed 1Oin - Primary (1) 99.3Wind Speed 60m - Primary 99.3

Wind Speed 10m - Backup (2) 99.5

Wind Speed 10m - Downriver (3) 100.0

Wind Direction 10m - Primary 98.4Wind Direction 60m - Primary 98.4Wind Direction 10m - Backup 99.6Wind Direction 10m - Downriver 100.0Temperature 10m -Primary 99.4

Dew Point 10m - Primary 100.0

Delta Temperature 60m - Primary 99.0

Sigma Theta lOm - Primary 98.4Sigma Theta 60m - Primary 98.4Sigma Theta 10m - Backup 99.6Sigma Theta 10m - Downriver 100.0

Precipitation - Primary 100.0

Composite Parameters

Wind Speed and Direction 10m, 98.1Delta Temperature 60-l1Om

Wind Speed and Direction 60m, 98.1Delta Temperature 60-10m

(1) SSES "Primary" meteorological tower

(2) SSES "Backup" meteorological tower

(3) SSES "Downriver" meteorological tower

3-3

TABLE 3-2

SSES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND WINDDIRECTION 10m VERSUS DELTA TEMPERATURE 60-10m FOR THE PERIOD OF

JANUARY 1, 2011 THROUGH DECEMBER 31, 2011

Joint Frequency Distribution

Hours at Each Wind Speed and Direction

Total PeriodPeriod of Record =

Elevation: Speed:Stability Class A

10_SPD

1/1/2011 00:00 - 12/31/2011 23:00Direction: 10_WD Lapse: DT60-10A

Delta Teniperattire Extremely Unstable

Wind Speed (mph)

Wind Direction

NNNENEENEEESESESSESSSWSWWSWWWNWNWNNW

1-4 4-8 8-13 13-19 19-25 > 25 Total

002333311

2320000

0050000104820000

0300000022610000

0000000000000000

0000000000000000

0000000000000000

0373333238

1750000

Total 23 20 14 0 0 0 57

Calm Hours not Included above for:Variable Direction Hours for:Invalid Hours for:Valid Hours for this Stability Class for:Total Hours for Period

Total PeriodTotal PeriodTotal PeriodTotal Period

00

16757

8760

3-4

TABLE 3-2(continued)


JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 (Continued)




Elevation: Speed:Stability Class B

1/1/2011 00:00 - 12/31/2011 23:001 0_SPD Direction: 1 0_WD Lapse: DT60-1OA

Delta Temperature Moderately Unstable

Wind Speed (mph)

Wind Direction


Total

1-4

0010100110100000

4-8 8-13 13-19

1 2 03 1 06 0 00 0 00 0 01 0 00 0 00 0 02 5 0

11 4 016 22 03 8 11 2 01 0 00 0 00 0 0

19-25

0000000000000000

> 25

0000000000000000

Total

34701

18

1539123100

5 45 44 1 0 0 95



00

16795

8760

3-5






Period of Record =Elevation: Speed: 10_SPDStability Class C

Total Period1/1/2011 00:00 - 12/31/2011 23:00

Direction: 10_WD Lapse: DT60-10A

Delta Temperature Slightly Unstable

Wind Speed (mph)

Wind Direction


1-411

02710013000000

4-8

610311341115

2243143161

8- 13

6911

205

137

3028

904

11

13 - 19

0100000001440053

19-25

0000000000000000

> 25

0000000000000000

Total

1321321612416

19337746121

1515

Total 16 162 127 18 0 0 323



00

167323

8760

3-6






Total Period

Period of Record= 1/1/2011 00:00 - 12/31/2011 23:00Elevation: Speed: 10_SPD Direction: 10_WD Lapse: DT60-IOAStability Class D Delta Temperature Neutral

Wind Speed (mph)

Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total

N 26 168 143 4 0 0 341NNE 77 212 43 0 0 0 332NE 141 203 10 0 0 0 354ENE 132 98 22 1 0 0 253E 117 49 10 0 0 0 176ESE 86 25 28 17 2 0 158SE 105 44 15 1 0 0 165SSE 81 103 12 1 0 0 197S 91 166 49 6 0 0 312SSW 81 209 39 1 0 0 330SW 63 301 163 15 0 0 542WSW 28 147 139 41 0 0 355W 17 77 87 42 0 0 223WNW 10 57 65 14 0 0 146NW 12 74 127 35 3 0 251NNW 7 90 139 11 0 0 247

Total 1074 2023 1091 189 5 0 4382

Calm Hours not Included above for: Total Period 0Variable Direction Hours for: Total Period 0Invalid Hours for: Total Period 167Valid Hours for this Stability Class for: Total Period 4382Total Hours for Period 8760

3-7






Total PeriodPeriod of Record= 1/1/2011 00:00 - 12/31/2011 23:00Elevation: Speed: 1 0_SPD Direction: 10_WD Lapse: DT60-10AStability Class E Delta Temperature Slightly Stable

Wind Speed (mph)

Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total


Total 1461 730 59 9 3 0 2262


3-8






Total Period

Period of Record =Elevation: Speed:

Stability Class F

1/1/2011 00:00 - 12/31/2011 23:00Direction: 10_WD Lapse: D10_SPD T60-1OA

Delta Temperature Moderately Stable

Wind Speed (mph)

Wind Direction


Total

1-4 4-8 8-13 13-19 19-25 > 25

2 3 0 0 0 026 7 0 0 0 0

106 7 0 0 0 0391 11 0 0 0 0171 0 0 0 0 048 0 0 0 0 036 0 0 0 0 030 0 0 0 0 027 4 0 0 0 021 14 0 0 0 0

3 7 0 0 0 03 1 0 0 0 00 0 0 0 0 01 0 0 0 0 02 0 0 0 0 01 1 0 0 0 0

Total

533

11340217148363031351040122

868 55 0 0 0 0 923



00

167923

8760

3-9







Elevation: Speed:Stability Class G

10_SPD

1/1/2011 00:00 - 12/31/2011 23:00Direction: 10_WD Lapse: DT60-10A

Delta Temperature Extremely Stable

Wind Speed (mph)

Wind Direction


Total

1-4 4-8 8-13 13-19 19-25 > 25 Total

22

67319

852321841001001

534

012

13000010000000

0000000000000000

0000000000000000

0000000000000,000

0000000000000000

23

69332

852321

851001001

17 0 0 0 0 551



00

167551

8760

3-10






Summary of All Stability ClassesTotal Period

1/1/2011 00:00 - 12/31/2011 23:00Period of Record =

Elevation: Speed: 10_SPD Direction: 10_WD Lapse: DT60-10A

Delta Temperature

Wind Speed (mph)

Wind Direction


1-4 4-8 8-13 13-19 19-25

58 224 153 5 0198 332 56 5 3477 317 14 0 0

1177 159 24 1 0579 61 11 0 0274 32 32 17 2290 54 17 1 0215 127 22 1 0262 272 80 7 0197 402 63 3 0118 480 233 20 049 213 180 47 030 98 101 42 017 66 65 14 022 94 134 40 318 121 150 14 0

> 25

0000000000000000

Total

440594808

1361651357362365621665851489271162293303

Total 3981 3052 1335 217 8 0 8593



00

16785938760

3-11

TABLE 3-3


JANUARY 1, 2011 THROUGH DECEMBER 31, 2011



Total Period

Period of Record= 1/1/2011 00:00 - 12/31/2011 23:00Elevation: Speed: 60SPD Direction: 60_WD Lapse: DT60-10AStability Class A Delta Temperature Extremely Unstable

Wind Speed (mph)



Total 17 16 14 9 1 0 57

Calm Hours not Included above for: Total Period 1Variable Direction Hours for: Total Period 0Invalid Hours for: Total Period 165Valid Hours for this Stability Class for: Total Period 57

Total Hours for Period 8760

3-12






Total PeriodPeriod of Record= 1/1/2011 00:00 - 12/31/2011 23:00Elevation: Speed: 60_SPD Direction: 60_WD Lapse: DT60-1OAStability Class B Delta Temperature Moderately Unstable

Wind Speed (mph)

Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total


Total 4 9 57 25 0 0 95

Calm Hours not Included above for: Total Period IVariable Direction Hours for: Total Period 0Invalid Hours for: Total Period 165Valid Hours for this Stability Class for: Total Period 95Total Hours for Period 8760

3-13






Total Period

Period of Record =

Elevation: Speed:Stability Class C

1/1/2011 00:00 - 12/31/2011 23:00Direction: 60_WD Lapse: DT60-10A60_SPD

Delta Temperature Slightly Unstable

Wind Speed (mph)

Wind Direction


1-4 4-8 8-13 13-19 19-25 > 25 Total

0243000011

000000

41712210111

11722110

131310111

327

1554199444

3500100285

201503

113

0000000011

430010

0000000000000000

203726

63145

18338539118

177

Total 11 63 160


76 10 0 320


I0

165320

8760

3-14







Elevation: Speed:Stability Class D

1/1/2011 00:00 - 12/31/2011 23:00Direction: 60_WD Lapse: DT60-1 OA60 SPD

Delta Temperature Neutral

Wind Speed (mph)

Wind Direction


1-4 4-8 8-13 13-19 19-25 > 25 Total

23517458413143414647441911103

12

116164155563035525365

135226

8433233334

148150723431183259

11898

2421699589

133158

2234109

1317109

3142

13312755526454

10007903

187

26412414102

0000261001

310100

310399311157124116138165278330674441218189243260

Total 554 1294 1646 682 162



15 4353

10

16543538760

3-15

TABLE 3-3





Total Period

Period of Record = 1/1/2011 00:00 - 12/31/2011 23:00Elevation: Speed: 60_SPD Direction: 60_WD Lapse: DT60-10AStability Class E Delta Temperature Slightly Stable

Wind Speed (mph)



Total 652 911 591 107 18 6 2285


3-16






Total PeriodPeriod of Record 1/1/2011 00:00 - 12/31/2011 23:00

Elevation: Speed: 60_SPD Direction: 60_WD Lapse: DT60-1OAStability Class F Delta Temperature Moderately Stable

Wind Speed (mph)



Total 375 490 58 9 0 0 932


3-17






Total Period

Period of Record= 1/1/2011 00:00 - 12/31/2011 23:00Elevation: Speed: 60_SPD Direction: 60_WD Lapse: DT60-1OAStability Class G Delta Temperature Extremely Stable

Wind Speed (mph)

Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25. Total


Total 198 316 37 1 0 0 552


3-18






Summary of All Stability ClassesTotal Period

Period of Record= 1/1/2011 00:00 - 12/31/2011 23:00Elevation: Speed: 60-SPD Direction: 60_WD Lapse: DT60-1OA

Delta Temperature

Wind Speed (mph)



Total 1811 3099 2563 909 191 21 8594


3-19

TABLE 3-4

2011 SSES Annual Relative Concentrations - No Decay, Undepleted X/Q (sec/mr3)

Miles

Direction 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50From

N 4.39E-06 8.30E-07 3.43E-07 1.80E-07 1.16E-07 4.26E-08 1.16E-08 5.55E-09 3.47E-09 2.44E-09

NNE 8.08E-06 1.65E-06 7.35E-07 3.92E-07 2.52E-07 9.29E-08 2.53E-08 1.23E-08 7.82E-09 5.56E-09

NE 1.59E-05 2.98E-06 1.35E-06 7.63E-07 5.03E-07 1.97E-07 5.92E-08 2.96E-08 1.90E-08 1.38E-08

ENE 4.34E-05 8.13E-06 3.94E-06 2.32E-06 1.54E-06 6.1OE-07 1.76E-07 8.53E-08 5.52E-08 4.05E-08

E 2.02E-05 3.69E-06 1.62E-06 9.16E-07 6.11E-07 2.48E-07 7.82E-08 3.95E-08 2.55E-08 1.86E-08

ESE 1.03E-05 1.99E-06 8.97E-07 5.OOE-07 3.32E-07 1.34E-07 3.70E-08 1.62E-08 1.04E-08 7.49E-09

SE 1.16E-05 2.28E-06 1.04E-06 5.88E-07 3.91E-07 1.59E-07 3.99E-08 1.47E-08 9.38E-09 6.75E-09

SSE 8.37E-06 1.63E-06 7.19E-07 4.01E-07 2.69E-07 1.15E-07 2.97E-08 1.05E-08 6.68E-09 4.78E-09

S 7.63E-06 1.62E-06 7.82E-07 4.49E-07 3.06E-07 1.41E-07 3.84E-08 1.31E-08 8.28E-09 5.90E-09

SSW 8.40E-06 1.69E-06 7.75E-07 4.37E-07 2.88E-07 1.19E-07 3.04E-08 1.15E-08 7.26E-09 5.16E-09

SW 6.59E-06 1.33E-06 6.25E-07 3.55E-07 2.36E-07 1.02E-07 2.56E-08 8.46E-09 5.27E-09 3.69E-09

WSW 3.76E-06 7.32E-07 3.40E-07 1.99E-07 1.36E-07 6.39E-08 1.98E-08 7.37E-09 3.75E-09 2.04E-09

W 1.86E-06 3.54E-07 1.52E-07 8.31E-08 5.44E-08 2.23E-08 5.99E-09 2.41E-09 1.49E-09 1.03E-09

WNW 1.19E-06 2.17E-07 8.67E-08 4.53E-08 2.88E-08 1.05E-08 2.81E-09 1.31E-09 8.06E-10 5.54E-10

NW 2.11E-06 3.91E-07 1.56E-07 7.99E-08 5.06E-08 1.82E-08 4.80E-09 2.27E-09 1.40E-09 9.71E-10

NNW 2.28E-06 4.32E-07 1.82E-07 9.65E-08 6.08E-08 2.12E-08 5.27E-09 2.49E-09 1.54E-09 1.07E-09

TABLE 3-5

2011 SSES Annual Relative Concentrations - 2.26-Day Decay, Undepleted X/Q (sec/m3 )

Miles

Direction 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50From

N 4.38E-06 8.25E-07 3.40E-07 1.78E-07 1.13E-07 4.13E-08 1.09E-08 5.01E-09 3.OOE-09 2.02E-09

NNE 8.07E-06 1.64E-06 7.27E-07 3.86E-07 2.47E-07 8.98E-08 2.36E-08 1.1OE-08 6.65E-09 4.52E-09

NE 1.59E-05 2.96E-06 1.33E-06 7.48E-07 4.91E-07 1.89E-07 5.44E-08 2.57E-08 1.55E-08 1.06E-08

ENE 4.32E-05 8.06E-06 3.89E-06 2.27E-06 1.50E-06 5.83E-07 1.61E-07 7.37E-08 4.50E-08 3.11E-08

E 2.02E-05 3.65E-06 1.60E-06 8.94E-07 5.93E-07 2.35E-07 7.05E-08 3.32E-08 2.OOE-08 1.36E-08

ESE 1.03E-05 1.97E-06 8.81E-07 4.88E-07 3.21E-07 1.27E-07 3.32E-08 1.35E-08 8.05E-09 5.41E-09

SE 1.16E-05 2.26E-06 1.03E-06 5.75E-07 3.79E-07 1.52E-07 3.61E-08 1.25E-08 7.43E-09 5.01E-09

SSE 8.35E-06 1.62E-06 7.09E-07 3.93E-07 2.62E-07 1.1OE-07 2.72E-08 9.12E-09 5.46E-09 3.69E-09

S 7.62E-06 1.61E-06 7.73E-07 4.42E-07 3.OOE-07 1.36E-07 3.57E-08 1.16E-08 7.OOE-09 4.75E-09

SSW 8.39E-06 1.68E-06 7.68E-07 4.31E-07 2.83E-07 1.15E-07 2.87E-08 1.04E-08 6.31E-09 4.30E-09

SW 6.58E-06 1.33E-06 6.20E-07 3.51E-07 2.33E-07 9.95E-08 2.44E-08 7.80E-09 4.71E-09 3.19E-09

WSW 3.75E-06 7.29E-07 3.38E-07 1.97E-07 1.34E-07 6.26E-08 1.90E-08 6.85E-09 3.39E-09 1.79E-09

W 1.85E-06 3.52E-07 1.51E-07 8.21 E-08 5.36E-08 2.17E-08 5.68E-09 2.20E-09 1.31E-09 8.81E-10

WNW 1.19E-06 2.16E-07 8.61E-08 4.49E-08 2.84E-08 1.03E-08 2.69E-09 1.22E-09 7.24E-10 4.83E-10

NW 2.11 E-06 3.90E-07 1.55E-07 7.91E-08 5.OOE-08 1.78E-08 4.59E-09 2.1OE-09 1.26E-09 8.46E-10

NNW 2.28E-06 4.30E-07 1.81E-07 9.56E-08 6.OOE-08 2.07E-08 5.05E-09 2.32E-09 1.39E-09 9.41E-10

3-21

TABLE 3-6

2011 SSES Annual Relative Concentrations - 8-Day Decay, Depleted X/Q (sec/mr3)

Miles

Direction 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50From

N 4.01E-06 7.03E-07 2.77E-07 1.40E-07 8.65E-08 2.96E-08 7.11E-09 2.98E-09 1.67E-09 1.06E-09

NNE 7.39E-06 1.40E-06 5.94E-07 3.03E-07 1.89E-07 6.45E-08 1.55E-08 6.61E-09 3.74E-09 2.41E-09

NE 1.45E-05 2.53E-06 1.09E-06 5.90E-07 3.76E-07 1.37E-07 3.62E-08 1.57E-08 8.99E-09 5.88E-09

ENE 3.96E-05 6.88E-06 3.19E-06 1.79E-06 1.15E-06 4.22E-07 1.08E-07 4.52E-08 2.61E-08 1.73E-08

E 1.85E-05 3.12E-06 1.31E-06 7.07E-07 4.56E-07 1.71E-07 4.75E-08 2.08E-08 1.19E-08 7.81E-09

ESE 9.41E-06 1.69E-06 7.24E-07 3.86E-07 2.48E-07 9.23E-08 2.24E-08 8.50E-09 4.83E-09 3.14E-09

SE 1.06E-05 1.93E-06 8.41E-07 4.55E-07 2.92E-07 1.1OE-07 2.43E-08 7.75E-09 4.40E-09 2.85E-09

SSE 7.64E-06 1.38E-06 5.81E-07 3.1OE-07 2.01E-07 7.94E-08 1.81E-08 5.59E-09 3.16E-09 2.04E-09

S 6.97E-06 1.37E-06 6.32E-07 3.48E-07 2.29E-07 9.77E-08 2.36E-08 6.99E-09 3.95E-09 2.55E-09

SSW 7.68E-06 1.43E-06 6.27E-07 3.38E-07 2.16E-07 8.24E-08 1.87E-08 6.17E-09 3.49E-09 2.25E-09

SW 6.02E-06 1.13E-06 5.06E-07 2.75E-07 1.77E-07 7.1OE-08 1.58E-08 4.57E-09 2.56E-09 1.63E-09

WSW 3.43E-06 6.20E-07 2.75E-07 1.55E-07 1.02E-07 4.46E-08 1.23E-08 3.99E-09 1.82E-09 9.02E-10

W 1.70E-06 3.OOE-07 1.23E-07 6.44E-08 4.08E-08 1.55E-08 3.69E-09 1.30E-09 7.19E-10 4.53E-10

WNW 1.09E-06 1.84E-07 7.02E-08 3.51E-08 2.16E-08 7.32E-09 1.74E-09 7.11 E-10 3.91E-10 2.45E-10

NW 1.93E-06 3.31E-07 1.27E-07 6.19E-08 3.80E-08 1.27E-08 2.97E-09 1.23E-09 6.80E-10 4.29E-10

NNW 2.08E-06 3.66E-07 1.47E-07 7.48E-08 4.56E-08 1.48E-08 3.26E-09 1.35E-09 7.51E-10 4.75E-10

TABLE 3-7

2011 SSES Annual Relative Concentrations - D/Q (m 2)

Miles

Direction 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50From

N 2.59E-08 3.82E-09 1.57E-09 7.43E-10 4.39E-10 1.39E-10 3.33E-11 1.23E-11 6.54E-12 4.11E-12

NNE 3.35E-08 5.18E-09 2.25E-09 1.07E-09 6.30E-10 1.96E-10 4.57E-11 1.68E-11 8.99E-12 5.65E-12

NE 4.15E-08 6.26E-09 2.68E-09 1.30E-09 7.69E-10 2.48E-10 6.07E-11 2.23E-11 1.19E-11 7.49E-12

ENE 7.38E-08 1.15E-08 5.1OE-09 2.50E-09 1.48E-09 4.67E-10 1.06E-10 3.73E-11 1.99E-11 1.25E-11

E 3.42E-08 4.99E-09 2.03E-09 9.71E-10 5.80E-10 1.91E-10 4.84E-11 1.78E-11 9.51E-12 5.97E-12

ESE 2.16E-08 3.27E-09 1.39E-09 6.73E-10 4.02E-10 1.33E-10 3.03E-1I 9.78E-12 5.22E-12 3.28E-12

SE 2.64E-08 4.01E-09 1.75E-09 8.65E-10 5.20E-10 1.76E-10 3.65E-11 1.00E-11 5.34E-12 3.35E-12

SSE 2.53E-08 3.78E-09 1.61E-09 7.95E-10 4.84E-10 1.73E-10 3.80E-11 1.01E-11 5.40E-12 3.39E-12

S 3.04E-08 4.87E-09 2.29E-09 1.18E-09 7.32E-10 2.84E-10 6.62E-11 1.70E-11 9.06E-12 5.69E-12

SSW 3.90E-08 5.96E-09 2.67E-09 1.35E-09 8.19E-10 2.86E-10 6.35E-11 1.81E-11 9.67E-12 6.08E-12

SW 4.49E-08 7.13E-09 3.36E-09 1.74E-09 1.07E-09 4.03E-10 9.11E-11 2.32E-11 1.24E-11 7.78E-12

WSW 2.95E-08 4.55E-09 2.12E-09 1.14E-09 7.23E-10 2.98E-10 8.39E-11 2.43E-11 1.06E-11 5.21E-12

W 1.38E-08 2.07E-09 8.94E-10 4.46E-10 2.72E-10 9.73E-11 2.37E-11 7.44E-12 3.97E-12 2.49E-12

WNW 9.08E-09 1.31E-09 5.28E-10 2.52E-10 1.50E-10 4.85E-11 1.20E-11 4.41E-12 2.36E-12 1.48E-12

NW 1.79E-08 2.62E-09 1.05E-09 4.88E-10 2.89E-10 9.16E-I1 2.20E-11 8.09E-12 4.32E-12 2.71E-12

NNW 1.85E-08 2.74E-09 1.16E-09 5.60E-10 3.28E-10 1.OOE-10 2.25E-11 8.28E-12 4.42E-12 2.78E-12

3-23

TABLE 3-8

2011 ATMOSPHERIC DISPERSION ESTIMATESFOR RETDAS INPUT AT SELECTED LOCATIONS

X/Q DEC+AFFECTED (1) (2) (3) (4)SECTOR LOCATION MILES X/O X/Q DEC DEP DEPOSITION

11/SW Maximum (X/Q) Site 0.61 1.18E-05 1.17E-05 1.06E-05 2.95E-08Boundary

9/S Closest (X/Q) Site Boundary 0.38 6.66E-06 6.65E-06 6.20 E-06 4.18E-0812 / WSW Maximum (X/Q) Residence 1.3 1.01 E-05 1.00E-05 8.65E-06 1.46E-0816 / NNW Maximum (D/Q) Residence 0.6 6.37E-06 6.35E-06 5.75E-06 1.84E-0812 / WSW Maximum (D/Q) Garden 1.3 1.01 E-05 1.OOE-05 8.65E-06 1.46E-0812 / WSW Maximum (D/Q) Dairy 1.7 6.82E-06 6.75E-06 5.70E-06 9.41 E-0912 / WSW Maximum (D/Q) Meat 1.7 6.82E-06 6.75E-06 5.70E-06 9.41 E-09

Producer3/ NE Riverlands / EIC 0.7 4.04E-06 4.03E-06 3.60E-06 2.56E-08

12 / WSW Tower's Club 0.5 4.33E-05 4.32E-05 3.95E-05 7.37E-08

NEAREST RESIDENCE WITHIN A 5-MILE RADIUS BY SECTOR

SECTOR AFFECTED X/Q DECNUMBER SECTOR NAME MILES X/Q X/Q DEC +DEP DEPOSITION

1 N H. Burd 1.3 1.99E-06 1.97E-06 1.70E-06 6.18E-092 NNE E. Ashbridge III 1 3.06E-06 3.05E-06 2.67E-06 1.19E-083 NE W. Tuggle 0.9 2.80E-06 2.79E-06 2.46E-06 1.68E-084 ENE R. Dickosky 2.1 4.42E-07 4.39E-07 3.63E-07 2.76E-09

5 E L.Kozlowski/M. Witts 1.4 3.93E-07 3.91E-07 3.34E-07 2.33E-096 ESE R. Panetta 0.5 1.19E-06 1.19E-06 1.08E-06 9.06E-097 SE J. Futoma 0.5 2.11E-06 2.1OE-06 1.92E-06 1.79E-08

8 SSE M. Naunczek 0.6 1.73E-06 1.72E-06 1.56E-06 1.34E-08

9 S S. Slusser 1 1.54E-06 1.53E-06 1.34E-06 7.75E-0910 SSW S. Molnar 0.9 3.45E-06 3.44E-06 3.03E-06 1.23E-0811 SW F. Michael 1.5 2.99E-06 2.96E-06 2.53E-06 6.27E-0912 WSW F. Michael 1.3 1.01 E-06 1.00E-06 8.65E-06 1.46E-0813 W F. Hummel 1.2 5.22E-06 5.17E-06 4.48E-06 7.38E-0914 WNW R. Orlando 0.8 5.1OE-06 5.06E-06 4.51 E-06 9.63E-0915 NW B. Kramer 0.7 7.06E-06 7.02E-06 6.30E-06 1.48E-0816 NNW G. John 0.6 6.37E-06 6.35E-06 5.75E-06 1.84E-08

NEAREST GARDEN WITHIN A 5-MILE RADIUS BY SECTOR

SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEC DEPOSITIONNUMBER SECTOR +DEP

1 N B. J. Wojcik 3.2 5.20E-07 5.12E-07 4.07E-07 1.40E-092 NNE R. Chapin 2.3 8.80E-07 8.72E-07 7.17E-07 3.05E-093 NE M. Welch 2.7 5.49E-07 5.44E-07 4.40E-07 2.89E-094 ENE G. Dennis 2.4 3.62E-07 3.59E-07 2.94E-07 2.26E-095 E W. Daily 1.8 2.62E-07 2.60E-07 2.18E-07 1.53E-096 ESE B. Smith 3.1 5.72E-08 5.67E-08 4.51 E-08 3.29E-107 SE T. Scholl 0.6 1.59E-06 1.59E-06 1.44E-06 1.30E-088 SSE H. Roinick 2.9 1.38E-07 1.36E-07 1.09E-07 8.40E-109 S T. Stemrich 2.7 2.96E-07 2.93E-07 2.37E-07 1.32E-0910 SSW S. Bodnar 1.2 2.28E-06 2.26E-06 1.96E-06 7.58E-0911 SW R. Broody 1.9 2.07E-06 2.05E-06 1.71 E-06 4.23E-0912 WSW F. Michael 1.3 1.01 E-05 1.OOE-05 8.65E-06 1.46E-0813 W F. Hummel 1.2 5.22E-06 5.17E-06 4.48E-06 7.38E-0914 WNW P. Moskaluk 1.3 2.47E-06 2.45E-06 2.11E-06 4.18E-0915 NW D. Goff 1.8 1.73E-06 1.71 E-06 1.44E-06 2.99E-0916 NNW P. Culver 4 3.24E-07 3.17E-07 2.46E-07 6.10E-10

0

0

3-24


NEAREST ANIMAL RAISED FOR MEAT CONSUMPTIONWITHIN A 5-MILE RADIUS BY SECTOR

SECTOR AFFECTED NAME MILES X/Q X/Q DEC DEPOSITIONNUMBER SECTOR DEC+DEP

2 NNE R.Chapin 2.3 8.80E-07 8.72E-07 7.17E-07 3.05E-094 ENE G.Dennis 2.4 3.62E-07 3.59E-07 2.94E-07 2.26E-095 E W. Daily 1.8 2.62E-07 2.60E-07 2.18E-07 1.53E-096 ESE B. Smith 3.1 5.72E-08 5.67E-08 4.51 E-08 3.29E-1010 SSW K. & C. Drasher 3.5 3.92E-07 3.85E-07 3.03E-07 1.07E-0912 WSW T. & M Berger 1.7 6.82E-06 6.75E-06 5.70E-06 9.41 E-09

ALL DAIRY LOCATIONS

SECTOR AFFECTED NAME MILES X/O X/Q DEC X/ DEPOSITIONNUMBER SECTOR DEC+DEP

5 E W.Bloss 4.5 5.44E-08 5.85E-08 4.08E-08 2.72E-1010 SSW K. & C. Drasher 3.5 3.92E-07 3.85E-07 3.03E-07 1.07E-0910 SSW K.Davis 14.01 2.87E-08 2.69E-08 1.79E-08 5.28E-1112 WSW T. & M. Berger 1.7 6.82E-06 6.75E-06 5.70E-06 9.41 E-0913 W J. Dent 5 5.07E-07 4.90E-07 3.72E-07 4.61E-10

1 X/Q RELATIVE CONCENTRATION (SEC/M)2 X/Q DEC DECAYED AND UNDEPLETED, HALF-LIFE 2.26 DAYS (SECIM')3 X/O DEC+DEP DECAYED AND DEPLETED, HALF-LIFE 8 DAYS (SEC/M-)4 DEPOSITION RELATIVE DEPOSITION RATE (1/MT)

3-25

FIGURE 3-1

2011 ANNUAL WIND ROSE 10M LEVEL - PRIMARY TOWER

Run Date: 2/9/2012 09:30a47

WIND ROSE

(WINDS FROM)N

0.00% PERCENT CALMS(NOT INCLUDED IN PLOT)

StartDate: 1/1/2011 00:00

End Date: 12/31/2011 23:00

-Sensors Selected1 0..SPD1 0-WD 4

16%

- LegendA WIND SPEED LESS THAN 3.5 MPH

WIND SPEED LESS THAN 7.5 MPHn WIND SPEED LESS THAN 12.5 MPH= WIND SPEED GREATER THAN 12.5 MPH

This wind rose displays the frequency of hourly average wind direction from a given sector. In 2011, thepredominant wind direction occurred 15.8 % of the time from the ENE sector. The average wind speedwas 4.8 mph and the average wind speed for the predominant sector (ENE) was 2.8 mph. The sector withthe highest average wind speed was NW (8.7 mph).

3-26

FIGURE 3-2

2011 ANNUAL WIND ROSE 60M LEVEL - PRIMARY TOWER

Run Date: 2/9/2012 09:31:58

WIND ROSE

(WINDS FROM)N

0.01% PERCENT CALMS(NOT INCLUDED IN PLOT)

Start Date: 1/1/2011 00:00

End Date: 12/31/2011 23:00

-Sensors Selected60_SPD60_WD

[LegendA WIND SPEED LESS THAN 3.5 MPH, WIND SPEED LESS THAN 7.5MPHo WIND SPEED LESS THAN 12.5 MPH= WIND SPEED GREATER THAN 12.5 MPH

This wind rose displays the frequency of hourly average wind direction from a given sector. In 2011, thepredominant wind direction occurred 14.8 % of the time from the NNE sector. The average wind speed was 7.5mph and the average wind speed for the predominant sector (NNE) was 5.9 mph. The sector with the highestaverage wind speed was WSW (10.8 mph.).

3-27

FIGURE 3-3

PASQUIL STABILITY CLASS PREVALENCES DATAPeriod: 2011

Joint Frequency Distributions at 10 MetersWind Speed and Direction 10M vs. Delta Temperature 60-IOM

(Based on 8,593 Valid Hours)

G6"4• 'c

A B C

73/8 1 %F .

E'r, I30/

5 D513/c

3-28

SECTION 4

DOSE MEASUREMENTS AND ASSESSMENTS

4-1

Radioloqical Impact on Man

Sampling and analysis of airborne and waterborne effluents were performed inaccordance 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 effluentsamples analyzed. Dose calculations using measured and calculated effluentactivity levels, meteorological data from the current reporting period and averageriver flow dilution factors resulted in estimated doses to individuals at levels below10 CFR 20 and 10 CFR 50, Appendix I limits. Direct radiation resulting from plantoperation (reported in the 2011 Annual Radiological Environmental OperatingReport) contributed a maximum of 6.68E-1 mrem (measured at TLD Location 9S2and based on an occupancy time by a member of the public of 20 hours perquarter) at the Protected Area Boundary south of the plant. Based on airborneeffluent sample data, the maximum organ (including thyroid)/total body dose is4.52E-1 mrem (CHILD, LUNG Table 4-4). The maximum organ/total body dosefrom all liquid effluent is 6.OOE-3 mrem (TEEN, LIVER Table 4-2). Conservativelyadding the maximum organ/total body dose from liquid and gaseous effluent andthe maximum total body dose determined from direct radiation results in a dose of1.13 mrem, which is 4.5% of the 40CFR190 limit of 25 mrem to total body/organ(except thyroid) and 1.5% of the 40CFR1 90 limit of 75 mrem to the thyroid.

Doses to a maximally exposed member of the public from waterborne effluents arecalculated for fish ingestion and shoreline exposure at the plant outfall, and drinkingwater ingestion at Danville, PA. Site specific parameters used in the calculationsfor the Danville receiver, specific for actual average blowdown and river level for theentire year are shown in Table 4-1.

TABLE 4-1

SITE-SPECIFIC PARAMETERS USED FOR RETDAS CALCULATIONS(DANVILLE RECEIVER)

FOR 2011

PARAMETER ENTIRE YEAR

Cooling Tower Blowdown (CFS) 25.4

Average Net River Level (ft.) 9.0

Dilution Factor at Danville(1) 1071.8

Transit time to Danville (hr.)(1 ) 14.7

(')From ODCM-QA-005, Att. E

4-2

Summaries of maximum individual doses resulting from airborne and waterborneradioactive effluent releases from each unit are given in Table 4-2. Meteorologicaldata from Section 3 were used to calculate the dose from airborne effluents.

The Radioactive Effluent Release Report includes an assessment of the radiationdose from radioactive effluents to members of the public within the site boundary.Within the Site Boundary there are several areas frequented by members of thepublic. There are no significant exposure pathways from waterborne effluents inthese areas. Doses from airborne effluent are calculated for members of the publicfor the following locations: Riverlands Energy Information Center, the Towers Club,and residence with the maximum X/Q value; the garden, dairy and meat producingfarm with the maximum D/Q value; and the site boundary with the maximum X/Qvalue. Summaries of the calculated maximum doses within the site boundary andselected locations beyond the site boundary resulting from airborne effluents arepresented 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 EnergyInformation Center, three pathways of radiation exposure can be identified: plume,ground, and inhalation. There are no significant exposure pathways fromwaterborne effluents in this area. There are approximately 100,000 visitors to theRiverlands/Energy Information Center complex each year. For dose calculations, itis assumed the visitor stays in the area for one hour. The calculated dose rate andcollective dose for visitors to the Riverlands/Energy Information Center during 2011are shown on Table 4-3.

Use of the RETDAS code yields calculated doses for the Riverlands area for thereport period. These doses assume an occupancy factor of 100% for a member ofthe public during 2011. These calculated dose values are shown on Table 4-4.

In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and ReportingRadioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRChas recommended that U.S. nuclear power plants evaluate whether Carbon-14 (C-14) is a "principal radionuclide", and if so, report the amount of C-14 released.Radioactive effluent releases of C-14 have not increased but the decline in releasesof other radionuclides has resulted in C-14 possibly becoming more prominent,specifically in airborne effluents. This regulatory guidance has led to an industryinitiative to evaluate and report C-14 in the Annual Radioactive Effluent ReleaseReport.

Information for C-14 dose impact is included as supplemental information in thisreport. Reportable values for dose impact do not include C-14 contribution. C-14,with a half-life of 5730 years, is a naturally occurring isotope of carbon produced bycosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950sand 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is

4-3

also produced in commercial nuclear reactors, but the amounts produced are muchless than those produced naturally or from weapons testing. 0In December 2010 the Electric Power Research Institute (EPRI) published Report1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents",which provides conservative technical guidance to support the calculation of C-14released in radioactive effluents. The calculation of C-14 discharged from theSusquehanna station and resultant offsite dose during 2011 is based upon themethodology outlined in the referenced EPRI report. In a BWR the majority of C-14is generated in the reactor core by neutron activation of reactor coolant, specifically170(n,a) 14C. Thus C-14 generation is directly proportional to reactor power. Asdocumented in the EPRI report, approximately 99% of the C-14 produced in thereactor core is discharged as gaseous effluent (primarily as C02) through the offgassystem and released from the Turbine Building vents. The remaining 1 % isreleased in the form of solid radwaste. There is minimal (<1%) C-14 released in theliquid effluent pathway. Based on the EPRI methodology, approximately 23 Curiesof C-14 were released in gaseous effluents in 2011.

The airborne effluent pathway with the highest offsite dose potential (for C-14releases) is the vegetation ingestion pathway. The maximum expected annualdose from C-14 released from Susquehanna Unit-1 (1.83E-1 mrem) and Unit-2(1.55E-1 mrem) has been calculated based on methodology in Regulatory Guide1.109 and includes site specific parameters (e.g., nearest garden with highest X/Qvalue, producing both broad leaf and non-broad leaf vegetation). The maximumorgan dose from airborne effluent C-14 released from the Susquehanna station in2011 is well below the 1 0CFR50, Appendix I, ALARA design objective (i.e., 15mrem/yr per unit). The annual dose to the maximally exposed individual from allgaseous releases of C-14 (calculated by the above referenced methodology) is3.38E-1 mrem to the critical organ (bone) and 6.74E-2 mrem to the total body.

Conservatively adding the maximum dose (calculated based on liquid and gaseouseffluent sample results combined with direct radiation results) referenced on page4-2 to the maximum dose due to the calculated release of C-14 (3.38E-1 mrem,CHILD, BONE) bounds the dose that any member of the public receives fromstation operations to 1.47 mrem, which is 6% of the 40CFR190 limit of 25 mrem tototal body/organ (except thyroid) and 2% of the 40CFR190 limit of 75 mrem to thethyroid.

4-4

TABLE 4-2

SUMMARY OF MAXIMUM INDIVIDUAL DOSESTO MEMBERS OF THE PUBLIC (4)DATA PERIOD: 1/1/11 TO 12/31/11

ESTIMATEDMAXIMUM LIMIT

AGE APPLICABLE DOSE PERCENT (MREM/

UNIT EFFLUENT GROUP ORGAN (MREM/MRAD) LOCATION OF LIMIT MRAD)(2)

DIST AFFECTED(MILES) SECTOR

1 Liquid(l Teen Total Body 2.12E-03 (3) 0.07 3

1 Liquid~l) Teen Liver 3.OOE-03 (3) 0.03 101 Noble Gas N/A Air Dose 0 0.5 WSW 0 10

(Gamma-MRAD)

1 Noble Gas N/A Air Dose 0 0.5 WSW 0 20(Beta-MRAD)

1 Airborne Child Liver 2.73E-01 0.5 WSW 1.8 15Iodine,Tritium andParticulates

Liuid_ . Teen Total Body 2.12E-03 (3) 0.07 3

Liquid"l Teen Liver 3.OOE-03 (3) 0.03 102 Noble Gas N/A Air Dose 0 0.5 WSW 0 10

(Gamma-MRAD)

2 Noble Gas N/A Air Dose 0 0.5 WSW 0 20(Beta-MRAD)

2 Airborne Child Lung 1.79E-01 0.5 WSW 1.2 15Iodine,Tritium andParticulates

(')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 siteoutfall and from the drinking water pathway at Danville, PA.

0 Dose due to calculated release of C-14 not included.

4-5

TABLE 4-3

CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THERIVERLANDS/ENERGY INFORMATION CENTER COMPLEX

DATA PERIOD: 1/1/11 TO 12/31/11

COLLECTIVEAPPLICABLE DOSE RATE(1 ) DOSE(2 "

EFFLUENT AGE GROUP ORGAN (MREM/HR) (PERSON-REM)

Noble Gas N/A Total Body 0 0

Noble Gas N/A Skin 0 0

Iodine, Tritium and Child GI-LLI 4.93E-06 4.93E-04Particulates (3) 1 1 1

(')Estimated dose and dose rate is based on annual site total activity release.

(2)Collective dose is based on 100,000 person-hours.

(3) Dose due to calculated release of C-14 not included. ITABLE 4-4

SUMMARY OF MAXIMUM INDIVIDUAL DOSES FROM AIRBORNE EFFLUENT

MAXIMUM MAXIMUM MAXIMUMTOTAL BODY ORGAN THYROID

DOSE DOSE DOSELOCATION PATHWAY (MREM) (MREM) (MREM)

1. Maximum site boundary X/QTotal (All) 1.24E-01 (CHILD) 1.24E-01 (CHILD, LUNG) 1.23E-01 (CHILD)

2. Maximum X/Q ResidenceMaximum D/Q Garden Total (All) 1.05E-01 (CHILD) 1.05E-01 (CHILD, LUNG) 1.05E-01 (CHILD)

3. Maximum D/Q Dairy +Maximum D/Q Meat Total (All) 7.1 OE-02 (CHILD) 7.11E-02 (CHILD, LUNG) 7.1 OE-02 (CHILD)

4. Tower's ClubTotal (All) 4.52E-01 (CHILD) 4.52E-01 (CHILD, LUNG) 4.51 E-01 (CHILD)

5. Riverdand/EiC5._______________ ITotal (All) 1 4.31 E-02 (CHILD) 4.32E-02 (CHILD, GI-LLI) 4.30E-02 (CHILD)

Note: The doses shown above are based on 100% occupancy at the indicated locations. They arebased on a composite of all pathways resulting in a total dose to the maximally exposed individualdue to airborne effluents from both Unit-1 and Unit-2 operations. Dose due to calculated release ofC-14 not included. A

4-6

Erill *IItl• A .4ruI.GU 4-1

AIRBORNE-DOSE CALCULATION LOCATIONS

0------------------

# 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-003, Effluent Monitor Setpoints, was revised in 2011. Revision 7was issued on March 24, 2011. The revision incorporated setpoint guidance to supportthe current airborne effluent SPING (System Particulate, Iodine and Noble Gas) unitsas well as the VERMS (Vent Effluent Radiation Monitoring System) units.

ODCM-QA-008, Radiological Environmental Monitoring Program, was revised in 2011.Revision 14 was issued October 21, 2011. The revision: a) added a new groundwatersampling location; b) deleted three dairy farm locations which were no longer inoperation and c) updated a note to clarify that some dairy farms may not participate inthe REMP milk sampling program but are still listed in the ODCM since the exposurepathway exists.

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 arecontained in Section 3.11: liquid and gaseous effluent dose limits, liquid and gaseouseffluent treatment system operability criteria (based on effluent dose), liquid andgaseous effluent treatment system operability criteria and the conduct of theRadiological Environmental Monitoring Program. Section 3.6.1 contains requirementsfor venting or purging of primary containment.

There were no changes to TRM Sections 3.6.1 or 3.11 during 2011.

5-3

PROCESS CONTROL PROGRAM CHANGES

The following changes were made to the Process Control Program and implementingprocedures during 2011. None of the changes reduce the overall conformance of thesolidified waste product to existing criteria for solid wastes. All changes were reviewedand approved (as necessary) by the Plant Operations Review Committee (PORC) asdocumented on the attached summary of procedure changes. The followingprocedures were changed:

1. WM-RP-107, Transfer and Dewater A (B) RWCU Phase Separator

2. WM-RP-1 13, Transfer and Dewatering of Waste Mix Tanks

3. WM-RP-106, Transfer and Dewatering Bead Resin

4. MT-EO-051, Fuel Pool Cleanout - Operation of EnergySolutions ShieldedTransfer Bell and Verification of No Free-Standing Water in FEXMHigh Integrity Container

5. CH-TP-055, Solid Radwaste 10CFR61 Correlation Factor Determination -

Sample Collection and Preparation

6. WM-RP-104, Gross Dewatering

7. WM-RP-1 12, Dewatering to Waste Disposal Criteria

8. ME-ORF-1 72, Fuel Pool Cleanout - EnergySolutions Operating Guidelines forUse of Polyethlyene High Integrity Containers

NDAP-QA-0646 continues to fully implement the requirements and intent of thefollowing:

1. Sections 11.4 and 13.5 of the FSAR2. Section 3.7.4 of the Technical Requirements Manual3. 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 metas the result of these changes to the program. These changes to the Process ControlProgram will not reduce the overall conformance of the solidified waste product toexisting criteria for solid wastes.

5-4

PROCEDURE REVISION SUMMARYWM-RP-107, TRANSFER AND DEWATER A (B) RWCU PHASE SEPARATOR

1. Change in Step 7.5.4.a to incorporate change in vendors procedure.

PROCEDURE REVISION SUMMARYWM-RP- 113, TRANSFER AND DEWA TERING OF WASTE MIX TANKS


PROCEDURE REVISION SUMMARY

WM-RP-106, TRANSFER AND DEWA TERING BEAD RESIN


PROCEDURE REVISION SUMMARYMT-EO-051, FUEL POOL CLEANOUT-OPERA TION OF ENERGYSOLUTIONS

SHIELDED TRANSFER BELL AND VERIFICATION OF NO FREE STANDING WATERIN FEXM HIGH INTERGRITY CONTAINER

1. Changes reflect revisions made to EnergySolutions FP-OP-023, Rev. 9.

2. Made various administrative changes.

3. Added CAUTION before Step 8.2.1

4. Added checkboxes at Notes and Cautions

PROCEDURE REVISION SUMMARYCH-TP-055, SOLID RADWASTE 10CFR61 CORRELATION FACTOR DETERMINATION

- SAMPLE COLLECTION AND PREPARATION

1. Deleted PCAF 2007-1223 (Admin change). Reincorporated pertinent changes

as below.

2. Change procedure format, owner and adherence level.

3. Minor typographical changes

4. Deleted specific waste type information and Reference NDAP-QA-0646 forinformation.

5. Changed volume to Grams on FORM CH-TP-055-1, and updated Waste Streaminformation.

5-5

6. Added clarification about performing isotopic analyses based on deadtimecriteria in Section 7.1. Updated sample frequency and quantity requirements inSection 7.1

7. Updated requirement for saving remaining original composite until vendor resultsare evaluated.

8. Move multiple notes to above the step they expand and made others proceduresteps as appropriate.

9. Add Radwaste Health Physicist to Recommended Reviews

10. Adjust sampling frequency from 9 months to 1 year per Health Physicist-Radwaste and added provision for Health Physicist-Radwaste to be able tochange frequency.

11. Added step in records section allowing the continued use of previous revisions of

the FORM that are in use.

12. Update references.

PROCEDURE REVISION SUMMARYWM-RP-104, GROSS DEWA TERING

1. Added note to clarify how to proceed following completion of Step 6.4.4. 0PROCEDURE REVISION SUMMARY

WM-RP -112, DEWA TERING TO WASTE DISPOSAL CRITERIA

1. Added note to clarify how to proceed following completion of Step 6.6.8.

PROCEDURE REVISION SUMMARYME-ORF -172, FUEL POOL CLEANOUT- ENERGYSOLUTIONS OPERATING

GUIDELINES FOR USE OF POLYETHYLENE HIGH INTEGRITY CONTAINERS

1. Revise vendor name throughout procedure.

2. Revisions in accordance with EnergySolutions FO-AD-002, Revision 35changes.

3. Add checkboxes to Notes and Cautions.

5-6

SECTION 6

MISCELLANEOUS TECHNICAL REQUIREMENTS MANUAL (TRM),FSAR, 40CFR 190 AND NEI GROUNDWATER PROTECTION INITIATIVE

REPORTING

6-1

1. TRM Action 3.11.1.4.F.2 requires the reporting of Liquid Radwaste EffluentMonitoring Instrumentation inoperability not corrected in a timely manner.

The liquid radwaste discharge radiation monitor was declared inoperableat 0815 on 1/13/11 (requiring entry into TRO 3.11.1.4 Condition B) due toa leak in the detector canister assembly. Replacement parts wereordered to repair the leaking canister. The replacement parts were notavailable onsite until 1/26/11. TRO 3.11.1.4 Condition F was entered at0815 on 1/27/11 due to exceeding the 14 day return to servicerequirement of TRO 3.11.1.4 Condition B. The liquid radwaste dischargeradiation monitor detector canister leak was repaired and the monitor wasdeclared operable at 1227 on 1/27/11.

The liquid radwaste discharge radiation monitor was declared inoperableat 0543 on 10/15/11 (requiring entry into TRO 3.11.1.4 Condition B) dueto a problem with circuit boards related to detector response. Multipleattempts were made to repair/replace the failed circuit boards. TRO3.11.1.4 Condition F was entered at 0543 on 10/29/11 due to exceedingthe 14 day return to service requirement of TRO 3.11.1.4 Condition B.The liquid radwaste discharge radiation monitor circuit board problem wascorrected and the monitor was declared operable at 1411 on 11/5/11.

2. TRM Action 3.11.1.5.C.1 requires the reporting of Radioactive Liquid ProcessEffluent Monitoring Instrumentation inoperability not corrected in a timelymanner.

None to report for 2011.

3. TRM Action 3.11.2.6.K requires an explanation for Radioactive GaseousEffluent Monitoring Instrumentation required actions and completion times notmet.


4. TRM Action 3.11.4.1 .F.2 requires reporting the cause of the unavailability ofmilk or fresh leafy vegetable samples and identify the new locations forobtaining replacements.


5. TRM Action 3.11.4.2.A requires reporting when land use census identifies anew location which yields a calculated dose or dose commitment greater thanthe values currently being calculated in Requirement 3.11.2.3 (GaseousEffluent Dose due to Iodine, Tritium, and Radionuclides in Particulate Form).


6-2

6. TRM Action 3.11.4.2.B requires reporting when land use census identifieslocations that yield a calculated dose or dose commitment (via the sameexposure pathway) 20 percent greater than at a location from which samplesare currently being obtained in accordance with Requirement 3.11.4.1(Radiological Environmental Monitoring Program).


7. The limits outlined in 40CFR190.10 (Environmental Standards for theUranium Fuel Cycle-Standards for Normal Operations) were not exceeded bystation operations during 2011. Refer to Section 2 and Section 4 for specificvalues.

8. FSAR Section 11.6.11 requires the reporting of airborne radioactivitydetected in the Low Level Radwaste Holding Facility.

Only naturally occurring airborne radioactivity was detected aboveanalysis MDC's in air samples from the Low Level Radwaste HoldingFacility during 2011.

9. The PPL Susquehanna station has implemented an Action Plan in responseto the NEI Initiative on Groundwater Protection. Part of the Action Planincludes the assessment of the current groundwater monitoring program.Groundwater is sampled and analyzed quarterly as part of the RadiologicalEnvironmental Monitoring Program (REMP). REMP groundwater samplinglocations are defined in ODCM-QA-008 Attachment G. In August 2006,additional groundwater sampling was initiated at locations which are not listedin the ODCM. The additional locations are three manholes which collectwater from a perimeter drain system. The perimeter drain system consists ofperforated piping installed just above the footing along the exterior base ofthe vertical walls of the reactor, turbine and radwaste buildings. Outlined inTable 6-1 are the tritium analysis results from sampling of the perimeter drainsystem. No nuclear by-product gamma emitting radionuclides were identifiedabove analysis MDC's for the perimeter drain samples in 2011. The tritiumresults reported in Table 6-1 did not exceed any Reporting Level thresholdsin the PPL Susquehanna Technical Requirements Manual or any reportingcriteria established in response to the NEI Groundwater Protection Initiative.Figure 6-1 is a trend graph of airborne and waterborne effluent tritiumreleases from the PPL Susquehanna Station starting in 1982.

6-3

TABLE 6-1

NEI Ground Water Protection Initiative Relortincl

Perimeter Drain Sampling Results: 2011

Manhole FD-1 Manhole FD-2 Manhole FD-3

(16S3- NW corner (9S3 - I/S RCA @ U2(7S9 - E of U2 CST) of RW Bldg.) HP Cont. Pt. Closet)

Date Tritium (pCi/liter) Tritium (pCi/liter) Tritium (pCi/liter)

2t7/2011 223 318 417

5/16/2011 215 237 195

8/16/2011 152 261 210

11/14/2011 153 216 234

6-4

Figure 6-1

SSES Tritium Effluent Releases(Airborne, Waterborne & Total Curies Released)

"o250

2000E 150

100

0

N c mt wo C 0 N4 "t (0 CO 0 N 4t C0 w 0SCO CO COO) 0) 0 0)0 0 0 0 0 0'-

1 -" •-- *- • 1- - 1- • - - C04J C0 4 C '4 C0 4 C 4 C

Year - Airborne H-3--• Waterborne H-3

-- Total Curies

6-5

SECTION 7

CORRECTIONS TO PREVIOUSRADIOACTIVE EFFLUENT RELEASE REPORTS

7-1

CORRECTIONS TO PREVIOUSRADIOACTIVE EFFLUENT RELEASE REPORTS

No corrections to previous Radioactive Effluent Release Reports are submitted for thisreport period.

7-2

SECTION 8

EFFLUENT FROM SYSTEMS CLASSIFIED ASINSIGNIFICANT EFFLUENT PA THWA YS

8-1

EFFLUENT FROM SYSTEMS CLASSIFIED ASINSIGNIFICANT EFFLUENT PATHWAYS

Insignificant Effluent Pathways are: 1) evaporation from the Unit 1 and Unit 2Condensate Storage Tanks (CST's); 2) evaporation from the common Refueling WaterStorage Tank (RWST); 3) gaseous effluent from the Hydrogen Seal Oil, Main Turbineand RFPT lubrication oil mist eliminators which vent to the turbine building roofs.

These pathways are not continuously monitored. The CSTs and RWST are sampledmonthly to determine the concentration of radionuclides present in these tanks. Tritiumanalysis on these samples is performed quarterly. Airborne release to the environmentfrom the tanks is estimated based on conservative estimates of the evaporation ratesfrom each of the tanks using a modified method established within Chapter 7 ofEPA AP-42. A conservative carry-over fraction of radionuclides from the water to theevaporated liquid is then assumed. Airborne release to the environment from thedemisters conservatively assumes the maximum moisture (condensate) concentrationof the lubrication oil as measured via sampling during 2011. The calculation alsoassumes immediate removal of 100% of the water by the oil mist eliminators as itpasses through the turbines.

The annual release of tritium, iodines and particulates with half-lives greater than 8days was calculated based on the conservative assumptions outlined above. Thecalculated releases are shown in Table 8-1. All nuclides, except for tritium, releasedfrom insignificant effluent pathways are negligible compared to the airborne releasedata shown in Tables 2-1 and 2-2. The maximum dose to the public from a release of4.50 Ci of tritium is calculated to be 4.34E-2 mrem (child). This is a small fraction of themaximum dose from airborne effluent reported in Section 4.

8-2

TABLE 8-1

ANNUAL RELEASE FROM SYSTEMS CLASSIFIED ASINSIGNIFICANT EFFLUENT PATHWAYS

U1-CST and U2-CST andMain Turbine/RFPT Main Turbine/RFPT

Nuclide RWST Lube Oil Systems Lube Oil Systems Total(ci) (ci) (ci) (ci)

H-3 4.66E-02 2.25E+00 2.20E+00 4.50E+00

Mn-54 6.74E-09 2.58E-06 2.80E-07 2.86E-06

Co-60 4.06E-08 7.21E-06 8.96E-07 8.14E-06

Co-58 6.17E-09 5.28E-06 7.38E-07 6.02E-06

Zn-65 1.54E-09 9.67E-07 1.49E-07 1.12E-06

8-3

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