Revision as of 20:19, 5 April 2019

Text

Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1992. W/930301 Ltr
	ML18017A266
Person / Time
Site:	Susquehanna
Issue date:	12/31/1992
From:	KEISER H W; PENNSYLVANIA POWER & LIGHT CO.
To:	MARTIN T T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	PLAS-3930, NUDOCS 9303090559
	Download: ML18017A266 (287)
	v • d • e

ACCEI ERAT DOCUMENT DISTR UTION SYSTEM REGULAT INFORMATION DISTRIBUTIO STEM (RIDS)DOCKET FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 0500()387 50-388 Susquehanna Steam Electric Station, Unit 2, Penns'ylva 05000388 AUTH.NAME AUTHOR AFFILIATION

""'KEISER,H.W.

Pennsylvania Power&Light Co.P RECIP.'NAME RECIPIENT AFFILIATION R I

SUBJECT:

"SemiAnnual luent&Waste Disposal, Rept.for July-'ec 1992." 930301 tr.DISTRIBUTION CODE: ZE48D COPIES RECEIVED:LTR J ENCL L SIZE: TITLE: 50.36a(a)(2)

Semiannual Effluent Release Reports NOTES: D S RECIPIENT ID CODE/NAME PD1-2 LA CLARK,R INTERNAL: L Ol RGN1 FILE 02 EXTERNAL: BNL TICHLER,J03 NRC PDR COPIES LTTR ENCL 3 3 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-2 PD NRR/DRSS/PRPB11 RGN1 DRSS/RPB EG&G SIMPSON,F COPIES LTTR ENCL-1 1 2 2 2 2 2 2 A D D D D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl D TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16 fr~/

Pennsylvania Power 8 Light Company Two North Ninth.Street~Allentown, PA 18101-1179

~215/774-5151 Harold W.Keiser Senior Vice President-Nuclear 015/7744194 MAR 01 j993 Mr.Thomas T.Martin Regional Administrator, Region I U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT PLA-3930 FILE R41-2A Docket No.50-387 and 50-388

Dear Mr.Martin:

In accordance with 10CFR50.36a(a)(2) and the Susquehanna SES Unit 1 and 2 Technical Specifications, attached is the Semi-Annual Radioactive Effluent Release Report for SSES Units 1 and-2 covering the period July 1 through December 31, 1992.Very truly yours, H.W.Keiser Attachment CC: NRC Document Control Desk (original)

NRC Region I Mr.G.S.Barber-NRC Resident Inspector Mr.R.J.Clark-NRR Project Manager 08005'303090559 92l231 PDR ADQCK 05000387 R PDR SEMIANN.UAL EFFLUENT 8 VfASTE DISPOSAL REPORT FOR JULY-DECEMBER 1S92 Pennsylvania Power&Light Company Two North Ninth Street Allentown, Pennsylvania 18101-1179 February 1993

~I pi SUSQUEHANNA STEAM ELECTRIC STATION SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT REPORT PERIOD: 07/01/92-12/31/92 Prepared by: ar son Health Physicist R..Bare ay Health Physicist Reviewed by:.San Supervisor

-Environmental Services-Nuclear Approved by: I4(4 I oty Supervisor

-Operations Te nology Pennsylvania Power 5 Light Company Two North Ninth Street Allentown, Pennsylvania 18101

TABLE OF CONTENTS SECTION PAGE 1.Introduction and Supplemental Information

.~~~1 2.Effluent and Waste Disposal Data..........

13 3.Heteorological Data and Dispersion Estimates....35 4.Dose Heasurements and Assessments

..........56 5.Changes to the Offsite Dose Calculation Hanual and the Solid Waste Process Control Program 68 6.Reports of Exception to the SSES Effluent......

165 Honitoring Program LIST OF TABLES PAGE Table 1: Technical Specification Limits............

10 Table 2: Airborne Effluents-Summation of All Releases.....15 Table 3: Airborne Effluents..................16 Table 4: Waterborne Effluents-Summation of All Releases....18 Table 5: Waterborne Effluents.................19 Table 6: Semiannual Effluent and Waste Disposal Report.....24 Solid Waste and Irradiated Fuel Shipments Table 7: Table 8: Solid Radioactive Waste-Class A.......Principal Radionuclides and Percent Composition Condensate Demineralizer/Radwaste Demineralizer-Carbon Steel Liner (Dewatered)

Solid Radioactive Waste-Class A.Principal Radionuclides and Percent Composition Condensate Demineralizer/Radwaste Demineralizer-HIC (Dewatered)

.25 26 Table 9.Solid Radioactive Waste-Class A...........27 Principal Radionuclides and Percent Composition Ultrasonic Resin Cleaning Waste-HIC (Dewatered)

Table 10: Solid Radioactive Waste-Class A...........28 Principal Radionuclides and Percent Composition Liquid Radwaste Filter Media-HIC (Dewatered)

Table 11: Solid Radioactive Waste-Class A............29 Principal Radionuclides and Percent Composition Sump Sludge-Carbon Steel Liner (Portland Cement)Table 12: Solid Radioactive Waste-Class A...........30 Principal Radionuclides and Percent Composition Processed DAW-Strong Tight Container Table 13: Solid Radioactive Waste-Class A...........31 Principal Radionuclides and Percent Composition Non-Processed DAW-Strong Tight Container Table 14: Solid Radioactive Waste-Class C...........32 Principal Radionuclides and Percent Composition RWCU Filter Media-HIC (Dewatered)

L'JL LIST OF TABLES (cont.)PAGE Table 15: Estimated Total Errors Associated with........33 Effluent Measurements Table 16: Data Not Reported in Previous.............34 Semiannual Report Table 17: Meteorological Data Availability

...........37 I Table 18: Joint Wind Frequency Distribution by.Stabil ity Class 41 Table 19: Average Annual Relative Concentrations

........51 Table 20: Summary of Maximum Individual Offsite.........58 Doses and Dose Commitments to Members of the Public Table 21: Calculated Collective Doses to Members........60 of the Public Within the L Riverl ands/Information Center Complex Table 22: Calculated Doses for Residences.

...........62 Within the SSES Site Boundary (NNE and ESE sectors)Table 23: Calculated Doses for the Residences.

.........63 Within the SSES Site Boundary (SE and WSW sectors)Table 24: Calculated Doses for Residences.

...........64 Within the SSES Site Boundary (W and WNW sectors),Table 25: Calculated Doses for Residences.

.......;-...65 Within the SSES Site Boundary (NNW sector) 4 Ql LIST OF FIGURES Figure 1: SSES Airborne Effluent Release Points....Figure 2: SSES Waterborne Effluent Release Pathway.Figure 3: Susquehanna River Honthly Average Flow Rates.Figure 4: Honthly Liquid Radwaste Discharge Totals.Figure 5: SSES Wind Rose: 10-meter Sensors.Figure 6: SSES Wind Rose: 60-meter Sensors.Figure 7: SSES Pasquill Stability Class Prevalences

..PAGE~~~~5~~~~6~~~~20 21~i~~38 39 40 Figure 8: Areas Within the SSES Site Boundary Open.to Hembers of the Public 61 1

SECTION I INTRODUCTION AND SUPPLEMENTAL INFORMATION I,I hl 4;"$l INTRODUCTION The Susquehanna Steam Electric Station (SSES)is located in Salem Township, Luzerne County, Pennsylvania.

It is on the west bank of the Susquehanna River, 8 km northeast of Berwick.The Station consists of two boiling water reactor generating units, each with 1,050 HW 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 100X power for the first time on February 4, 1983.Commercial operation of Unit 1 was declared on June 8, 1983.Initial criticality of Unit 2 occurred on May 8, 1984.Unit 2 was declared commercial on February 12, 1985.Airborne effluents are released from the Susquehanna Station via five rooftop vents on the reactor building (see Figure 1).Each vent is continuously monitored, and a program of periodic sampling and analysis is conducted as specified in the plant Technical Specifications.

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 2).Blowdown line flow rates are at least 5,000 gpm during periods of liquid radwaste release.The diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed.The diffuser serves to rapidly and uniformly mix the station discharge with the main flow of the river.This report presents a summary of the quantities of radioactive materials which were released from the Susquehanna Steam Electric Station during the period from July 1, 1992 to December 31, 1992.In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to PPSL's Offsite Dose Calculation Manual (ODCM)and Solid Waste Process Control Program (PCP)and documentation of any exceptions to the SSES effluent monitoring program which must be reported per Technical.

Specifications 3.3.7.10 and 3.3.7.11.Airborne and waterborne radioactive effluent releases to the environment during the report period were sampled and analyzed in accordance with the requirements of the Technical Specifications.

All radioactive effluent releases were within the concentration and release limits specified in the Radiological Effluent Technical Specifications (RETS).Calculations and terms utilized in this report are those outlined in the SSES Offsite Dose Calculation Manual (ODCM).

h F.f~>t e Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant.Included are regulatory limits (Table 1), sampling and analysis methods, and characterization of the number and duration of batch and abnormal releases, if any.Section 2 contains effluent and waste disposal data for the report period.Table 2 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 3 presents the totals of specific radionuclides in airborne effluents.

Waterborne effluents are summarized in Table 4.Average diluted concentrations are presented and compared to the applicable limits.Table 5 presents the release quantities of specific radionuclides in waterborne effluents over the report period.Figure 3 lists the Susquehanna River monthly flow rates for 1992 while Figure 4 presents the monthly discharge totals of liquid radwaste from SSES during 1992.Tables 6 through 14 present a characterization of the solid radioactive waste shipped off site during the report period.Included are the volumes and curie contents associated with each type of solid waste.An estimate of major nuclide composition is presented for each waste type, as well as the number of waste shipments from the site, how they were transported, and'their final destination.

Table 15 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.Table 16 presents effluent data from previous report periods which was not available at preparation time for the associated semiannual report.I Section 3 of this report contains the meteorological data associated with the year 1992.Availability data for the SSES meteorological data are shown in Table 17.Meteorological data for the calendar year is presented in the form of joint wind frequency distributions by atmospheric stability class.These distributions are presented in Table 18.Figures 5 and 6 are wind rose plots for the SSES primary meteorological 10-meter and 60-meter sensors, respectively.

Figure 7 presents the relative prevalences of the Pasquill stability classes.In addition, the meteorological data from the report year were used to generate annual average relative concentrations (X/gs)and deposition rates (D/gs).These values are presented in Table 19, and are required input for use of the GASPAR code for calculation of the doses resulting from airborne releases.

Xq E QS e C J Section 4 of this report contains an assessment of the calculated doses attributed to the reported radiological effluents for the calendar year.The LADTAP II code was used for calculation of doses from waterborne effluents.

The GASPAR code was 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 20 summarizes maximum calculated doses and dose commitments to members of the public from waterborne and airborne effluents and direct radiation.

Table 21 presents calculated collective doses to members of the public within the Riverlands/Information Center Complex.Tables 22 through 25 summarize the calculated doses for residences and other occupied areas within the SSES site boundary.Section 4 also contains an effluent tabulation and dose assessment for an abnormal gaseous release which occurred on ll/12/92.Section 5 of this report is reserved for documentation of changes to the Offsite Dose Calculation manual and the Solid 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 Specification Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.

Ci!p'g LWIT I ht AC I OH~UILDWG EXHAUST VSHT IT II HSACTOh~Ull DIHG SXHAUST VSHT ISS,SSh CSQ AT W t-I Wt IShlSOCTM AT gA IIO T SL.STS'4"~~%~'~~y OUTSIDE Alh WTAXE Hf ACTOh hUILDIIIG S XIIAUQT STACKS DIRStL EXIIAUST titian OIESCL ORHKHATOh SIHLDINO WSI ON'~t 305 QN Ct M AT IIXP/le T UHI I I IUHSIIIL OUI L D I II lr EXHAUST VTIIT 6 UIII I I I IUHXIlel~UIL 0 IIIIr SXHAUST Vlhl I%IXI CSM llO IXXI Cl M AT llO S A'I l~I~&0~5 rIT C C q TTT CONTHOL hUILDWG f L~N'I" r e-+f.)o+>a-+a a-Q Rl'4"--~HAOhIAST a aUI LD~WO TUHSIHE NJILOIHG l~UHIT I SL STSO-UHIT II

$V~W~8 t

~~0~~~Rm~yawp~J I C 4~

SUPPLEMENTAL IHFORNATION 1.Re ulator Limits Technical Specifications 3/4.11.1 and 3/4.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively.

Concentration of radioactive material liquid effluents and dose or dose commitment resultant thereof are limited in unrestricted areas.Dose and dose rate due to radioactive materials released in gaseous effluents are limited in areas at or beyond the site boundary.Technical Specification limits are listed in Table 1.2.Maximum Permissible Concentrations in Waterborne Effluents The concentrations of radioactive materials in waterborne effluents are limited to the concentrations specified in 10 CFR Part 20 Appendix B Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentrations are limited to the following values, as stated in the applicable Technical Specification:

Nuclide 85'Kr"Kr Kr"Ar 133oX 133X 135mX 135X PC uCi ml 2.0E-04 5.0E-04 4.0E-05 9.0E-05 7.0E-05 5.0E-04 6.0E-04 2.0E-04 2.0E-04 3.era e Ener Based on gaseous effluent releases for the report period average beta energy is 0.146 HeV and average gamma energy is 0.030 NeV.4.e surements and A ro imat ons of Total Rad oactivit Analyses of specific radionuclides in effluent samples are used to evaluate the radioactive composition and concentration of r effluents.

Tk 1 s4 8 ft4 L 5.Methods of uantif in Effluents a~b.C.d.Fission and Activation Gases: Gas samples are routinely collected monthly and analyzed with a high resolution (Ge[Li]or HPGE)detector system which incorporates a data reduction program to determine radionuclide composition in terms of specific activity.Data tapes from the continuous vent monitors are used to determine the average concentration of noble gases.The high resolution (Ge[Li]or 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 samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).Iodines: Iodine is continuously collected via an isokinetic sampling assembly in each vent.Filters are normally exchanged once per week and analyzed on a high resolution (Ge[Li]or HPGE)system.The daily average flow rates for the vents and sample pumps are averaged for the duration of the sampling period, and a ratio of vent flow rate to sample flow rate is determined.

The ratio is used to determine the total activity of each isotope released during the time period in question.When the continuous monitors are out of service, iodine is continuously collected on charcoal cartridges attached to air samplers which draw directly from the affected rooftop vent(s)or from alternate sampling ports available on the sample lines.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 (Ge[Li]or HPGE)system.Flow rate corrections are performed as for iodines.When the continuous vent monitors are out of service, particulates are continuously sampled directly from the affected rooftop vent(s)or from alternate sampling ports available on the sample lines.Tritium: Airborne tritium is collected montly via bubbler sampler.The sample is collected for one hour at a flow rate of approximately 1000 cc/min.Tritium activity in the bubbler sample is determined by liquid scintillation counting.The liquid sample tritium concentration is converted to air concentration by volume proportion,, then compared to the Technical Specification Table 4.11.2.1.2-1 Lower Limit of Detection (1 E-6 uCi/cc).

/g 3[4 g.C 1 1 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 (GeI'Li]or HPGE)system and release permits are generated based on the values obtained from the isotopic analysis and the most recent values for tritium, gross alpha, iron-55, and strontium-89 and-90.An aliquot based on release volume is saved and added to monthly and quarterly composite containers.

The monthly tritium analysis is done in-house.The quarterly composite is sent to a vendor laboratory for iron-55, strontium-89 and-90, and gross alpha analyses.The concentration of each radionuclide in each batch is decay corrected from the time of counting to the midpoint of the release period, and is then multiplied by the volume of the batch to determine the total quantity of each nuclide released in each batch.The isotopic totals for each are summed to determine the total source term for the report period.

TABLE 1 1.T N S CIF CATION H TS A.~AB: 1.<500 mrem-TOTAL BODY<3000 mrem-SKIN annual site total"instantaneous" limits (Tech Spec.3.11.2.1}2.g 5 mrad-AIR GAMMA g 10 mrad-AIR BETA-qu'arterly air dose limits per reactor unit (Tech Spec.3.11.2.2)3.g 10 mrad-AIR GAMMA g 20 mrad-AIR BETA-annual air dose limits per reactor unit (Tech Spec.3.11.2.2)B.C.RN-3 TR T M PART CU AT W TH HA F-V S>8 OAYS: 1.g 1500 mrem-ORGAN (inhalation pathways only)annual site total"instantaneous" limits (Tech Spec.3.11.2.1)2.~7.5 mrem-ORGAN-quarterly dose limits per reactor unit (Tech Spec.3.11.2.3)3.g 15 mrem-ORGAN-annual dose limits per reactor unit (Tech Spec.3.11.2.3)~FF UEATE: 1.Concentration g 10CFR20 Appendix B, Table II, Column 2-site total"instantaneous" limits (Tech Spec.3.11.1.1}10

<<~'L>1 QT C>

2.g 1.5 mrem-TOTAL BODY g 5 mrem-ORGAN-quarterly dose limits per reactor unit (Tech Spec.3.11.1.2)3.<3 mrem-TOTAL BODY g 10 mrem-ORGAN-annual dose limits per reactor unit (Tech.Spec.3.11.1.2)A RN FUN: AS FOR P T N CA SP CAT ON H OF APP Fission and Activation Gases A derived release rate limit based on the Technical Specification limit of 500 mrem/yr was calculated from the expected mix of noble gas radionuclides presented in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564).The limit is 8.51E+05 uCi/min (1.42E+04 uCi/sec).Iodine-131 A derived release rate limit based on the Technical Specification limit of 1500 mrem/yr from I-131, tritium and particulates with half-lives greater than 8 days was calculated from the annual release quantity of I-131 provided in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564).

The limit is 1.41E+02 uCi/min (2.35E~OO uCi/sec).Particulates A derived release rate limit based on the Technical Specification limit of 1500 mrem/yr from I-131, tritium and particulates with half-lives greater than 8 days was calculated based on the expected mix of particulate radionuclides presented in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564).

The limit is 7.72E+02 uCi/min (1.29E+01 uCi/sec).Tritium A derived release rate was calculated based on the 10 CFR 20 Appendix B, Table II, Column 1, Haximum Permissible Concentration for tritium (2.0E-07 uCi/cc)to unr~stricted areas.A relative concentration of 4.1E-05 sec/m was assumed.The limit is 2.93E>05 uCi/min (4.88003 uCi/sec).11 F.MAT R RN FFLUENT: BAS S FOR P RC NT OF APP CAB HN A P ICAT Fission and Activation Products Dose calculations are performed on quarte'rly activity totals from waterborne effluents using the LADTAP II dose program.The calculated doses are then compared to Technical Specification 3.11.1.2 quarterly dose limits for liquid effluents (TOTAL BODY LIHIT: 1.5 mrem per reactor unit, ORGAN LIHIT: 5 mrem per reactor unit).Tritium Liquid effluent quarterly tritium concentrations are compared to the 10 CFR 20 Appendix B, Table II, Column 2, Haximum Permissible Concentration limit of 3.0E-03 uCi/ml to unrestricted areas.Dissolved and Entrained Gases Liquid effluent quarterly concentration totals for dissolved and entrained gases are compared to the most restrictive Haximum Permissible Concentration for a noble gas 4.0E-05 uCi/ml (Kr-87)from the SSES Technical Specification Table 3.11.1.1-1.12 SECTION 2 EFFLUENT AND WASTE DISPOSAL DATA 13 ye EP~r$0 A rborne Effluents Summaries of the radionuclide total curie activities, average release rates are included in Tables 2 and 3.Third Fourth guarter~rter 1.2.3.4.5.Number of Batch Releases: Total Time Period for Hatch Release: Maximum Time Period for a Batch Release: Average Time Period for-a Batch Release: Minimum Time Period for a Batch Release: Abnormal Releases 0 NA NA NA NA 0 NA NA NA NA 1.Number of Releases 0 1*2.Total Activity Released NA 5.00E-03*Details of this release discussed in Section 4, Dose Measurements and Assessments.

If a radionuclide was not detected, zero activity was used for that isotope in dose calculations.

A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD)as specified in the SSES Technical Specification Table 4.11.2.1.2-1, Radioactive Gaseous Waste Sampling and Analysis Program.In all cases, these LLDs were less than the levels required by Technical Specifications.

The following are typical LLDs.Radionuclide Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 LLD uCi cc 4.6 E-08 5.3 E-08 5.4 E-08 1.3 E-07 1.5 E-08 1.2 E-07 2.9 E-14 2.8 E-14 1.8 E-14 3.8 E-14 4.4 E-14 3.3 E-13 2.4 E-14 2.1 E-14 1.5 E-14 7.0 E-14 I-131 I-133 4.4 E-14 2.8 E-13 Sr-89 Sr-90 H-3 Gross Alpha 2.0 E-15 3.0 E-16 2.6 E-08 5.0 E-16 14 4 I 4 0 0 TABLE 2 SENIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1992)AIRBORNE EFFLUENTS-SUMMATION OF ALL RELEASES A.Fission and Activation Gases Unit Third Quarter Fourth auarter Total Release Average Release Rate for Period Percent of Technical Specification Limit 8.Iodines CI uCI/sec 1.25E+01 1.57E+00 1.11E-02 4.22E+00 5.31E-01 3.74E.03 Total 1-131 Average Release Rate for Period Percent of Technical Specification Limit C.Particulates CI uCI/sec 8.75E-06 1~10E-06 4.68E-OS 8.14E-06 1'2E-06 4.36E-05 Particulates arith Half-Lives

>8 Da s Average Release Rate for Period Percent of Technical Specification Limit Gross Alpha Radioactivity D.Tritiun Ci uCi/sec Ci 1.01E-03 1.28E-04 9.88E-04 1.55E-06 1.03E-030 1.29E.04 1.00E-03 1.40E-06'otal Release Average Release Rate for Period Percent of Technical Specification Limit Ci uCI/sec 2.25E+01 2.83E+00 5.80E-02 8.88E+00 1~12E+00 2.29E-02 Sr-89, Sr-90 and Gross Alpha values are estimated based on third quarter 1992 san@le analyses and fourth quarter 1992 ventilation exhaust rates.15

~~

TABLE 3 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1992)AIRBORNE EFFLUENTS Nucl ides Released A.Fission and Activation Gases Unit Continuous Node Continuous Node Third Quarter Fourth Quarter Ar-41 Kr-85m Kr-88 XQ-133 Total for Period B.iodines Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 1.25E+01 1.25E+01 O.OOE+00 O.OOE+00 O.OOE+00 4.22E+00 4.22E+00 1-131 i-133 1-135 Total for Period C.Particulates Ci Ci Ci Ci 8.75E.06 O.OOE+00 O.OOE+00 8.75E.06 8.14E.06 O.OOE+00 O.OOE+00 8.14E-06 Cr-51 Hn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Cs-134 Cs-137 C@.141 Ce-144 Total for Period Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 6.24E-04 6.44E-OS 9.27E.05 1.69E-04 6.35E.05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.01E.03 O.OOE+00 6.96E-04 1.48E 04 3.50E-05 1.50E-04 O.OOE+00 O.OOE+00*O.OOE+00i O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.03E.03**Reported values are estimated based on third quarter 1992 sea@le analyses and fourth quarter 1992 ventilation exhaust rates.16 P~"-4~r ,j i~'I Waterborne Effluents Summaries of the radionuclide total curie activities, average diluted concentrations, and percent of applicable Technical Specification limits are included in Tables 4 and 5.Third Fourth Batch Releases*guarter guarter 1.2.3.4, 5.6.Number of Batch Releases: Total Time Period for Batch Releases: Haximum Time Period for a Batch Release: Average Time Period for a Batch Release: Hinimum Time Period for a Batch Release: Average Stream Flow During Period of Release of Effluent into a Flowing Stream:*Units of time and flow are expressed in minutes and gallons per minute (gpm), respectively.

1.17E+02 1.54E+04 2.83E+02 1.32E+02 2.20E+01 8.60E+01 9.11E+03 2.70E+02 1.06E+02 2.00E+01>7.37E+03->7.37E+03 (Cooling Tower Blowdown Flow Rate)3.73E+06 7.95E+06 (Susquehanna River Flow Rate)l.2.3.Abnormal Releases Number of Releases: Volume Released: Total Activity Released: 0 NA NA 0 NA'A If a radionuclide was not detected, zero activity was used for that isotope in dose calculations.

A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD)as specified in the SSES Technical Specification Table 4.11.1, 1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.In all cases, these LLDs were less than the levels required by Technical Specifications.

The following are typical LLDs.Radionuclide LLD uC'l Hn-54 Fe-59 Co-58 Co-60 Zn-65 Ho-99 I'-131 Cs-134 Cs-137 Ce-141 Ce-144 Sr-89 Sr-90 Fe-55 H-3 Gross Alpha 4.5 E-08 5.0 E-08 2.4 E-08 5.4 E-08 4.9 E-08 1.7 E-07 2.0 E-08 2.2 E-08 2.6 E-08 3.2 E-08 1.3 E-07 4.0 E-08 4.0 E-09 1.0 E-06 4.6 E-06 3.0 E-08 17 t lW~4'Vv TABLE 4 SENIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1992)WATERBORNE EFFLUENTS-SUPINATION OF ALL RELEASES AD Fission and Activation Products Unit Third Quarter Fourth Quarter 1.Total Release (Hot Including Tritiua, Gases, Al a)2.Average Diluted Concentration During Period 3.Percent of Applicable Limit Ci uCI/ml 2.21E-02 4.97E-08 4.36E-03 2.05E-03>>8.39E-09 8.73E-04 8.Tri t iua Total Release 2.Average Diluted Concentration During Period 3.Percent of Applicable Limit C.Dissolved and Entrained Gases Ci uCi/ml 2.42E+01 5.46E-05 1.82E+00 1.13E+Ol 4.63E-05 1.54E+00'I.Total Release 2.Average Diluted Concentration During Period 3.Percent of Applicable Limit D.Gross Alpha Radioactivity Ci uCi/ml 4'9E-04 9.22E-10 2.31E-03 1.32E-04 5.42E-10 1.35E-03 1.Total Release O.DOE+00 O.DOE+00 E.Volune of Maste Released (Prior to Dilution)Gal lons Liters 1.18E+06 4.47E+06 6.90E+05 2.61E+06 F.Volune of Dilution Mater Used During Period of Release t G.Voluae of Dilution Mater Used Over Entire Period Gallons Liters Gallons Liters 1.16E+08 4.39E+08 9.76E+08 3.70Ei09 6.38E+07 2.41E+08 9.25E+08 3.50E+09>>Reported values are estimated based on third quarter 1992 sample analyses and fourth quarter 1992 discharge volumes.18

~W\w\~kd'(k~t<<S TABLE 5 SEHINDRIAL EFFLIKNT ND UASTE DISPOSAL REPIXIT (1992)I MATERBORNE EFFLlKNTS Hucl ides Released Uni t Batch Hode Third Quarter Batch Hode Fourth Quarter A.Fission and Activation Products F-18 Ci 9.33E-OB O.OOE+00 Ha-24 Ci O.DOE+00 O.DOE+00 Cr-51 Hn-54 Fe-55 Fe-59 Co-58 Co-60 Zn-65 As-76 Sr-89 Sr-90 Ho-99 Tc-99m Ag-110m 1.131 Cs-134 Cs-137 Ce-141 M-187 Total for Period B.Tritium H-3 Total for Period C.Dissolved and Entrained Gases Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Xe-133m Xe-133 Xe-135m Xe-135 Total for Period Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.08E-02 5.86E-03 O.DOE+00 1.22E.03 2.17E-04 3'9E.03 5.41E-04 1.28E-04 O.OOE+00 O.DOE+00 6.66E-05 O.OOE+00 1.28E-05 O.DOE+00 O.OOE+00 1.39E-06 O.OOE+00 1.60E-OS 2.21E-02 2.42E+01 2.42E+01 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 2.16E-04 0~OOE+00 1.93E 04 4.09E-04 4.85E-05 9.10E-04 O.DOE+00*8.11E.05 2.05E-05 8.94E-04 9.23E-05 O.DOE+00 O.DOE+00*O.OOE+00*O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 2.23E-06 O.DOE+00 O.OOE+00 2.05E-03*1~13E+01 1.13E+01 O.OOE+00 O.OOE+00 O.DOE+00 1.06E-08 O.DOE+00 O.DOE+00 7.56E-05 O.DOE+00 5.66E-05 1.32E-04*Reported values are estimated based on third quarter 1992 seapte analyses and fourth quarter 1992 discharge volunes.19 FIGURE 3 SUSQUEHANNA RIVER MONTHLY AVERAGE FLOW RATES DATA PERIOD: 1992 14 GALLONS PER MINUTE x 1E6 12--10..x x~~~r~'x~~~x I~~.~x, ,~~x-x;;~~."x<<~x~, x x x.,~.'.x.<.<X~'x.:x.<X:<,<x'x".',x,~"~.x,'x': x.x.<"'x 0 J F M A M J J A S 0 N D 1992 20

FIGURE 4 SSES MONTHLY LIQUID RADWASTE DISCHARGE TOTALS DATA PERIOD: 1992 Gallons X 1000 600, 500.~~x~~r w~,~~~x~~~i;~,'~X a~~~.~r~i,~~~r',~,~,S 400=-300 200 100:: 0 J F M A M J J A S 0 N D 1992 SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT SEMI-ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT SOLID RADIOACTIVE WASTE DATA PERIOD: Jul 1 1992-December 31 1992 PREPARED BY: C P.LEWIS-HEALTH YSICIST APPROVED BY: D.L.HAGAN-EFFL TS MANAGEMENT SUPV 22

@a-RE ORT NOTES l.All activities reported in millicuries (mCi)unless otherwise noted.2.Reported activities, as indicated with the (<)sign, are comprised in whole or part, of NDL,Values.

3.No Class B Waste was disposed during this report period.4.No waste disposed of in the following Waste Streams during this report period: Condensate Demineralize/Radwaste Demineralizer Solidified using Portland Cement Evaporator Concentrates Solidified using Portland Cement Absorbed Oil Liquid Oily Waste (Petroleum Based Haterial)Liquid Radwaste Filter Hedia Solidified using Portland Cement Cartridge Filters 5.Processed DAW is that which, has been volume-reduced by means of compaction, supercompaction, incineration or other means prior to disposal.Non-processed DAW is that which has been disposed of without benefit of volume reduction (usually metals).23 TABLE 6 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Data Period: July 1, 1992-December 31, 1992 A.*SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Number of Shi ments Mode of Trans ortation Destinatio 20 Truck Barnwell, SC B.IRRADIATED FUEL SHIPMENTS Number of Shi ments Mode of Trans ortation Destinatio NONE NOT APPLICABLE NOT APPLICABLE

,*The number of shipments listed in A include only the shipments from SSES to a disposal site.It does not include shipments made to or from volume reduction vendors.24 1 A" I 1 f l~

TABLE 7 CLASS A SOURCE OF WASTE: TYPE OF CONTAINER:

CONDENSATE DEMZNERALZZER/

RADWASTE DEMINERALIZER CARBON STEEL LINER METHOD OF PROCESS: ISOTOPES Ag-110m Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 I-13 1 Mn-54 Ni-63 PQ-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)CONTAINER VOLUME DEWATERED'CTIVITY.+

mCi)0~OOOE+00 1.300E-03'.595E+00 O.OOOE+00 9.000E-04 3.365E+01 2.113E+02 O.OOOE+00 O.OOOE+00 0~OOOE+00 2.901E+02 5.392E+00 2.772E+01 (1.324E-01 O.OOOE+00 2.068E+02 3.426E+00 3.500E-03 2.100E-03 2.000E-04 O.OOOE+00 O.OOOE+00 O.OOOE+00 4 1.087E-01 1.857E+02 0'71 197.500 ft3 OF TOTAL 0.00%0 F 00%0.68%o.oo%o.oo%3.47%21.76%o.oo%o.oo%0.00%29.88%0.56%2.85%0.01%o.oo%21.30%0.35%'.oo%o.oo%o.oo%o.oo%o.oo%o.oo%0 F 01%19.12%100.00%5.593 m3 25 TABLE 8 SOURCE OF WASTE: TYPE OF CONTAINER:

METHOD OF PROCESS: ISOTOPES DEWATERED ACTIVITY (mCi)CLASS A CONDENSATE DEMINERALIZER/

RADWASTE DEMINERALIZER HIC OF TOTAL Ag-llom Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 I-131 Mn-54 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 Xe-131m Nb-95 TOTAL AC CONTAINE TIVITY (Ci)R VOLUME 3.220E+00 5.637E-02 2.383E+02 0.000E+00 4.454E-02 1.694E+03 8.373E+03 3.629E+02 4.391E+00 1.405E+Ol 1.114E+04 3.539E+02 1.917E+02 1.403E+00 1.772E+00 6.319E+03 1.237E+02 1.461E-01 8.792E-02 0.000E+00 5.043E+00 0.000E+00 2.928E-01 1.107E+00 1.177E+03 3.093E-02 1.754E+00 30.004 2137.200 ft3 0.01 0.00 0.79 0.00 0.00 5.65 27.91 4 1 21 0.01 0.05 37.13 1.18 0.64 0.00 0 F 01 21.06 0~41 0.00 4 0.00 0.00 0.02 0.00 0.00 0.00 3.92 o.oo 4 0.01.100.00 60.520 m3 26 i Ak II TABLE 9 CLASS A SOURCE OF WASTE: TYPE OF CONTAINER:

METHOD OF PROCESS: ISOTOPES DEWATERED ACTIVITY (mCi)OF TOTAL ULTRASONIC RESIN CLEANING WASTE HIC Ag-aaom Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 I-131 Mn-54 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 Ce-144 TOTAL ACT CONTAINER IVITY (Ci}VOLUME 8.655E+01 1.181E-01 1.964E+02 8.816E-03 4.870E-03 7.185E+02 2.897E+04 1.169E+03 O.OOOE+00 7.139E+01 2.434E+05 3.326E+03 3.520E+01<5.813E-01 O.OOOE+00 4.023E+04 3.764E+02 1.750E-02 4.682E-02 3.722E+01 5.987E+01 0~OOOE+00 4.349E-01<9.476E-01'

'44E+03 1.350E+02 322.29?188.900 ft3 0.03%0.00%0.06%0.00%0.00%0.22%8.99%0.36%0.00%0~02+o 75.51%1.03%'.01+0.004 0.00~12.48%0.12%0.004 0.004 0.01<0.02%0.00%0.00%0.004 1.13%o.04.x 100.00K 5.349 m3 27 "l b P W Yi r SOURCE OF HASTE: TYPE OF CONTAINER:

METHOD OF PROCESS: ISOTOPES DEWATERED ACTIVITY (mCi)o OF TOTAL TABLE 10 CLASS A'QUID RAD'HASTE FILTER MEDIA HIC IVITY (Ci)VOLUME Ag-110m Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55'e-59 H-3 I-129 I-131 Mn-54 Ni-63 PQ-238 PQ-239 PQ-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 Hf=181 Nb-9 5 TOTAL ACT CONTAINER 3.592 E+0 1 9.842E-03 2.768E+00 8.343E-03 6.370E-03 5.440E+03 2.195E+04 2.350E+04 O.OOOE+00 O.OOOE+00 2.130E+05 1.622E+04 3.446E+01 (1.821E-01 O.OOOE+00 9.501E+04 5.580E+02 O.OOOE+00 O.OOOE+00 O.OOOE+00 3.229E+02 O.OOOE+00 O.OOOE+00 1.263E-01 8'02E+03 1.271E+02 9.308E+01 385.186 357.800 Ct:3 0.01'o 0.00'o 0.00~o 0.00%0.00%1.41%5.70o 6.10%0.00'o 0.00~o 55.33'-o 4.21'o 0.01'o 0.00'o 0.00'o 24.68': 0.14'o 0.00~o 0.00%0.00o 0.08 o 0.00%0.00o 0.00+o 2.31%0.03X 0.02K l.OO.OOX 10.132 m3 28 TABLE ll CLASS A SOURCE OF WASTE: SUMP SLUDGE TYPE OF CONTAINER:

CARBON STEEL'INER METHOD OF PROCESS: ISOTOPES SOLIDIFICATION-PORTLAND CEMENT ACTIVITY.+mCi)

%OF TOTAL Ag-110m Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 I-131 Mn-54 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)CONTAINER VOLUME O.OOOE+00 O.OOOE+00 5.292E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 2.731E+03 O.OOOE+00 1.484E+01 3.378E+01 2.163E+04 O.OOOE+00 8.397E+00 (6.473E-02 O.OOOE+00.1.066E+03 7.675E+01 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 7.143E-01 4.511E-02 C 4.803E-02 1.007E+02 25.668 177.900 ft3 0 F 00%0 F 00%0.02%0.00%0 F 00%0.00%10.64%0.00%0.06%0.13%84.27%0.00%'.03%0.00%0.00%4'5%0.30%0.00%0.00%0.00%0.00%0.00%0 F 00%0.00%0.39%100.00%5.038 m3 29 SOURCE OF WASTE: TYPE OF CONTAINER:

TABLE 12 CLASS A PROCESSED DAW STRONG TIGHT CONTAINER METHOD OF PROCESS: ISOTOPES Ag-110m Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 I-131 Mn-54 Ni-63 Pu-238 Pu-239 Pu-241 Sb-3.24 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)CONTAINER VOLUME N/A ACTIVITY..+mCi) 0~OOOE+00 7.700E-03 1.676E-01 1.490E-02 4.200E-03 2.040E+01 6.027E+02 1.435E+01 O.OOOE+00 O.OOOE+00 5.681E+03 1.295E+02 1.797E-01 7'05E-01 O.OOOE+00 1.154E+03 1.949E+01 2.490E-02 5.200E-03 1.500E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 6.636E-01 5.087E+Ol 7.676 1517.300 ft3 OF TOTAL 0.004 0.004 0.004 0.004 0.00t 0.27%7.85%0.19%0.00%0.00%74.014 1.694'.004 0.01%0.004 15.044 0.25%0.004 0.004'.024'.004 0.004'.004 0.014'.664 100.004 42.966 m3 30' TABLE 13 CLASS A SOURCE OF WASTE: TYPE OF CONTAINER:

METHOD OF PROCESS: ISOTOPES Ag-llom Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 I-131 Mn-54 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)CONTAINER VOLUME NON-PROCESSED DAW STRONG TIGHT CONTAINER N/A ACTIVITY.+mCi)

O.OOOE+00 7.697E-05 5'65E-03 2.789E-05 3'57E-05 6.786E+01 5.420E+02 6.968E+02 O.OOOE+00 O.OOOE+00 5.402E+03 1.058E+02 2.202E-02 (5'13E-04 O.OOOE+00 7.982E+02 1.323E+01 2'81E-05 2 754E-05 2'31E-02 O.OOOE+00 7.897E+00 O.OOOE+00 5.641E-04 9.967E+01 7.734 210.000 f03 OF TOTAL O.OO%0.00%O.OO%0.00%.O.OO%0'8%7.01%9.01%0.00%0 F 00%69.85%1~37%0.00%0 F 00%0.00%10'2%0.17%O.OO%0.00%0 F 00%0 F 00%0.10%0.00%0.00%1.29%100.00%5.947 m3 31 TABLE 14 CLASS C SOURCE OF WASTE: RWCU FILTER MEDIA TYPE OF CONTAINER:

HIC Ag-110m Am-241 C-14 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 I-131 Mn-54 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL AC CONTAIN TIVITY (Ci)ER VOLUME METHOD OF PROCESS: ISOTOPES DEWAT ERED.ACTIVITY (mCi)O.OOOE+00 2.203E-01 3.868E+00 2.578E-02 2.960E-02 5.563E+04 5.564E+05 1.416E+05 O.OOOE+00 O.OOOE+00 5.&05E+05 6.766K+04 1.254E+01 3.454E+00 O.OOOE+00 8.886E+05 2.434E+01 1 485E-01 5.942E-02 1.300E+03 O.OOOE+00 O.OOOE+00 7.583E+00 6.564E+01 3.&34E+05 2675.300 220.200 ft3 OF TOTAL 0.00%0.004 0.004 0.004 0.004 2.084 20.804 5.294 0.004 0.00%21.70%2.53%0.004 0.00%0.004 33.22%0.004'.004 0.004 0.05%0~004 0.004 0.004 0.004 14.334 100.004'.235 m3 32

TABLE 15 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT ESTIMATED TOTAL ERRORS ASSOCIATED WITH EFFLUENT MEASUREMENTS Data Period: July 1, 1992-December 31, 1992 Measurement Estimated Total Error l.Airborne Effluents a 0 b.C.d.Fission and Activation Gases 1-131 Particulates Tri tium 15.9X 13.3X 15.8X 13.6X 2.Waterborne Effluents'a~b.C.d.e.f.Fission and Activation Products Tritium Dissolved and Entrained Gases Gross Alpha Activity Volume of Waste Released (Prior to Dilution)Volume of Dilution Water Used During Period 5.0X 3.3X 8.4X 6.0X 5.0X 15;OX 3.Solid Wastes a~Condensate Demineralizer/

Radwaste Demineralizer 15.1X (Dewatered

-Carbon Steel Liner)b.Condensate Demineralizer/

15.1X c~d.e.f.g.h.Radwaste Demineralizer (Dewatered

-HIC)Liquid Radwaste Filter Media (Dewatered

-HIC)RWCU Filter Media (Dewatered

-HI C)Ultrasonic Resin Cleaning Waste (Dewatered

-HIC)Sump Sludge Solidified with Portland Cement Processed DAW (Strong Tight Container)

Non-Processed DAW (Strong Tight Container) 15.1X 15.1X 15.1X 15.1X 25.0X 25.0X 33

$\I: g4 TABLE 16 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT DATA NOT REPORTED IN PREVIOUS SEMIANNUAL REPORT NUCLIDE CATEGORY UNIT SECOND QUARTER 1992 A.Airborne E f fl uents 1.Sr-89 2.Sr-90 3.Gross Alpha Ci Ci Ci O.OOE+00 0.00E+00 2.24E-07 B.Waterborne Effluents 1.Sr-89 2.Sr-90 3.Gross Al ha Ci Ci Ci 0.00E+00 0.00E+00 O.OOE+00 34 SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 35 R.IC METEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the Susquehanna SES 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 10-meter and 60-meter 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.Oew 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 10-meter tower providing alternate measurements of wind speed, wind direction, and sigma theta.SSES meteorological data is transmitted to the plant control room, Technical Support Center, and Emergency Operations Facility for emergency response availability.

The data is also transmitted via telephone line data-link to the PPLL corporate computer in Allentown.

On the corporate computer, the data is available for preparation of summary reports, wind rose plots, and dispersion estimates.

Dispersion modeling for effluents from normal operation of SSES is done using XOQDOQ, a straight-line air flow Gaussian plume model designed to estimate average relative concentrations.

The model was developed in accordance with Regulatory Guide 1.111.Calm periods are distributed as the first non-zero wind-speed class in the input joint frequency distribution file.XOQDOQ uses terrain correction factors to account for the temporal and spatial variations in the airflow in the region, since a straight-line trajectory model assumes that a constant mean wind transports and diffuses effluents in the direction of air flow at the release point within the entire region of interest.The SSES terrain correction factors were determined by the ratio of the results of the straight-line model to the puff-advection model, and are incorporated into Table 19.36 I l4 TABLE 17 SENIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT METEOROLOGICAL DATA AVAILABILITY Data Period: 1992~PARACLETE PERCENT OF VALID HOURS DURING PERIOD 1.Wind speed a.All Sensors Combined b.10-Meter Sensors c.60-Meter Sensor 99.8X 99.8X 99.8X 2.Wind direction a..All Sensors Combined b.10-Heter Sensors c.60-Heter Sensor 99.8X 99.8X 99.8X 3.Indicator of Atmospheric Stability (Primary Tower)a.Temperature Differential

('A'ensor) b.Temperature Differential

('B'ensor) c.Sigma Theta 8 10 Heters 96.3X 97.7X 99.8X 4.Percent of hours for which valid 10-meter wind speed, 10-meter wind direction, and temperature differential were available.

5.Percent of hours for which valid 60-meter wind speed, 60-meter wind direction, and temperature differential were available.

97.7X 97.8X 37 FIGURE 5 N GALH O.O 0 0 0 ANNUAL b770 ObQ~RRm3 WIND DIRECTION FREQUENCY (PERCENT)Z2Z3 MEAN W INO SPEED (Mj'SEC)SUsquehanna Steam Electr ic St.iO-meter level 38 FIGURE 6 CALM O.Q a s 0 ss~g,6 ANNUAL d77 t ObQ~~@5 WINO 0 I RECT ION FREQUENCY (PERCENT)!Z2~MEAN W INO SPEEO (M/SEC)Staaquehanna Steam Electr ic St.60-meter level 39 0 II F$i t Figure 7 SES PASQUILL STABILITY CLASS PREVALENCES Data Period: 1992 Based on Joint Frequency Distributions at 10 Meters (8686 Hourly Values)Neutral 3216 37.46%~Slightly Unstable 325 3.79%Very Stable 682 7.94%Slightly Stable 1770 20.61%Moderately Stable 823 9.59%Moderately Unstable 329 3.83%Very Unstable 1441 16.78%40 PENNSYLVANIA POMER IL LIGHT COKPAHY (PPCL)-Susquehsnns Stean Electric Ststion PROGRAK: JFD VERSIOHI PC-1.1 Prisiry Toiler Dots-10-ester level SITE IDENTIFIERt DATA PERIOD EXAKINEDY 1/1/92-12/31/92 sea ANNUAL*tt STABILITY BASED MIND KEASINED MIND TKRESHOLD'OINT FREOIENCY SPEED (K/S)Ol: DELTA T BETMEEN 60.0 AT: 10.0 KETERS AT:.23 K/S DISTRIBUTION OF MIND SPEED AND STABILITY CLASS A ANO 10.0 KETERS DIRECTION IH HOURS AT 10.00 KETERS SE SSE S SSM H NHE NE ENE E ESE SM MSM M MHM HM NNM TOTAL CALK.24-1.50 1.51-3.00 3.01-5.00 5.01-7.50 7.51-10.00

>10.00 14 17 25 24 30 43 56 53 29 21 30 25 10 2 6 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 26 22 2 0 0 0 22 22 22 41 36 58 16 8 17 0 0 1 0 0 0 0 0 0 17 67 16 0 0 0 15 9 1 3 0 144 51 19 12 24 99 84 30 30 38 3 17 4 0 4 0 4 0, 0 0 0 0 1 0 0 1 3 250 26 702 38 451 2 32 0 4 0 1 TOTAL M 98 M 55 57 50 79 66 98 100 261 165 55 45 66 69 1441 STABILITY BASED II IND KEASURED MIND THRESHOLD JOINT FRE(NENCY SPEED (K/S)OHI DELTA T BETMEEN 60.0 AT: 10.0 KETERS AT:.23 K/S DISTRIBUTION OF MIND SPEED AHD STABILITY CLASS 8 AHD 10.0 KETERS DIRECTION IH HOURS AT 10.00 KETERS N NNE NE EHE E ESE SE SSE S SSM SM MSM M MHM HM NNM TOTAL CALK.24.1.50 1.51-3.00 3.01-5.00 5.01-7.50'7.51-10.00

>10.00 5 4 12 9 11 5 12 12 8 7 3 9 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 13 0 0 0 0 6 4 3 10 14 7 4 2 6 0 0 0 0 0 0 0 0 0 6 1 1 0 17 12 9 14 7 14 10 3 5 4 6 4 2 0 1 0 2 0 0 0 0 0 0 1 0 0 0 77 8 161 7 74 1 14 0 2 0 1 TOTAL 13 25 28 17 18 19 20 20 16 15 40 34 15 21 12 16 329 0

PENNSYLVANIA POMER 8 LIGHT COMPANY (PPAL)-Susquehsma Steam Electric Station PROGRAM t JFD VERS IOH: PC-1.1 Primary Touer Data-10-meter level SITE IDENTIFIER:

DATA PERIOD EXAKINEDt 1/1/92-12/31/92 ANNUAL STABILITY BASED II)NO MEASURED llIMD THRESHOLD JOINT FREOUENCY SPEED (K/S)ON: DELTA'I BETlKEN 60.0 AT: '10.0 METERS AT:.23 ll/S DISTRIBUTION OF lllMD SPEED AND STABILITY CLASS C ANO 10.0 METERS DIRECTION IN MRJRS AT 10.00 METERS N NHE NE ENE E ESE SE SSE S SS'W Il MMM MM NMN TOTAL CALM~24 1.50 1.51-3.00 3.01-5.00 5.01.7.50 7.51 10.00%10.00 2 7 17 8 8 13 10 15 6 6 8 4 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9 3 6 18 4 11 3 1 4 0 0 0 0 0 0 0 0 0 8 19 1 0 0 0 3 0 17 8 21 8 4 10 0 0 0 0 0 0 0 3 11 2 7 0 3 3 0 1 0 0 0 0 0 0 0 0 78 6 155 5 73 1'19 0 0 0 0 TOTAL 23 21 40 14 14 13 30 8 21 28 45 26 13 11 6 12 325 STABILITY BASED OH: DELTA T BETMEEH 60.0 MIND MEASURED AT: 10.0 KETERS llIHD THRESHOLD AT:.23 K/S.JOINT FREOUENCY DISTRIBUTION OF llIMD SPEED AMD SPEED (K/S)H HHE ME EHE E STABILITY CLASS D AND 10.0 METERS DIRECTION IH HOURS AT 10.00 METERS ESE SE SSE S SSll Ql MSll ll MNM Mll NHll TOTAL CALM.24-1.50 1.51-3.00 3.01.5.00 5.01-7.50 7.51-10.00

%10.00 40 86 117 100 81 104 148 136 43 41 71 38 31 16 23 5 1 14 3 3 0 0 0 0 0 0 0 0 0 0 72 33 22 0 0 0 67 6'7 84 62 58 74 21 16 17 3 3 4 0 0 0 0 0 0 76 104 22 1 0 0 56 12 12 6 2 123 89 65 61 54 83 61 59 73 124 22 55 36 15 23 1 9 5 0 0 0 2 0 0 0 1 11 889 91 1286 140 817 18 206 0 15 0 2 TOTAL 220 273 298 162-148 127 153 144 179 203 285 228 177 155 203 260 3216 O C)

PENNSYLVANIA POuER 8 LIGHT COMPANY (PPCL)-Susquehanna Steam Electric Station PROGRAM: JFD VERSIOHT PC-1.1 Primary Teer Data-10-meter level SITE IDENTIFIER:

DATA PERIOD EXAHIHEDY 1/1/92-12/31/92 ANNUAL STABILITY BASED V I ND HEASURED HIND THRESHOLD JOINT FREOUENCY SPEED (H/S)OH: DELTA T BETHEEH 60.0 AT 10.0 METERS AT:.23 H/S DISTRIBUTION OF HIND SPEED AND STABILITY CLASS E AND 10.0 HE IERS DIRECTION IH HOURS AT 10.00 METERS N NNE NE ENE E EsE sE ssE s ssu su usu u uMu Mu HMu TDTAL CALH~24-1.50 1.51-3.00 3.01-5~00 5.01-7.50 7.51-10.00

>10.00 136 221 39 26 2'5 1 6 0 4 0 0 25 94, 154 20 45 6 4 1 4 0 0 2 0 0 0 0 0 0 107 2 2 0 0 0 90 74 104 11 23 77 0 2 5 0 2 4 0 0 0 0 0 0 96 110 3 0 0 0 45 21 6 6 7 59 14 6 4 12 18 15 1 2 2 0 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 1192 28 482 7 73 1 19 0 4 0 0 TOTAL 49 140 178 262 166 111 101 101 190 209 122 53 13 12 21 42 1770 STABILITY BASED HIND IIEASURED HIND THRESHOLD JOINT FREOUENCY SPEED (H/S)OH: DELTA T BETHEEN 60.0 AT: 10.0 METERS AT:.23 H/S.DISTRIBUTIOH OF uIHD SPEED AND STABILITY CLASS F AMD 10.0 METERS DIRECTION IH HOURS AT 10.00 HETERS N HME ME EHE E EsE sE ssE s ssu su usu u uMH Hu HNH T0TAL CALH.24-1.50 1.51-3.00 3.01-5.00 5.01-7.50 7.51-10.00

%10.00 7 19 102 4 8 13 0 0 0 0 0 0 0 0 0 0 0 0 286 140 46 1 0 0 0 0 0 0 0 0 52 0 0 0 0 0 24 30 27 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 24 4 0 0 0 0 8 3 0 0 2 8 3 0 1 2 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 726 3 96 0 41 0 0 0 0 0 0 TOTAL 11 27 115 332 141 52 25 31 28 28 16 6 1 I 4 5 823 r E'I'rh h PEHHSTLVANIA POMER 8 LIGHT COHPANZ (PPSL)-Susquehanna Steam Electric Station PROGRAH JFD VERSION PC-1.1 Primary Teer Dote-10-meter Level S I TE IDENT IF IER2 DATA PERIOD FXAHIHED2 1/1/92-12/31/92**~ANNUAL STABILITY BASED IIIND HEASURED MIND THRESHOLD JOINT FREOUEHCY SPEED (N/S)OH2 DELTA T SETMEEN 60.0 AT: 10.0 NETERS AT2.23 N/S DISTRIBUTION OF MIND SPEED AHD STAB!LITT CI.ASS 0 AHD 10.0 NETERS DIRECTION IN HmlRS AT 10.00 HETERS SE SSE S SSM H HHE NE EHE E ESE SM'MSM M MHM NM NN'M TOTAL CALH.24-1.50 1.51.3.00 3.01-5.00 5.01-7.50 7.51-10.00

>10.00 3 16 67 395 89 0 1 6 53 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13 0 0 0 0 0 13 13 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 I 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0-0 0 0 0 0 621 0 61 0 0 0 0 0 0 0 0 TOTAL 3 17 73 448 90 13 13 13 5 2 2 0 1 2 0 0 682 STABILITY BASED OH2 DELTA T BETMEEH 60.0 MIND NEASUREO At!10.0 NETERS MIND THRESHOLD AT:.23 II/S JOINT FREQUEHCT DISTRIBUTION OF MIND SPEED AHD SPEED (N/S)H HNE HE EKE E SIABILITT CLASS ALL AHD 10.0 HETERS DIRECTION IH HOURS AT 10.00 HETERS ESE SE SSE S SSM SM MSM M MNM NM HHM TOI'AL CALH.24.1~50 1.51-3.00 3.01-5.00 5.01.7.50 7.51.10.00

>10.00 96 189 116 6 0 0 243 280 77 1 0 0 476 1043 274 211 55 23 15 9 0 4 0 0 513 83 33 5 0 0 283 231 213 76 143 136 26 44 29 0 35 0 0 0 0 0 0 251 229 228 310 49 45 9 1 0 0 0 0 132 368 235 35 1 0 51 21 177 102 178 101 89 45 15 5 2 1 18 103 110 15 0 1 11 101'171 29 0 0 2 22 3833 162 2943'197 1489 23 290*0 25 0 4 TOTAL 407 601 820 1290 634 385 421 383 537 585 771 512 275 247 312 404 8586 PENNSYLVANIA POMER t LIGHT ONPANY (PPCL)-Susquehanna Steam Electric Station PROGRAH t JFD VERS IOH: PC-1.1 Primary Tcwer Data-10-meter Level SITE IDENTIFIER DATA PERIOD EXANINEDY 1/1/92-12/31/92~as ANNUAL STABI)ITY BASED OH: DELTA T BETMEEN 60.0 AHD 10.0 NETERS MIND+AIRED AT: 10.0 NETERS MINII THRESHOLD AT:.23 Il/8 TOTAL NWBER OF OBSERVATIONS:

8784 TOTAL NQIBER OF VALID OBSERVATIONS:

8586 TOTAL NQIBER OF HISSING OBSERVATIONS) 198 PERCENT DATA RECOVERY FOR THIS PERIG)t 97.7 X NEAN MIND SPEED FOR THIS PERIOD: 2.1 H/S NUHBER OF OBSERVATIONS MITH BACKUP STABILITY:

TOTAL NINIBER OF OBSERVATIOHS MITH BACKUP DATA: 121 121 PERCENtAGE OCCURRENCE Of STABILITY CLASSES A 8 C D E F G 16.78 3.83 3.79 37.46 20.61 9.59 7.94 DISTRIBUTION OF MIND DIRECTIOH VS STABILITY H NNE NE EHE E ESE SE SSE S SSM SM IISM M MHM NM NNM CAN 55 57 17 18 14 14 162 148 262 166 332 141 448 90 1290 634 A 88 98 88 50 B 13 25.28 19 C 23 21 40 13 0 220 273 298 127 E 49 140 178 111 F 11 27 115 52 G 3 17 73 13 TOTAL 407 601 820 385 79 20 30 153 101 25 13 421 66 98 20 16 8 21 144 179 101 190 31 28 13 5 383 537 100 15 28 203 209 28 2 585 261 165 40 34 45 26 285 228 122 53 16 6 2 0 771 512 55 15 13 177 13 1 1 275 45 21 11 155 12 1 2 247 66 69 12 16 6 12 203 260 21 42 4 5 0 0 312 404 5S ft PEHNSYLVANIA POMER C LIGNT C(NIPANY (PAL)-Susquehanna Steam Electric Station PROGRAK: JFD VERSION: PC-1.1 Primary Teer Data'60-meter level SITE IDENT IFIERY DATA PERIOD EXANIHED: 1/1/92-12/31/92*a~ANNUAL a@a STABILITY BASED MlkD KEASURED MlkD THRESHOLD JOINT FREOUENCY SPEED (K/S)ON: DELTA T BETMEEN 60.0 AT: 60.0 KETERS AT:.23 N/S DISTRIBUTION OF MIND SPEED AND STABILITY CLASS A AND 10.0 KETERS DIRECTION IN HOURS AT 60.00 KETERS H NHE NE EHE E ESE SE SSE S SSM SM MSM M MNM HM HHM TOTAL CALK.24.1~50 1~51-3.00 3.01-5.00 5.01-7.50 7.51-10.00

>10.00 4 10 20 18 23 24 47 33 28 18 35 53 30 8 8 9 16 6 2 1 0 0 0 0 0 0 0 0 0 0 9 14 11 1 0 0 12 7 6 12 14 29 21 33 26 8 9 12 0 0 2 0 0 0 15 40 32 30 2 0 11 4 2 0 1 56 27 6 7 12 143 94 31 25 29 41 71 29 12 15 2 10 0 0 0 0 4 0 0 0 0 1 143 15 382 37 616 18 280 0 16 0.4 TOTAL 72 126 89 56 50 35 53 63 75 119 253 210 68 44 57 71 1441 STABILITY BASED MIND KEASURED MlkD THRESHOLD JOINl FREQUENCY SPEED (K/S)OH: DELTA T BETIIEEH 60.0 AT 60.0 KETERS AT:.23 K/S DISTRIBUTIOH OF MIND SPEED AND S'TAB I LITT CLASS B AHD 10.0 KETERS DIRECTION IH HOURS AT 60.00 METERS N NNE NE ENE E ESE SE SSE S SQI SM MSM M MNM HM NHM TOTAL CALII.24-1.50 1.51.3.00 3.01.5.00 5.01.7.50 7.51-10.00

%10.00 4 2 2 5 8 4 5 5 7 7 1 10 11 3 3 2 10 4 0 0 0 0 0 0 0 0 0 0 0 0 4 16 4 0 0 0 0 2 6 5 6 12 2 2 0 0 0 0 0 5 1 3 3 3 4 0 2 0 0 3 1 0 0 0 9 10 6 8 9 16 14 9 9 3 4 16 3 3 3 3 4 0 0 0 0 2 0 0 0 0 0 36 5 106 7 114 2 62 0 9 0 2 TOTAl.11 27 22 15 18 24 14 21 8 20 35 47 18 20 15 14 329 pt I'ca PENNSYLVANIA POMER 8 LIGHT CQIPANY (PAL)-Susquehanna Steam Electric Station PROGRAHt JFD VERSION: PC-1.1 Primary Teer Data-60-meter level SITE IDENTIFIERt DATA PERICO EXAHINED: 1/1/92-12/31/92 ANNUAL~"~STABILITY BASED MIND HEASURED MIND THRESHOLD JOINT FREOUENCY SPEED (H/S)CALH.24.1.50 1.51-3.00 3.01-5.00 5.01-7.50 7.51-10.00

>10.00 ON: DELTA T BETMEEN 60.0 AT 60.0 HETERS AT!.23 H/S DISTRIBUTION OF MIND SPEED AHD STABILITY CLASS C AND 10.0 HETERS DIRECTIOH IH HOURS AT 60.00 HETERS N HHE NE EKE 1 4 3 11 11 16 4 2 0 0 0 0 6 8 12 6 0 0 7 5 5 8 0 1 0.0 0 0 0 0 4 1 3 8 5 5 9 6 5 2 0 2 0 0 0 0 0 0 1 10 9 7 0 0 0 0 0 0 0 14 6 4 2 5 13 18 1 4 3 8 16 12 1 3 1 4 1 0 0 0 0 0 0 0 0 0 35 3 102 4 116 3 66 0 6 0 0 E ESE SE SSE S SSM S'M MSM M MHM N'M HNM TOTAL TOTAL 19 33 32 12 1C 12 23 12 15 27 36 44 18 7 11 10 325 STABILITY BASED OHI DELTA T BETMEEN 60.0 MIND HEASURED AT: 60.0 HETERS MIND THRESHOLD ATt.23 H/S JOINT FREOUENCY DISTRIBUTION OF MIND SPEED AND SPEED (H/S)N HHE NE EHE E STABILITY CLASS D AHD 10.0 HETERS DIRECTION IH HOURS AT 60.00 HETERS ESE SE SSE S SSM SM MSM M MHM NM NNM TOTAL CALH.24.1.50 1.51-3.00 3.01-5.00 5.01-7.50 7.51.10.00

>10.00 17 53 101 24 0 51 88 96 39 5 0 69 45 111 50 78 25 18"19 10 3 0 30 37 33 11 3 0 16 31 31 18 1 0 28 21 38 35 33-45 13 16 5 5 0 0 33 35 40 59 39 65 21 42 3 4 1 1 37 17 8 104 76 37 68 122 87 21 130 73 4 53 27 1 14 5 2 5 36 24 67 120 61 64 1 5 0 0 0 4 41S 30 849 140 1150 67 637 1 134 0 29 TOTAL 199 279 293 142 11C 97 117 122 137 206 235 412 237 167 21S 242 3217 PENNSYLVANIA POMER C LIGHT COMPANY (PAL)-Susquehanna Stenm Electric Station PROGRAH$JFD VERSION$PC-1.1 Prieary Tcuer Data-60.meter level SITE IDENT IF IER$DATA PERIOD EXAHINED$1/1/92-12/31/92 ANNUAL*~*STABILITY BASED MIND llEASURED MIND THRESHOLD JOINT FREOUENCY SPEED IH/S)ON: DELTA T BETMEEN 60.0 AT$60+0 METERS AT:.23 H/S DISTRIBUTION OF MIND SPEED AND STABILITY CLASS E AKD 10.0 HETERS DIRECTION IN HIJRS AT 60.00 METERS H KKE KE ENE E ESE SE SSE S SSM SM MSM M MKM NM NHM TOTAL CALH.24-1.50 1.51-3.00 3.01-5.00 5.01.7.50 7.51-10.00 F10.00 20 69 98 51 45 56 1C1 86 23 12 8 23 27 7 10 4 2 4 5 5 0 0 0 3 1 0 0 1 8 0 30 12 1 2 0 0 38 47 46 18 24 22 7 17 46 1 2 10 0 1 1 0 1 3 28 57 112 26 0 1 32 11 4 85 40 12 71 64 10 11 48 3 1 3 1 0 0 0 3 13 5 0 0 0 6 13 22 2 0 0 0 11 539 11 625 24 454 1 126 1 12 0 14 TOTAL 88 235 216 97 73 CS 64 92 128 224 200 166 30 21 C3 48 1770 STABILITT BASED MIND MEASURED VINO THRESHOLD JOINT FREOUENCT SPEED (H/S)ON$DELTA T BETMEEN 60.0 AT: 60.0 IIETERS AT$.23 H/S DISTRIBUTION OF MIND SPEED AND Sl'ABIL I'IT CLASS F AND 10.0 METERS DIRECTION IN HOURS AT 60.00 METERS H HKE NE EKE E ESE SE SSE S SSM SM MSM M MHM KM NNM TOTAL CALH.24-1.50 1.51-3.00 3.01.5.00 5.01.7.50 7.51.10.00

%10.00 12 57 89 30 26 32 193 83 7 4 4 4 6 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 19 1 0 0 0 0 24 10 12 12 11 19 2 5 4 0 0 0 0 0 0 0 0 0 14 9 20 25 8 13 0 0 0 0 0 0 6 1 1 1 11 1 0 4 15 0 2 1 6 1 0 0 0 0 0 0 0 0 0 0 0 2 313 6 429 3 7C 0 7 0 0 0 0 TOTAL 48 254 178 44 30 20 38 26 35 42 47 38 3 3 6 11 823 PEHNSTLVANIA POMER 8 LIGHT CO(PANT (PPCL)-Susquehanna Steam Electric Station PROGRAHt JFO VERSIOHt PC-1.1 Primary Touer Data-60-meter level SITE IDENTIFIER Y DATA PERIOD ENAKINEDt 1/1/92-12/31/92 ANNUAL*i*STABILITY BASED MIND KEASURED MIND TNESHOLD JOINT FREQUENCY SPEED (H/S)ON: DELTA T BETMEEN 60.0 AT: 60.0 KETERS AT:.23 K/S DISTRIBUTION OF MIND SPEED AND STABILITY CLASS G AHD 10.0 HETERS DIRECTIOH IH HOURS AT 60.00 HETERS N NHE NE EHE E ESE SE SSE S SSM SM MSM'M MNM NM HNM TOTAL CALH.24-1.50 1.51-3.00 3.01-5.00 5.01-7.50 7.51-10.M>10.00 5 56 64 36 28 19 212 81 8 6 6 7 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 11 9 0 0 0 0 4 15 1I 6 4 6 0 1 0 0 0 0 0 0 0 0 0 0 7 12 4 0 0 0 3 3 0 0 1 17 4 2 2 3 2 11 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 246 6 397 2 39 0 0 0 0 0 0 TOTAL 30 275 150 44 34 20 10 20 17 23 22 18 2 2 5 10 682 STABILITY BASED ONt DELTA T BETMEEN 60.0'MIND KEASURED AT 60.0 KETERS MIND TNESHOLO AT:.23 H/S JOINT FREQUENCY DISTRIBUTIOH OF MIHO SPEED AHD SPEED (H/S)N NNE NE EHE E STABILITY CLASS ALL AHD 10.0 KETERS DIRECTIOH IH HOURS AT 60.00 HE'TERS ESE SE SSE S SSM SM MSM M MNM k'M NHM TOTAL CALH.24-1.50 1.51-3.00 3.01-5.00 5.01-7.50 7.51-10.00

>10.00 63 191 166 43 4 0 249 34S 697 407 209 169 69.38 5 10 0 8 192 165 128 92 50 55 26 17 6 4 8 0 92 88 51 21 1 0 110 103 100 98 78 119 26 29 5 6 0 1 111 105 122 201 123 233 49 112 6 8 4 2 95 310 326 85 11 1 42 15 174 68 338 138 287 121 74 29 20 5 6 68 112 77 1 0 0 14 20 1730 70 76 2890 179 217 2563 87 91 1178, 5 2 177 0 0 49 TOTAL 467 1229 980 410 333 253 319 356 415 661 828 935 376 264 355 406 85S7 PENNSYLVANIA POMER t LIGHT COHPANY (PPCL)-Susquehanna Steam Electric Station PROGRAHt JFD VERSIOH: PC-1.1 Primary Teer Data-60-meter level SITE IDENTIFIER:

DATA PERIOD EXAHIHEDt 1/1/92-12/31/92**~ANNUAL STABII,ITY BASED ON: DELTA T BETMEEH 60.0 AND 10.0 METERS MINP QASbRED AT: 60.0 HETERS MIND THRESHOLD AT:.23 II/S'TOTAL HISSER OF OBSERVATIOHS:

8784 TOTAL NOSER OF VALID OBSERVATIONS:

8587 TOTAL IRBIBER OF HISSIHG OBSERVATIDHSt 197 PERCEHT DATA RECOVERY FOR'THIS PERIMt 97.8 X IIEAN IIIND SPEED FOR THIS PER100: 3.2 H/S NINBER OF OBSERVATIONS IIITH BACKUP STABlLITY:

121 TOTAL NLNBER OF OBSERVATIONS MITH BACKUP DATA: 121 PERCEHTAGE OCCURRENCE OF STABILITY CLASSES A 8 C D E F G 16.78 3.83 3.78 37.46 20.61 9.58 7.94 OISTRIBUTIOH OF MIND DIRECTION VS STABILITY H NNE NE EHE E ESE SE SSE S SSM SM MSM M MNM NM NHM CALH A 8 C D E F G TOTAL 72 126 11 27 19 33 199 279 88 235 48 254 30 275 467 1229 89 22 32 293 216 178 150 980 56 50 15 18 12 14 142 114 97 73 44 30 44 34 410 333 35 24 12 97 45 20 20 253 53 14 23 117 64 38 10 319 63 75 21 8 12 15 122 137 92 128 26 35 20 17 356 415 119 253 20 35 27 36 206 235 224 200 42 47 23 22 661 828 210 68 47 18 44 18 412 237 166 30 38 3 18 2 935 376 44 57 20 15 7 11 167'18 21 43 3 6 2 5 264 355 71 0 14 0 10 0 242 0 48 0 11 0 10 0 406 0

$'C'f k y e fP g'l R Page 1 of 5 TABLE 19 AVERAGE ANNUAL RELATIVE CONCENTRATIONS SlJaqueh4tea Steee Electric Station-GROUND.LEVEL RELEASE~1992 KO DECAY, UKDEPLETED CORRECTED FOR OPEN TERRAIN RECIRCULATION USING SPECIAL TERRAIN ADJUSTHKNT FACTORS ANNUAL AVERAGE CHI/4 (SEC/HETER CUBED)DISTANCE IH HILES SECTOR.250.500.750 1.000 1.500 Z.ooo 2.500 3.000 3.500 C.ooo 4.500 S SSM SM i MSM M MKM N'M NNM N KNE NE ENE E ESE SE SSE 1.149E-OS 3.940E.06 2.191E 06 1.404E 06 7.303E-OT C.651E-OT 3.24BE 07 2.574E.OS 8.198E.06 4.738E.06 2.972E.06 1.717K-06 1.113E.06 7.959E 07 4.417K.05 1.383E.05 8.123E.06 5.292E-06 2.929E-06 1.921E-06 1.391E.06 1.152E.04 3.584K.05 2.159E-05 1.450E.05 8.185E.06 5.647E.06 4.318E 06 5.693E-05 1.745E-05 9.021E-06 5.629E-06 2.985E-06 1.946K-06 1.399E.06 2.755E.05 8.657E.06 4.825E.06 3.068E.06 1.747E.06 1.125E.06 7.915E 07"2.721E-05 8.626E-06 4.974E.06 3.123E.06 1.752K.06 1.129E.06 S.040E 07 2.046E-05 6.M3f.ob 4.016E.06 2.828E.06 1.515E.06 9.988E.OT 7.249E 07 2.257E-05 7.160E-06 4.041E.06 2.520E.06 1.483K-06 9.770E-OT 7.719E.OT 2.207E.05 7.835E.06 4.431E.06 3.045E 06 1.646E-06 1.122E 06 8.399E-07 1.Q6E.05 5.371K.ob 3.072E 06 1.944E 06 1.111K 06 7.567E-07 5.640E-OT S.61CE.06 2.802E.06 1.585K.06 1.068E-06 5.700E.OT 3.882E.OT 2.906E 07 4.702E-06 1.618E-06 8.858E-OT 5.291K-07 2.770E-OT 1.7S1E-OT 1.265E 07 5.306E 06 1.700E 06 9'40E-07 5.475E 07 2.768E.07 1.694K 07 1.143K 07 5.178K-06 1.740E.06 1.011E.06 6.562E-OT 3.412E.OT 2.13$E.OT 1.467E 07 7.928E-06 2.834E-06 1.626E-06 9.804E-07 5,04bf-07 3.279E-OT 2.336E.OT 2.271E-OT 1.641K-OT 5.559E.OT 3.978E-OT 1.013E.06 7.577E.OT 3.174E 05 2.391E-06 1.010E.06 7.511E.07 5.785E.07 4.383E.OT 6.003E.OT 4.661E-OT 5.247K 07 3.917E.OT 5.624E.OT 4.252E 07 6.136E 07 4.657E-OT 4.201E.OT 3.260E.07 2.227E 07 1.774E-07 9.137E.OS 6.873K.OB 8.216E N 6.146E OS 9.930E.OB 6.905E.OS 1.653E.07 1.208E.07 1.269K.07 3.064E 07 5.934E.OT 1.952E.06 6.071E 07 3.540E-OT 3.737E-OT 3.279E.07 3.500E-07 3.846E-OT 2.720E 07 1.C95E 07 5.531E 0$4.640E OS 5.110E-OB e.scbf-oe 1.000E.07 2.386K.OT 4.727E.07 1.623K 06 4.970E.OT 2.907E.07 3.048E-07 2.795E.OT 2.933E.OT 3.235E.07 2.312E 07 1.289K-OT C.557E-OS 3.562E.OS 3.828E.M 6.502E 08 ANKUAL AVERAGE CHI/O (SKC/HETER CUBED)BEARIKG 5.000 7.500 10.000 DISTANCE IH HILES 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 6.366E-11 1.0988-10 7.9108-10 8.869E-10 1.514E-10 4.607E-11 9.149E-11 3.612E 10 2.549E 10 3.465 E-10 2.333E-10 4.399E 10 6.159E-11 2.321K-11 8.414E.12 3.637E-11 40 5I S 8.261E-OS 3.708K-OB 1.903E-OS SSM 1.980E-OT 9.045E-OS 4.948E.OB SM 3.971K-OT 1.957K-OT 1.074E.OT MSM 1.385E-06 7.256E-OT 4.028E-OT lI 4.186E-07 1.995K-OT 1.083E-07 MKM 2.C51E-OT 1.241E.OT 6.929E-OB NM 2.580E 07 1.335E-07 T.565E 08 KKM 2.395E-07 1.324E-OT 7.424E.OB N 2.648E-OT 1.853K.OT 9.869E-OS NKE 2.760E.OT 1.485E-OT 8.051E-OS Nf 1.977E-OT 1.097E-07 6.308K-OS KNE 1.105K-OT 6.087E.OS 3.917K.OS E 3.850E-OB 2.002E-OB 1.131E.OB ESE 2.906E-OS 1.235E.OS 7.102E.09 SE 3.089E-OS 1.189E-OB 6.881K-09 SSE 5.251E-OS 2.095E-OB 1.176K 08 CHI/O (SEC/HETER CUBED)FOR EACH SEQlEN'I 7.346E-11 1.2QE-10 9.039E-10 1.007E.09 1.727K.10 5.2S6E 11 1.050E-10 4.146E 10 2.936E-10 3.996E 10 2.689E-10 5.076E-10 7.141E 11 2.681E-11 9.754E-12 4.220E-11 SKQlfHT BOUNDARIES IH HILES 3-4 4.5 5.10 20.30 30.40 10-20 1-2 2-3 D I RECT IOH.5.1 FROH SITE S 2.230E.06 7.621E-07 3.231E.07 SSM 4.722K-06 1.727E-06 7.846E-07 SM 8.132K-06 3.006E 06 1.381E-06 MSM 2.160E-05 8.461E.06 4.215E 06 M 9.385E.06 3.111E.06 1.389E.06 MKM 4.896E 06 1.764E 06 7.952E 07 NM 4'.9QK-06 1.780K-ob e.093K-OT NNM 4.125E.06 1.577K.06 7.179E 07 N 4.058E-06 1.489K.ob 7.428E-OT KKE C.571E 06 1.724E 06 S.247E-07 NE 3.081K.06 1.139E 06 5.578E-OT ENE 1.626E 06 5.998K-OT 2.895E-OT E 8.900E.OT 2.891K.07 1.262E.OT ESE 9.292E 07 2.892E-OT 1.161E-OT SE 1.015E 06 3.546E 07 1.456E-OT SSE 1.607E-06 5.319E-OT 2.315E-OT VENT AKD BUILDlNG PARAHETERS:

RELEASE HEIGHT (I(ETERS)10.00 DIASTER (HETERS).00 , EXlT VELOCI'TY (N/SEC).00 AT THE RELEASE HEIGHT RS/SEC)9.292E 10~3.300K-09 8.480K.09 2.518E 08 5.462E.09 5.028E 09 4.943K.09 5.112E.09 6.829E 09 5.213E 09 4.592E.09 6.060E 09 1.207E 09 8.489K-lo 5.152E.10 8.55E-10 8.214E.1.703E.3.917E.OS 9.614E 08 2.012E-07 7.2SbE.OT 2.077E-OT 1.266E.OT 1.354E.07 1.303E-07 1.645E 07 1A66K 07 1.085K-OT 6.226K.OB 2.026E 08 1.373E.OS 1.388K-OS 2388K.OS 2.110E-10 6.317E-10 2.588K 09 5.306E.09 9.Q4E 10 6.648E 10 7.266K-10 1.389K 09 1.4QE.09 1.254E.09 9.725E-10 1.760E 09 2.960E-10 1.TS1E-10 9.065K-11 1.786E-10 6.614E.09 1.944E.OB CD 178E.OB 1.519E.07 3.998E.OS 2.818E.OS 3.094K.08 2.983K.N 3.696E 08 3.102K 08 2.681E 08 1.996E-OS 4.924E.09 3.190E.09 2.966E.09 4.9MK.O9 1.679K.OT 4.081E-07 7.679K.OT 2.448E.06 7.702E.OT 4.4QE.OT 4.692E.07 4.054E.OT 4.35SE-OT 4.770E.OT 3.323E.OT 1.797E 07 7.009E.M 6.164E 0$7.M5E-M 1.212E.OT 1.015E.07 2.436E.07 4.805K.07 1.632E.06 5.006E.OT 2.926E 07 3.079E 07 2.790E.07 2.995E.OT 3.240E.OT 2.309E-OT 1.282E.OT 4.58CE.OB 3.99E-OB 3.934K.08 6.733E.N 1.061'1.352E 2.322E 8.035E 1A16E 5.050E 3.758K 4.399K 3.228E 6.061 E 8.721E 3.621E 1.660E 5.2'16E REP.MIND HEIGHT (HETERS)10.0 BUILDING HEIGHT (HETERS)61.3 BLDG.HIN.CRS.SKC.AREA (SO.HETERS) 2575.0 HEAT EHISSION RATE (CAL/SEC).0 AT THE HEASURED MIND HEIGHT (10.0 NETERS): VENT RELEASE HNE MIND SPEED (HKTERS/SEC)

STABLE C(WO IT IOHS LESS THAN.000 BETMKEN.000 AND ABOVE F 000 MIND SPEED (NETERS/SEC)

UNSTABLE/NEUTRAL CONDIT LESS THAN.000.000 BETMEEN.000 AKD ABOVE.000 VENT RELEASE INmf MIND SPEED (HKTE ELEVATED LESS THAN.000 ELEVATED Hl XKD GRIXIND LEVEL NIXED BKTMEEN.000 AKD GR(W LEVEL ABOVE.000.000 4.467K-09 2.018E-09 7.129E-10 3.838E.10 1.725E.10 1.150E-10 1.582E N 7.129K.09 2.635E.09 1.302E 09 4.413E.10 2.954E-10 3.216E.OB 1.618K.DB 7.343E.09 4.295E-09 2.282K.09 1.575E.09 1.153E 07 5.399E.OS 1.952E.OS 1.070E-OB 4.095K.09 2.322K.09 3.045E-OB 1.295E.OB 3.615E.09 2.010E-09 7.097E.10 4.002E.10 2.373E-OS 1.097E.OS 4.150E.09 1.800E.09 2.755E.10 1.542E-10 2.699E 08 1.155K.OS 3.543E.09 1.704K.09~4.388K-IO 2.453E.10 2.522E.OB 1.107E-OS 3.717E 09 2.299E-09 1.298E 09 7.864E-10 2.721E 08 1.340E 08 6.112E-09 3.045K 09 1.071E 09 6-193E 10 2.466E-OB 1.105E-OS 4.066K.09 2.278E 09 1.043E 09 6.695E 10 2.4C2E 08 1.046E.OB 3.248E 09 1.798E-09 8.098E 10 4.954E 10 1.965E-OS 1.058E 08 5.879E-09 3.200E.09 1.480E.09 9.246E-10 4.286E.09 2.207K-09 1.151E.09 5.862E 10 2.291K 10 1.370K.10 2.813E 09 1.516K.09 8.465E 10 4.065E-10 1.137E 10 6.304E-11 2.7C9E 09 1.171E.09 3.BOSE.10 1.902K 10 6.948E.11 3.C53E-11 C.407E-09 1.924E 09 6.819E 10 3.503E 10 1.C06E-10 8.309E-11 51 4J fk g1)

Page 2 of 5 Suaqueheraa Steaa Electric Station-GR(XJMD-LEVEL RELEASE-1992-2+260 DAT DECAY, UHDKPLETKD CORRECTED FOR OPEN TERRAIN RECIRCULATION USING SPECIAL TERRAIN ADJUSTHEHT FACTORS ANNUAL AVERAGE CHI/O (SKC/HETER CUBED)DISTANCE IH HILES SECTOR.250.500.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S SSM SM , MSM MN N NHM N NNE NE EHE E ESE SE SSE 1.147E.05 3.931E-OS 2.183K.06 1.397E 06 7.250E-OT 4.607E-OT 3.209K 07 2.571K 05 8.175K OS 4.718K 06 2.955E 06 1.702E 06 1.101E.OS 7.84&E 07 4.411E-05 1.378E-05 8.086E-OS 5.259E 06 2.902E-06 1.89&E-06 1.370E 06 1.151K.04 3.572E.05 2.14&E.05 1.441E.05 8.107E.06 5.575K.06 4.249E-06 5.684K 05 1.739K 05 S.977E 06 5.592E-06 2.957E 06 1.921K 06 1.377K-M 2.751E-05 S.QOE-OS 4.802E.06 3.04&E.06 1.730K 06 1.110E.06 7.7&BE-OT 2.717K-05 8.600E-OS 4.951K-06 3.104E-OS 1.736E-06 1.115E-06 7.91&E-OT 2.043E.05 6.862E 06 3.998K.OS 2.811E-06 1.501E.OS 9.867E.07 7.139E.OT 2.253E.05 7.139K.OS 4.024E-06 2.505E-06 1.471K 06 9.65&E.OT 7.608K-OT 2.204E.05 T.SICK.OS 4.413E.OS 3.02&E.06 1.Q2E.06 1.110E.OS 8.285E.OT 1.QCE.05 5.359E.06 3.061E.OS 1.935E 06 1.104E 06 7.497E.DT 5.575E-OT 8.606E-06 2.797K-OS 1.581E-06 1.064E-06 5.667E-OT 3.852K-OT 2.878E-OT 4.698K 06 1.615E 06 8.835E-OT 5.273E 07 2.755K 07 1.769E 07'1.254E-OT 5.301E-06 1.69BE.06 9.217E.OT 5.456E.OT 2.754E-OT 1.682E-DT 1.133E.07 5.174K.06 1.737E-06 1.008K-OS 6.5C3E.OT 3.39&E.OT 2.126E.OT 1.456E.OT 7.922E 06 2.829E 06 1.622E-06 9.774E 07 5.025E 07 3.260E-OT 2.319E 07 2.23&E-OT I ALICE-07 1.2CSE 07 9.784E.OB 5.465E.OT 3.900E-OT 2.996E.OT 2.326E.OT 9.942E 07 7.416E-OT 5.790K.OT 4.599E 07 3.11CE-06 2.338K.06 1.903E-06 1.577E-06 9.906E.07 7.342E-OT 5.915E.OT 4.827E.07 5.675E 07 4.285E-OT 3.450E 07 2.824E-OT 5.S93E 07 4.562E-OT 3.646E 07 2.965K.OT 5.152E.OT 3.834K.OT 3.200E.OT 2.719E.OT 5.527K 07 4.167K-OT 3.420E 07 2.857E-OT 6.036K.OT C.569E-OT 3.763E-OT 3.157E.07 4.143E-OT 3.207E-OT 2.669E-OT 2.264E 07 2.201E 07 1.750E-OT 1.472E-OT 1.267E 07 9.040E-OS 6.788E-O&5.C53E-OS 4.484E-OS 8.131E-OS 6.071E.OS C.576E-OS 3.506E-OS 9.S43E.OB 6.&34K 08 5~050E-08 3.777K.OS'\.63&E-07

'1.195E 07 8.73&E 08 6.41ZE 08 ANNUAL AVERAGE CHI/O (SEC/HETER CUBED)BEARING 5.000 7.500 10.000 DISTANCE IH HILES 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S&.062E-OB 3.574E-OS 1.811E.OB SSM 1.925E-OT 8.668E.OB 4.674E.OB SM 3.851K 07 1.869K 07 1.010E 07 MSM 1.341E 06 6.917E-OT 3.779E.OT M 4.052K 07 1.900E.OT 1.015E 07 MMM 2.373E-OT 1.182E.OT 6.496E.OS NM 2.501E.07 1.274E.OT 7.110E.OS NN 2.322E.OT 1.264E-OT 6.981E-OS N 2.572K.OT 1.7T4E-OT 9.312K F 08 NNE 2.686E.DT 1.426E.07 7.623E-OS HE 1 932E 07 1.059E-OT 6.020E OS ENE 1.084E 07 5.910E 08 3.765E.OB E 3.781K.OS 1.948E-OS 1.091E.OS ESE 2.855E-O&'1.202E-OB 6.84&E-09 SE 3.043K.OB 1.162E.OS 6.675E.09 SSE 5.17OE-OS 2.047E.OS 1.140E-OS CHI/O (SEC/HETER CUBED)FOR EACH SEGMENT 4.14&E 09 1.828K.09 6.301E-10 3.309E-10 1.452E-10 9.441E 11 1.C52E-OS 6.360E 09 2.285E.09 1.097K 09 3.615E.10 2.352E-10 2.932E-OB 1.C30E-OB 6.291K-09 3'67E-09 1.83&E 09 1.230K.09 1.04BE.07 C.753E 08 1.665E.OS 8.&39K-09 3.277K.09 1.801E.09 2.761E-OS 1.137E 08 3.072E-09 1.654E.09 5.651E 10 3.085E-10 2.154E 08 9.6COE.09 3.532E.09 1.4&3E 09 2.19&E-10 1.191E 10 2.459E.OS 1.020E-OB 3.034E.09 1.415E.09 3.532E.10 1.915E-10 2.300E OS 9.792E-09 3.18&E-09 1.912K-09 1.047E.09 6.152E 10 2.495E.OB 1.193E.OS 5.289K.09 2.561E-09 8.753K-10 4.919E.10 2.272E.OS 9.90&E.09 3.549K.09 1.935K.09 S.Q1E 10 5.392E-10 2.277E 08 9.533K-09 2.894E 09 1.566K 09 6.896E-10 4.126K-10 1.852K OS 9.771E 09 5.325E 09 2.842E 09 1.289K 09 7.900E 10 4.058K-09 2.052E-09 1.050E 09 5.254E-lo 2.017E-10 1.184E-10 2.661K.09 1.407E-09 7.709K-10 3.632E-10 9.961E.11 5.419E-11 2.625E 09 1.101E.09 3.524E-10 1.732E-10 6.231K 11 3.049E-11 4.206E.09 1.&07K.09 6.307E.10 3.189E-10 1.261E-10 7.336E-11 5.886E.11 4.97&E-11 9.772K 11 8.26OE.11 6.844E-10 5.806E 10 7.565E-10 6.455E.10 1.288K 10 1.094K-10 3.955E-11 3.338K-11 7.951E.11 6.715E 11 3.146E-10 2.65&E 10 2.267E.10 1.913E-10 3.133E-10 2.646E.10 2.190E 10 1.859E 10 4.254K-10 3.618E 10 S.ICE 11 5.138K 11 2.261E-11 1.921E-11 8.478E-12 7.201E 12 3.669E-11 3.114E-11 SEGHENT BCUMDARIES IM HILES 3.4 4.5 5.10 20.30 30-40 10-20 DIRECT IOI.5-1 1-2 2-3 FRDH SITE S 2.222E 06 7.569E 07 3.193E.07 SSM 4.703E 06 1.713E 06 7.73&E 07 SM 8.096E.06 2.980K.06 1.361K.06 MSM 2.150E-05 8.383K-OS 4.149E OS M 9.342E-06 3.082E-06 1.367K-06 MN 4.873K 06 1.748K 06 T.BZTK.OT NM 4.941E-OS.1.764E.06 7.9nE.OT NN, Co107K 06 1.564K 06 7.072E 07 H 4.041E.OS 1.476E-06 7.322E.DT HHK 4.553K-OS 1;nOK-06 8.137K-OT NE 3.071E 06'I'31E-06 5.515E-07 ENE 1.621K 06 5.965K-07 2.&67K.OT E 8.878K 07 2.876K-OT 1.251E.07 ESK 9.270K 07 2.878K 07 1.151E 07 SK 1.013E OS 3.532E 07 1.446E OT SSK 1.604K.06 5.296E 07 2.297E.OT VENT NO BUILDING PARAIKTERST RELEASE HEIGHT (I%TERS)10.00 DIASTER (i%TERS).00 i EX IQ VELOCITT (H/SKC).00 AT THE RELEASE HEIGHT: VENT RELEASE IKOE MIND SPEED (METERS/SEC) 40-50 8.298E-10 2.897E-09 7.337E-09 2.176K-08 4.717E-09 4.341E-09 4.298K.09 4 439K-09 5.970E-09 4.599E-09 C.133E.09 5.517E.09 1.107K.09 7.774E.10 4.803K 10 8.198K.10 3.7&BE.OS 9.243E.OS 1.927E 07 6.966E.OT 1.985E.07 1.210E 07 1.297E.07 1.24&E 07 1.577E.07 1.411E.OT 1.050K.OT 6.052E.OB 1.975E 08 1.340E-M 1.360K 08 2.33SE.OS 1.652E-07 C.003E-OT 7.51&E 07 2.394E.06 7.531E-OT 4.364K-OT 4.593E-OT 3.969K-OT 4.271 E-OT 4.681E 07 3.270E-OT 1.773E 07 6.923E-OS 6.090K-08 7.014E 08 1.199E-OT 9.935E.OS 2.376E.07 4.675E.OT 1.586E.06 4.&QE.07 2.843E.07 2.995E.OT 2 714E 07 2.91&E 07 3.162K-OT 2.261E-07 1.260K 07 4.511E.OS 3.582E.OS 3.882E-OB 6.641E.OS 1.789E-10 5.236E-10 2.100E.09 4.304E.09 7.783K 10 5.424E 10 5.949E 10 1.130K 09 1.211E.09 1.046E.09 8.345E-10 1.543K.09 2.6Z4E-10 1.576E 10 8.1SSE.11 1.611E-10 6.603E.11 1.32&E.1C 8.075E-1C 1.025E 09'1.74&E 10 6.084E-11 1.081E.10 3.856E 10 2.921E.10 3.622E 10 2.641K 10 5.099E-10 7.433K.11 3.071E.11 1.453E 11 4.550E.11 6.221K.09 1~806E 08 3.S56E.OB 1.400E-07 3.6S'lE-08 2.590E.OB 2.853K.OS 2.753E.OS 3.C31E-OS 2.892K-OB 2.520K 08 1.&BBE.OS C.S&9E 09 3.034E.09 2.84&E.09 4.739E.09 MIND SPEED (HETERS/SKC)

UNSTABLE/NEUTRAL CONDITION LESS THAN~000 BETMEEM.000 AMD.00 ABOVE.000 ELEVATED LESS THAN.000 HIXED BEllKEN.000 AND GR(XNH)LEVEL ABOVE.000~000 REP, MIND HEIGHT (HETERS)10.0 BUILDING HEIGHT (HETERS)61.3 BLDG.HIN.CRS.SEC.AREA (SD.HETKRS) 2575 0 HEAT KHISSION RATE (CAL/SEC).0 AT THE HEASURED MIND HEIGHT (10.0 HETERS): VENT RELEASK IHIE IJIND SPEED (HETERS/SEC)

STABLE COID IT IONS ELEVATED LESS THAN.000 HIXED BETMEEN.000 AMD.000 GR(AJMD LEVEL ABOVE ,.000 52 Page 3 of 5~~Susquehsms Stesa Electric Station-GROUND-LEVEL RELEASE-1992 8.000 DAY DECAY, DEPLETED CORRECTED fOR OPEN TERRAIN RECIRCULATION USING SPECIAL TERRAIN ADJUSTHKHT FACTORS ANNUAL AVERAGE CHI/O (SEC/HETER CUBED)DISTANCE IH HILES SECTOR.250.500.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S SSM SM MX MKM NM NNM N NNE NE EKE E ESE SE SSE 1.087E.05 3.596K 06 1.950E 06 1.227E-06 6.1S9E-07 3.841E 07 2.622E-07 2.436E 05 7.CSIE-06 4.217E 06 2.597E-06 1.454E-06 9.191E.07 6 CZZE-07 C.179E 05 1.262E-05 7.230K 06 4.624E-06 2.4S1E.06 1.585E-06 1.122E-06 1.090K.OC 3.270E.05 1.921E.05 1.267E-05 6.933E-06 4.659E-06 3.482E.06 5.386E 05 1.592E 05 8.02SE.06 4.918E 06 2.529E-06 Is606E-06 1.128E.06 2.606E.05 7.899K.06 4.294E.06 2.681K.06 1.480K.O6 9.2S1E-07 6.382E.07 2.574E-05 7.870K 06 4.427E 06 2.729E 06 1.48CE 06 9.318E-07 6.485K-07 1.935K 05 6.280E 06 3.575E 06 2.472E-06 1"283K.06 S.242E 07 5-847E 07 2.135K.05 6.533E.06 3.597K.06 2.202K-06 1.257E.06 8.064K.07 6.227E-07 2.088E-OS 7.149E.06 3.944E.06 2.661E-06 1.394E.06 9.266E.07 6.777E-07 1.547E-05 4.901K-06 2.735E 06 1.699E-06 9.420E.07 6.250E.07 4.554E 07 8.151E.06 2.55SE.06 1.411E.O6'9.336E-07 4.833E 07 3.207E-07 2.347E-07 C.449E 06 1.477E.06 7.MSE.07 4.627E.07 2.349E 07 1.C72E.07 1.022E-07 5.0208-06 1.552E-06 8.228E.07 C.7SSE.07 2.347E-07 1.400E.07 9.233E.OS 4.899E-06 1.5SSE-06 9.000E-07 5.739E-07 2.895E-07 1.768K-07 1.1S6E-07 7.501K-06 2.5S6K.06 1.448E.06 8.574E.07 4.2S2E 07 2.711E 07 1.889E-07 1.797K 07 1.275E 07 9.68SE 08 7.515E-OS C.39CE.07 3:087E 07 2.337E 07 1.791E.07 8.002E 07 5.877E 07 4 524E 07 3.546E 07 2.508K.06 1454K 06 1.488E 06 1.217E 06 7.979E.07 5.823E-07 4.626E 07 3.727E.07 4.570E.07 3.398E D7 2.698K 07 2.180E.07 4.7C3E 07 3.615E 07 Zo849E-07 2.287E 07 4.146E.07 3.0ME 07 2.500K-07 2.097E 07 4~445E.07 3.299E-07 2.669E-07 2.201E.07 4.851E 07 3.614E 07 2.934E.07 2.C29E.07 3.324E.07 2.532K 07 2.077E.07 1.738K.07 1.7QE 07 1.379K 07 1.143E 07 9.697E OS 7.236K.08 5.344E OS 4.229E.OS 3.430E.M 6.507E-OS 4.779K.OS 3.548K.OS 2.681E.M 7.86SE.08 5.372E.OS 3.910E.OS Z.M3E.08 1.310E-07 9.396E-OS 6.767E-08 4.896E 08 ANNUAL AVERAGE CHI/O (SEC/HETER CUBED)BEARING 5.000 7.500 10 F 000 DISTANCE IH HILES 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000S 6.115E-OS 2.587E-OS 1.261E-08 SSM 1.464E-07 6.300K-OS 3.271E-08 SM 2.935E 07 1.362E-07 7.090E-08 MSM 1,023E.06 5.046E 07 2.65SE.07 M 3.092K 07 1.387E-07 7.1C6E-O8 MKM 1.811E-07 8.629E 08 4.571E.08 KM 1.906E.07 9.287E.08 4.994E.OS NHM 1.770E 07 9.210E.08 4.9D1E.OS N 1.95SE 07 1.290E.07 6.522E.08 NNE 2.041E 07 1.035E-07 5.326E.OS NE 1.464E 07 7.655E.08 4.182K.OS EHE 8.193K.OS 4.255E.OS 2.602E.OS E 2.855E.OS 1.400E-OS 7.523K-09 ESE 2.155E-08 8.641E-09 4.722E-09 SE 2.293K-OS 8.326E.09 4.583E.09 SSE 3.897E.OS 1.467K-OS 7.833E-09 CHI/O (SEC/HETER CUBED)FOR KACH SEGHEHT 2.720E.09 1.146E-09 3.808E-10 1.940E-10 8.290K.11 5.269E 11 9.602K 09 4.030K-09 1.400E-09 6.542E 10 2.105E.10 1.342E-10 1.948E 08 9.124E.09 3.889E 09 2.149E 09 I.M3E 09 7.119E 10 6.978E.08 3.042E-08 1.033E 08 5.346K-09 1.941E 09 1.048E 09 1.842K.08 7.2S9E.09 1.910E.09 1.003K-09 3.360E.10 1.803E-10 1.436K.08 6.176E-09 2.194K.09 8.985K-10 1.305K.10 6.948E-11 1.635E-OS 6.513E-09 1.876E-09 8.526K-10 2.083E-10 1.109K 10 1.528E-OS 6.245E 09 1.969E 09 1.151E-09 6.166E.10 3.556E.10 1.651K-OS 7.573E 09 3.246E-09 1.529E 09 5.105E 10 2.812E-10 1.498E-OS 6.255E 09 2.164E.09 1.1C7E.09 4.991E.10 3.052E-10 1.489E-OS 5.949E-09 1.739E-09 9.116E-10 3.904E.10 2.279E-10 1.201E-08 6.039E-09 3.162E.09 1.631E-09 7.180E-10 4.284E 10 2.624K-09 1.262K.09 6.202E.10 2.996E 10 1.115K.10 6.369E 11 1.722E 09 8.665E 10 4.560E-10 2.076E.10 5.525E.I I 2.926E-11 1.687E-09 6.719E-10 2.061E-10 9.764E.11 3.400E-11 1.616E 11 2.704E-09 1.104K-09 3.690E-10 1.798K-IO 6.8SOE-11 3.887E-11 3.218E-11 2.672E-11 5.480E-11 4.561K.11 3.900E-10 3.264E.10 4.337K-10 3.653E 10 7.423K-11 6.223E-11 2.273E-11 1.895E 11 4.531E 11 3.775E-11 1.790E-10 1.491E.10 1.273E 10 1.058E.10 1.740E-10 1.445E.10 1.183E 10 9.844E.11 2.252K-10 1.873E.10 3.180K.11 2.633K.11 1.192E-11 9.902E-12 4.374E-12 3.625E.12 1.892E-11 1.567K.11 2.617E 07 6.349E.07 1.117E.06 3.C06E.06 1.123E-06 6.QOE-07 6.544E.07 5.805E.07 6.004E.07 6.670E.07 4.51CE.07 2.343E.07 1.023E.07 9.413K.OS 1.181E.07 1.876E 07 ELEVATED HIXED GR(RJKD LEVEL LESS THAN BETMEEN ABOVE;000.000 AND.000.000 DIRECTION.5.1 1-2 2-3 FROH SITE S 1.994E.06 6.497E-07 SSM 4.222E.06 1.470E.06 SM 7.269E.06 2.559E-06 MSM 1.930E 05 7.197E-06 M 8.399E.06 2.6C9E.06 MHM 4.378K 06 1.501E.06 NM 4.437K-06 1.515 E.06 NHM 3.685E 06 1.343E.06 N 3.629E 06 1.267E.06 NKK 4 lW&06 1 468K 06 KE 2.756E 06 9.694E 07 ENE 1.454K 06 5~111K 07 E 7.968K 07 2.46SE 07 ESE 8.320E 07 2 468K 07 SE 9.080K 07 3.026E.07 SSE 1.439E 06 4.5388.07 VENT ANO BUILDING PARAHKTERS:

RELEASE HEIGHT (HETERS)10.00 OIAHETER (HETERS).00 , EXI'T VELOCITY'H/BEC).00 AT THE RELEASE HEIGHTt VENT RELEASE IHXIE MIND SPEED (HETERS/SEC) 30.40 40.50 1.307E 07 3.175E 07 5.968E 07 1.901E 06 5.983K-07 3.466E 07 3.645E-07 3.150E-07 3.387E 07 3.708E 07 2.585K-07 1.399E 07 5.460E 08 4.804E 08 5.528K 08 9.452K 08 7.641E.OS 1.832E.07 3.609K-07 1.225E-06 3.758E-07 2.197E.07 2.312E 07 2.095E 07 2.25OE-07 2.435E.07 1.737E.07 9.653E 08 3 45CE-08 2.743E 08 2.969E 08 5.081E-M 2.782E-OS 6.807E.08 1.421E-07 5.137E-07 1.467K.07 8.931K-OS 9.551E 08 9.181E 08 1.155E 07 1.035E.07 7.664E.08 4.396E-08 1.436E.OS 9.769K 09 9.907K-09 1.703K-M 4.217K.09 1.226E.OS 2.QOE.08 9.584E.OS 2.526E-OS 1.769K-OS 1.944E.OS 1.876E.08 2.336E-OS 1.961E.OS 1.690K.08 1.247E-OS 3.108K.09 2.0088.09 1.879E-09 3.133E-09 5.100E-10 1.803E.09 4.589E.09 1.369E-OS 2.982E.09 2.738E.09 2.703E.O9 2.782E.09 3.713E.09 2.SCSE.09 2.531E.09 3.317E.09 6.Q2E.10 4.661E-10 2.869E-10 4.893K.10 1.031E-10 3.082E-10 1.246E 09 2.574K-09 4.673E-10 3.267E-10 3.553E-10 6.698K 10 7.141E-10 6.102K-10 4.774E-10 S.686E 10 1.C70E 10 S.887K-11 4.539E 11 8.912E-11 3.624E-11 7.493E-11 4.61SE-10 5.903E-10 1.012E-10 3.518K-11 6.193E-11 2.203K-IO 1.650E-10 2.020E 10 1.Q4E 10 2.714E-10 3.92%-11 1.Q1E 11 7.587E-12 2.3QE-11 REP.MIND'EIGHT (NETERS)10.0 BUILD IKG HEIGHT (HETERS)61 3 BLDG.HIN.CRS+

SEC.AREA (SO.HETERS) 2575.0 HEAT BIISSION RATE (CAL/SEC).0 AT THE HEASURED MIND HEIGHT (10.0 HETERS): VENT RELEASE IHXIE MIND SPEED (HETERS/SEC)

STABLE CNO IT IONS ELEVATED LESS THAN.000 HIXED BETMEEN.000 AKD GR(XJKD LEVEL ABOVE.000 MIND SPEED (HETERS/SEC)

UNSTABLE/NEUTRAL COKDITIONC LESS THAN.000.000 BETMEEN~000 AKD~OOC ABOVE.000 SEGHEHT BIJKDARIES IN HILES 3.4 4-5 5-10 10-20 20.30 53 l(!1 f3 S..I Page 4 of 5 Stean Electric FOR OPEN TERRAI Station-GR(XND-Lf VEL RELEASE.1992 N RECIRCULATION USING SPECIAL TERRAIN ADJUSTKEHT FACTORS RELATIVE DEPOSITIOH PER UHIT AREA (K e-2)AT FIXED POINTS BY DOMHMIHO SECTORS DISTANCES IN KILES.50.75 1.00 1.50 2.00 2.50 3.00 3.50 C.OO 4.50'.265E-OB 1'92E-08 7.200E 09 3.400E.09 2.009E-09 1.316E-09 8.715E-10 6.000E 10 4.442E-10 3.364E 10 3.112E-OB 1.696E 08 9.98CE.09 5.193E.09 3.097E 09 2.059E 09 1.351E.09 9.1S3E-10 6.712E-10 4.999E-10 3.591E-DB 2.074E.OB 1.274E.08 6.292E.09 3.745E.09 2.483E-09 1.677E.09 1.176E-09 8.687E 10 6.567E-10 5.355E-OB 3.323E 08 2.134E.08 1.078E.M 6.647E.09 4.551E.09 3.051E-09 2.121E 09 1.613E-09 1.260E.09 3.355E-OB 1.730E-OB 1.017E 08 4.774E.09 2.799E-09 1.827E 09 1.216E-09 8.423E-10 6.393E 10 4.947E-10 2.249E-OB 1.200E.DB 7.117E.09 3.590E.09 2.102E-09 1.364E.09 9.313E 10 6.644E.10 5.087E-10 3.979E-10 2.881E-OB 1.578E.08 9.296E.09 4.680E-09 2.765E-09 1.826E.09 1.278E 09 9.380E-'10 7.148E-10 5.569E.10 2 184E 08'1.216E 08 8.016E 09 3.832E 09 2.307E.09 1.549E-09 1.049E.09 7,385E 10 5.867E.10 Co770E 10 2.QCE 08 1.384E-OB S.033E 09 4.217E.09 2.546E-09 1.871E-09 1.282E.09 9.179E-10 7.1988-10$.771E-10 3.136E-OB 1.644E.OB 1.052E.08 5.076E.09 3.180E-09 2.219E.09 1.527E-09 1.099E.09 8.662E-10 6.982E 10 3.886E 08 2.095E 08 1.247E.DB 6.4COE 09 4.057E-09 2.833E 09 1.996E 09 1.474E 09 1.176E 09 9.599E 10 2.779E 08 1.487E 08 9.461E-09 4.588E.09 2.905E.09 2.047E.09 1.489E 09 1.132E-09 9.148E-10 7.591E-10 1.455E.OB 7.503E-09 4~251E.09 2.050E.09 1.238E-09 8.327E-10 5.741E-10 4.1C3E.10 3.211E'10 2 557E-10 1.453E.OB 7.520E.09 4.Z45E.09 1.983E.09 1.138E-09 7.261E.10 4.972E 10 3.561E.10 2.585E 10 1.914E 10 1.729E-OB 9.425E-09 5.765E.09 2.729E 09 1.594E-09 1.032E 09 6.646E 10 4.422E-10 3.145E-10 2.272E 10 2.469E-OB 1.325E.OB 7.523E.09 3.533E.09 2.1C3E-09 1.443E.09 9.725E-10 6.806E.10'4.795E-10 3.C02E.10 DISTANCES IH KILES 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 1.057E-10 5-13CE-11 1.081E-11 4.418E-12 1.426E 12 7.075E-13 2.951E.13 1.836E 13 1.100E-13 8.977E-14 1.573E-10 8.056E-11 2.275E-11 9.181E-12 3.078E-12 1.393E-12 4.358E-13 2.711E.13 1.083E-13 8.837E.14 2.181E-10 1.099E-10 2.832E.11 1.253E-11 5.084E-12 2.692E-12 1.308E 12 8.322E.13 4.432E-13 3.617E 13 4.322E 10 2.153E-10 5.1C1E 11 2.074E-11 6.606E.12 3.239E.12 1.122E 12 5.818E-13 2.324E-13 1.897E-13 1.567E-10 7.7C9E-11 1.853E.11 6.882E.12 1.709E.12 8.572E-13 2.759E 13 1.430E.13 5.711E-14 4.662E-14 1.387E-10 7.186E-11 2.149E.11 8.824E-12 3.010E-12 1.190E-12 1.675E 13 8.685E 14 2.775E-TC 2.265E-14 2.011E-10 1.062E-10 3.328E.11 1.270E-11 3.518E-12 1.545E-12 3.664E-13 1.899E.13 7.585E 14 6.191E-1C 1.853E-10 9.665E-11 2.875E-11 1.124E-11 3.407E-12 1.924E-12 1.000E 12 5.615E.13 2.76OE-13 2.253E-13 3.037E.10 1.517E.10 3.710E-11 1.641E 11 6.804E-12 3.112E.12 1.013E-12'.450E.13 2.419E'13 1.974E 13 2.683E-10 1.368E 10 3.730E-11 1.505E 11 5.046E-12 2.599E 12 1.103E 12 6.597E 13 3.689E 13 3.011E 13 3.843E.10 2.087E-10 7.220E 11 2.789E 11 7.896E-12 4.020E.12 1.677E.12 9.562E.13 4.861E-13 3.968E-13 3.045E-10 1.857E.10 8.365E.11 4.075E.11 2.070E-11 1.038E-11 4.455E.12 2.598E-12 1.337E-12 1.091E-12 9.732E-11 5.275E 11 1.826E.11 8.62ZE 12 4.150E-12 1.965E.12 7.177E.13 4.030E 13 1.981E-13 1.617E-13 5.689E-11 3.115E 11 1.115E.11 5.460E-12 2.796E-12 1.240E-12 3.223E-13 1.671E.13 6.673E-14 5.447E-14 6.075E-11 3~361E-11 1.222E.11 4.765E-12 1.429E-12 6,627E-13 2.262E.13 1.055E.13 2.810E 14 2.293E-IC 9.475E-11 5.096E-I I 1.744E-11 6.982E-12 2.286E-12 1.092E-12 4~101E-13 2.277E.13 1.091E-13 8.909E-14 RELATIVE DEPOSITION PER UNIT AREA (K~~2)BT OOMHMIND SECTORS SEGKEHT B(XIHDARIES IN KILES 2.3 3.4 4 5 5-10 30-40 DIRECTION FROH SITE S SSM SM MSM M MHM~NM NNM H HNE NE ENE E ESE'E SSE DIRECTION FROI SITE S SSM SM MQI M MNM NM NHM N NHE NE ENE E ESE SE SSE.25 6.452E.OS 9.324E.OB 1.051E 07 1.505E 07 9.794E-DB 6.6Z4E-OB 8.521E 0$.6.072E 08 7.861f-08 8.405E-08 1.128E 07 8.184E.OB 4.2S4E.DB 4.51CE.OB 5.155E.OB 6.975E 08 5.00 2.679E 10 3.981E 10 5.257E-10 1.01CE.09 3.956E.10 3.209E 10 4.517E.10 3.913E-10 5.004E 10 5.725E-10 7.907E.10 6.279E.10 2.092E.10 1.509E.10 1.773E 10 2.658E.10 1ttOHII~O~10000t 40.50 20.30 10-20 DIRECT IOH.5 1 1-2 FROH SITE S 1.221E-OB SSM 1.701E.OB SM 2.056E.OB MSM 3.246E.08 M 1.774E.OB MNM 1.216E.OB NM 1.579E-DB NNM 1.2C7E.OB H 1.404E.OB NNE 1.712E 08 NE 2.116E.OB ENE 1.534E 08 f 7.624E.09 ESE 7.623E 09 SE 9.546E 09 SSE 1.325f 08 VENT AND BUILDING P RELEASE HEIGHT DIANE TER EXIT VELOCITY 6.182E.10 9.468E-10 1.202E-09 2.193E.09 8.717E.10 6.814E 10 9.502E-10 7.694E.10 9.4QE.10 1.133E-09 1.509E 09 1.151E 09 4.244E.10 3.592E.10 4.571 E-10 6.874E-10 3.626E-09 5.326E-09 6.592E 09 1.129E.OB 5.095E-09 3.712E.09 4.855E 09 4.084E-09 4.322E-09 5.443E 09 6.7228-09 Ci923f 09 2.1788.09 2~1'IOE 09 2.899f-09 3.802f 09 ARAKE TERS t (i%TERS)(%TERS)(K/SEC)3.430E 10 5.130E-10 6.710E-10 1.274E.09 5.008E-10 4.022E-10 5.647E-10 C.778E 10 5.910E 10 7.014E.10 9.612E.10 7.566E-10 2.578E 10 1.9QE-10 2.346E 10 3.539E 10 1.176E-10 1.767E-10 2.384E-10 4.652E-10 1.746E-10 1.495E-10 2.146E-10 1.917E-10 2.799E-10 2.775E-10 3.966E 10 3.235E-10 1.024E-10 6.Q5E-11 7.459E 11 1.133E 10 1.323E-09 2.053E.09 2.497E.09 4.510E.09 1.842E-09 1.388E.09 1.857E-09 1.551E-09 1.815E-09 2.198E.09 2.82SE.09 2.053E.09 8.372E 10 7.445E-10 1.035E.09 1.441E-09 1.936E.12 4.032E 12 6.112E 12 9.029E 12 2.748E.12 3.832E.12 5.176E 12 C.903E-12 7.8888-12 6.73SE.12 1.168E-11 2.192E.11 4.4688.12 2.884E 12 2.012E-12 3.061E 12 1.698E-11 2.957E.11 3.943E.11 7.419E.11 2.646E.11 2.705E-11 C.034E.11 3.606E.11 5.338E.11 4.953E.11 8.284E 11 8.725E-11 2.164E.11 1.307E.11 1.366E-11 2.024E-11 3.704E-13 6.465E-13 1.522E-12 1.521E-12 3.913E-13 4.289E-13 6.3S9E 13 1.097E-12 1.434E-12 1.361 E-12 2.072E 12 S.441E-12 9.542E 13 5.254E 13 3.049E 13 5.355E-13 1.243E-13 1.491E-13 5.283E-13 3.201E-13 7.867E-14 C.337E-14 1.045E-13 3.418E-13 3.152E-13 4.299E 13 5.923E-13 1.620E-12 2.454E 13 9.192E-14 4.912E-14 1.369E.13 10.00.00.00 REP MIND HEIGHT (KETERS)10.0 BUILD ING HEIGHT (KETERS)61.3 BLDG.NIN.CRS.SEC.AREA (SO.KETERS) 2575.0 HEAT EK I SS ION RATE (CAL/SEC).0 AT THE IIEASURED MIND HEIGHT (10.0 KETERS)t VENT RELEASE KOOE'MIND SPEED (KETERS/SEC)

STABLE CNOITIONS ELEVATED LESS THAN.000 HIXEO BETME EN.000 AND AT THE RELEASE HEIGHT VENT RELEASE K(X)f MIND SPEED\'ELPOTEO LESS THAN IIIXED BHMEEN (KETERS/SEC)

MIND SPEED (KETERS/SEC)

UNSTABLE/NEUTRAL CONOI TI(HIS LESS THAN~000.000 BETMEEN.000 AND.000.000~000 AND.000 GR(X%0 LEVEL ABOVE.000 GR(RIND LEVEL ABOVE.000 ABOVE.000 54 0'K k'6", K Pp gl gl' Page 5 of 5 GRQJNO~LEVEL RELEASE.1992 Suaquehsme Steaa Electric Stet(on SPECIFIC POINTS OF INTEREST ORELEASE TTPE OF DIRECTION ID LOCAT ION: UNDEPLETED UKDEPLETED 3.561E-OB 4.066E.OB 1.541E 08 1.864E.OB 1.062E 08 1.645E~08 l.741E.08 1.844E.M 2.069E-08 1.440E.OB 2.923E.OB 2.656E.OB 1.180E-08 1.368E.OB 2.256E.OB 3.956E.OB 7.200E.09 9.984E 09 6.289E.09 1.813E-OB 7.010E.09 1.306E-OB 1.460E.08 1.640E.OB 5.297E-09 1.223E.OB 3.241E.09 2.687E.09 2.331E.09 1.452E.OB 2.489E.OB 1.852E.OB 2.340E.OB 6.044E-09 7.435E.09 4.113E.09 1.813E.08 4.772E.09 4.576E.09 3.409E.09 5.866E 10 1.117E.09 6.576E 09 3.241E.09 2.496E.09 2.331E.09 8.748E 10 2.489E.OB 9.535E.09 4.701E.10 1.350E 09 1.274E.09 9.1C9E-10 7.563E.10 2.290E-11 6.644E.09 3.954E.10 2.555E.09 5.374E 10 1.036E 09 2.556E 10 2.457E 10 6.211E.10 2A27E-10 1.734E-10 9.627E.10 1.448E.09 3.21CE.10 6.090E-06 1.061E-OS 6.113E-06 1.275 E.05 5.901E.06 6.482E-06 5.355E.06 5.923E-06 5.791E.06 3.914E.06 4.161E-06 2.702E-06 1.323E-06 1.606E-06 2.224E.06 4.371E.06 1.404E.06 2.972E.06 2.928E.06 1.261E.DS 4.090E 06 5.198E.06 4.652E 06 5.280E 06 1.789E.06 3.440E 06 6.294E.OT 3.637E.OT 3.105E.07 1.699E 06 2.C47E-06 2.191E-06 3.392E.06 1.205E 06 2.318E.06 2.069E.06 1.261E 05 2.985E-06 2.132E.06 1.3CSE.06 3.275E-07 5.013E.OT 2'47E.06 6.294E.07 3.421E.07 3.105E.07 1.377E.07 2.447E-06 1.252E.06 1.332E-07 5.557E.OT 5.303E.OT 3.976E.OT 3.388E.OT 1.555E.OB 5.645E-06 4.185E.OT 1.318E.06 3.063E.OT 1.653E 07 4.556E.OB 4.4088.08 9.9758.08 4.390E-08 3.271E.08 1.USE-07 8.986E-07 5.595E 07 549.664.1338.1651.1634.990.1038.944.946.1260~984.859.848.827.671.549.1609.1609.2415.1770.1931.1127., 1287.966.2092.1448.3702.3381.2253.805.644.966.1127.1770.1931.3059.1770.2415.2092.2898.6438.5151.2092.3702.35C1.2253.4024.644.1448.6277.'829.4990.5634.6117.22536.3220.8049.2895.6760.5955.7244.7405.4346.6599.7566.4185.5151.13360..34.41.53 1.03'1.02.62.65.59.59.78.61.53.53.51.42.34 1.00 1.00 1.50 1.10 1.20.70.80.60 1.30.90 2.30 2.10 1.40.50.40.60.70 1.'10 1.20 1.90 1.10 1.50 1.30 1.80 4.00 3.20 1.30 2.30 2.20 1.40 2.50.CO.90 3.90 3.00 3.10 3.50 3.80 14.00 2.00 5.00 1080 4.20 3.70 4.50 4.60 2.70 4.10 4.70 2.60 3.20 5.30 5.678E 06 9.791E.06 6.080E 06 1.058E.05 6.082E-06 1.267E-OS 5.863E.06 6.457E.06 5.337E-06 5.902E.06 5.772E.06 3.898E.06 4.149E 06 2.697E.06 1.321E.06 1.604E.06 2.221E.06 4.366E.06 1.397E.06 2.955E.06 2.901E 06 1.253E 05 4.058E 06 5.175E-06 4.629E.06 5.261E 06 1.775E-06 3.423E-06 6.227E.OT 3.607E.OT 3.090E.OT 1.696E.06 2.444E.06 2.187E 06 3.351E-06 1.199E.06 2.302E.06 2.045E 06 1.253E-OS 2.956E.06 2.114E-06 1.331E 06 3.199E.07 4.921E.DT 2.033E.06 6.227E.OT 3.392E.07 3.090E-OT 1.365E.OT 2.444E.06 1.248E.06 1.307E.OT 5.464E.OT 5.211E.07 3.899E.OT 3.316E.OT 1.436E.OB 5.573E.06 4.051E 07 1.303E.06 2.985E.07 1.629E.07 4.483E-08 4.336E-OB 9.882E-OB 4.327E-DB 3.217E.OB 1.372E.OT 5.511E-OT 5.307E.07 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S SITE BQJKDARY SITE BQKIDARY SITE BOUNDART SITE BQJHOARY SITE BQJKDARY SITE BQINOART SITE BQJKDARY SITE BQJNDARY SITE BQJNDART SITE BQJKOARY SITE BQJNDARY SITE BQJNDARY SITE BOUNDARY SITE BQJKDARY SITE BQJKOARY SITE BOUNDARY RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIOEKCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDENCE GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN CARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GAROEH CARDEN DAIRY DAIRY DAIRT DAIRY DAIRY OAIRT DAIRT DAIRY DAIRY DAIRT DAIRT DAIRY DAIRY DAIRT DAIRT DAIRT DAIRY I RR I CATION I RR I CATION BUILDING PARAHETERS HEIGHT (HETERS)TER (HETERS)VELOCITT (H/SEC)S SQI QI MSM'N MNN N'N NN'N N NHE HE EHE E ESE SE SSE S SSM SN MSM M MNM NM NNM N HNE NE EHE E ESE , SE SSE HE S SSM QI MSM M MNN NM NHM N NNE NE ENE E ESE SE SSE S SSM SQI SQI SSN SQI MSM M ISN KHM ENE E E ESE ESE ESE SE SM MSM 10.00.00.00 S.407E-06 1.112E.OS 5.151E.06 5.835E.06 4.809E.06 5.349E-06 5.229E.06 3.475E.06 3.748E-06 2.456E.06 1.204E-06 1.464E.06 2.052E 06 4.076E-06 1.227E.06 2.597E.06 2.480E-06 1.095E 05 3.527E.06 4.644E.06 4.124E.06 4.761E-06 1.533E 06 3.028E.06 5.126E 07 2.990E.07 2.648E.OT 1.551E 06 2.263E.06 1.977E.06 3.031E-06 1.046E.06 1.999E 06 1.716E-06 1.095E.OS 2.528E-06 1.827E-06 1.121E-06 2.499E 07 3.932E.07 1.755E.06 5.126E 07 2.801E.07 2.648E.07 1.112E-07 2.263E-06 1.102E.06 1.020E-07 4.393E.OT 4.176E-07 3.085E.07 2.601E-07 9.588E.09 4.657E 06 3.091E-07 1.0988-06 2.320E-OT 1.276E-OT 3.429E-OB 3.307E-05 7.993E.OB 3.346E-OB 2.447E-08 1.113E.07 7.046E-07 3.822E-OT VENT AND RELEASE DIA%EXIT REP.MIKO KEIGHt (HETERS)10.0 BUILDING KEIGHT (HETERS)61.3 BLOC.HIN.CRS.SEC.AREA (SO.HETERS) 2575.0 HEAT EHISSION RATE (CAL/SEC).0 AT'tHE HEASURED MIND HEIGH'I (10.0 HETERS): VENt RELEASE HCOE MIND SPEED (HETERS/SEC)

STABLE CONDITIONS ELEVATED LESS THAN F 000 HIKED BETMEEN.NO ANO.000 GROUND LEVEL ABOVE.000AT THE RELEASE HEIGHT: VENT RELEASE NODE MIND SPEED (HETERS/SEC)

MIND SPEED (HETERS/SEC)

UNSTABLE/NEUTRAL COKDITIOHS LESS THAN.000.BETMEEN.000 AKD.000 ABOVE.000 ELEVATED LESS THAN.000 HIKED BETMEEN.000 ANO CRQJND LEVEL ABOVE.NO.000 55 D I StANCE X/O X/0 x/a 0/O (HILES)(HETERS)(SEC/CUB.HETER)(SEC/CUB.HETER)(SEC/CUB.HETER)(PER SO0HETER)KO DECAY 2.260 OAY DECAY.5.000 DAY DECAY DEPLETED SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 56

'!<4v t~e l4~'gA adiolo ical Im act on lan Sampling and analysis of airborne and waterborne effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (LLD)outlined in the SSES Technical Specifications.

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 monthly averaged river flow dilution factors resulted in estimated doses'to individuals at levels below 10 CFR 20 and 10 CFR 50, Appendix I limits.Direct radiation resulting from plant operation, as measured by environmental thermoluminescent dosimeters located around the plant, did not contribute any measurable dose to members of the public for the reporting period.This was based on a quarterly comparison of 1992 average (indicator) results to the 1+9-1981 preoperational average (control)values.In all cases the 1992 data was not significantly different from the preoperational average at the 95'onfidence level.Since there are no other fuel cycle sources within 8 km of SSES, 40 CFR 190 limits were not exceeded.Summaries of maximum individual doses resulting from airborne and waterborne radioactive effluent releases are given in Table 21.Heteorological data from Section 3 were used to calculate the dose from airborne effluents.

Technical Specification 6.9.l.ll requires assessment of radiation doses from radioactive airborne and waterborne effluent to members of the public within the site boundary.There are no significant exposure pathways from waterborne effluents in these areas.Onsite doses are assessed relative to offsite dose values and are adjusted for appropriate dispersion and occupancy factors.Summaries of the calculated maximum onsite doses resulting from airborne effluents are presented in Tables 22 through 25.57

\1/4 I ,P!C.Ki TABLE 20 SUNNARY OF NAXINUN,INDIVIDUAL OFFSITE DOSES AND DOSE CONNITNENTS TO NENBERS OF THE PUBLIC DATA PERIOD: 1/1/92 TO 12/31/92 EFFLUENT LIQUID APPLICABLE ORGAN CHILD TOTAL BODY EST I HATED NAXIIRBI Dosd" (NREM)1.41E-03 LOCATISI DIST AFFECTED (NI LES)SECTOR DAHVILLE, PA PERCENT OF LINIT 0.02 LINIT (NREN)"'IQUID CHILD LIVER 1.51E-03 DAHVILLE, PA 0.01 10 NOBLE GAS NOBLE GAS N/A N/A AIR DOSE (GAHHA-HRAD)

AIR DOSE (BETA-HRAD) 8.17E-03 2.43E-02 1.03 1~03'MSM 0.04 0.06 10 20 NOBLE GAS NOBLE GAS IOOIHE AND PARTICULATES H/A TOTAL BODY H/A SKIN CHILD LUNG 4.76E-03 1.34E-02 1.10E-01 1.03 MSM 1.03 MS'M 1.10 MS'M 0.05 0.04 0.37 15"'Estimated dose is based on a site total activity release.~10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

AIRBORNE PATHMAYS ANALYZED: 1.03 (MSM)PLUHE, GROUHD, IHHALATIOH, DIRECT 1.10 (MSM)PLUHE, GROUHD, VEGETATIOH, IHHALATIOH, DIRECT MATERBORNE PATHMAYS ANALYZED: FISH, DRINKING'MATER, SHORELINE The maximsa calculated dose from all 1992 SSES waterborne effluents at Danville, PA was 1.51E-03 mrem (CHILD, LIVER).The maxisxsa calculated dose from all 1992 SSES airborne effluents at 1.03 miles (MSM sector)was 5.34E-02 mrem (TEEN, SKIN)~The maxisua calculated dose from all 1992 SSES airborne effluents at 1.10 miles (MSM sector)was 1.21E-01 mrem (CHILD, SKIN).58 4<<C DOSES TO MEMBERS OF THE PUBLIC WITHIN THE SITE BOUNDARY SSES Technical Specification 6.9.1.11 requires that the Semiannual Effluent Release Reports include an assessment of the radiation dose from radioactive effluents to members of the public within the site boundary.Within the SSES site boundary there are seven areas which are open to members of the public (See Figure 8):~The Susquehanna Riverlands Recreation Area/Energy Information Center~Residences in the north-northeast, east southeast, southeast, west southwest', west, west northwest and north northwest sectors In the area comprising the Riverlands recreation area, which surrounds the Energy Information Center, four pathways of radiation exposure can be identified; plume, ground, inhalation, and direct radiation.

There are no significant exposure pathways from.waterborne effluents in this area.There are approximately 100,000 visitors to the Riverlands/Information Center complex each year.In order to facilitate dose calculations, it is assumed that each visitor stays in the area for one hour.Use of the GASPAR code yields calculated doses for the Riverlands area for the report period.These doses are the total doses at the location from gaseous effluents during the report period.In order to compute doses to members of the public who stay for only short periods of time, these doses are converted to dose rates.Taking into account the estimated 100,000 person-hours of occupancy, the collective (person-rem) doses shown in Table 21 are calculated.

Calculated doses for residences within the SSES site boundary for the following sectors are presented in Tables 22 through 25.~north northeast (0.90 miles)~east southeast (0.50 miles)~southeast (0.40 miles)~west southwest (1.10 miles)~west (1.20 miles)~west northwest (0.70 miles)and~north northwest (0.60 miles)59

~i 4 C.~II S 0 TABLE 21 CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/INFORMATION CENTER COMPLEX Data Period: 1/1/92-12/31/92 EFFLUENT AGE GROUP APPLICABLE ORGAN MAXIMUM DOSE RATE>>MREM HR COLLECTIVE DOSE PERSON-REM NOBLE GAS N/A TOTAL BODY 1.44E-07 1.44E-05 NOBLE GAS N A SKIN 4.06E-07 4.06E-05 IODINE AND PARTICULATES TEEN SKIN 2.68E-06 2.68E-04 10 CFR 50, Appendix i limits are in terms of mrad or mrem/reactor-year.

Estimated maxima dose rate is based on a site total activity release.PATHWAYS AHALYZED: PLUHE, GROUHD, IHHALATlOH, DiRECT 60 I I rl'J L't WNW e I~ppeL property the a~a I I I I , 3249~W erne~l 4134 I\T~re~ence PPEL le 3f DS 3ai8 3228 I arrrarstrsea I ldrrttNerN I I I free I 5@f8 Errerusap Opoa5oQ~~ee f r PS~I tJ~~a e r qe 281 ,~278f t~e'~L.~par 8 I I CL<etretcn Et Ir~a A I I I~PPEL Property Une~w a~>a%le~+I, I~I I I I S SE-SUSQUEHANNA STEAN ELECTRIC STATION SITE BOUNDARY DISTANCES (DISTANCES IN FEET)ENNSYLVANIA POWER&LIIRHT COMPANY HALUBURTON NUS Envtronmantal Corp.DECEMBER 10, 1992 61.LEGEND r~'PAL Property Boundary Sector Wtteel (22.5-derjree)

I Roade Raiiroade Qg Residence Scale in Feet 0 500l000 2000 ls 4;e I~C'I~q, 1 TABLE 22 CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.90 NILES NNE SECTOR Data Period: 1/1/92-12/31/92 EFFUKNT EST INATED NAX IIRHI DOSE (%EN)PERCENT OF LINIT LINIT (IBLEN)NOBLE GAS N/A TOTAL B(OY 1.28E.03 0.01 NOBLE GAS M/A SKIN 3.61E.03 0.01 15 IODINE AND PARTICULATES TEEN LUNG, SKIN 1.58E.02 0.05 15 10 CFR 50, Appendix I Limits are in terms of mrad or mrem/reactor-year.

'Estimated maximum dose rate is based on n site total activity release.PATHNAYS ANALYZED: PLLHIE, GRImHD, INHALATIOH, DIRECT The maxiaam calculated dose from all 1992 SSES airborne effluents at this Location was 1.94E-02 mrem (TEEN, SKIN).CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.50 WILES ESE SECTOR DATE PERIOD: 1/1/92 TO 12/31/92 EFFLtKNT NOBLE GAS NOBLE GAS N/A N/A TOTAL BODY SKIN EST INATED NAXIMHI DOSE ()BIEN)6.34E-04 1.79E-03 PERCENT OF LINIT 0.01 0.01 LINIT (IBEN)15 IODINE AND PARTICULATES ADULT, TEEN SKIN 1.37E.02 0.05 15 10 CFR 50, Appendix I limits are in terms of mrnd or mrem/reactor-year.

~Estimated mnxiaass dose is based on a site total activity release.PATHMAYS ANALYZED: PLQIE, GROUND, INHALATIOH, DIRECT The mnxlsasa calculated dose from all 1992 airborne ef f Luents at this location Has 1.55E-02 mrem (ADULT/TEEN, SKIN).

~~

TABLE 23 CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.40 WILES SE SECTOR DATA PERIOD: 1/1/92-12/31/92 EFFUKNT NOBLE GAS NOBLE GAS I(X)INE AND PARTICULATES N/A N/A'EEN TOTAL BMY SKIN SKIN ESTINATED NAXIIRN DOSE (IRBI)9.13E-04 2.57E-03 2.26E-02 PER CHIT OF LINll'.01 0.01 0.08 LINIT (IBIBI)15 15 10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

<<Estimated maxiaua dose is based on a site total activity release.PATHMAYS ANALYZED PLUHE~GROUND~INHALATION

~DIRECT The maxiaam calculated dose from all 1992 airborne effluents at this location uas 2.51E-02 area (ADULT/TEEN, SKIN).CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 1.10 NILES WSW SECTOR DATA PERIOD: 1/1/92 TO 12/31/92 EFFLLKIF NOBLE GAS NOBLE GAS ICOINE AND PARTICULATES N/A N/A CHILD SKIN 1.32E-02 LUNG 1.10E-01 EST I HATED NAXIIRSI DOSE (IRIEN)TOTAL BODY 4.69E.03 PERCENT OF LIIIIT 0.05 0.04 0.37 LINIT'IBW 15 15 10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

<<Estisated dose is based on a site total release.PATHMAYS ANALYZED: PLQIE, GROUND, VEGETATION, INHALATION, DIRECT The mexisua calculated dose from all 1992 SSES airborne effluents at this location Has 1.21E.01 mrcm (CHILD, SKIN).63 Y~~h ir~" e N<<a TABLE 24 CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 1~20 NILES W SECTOR DATA PERIOD: 1/1/92-12/31/92 EFFUKNT NOBLE GAS NOBLE GAS N/A N/A APPLICABLE ORGAN TOTAL BtSY SKIN EST INATED NAXIIRM DOSE (iaEN)1.52E.03 4.29E 03 PERCENT OF LINIT 0.02 0.01 LINIT (I%EN)15 IODINE AHD PARTICULATES TEEN LUNG 1.42E.02 0.05 15 10 CFR 50, Appendix I limits are in terms of mrad or mrea/reactor-year.

Estimated maxiaasa dose rate is based on a site total activity release.PATKNAYS ANALYZED: PLUHE, GROUND, INHALATIOH, DIRECT The maxiaMa calculated dose from all 1992 SSES airborne effluents at this location was 1.?BE-02 mrea (ADULT/TEEN, SKIN).CALCULATED DOSE FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.70 MILES WNW SECTOR DATA PERIOD: 1/1/92 TO 12/31/92 EFFLIKNT NOBLE GAS NOBLE GAS IODINE AND PART I CULATES N/A N/A TEEN APPLICABLE ORGAN TOTAL BODY SKIN LUNG ESTINATED NAXIIRRI DOSE (I%EN)1.94E.03 5.46E-03 2.07E.02 PERCENT OF LINIT 0.02 0.02 0.07 LINIT (NREN)15 15 10CFR50, Appendix I limits are in terms of mrad or mrem/reactor-year

Estimated dose is based on a site total activity release.PATHNAYS ANALYZED: PLWE, GRQlMD, INHALATION, DIRECT The maxiaua calculated dose from all 1992 SSES airborne effluents at this location Has 2.56E-02 mrem (TEENt SKIN).

TABLE 25 CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.60 NILES NNW SECTOR DATA PERIOD: 1/1/92-12/31/91 EFFLlKNT NOBLE GAS NOBLE GAS N/A N/A APPLI CABLE ORGAN TOTAL BCOT SKIN EST lllATED WLXWI DOSE (I%BI)1.97E-03 5.55E 03 PERCENT OF LTN!T 0.02 0.02 LINIT (IRE)I)15 1N)1NE AND PARTlCULATES TEEH LUNG 2.28E-02 0.08 15 10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

Estimated maxiaun dose rate is based on a site total activity release.PATNMATS ANALTZED: PL(RE, GROUND, lNHALATlON, DIRECT The maxlaua calculated dose from all 1992 SSES airborne effluents at this location Mas 2.81E-02 mrem (ADULT, TEEN, SKlN).65 kl g>>Z>>A ll'pg C 6'4 DOSE ASSESSNENT FOR ABNORNAL GASEOUS RELEASE ON 11/12/92 Desc i tion of Event: As a result of routine sample collection from t)e Auxiliary Boiler system, short-lived activation gases (F'nd N'were discovered.

Thy preseng of N'nd the absence of activation products such as Co and Mn indicated that the Aux Boiler contamination occurred via main steam.The sour'ce of the contamination was traced to the Unit 1 main steam supply to the Steam Jet Air Ejector, which was leaking past HV 10752 and check valve 107027.(HV 10752 was in the closed position).

The remainder of the flow path is through ST 10702 to the Aux Boiler Deaerator.

Subsequent sampling showed the activity decreasing due to decay, becoming less than detectable by ll/13/92.One sample of the Aux Boiler Deaerator vent collected on the radwaste building roof (where the'ent exits the turbine building)showed Xe-135 activity.A follow-up sample at this location showed less-than-detectable activity.This event was investigated under Significant Operating Occurrence Report 1-92-352.At the time of the event, Unit 2 was nearing start-up;soon after the event, Unit 1 scrammed.With both units down, the Aux Boiler contamination quickly decayed to background levels.Nothing had been done, however, to correct the steam leak during operation, and it was not easy to identify and to correct the leak with the units out of service.Safety Evaluation NL-92-032 was written to permit use of the Aux Boilers as a contaminated system to support start-up.To ensure minimal offsite doses, the Safety Evaluation required shutdown and cooldown of the Aux Boilers if offgas pretreatment release rates exceeded 1000 uCi/second.

Calculation of Source Term and Offsite Dose Samples from the Aux Boiler and Deaerator vent confirm contamination in a normally uncontaminated system, and an unmonitored release.These samples, however, do not provide enough information to quantify the release.The path of contaminated steam flowed into the Aux Boiler Deaerator.

Since the Deaerator removes noncondensible gases (air, oxygen, xenons, kryptons), and discharges them through its vent, fission gases from main steam would have been released rather than dissolving in Deaerator or Aux Boiler condensate.

Since no information was available to indicate the amount of steam leaking into the Aux Boiler, and thus the fission gas release source term, pure main steam was conservatively assumed through the unmonitored release point.The total release was calculated assuming a period of eight (8)days and five (5)hours, estimated for the time the Aux Boilers were in service since they were last known to be uncontaminated through sampling on 10/29/92.The following fission gas source term was determined for the event: 66 pt~')I T.IS+lP (

Nuclide Kr-90 Xe-139 Kr-89 Xe-137 Xe-138 Xe-135m Kr-87 Kr-83m Kr-88 Kr-85m Xe-135 Xe-135m Xe-133 Xe-131m Kr-85 Release Rate uCi sec 2.11E-07 2.08E-06 1.15E-03 2.33E-03 2.47E-03 3.95E-04 2.61E-04 4.14E-05 1.92E-04 4.51E-05 1.11E-07 5.33E-07 8.18E-06 8.88E-09 4.67E-10 Total Release Uci 1.51E-01 1.48E+00 1.07E+03 1.65Ew03 1.75E+03 2.80E+02 1.85E+02 2.94E+01 1.36E-02 3.20E+01 7.87E-02 3.78E-01 5.80E+00 6.30E-03 3.31E-04 The sum of twenty-two (22)fission product gases produced a release rate of 7.37 E-3 uCi/second.

Typical LLD release rates from the five monitored vents are in the range 50-70 uCi/second.

This release rate, therefore, yields only a small fraction of the value at which routine releases would be determined as being above the minimum detection level.Using this fission gas source term and a conservative meteorological data set, an offsite dose calculation was performed using GASPAR.The total body dose determined at the maximum site boundary X/g=2.12 E-5 mrad, which is insignificant compared to Tech.Spec.3.11.2.2.a quarterly limit of 5 mrad.The skin dose calculated at the maximum site boundary X/g 5.54 E-5 mrad.which is also of noconsequence compared to Tech.Spec.3.11.2.2.a quarterly limit of 10 mrad.Given that this release was not continuous throughout the year, the annual total body dose rate (2.12 E-5 mrad/197 hr*8760 hr/yr-9.78 E-3 mrad/yr)is insignificant compared to Tech.Spec.3.11.2.1.a limit of 500 mrem/yr.The annual skin dose rate (5.54 E-5 mr ad/197 hrs*8760 hr/yr 2.46 E-3 mrad/yr)is also of no consequence compared to Tech.Spec.3.11.2.1.a limit of 3000 mrad/yr.67 SECTION 5 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL AND THE SOLID WASTE PROCESS CONTROL PROGRAM 68 K,~Ih h

.CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The SSES ODCM was revised twice during the reporting period.The first revision, November 25, 1992, documented changes to sampling stations pursuant to Technical Specification 3.12.Ic and 3.12.2b.Changes occurred to either the actual monitoring locations or to the descriptions for such locations for airborne, direct radiation and milk sampling: Milk sampling location 12D2 was deleted from Table 6 and Figure 6 because the farmer terminated the dairy business in July, 1992.Location 10D1, which is located 3.0 miles SSW of the SSES, replaces 12D2 as a monthly and semi-monthly sampling location.The location designation of air sampling station 12S2 was changed to 12Sl to ensure consistency in the assignment of such designations.

TLD monitoring location 3G5, the Parish Street Substation in Wilkes-Barre, replaces the former location 3G3, the Horton Street Substation.

This change was necessary due to PCB contamination at the former location.Both locations are in the NE sector and are essentially the same distance (16.0 miles)from the SSES.The position of TLD monitoring station 13S2 in Figure 5 has been changed to reflect correctly its location east of the road.No change to the actual monitoring location has been made.Figure 5 has also been changed to reflect the site boundary placement to the northeast (Sector 3: Gould Island)and the south (Sector 7)more accurately.

Additionally, the setpoint description of the main condenser offgas pre-treatment monitor was changed in the 11/25/92 revision, to specify basis in Tech.Spec.3.11.2.7 noble gas release rate of 330 millicuries/second.

The second revision to the ODCM (12/4/92)concerned correction and addition to the Maximum Pathway Dose Factor listings (Table 4): A correction to the Maximum Pathway Dose Factor (Page 4-1)for gaseous tritium was submitted.

The basis for this correction, which was made for the H-3/vegetation ingestion pathway, is discussed in file document PLI-72980 (11/24/92).

The Maximum Pathway Dose Factor table for I-134 was submitted as an addition (new page 4-29).Although the offsite dose from I-134 would not be the subject of routine operational dose calculations, due to its short half-life (52.5 minutes), the isotope is considered in certain design basis effluent dose calculations.'-

134 was included to permit consistency in calculations performed using certain design basis source terms.Tables for subsequent isotopes have been renumbered to accommodate the addition of I-134.'9 PENNSYLVANIA POWER 5 LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL Prepared By Date Reviewed By Supervisor-Environmental Services Nuclear Date I 2~02-/7 Reviewed By Zo A49W~y'cting o.Approved By Hanager-Nuclear Technology Date Date/I 1S 0~Pj.'A pC ti~e:

SUNNARY OF ODCM CHANGES l Milk sampling location 1202, the Dagostin Farm, was deleted from Table 6 and Figure 6 because the farmer quit the dairy farming business in July 1992.Location 10D1, the Ryman Farm, which is 3.0 miles SSW of the SSES replaces 12D2 as a monthly and semi-monthly sampling location.The location designation for the air sampling location 12S2 was changed to 12S1 in the interest of ensuring consistency in the assignment of such designations.

TLD monitoring location 3GS, the Parrish Street Substation in Wilkes-Barre, replaces the former location 3G3, the Horton Street Substation.

This change was necessitated as a result of the PCB contamination at location 3G3.Both locations are in the Nf sector and essentially the same distance, 16.0 miles, from the SSES.The position of TLD monitoring station 13S2 in Figure 5 has been changed to reflect correctly its location east of the road.No change to the actual monitoring location has been made.Figure 5 has also been changed to reflect the site boundary placement to the northeast (Sector 3: Gould Island)and to the south (Sector T)more accurately.

The setpoint description for the main condenser offgas pre-treatment monitor has been changed to specify basis in Tech.Spec.3.11.2.7 noble gas release'ate of 330 millicuries/second.

Changes performed herein will not reduce the accuracy or reliability of dose calculations or setpoint determinations in accordance with Technical Specification 6.14.2.a.2.

S TABLE OF CONTENTS t

1.0 INTRODUCTION

7.0 TOTAL

DOSE.2.0 SETPOINTS...........,........

2.1 WATERBORNE

EFFLUENT MONITORS.2.2 AIRBORNE EFFLUENT MONITORS..

3.0 WATERBORNE

EFFLUENT CONCENTRATION MEASUREMENTS

4.0 AIRBORNE

EFFLUENT DOSE RATES 4.I NOBLE GASES.4.2 RAOIONUCLIOES OTHER THAN NOBLE GASES......

5.0 INDIVIDUAL

DOSE DUE TO WATERBORNE EFFLUENT....

6.0 INDIVIDUAL

DOSE OUE TO AIRBORNE EFFLUENT......

6.1 NOBLE

GASES 6.2 RAOIONUCLIOES OTHER THAN NOBLE GASES......

8.0 OPERABILITY

OF WASTE TREATMENT SYSTEMS........

8.1 LIQUID

WASTE TREATMENT..8.2 GASEOUS WASTE TREATMENT...................

8.3 SOLID

WASTE TREATMENT....................

~Pa e 2 3 4 4 5 6 7 8 9 10 11 12 13 14 15 15 16 17 18 19 20 21 22 23 24 25 25 26 27 2&29 30 30 30 31 32 32 33 Revision~l~<i 12/ll/89 2/21/92 12/11/89 2/21/92 2/21/92 12/11/89 2/21/92 12/11/89 12/11/89 2/21/92 12/11/89 12/11/89 11/25/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 12/11/89 2/21/92 2/21/92 2/21/92 12/11/89 12/ll/89 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92 2/21/92

LIST OF TABLES Revision~Pa e~0at Table 3 Table 4 Sample Annual Average Relative Concentrations and Deposition Rates............................

19 Dose Factors for Inhalation, Ingestion and Ground Exposure Pathways: Radionuclides Other Than Noble Gases 20 Table 5 Waterborne Effluent Dose Parameters for Adults..24 Table 1 Radiological Effluent Objectives and Standards..

3 Table 2 Dose Factors for Noble Gases...................

18 12/11/89 2/21/92 12/11/89 2/21/92 12/11/89 Tabl e 6 Operational Radiological Environmental Honitoring Program.........

..................

44 45 46 11/25/92 ll/25/92 11/25/92 Table 7 Detection Capabilities for Environmental Sample Analysis.................................

47 48 2/21/92 2/21/92 Table B-1 Radiological Environmental Monitoring Program Annual Summary...............B-3 12/11/89 Table 8-2 Reporting Levels for Nonroutine Operating Reports B-4 12/11/89 Table D-l Dilution Factors and Transit Times for SSES Effluents to Danville, PA.......................

D-3 2/21/92 LIST OF FIGURES Revision~Pa e~Da Figure 1 Liquid Radwaste System Flow Diagram.........

34 3/6/92 Figure 4 Figure 5 SSES Dry Contaminated Waste Processing......

37 Environmental Monitoring Locations Within One Mile of SSES............................

42 Figure 6 Environmental Monitoring Locations Greater than One Mile from SSES.....................

43 Figure 2 Offgas and Recombiner System Flow Diagram...

35 Figure 3 Solid Waste Management System Flow Diagram..36 2/21/92 2/21/92 2/21/92 11/25/92 11/25/92 ll,~gll C.NDAP-QA-0646 Revision 0 Page 25 of 61 Liquid:Oil Waste at concentrations I/and greate1 may be solidified provided the following are adhered to: 6.2.9 (1)An emulsification agent is added at required concentrations.

(2)The Liner is NOT SHIPPED to Barnwell S.C.Disposal Facility.Solid Sealed Sources Solid Sealed Sources requiring disposal shall be packaged for disposal as requested by Health Physics Supervision.

Method of disposal is dependent on waste class of the Solid Sealed Source and disposal facility requirements.

Acceptable methods of disposal include: (1)Placement within a container consisting of another waste type.6.2.10 (2)Class 8 and C sources shall be stabilized within an approved solidification or encapsulation media.A Waste Type that is combined with a known amount of hazardous waste or"Mixed Waste" shall be processed for final disposal pending approval obtained from the disposal faci.lities, Environmental Protection Agency, and U.S.Nuclear Regulatory Commission.

6.2.]I r6.3.1 r Various other materials not specifically identified as waste types will be evaluated for solidification or dewatering volume reduction or other processing on a case by case basis.RAD IOACT I VE WASTE ANALYSIS'ND CLASS IF ICATION Radionuclide concentrations of radioactive waste are used to'classify waste for shipping and disposal.Radionuclide concentrations should be determined based upon isotopic analysis, volume and weight of final waste form.

I4 V' NDAP-QA-0646 Revision 0 Page 26 of 61 The 10 CFR 61 Compliance Program establishes a methodology for characterizing radioactive waste through t~h use of correlation factors.This program shall require as a minimum that: Samples repre'sentative of Susquehanna's waste streams are collected and analyzed such that results are obtained from a designated laboratory at least every two years (Class A)for development of specific correlation factors.Waste streams known or suspected to be classified Class B or Class C should be analyzed on an annual basis.Technical basis documentation and justification of correlation factors are developed for each waste stream and are acceptable for use.Periodic e'valuations and necessary adjustments to established ratios are performed in a timely manner.Correlation factors are re-evaluated followino sign':cant c!;anges (greate~xnan a racaor or 10)in plant operations (such.as significant changes in fuel leakage, radwaste operations, or equipment).

Determination of waste classification shall be in accordance with 10 CFR 61.55, Waste Classification, and its supplementary Branch Technical Position on Radioactive Waste Classification as follows: a.b.C.Class A-Usually segregated from other waste classes at the disposal facility.Physical form and'haracteristics shall meet the minimum requirements specified in 10 CFR 61.56(a).If the stability requirements in 10 CFR 61.56(b}are met, the waste does not have to be segregated for disposal.Class B-Physical form and characteristics shall meet both the minimum and stability requirements specified in 10 CFR 61.56.Class C-Physical.form and characteristics shall meet both the minimum and stability requirements specified in 10 CFR 61.56.In addition, measures shall be taken at the disposal facility to protect against inadvertent intrusion.

Af rvr NDAP-QA-0646 Revision 0 Page 27 of 61 Isotopic analysis may be performed by: a.Gamma spectrometry of a sample and use of correlation factors.b.Direct gamma spectrometry of waste and use of correlation factors.c.Complete radionuclide analysis of waste sample.d.Dose to Curie calculations.

e.Activation analysis.Volume and weiaht of final waste may be determined by: a.Calculation using analytically derived sample densities.

t'.Calculation using standard waste densities.

Direct measurement of volume and weiaht.If samples of waste are used for classification, sampling program shall include: a.Samples shall be obtained and analyzed for each batch of waste if practical and ALARA.Preferentially, samples should be taken for analysis following processing into a final waste form.c.Samples taken prior to final processing should enable results of sample analysis to be directly translated to final~aste form.d.Head resin used for chemical demineralization shall be sampled after resin has been depleted in process.e.Solidification/Oewatering Services Vendor or another qualified individual shall obtain'equired samples.Preparation of waste for sampling or analysis a.Met Waste Collection tanks shall be recirculated in accordance with approved operating procedures prior to sampling or analysis.

NOAP-QA-0646 Revision 0 Page 28 of 61 b.C.Bead resin processing in liners shall be mixed in accordance with approved operating procedures

-prior<o sampling or analysis.Wet waste to be processed may also be mixed, recirculated and sampled or analyzed from mobi1e processing equipment.

6.3.8 6 3 c Final waste form containing a mixture of waste types or streams shall be individually analyzed to determine radionuclide concentrations.

The summation of each individual radionuclide concentration shall be used to=characterize the final waste form for shipping and disposal.Waste types or streams of different waste classes (estimated by historical precedent or projected analysis)shall not be mixed.Deviations from sampling and analysis requirements sha11 be approved by Chemistry Supervisor and Effluents Management Supervision.(I)6.4 TESTING/TREATMENT OF SOLIDIFIED RAOWASTE FOR COMBUSTIBLE GASES 6.4.i Solidified waste shall be tested and/or treated to ensure it is not capable of generating quantities of flammable'or toxic gases, vapors or fumes which may be harmful to persons transporting, handling, storing or disposing of the waste.6.5.RADIOACTIVE WASTE SOLIDIFICATION 6.S.1 General Requirements a..Wet Waste Types which may be solidified.in steel liners are Evaporator Concentrates, Mixed Solids, Condensate/Radwaste Demineralizer Bead Resin, RWCU Filter Media and L'iquid Oil Waste or Petroleum Based Material, cartridge filters and Solid Sealed Sources.b.C.Sol'idification processing shall be conducted by qualified SSES or Solidification/Dewatering/

Services.Vendor personnel.

The solidification process shall be operated in accordance with.approved operating procedures.

Procedures shall specify waste stream, amounts of solidification agent and additives or method.for determination.

Waste Preconditioning NOAP-gA-0646 Revision 0 Page 29 of 61 Waste preconditioning requirements shall be determined by chemistry analysis.Preconditioning of waste shall be performed if required prior to determining mixing ratios.c.Waste preconditioning is required when any of the following conditions exist: (1)A high or low pH condition, as determined by chemical analysis.d e.(2)Liquid content of the batch's out of the acceptable envelope for solidification.

(3)Solids content of the batch is out of the acceptable envelope for solidification.

(4)Known potential problem chemicals and constituents within waste that may adversely affect setting and stability of cement-solidified waste form.p"I'Waste prec'onditioning shall be performed in accordance with approved procedures to ensure waste is.with'in'"-ttie'cceptable envelope for solidification; Upon completion of waste preconditioning, additional samples, as required, shall be obtained in accordance with R'adioactive Waste Analysis'and'Cl'ashification section of this procedure'etermination of Hixin'g Ratios a.b.c: Oetermination of'mixing ratios shall be performed for each waste batch to be processed.

Oeviation from the recommended mixing ratios shall be reviewed by Plant Operations Revie~Committee (PORC}.Chemistry Group determines:

(2)Oensity of the waste samples.Specific gravity of Sodium Sulfate Solution in Evaporator Concentrates.

e pe 0

"'.HOAP-QA-0646 Revision 0 Paae 30 of 61 SolidificationjOewatering/Services Vendor determines:

(1)Volume fraction solids.(2)Wet Weight fraction solids.(3)Final mixing ratios are within the acceptable envelope for solidification.

Chemistry, Group shall perform test solidification of waste as required by Test Solidification section of this procedure.

Chemistry Group determines mixina ratios.to ensure proper solidification.

Test Solidification Test solidification shall be performed to support waste mixing ratios as follows: same waste stream.(2)When sample analysis fall outside the established range and criteria indicating a change in waste characteristics.

(3)When it is believed that some unexpected or abnormal contaminant may be present.(4)When requested by Radwaste Supervisor.

(5)Hiking of materials shall be accomplished in a manner that duplicates, to the extent practical; mixing conditions that are obtained with full-scale mixing in liner.(6)Curing shall be performed under conditions-similar to those used in laboratory qualification test program.

'4 7~l), p 1k,,'4 HDAP-i(A-0646 Revels>on 0 Page 31 of 61 Upon failure oF a test solidification, an LCO is entered, additional samples shall be obtained, alternative solidification parameters are determined and a subsequent test verifies solidification.

Test solidification shall be performed on each subsequent batch of the same waste stream until at least three (3)consecutive initial test solidification demonstrate acceptability in accordance with Technical Specification 3/4.11.3.equality Control shall verify test solidification acceptability and indicate the acceptability on the surveillance documentation.

The acceptability requirements are defined in the PCP Surveillance Specimen section of this procedure.

Extra sample volume for backup testing shall be disposed of after liner burial.Class A Unstable test solidification billets should be disposed after the liner is buried.Class A Stable, B and C test solidification billets should be archived to support long term surveillance in accordance with PCP Surveillance Specimens section of this procedure.

Test solidification should be performed with waste from samples obtained as follows: (I)In accordance with Radioactive Waste Analysis and Classification section of~this procedure.

(2)Sampling of the solids in the liner and the liquids used for hydration, then mixed to the ratios that exist in the liner.Test Solidification Procedures shall be developed for each specific waste type.Cement, water type and additives to be used in actual solidification shall be used in preparation of test solidification.

PCP Surveillance Specimens NDAP-QA-06<6 Revision 0 Page 32 of 61 a.Class A Unstable Test Solidification billets shall be examined and tested for acceptability after the specified cure time for: (1)Liquid on surface of solidified product less that 0.5X by waste volume.(2)Insignificant visible defects, such as cracking, spalling, or disintegration.

(3)Strength by physically pokino tie surface of solidified product with a riaid unyielding device.t<ominal surface denting is acceptable.

Class A Stable, 8 and C test solidification billets shall be of sufficient quant'y to support both short and iona term PCP surveillance reauirements.

Stable long term PCP surveillance snecimens should be storvw':s"-ale'"--::.v'r.ai room temperatures.

e.Stable short term PCP surveillance specimens shall be examined and tested for acceptability after the specified cure time for: (1)Liquid on surface of solidifieo product less that 0.5/by waste volume.(2)Insignificant visible defects, such as cracking, spalling, or disintegration.

(3)Compressive strength or penetrometer test results within the values obtained as part of the laboratory qualification test program.Stable long term PCP surveillance specimens shall be examined at a time period approximately equal to 6 months after preparation for: (1)Insignificant cracking, spall ing, or bulk disintegration.

Z"X E' HOAP-OA-0646 Revision 0 Page 33 of 61 (2)Compressive strength or penetrometer test results within values obtained for an equivalent period of time as part of the laboratory qualification test program.f.Stable long term PCP surveillance specimens shall be examined at a time period approximately equal to 12 months after preparation for: (1)Insignificant cracking, spalling, or bulk disintegration.

(2)Compressive strength or penetrometer test, results within values obtained for an equivalent period of time as part of the laboratory qualification test program.(3)Immersion test in de-ionized or synthesized sea water for a minimum of 14 days, followed by a minimum 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months dry time in ambient air.(4)At completion of immersion test and dry time, the examinations in 6.5.5.f(l) and...I.6.5.5.f(2) are repeated.g, A suImiiary report, addressing the results of stable long term PCP surveillance specimen preparations and examinations shall be prepared and submitted to the NRC (Director.

Division of Waste Management and Decommissioning).

within 90 days of the end of each calendar year."'Curing Time a.b..A minimum of 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months shall be allowed for curing prior to capping or transporting container.

If liner contains waste which does not require stability as defined in 10CRF61.this requirement may be waived by Radwaste Supervisor.

The liner may be moved during the first hove , after solidification but must remain undistUrbed for the'remaining 29 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months .c~Deviations from minimum required curing tim-.shall be approved by Radwaste Supervisor and Justifications documented in remarks section of Solidification Record.

pl t$>>'

Solidification Product equality NDAP-()A-0646 Revision 0 Page 34 of 61 Solidif+cation product quality is assured by use of predetermined mixing ratios of waste, cement and additive.Liquid to be used for solidification should be demineralized water.Pre-qualification mixing ratios are based on laboratory testing using non-radioactive waste-materials.

Hixing ratios are re-enforced by the following:

(1)Test solidification performed periodically as-stated in Test Solidification section of this procedure.

(2)Visually and physically checking at least every fifth (5th)container of the same waste type.d Container checks shall consist of: (1)A visual check of solidified product for liquid on surface of product not to exceed 0.5%by waste volume.(2)Physically poking the surface of solidified product with a rigid unyielding device prior to capping (Nominal surface denting may occur and is acceptable).

e.()uality Control shall verify acceptability of solidified product when containers are checked.f.Deviation from the container checking requirement shall be approved by the Radwaste Supervisor.

Handling of Unacceptable Solidified Waste Containers.

a.if a solidified waste container does not meet acceptability requirements, a Non-Conformance Report (NCR)shall be issued.

t<DAP-gA-0646 Revision 0 Paae."5 of 61 If the product does not require stability as defined in IOCFR61, the following are applicable: (I)If the reason for unacceptability is free liquid: (a)The free liquid will be removed;or (b)Extra cement/additive will be added to solidify free liquid.(2)If portions or all of the proouct did not solidify after three days: (a)The waste container will be capped'and placed in a storaae location and periodically checKed until such a time product is acceptable; or.(b)Additional solidification aaents may be added to achi~v<<:>><<--'~

v solidification, as oeterminea oy tne Radwaste Supervisor.

Specific instructions shall be established for handling unacceptable solidified waste container on a case by case basis.equality Control shall re-verify acceptability oF solidified product by performance of Container Checks.If:the product solidifies prematurely prior to completing the addition of required amount of cement and additive, as calculated on the solidification calculation sheet for the specific procedure used, the following is required: (1)Chemistry Group shall perform a test solidification at actual ratio of cement and waste in the liner, provided sufficient sample volume remains to complete this item.(2)equality Control shall check the product for acceptability in accordance with Container Checks section of this procedure.

.C.IL, W, 8' (3)(4)NDAP-()A-0646 Revision 0 Page 36 of 61 The liner is considered to meet acceptable waste form criteria for shipping provided tftb subsequent test solidification and/or product quality checks are acceptable to equality Control and concurrence of the Radwaste Supervisor is obtained.The above apply only if the Effluents Hanagement Supervisor determines that waste can be classified as"Class A Unstable" in accordance with lOCFR61 and the disposal facility criteria.if the product is a class which requires stability as defined in 10CFR Part 61 and does not solidify properly in accordance with the specific operating procedure, the following is required: (1)An evaluation of the liner shall be made by the following personnel:

(2)(3)(a)effiuents Management Supervision (b)Solidification Vendor-Operations (c)Solidification Vendor-Engineering Disposal facilities shall be contacted and requirements for receipt of the liner in" question shall be defined.Alternative packaging/processing shall be evaluated.

(4)(6)(6)(7)Recommendations for, final disposition shall be made to the Power Production Engineer-Effluents Management.

Final disposition shall be reviewed by Plant Operations Review Committee (PORC).Records shall be kept and documentation supportive of final disposition attached to the solidification record package..The liner may be shipped after g.C.review of documentation is complete and.disposal facility concurrence is received in letter form.

N I Fi NOAP-OA-0646 Revision 0 Page 37 of 61 Capping of Solidified Waste Containers a.The reqN,irements of Solidification Product equality section of this procedure shall be met prior to capping the container.

If the container contents are within the requirements of Low Specific Activity (LSA)ensure one of the following:

(1)The container should be shipped within (10)ten days after capping;or (2)If a container has been capped for longer than (10)days, it shall be opened, vented, and re-capped within (10)ten days of shipment.If the container exceeds the limits for Low Specific Activity and contains water and/or organic substances which could radiolytically generate combustible gases, determination must be made such that the following criteria are met over a period of time that is twice the expected shipment time: (1)The hydrogen oenerated shall be limited to a molar quantity that would be no more than 5'X by volume of the container gas void;or (2)The container and shipping cask cavity shall be inerted with a diluent to assure that oxygen is limited to less than 5X by volume in those portions of the package which could have hydrogen greater than 5X.Solidification Agent Control a.Portland Cement-ASTM C-150 Type I shall be used for the mobile solidification process.Other solidification agents may be used only after acceptable testing of the agent has been completed that demonstrates acceptable solidification and disposal Facility approval has been obtained.

NOAP-OA-0646 Revision 0 Page 38 of 61 c.Documented Certification is not required for materials received in bags provided material verification can be obtained as follows: d.(1)Cement is acceptable provided the bag containing the cement indicates that'ement is Portland Type I.(2)Sodium'Silicate is acceptable provided the bag containing the additive indicates Anhydrous Sodium Hetasilicate and is a product of P()Corporation.

(3)Other additives are acceptable provided the container is clearly marked indicating the type of additive.Other additives may be used for enhancement of solidification process as specified in the operating procedure and documented in the solidification records.Radioactive Waste Solidification Records A Solidification Record Sheet (Form NOAP-(IA-0646-1) shall be completed for each liner filled with solidification products.Completion of the Solidification Record Sheet and the required accompanying documentation shall be as follows: a.The Radwaste Supervisor is responsible for initiating this form and completing Parts 1 and 2.C.Effluents Management Supervision, Chemistry and Solidification/Oewatering/Services Vendor personnel shall provide and check off the required documentation specified in Part 3.equality Control shall provide review as required for the Solidification Records.

0 K~'

NOAP-OA-0646 Revision 0 Paae 9 oi 61 RAO I GAC I I VE WASTE OEWATER ING General Requirements Waste Streams which may be dewatered in High Integrity Containers or steel 1iners are LRW Filter Media, Ultrasonic Resin Cleaner Waste, RWCU Filter Hedia, Condensate/Radwaste Oemineralizer Bead Resin and Cartridge Filters.Oewatering of Radioactive Waste shall be performed by qualified SSES or vendor personnel.

Oewatering of Radioactive Waste shall be performed in accordance with approvea operating procedures.

Oewatering proceoures shall be baseo on documented test data that has demonstrated the ability to achieve free liquid limits as specified by disposal facilities and applicable regulatory agencies.Liquid volume and drainage calculations and actual drainage.=..ification may also be used to meet free liquid limits.~~High Integrity Containers shall be used for disposal when the concentration of radionuclides with half-lives great,er than 5 years exceeds I pCi/cc.Oewatered Product Control The final dewatered product shall contain less than 1%free liquid for High Integrity Containers and 0.5%for steel liners.equality Control checks shall be performed on process steps.If a dewatered waste container does not meet acceptability requirements, a Non-Conformance Report (NCR)shall be issued.Specific instructions shall be established for handling unacceptable dewatered waste container on a case-by-case basis.Deviation from the container checking requirement shall be approved by the Power Production Engineer-E ffluents Management.

~II 6,6.3 Radioactive Waste Dewatering Records NDAP-gA-0646 Revision 0 Page 40 of 61 A Dewatering Record Sheet (Form NDAP-QA-0646-2) shall be completed for each container filled with dewatered waste streams.Parts of the form shall be completed by the following responsible individuals or groups a.The Radwaste Supervisor is responsible for initiating this form and completing Parts I and 2.b.Chemistry Group shall complete Part 3 Sampling and Analysis.Effluents Management Supervision.

Chemistry and Solidification/Dewatering/Services Vendor personnel shall provide and check off the required documentation specified in Part 4.d.equality Control shall provide review as required for the Dewatering Record Sheet.~;'"H: ll i EGR I T Y CONTAINERS (HIC)6.7.I Storage of High Integrity Containers Radlok, Nuhic, and CNSI High Integrity Containers (HIC)stored in direct sunlight or in areas where there is a strong source of ultraviolet radiation shall be filled within one year of manufacturing date.Radlok High Integrity.

Containers stored away from any sources of ultraviolet radiation shall be filled within two years of manufacturing date, or specific guidance from the vendor must be obtained.c.Once filled a Radlok High Integrity Container may be stored in an approved storage facility for up to (5)five years prior to burial.d.Once filled a CNSI High Integrity Container may be stored for a period until one (I)year of ultraviolet radiation is received.Short exposures (i.e., several hours)to sunlight, such as occurring during shipment and on site transfer need not be counted when determining total ultraviolet exposure.

y: H gl 0 Uses of High Integrity Containers NDAP-gA-0646 Revision 0 Page 41 of 6]a.High In&grity Containers may be used to package the following waste materials for burial at Barnwell, South Carolina, Richland, Washington, and Beatty, Nevada, low level waste disposal facility(ies).

-Oewatered bead ion exchange resin-Oewatered powdered ion exchange resin-Activated carbon, powdered carbon, diatamaceous earth and other granular or fibrous filter material-Cartridge filter elements-Filter sludge-Sand blasting grit and crud-Stabilized incinerator ash b.-Other dewatered and dry material provided concurrence is received by container vendor and disposal facility.Prior to using a High Integrity Container for a specific waste material, procedures shall be established to define the specific requirement that shall be met during use of the container.

The.procedures shall contain: Documentation requirements that specific conditions have been met such as inspection and exposure to degrading conditions.

Instructions as to how to handle and properly close the container.

Instructions for on-site storage of loaded containers for ultimate shipment for disposal.

hi wg e A I'I NOAP-gA-0646 Revision 0 Page 42 of 61 The procedures shall provide a method for documenting required information relevant to the container from initial receipt to shipping for dispos&.Required information shall be based upon the container certificate of compliance and disposal site requirements.

Retention and utilization of the documentation shall be defined in the procedures.

The procedures shall establish specific ()uality Control inspection requirements.

Prior to the first shipment of a specific type of High Integrity Container, authorization shall be requested and received from the applicable regulatory agency governing use of the container in question at the disposal facility of concern.Hiah Intearity Container Limitations a~High Integrity Containers are approved for use provided the following physical'imitations of the waste are met:, (1)Bulk density (2)pH 0.7 to 2.5 gms/cc 4 to 11 (3)Loading temperature

<140'F (4)Radlok 100 loaded weight: (5)Radlok 200 loaded weight:<10500 lb<5500 lb (6)Radlok 55 loaded weight:<950 lb (7)CNSI 14-195 loaded weight:<12200 lb (8)CNSI 14-170 loaded weight:<10800 lb (9)CNSI 8-120.loaded weight:<7500 lb (10)CNSI 6-80 loaded weight<5000 lb I'

NOAP-t}A-0646 Revision 0 Page 43 of 61 (11)CNSI 24-INCH FRP loaded weight<1600 lb (12)Radlok 500 loaded weight:<9500 lb (13)Radlok 179 loaded weight:<14000 lb (14)Radlok 195 loaded weight:<15500 lb (15)NUHIC 120 loaded weight: '<8500 lb (16)NUHIC 136 loaded weight:<8500 lb The maximum concentration of radionuclides with half lives greater than (5)five years that may be disposed of in a High Integrity Container is 350 pCi/cc.The following chemicals are prohibited and may not be disposed of in High Integrity Containers.

(1)Aqua Regia (2)Bromine (3)Chromic/Sulfuric Acid (4)'uming Sulfuric Acid (5)Nitric Acid>50K concentration (6)Organic peroxides k (7)Phenol-concentrated (8)Acetone (9)Butane (10)Carbon Oisulphide (11)Chloroform (12)Ethyl Ether (13)Ethylene Oichloride (14)Methylene Chloride (15)Methyl Ethyl Ketone NOAP-()A-0646 Revision 0 Page 44 of 61 (16)Propane (17)Pentane A passive vent design shall be incorporated into the container to relieve internal container pressure.Closure of High Integrity Containers Closure of High Integrity Containers shall be completed in accordance with'pproved procedures.

If the container is not equipped with a passive vent and its contents are within the limits of Low Specific Activity ensure one of the following:

(1)The container is shipped within (10)ten days after closing;or ir the cont,a>ner has been ciosea ior longer than (10)ten days, it shall be opened, vented, and re-closed within ten (10)days of shipment.If the container exceeds the limits for Low Specific Activity or contains water and/or.organic substances which could radiolytically generate combustible gases, determination must be made such that the following criteria are met over a period of time that is twice the expected shipment time: (1)The hydrogen generated shall be limited to a molar quantity that would be no more than 5X by volume of the container gas void;or (2)The container and shipping cask cavity shall be inerted with a diluent to assure that oxygen is limited to<5X by volume in those portions of the package which could have hydrogen greater than 5X.Step 6.7.4.b and 6.7.4.c shall also apply to dewatered waste in steel liners.

l~, 1 I

6.8 iRRA01'ATEO

HAROWARE PROCESSING ANO DEWATERING

6.8.1 General

Requirements NOAP-gA-0646 Revision 0 Page 45 of 61 a.Processing and dewatering of Irradiated Hardware shall be performed by qualified SSES or vendor personnel.

b.Processing and dewatering of Irradiated Hardware shall be performed in accordance with approved procedures.

6.8.E Oewatering procedures shall be based on liquid volume and drainage calculations and actual drainage verification to demonstrate the ability to achieve free liquid limits as specified by disposal facilities and applicable regulatory agencies.Oewatered.

Product Control 6.9 Tha fi~l dowatereA nvnhucf eha)1 conf>jn)mrs than 0.5/o free liquid for steel liners.b.guality Control checks shall be performed on process steps..6.8.3 Irradiated Hardware Processing and Oewatering Records\a.All records generated shall be completed and filed in accordance with approved implementing procedures.

CONTAINER INSPECTIONS

.6.9.1 6.9.2 6.9.3 guality Control shall inspect containers to be used for solidification, dewatering, and other packaging.

This inspection shall assure that prior to use, the containers to be used for solidification, dewatering, or other packaging are intact and their internals are free~of any visual damage that would prevent them from performing their intended function.Containers shall meet the general criteria for normal transport conditions in accordance with the requirements of 49 CFR.Type A containers shall meet the additional testing requirements specified in 49 CFR.

k$t 0 NOAP-gA-0646 Revision 0 Page 46 of 61 6.10 WASTE CONTAINER SPACE UTILIZATION 6.10.1 6.10.2 6.10.3 6.10.4 Waste volume shall be maximized within the guidelrrfes of specific operating procedures to minimize potential void space at the top of waste container after solidification or dewatering is complete.Waste volumes shall meet or exceed burial site criteria.If waste volume is less than disposal facility criteria, requirements for disposal of the container in question shall be defined by.the disposal facility.Specific waste volumes committed to by the vendor shall be met or otherwise justified as to why waste volumes were not achieved.Susquehanna Guaranteed Solidified/Oewatered Waste Volume Record, Form NDAP-(A-0646-3, shall be completed by vendor personnel, approved by Radwaste Supervisor and shall be used to track solidified/dewatered waste volumes achieved in each individual container.

6.11 STORAGE OF PACKAGED RADIOACTIVE WASTE 6.11.1 6.11.2 6.11.3~-6.11.4 Radwaste Supervisor shall provide Solidification and/or Oewatering Record sheets that have been'eviewed by equality Control personnel stating that processed waste has been solidified or de-watered in accordance with the Process Control Program and meets the applicable shipping and disposal criteria.Solidification and Dewatering Records shall include the isotopic mix, isotopic concentration of the waste that was packaged, the total volume of the waste, and the amount of water, cement or other solidification agent used, as appropriate.

Solidification and Dewatering Records shall be part of the permanent shipping records and adhere to requirements of the Process Control Program.For materials packaged in a high integrity container, documentation shall be maintained on HIC storage and pre-shipment checklist information.

6..5 6.11.6 NOAP-OA-0646 Revision 0 Page 47 of 61 Packaged radioactive waste shall be stored in areas designated by HP Foreman Effluents Hanagement. Storage of packaged radioactive waste in the Low Level Radwaste Holding Facility (LLRWHF)shall be in accordance with approved procedures. An inventory of stored, packaged waste by a unique container number such as L(Liner)-Year and-container number shall be maintained. The inventory shall include the contact dose rate, isotopic mix stated as concentration per gram of material and total volume of waste and solidification agent.as appropriate. 6.12 TRANSPORTATION, SHIPPING ANO OISPOSAL REGULATIONS 6.12.}Specific regulatory documents shall be maintained on site in a status that is current.Specific regulations that shall be maintained include but are not limited to the following: 10CFR71 Packaging of Radioactive Nateria}'n~.transport and transportation of radioactive material under certain conditions. ,'I~~C.49CFR100-199 Transportation. Chem-Nuclear Systems Inc.Barnwell S.C.disposal"site operating license number 097 State of South Carolina.d.e..9.'.Chem-Nuclear System Inc.NRC Haterial License 12-13536-01. '"'Chem-Nuclear System Inc.Barnwell S AC.disposal site operating procedures and site criteria.US Ecology NRC Haterial License 04-0376601.

US'.Ecology Richland Washington disposal site operating license WN-1019-2 State of Washington.

Scientific Ecology Group Licenses R-73008-E94, R-01052-A91. '\~Cask Hanuals for casks of which PP8L is an authorized user.A copy of the license for each facility to which Radioactive Material is sent. '4'I$p k NDAP-QA-0646 Revision 0 Page 48 of 61 10CFR61 Licensing requirements for land disposal of Radioactive Waste.6.12.2 Procedures applicable to transportation, shipping and disposal shall be developed. Procedures shall be established and maintained to provide directions and assure regulatory compliance for manifesting, which include applicable federal, state, and disposal facility regulations, and NRC guidance.Procedures shall contain check off lists where and when applicable to assure specific attention is paid to the critical function being controlled. 6.12.3 Procedures shall contain Quality Control notifications or hold points.Non-Process Control Computer software used,to implement applicable portions of the Process Control Program shall be in acco'ance~.D.-".P;".'-0 0!.6.13 SHIPPING OF RAD IOACTI VE WASTE 6.13.!All Radioactive waste shall be shipped by Effluents Management. 6.13.2 All waste shipped from SSES shall only be to facilities licensed to receive the waste and in accordance with 10CFR71 and 49CFR100-199. 6.13.3 6.13.4 Dry Active Waste (DAW)should normally be shipped as Type A quantities and therefore do not require specific licensed containers. Waste containers shall be placed in a USNRC approved licensed shipping container if it: a.Exceeds Type A quantities b.Exceeds 1000 mr/hr on contact r c.Exceeds 1000 dpm/100 cm loose surface contamination on the exterior of the container. The specific conditions of the Certificate of Compliance for each approved shipping cask shall be strictly adhered to. 'b CI 0 SOAP-QA-0646 Revision 0 Paae 49 of 61 Packaged~aste may be shipped unshielded if: a.Contact dose rates are less than 200 mrem/hr and dose rates at 6 feet are less than 10mrem/hr. b.Curie content of the package shall be a Type A quantity.c.Container shall be a minimum of a strong tight container. Prior to the shipment of a package of radioactive waste, the HP Foreman Effluents t)anaaement, shall assure the container is surveyed for contact dose rates and surface contamination. Oecontamination, if required, shall be done under the direction of'he HP Foreman Effluents Management. Oecontamination may be waived based upon radiological conditions. All vehicles used to transport radioactive waste requiring the vehicle to be placarded shall be checked for adequate opera'ion and s='e:.All Radwaste shipments from SSES shall normally be via"Exclusive Use" vehicles'pecific instructions given to the driver include: a.Expected route of travel to his fina)destination'. Maintaining"Exclusive Use" status..c.Specific actions to be taken in the event of an accident.No'vehicle carrying radioactive waste that.is overweight shall leave SSES without a Pennsylvania overweight permit.a.A OAW shipment or other shipment capable of having its weight adjusted, sha11 not be allowed to leave SSES overloaded. b.An overloaded condition for any vehicle is based on total weight and weight per axle. 'a 6.13.11 NDAP-OA-0646 Revision 0 Page 50 of 61 In the event access is denied to SSES at all operating a>sposal facilities, PPKL will provide carrier with a letter stating that SSES will meet all applicable federal, stat~and compact requirements for receipt back of the radioactive waste/material in carrier's possession. 6.14 SHIPMENT CONFIRMATION If disposal sit,e shipment acknowledgement is not received within 18 days from departure from SSES, Effluents Management Supervision shall conduct, a trace investigation for shipment location.If the disposai facility shipment receipt can not be confirmed within 20 days.a 5 gnificant Operating Occurrence Report (SOOR)shall be generat,eo. 6.15 CHANGES I': IHF SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM 6.15.i 6.15.2 Any changes as described in the Technical Specifications, to the Solid Radioactive Waste Process Control Program shall be provided in the Semi-annual ~adioactive Effluent Release Report filed with the p col'~ny changes to the Solid Radioactive Waste Process (ontrol Program shall be approved by Plant Operations '"'review Committee (PORC)prior to implementation. 6.16 EVALlJATION Of PROCESS OR OPERATIONAL CHANGES 6.16.1 6.16.2<.hanges in radioactive waste processing or operational changes shall be evaluated to determine any impacts on waste characteristics and/or form.Evaluation should include as a minimum: Operational evaluation of processing impacts.Chemistry evaluation of changes to sampling and analysis methodology. Effluents Management evaluation of packaging and/or shipping impacts.fffluents Management evaluation for 10 CFR 6l compliance. NOAP-QA-0646 Revision 0 Page 51 of 61 (2)6.17 REPORTING OF MISHAPS INVOLVING LOW LEVEL WASTE FORMS IOCFR61 establishes the minimum and stability requirements for Low Level Waste (LLW)forms.10CFR20 requires certification that the processed waste satisfies the requirements of IOCFR61.Mishaps which may impact the final waste form shall be reported to the NRC.6.17.2 Types of mishaps which should be reported include: Failure of high-integrity containers used to ensure a stable waste form.Container failure can be evidenced by changed container dimensions, crackina.or damaae resu)ting from mishandling (e.g., dropping or impacting against another object).Misuse of high-integrity containers. evidenced by a quantity of free liquid greater than 1 percent of container volume.or by an excessive Production of a solidified Class 8 or C waste form that has any of the following characteristics: (1)Contains free liquid in quantities exceeding 0.5 percent of the volume of the waste.(2)Contains waste with radionuclides in concentrations exceeding those considered during waste form qualification'testing accepted by the regulatory agency, which could lead to errors in assessment of waste class.(3)Contains a significantly different waste loading than that used in qualification testing accepted by the regulatory agency.(4)Contains chemical ingredients not present in qualification testing accepted by the regulatory agency, and those quantities are sufficient to unacceptably degrade the waste product.

NDAP-(jA-0646 Revision 0 Page 52 of 61 (5)Shows instability evidenced by crumbling, cracking, spalling, voids, softening, disintegration, non-homogeneity, or dinfensional changes.(6)Evidence of processing phenomena that exceed the limiting processing conditions identified in applicable topical reports or process control plans, e.g., foaming, temperature extremes, premature or slow hardening, and production of volatile material.i.Failure to adhere to high integrity container limitations as required by container certificate of compliance. Notification of violation by disposal'facility regulatory authorities at time of container receipt for disposal.Failure of cement-solidified stable waste form long term PCP surveillance specimens due to evidence of significant cracking, spalling, or bulk disintegration, compression or penetrometer strength and immersion test results.Requirements for reporting of mishaps shall apply only:o processing liners and high integrity containers containing radioactive w'aste in its,final product'orm.'ignificant Operating Occurrence Report (SOOR)shall be generated if one of the mishaps mentioned'occurs.6.)8 PCP!":i'LEHENTING PROCEDURES Pio'.conies required for implementation of the Process Control Proof~: are shown in Attachment 0.i 0 P.ECORDS in'.iioiFication Records or Oewatering Records and the attached oocu"eats shall be forwarded to Effluents Management Supervision ~oi'ention until such time as the container identified on A~co~': i: shipped for final disposition. HDAP-(}A-0646 Revision 0 Page 53 of 61 7.2 When:..".e identified container is shipped the Solidification Recoros or Oewatering Records and other documents concerning the Shipment.shall be filed with the shipping documentation and forwaraed to OCS for retention.

7.3 Documentation

of Radioactive Waste Shipments shall be retained as require@by SSES Technical Specifications.

7.4 Radioactive

waste shipping documentation shall consist of, but not limited to.the following records: 7.4.!Radioactive Haterial Shipping Hanifest 1.4," 4<valuation of isotopic, mix and concentration Radiological surveys oF: a.Vehicle upon arrival Package to be shipped 7.4.4 7.4.5 7.4.6 c.Loaded vehicle prior to shipment Vehicle Safety inspection Check-off sheet for loading procedure Documentation of adherence to Process Control Program (if applicable) 7.4.i.Special instructions to driver gv ll Aa PART I: 'OL IOIF ICATION RECORO SHEET Liner identification Information Attachment A NOAP-gA-0646 Revision 0 Page 54 of 61 PPi!L Liner Number Waste Stream 2.Liner Vendor Serial Number (RWCU Filter Media cannot be entered)PART Test Solidification required?YES NO (circle one)2: Container Selection (Refer to WN-PS-100 fHP-TP-800]) PART Estimated Liner Contact Oose Rates Projected Curie Concentration Expected Waste Classification/Stability Liner Iype to be Used Expected Cask Type to be Used Oocumentation Checklist mR/hr pCi/gm 5.Empty height of Liner'Ibs iyARI c~Form tsuAP-gA-0646-1 (original) Waste Form Oocumentation OP(WM)-068 (RP)-Forms (original) SC-068-002 'Forms (copy)Waste Form:.STABLE UNSTABLE (circle one)>85X Liner Volume Utilized: YES NO (circle one)>(aste Activity Oocumentation CH-RC-Forms (copy)isotopic Analysis (copy)Composte added/Log entry made on CH-TP-055-1 Health Physics Oata Liner Radiological Survey (original) Shipment i lb.(If available ALARA)REMARKS'://o~YM&Hf'n e.'1enol~sn FOR(:.SOAP-(}~-0646-1, Rev.0, Page I of 1 (File R69-1) lp, V OEWATERING RECORD SHEET Attachment 8 NOAP-QA-0646 Revision 0 Paae 55 of 6]PART i: Linei Identification Information PPKL Linei Number Liner Vendor Seria'I Number 3.Waste Stream PART 2: Cont;>ocr Selection (Refer to HH-PS-100[HP-TP-800]} Estimated L}TTi r Contact Dose Rates Projected Cut'it>Concentration Expected Wast,e Classification/Stability 4.Liner Type to be Used 6.Expected Cas): Type to be Used mR/hr pCijgm Empty Weight of Liner lbs.Radwaste Supervisor ate ime FORM NOAP-QA-0646-2, Rev.0, (DUPLEX}, Page I of 3 (File R69-I) rP PART 3:Sampling and Analysis 1.Tank/Liner sampled 2.Sample Number 3.Waste Stream Oil Content (Check one)a.None DEWATERING RECORD SHEET Attachment 6 NDAP-gA-0646 Revision 0 Page 56 of 61 b.less than 1%Isotopic Analysis attached 6.Specific activity of Dewatered Sample 7.a.Dewatered Volume b.Dewatered Weight gm pCi/gm c.Sample density gm/cc 8.Composite added/Log entry made on CH-TP-055-1 The above tank/liner containing solids has been analyzed in accordance with CH-RC-075 and found to contain the isotopes and specific activities as indicated on the attached data sheets.em>stry upervision ate lme FORM NDAP-OA-0646-2, Rev.0, (DUPLEX)Page 2 of 3 (File R69-I)

OEWATERING RECORO SHEET Attachment 8 NOAP-QA-0646 Revision 0 Page 57 of 61 pART a: Liner Shipment Information Summary 1.PPKL Liner Number 3.Form NOAP-QA-0646-2 (original) 4.Waste Form Documentation 2.Waste Volume Calculated ~'aste Weight=gm/cc x 62.2 x ft=lb.Actual F Iiled Liner Weight lb.(if available ALARA)IOO x (Oewat,ered Waste Volume)ft Part 4.2 ft=/o 3 Anat Vol ume>85%Container Volume Utilized YES/NO (Circle one)Wast.e Form: STABLE UNSTABLE 5.Waste Activity Oocumentation CH-RC-Forms (Copy)Isotopic Analysis (Copy)6.Health Physics Data Liner Radiological Survey (original) Shipment k PART 5: REHARKS: (Circle one)//adwaste oper sor y LIIate~eview Bate oreman FORH NOAP-QA-0646-2, Rev.0, (OUPLEX), Page 3 of 3 (File R69-1)gmt.ate 4% Attachment C NOAP-gA-0646 Revision 0 Page 58 of 61 SUS UEHANNA GUARANTEED SOLIOIfIEO OEWATEREO WASTE VOLUHE RECORD l.Date Waste'(ype Container Type Burial Volume Liner number Useable Con'tainer Volume Guaranteed llinimum Waste Volume Waste Volu::,:.- Attained inches x Wast,e Volun e Cont,ainer Usage ft~/inch 100 x (Wast~V~i Remarks: ft'-: Guaranteed Min.Waste Vel'.t'ta)-100'Y.~~a~a~10.Signature So idi ication Ven or epresentatsve-II.Signature Radwaste upervisor FORM NDAP-QA-0646 ~3.Rev.0, Page 1 of 1 (file R69-1)r~e;~~.a.g%P~~~r,g aa 2 t'+l WASTE PROCESSING PCP IMPLEMENTING PROCEDURE MATRIX Attachment 0 NOAP-gA-0646 Revision 0 Page 59 of 61 Eva orator Concentrates -Solidified SEG STO-P-05-008 (Steel Liner)Mixed Solids-Solidified SEG STO-P-05-051 (Steel Liner)(High Torque)WM-RP-201 (OP-068-133) CH-RC-051 CH-RC-054 LRW Filter Media.URC Waste RWCU Filter Media-Dewatered SEG STD-P-03-046 (HIC)WM-RP-103 (OP-068-116} Condensate Radwaste Oemineralizer Bead Resin-Solidified SEG'TD-P-05-054 (Steel Liner)Condensate Radwaste Oemineralizer Bead Resin-Oewatered SEG STD-P-03-048 (Steel Liner)..'WM-'RP-102 (OP-068-102) d CNSI FO-OP-019 (Overpack) WM-PS-230 (HP-TP-875) TFC Nuclear (HIC),'4g-RP-107 SEG STD-P-03-010 (HIC)SEG STD-P-22-002 (Resin Express)WM-RP-101 (OP-068-121) WM-RP-.104 Page 1 of 3" PCP IHPLEHENTING PROCEDURE HATRIX Irradiated Hardware-Oewatere Steel Liner None Attachment D NOAP-QA-0646 Revision 0 Page 60 of 61 Or Active Waste OAW-Packa in WH-PS-210 (HP-TP-841) Liouid Oil Waste-Solidified SEG STD-P-05-002 CH-RC-050 Solid Sealed Sources None I.i uid Oil Waste-Decontamination WH-PS-302 (OP-068-135) WASTE ANALYSIS ANO CLASSIFICATION -IOCFR61 CH-TI-037 CH-RC-075 CH-RC-076 CH-TP-055~~" RAO I OACT I VE WASTE'OL IO IF I CATION-G ERAL SEG STO-P-05-044 WM-RP-005 (OP-068-112) WM-RP-004 (OP-068-108) WH-PS-100 (HP-TP-800) WH-RP-008 WH-PS-110 (HP-TP-801) WH-PS-120'(HP,.-;:.TP,.-.,802) WH-PS-140.'(HP.,=.'TP;-".8'10)'.".... WH-PS-160.(HP,'-.'TP;851)- WH-PS-170.::(HP .TP.'~883)WH-PS-240 (HP-'TI.880).TESTING/TREATMENT COMBUSTIBLE GASES WM-RP-009 WH-RP-301 (OP-068-131) ~i SEG STO-P-05-022 ~WM-RP-205 (OP-068-120) SC-068-002 (Test Solidification).SEG STD-P-05-050 WH-RP-002 (OP-068-132) Paoe 2 of 3 4~C'lp g,.n PCP IMPLEMENTING PROCEDURE MATRIX RADIOACTIVE WASTE DEWATERING -GENERAC'ttachment D NDAP-gA-0646 Revision 0 Page 61 of 61 SEG STD-P-01-005 (Equipment) WM-RP-001 (OP-068-114) SEG STD-P-03-022 WM-RP-0!0 (OP-068-129) HIGH INTEGRITY COttTl It<ERS-CLOSURE SEG STD-P-03-"03 Wfl-RP-007 (OP-068-123)DISPOSAL FACILITY FEOUIREMENTS WM-PS-}90 (HP-TP-806) PACKAGING SEG STD-P-04-004 WM-RP-011 (OP-068-128) SEG STD-P-03-004 WM-RP-006 (OP-068-124) WM-PS-310 WM-PS-311 WM-PS-312 WM-PS-350 WM-PS-351 WM-PS-352 WM-PS-313 (HP-TP-826)(HP-TP-827)(HP-TP-831)(HP-TP-832)(HP-TP-835)(HN-142)(LN-142)(HN-100 I I I)(CNSI 14-195)(CNSI 21-300)(CNS I 8-120A)(HN-194)WM-PS-314 (HP-TP-836)(HN-190-1) WM-PS-353 (HP-TP-837)(CNSI 14-170)WM-PS-315 (HP-TP-838)(HN-200)WM-PS-316 (HP-TP-840)(CNSI 14-215)WM-PS-317 (HP-TP-852)(HN 215H)WM-PS-318 (Wes t inghouse TCT)WM-PS-319 (WCS Cask Drum)Page 3 of 3 SECTION 6 REPORTS OF EXCEPTIONS TO THE SSES EFFLUENT MONITORING PROGRAM 165 REPORTS OF EXCEPTION TO THE SSES EFFLUENT NONITORING PROGRA On 11/17/92, a radwaste release to the Susquehanna River was halted when HV-06432Al and A2 valves closed after the sample process pump tripped.This event occurred for E and F sample tanks under release permit 92-369.The pump was restarted, but tripped again immediately. A negligible amount of liquid was released prior to the pump trips.Operations noted that process rad monitor RR-06433 began to increase, which induced a High Rad alarm.The pump and discharge piping were flushed;subsequent Chemi,stry analyses were satisfactory, and the release proceeded. An initial investigation determined that the pump tripped on low flow due to air binding (low flow).No Limiting Condition for Operation was entered as a result of this evolution. The investigation is continuing on this event for resolution under Significant Operating Occurrence Report 1-92-354.Three events occurred related to operation of Unit 1 Cooling Tower Blowdown Flow Instrumentation: these events caused the instrumentation to be declared inoperable with Technical Specification Table 3.3.7.10-1 Action Statement 102 entered.All three events involved discrepancies in Blowdown Flow Valve position vs.flow acceptance criteria.In no case, however, was the time limit of the Action Statement actually exceeded: the longest period of inoperability was five days.These events were investigated and concluded under Significant Operating Occurrence Reports 1-92-337, 1-92-348 and 1-92-360, and are described for information only here. 1 I,~V ol (K S4 Limiting Vent Concentration, uCi/cc itin Release Rate Ci r E6uCi Ci (5.26E5 min/yr)(Vent Flow Rate, cc/min)'(Eq 6)Sample calculations of waterborne and airborne effluent monitor setpoints are presented in Section A.1.2 of Appendix A.Vent flow rates and sample flow rates are monitored and recorded for each of the five SSES release points.The measured flow rates are used to calculate vent concentrations and release rates.Flow channel setpoints are set at approximately 10X and 90X of the calibrated sensor ranges to provide indication of possibly abnormal flow rates.SP CIFICATION'.11.2.6 -THE CONCENTRATION OF HYDROGEN OR OXYGEN IN THE MAIN CONDENSER OFFGAS TREATMENT SYSTEM SHALL BE LIMITED TO LESS THAN OR EQUAL TO 4X BY VOLUME.Hydrogen recombiners are used at SSES to maintain the relative concentration of components of potentially explosive gas mixtures outside the explosive envelope.The main condenser offgas treatment system explosive gas monitoring system (offgas hydrogen analyzers) have setpoints to alarm at IX and 2X hydrogen.SP CATION 3.1.2.7-The radioactivity rate of the noble gases Kr-85m, Kr-87, Kr-88,Ãe-133, Xe-135 and Xe-138 measured at the motive steam jet condenser discharge shall be limited to less than or equal to 330 millicuries/second. The main condenser offgas pre-treatment monitor provides indication of offgas activity prior to input to the holdup system.Alarm setpoints are based on the Tech.Spec.3.11.2.7 noble gas release rate limit of 330 millicuries/second or less at the motive steam jet condenser discharge. 12 ~>'i, F. FIGURE 5 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES I I I I I I GOULD ISLAND 14 I I I I 13 I I r--~I I I I g,, Q p~~~I LAKE~TAW 554 T Q 555~6Al T~emwmmmW SITE BQUNDARIII 1 NILE 8 SUSQUEHANNA RIVER AIR g SIJRTWCe WATER T TIIERMOLUMIIIESCENT DOSIMEIY 42 FIGURE 6 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN ONE MILE FROM THE SSES 1EiF1 T/SUSQUEHANNA RIVER iVANTICOKE 14 15F1~~1 GLEN LYON m T T SHICKSHINN Y I MOCANAQUA'Ž1 POND HILL 4 BERWICK g.,J SE2 T WAPVALLOPEN A srir 7El yT 12H2 RLT Q.un MIFFLIN VILLE NESCOPECK T, T~INN 5 MILES CON YNGHAM 18 MILES HAZLETON~mOIInXWC riTZa~~ma~IIaX szmae THKRMOI.UMINESCKNT INSIM STIIY 43 Page 1 of 3 TABLE 6 OPERATlONAL RADIOLOGICAL EKVTRONHEKTAL lK)NiTORTKG PROGRAM Exposure Path<<ays a o e~raine Radioiodine and Particulates Nmaber of Saayles~Olid ochtloAS 12S1 (0.4 mi VSV-E.O.F.Building)981 (1.3 ml 5-Transmission Line)SS4 (0.8 mi E-V of Bio.Consult.)12El (4.7 ml VSV-Derrick Hospital)761 (14 mi SE-PPAL Hazleton Chem Lab)'52 (0.5 mi NE-SSES Backup Het.io<<er 1554 (0.6 ml NV-Transmission Corridor 102 (3.9 mi N-Hocanaqua Substatlon) 3Dl (3.4 mi HE-Pond Hill)12Gl (15 mi'USU-Bloomsburg Service Center)'52 Perimeter Fence-0.2 mi H 102 Hocanaqua Substation -4.0 mi H 253 Perimeter Fence-0.2 ml HNE 283 Durabond Corporation -1.3 mi NNE 2F1 St.Adalberts Cemetery-5.9 mi NHE 354 Perimeter Fence-0.3 mi NE 3Dl Pond Hill-3.4 mi NE 3Fl Valania Resident (Nanticoke) -9.1 mi NE 3GS Vllkes-Barre-Parrlsh St.Substation-16 ml NE'S3 Perimeter Fence-0.2 mi EHE 4E1 Ruckles Hill Road Pole (I)46422/H35191 -4.8 mi EHE 4Gl Hountain Top-industrial Park-14 ml EHE'57 Perimeter Fence-0.3 mi E SE2 Bloss Farm-4.5 mi E 654 Perimeter Fence-0.2 mi ESE 6A4 Former State Police-0.6 mi ESE Sasq)ing and Collection Fr uenc Continual sampler operation<<ith sample collection weekly.'Quarterly Type and uenc o Ana s Radioiodine Canister: analyze weekly for l-l3l Particulate Sample: Analyze for gross beta radioactivity less than 24 hours following filter change.Perform isotopic analysis on canposite sample (by location)quarterly. Gaane Dose: Quarterly. Ã) Page 2 of 3 Exposure Pathways a 0 e Hmaber of Samples~&&I~~ld O&C&&&&&1~0&I&I&& 6EI St.James Church-4.7 mi ESE 659 Perimeter Fence-0.2 mi ESE 7S6 Perimeter Fence-0.2 ml SE 7El Harwood Transmission Line Pole t2-4.2 QI SE 7GI Haz)eton Chemical Lab-14 mi SE'52 Perimeter Fence-0.2 mi SSE 882 La'Mall Residence-1.4 mi SSE BD3 Howry Residence-4.0 mi SSE 952 Security Fence-0.2 mi 5 9D4 Country Folk Store-3.6 mi 5 1051 Perimeter Fence-0.4 mi SSV 10DI Ross Ryman Farm-3.0 mi SSV 1153 Security Fence-0.3 ml SV IIEI Thomas Residence-4.7 mi SM 1253 Perimeter Fence-0.4 mi MSV 12E1 Berwick Hospital-4.7 mi VSM 1261 Bloomsburg -15 mi'MSV'3S2 Perimeter Fence-0.4 mi V 1364 Kessler Farm-4.I mi'M 1455 Site Pole 43996/il34230 0.5 mi MN 14E1 Canouse Farm-4.1 mi VN 15FI 2awatski Farm-5.4 mi N 1555 Perimeter Fence-0.4 mi N 1651 Perimeter Fence-0.3 mi HN 16S2 Perimeter Fence-0.3 mi HN 16F1 Hidlay Residence (Huntington Hills)-7.8 NN Saw@ling and Co ection Fr uenc Type and gaiCr or&&Surface Drinking Sediment fran Shoreline 656 river water intake line'57 cooling tower.blowdown discharge line 12H2 Danville Mater Co.(Approximately 30 miles downstream) 78 Bell Bend-1.2 mi SE Honthly composite Honthly composite Honthly composite Semi-annually Gaaae Isotopic analysis.Coayosite tritium analysis at least quarterly. Gross beta and ganma isotopic analyses monthly.Composite for tritium analysis at least quarterly. Gamna Isotopic analysis semi-annually.

Page 3 of 3 Exposure Pathways III 1k~'~Hmuber of Sax@les~hh ocstlal*1283 Young Farm-2.0 mi MSM IOGI Oavls Fare-14 mi.SSW'481 Stola Farm-1.8 ml.MNg 10D1 Ryman Farm-3.0 mi.SSM San@I Ing and Co lection Semi-monthly <<hen animals are on pasture, monthly otherwise Type and r uenc o Ana s Galena isotopic and 1-131 analysis of each sample.Fish and invertebrates Food Products Outfall area 2H Falls.PA'Approximately 30 mi HNE)1101 Zehner Farm-3.3.mi SM vegetable 12F7 Luplni Farm-8.3 mi MSM vegetable Semi-annually. One sample'rom each of t<<o reacreationally important species from any of the folio<<ing families: bullhead catfish.sunfish, pikes.or perches.At time of harvest Gaama isotopic on edible portions.Gamna isotopic on edible portions.<<The location of samples and equipment were designed using the guidance in the Branch technical Position to NRC Rev.Guide 4.8, Rev.1, Hov.1979, Reg.Guide 48.1975 and ORP/S10 72-2 Environmenta) Radioactivity Surveillance Guide.Therefore, the airborne sampler locations were based upon X/0 and/or 0/Q.~'A dust loadin A dust loading study (RHC-TR-81-01) concluded that the assumption of I for the transmission correction factor for gross beta analysis of air particulate samples Is valid.Air particulate samples need not be weighed to determine a transmission correction factor."lf a milk s 1 sample is unavailab)e for more than two sampling periods from one or more of the locations, a vegetation sample shall be substituted until a suitable milk location is evaluated. Such an occurrence wi11 be'documented In the REHP annual report.4 Control samp)e location.b Two-week composite If calculated doses due to consumption of water exceed one millirem per year.In these cases, 1-131 analyses wi)1 be performed. c The sample collector wi11 determine the species based upon availability,<<hich may vary seasonally and yearly. PENNSYLVANIA POWER 5 LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE OOSE CALCULATION MANUAL Prepared By 4'~~LCD~~Date I>/'F~Reviewed By Reviewed By Approved By Supervisor-Environmental Services Nuclear eetsng o.a er-Nuclear Technology Date (Z~Z.Date/N+PP~Date

SUMMARY

OF ODCM CHANGES Changes other than those of a minor, editorial nature are summarized below.A correction to the Maximum Pathway Dose Factor (Page 4-1)table for gaseous tritium (H-3)is submitted. The basis for this correction, which is made for the H-3/vegetation ingestion pathway, is discussed in PLI-72980 (11/24/92). This document is referenced on page 20.2.The Maximum Pathway Dose Factor table for I-134 is submitted as an addition (new page 4-29)to the ODCM.Although the offsite dose from I-134 would not be the subject of routine operational effluent dose calculations, due to its short half-life (52.6 minutes), the isotope is used in certain design basis calculations. It is included herein to permit consistency in calculations performed using certain design basis source terms.Isotope tables subsequent to that for I-134 have been renumbered to accommodate this addition, and are included in this submittal., 3.Changes performed herein will not reduce the accuracy or reliability of dose calculations or setpoint determinations in accordance with Technical Specification 6.14.2.a.2.

LIST OF TABLES~Pa e Revision Date Table 1 Table 2 Table 3 Radiological Effluent Objectives and Standards.. 3 Dose Factors for Noble Gases................... 18 Sample Annual Average Relative Concentrations and Deposition Rates............................ 19 12/11/89 2/21/92 12/11/89 Table 4 Dose Factors for Inhalation, Ingestion and Ground Exposure Pathways: Radionuclides Other Than Noble Gases....................... 20 Table 5 Waterborne Effluent Dose Parameters for Adults..24 12/4/92 12/11/89 Table 6 Operational Radiological Environmental Monitoring Program....... ................ 44 45 46 11/25/92 11/25/92 11/25/92 Table 7 Detection Capabilities for Environmental Sample Analysis................................. 47 48 Table B-1 Radiological Environmental Monitoring Program Annual Summary.........,........................ B-3 Table B-2 Reporting Levels for Nonroutine Operating R eports~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~B 4 Table D-1 Dilution Factors and Transit Times for SSES Effluents to Danville, PA................ .....D-3 2/21/92 2/21/92 12/11/89 12/11/89 2/21/92 LIST OF FIGURES Revision~Pa e~ate Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Liquid Radwaste System Flow Oiagram......... 34 Offgas and Recombiner System Flow Oiagram... 35 Solid Waste Management System Flow Oiagram..36 SSES Ory Contaminated Waste Processing...... 37 Environmental Monitoring Locations Within One Mile of SSES.....'.........42 Environmental Monitoring Locations Greater than One Mile from SSES....43 3/6/92 2/21/92 2/21/92 2/21/92 11/25/92 11/25/92 CST C. TABLE 4 DOSE FACTORS FOR INHALATION, INGESTION AND GROUND EXPOSURE PATHWAYS: RADIONUCLIDES OTHER THAN NOBLE GASES(1)(2)(1)Reference letter R.K.Barclay to File R9-5: Technical Documentation of Lotus 1-2-3 ODCHTAB and TGTHSTR files: Gaseous Dose Factor Calculation using NUREG-0133/Reg. Guide 1.109 Hethodology, PLI 69605, ll/8/91.(2)Reference letter R.K.Barclay to File R9-5: Technical Documentation: ODCHTAB.MKl Revision 1 Correction of Tritium in Vegetation Pathway Dose Calculations Factor Algorithms, PLI 72980, 11/24/92.20 k1~1%I k@c l O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: H-3 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOBOO CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEw00 O.OOE+00 O.OOE+00 INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 GOAT MILK ADULT TEEN CHILD INFANT O.OOE+00 1.38E+03 O.OOE+00 1.80E+03 O.OOE+00 2.84E+03 O.OOE+00 4.31E+03 1.38E+03 1.80E+03 2.84E+03 4.31E+03 1.38E+03 1.80E+03 2.84E+03 4.31E+03 1.38E+03 1.80E+03 2.84E+03 4.31E+03 1.38E+03 1.80E+03 2.84E+03 4.31E+03 1.38E+03 1.80E+03 2.84E+03 4.31E+03 N/A N/A N/A N/A COW MILK MEAT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT O.OOE+00 6.77E+02 6.77E+02 6.77E>02 6.77E>02 6.77Et02 6.77E+02 O.OOE+00 8.82E+02 8.82E+02 8.82E+02 8.82E+02 8.82E+02 8.82E+02 O.OOE+00 1.39E+03 1.39E+03 1.39E+03 1.39E+03 1.39E+03 1.39E+03 O.OOE+00 2.11E+03 2.11E+03 2.11E+03 2.11E+03 2.11E+03 2.11E+03 O.OOE+00 2.89E+02 2.89E+02 2.89E+02 2.89E+02 2.89E+02 2.89Ew02 O.OOE+00 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 O.OOE+00 2.08E+02 2.08E+02 2.08E+02 2.08E+02 2.08E+02 2.08E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A N/A N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT O.OOE+00 1.82E+03 1.82E+03 1.82E+03 1.82E+03 1.82E+03 1.82E+03 O.OOE+00 2.18E+03 2.18E+03 2.18E+03 2.18E+03 2.18f+03 2.18E+03 O.OOE+00 3.42E+03 3.42E+03 3.42E+03 3.42E+03 3.42E+03 3.42E+03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A TOTAL ADULT INGEST.TEEN CHILD INFANT O.OOE+00 4.17E+03 O.OOE+00 5.03E+03 O.OOE+00 7.86E+03 0.00E+00 6.43E+03 4.17E+03 4.17E+03 4.17E+03 4.17E+03 4.17E+03 5.03E+03 5.03E+03 5.03E+03 5.03E+03 5.03E+03 7.86E+03 7.86E+03 7.86E+03 7.86E+03 7.86E+03 6.43E+03 6.43E+03 6.43E+03 6.43E+03 6.43E+03 N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT O.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 O.OOE+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 O.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 O.OOE+00 6.47E+02 6.47f+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 N/A N/A N/A N/A LIV.ODY THYROID KIDNEY LUNG G.SK*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec

- - MAXIMUM VALUES FOR PATHWAYS**~

GROUND: GROUND: GOAT COW TOTAL T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: 0.00000 O.OOE+00 4.31E+03 2.11E+03 2.89E+02 3.42E+03 7.86E+03 INHAL.1.27E003 PAGE: 4-1 ~l'N'2 4>>R>>gl 0 O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: I-134 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN, CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 GOAT MILK COW MILK ADULT TEEN CHILD INFANT 1.09E-12 2.96E-12 1.06E-12 1.94E-12 5.13E-12 1.84E-12 4.58E-12 8.51E-12 3.92E-12 7.92E-12 1.95E-11 6.92E-12 ADULT 5.08E-13 1.38E-12 4.94E-13 TEEN 9.03E-13 2.39E-12 8.60E-13 CHILD 2.14E-12 3.97E-12 1.83E-12 INFANT 4.43E-12 9.08E-12 3.23E-12 5.13E-11 8.55E-11 1.96E-10 4.54E-10 2.39E-11 3.99E-ll 9.13f-ll 2.12E-10 4.71E-12 8.09E-12 1.30E-11 2.18E-11 1l 2.20E-12 3.77E-12 6.07E-12 1.02E-11 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.58E-15 6.76E-14 5.64E-12 2.01E-11 1.20E-15 3.15E-14 2.63E-12 9.39E-12 N/A N/A N/A N/A N/A N/A N/A N/A MEAT ADULT TEEN CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00000 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A VEGTBLE ADULT 3.19E-05 8.65E-05 3.10E-05 1.50E-03 1.38E-04 O.OOE+00 TEEN 2.88E-05 7.63E-05 2.74E-05 1.27E-03 1.20E-04 O.OOE+00 CHILD 5.12E-05 9.50E-05 4.37E-05 2.19E-03 1.45E-04 O.OOE+00 INFANT O.OOE+00 O,OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.54E-08 1.01E-06 6.30E-05 O.OOE+00'/A N/A N/A N/A TOTAL INGEST.INHAL.ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 3.19E-05 8.65E-05 3.10E-05 1.50E-03 1.38E-04 O.OOE+00 2.88E-05 7.63E-05 2.74E-05 1.27E-03 1.20E-04 O.OOE+00 5.12E-05 9.50E-05 4.37E-05 2.19E-03 1.45E-04 O.OOE+00 1.24E-11 2.85E-11 1.02E-11 6.66E-10 3.19E-11 O.OOE+00 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+00 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+00 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+00 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+00 7.54E-08 1~01E-06 6.30E-05 2.95E-11 1.019 00 2.04E+01 9.55&02 1.29E003'/A N/A N/A N/A N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec

~MAXIMUM VALUES FOR PATHWAYS***

GROUND: GROUND: GOAT COW TOTAL T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL.O.OOE+00 O.OOE+00 4.54E-10 2.12E-10 O.OOE+00 2.19E-03 2.19E-03 5.07E+04 PAGE: 4-29 'W 1~t I AI n 4 F O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Cs-134 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND GOAT MILK ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 1.06E+10 2.53E+10 1.85E+10 4.35E+10 4.26E+10 6.99E+10 2.29E+10 1.28E+11 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79Et09 2.07E+10 O.OOE+00 8.19E+09 2.72E+09 4.43E+08 2.02E+10 O.OOE+00 1.38E+10 5.27E+09 5.41E+08 1.47E+10 O.OOE+00 2.17E+10 7.77E+09 3.77E+08 1.29E+10 O.OOE+00 3.30E+10 1.35E+10 3.48E+08 7.92E+09 7.92E+09 7.92E+09 7.92E+09 N/A N/A N/A N/A COW MILK MEAT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 2.79E+09 6.63E+09 5.42E+09 O.OOE+00 2.15E+09 7.12E+08 1.16E+08 4.84E+09 1.14E+10 5.28E+09 O.OOE+00 3.62E+09 1.38E+09 1.42E+08 1.12E+10 1.83E+10 3.86E+09 O.OOE+00 5.68E+09 2.04E+09 9.87E+07 1.80E+10 3.35E+10 3.39E+09 O.OOE+00 8.63E+09 3.54E+09 9.11E+07 3.59E+08 8.54E+08 6.98E+08 O.OOE+00 2.76E+08 9.17E+07 1.49E+07 2.85E+08 6.71E+08 3.12E+08 O.OOE+00 2.13E+08 8.15E+07 8.35E+06 5.03E+08 8.26E+08 1.74E+08 O.OOE+00 2.56E+08 9.18E+07 4.45E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A N/A N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INFANT 4.21E+09 6.70E+09 1.53E+10 O.OOE+00 1.80E+10 3.03E+10 6.96E+10 4.09E+10 1.00E+10 8.19E+09'.OOE+00 3.24E+09 1.08E+09 1.75E+08 1.58E+10 7.31E+09 O.OOE+00 5.01E+09 1.91E+09 1.96E+08 2.52E+10 5.31E+09 O.OOE+00 7.80E+09 2.80E+09 1.36E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.28E+10 3.50E+10 O.OOE+00 1.39E+10 4.60E+09 7.49E+08 7.13E+10 3.31E+10 O.OOE+00 2.27E+10 8.65Ew09 8.87&08 1.14E+l1 2.41E+10 O.OOE+00 3.54E+10 1.27E+10 6.16E+08 1.62E+l1 1.63E+10 O.OOE+00 4.16E+10 1.70E+10 4.39E+08 N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 3.73E+05 8.48E+05 7.28E+05 O.OOE+00 2.87E+05 9.76E+04 1.04E+04 N/A 5.02E+05 1.13E+06 5.49E+05 O.OOE+00 3.75E+05 1.46E+05 9.76E+03 N/A 6.51E+05 1.01E+06 2.25E+05 O.OOE+00 3.30E+05 1.21E+05 3.85E+03;N/A 3.96E+05 7.03E+05 7.45E+04 O.OOE+00 1.90E+05 7.97E+04 1.33E+03N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec ~~MAXIMUM VALUES fOR PATHWAYS*** GROUND: GROUND: GOAT COW T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: 6.79E+09 7.92E+09 1.28E+ll 3.35E+10 8.'54E+08 2.52E+10 TOTAL INGEST: 1.62Etll INHAL.1.13E+06 PAGE: 4-30 P4~'5 2p p I. O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: I-135 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND GOAT MILK ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.93E+03 1.82Et04 1.23E+04 3.17E+04 2.92E+04 5.25E+04 5.05E+04 1.21E+05 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 6.70E+03 1.18E+04 2.48E+04 4.40E+04 1.20E+06 2.91E+04 O.OOE+00 2.04f+06 5.01E+04 O.OOE+00 4.65E+06 8.05E+04 O.OOE+00 1.08E+07 1.34E+05 O.OOE+00 2.05E+04 3.51E+04 4.00E+04 4.37E+04 N/A N/A N/A N/A O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00000 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 COW ADULT MILK.TEEN CHILD INFANT 3.24f>03 8.47E+03 3.13E+03 5.59E+05 1.36E+04 O.OOE+00 5.75E+03 1.48Et04 5.48E+03 9.52Ew05 2.34E+04 O.OOE+00 1.36E+04 2.45E+04 1.16E+04 2.17E+06 3.75E+04 O.OOE+00 2.83E+04 5.63E+04 2.05E+04 5.05E+06 6.27E+04 O.OOE+00 9.57E+03 1.64E+04 1.87E+04 2.04E+04 N/A N/A N/A N/A HEAT ADULT TEEN CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A.N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INFANT 1.29E+04 3.37E+04 1.24E+04 2.22E+06 5.40E+04 O.OOE+00 1.16E+04 2.99E+04 1.11Ew04 1.92E+06 4.73E+04 O.OOE+00 2.06E+04 3.72E+04 1.76E+04 3.29E+06 5.70E+04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OODOO O.OOE+00 2.30E+04 6.03E+04 2.23E+04 3.98E+06 9.67E+04 O.OOE+00 2.97E+04 7.64E+04 2.83E+04 4.92E+06 1.21E+05 O.OOE+00 6.34E+04 1.14E+05 5.40E+04 1.01&07 l.'75E+05 O.OOE+00 7.88E+04 1.77E+05 6.45E+04 1.59E+07 1.97E+05 O.OOE+00 3.80E+04 3.32E+04 2.83E+04 O.OOE+00 6.81E+04 8.47E+04 8.70E+04 6.40E+04 N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 2.68E+03 6.98E+03 2.57Et03 4.48E+05 l.11E+04 O.OOE+00 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+00 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 0.DOE+00 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 O.OOE+00 5.25E003 6.95003 4.44E+03 1.83003 N/A N/A N/A N/A B NE LI R T.BODY THYROID KIDNEY LUNG G.I.SKI*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec ~y GROUND'ROUND: T.B./ORG.SKIN O.OOE+00 O.OOE+00~~~MAXINUN VALUES FOR PATHWAYS*** GOAT COW TOTAL MILK: MILK: HEAT: VEGTBLE: INGEST-'NHAL 1.08E+07 5.05E+06 O.OOEw00 3.29f+06 1.59E+07 7.92Et05 PAGE: 4-31 E:l A O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Cs-136 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN CHILD INFANT 1.49E+08 1.49E+08 1.49E+08 1.49B08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69BOB 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 GOAT MILK ADULT TEEN CHILD INFANT 3.57E+08 1.41E+09 1.01E+09 O.OOE+00 7.84E+08 1.07E+08 6.07E+08 2.39E+09 1.61E+09 O.OOE+00 1.30E+09 2.05E+08 1.37E+09 3.77E+09 2.44E+09 O.OOE+00 2.01E+09 2.99E+08 8.93E+08 7.88E+09 2.94E+09 O.OOE+00 3.14E+09 6.42E+08 1.60E+08 1.92E+08 1.32E+08 1.20E+08 N/A N/A N/A N/A COW ADULT MILK TEEN CHILD INFANT 6.69E+07 2.64E+08 1.90E+08 O.OOE+00 1.47E+08 2.02E+07 1.14E+08 4.48E+08 3.01E+08 O.OOE+00 2.44E+08 3.85E+07 2.57E+08 7.07E+08 4.58E+08 O.OOE+00 3.77E+08 5.62E+07 5.02E+08 1.48E+09 5.52E+08 O.OOE+00 5.89E+08 1.20E+08 3.00E+07 3.61E+07 2.48E+07 2.24E+07 N/A N/A N/A N/A MEAT ADULT TEEN CHILD INFANT 4.00E+06 1.58E+07 1.14E+07 O.OOE+00 8.78E+06 1.20E+06 3.12E+06 1.23E+07 8.24E+06 O.OOE+00 6.68E+06 1.05E+06 5.38E+06 1.48E+07 9.57E+06 O.OOE+00 7.87E+06 1.17E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.79E+06 9.87E+05 5.20E005 O.OOE+00 N/A N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INFANT 2.03E+07 8.01E+07 5.76E+07 0.00E+00 4.46E+07 6.11E+06 2.43E+07 9.58E+07 6.43E+07 O.OOE+00 5.21E+07 8.22E+06 4.96E+07 1.36E+08 8.82E+07 O.OOE+00 7.26E+07 1.08E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.48E+08 1.77Et09 1.27Ew09 O.OOE+00 9.84E+08 1.35E+08 7.49E+08 2.95E+09 1.98E+09 O.OOE+00 1.60Ew09 2.53Ew08 1.68E+09 4.63E+09 2.99E+09 O.OOE+00 2.46E+09 3.67E+08 1.40E+09 9.35E+09 3.49E+09 O.OOE+00 3.73009 7.62E+08 9.10E+06 7.71E+06 4.79E+06 O.OOE+00" 2.01E+08 2.37E+08 1.63E+08 1.42E+08 N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 3.90E+04 1.46E+05 1.10E+05 O.OOE+00 8.56E+04 1.20E+04 5.15E+04 1.94E+05 1.37E+05 O.OOE+00 1.10E+05 1.78E+04 6.51E+04 1.71E+05 1.16E+05 O.OOE+00 9.55E+04 1.45E+04 4.83E+04 1.35E+05 5.29E+04 O.OOE+00 5.64E+04 1.18E+04 1.17E+04 1.09E+04 4.18E+03 1.43E+03 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec

- MAXIMUM VALUES GROUND: GROUND: GOAT COW T.B./ORG.SKIN MILK: MILK: 1.49E+08 1.69E+08 7.88E+09 1.48E+09 FOR PAT WAYS~**TOTAL MEAT: VEGTBLE: INGEST: 1.58Et07 1.36E+08 9.35E+09 INHAL.1.94E<05 PAGE: 4-32.

I P 41 A"'Aj O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Cs-137 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.19E+10 TEEN 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.19E+10 CHILD 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.19E+10 INFANT 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.02E+10 1.19E+10 GOAT MILK COW MILK MEAT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 1.42E+10 1.94E+10 1.27E+10 O.OOE+00 6.59E+09 2.19E+09 2.58E+10 3.43E+10 1.19E+10 O.OOE+00 1.17E+10 4.53E+09 6.20E+10 5.94E+10 8.77E+09 O.OOE+00 1.94E+10 6.96E+09 3.30E+10 1.16E+ll 8.22E+09 O.OOE+00 3.11E+10 1'.26E+10 3.78E+09 5.17E+09 3.39E+09 O.OOE+00 1.76E+09 5.84E+08 6.86E+09 9.12E+09 3.18E+09 O.OOE+00 3.10E+09 1.21E+09 1.65E+10 1.58E+10 2.33E+09 O.OOE+00 5.15E+09 1.85E+09 2.64E+10 3.09E+10 2.19E+09 O.OOE+00 8.28E+09 3.35E+09 4.91E+08 6.71E+08 4.40E+08 O.OOE+00 2.28E+08 7.58E+07 4.08E+08 5.42E+08 1.89E+08 O.OOE+00 1.85E+08 7.17B07 7.51E+08 7.19E+08 1.06E+08 O.OOE+00 2.34E+08 8.42E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEw00 3.76E+08 4.88E+08 3.72E+08 3.62E+08 1.00E+08 1.30E+08 9.90E+07 9.65E+07 1.30E+07 7.72E+06 4.50E+06 O.OOE+00 N/A N/A N/A N/A N/A N/A N/A N/A N/A.N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INfANT 5.76E+09 7.88E+09 5.16E+09 O.OOE+00 2.68E+09 8.89E+08 9.58E+09 1.27E+10 4.44E+09 O.OOE+00 4.34E+09 1.69E+09 2.29E+10 2.19E+10 3.24E+09 O.OOE+00 7.15E+09 2.57E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.42E+10 3.32E+10 2.17E+10 O.OOE+00 1.13E+10 3.74E+09 4.26E+10 5.67E+10 1.97E+10 O.OOE+00 1.93E+10 7.49E+09 1.02E+ll 9.79E+10 1.44E+10 O.OOE+00 3.19E+10 1.15E+10 5.94E+10 1.47E+11 1.04E+10 O.OOE+00 3.94E+10 1.60E+10 1.53E+08 1.81E+08 1.37008 0.00E+00'.420 08 8.06E+08 6.13E+08 4.59E+08 N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 4.78E+05 6.21E+05 4.28E+05 O.OOE+00 2.22E+05 7.52Et04 6.70E+05 8.48005 3.11Et05 O.OOE+00 3.04E+05 1.21E+05 9.07E+05 8.25Et05 1.28E+05 O.OOE+00 2.82E+05 1.04E+05 5.49E+05 6.12E005 4.55E+04 O.OOE+00 1.72E+05 7.13&04 8.40E+03 8.48E+03 3.62E+03 1.33B.03.- N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN<<Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec <<~MAXIMUM VALUES FOR PATHWAYS<<~ GROUND: GROUND: GOAT COW TOTAL T.B./ORG.SKIN.MILK: MILK: MEAT: VEGTBLE: INGEST: 1.02E+10 1.19E+10 1.16E+ll 3.09E+10 7.51E+08 2.29E+10 1.47E+ll INHAL.9.07E+05 PAGE: 4-33 P l g l 0 O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*'SOTOPE: Ba-140 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN CHILD INFANT 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.32E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.32E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.32E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.32E+07 GOAT MILK COW MILK ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 1.46E+06 1.83E+03 2.63E+06 3.22E+03 6.35E+06 5.56E+03 1.09E+08 1.3lf+04 6.83E+06 8.58E+03 1.23E+07 1.51E+04 2.97E+07 2.61E+04 6.12E+07 6.12E+04 9.54E+04 O.OOE+00 6.22E+02 1.05E+03 3.00E+06 1.69E+05 O.OOE+00 1.09E+03 2.17E+03 4.05E+06 3.70E+05 O.OOE+00 1.81E+03 3.31E+03 3.22E+06 6.73E+05 O.OOE+00 3.10E+03 8.02E+03 3.21E+06 4.47f+05 O.OOE+00 2.92E+03 4.91E+03 1,41E+07 7.94E+05 O.OOE+00 5.12E+03 1.02E+04 1.90E+07 1.74E+06 O.OOE+00 8.48E+03 1.55E+04 1.51E+07 3.15E+06 O.OOE+00 1.45E+04 3.76E+04 1.50E+07 N/A N/A N/A N/A N/A N/A N/A N/A MEAT ADULT TEEN CHILD INFANT 9.52E+06 1.20E+04 6.24E+05 O.OOE+00 4.07E+03 6.85E+03 1.96E+07 7.87E+06 9.65E+03 5.07E+05 O.OOE+00 3.27E+03 6.49E+03 1.21E+07 1.45E+07 1.27E+04 8.48E+05 O.OOE+00 4.14E+03 7.59E+03 7.36E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT 5.98E+07 7.51E+04 3.92E+06 O.OOE+00 2.55E+04 4.30E+04 1.23E+08 7.50E+07 9.19E+04 4.83E+06 O.OOE+00 3.12E+04 6.18E+04 1.16E+08 1.62E+08 1.42E+05 9.48E+06 O.OOE+00 4.63E+04 8.48E+04 8.23E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A TOTAL ADULT INGEST.TEEN CHILD INFANT 7.76E+07 9.78E+07 2.13E+08 1.70E+08 9.75E+04 5.08E+06 O.OOE+00 3.31E+04 5.58E+04 1.20E+05 6.31E+06 O.OOE+00 4.07E+04 8.06E+04 1.87E+05 1.24E+07 0.00E+00 6.08E+04 1.11E+05 7.43E+04 3.83E+06 O.OOE+00 1.76E+04 4.56E+04 1.60E+08 1.51E+08 1.08E+08 1.82E+07 N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 3.90E+04 5.47E+04 7.40E+04 5.60E+04 4.90E+01 6.94E+01 6.48E+01 5.60E+01 2.57E+03 O.OOE+00 1.67E+01 3.52Ew03 O.OOE+00'2.28E+01 4.33E+02 O.OOE+00 2.11E+01 2.90E+03 0.00E+00 1.34E+Ol 1.27B.06 2.18E+05 2.03E+06 2.29E+05 1.74E+06 1.02E+05 1.60E+06 3.84E+04 N/A N/A N/A N/A BO LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec r*~~MAXIMUM VALUES FOR PATHWAYS~~ GROUND: GROUND: GOAT COW TOTAL T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL.2.03E+07 2.32E+07 1.09E+08 6.12E+07 1.96E+07 1.62E+08 2.13B08 2.03E+06 PAGE: 4-34 Pp J l, g(I l'5 O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: La-140 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0:OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 GOAT MILK COW MILK MEAT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 2.44E-01 1.23E-01 3.25E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.38E-01 2.15E-01 5.72E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.05E+00 3.66E-01 1.23E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.82E+Ol 8.63E-Ol 2.22E-01 O.OOE+00,0.00E+00 O.OOE+00 1.14E+00 5.73E-Ol 1.51E-01 0.00900 O.OOE+00 O.OOE+00 2.04E+00 1.00E+00 2.67E-Ol O.OOE+00 O.OOE+00'.OOE+00 4.89E+00 1.71E+00 5.76E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.02E+01 4.03E+00 1.04E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.22E-02 6.16E-03 1.63E-03 O.OOE400 O.OOE+00 O.OOE+00 1.01E-02 4.94E-03 1.32E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.84E-02 6.44E-03 2.17E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 9.02E403 1.24E+04 1.02E+04 1.01E+04 4.21E+04 5.76E+04 4.76E+04 4.73E+04 4.53E+02 2.84f+02 1.79E+02 0.00E+00 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A VEGTBLE ADULT Tf EN CHILD INFANT TOTAL ADULT INGEST, TEEN CHILD INFANT 6.53Ew02 3.29E+02 8.69E+Ol O.OODOO O.OOE+00 O.OOE+00 5.96E+02 2.93E+02 7.79E+Ol O.OOE+00 O.OOE+00 O.OOE+00 1.07E+03 3.74E+02 1.26f+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.54E+02 3.30E+02 8.71E+Ol O.OOE+00 O.OOE+00 O.OOE+00 5.99E+02 2.94E+02 7.83E+01 O.OOE+00 O.OOE+00 0.00f+00 1.08E+03 3.76E+02 1.27E+02 O.OOE+00 O.OOE+00 O.OOE+00 2.85E+01 4.89E+00 1.26E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.41E+07 1.68E+07 1.04E+07 O.OOE+00 2.42Ew07 1.69E+07 1.05E+07 5.74E+04 N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 3.44E+02 1.74E+02 4.58E+01 0.00E+00 0.00E+00 1.36E+05 4.79E+02 2.36E+02 6.26E+Ol O.OOE+00 O.OOE+00 2.14E+05 6.44E+02 2.25E+02 7.55E+01 0.00E+00 0.00E+00 1.83E+05 5.05E+02 2.00E+02 5.15E+01 0.00E+00 0.00E+00 1.68E+05 4.58E+05 4.87E+05 2.26E+05 8.48E+04 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec <<<<<<MAXIMUM VALUES fOR PATHWAYS<<<<<< GROUND: 'ROUND: GOAT COW TOTAL T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL.0.00E+00 0.00E+00 1.24E+04 5.76E+04 4.53E+02 2.41E+07 2.42E+07 4 87B.05 PAGE: 4-35 K;L's E 1 M I K I'I~g'i~i';hat'V O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*.ISOTOPE: Ce-141 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN CHILD'NFANT 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.52E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.52E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 l.'35E+07 1.52E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.52E+07GOAT MILK COW MILK MEAT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 2.78E+02 1.88E+02 2.13E+01 O.OOE+00 8.73E+Ol O.OOE+00 5.10E+02 3.40E+02 3.91E+Ol O.OOE+00 1.60E+02 O.OOE+00 1.26E+03 6.26E+02 9.30E+Ol O.OOE+00 2.75E+02 O.OOE+00 2.07E+04 1.52E+03 1.79E+02 O.OOE+00 4.68E+02 O.OOE+00 1.41E+03 9.51E+02 1.08E+02 O.OOEi00 4.42Ew02 O.OOE+00 2.58E+03 1.72E+03 1.98E+02 O.OOE+00 8.11E+02 O.OOE+00 6.35E+03 3.17E+03 4.70E+02 O.OOE+00 1.39E+03 O.OOE+00 1.26E+04 7.68E+03 9.04E+02 O.OOE+00 2.37E+03 O.OOE+00 5.11E+03 3.46E+03 3.92E+02 O.OOE+00 1.61E+03 O.OOE+00 4.29E+03 2.87E+03 3.29E+02 O.OOE+00 1.35E+03 O.OOE+00 8.08E+03 4.03E+03 5.99E+02 O.OOE+00 1.77E+03 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.19E+05 9.74E+05 7.81B 05 7.84E+05 3.64E+06 4.93E006 3.95006 3.97606 1.32E+07 8.20E+06 5.03E+06 0.00f+00 N/A N/A N/A N/A N/A N/A N/A N/A N/A'/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INFANT 1.49E~OS 1.0 I f>05 2.38E>05 1.59E+05 5.73005 2.86E+05 O.OOE+00 O.OOE+00 1.56E+05 1.06E+05 2.46E+05 1.64E+05 5.89E+05 2.94E+05 3.33E+04 9.20E+03 1.14E+04 1.83E+04 4.25E+04 O.OOE+00 1.20E+04 1.88&04 4.36E+04 1.08E+03 O.OOE+00 4.69E+04 O.OOE+00 O.OOE+00 7.49E+04 O.OOE+00 O.OOE+00 1.25E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.90E+04 O.OOE+00 0.00E+00 7.72E+04 0.00E+00 O.OOE+00 1.29E+05 O.OOE+00 O.OOE+00 2.84E+03 O.OOE+00 3.86E+08 4.55E+08 3.57E+08 O.OOE+00 4.03E+08 4.69E+08 3.67&08 4.75E+06 N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT'EEN CHILD INFANT 1.99E+04 1.35E+04 1.53E+03 O.OOE+00 6.26E+03 3.62005 2.84E+04 1.90E+04 2.17E+03 O.OOE+00 8.88E+03 6.14E+05 3.92Et04 1.95E+04 2.90E+03 O.OOE+00 8.55E+03 5.44E+05 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 1.20E+05 1.26Ew05 5.66E+04 2.16E+04 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec

~MAXIMUM VALUES FOR PATHWAYS***

GROUND: GROUND: GOAT COW TOTAL T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL.1.35E+07 1.52E+07 9.74E+05 4.93E+06 1.32E+07 4.55E+08 4.69E+08 6.14E+05 PAGE: 4-36 ~el.>~5 C*4 l~e O.D.C.M.HAXIHUH PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Pr-143 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOBOO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEw00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 GOAT MILK ADULT TEEN CHILD INFANT 8.57E+00 3.44E+00 4.25E-Ol O.OOE+00 1.98E+00 O.OOE+00 3.75E+04 1.57E+01 6.28E+00 7.83E-01 O.OOE+00 3.65E+00 O.OOE+00 5.18E+04 3.89E+Ol 1.17E+Ol 1.93E+00 O.OOE+00 6.33E+00 O.OOE+00 4.20E+04 6.71E+02 3.01E+Ol 3.99E+00 O.OOE+00 1.12E+Ol O.OOE+00 4.25E+04 N/A N/A N/A N/A COW MILK ADULT TEEN CHILD INFANT 4.02E+01 7.39E+01 1.83E+02 3.78E+02 1.61E+01 1.99E+00 O.OOE+00 9.31E+00 O.OOE+00 2.95E+Ol 3.68E+00 O.OOE+00 1.71E+Ol O.OOE+00 5.49E+01 9.07E+00 O.OOE+00 2.97E+Ol O.OOE+00 1.41E+02 1.87E+01 O.OOE+00 5.26E+Ol O.OOE+00 1.76E+05 2.43E+05 1.97E+05 2.00E+05 N/A N/A N/A N/A HEAT ADULT TEEN CHILD INFANT 6.96E+03 2.79E+03 3.45E+02 O.OOE+00 1.61E+03 O.OOE+00 3.05E+07 5.86E+03 2.34E+03 2.92E+02 O.OOE+00 1.36E+03 O.OOE+00 1.93E+07 l.11E+04 3.33E+03 5.50E+02 O.OOE+00 1.80E+03 O.OOE+00 1.20E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT 3.04E+04 1.22E+04 1.51E+03 O.OOE+00 7.04E+03 O.OOE+00 1.33E+08 4.00E+04 1.60E+04 1.99E+03 O.OOE+00 9.27E+03 O.OOE+00 1.31E+08 8.98E004 2.69E+04 4.45E+03 O.OOE+00 1.46E+04 O.OOE+00 9.68E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00f+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A TOTAL INGEST, ADULT 3.74E+04 1.50E+04 1.86E+03 O.OOE+00 8.67E+03 O.OOE+00 1.64E+08 TEEN 4.59E+04 1.83E+04 2.28E+03 O.OOE+00 1.07E+04 O.OOE+00 1.51E+08 CHILD 1.01E+05 3.03E+04 5.01E+03 O.OOE+00 1.64E+04 O.OOE+00 1.09E+08 INFANT'.05E+03 1.72E+02 2.27E+Ol O.OOE+00 6.38E+Ol O.OOE+00 2.42E+05 N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 9.36E+03 3.75E+03 4.64E+02 O.OOE+00 2.16E+03 2.81E+05 2.00E+05 1.34E+04 5.31E+03 6.62E+02 O.OOE+00 3.09E+03 4.83E+05 2.14E+05 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec

- - MAXIMUM VALUES FOR PATHWAYS**~

GROUND: GROUND: GOAT COW T.B./ORG.SKIN MILK: MILK: HEAT: VEGTBLE: 0.00E+00 0.00E+00 5.18E+04 2.43E+05 3.05E+07 1.33E+08 TOTAL INGEST: INHAL.1.64E+08 4.83E+05 PAGE: 4-37 OAV p5+ O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Ce-144 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG'G.I.SKIN GROUND ADULT TEEN CHILD INFANT 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 7.96E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 7.96E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 7.96E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 7.96E+07 GOAT MILK COW MILK MEAT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 2.60E+04 1.09E+04 1.39E+03 O.OOE+00 6.44E+03 O.OOE+00 8.78E+06 4.78E+04 1.98E+04 2.57E+03 O.OOE+00 1.18E+04 O.OOE+00 1.20E+07 1.18E+05 3.69E+04 6.28E+03 O.OOE+00 2.04E+04 O.OOE+00 9.63E+06 1.41E+06 6.91E+04 9.46E+03 O.OOE+00 2.79E+04 O.OOE+00 9.68E+06 1.65E+05 6.91E+04 8.88E+03 O.OOE+00 4.10E+04 O.OOE+00 5.59E+07 3.04E+05 1.26E+05 1.63E+04 O.OOE+00 7.52E+04 O.OOE+00 7.65E+07 7.50E+05 2.35E+05 4.00E+04 O.OOE+00 1.30E+05 O.OOE+00 6.13E+07 1.07E+06 4.40E+05 6.02E+04 O.OOE+00 1.78E+05 O.OOE+00 6.17E+07 7.55E+05 3.16E+05 4.05E+04 O.OOE+00 1.87E+05 O.OOE+00 2.55E+08 6.36E+05 2.63E+05 3.42E+04 O.OOE+00 1.57E+05 O.OOE+00 1.60E+08 1.20E+06 3.76E+05 6.40E+04 O.OOE+00 2.08E+05 O.OOE+00 9,80E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INFANT 2.94E+07 1.23E+07 1.58E+06 O.OOE+00 7.30E+06 O.OOE+00 9.95E+09 4.95E+07 2.05E+07 2.66E+06 O.OOE+00 1.22E+07 O.OOE+00 1.24E+10 1.21E+08 3.80E+07 6'6E+06 O.OOE+00 2.10E+07 O.OOE+00 9.90E+09 O.OOE+00 O,OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.04E+07 1.27E+07 1.63Et06 O.OOE+00 7.53E+06 O.OOE+00 1.03E+10 5.05E+07 2.09E+07 2~71E+06 O.OOE+00 1.25E+07 O.OOE+00 1.27E+10 1.23E+08 3.86E+07 6.57E+06 O.OOE+00 2.14E+07 O.OOE+00 1.01E+10 2.48E+06 5.09E+05 6.97E+04 O.OOE+00 2.06E+05 O.OOEw00 7.14E+07 N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 3.43f+06 1.43Et06 1.84E+05 O.OOE+00 8.48E+05 7.78E+06 8.16E+05 4.89E+06 2.02E+06 2.62E+05 O.OOE+00 1.2IE+06 1.34E+07 8.64905 6.77E+06 2.12E+06 3.61E+05 O.OOE+00 1.17E+06 1.20E+07 3.89E+05 3.19E+06 1.21E+06 1.76E+05 O.OOE+00 5.38E+05 9.84606 1.48E+05 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec GROUND: GROUND: T.B./ORG.SKIN 6.88E+07 7.96E+07**>>MAXIMUM VALUES FOR PATHWAYS*>>>> GOAT COW MILK: MILK: MEAT: VEGTBLE 1.20E+07 7.65E+07 2.55E+08 1.24E+10 TOTAL INGEST'.27E+10 INHAL.1.34E+07 I DAT PAGE: 4-38 SE A I e O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Pr-144 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 GOAT MILK COW MILK MEAT VEGTBLE ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A'/A N/A N/A N/A N/A TOTAL ADULT INGEST.TEEN CHILD INFANT O.OOE+00 O.OOE+00 0.00f+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00, O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 3.01E-02 4.30E-02 5.96E-OZ 4.79E-02 1.25E-02 1.53E-03 O.OOBOO 7.05E-03 1.76E-02 2.18E-03 O.OODOO 1.01E-OZ 1.85E-02 3.00E-03 O.OOE+00 9.77E-03 1.85E-02 2.41E-03 O.OOE+00 6.72E-03 1.02E003 2.15E-08 1.75E+03 2.35E-04 1.57E+03 1.97Ew02 1.61E+03 4.28Ew03 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec

- ~MAXIMUM VALUES FOR PATHWAYS~~~

GROUND: GROUND: GOAT COW TOTAL T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL.O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.28E+03 PAGE: 4-39 OAT nfl h&aA O.D.C.M.MAXIHUH PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Nd-147 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND ADULT TEEN CHILD INFANT 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 9.97E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 9.97E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 9.97E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 9.97E+06 GOAT HILK COW MILK ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 5.09E+00 5.89E+00 3.52E-01 O.OOE+00 3.44E+00 O.OOE+00 9.80f+00 1.07E+Ol 6.38E-01 O.OOE+00 6.26E+00 O.OOE+00 2.40E+Ol 1.95E+01 1.51E+00 O.OOE+00 1.07E+Ol O.OOE+00 3.97E+02 4.90E+Ol 3.00E+00 O.OOE+00 1.89E+Ol O.OOE+00 2.38E+Ol 2.75E+Ol 1.65E+00 O.OOE+00 1.61E+Ol O.OOE+00 4.58E+01 4.98E+Ol 2.98E+00 O.OOE+00 2.93E+Ol O.OOE+00 1.12E+02 9.11E+01 7.05E+00 O.OOE+00 5.00E+01 O.OOE+00 2.23E+02 2.29E+02 1.40E+01 O.OOE+00 8.82E+Ol O.OOE+00 2.83E004 3.84E+04 3.09E+04 3.10E+04 1.32E+05 1.80E+05 1.44E+05 1.45E+05 N/A N/A N/A N/A N/A N/A N/A N/A HEAT ADULT TEEN CHILD INFANT VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INFANT 2.34E+03 2.70E+03 1.62E+02 O.OOE+00 1.58E+03 O.OOE+00 2.06E+03 2'4E+03 1.34E+02 O.OOE+00 1.31E+03 O.OOE+00 3.86E+03 3.13E+03 2.42E+02 O.OOE+00 1.72E+03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.39E+04 1.61E+04 9.61E+02 O.OOE+00 9.39E+03 O.OOE+00 1.72Ew04 1.87E+04 1.12E+03 O.OOE+00 1.10E+04 O.OOE+00 3.65E+04 2.95E+04 2.29f+03 O.OOEt00 1.62E+04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.63E+04 1.88E+04 1.12E+03 O.OOE+00 1.10E+04 O.OOE+00 1.93E+04 2.10E+04 1.26E+03 O.OOE+00 1.23E+04 O.OOE+00 4.05E+04 3.28E+04 2.54E+03 O.OOE+00 1.80E+04 O.OOE+00 6.20E+02 2.78E+02 1.70E+Ol O.OOE+00 1.07E+02 O.OOE+00 1.30E+07 8.08E+06 4.96E+06 O.OOE+00 7.71E>07 6,74E+07 4.68E+07 O.OOE+00 9.03E+07 7.57E+07 5.19E+07 1.76E+05 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 5.27E+03 6.10E+03 3.65E+02 O.OOEt00 3.56E+03 2.21E+05 7.86E+03 8.56E+03 5.13E+02 O.OOE+00 5.02E+03 3.72E+05 1.08B04 8.73E+03 6.81E>02 O.OOE+00 4.81Et03 3.28E+05 7.94E+03 8.13003 5.00E+02 O.OOE+00 3.15E+03 3.22E+05 1.73005 1.82Ew05 8.21E+04 3.12E+04 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium'ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-m2/yr/uCi/sec "*~MAXIMUM VALUES FOR PATHWAYS*~ GROUND: GROUND: GOAT CDW TOTAL T.B./ORG.SKIN MILK: MILK: HEAT: VEGTBLE: INGEST: INHAL.8.31E+06 9.97E+06 3.84E+04 1.80E+05 1.30E+07 7.71E+07 9.03E+07 3.72E+05 PAGE: 4-40 nate' Ill%K! O.D.C.M.MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES*ISOTOPE: Np-239 PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN GROUND GOAT MILK ADULT TEEN CHILD INFANT ADULT TEEN CHILD INFANT 1.98E-01 1.95E-02 1.08E-OZ O.OOE+00 6.08E-OZ O.OOE+00 3.79E-01 3.57E-02 1.98E-02 O.OOE+00 1.12E-01 O.OOE+00 9.32E-01 6.69E-02 4.70E-02 O.OOE+00 1.93E-01 O.OOE+00 1.64E+01 9.96E-02 9.96E-02 O.OOE+00 3.51E-01 O.OOE+00 4.00E+03 5.74E+03 4.95E+03 5.09B 03 N/A N/A N/A N/A O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O,OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 COW MILK ADULT TEEN CHILD INFANT 9.26E-01 9.10E-OZ 5.02E-02 O.OOE+00 2.84E-01 O.OOE+00 1.77E+00 1.67E-01 9.25E-02 O.OOE+00 5.23E-01 O.OOE+00 4.35E+00 3.12E-01 2.19E-01 O.OOE+00 9.02E-01 O.OOE+00 9.19E+00 8.22E-0 1 4.64E-01 0.OOE+00 1.64E+00 0.OOE+00 1.87E+04 2.68E+04 2.31E+04 2.38E+04 N/A N/A.N/A N/AMEAT ADULT TEEN CHILD INFANT VEGTBLE ADULT TEEN CHILD INFANT TOTAL ADULT INGEST.TEEN CHILD INFANT 8.54E-02 8.40E-03 4.63E-03 O.OOE+00 2.62E-02 O.OOE+00 7.47E-02 7.04E-03 3.91E-03 O.OOE+00 2.21E-02 O.OOE+00 1.41E-01 1.01E-02 7.09E-03 O.OOE+00 2.92E-OZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.71E+02 4.63E+01 2.55E+01 O.OOE+00 1.45E+02 O.OOE+00 4.57E+02 4.31Et01 2.40001 O.OOE+00 1.35E+02 O.OOEw00 8.44E+02 6.06E+01 4.26E+Ol O.OOE+00 1.75E+02 O.OOBOO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.72E+02 4.64E+Ol 2.56E+Ol O.OOE+00 1.45E+02 O.OOE+00 4.60E+02 4.33E+01 2.41E+01 O.OOE+00 1.36E+02 O.OOE+00 8.50E+02 6.10E+01 4.29E+Ol 0.00E+00 1.76E+02 0.00E+00 2.56E+01 9.22E-Ol 5.64E-01 O.OOE+00 1.99Ew00 O.OOE+00 1.72E+03 1.13Ew03 7.47E+02 O.OOBOO 9.50E+06 6.94E+06 4.49E+06 O.OOE+00 9.53E+06 6.97Ew06 4.52E+06 2.89E+04 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A INHAL.ADULT TEEN CHILD INFANT 2.30E+02 2.26E+01 1.24E+Ol O.OOE+00 7.00E+Ol 3.76E+04 3.38E+02 3.19E+01 1.77E+01 0.00E+00 1.00E+02 6.49E+04 4.66E+02 3.34E+01 2.35E+01 O.OOE+00 9.73E+01 5.81004 3.71Et02 3.32E+Ol 1.88E+01 O.OOE+00 6.62E+01 5.95E+04 1.19E+05 1.32E005 6.40E+04 2.49E+04 N/A N/A N/A N/A BONE LIVER T.BODY THYROID KIDNEY LUNG G.I.SKIN*Airborne pathways and tritium ingestion: units are mrem/yr/uCi/m3 Deposition pathways: units are mrem-mZ/yr/uCi/sec

~*MAXIMUM VALUES FOR PATHWAYS"~

GROUND: GROUND: GOAT COW TOTAL T.B./ORG.SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: O.OOE+00 O.OOE+00 5.74E+03 2'8E+04 1.72E+03 9.50E+06 9.53E+06 INHAL.1.32E+05 PAGE: 4-41 ~~PAGE 1 OF 2 REG.GUIDE 1.109.ISTOPE INPUT DATA DATE RUN: 11/18/92~4 IWC Zf II/I I/y2 VERIFIED 8:/DATE: APTURE****DATA C TIME: ISOTOPE: LAMBDA: Biv: Fm(COW): Ff: Fm(GOAT)E7bone E71iver E7TB E7Thy E7Kidn E7Lung E7GI E8bone ESliver E8TB ESThy ESKidn ESLung ESGI E9bone E91iver E9TB E9Thy E9Kidn E9Lung E9GI E10bone E101i ver E10TB ElOThy E10Kidn E10Lung E10GI 5.26E+01 1-134 2.20E-04 2.00E-02 6.00E-03 2.90E-03:6.00E-02 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 O.OOE+00 1.26E-10 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 O.OOE+00 2.55E-09 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 O.OOE+00 2.58E-07 6.58E-07 1.34E-.06 4.75E-07 3.18E-05 1.49E-06 O.OOE+00 9.21E-07 ~~PAGE 2 OF 2 REG.GUIDE 1.109 ISTOPE INPUT DATA ISOTOPE: I-134 DATE RUN:11/18/92 7~rM~/>-VERIFIEDED BY:/DATE: El lbone El ll i ver E11TB EllThy El lKi dn El lLung E11GI E12bone E121 iver E12TB E12Thy E12Ki dn E12Lung E12GI E13bone E131 iver E13TB E13Thy E13Kidn E13Lung E13G I E14bone E14l i ver E14TB E14Thy E14Ki dn E14Lung E14GI'6TB E6Skin ANST ANST 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00 2.51E-10 1.46E-Q7 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 O.OOE+00 5.16E-07 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+00 1.84E-06 1.60E-08 1.90E-08 1.00E+00 2.08E+09 CH NGES TO THE SOLID WASTE PROCESS CONTROL PROGRAM The SSES Solid Radioactive Waste Process Control Program has been redesignated as NDAP-gA-0646. This change was a result of an Operational Effectiveness Review (OER), which reorganized radioactive waste processing activities under the new fffluents Management organization. NDAP-(A-0646, Revision 0, was approved by the PORC during the report period.A copy of the Process Control Program is attached.The procedure revision summary on page 2 of the Process Control Program describes other previously approved changes that have been incorporated. 118 't C 4't PROCEDURE COVER SHEET q,P Klieg NUCLEAR DEPARTMENT PROCEDURE pe~c~~rc s<" SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM NDAP-QA-0646 Revision 0 Page 1 of 61 EFFECTIVE DATE: PERIODIC REVIEW FREQUENCY: Z PERIODIC REVIEW DUE DATE: REVISED PERIODIC REVIEW DUE DATE: 8-SS-7 PROCEDURE TYPE: QA Program (~)YES ()NO Plant Procedure (7"j YES (.)NO APPROVAL METHOD: ('Alternate (~)Committee (PogC.)TYPE Prepared by Reviewed by Recommended Pat Sgervi s I G.Date 8/-Z 0 Date" 14 Committee Meeting No.r Approved by Functional Unit a ger ZI+i-'~Wc'~.Date FORM NDAP-QA-0002-I.Rev.0, Page 1 of 1 lNBNlBllJIgl!EggggN tISINMSN TITLE: PROCEOURE REVISION

SUMMARY

SOL 10 RAOIOACTIYE WASTE'OCESS CONTROL PROGRAM NOAP-IIA-0646 Revision 0 Page 2 of 61 1.New Issue 2.The contents of the following procedures, which describe the Solid Radioactive Waste Program, have been incorporated into this NOAP: NOI-(A-6.5.1, Low Level Radwaste AO-I1A-311, Solid Radioactive Waste Process Control Program AO-OA-765, Solid Radwaste Program 3.Chanoes in responsibility section to reflect new OER re-organization-Effluents Management. 4.Added Solid Sealed Sources as a new waste type.Incoronrated PCdF'-9!-!081 to add underwater vacu'...to cartridge filter~aste type.6.7.8.9.Incorporated PCAF 1-92-0432 to.add.new high integrity container type, incorporate volume reduction'services offered and update PCP implementing procedures. Incorporated PILAF 1-92-0548 to dewatering record sheet to show documentation for 10 CFR 61 composite sample.Incorporated PCAF 1-92-0866 to provide analyses guidelines for mixing of waste types/streams within one waste container. Incorporated. PCP surveillance specimen requirements to Radioactive Waste Solidification Section, per BTP on Waste Form, Revision 1. SECTION 1.0 PURPOSE 2.0 POLICY/DISCUSSION

3.0 REFERENCES

4.0 RESPONSIBILITIES

TABLE OF CONTENTS NDAP-QA-0646 Revision 0 Page 3 of 61 PAGE 4.1:F;"LUEttTS MANAGEHENT SUPERVISOR

4.2 SUPEPVISOR

-OPERATIONS TECHNOLOGY 4.3 Pv'lr".r RODUC I IOfi ENGINEER-EFFLUEtPTS MANAGEMENT

4.4 HEALTH

PHYSICIST-EFFLUENTS MANAGEMENT 4.5 RAD's!ASTE SUPERVISOR

4.6 CHEt1ISTRY

SUPERVISOR 4.7 HP FOREt1AN-EFFLUENTS HANAGEHENT

4.8 ttuCLE'R

QUALITY ASSURANCE 4.9~".CILIARY SYSTEMS OPERATOR 4.10 SOLIDIFICATION/DEWATERING/SERVICES VENDOR 4.11 MANAGER-NUCLEAR PROCUREMENT 4.12 tlANAGER-NUCLEAR SYSTEHS ENGINEERING 4.13 MAN"GER-NUCLEAR MAINTENANCE-4.14 MANAGER-NUCLEAR REGULATORY AFFAIRS 4.15 MANAGER-NUCLEAR TRAINING 4.I f MANAGER-NUCLEAR SECURI TY 5.0 DEF-IN I T Iotas 10 10 12 13 13 13 14 14 14 15 15 15 15 SECTION 6.0 PROC'EDURE TABLE OF CONTENTS CONTINUED HOAP-QA-0646 Revision 0 Page 4 of 61 PAGE 19 6.1 CONTRACTED VENDOR SERVICES 6.2 WASTE TYPES 6.3 RADIOACTIVE WASTE ANALYSIS AND Cl.ASSIFICATION 6.4 T ST it'G"'F."ATt1ENT OF SOLIDIFIED RAOWASTE,FOR COMBUST!BLE GASES 6.5 RADIOACTIVE WASTE SOLIDIFICATION

6.6 RADIOACTIVE

WASTE DEWATERING 6.7 HIGH}t<TEGRITY CONTAINERS (HIC)6.8 iPF:~DIATED HARDWARE PROCESSING AND DEWATERING

6.9 CONTA

INER l ASPECT IONS 6.10 WASTE COt<TA INER SPACE: UTIL I'ZATION 5.'l l STORAGE OF PACKAGED RADIOACTIVE WASTE 6.12 TRANSPORTATION, SHIPPING AND:DISPOSAL REGULATIONS '6.13 SHI PP!ttG OF RADIOACTIVE'ASTE 6.14 SH IPtlENT CONF I RUAT ION 6.15 CHANGES TO THE SOLID RADIOACTIVE. WASTE PROCESS CONTROL PROGRAM 6.16 EVALUATION OF PROCESS OR OPERATIONAL CHANGES 6.17 REPORTING OF HISHAPS INVOLVING LOW LEVEL WASTE FORMS 6.18r PCP IMPLEMENTING PROCEDURES r 7.0 RECORDS 19 20 25 28 28 40 45 45 46 46 47.48,5Q 50 50 51 52 52 ATTACHMENT ATTACHMENTS NOAP-gA-0646 Revision 0 Page 5 of 61 PAGE A Solidification Record Sheet B Oewatering Record Sheet C Susquehanna Guaranteed Solidified/Oewatered Waste Volume Record PCP Implementing Procedure Matrix 54 55 58 59 1'V Ig+ 1,0 PURPOSE NDAP-gA-0646 Revision 0 Page 6 of 61 Provide aoministrative control, guidance and records for the processing, packagina.

ransportation, and disposal of Low Level Radwaste.This procedure.: the Process Control Program required by SSES Technical Speci ficat,ious.

2.0 POLICY

OISCUSSION This proceoure is applicable to Low Level Radwaste (LLRW)generated as a result, of t.",-aoeration of the Susquehanna Steam Electric Station lSSES)..">e i si.e streams include solid and liquid waste as defined in the 1'SAR.:.::o not include spent fuel or greater than Class C waste.EFFicient c=.~eration and processing of LLRW is very important to the overall ooe:i'on of SSES.An important objective with respect to LLRW oenerat on: io minimize the volume of waste generated. The processing of larae vciumes of waste can result in the inability to dispose of or".tore alii'.a;t=.packaged, the significant increased costs associated with increaseo waste oeneration, and the potential to over-burden the r rocessino'.'and Ji orade it~i@no ta~m reliahi litv.The Process i~.i v i;c.-=~ir ioes tne enveiope within which processing and'ackagino o'LRW is accomplished to provide reasonable assurance of compliance

.:th Low-Level Waste regulations and requirements,....

This procedure.: aoolicable to SSES instal.led systems, temporary systems and".quinm-:n': .:ed by vendors for processing, packaging, transportation, ano disposai;;aoplicable waste forms.II 0 REFERENCES 3.1 49 CFR 100-177,"Transportation" 3.2 10 CFP.20,"Standards for Protection Against Radiation".3.3 10 CFR 61."Licensing Requirement for Land Disposal of Radioactive Wast.e" 3 4 10 CFR 71."Packaging and Transportation of Radioactive Material" 3.5 40 CFR 261."Identification and Listing of Hazardous Waste" 3.6 i SSES Iechnical Specifications Section 3/4.11.3,"Solid Radwaste System-A 3.7 SSES I: ch.ical Specifications Section 6.1.3,"Process Control Prooran (PCP)" NDAP-OA-0646 Revision 0 Paae 7 of 61 3.8 3.9 3.10 3.11 3.12 3.13 3.14 3.15 NUREG 0800,"Standard Review Plan 11.4 Solid Waste Management Systems" Technical Position on Waste.Form Rev.1, 1991 Technical Position on Radioactive Waste Classification, Rev.0, 1983'Regulatory Guide 1.21,"Measuring, Evaluating and Reporting Radioactive Material in Solid Wastes and Release of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants" Regulatory Guide 1.143,"Design Guidance of Solid Waste Management Systems" Regulatory Guide 7.1,"Administrative Guide for Packaaing and Transporting Radioactive Material" ANS 40.35,"Volume Reduction of Low Level Radioactive Waste" ANS 55.1."Solid Radioactive Waste Prncessina Sv't>-fnr I baht Water Cooled Reactor Plant" 3.16 WHNI Mobile Incontainer Oewater ing and Solidification System (MOSS), Topical Report No;STD-R-05-011P-A 3.17 3.18 3.19 3.20 3.21'HNI Mobile Incontainer Oewatering and Solidification System Pr'ocess Control'Program (PCP), Report No.STO-PCP-03-003 Disposal Site Criteria for Barnwell, S.C.Disposal Site Criteria for Richland, Washington OHEC-HIC-PL-001 South Carolina Certificate of Compliance for CNSI High Integrity Containers OHEC-HIC-P0-006,"South Carolina Certificate of Compliance for CNSI Overpack High Integrity Containers" 3-22 OHEC-HIC-FRP-003,"South Carolina Certificate of Compliance for CNSI Fiberglass Reinforced Polyester 24 Inch Pressure Vessel as a , High Integrity Container"'r 3.23.DHEC-HIC-PL-005,"South Carolina Certificate of Compliance for KHNI RADLOK-100,-179, ANO-195 Containers" 3.24 OHEC-HIC-PL-004,"South Carolina Certificate of Compliance for KHNI RAOLOK-55 Container" NDAP-QA-0646 Revision 0 Page 8 of 61 3.25 DHEC-H!C-PL-014,"South Carolina Certificate of Compliance for WHNI RADLOK-500 Container-" 3.26 DHEC-HIC-PL-007."South carolina Certificate of Compliance for WHNI RADLOK-200" 3.27 DHEC-HIC-PL-010,"South Carolina Certificate of Compliance for TFC NUHIC-55,-120,-136, and-206 Containers" 3.28 PLA-1237,"Process Control Program", August 17, 1982 3.29 Review of Process Control Program for Susquehanna, Unit 1, Youngblooa to Curtis, September 30, 1982 3.30 Dewatei ing and Solidification Safety Evaluation for Mobile Radwaste System.PORC Mtg.No.82-234, November 24, 1982 3.31 IE Bullet.in 79-19,"Packaging of Low Level Radioactive Waste for Transportation and Burial" (I)3.32 NRC Information Notice No.90-.50,"Minimization of Methane Gas Generation in Plant Systems and Radwaste Shipping Containers" (2)(3)3.33 Generic Letter 91-02,"Reporting Mishaps Involving LLW Forms Prepared for Disposal" A 3.34 SOOR-1-90-148,"Barnwell Received Container Pressurized with Flammable Gas" (4)3..35 SOOR)-90-172."Incorrect-Sampling Method Used on Resin Liner" (5)3.36 SOOR 1-91-322,"Dose Rates on Container Higher Than Exepected" E~I'.1 Effluents Management Supervisor responsibilities:

4.1.1 Developing

and implementing programs and procedures for radioactive waste processing, packaging, transportation and disposal.4.1.2 Maintaining the overall radwaste program to ensure compliance with applicable radiological and shipping regulations. np 1$S Y I 4.1.3 t~DAP qr 0646 Revision 0 Paoe 9 of 61 Ensuring personnel who perform support activities such as processing, packing, and transportation of low level radioactive waste are available and meet all qualificatiom and training required by SSES procedures. 4.1.4 Collecting, maintaining, reviewing and submitting accurate data/information related to waste stream quantity and nuclide composition for inclusion into Semi-annual Radioactive Effluent Release Report and State DER-BRP quarterly Report 4.2 Supervisor 4.2.1 4.2.2-Operations Technology responsibilities: Providina technical assistance to Effluents Hanagement personnel. This includes interpretations of state.federal.and disposal facility regulations regarding new, imminent.or proposed regulatory changes governing processing, packaging, transportation, and disposal.Haintaining a current copy of local.state, federal and disoosal facility regulations pertaining to ui~posal ano t,ransportat>on or low ic.~i raa>oact.>ve waste.A.2.3 Coordinating the submittal of the Semi-annual'adioactive Effluent Release Report as per the SSES Technical Specifications.

4.2.4 Haintaining

non-process control computer software for main-frame based systems, including software vendor,.initiating program changes, and proper operation of the software.4.3 Power Production Engineer-Effluents Hanagement responsibilities: 4.3.1 4.3.2 4.3.3 Ensure procedures are adequate to provide for proper solidification and dewatering of waste.Ensure test data or rationale is available to justify applicable solidification and dewatering functions of each waste type, or any combinations, to address disposal and regulatory agencies'equirements. Evaluate services provided by various vendors to ensure contracted solidification and dewatering operations are performed in the most efficient and economical method.as required by the applicable regulatory agencies. 4.3.5 NOAP-gA-0646 Revision 0 Page 10 of 61 Perform the duties of Radwaste Supervisor as specified , in this procedure in his absence.Oefine waste streams based on generator, filtration media and means of processing. 4.3.6 Collecting, reviewing and submitting data related to the reporting of mishaps and results of PCP surveillance specimen examinations to applicable regulatory agencies.il l 4.4 Health Phvsicist-Effluents Management responsibilities:

4.4.1 Maintain

a sampling and analysis program to ensure 10 CFR 61 compliance.

4.4.2 Ensure

procedures are adequate to provide for proper packaging and shipment of waste to ensure compliance with all applicable regulations. 4 4 4.4.4 Evaluate services provided by various vendors to ensure contracted 'waste packaging, processino, and t,r ansportation services are performeo>n the most efficient and economical method, as required by applicable regulatory agencies.Perform the..duties of HP Foreman-Effluents Nanagement as.specified in.this procedure in his absence.Coordinate radioactive material evaluation of product acceptability. for disposal at specific disposal facilities.

4.5 Radwaste

Supervisor..responsibil.ities:

4.5.1 Ensure

Solidification/gewatering Equipment is operated in accordance with approved operating procedure, including vendor supplied equipment. 4.5.2 4.5'Ensure appropriate waste solidification and dewatering records are.generated. Interface. with station support groups to ensure proper implementation of process control programs. NDAP-gA-0646 Revision 0 Page 11 of 61 4.5.4 Provide direction to contractor personnel involved in solid waste processing activities including: a.Ensuring test data is available to justify specific processing techniques. b.Ensuring applicable vendor procedures and revisions are incorporated into applicable plant procedure and approved by PORC.c.Coordinating pre-processing and post-processing treatment activities. d.Evaluating services provided to ensure efficient and economical methods are used.4.5.5 4.5.6 Ensure Solidification and Oewatering operations are carried out in an ALARA manner.Interface with HP Foreman-Effluents Hanagement for liner and cask selection for solid waste shipping activities. 4.5.7 4.5.8 4.5.9 4.5.10 4.5.11 4.5.12 Jy Ensure proper marking of containers prior to filling.Ensure solidification/dewatering personnel are adequately trained per NTP-QA-42.3. Estimate classification of waste for container selection and processing method.Ensure that waste streams loaded into High Integrity Containers are sampled for radionuclide and evaluated for chemical compatibility applicable to the use of High Integrity Containers. Ensure proper inspections and documentation are complete prior to use of a High Integrity Container and ensure that container is properly used up to the point of transfer to HP Foreman-Effluents Management. Complete and process High Integrity Container User Certification Statement to ensure the container is used properly.4.6 Chemistry Supervisor responsibilities:

4.6.1 Perform

required sampling preparation and analysis in accordance with approved chemistry procedures. l HOAP-gA-0646 Revision 0 Page 12 of 61 4.6.2'erform test solidification if required.Store test solidification billet if required.4.6.3 Store samples used for dewatered waste stream analysis until associated liner is buried.4.6.4 4.6.5 4.6.6 4.6.7 Provide density of initial and final waste form.Provide the isotopic mix and concentration of isotopes detected in the material sampled for solidification or dewatering. Complete Chemistry portion of the Solidification and Oewatering Records.Ensure personnel are adequately trained per NTP-(A-41.2.

4.6.8 Provide

chemical analysis and/or treatment support as necessary for use of High Integrity Containers and liners.4.7 HP Foreman-Effluents Management responsibilities:

4.7.1 Interface

with Radwaste Supervisor for liner and cask selection and scheduling for solid waste shipping activities. 4.7.2 Complete, process, and file radioactive waste shipping documentation. ~1~~4.7.3 4.7.4 4.7.5 4.7.6.4.7.7 4.7.8 Storage of packaged radioactive waste outside the radwaste facility.Oetermine waste classification and description of solidified, dewatered, and other packaged waste.Final disposition of solidified, dewatered and other packaged waste.Ensures SSES is a registered user of applicable High Integrity Containers at specific disposal facilities. Ensures HP personnel involved with radioactive waste handling have received Radwaste Worker training per NTP-gA-42.3. Evaluate vendor services provided to ensure efficient and economical methods are used. C, I' 47~4.7.!0 NOAP-IIA-0646 Revision 0 Page 13 of 61 Complete and process Certification Statement for Disposal of High Integrity Containers as required by applicable regulatory agencies.Process and package Cartridge Filters, Dry Active Waste, and solid sealed sources.4.7.11 Collection of OAW and oily waste (10 CFR 61)samples.4.8 Nucleal Ouality Assurance responsibilities: Perform periodic audit of implementation of this program and review of radwaste service vendor's IlA Programs.4.E.." 4 Inspection of Radwaste Containers as required by applicable procedures. Ensure process controls are adhered to by inspection of test solidification, waste volumes, solidification agent additions, product acceptability checks,="ewater~ng process sequence/acceptance criteria and records review.Inspection of packaging, storage, and shipping activities, as required by applicable procedures.

4.9 Auxiiiary

Systems Operator is responsible for operating the plant soiid and liquid radwaste equipment in accordance with approved operating procedures as directed by the Radwaste Supervisor and Assistant Unit Supervisor. 4.10 Solidification/Dewatering/Services Vendor responsibilities: 4.10.1 Provide solidification, dewatering and/or volume reduction services in accordance with a valid contract for said services.4.10.2 4.10.3 Provide test data or make data available for PPEL review during vendor audits to demonstrate that their services and equipment meet the applicable regulatory and disposal facility limitations for the service they are providing. Provide training documentation to demonstrate that the personnel being provided, to conduct the applicable service, are in fact trained and knowledgeable in the applicable services. 4 4.10,4 4.10.6 4.10.7 NOAP-(jA-0646 Revision 0 Page 14 of 61 Provide procedures that are or can be placed into the SSES procedure format for the services being provided.Ensure an approved guality Assurance Program exists that covers the services being provided.The vendor shall work within the SSES guality Assurance Program when applicable. Complete applicable sections of Solidification and Oewatering Records required for each container processed. Ensure pre-qualification test data for each waste form shall be submitted to the Nuclear Regulatory Commission. 4.10.8 Provide a description of the equipment/process that is used in processing waste.4.10.9 ln in Obtain waste samples from processing equipment in accordance with approved operating procedures. Perform all pre and post treatment activities as determined by Radwaste Supervisor. 4.11 tianaaer-Nuclear Procurement responsibilities: Ensure High Integrity Containers are not exposed to ultra violet light (sunlight). 4.11.2'nsure proper material certification is complete prior..to issuance of High Integrity Containers to plant for use.4.11.3 Receipt inspection of High Integrity Containers and document review to ensure conformance. 4.11.4 Ensure Certificate of Compliance (C of C)is received with High Integrity Container. 4.12'Hanager-Nuclear Systems Engineering is responsible for providing engineering support as required for operation of assigned radwaste systems and equipment. 4.ld.Manager-Nuclear Haintenance responsibilities: 4.13.1 Calibration and maintenance of applicable equipment in Radwaste Processing Systems. fl f MA 4 K A f~p I 4.13.2 NDAP-OA-0646 Revision 0 Page 15 of 61 Provide maintenance personnel to support processing, packaaing and transportation of low level radioactive waste.4.14 Manager-Nuclear Regulatory Affairs responsibilities: 4.14.1 Submitting transportation cask user registration requests to NRC per 10 CFR 71.12.4.14.2 4.14.3 Submitting to the NRC the Semi-annual Radioactive Effluent Release Report.Coordinating and submitting to the NRC the reports required as a result of Significant Operating Occurrence Report (SOOR)events, investigations, and resolutions. 4.15 Manager-Nuclear Training responsibilities: 4.15.1 Providing training and re-training in applicable regulatory requirements to personnel directly involved in transfer, processing, packaging, storage, and su+r C'A p)/l~0p (~'.15.2 Maintaining a record of training, attendees, and subject material for all Low Level Radioactive Waste training.4.16 Manager-Nuclear Security is responsible for notifying appropriate law enforcement agencies in the event of lost radioactive material shipments. S.D~DFI 5.1" APPROVED CONTAINERS: Approved means approval issued or recognized by the NRC for use in shipment of radioactive material.5.2 BATCH: The total volume of waste contained in a liner, isolated-waste mixing tank-spent resin tank-concentrates tank or-phase separator that has been sampled for solidification/dewatering. 5.3'ILLS OF LADING: Shipping papers or manifests serving a similar~purpose and containing the information required by 49 CFR 172.202,-, 203, and 204.5.4 CARRIER: Means a person engaged in the transportation of passengers or property.(10 CFR 71.4) 0 C 5.5 5.6 5.7 5.8 NDAP-I)A-0646 Revision 0 Page 16 of 61 CERTI.FICATE OF COMPLIANCE: License requirements established by the Nuclear Regulatory Commission for the use of approved Radioactive Material Shipping Containers. CHEMICAL FORM: The chemical content of the Radioactive Material being shipped.CLOSED TRANSPORT VEHICLE: A vehicle equipped with a securely attached exterior enclosure, which during normal transport, restricts the access of unauthorized persons to the cargo space.(49 CFR 173-403[C]) COMPOSITE SAMPLE: A mixture of samples collected representing conditions at time of sampling, from the same sampling point, at different times.=.9 CONSIGNEE: The individual or organization to whom the shipment is consioneo oi intended.5.10 5.11 5.12 5.13 5.14 CURING TIME: The time allowed for the solidified product to set prioi to its evaluation for product acceptability. DECAY HEAT: The heat produced by radioactive decay, usually expressed in Watts or 8TU/hr, but can be related to Curie Content.DEWATERED: The removal of free liquid from solid material to a point where less than'1%for HIC's and less than 0.5%for steel liners by waste volume remains as required by the disposal facility license.EXCLUSIVE USE VEHICLE (a/k/a: Sole Use or Full Load): Shipment from a single consignor having the exclusive use of a transport vehicle and for which all initial, intermediate,. and final loading and unloading is carried out by, or under the direction. of the=consignor, consignee, or his designated agent.(49'FR 173.403[i]) FREE LIOUID: Liquid which is still visible after solidification or dewatering is complete, or is drainable from'the low point of a pu'nctured container. 5.15 HAlARDOUS WASTE: Waste which contains material listed in 40 CFR 261, Subpart D and/or exhibits one or more of the four characteristics cited in 40 CFR 261, Subpart C, and is not~excluded from regulation under 40 CFR 261, Subpart A.5.16.HIGH INTEGRITY CONTAINER (HIC): A disposal site approved container that has an expected life of 300 years and provides the stability to meet disposal requirements. <<Ca k NDAP-QA-0646 Revision 0 Page 17 of 61 5.17 HIGHWAY ROUTE CONTROLLED QUANTITY: A quantity, the aggregate radioactivity of which~eeds that specified in (49 CFR 173.403[1]). 5.18 ISOTOPIC ANALYSIS: The identification of the isotopic elements involved in a sample of Radioactive Haterial.5.19 LABELING: Labels applied to a container denoting the contents of the container and degree of hazard associated with the containers. The labels are identified as the White I label,.the Yellow II, and Yellow III label.A label stating Radioactive -LSA can also be applied to a container when appropriate. (49 CFR 172, Subpart E)5.20 LIHITED QUANTITY OF RADIOACTIVE MATERIAL: Heans a quantity of radioactive material not exceeding the material package limits specified in 49 CFR 172.423, and which conforms with requirements specified in 49 CFR 173.421.(49 CFR 403fmj)5.21 LINER: Steel container in which dewatered or solidification product is deposited. c')')w,I QPt'r I.I'7$1Tv~hl..Vl..: Mate.ial in which the activity is essentially uniformly distributed and in which the estimated average concentration per gram of.contents does not exceed the specification as.stated in 49.CFR 173..403 (n).5.23 LOW LEVEL RADIOACTIVE WASTE (LLRW): Radioactive waste generated as a result of operation of SSES, excluding spent fuel or by product material, is classified by the NRC as low-level radioactive waste.LLRW does not include"greater than class C" waste.P~5.24 MIXING RATIO: The ratio of waste to cement and additives required.for satisfactory..solidification. 5.25 MIXING RECIPE: The amount of waste, cement and additives mixed to solidify waste.5.26 MIXED WASTE: A mixture of low level radioactive and hazardous waste.5.27 NORMAL FORM RADIOACTIVE MATERIALS: Means radioactive materials which do not meet the requirements of Special,.Form Radioactive Jlaterials. 5.28 PLACARDING: A label affixed to all four sides of the transport vehicle denoting the presence and level of Radioactive material on the vehicle.(49 CFR 172, Subpart F) 8 Tv ll pg fi NDAP-OA-0646 Revision 0 Page 18 of 61 5.29 PROCESS CONTROL PROGRAM (LICP): Program which contains the sampling, analysis, and formulation determinati,on by which solidification of radioactive wastes from liquid systems is assured.5.30 RADIOACTIVE MATERIAL: For purposes of transportation only, material in which the activity is essentially uniformly distributed and the estimated specific activity exceeds 0.002 microcuries per gram of material.(49 CFR 173.403[y] and[aa])-5.3 1 RADWASTE WORKER: Any individual involved with the collection, packaging, and transportation of radioactive waste.".;2 SEALED SOURCES: Any by-product material that is encased in a capsule designed to prevent leakage or escape of by-product material.5.33 SOLIDIFICATION: A conversion of radioactive materials from liquid and solid systems to a homogeneous (uniformly distributed) mono)ithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free~tqnfiinn> 5.34=.35 5.36 5.37 5.38 SOLIDIFIED RADWASTE: Wet waste whi'ch is solidified (e.g.evaporator concentrates,, sludge), meets.'the.'r'ee l iquid criteria, and satisfies applicable transportati'on 'and+cfispos'al site requirements. Dewatered resins or filter:sludge satisfying the two latter criteria shall als'o.be'defined"as solidified radwaste.SPECIAL FORM RADIOACTIVE MATERIALS: Radioactive'aterial that is either a single piece, or is contained'in"a seal'ed capsule, that can be opened only'e destroying the.capsule and meets the additional requirements specified.in,.49:.CFR>Part, 173.403(z). STABLE AND UNSTABL'E'WASTE"FOfNS 'Sh'all,be"defi'ne'd 'as stated in 10 CFR Part 61 and other supporting regul.atory documents. TEST SOLIDIFICATION: The mixing of waste(s)and solidification agents in the laboratory to support selection of mixing ratios and provide insurance for final product acceptability. TRANSPORT INDEX'(TI): The, dimensionless number placed on the label of a package to designate'th'e degree'f control to be.exercised by the carr ier during'ransportation. The transport index will be determined in accordance with-"49'CFR 173.403(bb). gati, 4 9) NDAP-QA-0646 Revision 0 Page 19 of 61 5.39 TYPE: "A" PACKAGING: Packaging which is designed in accordance with the general packagjgg requirements of 49 CFR 173.24, and which is adequate to prevent the loss or dispersal of the radioactive contents, and to retain the efficiency of its radiation shielding properties if'he package is subjected to the test described in 49 CFR 173.465 or 173.466, as appropriate. (49 CFR 173.403[ggj) 5.40 TYPE"A" QUANTITY RAQIOACTIVE HATERIAL: That material which may be transported in Type"A" packaging. (173.431(aj) 5.41 TYPE"5" PACKAGING: Packaging which meets the standards for Type"A" PacKaging, and in addition.meets the standaros for the hypotnetical accident conditions of transport. (49 CFR 173.403thh]) 5.42:YPE"B" QUANTITY RADIOACTIVE HATERIAL: That material which may be transported in Type"B" packagino. (173.43 1[b])5.43 WASTE STREAN: A by-product of a process system or component with unique characteristics and maintained separate from other waste st vg.yr r 5.44 WASTE TYPE: Specific contents of a liner or tank which may contain one or multiple waste streams.the category of waste suitable foi a particular means of processing. 5.45 WASTE PRE-CONDITIONING: The physical or chemical adjustment of the waste to bring it'within an established envelope to assure solidification.

6.0 PROCEDURE

6.1 CONTRACTED VENDOR SERVICES 6.1.1 6.1.2 Solidification, dewatering and volume reduction services are provided by Scientific Ecology Group (SEG)for waste types included in the Process Control Program.NRC approved Topical Report STO-R-05-01]P-A, describes Scientific Ecology Group equipment, waste processing methods and verification of acceptable waste forms for solidification and dewatering. 6.1.3 NOAP-QA-0646 Revision 0 Page 20 of 61 Other contracted vendor services which are required for solidification, dewatering and volume reduction services shell be evaluated to the requirements stated in this, Process Control Program on a case by case basis.6.2 WASTE TYPES The following waste types shall be processed in accordance with..this procedure or in combinations as defined.The waste should be dewatered whenever possible to minimize disposal volume.6.2.1 Evaporator Concentrates The following are concentrated with the Radwaste Evaporators and are considered Evaporator Concentrates waste stream: b.(1)Condensate Oemineralizer regeneration effluent (2)Oecon Shop draihs (3)Chemistry Laboratory sink drains (4)Auxiliary Boiler blowdown effluent The constituents of this waste stream may include the following: (1)Tri-Sodium Phosphate (2)Sodium Sulfate (3)Phosphoric Acid (4)Sulfuric Acid (5)Sodium Hydroxide (6)Oecontamination solutions c~(7)Negligible amounts of reagent chemicals used for chemistry analysis Evaporator Concentrates in the range of 0-25 weight percent sodium sulfate (equivalent) shall be solidified in steel liners for final disposal. SOAP-(IA-0646 Revision 0 Page 21 of 61 Evaporator Concentrates shall not be mixed with any g,her waste type in final processing. Hixed Solids.The following process waste streams are collected either in Waste Hix Tanks, Waste Sludge Phase Separator or transferred directly to a liner and are considered Mixed Solids: (I)LRW Filter Hedia and drain liquid (2)Sump Sludge (3)Ultrasonic Resin Cleaner Waste (URC Waste)b.The constituents of these waste streams may include the following: (1)Oiatomaceous Earth (2)Powdered Resins (3)Fibrous material (4)Carbon material (5)Corrosion products C.(6)Various solids and dirt in small concentrations Hixed Solids may be solidified in steel liners or dewatered in High Integrity Containers for final disposal.Sump sludge shall not be dewatered. d.Each waste stream should be processed separately. RWCU Fil ter Hedi a a.The Reactor Water Cleanup System and Fuel Pool Cooling and Cleanup System filter/demineralizer waste are collected in the RWCU Phase Separator and should be allowed to,decay for 60 days.This waste stream is considered RWCU Filter Hedia. 0'I'p NDAP-QA-0646 Revision 0 Page 22 of 61 The constituents of this waste stream may incluch.anion and cation powdered resin, corrosion and contaminants removed from the primary coolant.RWCU Filter Media shall be dewatered in High Integrity Containers. If this waste must be solidified, Technical Specification 3/4.11.3 action statement must be performed; Condensate/Radwaste Demineralizer Bead Resin a~:.~fib.e r~Resins from the Condensate Oemineralizers, Liquid Radwaste Oemineralizer and vendor provided demineralization are collected in the Spent Resin Tank or transferred directly to a liner/container: This is considered to be Condensate/Radwaste Demineralizer Bead Resin.The'onstituents of this waste stream may include various types of anion.cation.mixo6 bead resin and corrosion and, contaminates removed from liquid waste streams.', 1 Bead Resin may be solidified in steel liners or dewatered for final disposal in either steel liners or.High Integrity Containers. Bead Resin may be used to demineralize Chemical Waste ipoxy steel liners.The Bead Resin may be..solidified or dewatered for final disposal.'onde'nrate'",demineralizer bead resin should be u'itras'oni'ca'Ily'.,'cleaned prior to collection in the Spent Re'sin Tank.Bead Resin may be processed by volume reduction methods'which include drying, incineration, compaction'or use as fill materials.

~g.~.>>!oo l Cartridge Filters NDAP-9A-0646 Revision 0 Page 23 of 61 a.Cartridge Filter waste type consists of the follow>ng waste streams and constituents:

(1)CRD Filters-CRO or other filters and small un-irradiated primary system equipment such as valves, CRO lift pump filters, Rinse Tank filters and other metal components. (2)RWCU Septa-Septa from RWCU Filter Demineralizer including septa from Fuel Pool Cleanup Filter Oemineralizer. (3)(4)Radwaste Filters-including degasifier filters and other fiber or paper filters other than primary system.Underwater Vacuum Filters-non-process filters generated from wet cleaning activities. b.Cartridge Filters are collected and disposed of by emplacement in a cement matrix in a steel drum/liner or by placing in a High Integrity Container. c., Cartridge Filters to be solidified for final disposal.shall not be mixed with any other waste type.Cartridge Filters to be placed in High Integrity Containers shall be dried to a point where no free liquid is visible.Absorbent material may be included to absorb unintentional and incidental amounts of liquids.Cartridge Filters may be dewatered in High Integrity Containers if drying is impractical. Each cartridge filter waste stream should be packaged separately unless analyzed prior to packaging in accordance with the requirements of this procedure. NOAP-QA-0646 Revision 0 Page 24 of 6i irradiated Hardware a~irradiated hardware is neutron activated metal removed from the internal area of the reactor pressure vessel.This waste stream is considered Irradiated Hardware.The constituents of this waste stream may include control rod blades, LPRHS's, IRH's, TIP's and components expended during hardware processing and packaging activities. Startup sources may also be processed as part of this waste stream.Irradiated hardware is packaged in steel liners for disposal.d.Liquid shall be drained to ensure free liquid Acceptance Criteria are met.Irradiated hardware shall not be mixed with any e'sea>spt, s sile pl 0<usa Ing Ory Active Waste (OAW)I a.Ory Active Waste is a waste stream.b.The constituents of this waste stream consist of contaminated paper, plastic, wood, metal and other discarded material.C.Ory Active Waste shall be processed by volume reduction methods which may include incineration, compaction, decontamination and metal melting.d.At a minimum, OAW shall be packaged in strong-tight containers. Liquid Oil Waste or Petroleum Based Materials'a~The constituents of this waste stream may include turbine lubricating oil, EHC fluid and other petroleum based materials. Contaminated Liquid Oil Waste generated at the facility should be processed by a decontamination system, solidified for final disposal, or volume reduced by incineration, or other acceptable methods. 0 l'h}}

@@ Line 2: / Line 2: @@
 | number = ML18017A266
 | issue date = 12/31/1992
-| title = Susquehanna Steam Electric Station Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1992. W/930301 Ltr
+| title = Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1992. W/930301 Ltr
 | author name = KEISER H W
 | author affiliation = PENNSYLVANIA POWER &amp; LIGHT CO.

ML18017A266: Difference between revisions

Revision as of 20:19, 5 April 2019

Text

SUBJECT:

Dear Mr.Martin:

1.0 INTRODUCTION

7.0 TOTAL

2.1 WATERBORNE

3.0 WATERBORNE

4.0 AIRBORNE

5.0 INDIVIDUAL

6.0 INDIVIDUAL

6.1 NOBLE

8.0 OPERABILITY

8.1 LIQUID

8.3 SOLID

6.8 iRRA01'ATEO

6.8.1 General

7.3 Documentation

7.4 Radioactive

SUMMARY

SUMMARY

3.0 REFERENCES

4.0 RESPONSIBILITIES

4.2 SUPEPVISOR

4.4 HEALTH

4.6 CHEt1ISTRY

4.8 ttuCLE'R

6.6 RADIOACTIVE

6.9 CONTA

2.0 POLICY

4.1.1 Developing

4.2.4 Haintaining

4.4.1 Maintain

4.4.2 Ensure

4.5 Radwaste

4.5.1 Ensure

4.6.1 Perform

4.6.8 Provide

4.7.1 Interface

4.9 Auxiiiary

6.0 PROCEDURE

Navigation menu

Search