ML18017A266
| ML18017A266 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/31/1992 |
| From: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| To: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| PLAS-3930, NUDOCS 9303090559 | |
| Download: ML18017A266 (287) | |
Text
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.
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RECIP.'NAME RECIPIENT AFFILIATION I
SUBJECT:
"SemiAnnual luent & Waste Disposal, Rept. for July-'ec 1992." 930301 tr. D DISTRIBUTION CODE: ZE48D TITLE: 50.36a(a)(2) Effluent ReleaseJ Reports COPIES RECEIVED:LTR Semiannual ENCL L SIZE:
S NOTES:
RECIPIENT COPIES RECIPIENT COPIES A ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL-PD1-2 LA 3 3 PD1-2 PD 1 1 CLARK,R 1 1 D INTERNAL: 1 1 NRR/DRSS/PRPB11 2 2 D L Ol 1 1 RGN1 DRSS/RPB 2 2 RGN1 FILE 02 1 1 EXTERNAL: BNL TICHLER,J03 1 1 EG&G SIMPSON,F 2 2 NRC PDR 1 1 D
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl 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-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT Docket No. 50-387 PLA-3930 FILE R41-2A 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
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SUSQUEHANNA STEAM ELECTRIC STATION SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT REPORT PERIOD: 07/01/92 - 12/31/92 Prepared by:
ar son R. . Bare ay Health Physicist 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 .
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- 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 68 and the Solid Waste Process Control Program
- 6. Reports of Exception to the Honitoring Program SSES Effluent...... 165
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: Solid Radioactive Waste - Class A. . . . . . . . 25 Principal Radionuclides and Percent Composition Condensate Demineralizer/Radwaste Demineralizer-Carbon Steel Liner (Dewatered)
Table 8: Solid Radioactive Waste - Class A. 26 Principal Radionuclides and Percent Composition Condensate Demineralizer/Radwaste Demineralizer-HIC (Dewatered)
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)
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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 . 41 Stabil ity Class 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)
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LIST OF FIGURES PAGE Figure 1: SSES Airborne Effluent Release Points . . . . ~ ~ ~ ~ 5 Figure 2: SSES Waterborne Effluent Release Pathway. ~ ~ ~ ~ 6 Figure 3: Susquehanna River Honthly Average Flow Rates. ~ ~ ~ ~ 20 Figure 4: Honthly Liquid Radwaste Discharge Totals. 21 Figure 5: SSES Wind Rose: 10-meter Sensors. ~ i ~ ~ 38 Figure 6: SSES Wind Rose: 60-meter Sensors. 39 Figure 7: SSES Pasquill Stability Class Prevalences . . 40 Figure 8: Areas Within the SSES Site Boundary Open. 61 to Hembers of the Public
1 SECTION I INTRODUCTION AND SUPPLEMENTAL INFORMATION
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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).
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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.
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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.
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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 PC uCi ml 85'Kr 2.0E-04 5.0E-04 "Kr 4.0E-05 Kr 9.0E-05 "Ar 7.0E-05 133oX 5.0E-04 133X 6.0E-04 135mX 2.0E-04 135X 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.
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- 5. Methods of uantif in Effluents a ~ 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).
- b. 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.
C. Particulates: Particulates are continuously collected via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a high resolution (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.
- d. 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).
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- 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. 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)
C. ~FF UEATE:
- 1. Concentration g 10CFR20 Appendix B, Table II, Column 2
- site total "instantaneous" limits (Tech Spec. 3.11.1.1}
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- 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 OF APP T N CA SP CAT ON H 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).
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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.
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SECTION 2 EFFLUENT AND WASTE DISPOSAL DATA 13
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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. Number of Batch Releases: 0 0
- 2. Total Time Period for Hatch Release: NA NA
- 3. Maximum Time Period for a Batch Release: NA NA
- 4. Average Time Period for- a Batch Release: NA NA
- 5. Minimum Time Period for a Batch Release: NA NA Abnormal Releases
- 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 LLD uCi cc Kr-87 4.6 E-08 Kr-88 5.3 E-08 Xe-133 5.4 E-08 Xe-133m 1.3 E-07 Xe-135 1.5 E-08 Xe-138 1.2 E-07 Mn-54 2.9 E-14 Fe-59 2.8 E-14 Co-58 1.8 E-14 Co-60 3.8 E-14 Zn-65 4.4 E-14 Mo-99 3.3 E-13 Cs-134 2.4 E-14 Cs-137 2.1 E-14 Ce-141 1.5 E-14 Ce-144 7.0 E-14 I-131 4.4 E-14 I-133 2.8 E-13 Sr-89 2.0 E-15 Sr-90 3.0 E-16 H-3 2.6 E-08 Gross Alpha 5.0 E-16 14
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TABLE 2 SENIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1992)
AIRBORNE EFFLUENTS - SUMMATION OF ALL RELEASES Third Fourth A. Fission and Activation Gases Unit Quarter auarter Total Release CI 1.25E+01 4.22E+00 Average Release Rate for Period uCI/sec 1.57E+00 5.31E-01 Percent of Technical Specification Limit 1.11E-02 3.74E.03
- 8. Iodines Total 1-131 CI 8.75E-06 8.14E-06 Average Release Rate for Period uCI/sec 1 ~ 10E-06 1 '2E-06 Percent of Technical Specification Limit 4.68E-OS 4.36E-05 C. Particulates Particulates arith Half-Lives > 8 Da s Ci 1.01E-03 1.03E-030 Average Release Rate for Period uCi/sec 1.28E-04 1.29E.04 Percent of Technical Specification Limit 9.88E-04 1.00E-03 Gross Alpha Radioactivity Ci 1.55E-06 D. Tritiun 1.40E-06'otal Release Ci 2.25E+01 8.88E+00 Average Release Rate for Period uCI/sec 2.83E+00 1 ~ 12E+00 Percent of Technical Specification Limit 5.80E-02 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.
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TABLE 3 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1992)
AIRBORNE EFFLUENTS Continuous Node Continuous Node Nucl ides Released Unit Third Quarter Fourth Quarter A. Fission and Activation Gases Ar-41 Ci O.OOE+00 O.OOE+00 Kr-85m O.OOE+00 O.OOE+00 Kr-88 Ci O.OOE+00 O.OOE+00 XQ-133 Ci 1.25E+01 4.22E+00 Total for Period Ci 1.25E+01 4.22E+00 B. iodines 1-131 Ci 8.75E.06 8.14E.06 i-133 Ci O.OOE+00 O.OOE+00 1-135 Ci O.OOE+00 O.OOE+00 Total for Period Ci 8.75E.06 8.14E-06 C. Particulates Cr-51 Ci O.OOE+00 O.OOE+00 Hn-54 Ci 6.24E-04 6.96E-04 Fe-59 Ci 6.44E-OS 1.48E 04 Co-58 Ci 9.27E.05 3.50E-05 Co-60 Ci 1.69E-04 1.50E-04 Zn-65 Ci 6.35E.05 O.OOE+00 Sr-89 Ci O.OOE+00 O.OOE+00*
Sr-90 Ci O.OOE+00 O.OOE+00i Cs-134 Ci O.OOE+00 O.OOE+00 Cs-137 Ci O.OOE+00 O.OOE+00 C@.141 Ci O.OOE+00 O.OOE+00 Ce-144 Ci O.OOE+00 O.OOE+00 Total for Period Ci 1.01E.03 1.03E.03*
- Reported values are estimated based on third quarter 1992 sea@le analyses and fourth quarter 1992 ventilation exhaust rates.
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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. Number of Batch Releases: 1. 17E+02 8.60E+01
- 2. Total Time Period for Batch Releases: 1.54E+04 9. 11E+03
- 3. Haximum Time Period for a Batch Release: 2.83E+02 2.70E+02 4, Average Time Period for a Batch Release: 1.32E+02 1.06E+02
- 5. Hinimum Time Period for a Batch Release: 2.20E+01 2.00E+01
- 6. Average Stream Flow During Period of Release of Effluent into a Flowing Stream: >7.37E+03 ->7.37E+03 (Cooling Tower
- Units of time and flow are expressed in Blowdown Flow Rate) minutes and gallons per minute (gpm),
respectively.
3.73E+06 7.95E+06 (Susquehanna River Flow Rate)
Abnormal Releases
- l. Number of Releases: 0 0
- 2. Volume Released:
- 3. Total Activity Released:
NA NA 'A NA If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in the SSES Technical 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 4.5 E-08 Fe-59 5.0 E-08 Co-58 2.4 E-08 Co-60 5.4 E-08 Zn-65 4.9 E-08 Ho-99 1.7 E-07 I'-131 2.0 E-08 Cs-134 2.2 E-08 Cs-137 2.6 E-08 Ce-141 3.2 E-08 Ce-144 1.3 E-07 Sr-89 4.0 E-08 Sr-90 4.0 E-09 Fe-55 1.0 E-06 H-3 4.6 E-06 Gross Alpha 3.0 E-08 17
t lW
~ 4
'Vv
TABLE 4 SENIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1992)
WATERBORNE EFFLUENTS SUPINATION OF ALL RELEASES Third Fourth AD Fission and Activation Products Unit Quarter Quarter
- 1. Total Release (Hot Including Tritiua, Gases, Al a) Ci 2.21E-02 2.05E-03>>
- 2. Average Diluted Concentration During Period uCI/ml 4.97E-08 8.39E-09
- 3. Percent of Applicable Limit 4.36E-03 8.73E-04
- 8. Tri t iua Total Release Ci 2.42E+01 1.13E+Ol
- 2. Average Diluted Concentration During Period uCi/ml 5.46E-05 4.63E-05
- 3. Percent of Applicable Limit 1.82E+00 1.54E+00 C. Dissolved and Entrained Gases
'I. Total Release Ci 4 '9E-04 1.32E-04
- 2. Average Diluted Concentration uCi/ml 9.22E-10 5.42E-10 During Period
- 3. Percent of Applicable Limit 2.31E-03 1.35E-03 D. Gross Alpha Radioactivity
- 1. Total Release O.DOE+00 O.DOE+00 E. Volune of Maste Released (Prior to Dilution) Gal lons 1.18E+06 6.90E+05 Liters 4.47E+06 2.61E+06 F. Volune of Dilution Mater Used During Period of Release Gallons 1.16E+08 6.38E+07 Liters 4.39E+08 2.41E+08 t
G. Voluae of Dilution Mater Used Over Entire Period Gallons 9.76E+08 9.25E+08 Liters 3.70Ei09 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 Batch Hode Batch Hode Hucl ides Released Uni t Third Quarter 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 Ci 1.08E-02 4.85E-05 Hn-54 Ci 5.86E-03 9.10E-04 Fe-55 O.DOE+00 O.DOE+00*
Fe-59 Ci 1.22E.03 8.11E.05 Co-58 Ci 2.17E-04 2.05E-05 Co-60 Ci 3 '9E.03 8.94E-04 Zn-65 5.41E-04 9.23E-05 As-76 Ci 1.28E-04 O.DOE+00 Sr-89 Ci O.OOE+00 O.DOE+00*
Sr-90 Ci O.DOE+00 O.OOE+00*
Ho-99 Ci 6.66E-05 O.DOE+00 Tc-99m Ci O.OOE+00 O.DOE+00 Ag-110m Ci 1.28E-05 O.DOE+00 1.131 Ci O.DOE+00 O.DOE+00 Cs-134 Ci O.OOE+00 O.DOE+00 Cs-137 Ci 1.39E-06 2.23E-06 Ce-141 Ci O.OOE+00 O.DOE+00 M-187 1.60E-OS O.OOE+00 Total for Period 2.21E-02 2.05E-03*
B. Tritium H-3 2.42E+01 1 ~ 13E+01 Total for Period Ci 2.42E+01 1.13E+01 C. Dissolved and Entrained Gases Ar-41 Ci O.DOE+00 O.OOE+00 Kr-85m Ci O.DOE+00 O.OOE+00 Kr-85 Ci O.DOE+00 O.DOE+00 Kr-87 Ci O.DOE+00 1.06E-08 Kr-88 Ci O.DOE+00 O.DOE+00 Xe-133m Ci O.DOE+00 O.DOE+00 Xe-133 Ci 2.16E-04 7.56E-05 Xe-135m Ci 0 ~ OOE+00 O.DOE+00 Xe-135 Ci 1.93E 04 5.66E-05 Total for Period Ci 4.09E-04 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 GALLONS PER MINUTE x 1E6 14 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: CONDENSATE DEMZNERALZZER/
RADWASTE DEMINERALIZER TYPE OF CONTAINER: CARBON STEEL LINER METHOD OF PROCESS: DEWATERED ISOTOPES mCi)
'CTIVITY.+
OF TOTAL Ag-110m 0 ~ OOOE+00 0.00%
Am-241 1.300E-03 0 F 00%
C-14 '.595E+00 0.68%
Cm-242 O.OOOE+00 o.oo%
Cm-244 9.000E-04 o.oo%
Co-58 3.365E+01 3.47%
Co-60 2.113E+02 21.76%
Cr-51 O.OOOE+00 o.oo%
Cs-134 O.OOOE+00 o.oo%
Cs-137 0 ~ OOOE+00 0.00%
Fe-55 2.901E+02 29.88%
Fe-59 5.392E+00 0.56%
H-3 2.772E+01 2.85%
I-129 I-13 1
( 1.324E-01 O.OOOE+00 0.01%
o.oo%
Mn-54 2.068E+02 21.30%
Ni-63 3.426E+00 0.
PQ-238 3.500E-03 35%'.oo%
Pu-239 2.100E-03 o.oo%
Pu-241 2.000E-04 o.oo%
Sb-124 O.OOOE+00 o.oo%
Sr-89 O.OOOE+00 o.oo%
Sr-90 O.OOOE+00 o.oo%
Tc-99 4 1.087E-01 0 F 01%
Zn-65 1.857E+02 19.12%
TOTAL ACTIVITY (Ci) 0 '71 100.00%
CONTAINER VOLUME 197.500 ft3 5.593 m3 25
TABLE 8 CLASS A SOURCE OF WASTE: CONDENSATE DEMINERALIZER/
RADWASTE DEMINERALIZER TYPE OF CONTAINER: HIC METHOD OF PROCESS: DEWATERED ISOTOPES ACTIVITY (mCi) OF TOTAL Ag-llom 3.220E+00 0. 01 Am-241 5.637E-02 0.00 C-14 2.383E+02 0.79 Cm-242 0.000E+00 0.00 Cm-244 4.454E-02 0.00 Co-58 1.694E+03 5.65 Co-60 8.373E+03 27.91 4 Cr-51 3.629E+02 1 21 Cs-134 4.391E+00 0. 01 Cs-137 1.405E+Ol 0.05 Fe-55 1.114E+04 37.13 Fe-59 3.539E+02 1.18 H-3 1.917E+02 0.64 I-129 1.403E+00 0.00 I-131 1.772E+00 0 01 F
Mn-54 6.319E+03 21.06 Ni-63 1.237E+02 0 ~ 41 Pu-238 1.461E-01 0.00 4 Pu-239 8.792E-02 0.00 Pu-241 0.000E+00 0.00 Sb-124 5.043E+00 0. 02 Sr-89 0.000E+00 0. 00 Sr-90 2.928E-01 0.00 Tc-99 1.107E+00 0.00 Zn-65 1.177E+03 3.92 Xe-131m 3.093E-02 o.oo 4 Nb-95 1.754E+00 0.01 TOTAL ACTIVITY (Ci) 30.004 .100.00 CONTAINER VOLUME 2137.200 ft3 60.520 m3 26
i Ak II
TABLE 9 CLASS A SOURCE OF WASTE: ULTRASONIC RESIN CLEANING WASTE TYPE OF CONTAINER: HIC METHOD OF PROCESS: DEWATERED ISOTOPES ACTIVITY (mCi) OF TOTAL Ag-aaom 8.655E+01 0.03%
Am-241 1.181E-01 0.00%
C-14 1.964E+02 0.06%
Cm-242 8.816E-03 0.00%
Cm-244 4.870E-03 0.00%
Co-58 7.185E+02 0.22%
Co-60 2.897E+04 8.99%
Cr-51 1.169E+03 0.36%
Cs-134 O.OOOE+00 0.00%
Cs-137 7.139E+01 0 ~ 02 +o Fe-55 2.434E+05 75.51%
Fe-59 3.326E+03 1.
H-3 3.520E+01 03%'.01+
I-129 < 5.813E-01 0.004 I-131 O.OOOE+00 0.00~
Mn-54 4.023E+04 12.48%
Ni-63 3.764E+02 0.12%
Pu-238 1.750E-02 0.004 Pu-239 4.682E-02 0.004 Pu-241 3.722E+01 0.01<
Sb-124 5.987E+01 0.02%
Sr-89 0 ~ OOOE+00 0.00%
Sr-90 4.349E-01 0.00%
Tc-99 < 9.476E-01' 0.004 Zn-65 '44E+03 1. 13%
Ce-144 1.350E+02 o.04.x TOTAL ACTIVITY (Ci} 322.29? 100.00K CONTAINER VOLUME 188.900 ft3 5.349 m3 27
"l b
P W
Yi r
TABLE 10 CLASS A SOURCE OF HASTE: 'QUID RAD'HASTE FILTER MEDIA TYPE OF CONTAINER: HIC METHOD OF PROCESS: DEWATERED ISOTOPES ACTIVITY (mCi) o OF TOTAL Ag-110m 3 . 592 E+0 1 0. 01'o Am-241 9.842E-03 0. 00'o C-14 2.768E+00 0. 00~o Cm-242 8.343E-03 0.00%
Cm-244 6.370E-03 0.00%
Co-58 5.440E+03 1.41%
Co-60 2.195E+04 5.70o Cr-51 2.350E+04 6. 10%
Cs-134 O.OOOE+00 0. 00'o Cs-137 O.OOOE+00 0. 00~o Fe-55 2.130E+05 55. 33'-o
'e-59 1.622E+04 4. 21'o H-3 3.446E+01 0. 01'o I-129 I-131
( O.OOOE+00 1.821E-01 0. 00'o
- 0. 00'o Mn-54 9.501E+04 24.68':
Ni-63 5.580E+02 0. 14'o PQ-238 O.OOOE+00 0. 00~o PQ-239 O.OOOE+00 0.00%
PQ-241 O.OOOE+00 0.00o Sb-124 3.229E+02 0.08 o Sr-89 O.OOOE+00 0.00%
Sr-90 O.OOOE+00 0.00o Tc-99 1.263E-01 0. 00+o Zn-65 8 '02E+03 2. 31%
Hf=181 1.271E+02 0.03X Nb-9 5 9.308E+01 0.02K TOTAL ACT IVITY (Ci) 385.186 l.OO.OOX CONTAINER VOLUME 357.800 Ct:3 10.132 m3 28
TABLE ll CLASS A SOURCE OF WASTE: SUMP SLUDGE TYPE OF CONTAINER: CARBON STEEL'INER METHOD OF PROCESS: SOLIDIFICATION- PORTLAND CEMENT ISOTOPES ACTIVITY.+mCi) % OF TOTAL Ag-110m O.OOOE+00 0 F 00%
Am-241 O.OOOE+00 0 F 00%
C-14 5.292E+00 0.02%
Cm-242 O.OOOE+00 0.00%
Cm-244 O.OOOE+00 0 F 00%
Co-58 O.OOOE+00 0.00%
Co-60 2.731E+03 10.64%
Cr-51 O.OOOE+00 0.00%
Cs-134 1.484E+01 0.06%
Cs-137 3.378E+01 0.13%
Fe-55 2.163E+04 84.27%
Fe-59 O.OOOE+00 0.
H-3 8.397E+00 00%'.
03%
I-129 I-131
( 6.473E-02 0.00%
O.OOOE+00 .
0.00%
Mn-54 1.066E+03 4 '5%
Ni-63 7.675E+01 0.30%
Pu-238 O.OOOE+00 0.00%
Pu-239 O.OOOE+00 0.00%
Pu-241 O.OOOE+00 0.00%
Sb-124 O.OOOE+00 0.00%
Sr-89 7.143E-01 0.00%
Sr-90 4.511E-02 0 F 00%
Tc-99 C 4.803E-02 0.00%
Zn-65 1.007E+02 0.39%
TOTAL ACTIVITY (Ci) 25.668 100.00%
CONTAINER VOLUME 177.900 ft3 5.038 m3 29
TABLE 12 CLASS A SOURCE OF WASTE: PROCESSED DAW TYPE OF CONTAINER: STRONG TIGHT CONTAINER METHOD OF PROCESS: N/A ISOTOPES ACTIVITY..+mCi) OF TOTAL Ag-110m 0 ~ OOOE+00 0.004 Am-241 7.700E-03 0.004 C-14 1.676E-01 0.004 Cm-242 1.490E-02 0.004 Cm-244 4.200E-03 0.00t Co-58 2.040E+01 0.27%
Co-60 6.027E+02 7.85%
Cr-51 1.435E+01 0.19%
Cs-134 O.OOOE+00 0.00%
Cs-137 O.OOOE+00 0.00%
Fe-55 5.681E+03 74.014 Fe-59 1.295E+02 1. 694'.004 H-3 1.797E-01 I-129 7 '05E-01 0.01%
I-131 O.OOOE+00 0.004 Mn-54 1.154E+03 15.044 Ni-63 1.949E+01 0.25%
Pu-238 2.490E-02 0.004 Pu-239 5.200E-03 0. 004'.
Pu-241 1.500E+00 024'.004 Sb-3.24 O.OOOE+00 Sr-89 O.OOOE+00 0.
Sr-90 O.OOOE+00 004'.004 Tc-99 6.636E-01 0. 014'.
Zn-65 5.087E+Ol 664 TOTAL ACTIVITY (Ci) 7.676 100.004 CONTAINER VOLUME 1517.300 ft3 42.966 m3 30'
TABLE 13 CLASS A SOURCE OF WASTE: NON-PROCESSED DAW TYPE OF CONTAINER: STRONG TIGHT CONTAINER METHOD OF PROCESS: N/A ISOTOPES ACTIVITY.+mCi) OF TOTAL Ag-llom O.OOOE+00 O.OO%
Am-241 7.697E-05 0.00%
Cm-242 2.789E-05 0.00%
Cm-244 3 '57E-05 .O. OO%
Co-58 6.786E+01 0 '8%
Co-60 5.420E+02 7.01%
Cr-51 6.968E+02 9.01%
Cs-134 O.OOOE+00 0.00%
Cs-137 O.OOOE+00 0 F 00%
Fe-55 5.402E+03 69.85%
Fe-59 1.058E+02 1 ~ 37%
H-3 2.202E-02 0.00%
I-129 I-131
( 5O.OOOE+00
'13E-04 0 F 00%
0.00%
Mn-54 Ni-63 7.982E+02 10 '2%
1.323E+01 0.17%
Pu-238 2 '81E-05 O.OO%
Pu-239 2 754E-05 0.00%
Pu-241 2 '31E-02 0 F 00%
Sb-124 O.OOOE+00 0 F 00%
Sr-89 7.897E+00 0.10%
Sr-90 O.OOOE+00 0.00%
Tc-99 5.641E-04 0.00%
Zn-65 9.967E+01 1.29%
TOTAL ACTIVITY (Ci) 7.734 100.00%
CONTAINER VOLUME 210.000 f03 5.947 m3 31
TABLE 14 CLASS C SOURCE OF WASTE: RWCU FILTER MEDIA TYPE OF CONTAINER: HIC METHOD OF PROCESS: DEWATERED .
ISOTOPES ACTIVITY (mCi) OF TOTAL Ag-110m O.OOOE+00 0.00%
Am-241 2.203E-01 0.004 C-14 3.868E+00 0.004 Cm-242 2.578E-02 0.004 Cm-244 2.960E-02 0.004 Co-58 5.563E+04 2.084 Co-60 5.564E+05 20.804 Cr-51 1.416E+05 5.294 Cs-134 O.OOOE+00 0.004 Cs-137 O.OOOE+00 0.00%
Fe-55 5.&05E+05 21.70%
Fe-59 6.766K+04 2.53%
H-3 1.254E+01 0.004 I-129 3.454E+00 0.00%
I-131 O.OOOE+00 0.004 Mn-54 8.886E+05 33.22%
Ni-63 2.434E+01 0. 004'.004 Pu-238 1 485E-01 Pu-239 5.942E-02 0.004 Pu-241 1.300E+03 0.05%
Sb-124 O.OOOE+00 0~004 Sr-89 O.OOOE+00 0.004 Sr-90 7.583E+00 0.004 Tc-99 6.564E+01 0.004 Zn-65 3.&34E+05 14. 334 TOTAL ACTIVITY (Ci) 2675.300 100.004'.235 CONTAINER VOLUME 220.200 ft3 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 Fission and Activation Gases 15.9X
- b. 1-131 13.3X C. Particulates 15.8X
- d. Tri tium 13. 6X
- 2. Waterborne Effluents
'a ~ Fission and Activation Products 5.0X
- b. Tritium 3.3X C. Dissolved and Entrained Gases 8.4X
- d. Gross Alpha Activity 6.0X
- e. Volume of Waste Released 5.0X (Prior to Dilution)
- f. Volume of Dilution Water Used During 15;OX Period
- 3. Solid Wastes a ~ Condensate Demineralizer/ 15.1X Radwaste Demineralizer (Dewatered - Carbon Steel Liner)
- b. Condensate Demineralizer/ 15.1X Radwaste Demineralizer (Dewatered HIC) c ~ Liquid Radwaste Filter Media 15.1X (Dewatered HIC)
- d. RWCU Filter Media 15.1X (Dewatered HI C)
- e. Ultrasonic Resin Cleaning Waste 15.1X (Dewatered HIC)
- f. Sump Sludge Solidified with Portland 15.1X Cement
- g. Processed DAW 25.0X (Strong Tight Container)
- h. Non-Processed DAW 25.0X (Strong Tight Container) 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 ffluents
- 1. Sr-89 Ci O.OOE+00
- 2. Sr-90 Ci 0.00E+00
- 3. Gross Alpha Ci 2.24E-07 B. Waterborne Effluents
- 1. Sr-89 Ci 0.00E+00
- 2. Sr-90 Ci 0.00E+00
- 3. Gross Al ha Ci O.OOE+00 34
SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 35
R.
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 PERCENT OF
~PARACLETE VALID HOURS DURING PERIOD
- 1. Wind speed 99.8X
- a. All Sensors Combined
- b. 10-Meter Sensors 99.8X
- c. 60-Meter Sensor 99.8X
- 2. Wind direction 99.8X a..All Sensors Combined
- b. 10-Heter Sensors 99.8X
- c. 60-Heter Sensor 99.8X
- 3. Indicator of Atmospheric Stability (Primary Tower) 96.3X
- a. Temperature Differential
('A'ensor) 97.7X
- b. Temperature Differential
('B'ensor) 99.8X
- c. Sigma Theta 8 10 Heters
- 4. Percent of hours for which valid 97.7X 10-meter wind speed, 10-meter wind direction, and temperature differential were available.
97.8X
- 5. Percent of hours for which valid 60-meter wind speed, 60-meter wind direction, and temperature differential were available.
37
FIGURE 5 N
0 0
0 GALH O.O 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 a
0 s CALM O.Q ss ~g,6 ANNUAL d77 t ObQ ~
I
~@5 WINO 0 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 STABILITYCLASS PREVALENCES Data Period: 1992 Based on Joint Frequency Distributions at 10 Meters (8686 Hourly Values)
Neutral 3216 Slightly Unstable 37.46% 325
~ 3.79%
Slightly Stable Very 1770 Stable 20.61%
682 7.94%
Moderately Stable 823 9.59% Very Unstable Moderately Unstable 1441 329 16.78%
3.83%
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 CLASS A STABILITY BASED Ol: DELTA T BETMEEN 60.0 ANO 10.0 KETERS MIND KEASINED AT: 10.0 KETERS MIND TKRESHOLD AT: .23 K/S
'OINT FREOIENCY DISTRIBUTION OF MIND SPEED AND DIRECTION IH HOURS AT 10.00 KETERS SPEED (K/S) H NHE NE ENE E ESE SE SSE S SSM SM MSM M MHM HM NNM TOTAL CALK 1
.24- 1.50 14 17 25 24 30 26 22 22 22 17 15 9 1 3 0 3 250 1.51- 3.00 43 56 53 29 21 22 41 36 58 67 144 51 19 12 24 26 702 3.01- 5.00 30 25 10 2 6 2 16 8 17 16 99 84 30 30 38 38 451 5.01- 7.50 1 0 0 0 0 0 0 0 1 0 3 17 4 0 4 2 32 7.51-10.00 0 0 0 0 0 0 0 0 0 0 0 4 0, 0 0 0 4
>10.00 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 TOTAL M 98 M 55 57 50 79 66 98 100 261 165 55 45 66 69 1441 STABILITY CLASS 8 STABILITY BASED OHI DELTA T BETMEEN 60.0 AHD 10.0 KETERS IIIND KEASURED AT: 10.0 KETERS MIND THRESHOLD AT: .23 K/S JOINT FRE(NENCY DISTRIBUTION OF MIND SPEED AHD DIRECTION IH HOURS AT 10.00 KETERS SPEED (K/S) N NNE NE EHE E ESE SE SSE S SSM SM MSM M MHM HM NNM TOTAL CALK 0
.24. 1.50 5 4 12 9 11 6 6 4 3 6 1 1 0 0 77 1.51- 3.00 5 12 12 8 7 13 10 14 7 17 12 9 14 7 8 161 3.01- 5.00 3 9 4 0 0 0 4 2 6 14 10 3 5 4 7 74 5.01- 7.50 0 0 0 0 0 0 0 0 0 6 4 2 0 1 1 14
'7.51-10.00 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 2
>10.00 0 0 0 0 0 0 0 0 0 0 0 0 1 0 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 CLASS C STABILITY BASED ON: DELTA 'I BETlKEN 60.0 ANO 10.0 METERS II)NO MEASURED AT: '10.0 METERS llIMD THRESHOLD AT: .23 ll/S JOINT FREOUENCY DISTRIBUTION OF lllMD SPEED AND DIRECTION IN MRJRS AT 10.00 METERS SPEED (K/S) N NHE NE ENE E ESE SE SSE S SS'W Il MMM MM NMN TOTAL CALM 0
~ 24 1.50 2 7 17 8 8 9 3 6 8 3 0 0 0 0 0 78 1.51- 3.00 13 10 15 6 6 18 4 11 19 17 8 3 11 2 6 155 3.01- 5.00 8 4 8 0 0 3 1 4 1 21 8 7 0 3 5 73 5.01. 7.50 0 0 0 0 0 0 0 0 0 4 10 3 0 1 1 '19 7.51 10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
%10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 23 21 40 14 14 13 30 8 21 28 45 26 13 11 6 12 325 STABILITY CLASS D STABILITY BASED OH: DELTA T BETMEEH 60.0 AND 10.0 METERS MIND MEASURED AT: 10.0 KETERS llIHD THRESHOLD AT: .23 K/S .
JOINT FREOUENCY DISTRIBUTION OF llIMD SPEED AMD DIRECTION IH HOURS AT 10.00 METERS SPEED (K/S) H HHE ME EHE E ESE SE SSE S SSll Ql MSll ll MNM Mll NHll TOTAL CALM 1
.24- 1.50 40 86 117 100 81 72 67 6'7 84 76 56 12 12 6 2 11 889 1.51- 3.00 104 148 136 43 41 33 62 58 74 104 123 89 65 61 54 91 1286 3.01. 5.00 71 38 31 16 23 22 21 16 17 22 83 61 59 73 124 140 817 5.01- 7.50 5 1 14 3 3 0 3 3 4 1 22 55 36 15 23 18 206 7.51-10.00 0 0 0 0 0 0 0 0 0 0 1 9 5 0 0 0 15
%10.00 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 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 CLASS E STABILITY BASED OH: DELTA T BETHEEH 60.0 AND 10.0 HE IERS V I ND HEASURED AT 10.0 METERS HIND THRESHOLD AT: .23 H/S JOINT FREOUENCY DISTRIBUTION OF HIND SPEED AND DIRECTION IH HOURS AT 10.00 METERS SPEED (H/S) N NNE NE ENE E EsE sE ssE s ssu su usu u uMu Mu HMu TDTAL CALH 0
~ 24- 1.50 25 94, 136 221 154 107 90 74 104 96 45 21 6 6 7 6 1192 1.51- 3.00 20 45 39 26 6 2 11 23 77 110 59 14 6 4 12 28 482 3.01- 5 ~ 00 4 1 2 '5 4 2 0 2 5 3 18 15 1 2 2 7 73 5.01- 7.50 0 0 1 6 2 0 0 2 4 0 0 3 0 0 0 1 19 7.51-10.00 0 0 0 4 0 0 0 0 0 0 0 0 0 0 0 0 4
>10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 49 140 178 262 166 111 101 101 190 209 122 53 13 12 21 42 1770 STABILITY CLASS F STABILITY BASED OH: DELTA T BETHEEN 60.0 AMD 10.0 METERS HIND IIEASURED AT: 10.0 METERS HIND THRESHOLD AT: .23 H/S.
JOINT FREOUENCY DISTRIBUTIOH OF uIHD SPEED AND DIRECTION IH HOURS AT 10.00 HETERS SPEED (H/S) N HME ME EHE E EsE sE ssE s ssu su usu u uMH Hu HNH T0TAL CALH 0
.24- 1.50 7 19 102 286 140 52 24 30 27 24 8 3 0 0 2 2 726 1.51- 3.00 4 8 13 46 1 0 1 1 1 4 8 3 0 1 2 3 96 3.01- 5.00 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 41 5.01- 7.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.51-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
%10.00 0 0 0 0 0 0 0 0 0 0 0 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 STAB!LITT CI.ASS 0 STABILITY BASED OH2 DELTA T SETMEEN 60.0 AHD 10.0 NETERS IIIND HEASURED AT: 10.0 NETERS MIND THRESHOLD AT2 .23 N/S JOINT FREOUEHCY DISTRIBUTION OF MIND SPEED AHD DIRECTION IN HmlRS AT 10.00 HETERS SPEED (N/S) H HHE NE EHE E ESE SE SSE S SSM SM 'MSM M MHM NM NN'M TOTAL CALH 0
.24- 1.50 3 16 67 395 89 13 13 13 5 2 0 I 2 0 0 621 1.51. 3.00 0 1 6 53 1 0 0 0 0 0 0 0 0 0 0 61 3.01- 5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.01- 7.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.51-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
>10.00 0 0 0 0 0 0 0 0 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 SIABILITT CLASS ALL STABILITY BASED OH2 DELTA T BETMEEH 60.0 AHD 10.0 HETERS MIND NEASUREO At! 10.0 NETERS MIND THRESHOLD AT: .23 II/S JOINT FREQUEHCT DISTRIBUTION OF MIND SPEED AHD DIRECTION IH HOURS AT 10.00 HETERS SPEED (N/S) H HNE HE EKE E ESE SE SSE S SSM SM MSM M MNM NM HHM TOI'AL CALH 2
.24. 1 ~ 50 96 243 476 1043 513 283 231 213 251 229 132 51 21 18 11 22 3833 1.51- 3.00 189 280 274 211 83 76 143 136 228 310 368 177 102 103 101 162 2943 3.01- 5.00 116 77 55 23 33 26 44 29 49 45 235 178 101 110 '171 '197 1489 5.01. 7.50 6 1 15 9 5 0 3 5 9 1 35 89 45 15 29 23 290 7.51.10.00 0 0 0 4 0 0 0 0 0 0 1 15 5 0 0 0 25
>10.00 0 0 0 0 0 0 0 0 0 0 0 2 1 1 0 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: 121 TOTAL NINIBER OF OBSERVATIOHS MITH BACKUP DATA: 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 A 88 98 88 55 57 50 79 66 98 100 261 165 55 45 66 69 B 13 25 . 28 17 18 19 20 20 16 15 40 34 15 21 12 16 C 23 21 40 14 14 13 30 8 21 28 45 26 13 11 6 12 0 220 273 298 162 148 127 153 144 179 203 285 228 177 155 203 260 E 49 140 178 262 166 111 101 101 190 209 122 53 13 12 21 42 F 11 27 115 332 141 52 25 31 28 28 16 6 1 1 4 5 G 3 17 73 448 90 13 13 13 5 2 2 0 1 2 0 0 TOTAL 407 601 820 1290 634 385 421 383 537 585 771 512 275 247 312 404
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 CLASS A STABILITY BASED ON: DELTA T BETMEEN 60.0 AND 10.0 KETERS MlkD KEASURED AT: 60.0 KETERS MlkD THRESHOLD AT: .23 N/S JOINT FREOUENCY DISTRIBUTION OF MIND SPEED AND DIRECTION IN HOURS AT 60.00 KETERS SPEED (K/S) H NHE NE EHE E ESE SE SSE S SSM SM MSM M MNM HM HHM TOTAL CALK 0
.24. 1 ~ 50 4 10 20 18 23 9 12 7 6 15 11 4 2 0 1 1 143 1 ~ 51- 3.00 24 47 33 28 18 14 12 14 29 40 56 27 6 7 12 15 382 3.01- 5.00 35 53 30 8 8 11 21 33 26 32 143 94 31 25 29 37 616 5.01- 7.50 9 16 6 2 1 1 8 9 12 30 41 71 29 12 15 18 280 7.51-10.00 0 0 0 0 0 0 0 0 2 2 2 10 0 0 0 0 16
>10.00 0 0 0 0 0 0 0 0 0 0 0 4 0 0 0 0 . 4 TOTAL 72 126 89 56 50 35 53 63 75 119 253 210 68 44 57 71 1441 S'TAB I LITT CLASS B STABILITY BASED OH: DELTA T BETIIEEH 60.0 AHD 10.0 KETERS MIND KEASURED AT 60.0 KETERS MlkD THRESHOLD AT: .23 K/S JOINl FREQUENCY DISTRIBUTIOH OF MIND SPEED AND DIRECTION IH HOURS AT 60.00 METERS SPEED (K/S) N NNE NE ENE E ESE SE SSE S SQI SM MSM M MNM HM NHM TOTAL CALII 0
.24- 1.50 4 2 2 5 8 4 0 2 0 5 3 1 0 0 0 0 36 1.51. 3.00 4 5 5 7 7 16 6 5 1 3 9 10 6 8 9 5 106 3.01. 5.00 1 10 11 3 3 4 6 12 3 3 16 14 9 9 3 7 114 5.01. 7.50 2 10 4 0 0 0 2 2 4 4 16 3 3 3 2 62 7.51-10.00 0 0 0 0 0 0 0 0 0 2 3 4 0 0 0 0 9
%10.00 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 2 TOTAl. 11 27 22 15 18 24 14 21 8 20 35 47 18 20 15 14 329
pt I'
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PENNSYLVANIA POMER 8 LIGHT CQIPANY (PAL) - Susquehanna Steam Electric Station PROGRAHt JFD VERSION: PC-1.1 Primary Teer Data meter level SITE IDENTIFIERt DATA PERICO EXAHINED: 1/ 1/92 - 12/31/92
~ " ~
ANNUAL STABILITY CLASS C STABILITY BASED ON: DELTA T BETMEEN 60.0 AND 10.0 HETERS MIND HEASURED AT 60.0 HETERS MIND THRESHOLD AT! .23 H/S JOINT FREOUENCY DISTRIBUTION OF MIND SPEED AHD DIRECTIOH IH HOURS AT 60.00 HETERS SPEED (H/S) N HHE NE EKE E ESE SE SSE S SSM S'M MSM M MHM N'M HNM TOTAL CALH 0
.24. 1.50 1 4 6 7 5 4 1 3 1 0 0 0 0 0 0 35 1.51- 3.00 3 11 8 5 8 8 5 5 10 14 6 4 2 5 3 102 3.01- 5.00 11 16 12 0 1 9 6 5 9 13 18 1 4 3 4 116 5.01- 7.50 4 2 6 0 . 0 2 0 2 7 8 16 12 1 3 3 66 7.51-10.00 0 0 0 0 0 0 0 0 0 1 4 1 0 0 0 6
>10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 19 33 32 12 1C 12 23 12 15 27 36 44 18 7 11 10 325 STABILITY CLASS D STABILITY BASED OHI DELTA T BETMEEN 60.0 AHD 10.0 HETERS MIND HEASURED AT: 60.0 HETERS MIND THRESHOLD ATt .23 H/S JOINT FREOUENCY DISTRIBUTION OF MIND SPEED AND DIRECTION IH HOURS AT 60.00 HETERS SPEED (H/S) N HHE NE EHE E ESE SE SSE S SSM SM MSM M MHM NM NNM TOTAL CALH 0
.24. 1.50 17 51 69 45 30 16 28 21 33 35 37 17 8 2 5 4 41S 1.51- 3.00 53 88 111 50 37 31 38 35 40 59 104 76 37 36 24 30 849 3.01- 5.00 101 96 78 25 33 31 33 - 45 39 65 68 122 87 67 120 140 1150 5.01- 7.50 24 39 18 "19 11 18 13 16 21 42 21 130 73 61 64 67 637 7.51.10.00 5 10 3 3 1 5 5 3 4 4 53 27 1 5 1 134
>10.00 0 0 0 0 0 0 0 1 1 1 14 5 0 0 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 CLASS E STABILITY BASED ON: DELTA T BETMEEN 60.0 AKD 10.0 HETERS MIND llEASURED AT$ 60+0 METERS MIND THRESHOLD AT: .23 H/S JOINT FREOUENCY DISTRIBUTION OF MIND SPEED AND DIRECTION IN HIJRS AT 60.00 METERS SPEED IH/S) H KKE KE ENE E ESE SE SSE S SSM SM MSM M MKM NM NHM TOTAL CALH 0
.24- 1.50 20 69 98 51 45 30 38 47 46 28 32 11 4 3 6 11 539 1.51- 3.00 56 1C1 86 23 12 12 18 24 22 57 85 40 12 13 13 11 625 3.01- 5.00 8 23 27 7 10 1 7 17 46 112 71 64 10 5 22 24 454 5.01. 7.50 4 2 4 5 5 2 1 2 10 26 11 48 3 0 2 1 126 7.51-10.00 0 0 0 3 1 0 0 1 1 0 1 3 1 0 0 1 12 F10.00 0 0 1 8 0 0 0 1 3 1 0 0 0 0 0 0 14 TOTAL 88 235 216 97 73 CS 64 92 128 224 200 166 30 21 C3 48 1770 Sl'ABIL I 'IT CLASS F STABILITT BASED ON$ DELTA T BETMEEN 60.0 AND 10.0 METERS MIND MEASURED AT: 60.0 IIETERS VINO THRESHOLD AT$ .23 H/S JOINT FREOUENCT DISTRIBUTION OF MIND SPEED AND DIRECTION IN HOURS AT 60.00 METERS SPEED (H/S) H HKE NE EKE E ESE SE SSE S SSM SM MSM M MHM KM NNM TOTAL CALH 0
.24- 1.50 12 57 89 30 26 19 24 10 12 14 9 6 1 1 1 2 313 1.51- 3.00 32 193 83 7 4 1 12 11 19 20 25 11 1 0 4 6 429 3.01. 5.00 4 4 6 7 0 0 2 5 4 8 13 15 0 2 1 3 7C 5.01. 7.50 0 0 0 0 0 0 0 0 0 0 0 6 1 0 0 0 7 7.51.10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
%10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 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 meter level SITE IDENTIFIER Y DATA PERIOD ENAKINEDt 1/ 1/92 - 12/31/92 ANNUAL *i*
STABILITY CLASS G STABILITY BASED ON: DELTA T BETMEEN 60.0 AHD 10.0 HETERS MIND KEASURED AT: 60.0 KETERS MIND TNESHOLD AT: .23 K/S JOINT FREQUENCY DISTRIBUTION OF MIND SPEED AND DIRECTIOH IH HOURS AT 60.00 HETERS SPEED (H/S) N NHE NE EHE E ESE SE SSE S SSM SM MSM 'M MNM NM HNM TOTAL CALH 0
.24- 1.50 5 56 64 36 28 11 4 15 1I 7 3 3 0 0 1 2 246 1.51- 3.00 19 212 81 8 6 9 6 4 6 12 17 4 2 2 3 6 397 3.01- 5.00 6 7 5 0 0 0 0 1 0 4 2 11 0 0 1 2 39 5.01- 7.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.51-10.M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
>10.00 0 0 0 0 0 0 0 0 0 0 0 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 CLASS ALL STABILITY BASED ONt DELTA T BETMEEN 60.0 AHD 10.0 KETERS
'MIND KEASURED AT 60.0 KETERS MIND TNESHOLO AT: .23 H/S JOINT FREQUENCY DISTRIBUTIOH OF MIHO SPEED AHD DIRECTIOH IH HOURS AT 60.00 HE'TERS SPEED (H/S) N NNE NE EHE E ESE SE SSE S SSM SM MSM M MNM k'M NHM TOTAL CALH 0
.24- 1.50 63 249 34S 192 165 92 110 103 111 105 95 42 15 6 14 20 1730 1.51- 3.00 191 697 407 128 92 88 100 98 122 201 310 174 68 68 70 76 2890 3.01- 5.00 166 209 169 50 55 51 78 119 123 233 326 338 138 112 179 217 2563 5.01- 7.50 43 69. 38 26 17 21 26 29 49 112 85 287 121 77 87 91 1178, 7.51-10.00 4 5 10 6 4 1 5 6 6 8 11 74 29 1 5 2 177
>10.00 0 0 8 8 0 0 0 1 4 2 1 20 5 0 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 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 72 126 89 56 50 35 53 63 75 119 253 210 68 44 57 71 0 8 11 27 22 15 18 24 14 21 8 20 35 47 18 20 15 14 0 C 19 33 32 12 14 12 23 12 15 27 36 44 18 7 11 10 0 D 199 279 293 142 114 97 117 122 137 206 235 412 237 167 '18 242 0 E 88 235 216 97 73 45 64 92 128 224 200 166 30 21 43 48 0 F 48 254 178 44 30 20 38 26 35 42 47 38 3 3 6 11 0 G 30 275 150 44 34 20 10 20 17 23 22 18 2 2 5 10 0 TOTAL 467 1229 980 410 333 253 319 356 415 661 828 935 376 264 355 406 0
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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 1.149E-OS 3.940E.06 2.191E 06 1.404E 06 7.303E-OT C.651E-OT 3.24BE 07 2.271E-OT 1.641K-OT 1.269K.07 1.000E.07 SSM 2.574E.OS 8.198E.06 4.738E.06 2.972E.06 1.717K-06 1.113E.06 7.959E 07 5. 559E.OT 3.978E-OT 3.064E 07 2.386K.OT SM 4.417K.05 1.383E.05 8.123E.06 5.292E-06 2.929E-06 1.921E-06 1.391E.06 1.013E.06 7.577E.OT 5.934E.OT 4.727E.07 i MSM 1.152E.04 3.584K.05 2.159E-05 1.450E.05 8.185E.06 5.647E.06 4.318E 06 3.174E 05 2.391E-06 1.952E.06 1.623K 06 M 5.693E-05 1.745E-05 9.021E-06 5.629E-06 2.985E-06 1.946K-06 1.399E.06 1.010E.06 7.511E.07 6.071E 07 4.970E.OT MKM 2.755E.05 8.657E.06 4.825E.06 3.068E.06 1.747E.06 1.125E.06 7.915E 07 5.785E.07 4.383E.OT 3.540E-OT 2.907E.07 N'M "2.721E-05 8.626E-06 4.974E.06 3.123E.06 1.752K.06 1.129E.06 S.040E 07 6.003E.OT 4.661E-OT 3.737E-OT 3.048E-07 NNM 2.046E-05 6.M3f.ob 4.016E.06 2.828E.06 1.515E.06 9.988E.OT 7.249E 07 5.247K 07 3.917E.OT 3.279E. 07 2.795E.OT N 2.257E-05 7.160E-06 4.041E.06 2.520E.06 1.483K-06 9.770E-OT 7.719E.OT 5.624E.OT 4.252E 07 3.500E-07 2.933E.OT KNE 2.207E.05 7.835E.06 4.431E.06 3.045E 06 1.646E-06 1.122E 06 8.399E-07 6.136E 07 4.657E-OT 3.846E-OT 3.235E.07 NE 1.Q6E.05 5.371K.ob 3.072E 06 1.944E 06 1.111K 06 7.567E-07 5.640E-OT 4.201E.OT 3.260E.07 2.720E 07 2.312E 07 ENE S.61CE.06 2.802E.06 1.585K.06 1.068E-06 5.700E.OT 3.882E.OT 2.906E 07 2.227E 07 1.774E-07 1.C95E 07 1.289K-OT E 4.702E-06 1.618E-06 8.858E-OT 5.291K-07 2.770E-OT 1.7S1E-OT 1.265E 07 9. 137E.OS 6.873K.OB 5.531E 0$ C.557E-OS ESE 5.306E 06 1.700E 06 9 '40E-07 5.475E 07 2.768E.07 1.694K 07 1.143K 07 8.216E N 6.146E OS 4.640E OS 3.562E.OS SE 5.178K-06 1.740E.06 1.011E.06 6.562E-OT 3.412E.OT 2.13$ E.OT 1.467E 07 9.930E.OB 6.905E.OS 5.110E-OB 3.828E.M SSE 7.928E-06 2.834E-06 1.626E-06 9.804E-07 5,04bf-07 3.279E-OT 2.336E.OT 1.653E.07 1.208E.07 e.scbf-oe 6.502E 08 ANKUAL AVERAGE CHI/O (SKC/HETER CUBED) DISTANCE IH HILES BEARIKG 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S 8.261E-OS 3.708K-OB 1.903E-OS 4.467K-09 2.018E-09 7.129E-10 3.838E.10 1.725E.10 1.150E-10 7.346E-11 6.366E-11 SSM 1.980E-OT 9.045E-OS 4.948E.OB 1.582E N 7.129K.09 2.635E.09 1.302E 09 4.413E.10 2.954E-10 1.2QE-10 1.0988-10 SM 3.971K-OT 1.957K-OT 1.074E.OT 3.216E.OB 1.618K.DB 7.343E.09 4.295E-09 2.282K.09 1.575E.09 9.039E-10 7.9108-10 MSM 1.385E-06 7.256E-OT 4.028E-OT 1.153E 07 5.399E.OS 1.952E.OS 1.070E-OB 4.095K.09 2.322K.09 1.007E.09 8.869E-10 lI 4.186E-07 1.995K-OT 1.083E-07 3.045E-OB 1.295E.OB 3.615E.09 2.010E-09 7.097E.10 4.002E.10 1.727K.10 1.514E-10 MKM 2.C51E-OT 1.241E.OT 6.929E-OB 2.373E-OS 1.097E.OS 4.150E.09 1.800E.09 2.755E.10 1.542E-10 5.2S6E 11 4.607E-11 NM 2.580E 07 1.335E-07 T.565E 08 2.699E 08 1.155K.OS 3.543E.09 1.704K.09~4.388K-IO 2.453E.10 1.050E-10 9.149E-11 KKM 2.395E-07 1.324E-OT 7.424E.OB 2.522E.OB 1.107E-OS 3.717E 09 2.299E-09 1.298E 09 7.864E-10 4.146E 10 3.612E 10 N 2.648E-OT 1.853K.OT 9.869E-OS 2.721E 08 1.340E 08 6.112E-09 3.045K 09 1.071E 09 6-193E 10 2.936E-10 2.549E 10 NKE 2.760E.OT 1.485E-OT 8.051E-OS 2.466E-OB 1.105E-OS 4.066K.09 2.278E 09 1.043E 09 6.695E 10 3.996E 10 3.465 E-10 Nf 1.977E-OT 1.097E-07 6.308K-OS 2.4C2E 08 1.046E.OB 3.248E 09 1.798E-09 8.098E 10 4.954E 10 2.689E-10 2.333E-10 KNE 1.105K-OT 6.087E.OS 3.917K.OS 1.965E-OS 1.058E 08 5.879E-09 3.200E.09 1.480E.09 9.246E-10 5.076E-10 4.399E 10 E 3.850E-OB 2.002E-OB 1.131E.OB 4.286E.09 2.207K-09 1.151E.09 5.862E 10 2.291K 10 1.370K. 10 7.141E 11 6. 159E-11 ESE 2.906E-OS 1.235E.OS 7.102E.09 2.813E 09 1.516K.09 8.465E 10 4.065E-10 1.137E 10 6.304E-11 2.681E-11 2.321K-11 SE 3.089E-OS 1.189E-OB 6.881K-09 2.7C9E 09 1.171E.09 3.BOSE.10 1.902K 10 6.948E.11 3.C53E-11 9.754E-12 8.414E.12 SSE 5.251E-OS 2.095E-OB 1.176K 08 C.407E-09 1.924E 09 6.819E 10 3.503E 10 1.C06E-10 8.309E-11 4.220E-11 3.637E-11 CHI/O (SEC/HETER CUBED) FOR EACH SEQlEN'I SKQlfHT BOUNDARIES IH HILES D I RECT IOH .5.1 1-2 2-3 3-4 4.5 5.10 10-20 20.30 30.40 40 5I FROH SITE S 2.230E.06 7.621E-07 3.231E.07 1.679K.OT 1.015E.07 3.917E.OS 6.614E.09 9.292E 10 ~ 2.110E-10 8.214E.
SSM 4.722K-06 1.727E-06 7.846E-07 4.081E-07 2.436E.07 9.614E 08 1.944E.OB 3.300K-09 6.317E-10 1.703E.
SM 8.132K-06 3.006E 06 1.381E-06 7.679K.OT 4.805K.07 2.012E-07 CD 178E.OB 8.480K.09 2.588K 09 1.061' MSM 2.160E-05 8.461E.06 4.215E 06 2.448E.06 1.632E.06 7.2SbE.OT 1.519E.07 2.518E 08 5.306E.09 1.352E M 9.385E.06 3.111E.06 1.389E.06 7.702E.OT 5.006E.OT 2.077E-OT 3.998E.OS 5.462E.09 9.Q4E 10 2.322E MKM 4.896E 06 1.764E 06 7.952E 07 4.4QE.OT 2.926E 07 1.266E.OT 2.818E.OS 5.028E 09 6.648E 10 8.035E NM 4'.9QK-06 1.780K-ob e.093K-OT 4.692E.07 3.079E 07 1.354E.07 3.094K.08 4.943K.09 7.266K-10 1A16E NNM 4.125E.06 1.577K.06 7.179E 07 4.054E.OT 2.790E.07 1.303E-07 2.983K.N 5. 112E.09 1.389K 09 5.050E N 4.058E-06 1.489K.ob 7.428E-OT 4.35SE-OT 2.995E.OT 1.645E 07 3.696E 08 6.829E 09 1.4QE.09 3.758K KKE C.571E 06 1.724E 06 S.247E-07 4.770E.OT 3.240E.OT 1A66K 07 3.102K 08 5.213E 09 1.254E.09 4.399K NE 3.081K.06 1.139E 06 5.578E-OT 3.323E.OT 2.309E-OT 1.085K-OT 2.681E 08 4.592E.09 9.725E-10 3.228E ENE 1.626E 06 5.998K-OT 2.895E-OT 1.797E 07 1.282E.OT 6.226K.OB 1.996E-OS 6.060E 09 1.760E 09 6.061 E E 8.900E.OT 2.891K.07 1.262E.OT 7.009E.M 4.58CE.OB 2.026E 08 4.924E.09 1.207E 09 2.960E-10 8.721E ESE 9.292E 07 2.892E-OT 1.161E-OT 6.164E 0$ 3.99E-OB 1.373E.OS 3.190E.09 8.489K-lo 1.TS1E-10 3.621E SE 1.015E 06 3.546E 07 1.456E-OT 7.M5E-M 3.934K.08 1.388K-OS 2.966E.09 5.152E.10 9.065K-11 1.660E SSE 1.607E-06 5.319E-OT 2.315E-OT 1.212E.OT 6.733E.N 2388K.OS 4.9MK.O9 8.55E-10 1.786E-10 5.2'16E VENT AKD BUILDlNG PARAHETERS:
RELEASE HEIGHT (I(ETERS) 10.00 REP. MIND HEIGHT (HETERS) 10.0 DIASTER (HETERS) .00 BUILDING HEIGHT (HETERS) 61.3
, EXlT VELOCI'TY (N/SEC ) .00 BLDG.HIN.CRS.SKC.AREA (SO.HETERS) 2575.0 HEAT EHISSION RATE (CAL/SEC) .0 AT THE RELEASE HEIGHT AT THE HEASURED MIND HEIGHT ( 10.0 NETERS):
VENT RELEASE INmf MIND SPEED (HKTERS/SEC) VENT RELEASE HNE MIND SPEED (HKTERS/SEC) MIND SPEED (NETERS/SEC)
STABLE C(WO IT IOHS UNSTABLE/NEUTRAL CONDIT ELEVATED LESS THAN .000 ELEVATED LESS THAN .000 LESS THAN .000 NIXED BKTMEEN .000 AKD .000 Hl XKD BETMKEN .000 AND .000 BETMEEN .000 AKD GR(W LEVEL ABOVE .000 GRIXIND LEVEL ABOVE F 000 ABOVE .000 51
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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 1.147E.05 3.931E-OS 2.183K.06 1.397E 06 7.250E-OT 4.607E-OT 3.209K 07 2.23&E-OT I ALICE-07 1.2CSE 07 9.784E.OB SSM 2.571K 05 8.175K OS 4.718K 06 2.955E 06 1.702E 06 1.101E.OS 7.84&E 07 5.465E.OT 3.900E-OT 2.996E.OT 2.326E.OT SM 4.411E-05 1.378E-05 8.086E-OS 5.259E 06 2.902E-06 1.89&E-06 1.370E 06 9.942E 07 7.416E-OT 5.790K.OT 4.599E 07
, MSM 1.151K.04 3.572E.05 2.14&E.05 1.441E.05 8.107E.06 5.575K.06 4.249E-06 3.11CE-06 2.338K.06 1.903E-06 1.577E-06 5.684K 05 1.739K 05 S.977E 06 5.592E-06 2.957E 06 1.921K 06 1.377K-M 9.906E.07 7.342E-OT 5.915E.OT 4.827E.07 MN 2.751E-05 S.QOE-OS 4.802E.06 3.04&E.06 1.730K 06 1.110E.06 7.7&BE-OT 5.675E 07 4.285E-OT 3.450E 07 2.824E-OT N 2.717K-05 8.600E-OS 4.951K-06 3.104E-OS 1.736E-06 1.115E-06 7.91&E-OT 5.S93E 07 4.562E-OT 3.646E 07 2.965K.OT NHM 2.043E.05 6.862E 06 3.998K.OS 2.811E-06 1.501E.OS 9.867E.07 7.139E.OT 5.152E.OT 3.834K.OT 3.200E.OT 2.719E.OT N 2.253E.05 7.139K.OS 4.024E-06 2.505E-06 1.471K 06 9.65&E.OT 7.608K-OT 5.527K 07 4.167K-OT 3.420E 07 2.857E-OT NNE 2.204E.05 T.SICK.OS 4.413E.OS 3.02&E.06 1.Q2E.06 1.110E.OS 8.285E.OT 6.036K.OT C.569E-OT 3.763E-OT 3.157E.07 NE 1.QCE.05 5.359E.06 3.061E.OS 1.935E 06 1.104E 06 7.497E.DT 5.575E-OT 4.143E-OT 3.207E-OT 2.669E-OT 2.264E 07 EHE 8.606E-06 2.797K-OS 1.581E-06 1.064E-06 5.667E-OT 3.852K-OT 2.878E-OT 2.201E 07 1.750E-OT 1.472E-OT 1.267E 07 E 4.698K 06 1.615E 06 8.835E-OT 5.273E 07 2.755K 07 1.769E 07 '1.254E-OT 9.040E-OS 6.788E-O& 5.C53E-OS 4.484E-OS ESE 5.301E-06 1.69BE.06 9.217E.OT 5.456E.OT 2.754E-OT 1.682E-DT 1.133E.07 8.131E-OS 6.071E.OS C.576E-OS 3.506E-OS SE 5.174K.06 1.737E-06 1.008K-OS 6.5C3E.OT 3.39&E.OT 2.126E.OT 1.456E.OT 9.S43E.OB 6.&34K 08 5 ~ 050E-08 3.777K.OS SSE 7.922E 06 2.829E 06 1.622E-06 9.774E 07 5.025E 07 3.260E-OT 2.319E 07 '\.63&E-07 '1.195E 07 8.73&E 08 6.41ZE 08 ANNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IH HILES BEARING 5.000 7.500 10.000 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 4.14&E 09 1.828K.09 6.301E-10 3.309E-10 1.452E-10 9.441E 11 5.886E.11 4.97&E-11 SSM 1.925E-OT 8.668E.OB 4.674E.OB 1.C52E-OS 6.360E 09 2.285E.09 1.097K 09 3.615E.10 2.352E-10 9.772K 11 8.26OE.11 SM 3.851K 07 1.869K 07 1.010E 07 2.932E-OB 1.C30E-OB 6.291K-09 3 '67E-09 1.83&E 09 1.230K.09 6.844E-10 5.806E 10 MSM 1.341E 06 6.917E-OT 3.779E.OT 1.04BE.07 C.753E 08 1.665E.OS 8.&39K-09 3.277K.09 1.801E.09 7.565E-10 6.455E.10 M 4.052K 07 1.900E.OT 1.015E 07 2.761E-OS 1.137E 08 3.072E-09 1.654E.09 5.651E 10 3.085E-10 1.288K 10 1.094K-10 MMM 2.373E-OT 1.182E.OT 6.496E.OS 2.154E 08 9.6COE.09 3.532E.09 1.4&3E 09 2.19&E-10 1.191E 10 3.955E-11 3.338K-11 NM 2.501E.07 1.274E.OT 7.110E.OS 2.459E.OS 1.020E-OB 3.034E.09 1.415E.09 3.532E.10 1.915E-10 7.951E.11 6.715E 11 NN 2.322E.OT 1.264E-OT 6.981E-OS 2.300E OS 9.792E-09 3.18&E-09 1.912K-09 1.047E.09 6.152E 10 3.146E-10 2.65&E 10 N 2.572K.OT 1.7T4E-OT 9.312K F 08 2.495E.OB 1.193E.OS 5.289K.09 2.561E-09 8.753K-10 4.919E.10 2.267E.10 1.913E-10 NNE 2.686E.DT 1.426E.07 7.623E-OS 2.272E.OS 9.90&E.09 3.549K.09 1.935K.09 S.Q1E 10 5.392E-10 3.133E-10 2.646E.10 HE 1 932E 07 1.059E-OT 6.020E OS 2.277E 08 9.533K-09 2.894E 09 1.566K 09 6.896E-10 4.126K-10 2.190E 10 1.859E 10 ENE 1.084E 07 5.910E 08 3.765E.OB 1.852K OS 9.771E 09 5.325E 09 2.842E 09 1.289K 09 7.900E 10 4.254K-10 3.618E 10 E 3.781K.OS 1.948E-OS 1.091E.OS 4.058K-09 2.052E-09 1.050E 09 5.254E-lo 2.017E-10 1.184E-10 S.ICE 11 5.138K 11 ESE 2.855E-O& '1.202E-OB 6.84&E-09 2.661K.09 1.407E-09 7.709K-10 3.632E-10 9.961E.11 5.419E-11 2.261E-11 1.921E-11 SE 3.043K.OB 1.162E.OS 6.675E.09 2.625E 09 1.101E.09 3.524E-10 1.732E-10 6.231K 11 3.049E-11 8.478E-12 7.201E 12 SSE 5.17OE-OS 2.047E.OS 1.140E-OS 4.206E.09 1.&07K.09 6.307E.10 3.189E-10 1.261E-10 7.336E-11 3.669E-11 3.114E-11 CHI/O (SEC/HETER CUBED) FOR EACH SEGMENT SEGHENT BCUMDARIES IM HILES DIRECT IOI .5-1 1-2 2-3 3.4 4.5 5.10 10-20 20.30 30-40 40-50 FRDH SITE S 2.222E 06 7.569E 07 3.193E.07 1.652E-07 9.935E.OS 3.7&BE.OS 6.221K.09 8.298E-10 1.789E-10 6.603E. 11 SSM 4.703E 06 1.713E 06 7.73&E 07 C.003E-OT 2.376E.07 9.243E.OS 1 ~ 806E 08 2.897E-09 5.236E-10 1.32&E.1C SM 8.096E.06 2.980K.06 1.361K.06 7.51&E 07 4.675E.OT 1.927E 07 3.S56E.OB 7.337E-09 2.100E.09 8.075E-1C MSM 2.150E-05 8.383K-OS 4.149E OS 2.394E.06 1.586E.06 6.966E.OT 1.400E-07 2.176K-08 4.304E.09 1.025E 09 M 9.342E-06 3.082E-06 1.367K-06 7.531E-OT 4.&QE.07 1.985E.07 3.6S'lE-08 4.717E-09 7.783K 10 '1.74&E 10 MN 4.873K 06 1.748K 06 T.BZTK.OT 4.364K-OT 2.843E.07 1.210E 07 2.590E.OB 4.341E-09 5.424E 10 6.084E-11 NM 4.941E-OS .1.764E.06 7.9nE.OT 4.593E-OT 2.995E.OT 1.297E.07 2.853K.OS 4.298K.09 5.949E 10 1.081E.10 NN, Co107K 06 1.564K 06 7.072E 07 3.969K-OT 2 714E 07 1.24&E 07 2.753E.OS 4 439K-09 1.130K 09 3.856E 10 H 4.041E.OS 1.476E-06 7.322E.DT 4.271 E-OT 2.91&E 07 1.577E.07 3.C31E-OS 5.970E-09 1.211E.09 2.921E.10 HHK 4.553K-OS 1;nOK-06 8.137K-OT 4.681E 07 3.162K-OT 1.411E.OT 2.892K-OB 4.599E-09 1.046E.09 3.622E 10 NE 3.071E 06 'I'31E-06 5.515E-07 3.270E-OT 2.261E-07 1.050K.OT 2.520K 08 C.133E.09 8.345E-10 2.641K 10 ENE 1.621K 06 5.965K-07 2.&67K.OT 1.773E 07 1.260K 07 6.052E.OB 1.&BBE.OS 5.517E.09 1.543K.09 5.099E-10 E 8.878K 07 2.876K-OT 1.251E.07 6.923E-OS 4.511E.OS 1.975E 08 C.S&9E 09 1.107K.09 2.6Z4E-10 7.433K.11 ESK 9.270K 07 2.878K 07 1.151E 07 6.090K-08 3.582E.OS 1.340E-M 3.034E.09 7.774E.10 1.576E 10 3.071E.11 SK 1.013E OS 3.532E 07 1.446E OT 7.014E 08 3.882E-OB 1.360K 08 2.84&E.09 4.803K 10 8.1SSE.11 1.453E 11 SSK 1.604K.06 5.296E 07 2.297E.OT 1.199E-OT 6.641E.OS 2.33SE.OS 4.739E.09 8.198K. 10 1.611E-10 4.550E.11 VENT NO BUILDING PARAIKTERST RELEASE HEIGHT (I%TERS) 10.00 REP, MIND HEIGHT (HETERS) 10.0 DIASTER (i%TERS) .00 BUILDING HEIGHT (HETERS) 61.3 i EX IQ VELOCITT (H/SKC ) .00 BLDG.HIN.CRS.SEC.AREA (SD.HETKRS) 2575 0 HEAT KHISSION RATE (CAL/SEC) .0 AT THE RELEASE HEIGHT: AT THE HEASURED MIND HEIGHT ( 10.0 HETERS):
VENT RELEASE IKOE MIND SPEED (METERS/SEC) VENT RELEASK IHIE IJIND SPEED (HETERS/SEC) MIND SPEED (HETERS/SKC)
STABLE COID IT IONS UNSTABLE/NEUTRAL CONDITION ELEVATED LESS THAN .000 ELEVATED LESS THAN .000 LESS THAN ~ 000 HIXED BEllKEN .000 AND ~ 000 HIXED BETMEEN .000 AMD .000 BETMEEM .000 AMD .00 GR(XNH) LEVEL ABOVE .000 GR(AJMD LEVEL ABOVE , .000 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 1.087E.05 3.596K 06 1.950E 06 1.227E-06 6.1S9E-07 3.841E 07 2.622E-07 1.797K 07 1.275E 07 9.68SE 08 7.515E-OS SSM 2.436E 05 7.CSIE-06 4.217E 06 2.597E-06 1.454E-06 9.191E.07 6 CZZE-07 C.39CE.07 3:087E 07 2.337E 07 1.791E.07 SM C.179E 05 1.262E-05 7.230K 06 4.624E-06 2.4S1E.06 1.585E-06 1.122E-06 8.002E 07 5.877E 07 4 524E 07 3.546E 07 1.090K.OC 3.270E.05 1.921E.05 1.267E-05 6.933E-06 4.659E-06 3.482E.06 2.508K.06 1454K 06 1.488E 06 1.217E 06 MX 5.386E 05 1.592E 05 8.02SE.06 4.918E 06 2.529E-06 Is606E-06 1.128E.06 7.979E.07 5.823E-07 4.626E 07 3.727E.07 MKM 2.606E.05 7.899K.06 4.294E.06 2.681K.06 1.480K.O6 9.2S1E-07 6.382E.07 4.570E.07 3.398E D7 2.698K 07 2.180E.07 NM 2.574E-05 7.870K 06 4.427E 06 2.729E 06 1.48CE 06 9.318E-07 6.485K-07 4.7C3E 07 3.615E 07 Zo849E-07 2.287E 07 NNM 1.935K 05 6.280E 06 3.575E 06 2.472E-06 1 "283K.06 S.242E 07 5-847E 07 4.146E.07 3.0ME 07 2.500K-07 2.097E 07 N 2.135K.05 6.533E.06 3.597K.06 2.202K-06 1.257E.06 8.064K.07 6.227E-07 4 ~ 445E.07 3.299E-07 2.669E-07 2.201E.07 NNE 2.088E-OS 7.149E.06 3.944E.06 2.661E-06 1.394E.06 9.266E.07 6.777E-07 4.851E 07 3.614E 07 2.934E.07 2.C29E.07 NE 1.547E-05 4.901K-06 2.735E 06 1.699E-06 9.420E.07 6.250E.07 4.554E 07 3.324E.07 2.532K 07 2.077E.07 1.738K.07 EKE 8.151E.06 2.55SE.06 1.411E.O6'9.336E-07 4.833E 07 3.207E-07 2.347E-07 1.7QE 07 1.379K 07 1.143E 07 9.697E OS E C.449E 06 1.477E.06 7.MSE.07 4.627E.07 2.349E 07 1.C72E.07 1.022E-07 7.236K.08 5.344E OS 4.229E.OS 3.430E.M ESE 5.0208-06 1.552E-06 8.228E.07 C.7SSE.07 2.347E-07 1.400E.07 9.233E.OS 6.507E-OS 4.779K.OS 3.548K.OS 2.681E.M SE 4.899E-06 1.5SSE-06 9.000E-07 5.739E-07 2.895E-07 1.768K-07 1.1S6E-07 7.86SE.08 5.372E.OS 3.910E.OS Z.M3E.08 SSE 7.501K-06 2.5S6K.06 1.448E.06 8.574E.07 4.2S2E 07 2.711E 07 1.889E-07 1.310E-07 9.396E-OS 6.767E-08 4.896E 08 ANNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IH HILES BEARING 5.000 7.500 10 F 000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S 6.115E-OS 2.587E-OS 1.261E-08 2.720E.09 1.146E-09 3.808E-10 1.940E-10 8.290K.11 5.269E 11 3.218E-11 2.672E-11 SSM 1.464E-07 6.300K-OS 3.271E-08 9.602K 09 4.030K-09 1.400E-09 6.542E 10 2.105E.10 1.342E-10 5.480E-11 4.561K.11 SM 2.935E 07 1.362E-07 7.090E-08 1.948E 08 9.124E.09 3.889E 09 2.149E 09 I.M3E 09 7.119E 10 3.900E-10 3.264E. 10 MSM 1,023E.06 5.046E 07 2.65SE.07 6.978E.08 3.042E-08 1.033E 08 5.346K-09 1.941E 09 1.048E 09 4.337K-10 3.653E 10 M 3.092K 07 1.387E-07 7.1C6E-O8 1.842K.08 7.2S9E.09 1.910E.09 1.003K-09 3.360E.10 1.803E-10 7.423K-11 6.223E-11 MKM 1.811E-07 8.629E 08 4.571E.08 1.436K.08 6.176E-09 2.194K.09 8.985K-10 1.305K.10 6.948E-11 2.273E-11 1.895E 11 KM 1.906E.07 9.287E.08 4.994E.OS 1.635E-OS 6.513E-09 1.876E-09 8.526K-10 2.083E-10 1.109K 10 4.531E 11 3.775E-11 NHM 1.770E 07 9.210E.08 4.9D1E.OS 1.528E-OS 6.245E 09 1.969E 09 1.151E-09 6.166E.10 3.556E.10 1.790E-10 1.491E.10 N 1.95SE 07 1.290E.07 6.522E.08 1.651K-OS 7.573E 09 3.246E-09 1.529E 09 5.105E 10 2.812E-10 1.273E 10 1.058E.10 NNE 2.041E 07 1.035E-07 5.326E.OS 1.498E-OS 6.255E 09 2.164E.09 1.1C7E.09 4.991E.10 3.052E-10 1.740E-10 1.445E.10 NE 1.464E 07 7.655E.08 4.182K.OS 1.489E-OS 5.949E-09 1.739E-09 9.116E-10 3.904E.10 2.279E-10 1.183E 10 9.844E.11 EHE 8.193K.OS 4.255E.OS 2.602E.OS 1.201E-08 6.039E-09 3.162E.09 1.631E-09 7.180E-10 4.284E 10 2.252K-10 1.873E.10 E 2.855E.OS 1.400E-OS 7.523K-09 2.624K-09 1.262K.09 6.202E.10 2.996E 10 1.115K.10 6.369E 11 3.180K.11 2.633K.11 ESE 2.155E-08 8.641E-09 4.722E-09 1.722E 09 8.665E 10 4.560E-10 2.076E.10 5.525E. I I 2.926E-11 1. 192E-11 9.902E-12 SE 2.293K-OS 8.326E.09 4.583E.09 1.687E-09 6.719E-10 2.061E-10 9.764E.11 3.400E-11 1.616E 11 4.374E-12 3.625E.12 SSE 3.897E.OS 1.467K-OS 7.833E-09 2.704E-09 1.104K-09 3.690E-10 1.798K-IO 6.8SOE-11 3.887E-11 1.892E-11 1.567K.11 CHI/O (SEC/HETER CUBED) FOR KACH SEGHEHT SEGHEHT BIJKDARIES IN HILES DIRECTION .5.1 1-2 2-3 3.4 4-5 5-10 10-20 20.30 30.40 40.50 FROH SITE S 1.994E.06 6.497E-07 2.617E 07 1.307E 07 7.641E.OS 2.782E-OS 4.217K.09 5.100E-10 1.031E-10 3.624E-11 SSM 4.222E.06 1.470E.06 6.349E.07 3.175E 07 1.832E.07 6.807E.08 1.226E.OS 1.803E.09 3.082E-10 7.493E-11 SM 7.269E.06 2.559E-06 1. 117E.06 5.968E 07 3.609K-07 1.421E-07 2.QOE.08 4.589E.09 1.246E 09 4.61SE-10 MSM 1.930E 05 7.197E-06 3.C06E.06 1.901E 06 1.225E-06 5.137E-07 9.584E.OS 1.369E-OS 2.574K-09 5.903E-10 M 8.399E.06 2.6C9E.06 1.123E-06 5.983K-07 3.758E-07 1.467K.07 2.526E-OS 2.982E.09 4.673E-10 1.012E-10 MHM 4.378K 06 1.501E.06 6.QOE-07 3.466E 07 2.197E.07 8.931K-OS 1.769K-OS 2.738E.09 3.267E-10 3.518K-11 NM 4.437K-06 1.515 E.06 6.544E.07 3.645E-07 2.312E 07 9.551E 08 1.944E.OS 2.703E.O9 3.553E-10 6.193E-11 NHM 3.685E 06 1.343E.06 5.805E.07 3.150E-07 2.095E 07 9.181E 08 1.876E.08 2.782E.09 6.698K 10 2.203K-IO N 3.629E 06 1.267E.06 6.004E.07 3.387E 07 2.25OE-07 1.155E 07 2.336E-OS 3.713E.09 7.141E-10 1.650E-10 NKK 4 lW&06 1 468K 06 6.670E.07 3.708E 07 2.435E.07 1.035E.07 1.961E.OS 2.SCSE.09 6.102K-10 2.020E 10 KE 2.756E 06 9.694E 07 4.51CE.07 2.585K-07 1.737E.07 7.664E.08 1.690K.08 2.531E.09 4.774E-10 1.Q4E 10 ENE 1.454K 06 5 ~ 111K 07 2.343E.07 1.399E 07 9.653E 08 4.396E-08 1.247E-OS 3.317E.09 S.686E 10 2.714E-10 E 7.968K 07 2.46SE 07 1.023E.07 5.460E 08 3 45CE-08 1.436E.OS 3.108K.09 6.Q2E.10 1.C70E 10 3.92%-11 ESE 8.320E 07 2 468K 07 9.413K.OS 4.804E 08 2.743E 08 9.769K 09 2.0088.09 4.661E-10 S.887K-11 1.Q1E 11 SE 9.080K 07 3.026E.07 1.181E.07 5.528K 08 2.969E 08 9.907K-09 1.879E-09 2.869E-10 4.539E 11 7.587E-12 SSE 1.439E 06 4.5388.07 1.876E 07 9.452K 08 5.081E-M 1.703K-M 3.133E-09 4.893K.10 8.912E-11 2.3QE-11 VENT ANO BUILDING PARAHKTERS:
RELEASE HEIGHT (HETERS) 10.00 REP. MIND'EIGHT (NETERS) 10.0 OIAHETER (HETERS) .00 BUILDIKG HEIGHT (HETERS) 61 3
, EXI'T VELOCITY 'H/BEC ) .00 BLDG.HIN.CRS+ SEC.AREA (SO.HETERS) 2575.0 HEAT BIISSION RATE (CAL/SEC) .0 AT THE RELEASE HEIGHTt AT THE HEASURED MIND HEIGHT ( 10.0 HETERS):
VENT RELEASE IHXIE MIND SPEED (HETERS/SEC) VENT RELEASE IHXIE MIND SPEED (HETERS/SEC) MIND SPEED (HETERS/SEC)
STABLE CNO IT IONS UNSTABLE/NEUTRAL COKDITIONC ELEVATED LESS THAN ;000 ELEVATED LESS THAN .000 LESS THAN .000 HIXED BETMEEN .000 AND .000 HIXED BETMEEN .000 AKD .000 BETMEEN ~ 000 AKD ~ OOC GR(RJKD LEVEL ABOVE .000 GR(XJKD LEVEL ABOVE .000 ABOVE .000 53
l(
! 1 f3 S.
.I
Page 4 of 5 Stean Electric Station - GR(XND-LfVEL RELEASE . 1992 FOR OPEN TERRAI N RECIRCULATION USING SPECIAL TERRAIN ADJUSTKEHT FACTORS RELATIVE DEPOSITIOH PER UHIT AREA (K e-2) AT FIXED POINTS BY DOMHMIHO SECTORS DIRECTION DISTANCES IN KILES FROH SITE .25 .50 .75 1.00 1.50 2.00 2.50 3.00 3.50 C.OO S 6.452E.OS 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 4.50'.265E-OB SSM 9.324E.OB 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 SM 1.051E 07 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 MSM 1.505E 07 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 M 9.794E-DB 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 MHM ~ 6.6Z4E-OB 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 NM 8.521E 0$ 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 NNM .6.072E 08 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 H 7.861f -08 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 HNE 8.405E-08 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 NE 1.128E 07 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 ENE 8.184E.OB 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 E 4.2S4E.DB 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
'EESE 4.51CE.OB 5.155E.OB 1.453E.OB 1.729E-OB 7.520E.09 4.Z45E.09 1.983E.09 1.138E-09 9.425E-09 5.765E.09 2.729E 09 1.594E-09 7.261E.10 1.032E 09 4.972E 10 3.561E.10 2.585E 10 6.646E 10 4.422E-10 3.145E-10 1.914E 10 2.272E 10 SSE 6.975E 08 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 DIRECTION DISTANCES IH KILES FROI SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 S 2.679E 10 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 SSM 3.981E 10 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 SM 5.257E-10 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 MQI 1.01CE.09 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 M 3.956E. 10 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 MNM 3.209E 10 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 NM 4.517E.10 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 NHM 3.913E-10 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 N 5.004E 10 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 NHE 5.725E-10 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 NE 7.907E.10 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 ENE 6.279E.10 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 E 2.092E.10 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 ESE 1.509E.10 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 SE 1.773E 10 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 SSE 2.658E.10 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 1ttOHII~O~10000t RELATIVE DEPOSITION PER UNIT AREA (K~~ 2) BT OOMHMIND SECTORS SEGKEHT B(XIHDARIES IN KILES DIRECT IOH .5 1 1-2 2.3 3.4 4 5 5-10 10-20 20.30 30-40 40.50 FROH SITE S 1.221E-OB 3.626E-09 1.323E-09 6. 182E. 10 3.430E 10 1.176E-10 1.698E-11 1.936E.12 3.704E-13 1.243E-13 SSM 1.701E.OB 5.326E-09 2.053E.09 9.468E-10 5.130E-10 1.767E-10 2.957E.11 4.032E 12 6.465E-13 1.491E-13 SM 2.056E.OB 6.592E 09 2.497E.09 1.202E-09 6.710E-10 2.384E-10 3.943E.11 6.112E 12 1.522E-12 5.283E-13 MSM 3.246E.08 1.129E.OB 4.510E.09 2.193E.09 1.274E.09 4.652E-10 7. 419E.11 9.029E 12 1. 521E-12 3.201E-13 M 1.774E.OB 5.095E-09 1.842E-09 8.717E.10 5.008E-10 1. 746E-10 2.646E. 11 2.748E.12 3.913E-13 7.867E-14 MNM 1.216E.OB 3.712E.09 1.388E.09 6.814E 10 4.022E-10 1.495E-10 2.705E-11 3.832E.12 4. 289E-13 C.337E-14 NM 1.579E-DB 4.855E 09 1.857E-09 9.502E-10 5.647E-10 2. 146E-10 C.034E.11 5.176E 12 6.3S9E 13 1.045E-13 NNM 1.2C7E.OB 4.084E-09 1.551E-09 7.694E.10 C.778E 10 1.917E-10 3.606E.11 C.903E-12 1. 097E-12 3.418E-13 H 1.404E.OB 4.322E-09 1.815E-09 9.4QE.10 5.910E 10 2.799E-10 5.338E.11 7.8888-12 1.434E -12 3.152E-13 NNE 1.712E 08 5.443E 09 2.198E. 09 1.133E-09 7.014E.10 2.775E-10 4.953E.11 6.73SE.12 1.361 E-12 4.299E 13 NE 2.116E.OB 6.7228-09 2.82SE.09 1.509E 09 9.612E.10 3.966E 10 8.284E 11 1. 168E-11 2.072E 12 5.923E-13 ENE 1.534E 08 Ci923f 09 2.053E.09 1.151E 09 7.566E-10 3.235E-10 8.725E-11 2. 192E.11 S.441E-12 1.620E-12 f 7.624E.09 2.1788.09 8.372E 10 4.244E.10 2.578E 10 1.024E-10 2.164E.11 4.4688.12 9.542E 13 2.454E 13 ESE 7.623E 09 2 ~ 1'IOE 09 7.445E-10 3.592E. 10 1.9QE-10 6.Q5E-11 1.307E.11 2.884E 12 5.254E 13 9.192E-14 SE 9.546E 09 2.899f-09 1.035E.09 4.571 E-10 2.346E 10 7.459E 11 1.366E-11 2.012E-12 3.049E 13 4.912E-14 SSE 1.325f 08 3.802f 09 1.441E-09 6.874E-10 3.539E 10 1.133E 10 2.024E-11 3.061E 12 5.355E-13 1.369E.13 VENT AND BUILDING P ARAKETERS t RELEASE HEIGHT (i%TERS) 10.00 REP MIND HEIGHT (KETERS) 10.0 DIANE TER (%TERS) .00 BUILDING HEIGHT (KETERS) 61.3 EXIT VELOCITY (K/SEC ) .00 BLDG.NIN.CRS.SEC.AREA (SO.KETERS) 2575.0 HEAT EK I SS ION RATE (CAL/SEC) .0 AT THE RELEASE HEIGHT AT THE IIEASURED MIND HEIGHT ( 10.0 KETERS)t VENT RELEASE K(X)f MIND SPEED (KETERS/SEC) VENT RELEASE KOOE 'MIND SPEED (KETERS/SEC) MIND SPEED (KETERS/SEC)
\ STABLE CNOITIONS UNSTABLE/NEUTRAL CONOI TI(HIS
'ELPOTEO LESS THAN .000 ELEVATED LESS THAN .000 LESS THAN ~ 000 IIIXED BHMEEN ~ 000 AND .000 HIXEO BETMEEN .000 AND .000 BETMEEN .000 AND .000 GR(X%0 LEVEL ABOVE .000 GR(RIND LEVEL ABOVE .000 ABOVE .000 54
0
'K k
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Suaquehsme Steaa Electric Stet(on GRQJNO ~ LEVEL RELEASE . 1992 Page 5 of 5 SPECIFIC POINTS OF INTEREST ORELEASE TTPE OF DIRECTION D I StANCE X/O X/0 x/a 0/O ID LOCAT ION (HILES) (HETERS) (SEC/CUB.HETER) (SEC/CUB.HETER) (SEC/CUB.HETER) (PER SO0HETER)
KO DECAY 2.260 OAY DECAY
. 5.000 DAY DECAY UNDEPLETED UKDEPLETED DEPLETED S SITE BQJKDARY S .34 549. 6.090E-06 6.080E 06 5.678E 06 3.561E-OB S SITE BQKIDARY SQI .41 664. 1.061E-OS 1.058E. 05 9.791E.06 4.066E.OB S SITE BOUNDART QI .53 1338. 6.113E-06 6.082E-06 S. 407E-06 1.541E 08 S SITE BQJHOARY MSM 1.03 1651. 1. 275 E. 05 1.267E-OS 1.112E.OS 1.864E.OB S SITE BQJKDARY 'N '1.02 1634. 5.901E. 06 5.863E.06 5.151E.06 1.062E 08 S SITE BQINOART MNN .62 990. 6.482E-06 6.457E.06 5.835E.06 1.645E ~ 08 S SITE BQJKDARY N'N .65 1038. 5.355E.06 5.337E-06 4. 809E. 06 l.741E.08 S SITE BQJNDARY NN'N .59 944. 5.923E-06 5.902E.06 5. 349E-06 1.844E.M S SITE BQJNDART N .59 946. 5.791E.06 5.772E.06 5.229E.06 2.069E-08 S SITE BQJKOARY NHE .78 1260 ~ 3.914E.06 3.898E.06 3.475E.06 1.440E.OB S SITE BQJNDARY HE .61 984. 4. 161E-06 4.149E 06 3.748E-06 2.923E.OB S SITE BQJNDARY EHE .53 859. 2.702E-06 2.697E.06 2.456E.06 2.656E.OB S SITE BOUNDARY E .53 848. 1.323E-06 1.321E.06 1.204E-06 1.180E-08 S SITE BQJKDARY ESE .51 827. 1.606E-06 1.604E.06 1.464E.06 1.368E.OB S SITE BQJKOARY SE .42 671. 2.224E.06 2.221E.06 2.052E 06 2.256E.OB S SITE BOUNDARY SSE .34 549. 4.371E.06 4.366E. 06 4.076E-06 3.956E.OB S RESIDENCE S 1.00 1609. 1.404E.06 1.397E.06 1.227E.06 7.200E.09 S RESIDENCE SSM 1.00 1609. 2.972E.06 2.955E.06 2.597E.06 9.984E 09 S RESIDENCE SN 1.50 2415. 2.928E.06 2.901E 06 2.480E-06 6.289E.09 S RESIDENCE MSM 1.10 1770. 1.261E.DS 1.253E 05 1.095E 05 1.813E-OB S RESIDENCE M 1.20 1931. 4.090E 06 4.058E 06 3.527E.06 7.010E. 09 S RESIDENCE MNM .70 1127. , 5.198E.06 5.175E-06 4.644E.06 1.306E-OB S RESIDENCE NM .80 1287. 4.652E 06 4.629E.06 4.124E.06 1.460E. 08 S RESIDENCE NNM .60 966. 5.280E 06 5.261E 06 4.761E-06 1.640E.OB S RESIDENCE N 1.30 2092. 1.789E.06 1.775E-06 1.533E 06 5.297E-09 S RESIOEKCE HNE .90 1448. 3.440E 06 3.423E-06 3.028E.06 1. 223E.OB S RESIDENCE NE 2.30 3702. 6.294E.OT 6.227E.OT 5.126E 07 3.241E.09 S RESIDENCE EHE 2.10 3381. 3.637E.OT 3.607E.OT 2.990E. 07 2.687E.09 S RESIDENCE E 1.40 2253. 3.105E.07 3.090E.OT 2.648E.OT 2.331E.09 S RESIDENCE ESE .50 805. 1.699E 06 1.696E.06 1.551E 06 1.452E.OB S RESIDENCE , SE .40 644. 2.C47E-06 2.444E.06 2.263E.06 2.489E.OB S RESIDENCE SSE .60 966. 2.191E-06 2.187E 06 1. 977E.06 1.852E.OB S RESIDENCE HE .70 1127. 3.392E.06 3.351E-06 3.031E-06 2.340E.OB S GARDEN S 1.'10 1770. 1.205E 06 1. 199E. 06 1.046E.06 6.044E-09 S GARDEN SSM 1.20 1931. 2.318E.06 2.302E.06 1.999E 06 7.435E.09 S GARDEN QI 1.90 3059. 2.069E.06 2.045E 06 1.716E-06 4.113E.09 S GARDEN MSM 1.10 1770. 1.261E 05 1.253E-OS 1.095E.OS 1.813E.08 S GARDEN M 1.50 2415. 2.985E-06 2.956E.06 2. 528E-06 4.772E.09 S GARDEN MNN 1.30 2092. 2.132E.06 2.114E-06 1.827E-06 4.576E.09 S GARDEN NM 1.80 2898. 1.3CSE.06 1.331E 06 1. 121E-06 3.409E.09 S CARDEN NHM 4.00 6438. 3.275E-07 3. 199E. 07 2.499E 07 5.866E 10 S GARDEN N 3.20 5151. 5.013E.OT 4.921E.DT 3.932E.07 1. 117E.09 S GARDEN NNE 1.30 2092. 2 '47E.06 2.033E.06 1.755E.06 6.576E 09 S GARDEN NE 2.30 3702. 6.294E.07 6.227E.OT 5.126E 07 3.241E.09 S GARDEN ENE 2.20 35C1. 3.421E.07 3.392E.07 2.801E. 07 2.496E. 09 S GARDEN E 1.40 2253. 3.105E.07 3.090E-OT 2.648E. 07 2.331E.09 S GARDEN ESE 2.50 4024. 1.377E.07 1.365E.OT 1. 112E-07 8.748E 10 S GAROEH SE .CO 644. 2.447E-06 2.444E.06 2.263E-06 2.489E.OB S CARDEN SSE .90 1448. 1.252E.06 1.248E.06 1.102E.06 9.535E.09 S DAIRY S 3.90 6277. 1.332E-07 1.307E.OT 1.020E-07 4.701E.10 S DAIRY SSM 3.00 '829. 5.557E.OT 5.464E.OT 4.393E.OT 1.350E 09 S DAIRT SQI 3.10 4990. 5.303E.OT 5.211E.07 4.176E-07 1.274E.09 S DAIRY SQI 3.50 5634. 3.976E.OT 3.899E.OT 3.085E.07 9.1C9E-10 S DAIRY SSN 3.80 6117. 3.388E.OT 3.316E.OT 2.601E-07 7.563E.10 S OAIRT SQI 14.00 22536. 1.555E.OB 1.436E.OB 9.588E.09 2.290E-11 S DAIRT MSM 2.00 3220. 5.645E-06 5.573E.06 4.657E 06 6.644E.09 S DAIRY M 5.00 8049. 4.185E.OT 4.051E 07 3.091E-07 3.954E.10 S DAIRY ISN 1080 2895. 1.318E.06 1.303E.06 1.0988-06 2.555E.09 S DAIRT KHM 4.20 6760. 3.063E.OT 2.985E.07 2.320E-OT 5.374E 10 S DAIRT ENE 3.70 5955. 1.653E 07 1.629E.07 1.276E-OT 1.036E 09 S DAIRY E 4.50 7244. 4.556E.OB 4.483E-08 3.429E-OB 2.556E 10 S DAIRY E 4.60 7405. 4.4088.08 4.336E-OB 3.307E-05 2.457E 10 S DAIRT ESE 2.70 4346. 9.9758.08 9.882E-OB 7.993E.OB 6.211E.10 S DAIRT ESE 4.10 6599. 4.390E-08 4.327E-DB 3.346E-OB 2A27E-10 S DAIRT ESE 4.70 7566. 3.271E.08 3.217E.OB 2.447E-08 1.734E-10 S DAIRY SE 2.60 4185. 1. USE-07 1.372E.OT 1.113E.07 9.627E.10 S I RR I CATION SM 3.20 5151. 8.986E-07 5.511E-OT 7.046E-07 1.448E.09 S I RR I CATION MSM 5.30 13360. 5.595E 07 5.307E.07 3.822E-OT 3.21CE.10 VENT AND BUILDING PARAHETERS RELEASE HEIGHT (HETERS) 10.00 REP. MIKO KEIGHt (HETERS) 10.0 DIA%TER (HETERS) .00 BUILDING KEIGHT (HETERS) 61.3 EXIT VELOCITT (H/SEC ) .00 BLOC.HIN.CRS.SEC.AREA (SO.HETERS) 2575.0 HEAT EHISSION RATE (CAL/SEC) .0 AT THE RELEASE HEIGHT: AT 'tHE HEASURED MIND HEIGH'I ( 10.0 HETERS):
VENT RELEASE NODE MIND SPEED (HETERS/SEC) VENt RELEASE HCOE MIND SPEED (HETERS/SEC) MIND SPEED (HETERS/SEC)
STABLE CONDITIONS UNSTABLE/NEUTRAL COKDITIOHS ELEVATED LESS THAN .000 ELEVATED LESS THAN F 000 LESS THAN .000.
HIKED BETMEEN .000 ANO .000 HIKED BETMEEN .NO ANO .000 BETMEEN .000 AKD .000 CRQJND LEVEL ABOVE .NO GROUND LEVEL ABOVE .000 ABOVE .000 55
SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 56
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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.
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TABLE 20 SUNNARY OF NAXINUN,INDIVIDUALOFFSITE DOSES AND DOSE CONNITNENTS TO NENBERS OF THE PUBLIC DATA PERIOD: 1/1/92 TO 12/31/92 EST I HATED LOCATISI PERCENT APPLICABLE NAXIIRBI DIST AFFECTED OF LINIT EFFLUENT ORGAN Dosd" (NILES) SECTOR LINIT (NREM)
(NREN)"'IQUID LIQUID CHILD TOTAL BODY 1.41E-03 DAHVILLE, PA 0.02 CHILD LIVER 1.51E-03 DAHVILLE, PA 0.01 10 N/A AIR DOSE 8.17E-03 1.03 0.04 10 NOBLE GAS (GAHHA-HRAD)
NOBLE GAS N/A AIR DOSE 2.43E-02 1 ~ 03 'MSM 0.06 20 (BETA-HRAD)
NOBLE GAS H/A TOTAL BODY 4.76E-03 1.03 MSM 0.05 NOBLE GAS H/A SKIN 1.34E-02 1.03 MS'M 0.04 IOOIHE AND CHILD LUNG 1.10E-01 1.10 MS'M 0.37 15 PARTICULATES
"'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).
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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
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TABLE 21 CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/INFORMATION CENTER COMPLEX Data Period: 1/1/92 - 12/31/92 MAXIMUM COLLECTIVE EFFLUENT AGE APPLICABLE DOSE RATE>> DOSE GROUP ORGAN MREM HR 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 TEEN SKIN 2.68E-06 2.68E-04 PARTICULATES 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
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-SUSQUEHANNA STEAN ELECTRIC STATION SITE BOUNDARY DISTANCES r ~'PAL Property Boundary Sector Wtteel (22.5-derjree)
(DISTANCES IN FEET) I Roade ENNSYLVANIA POWER & LIIRHT COMPANY Raiiroade Qg Residence Scale in Feet HALUBURTON NUS Envtronmantal Corp.
0 500 l000 2000 DECEMBER 10, 1992 61
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TABLE 22 CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.90 NILES NNE SECTOR Data Period: 1/1/92 12/31/92 EST INATED PERCENT NAXIIRHI DOSE OF LINIT EFFUKNT (%EN) 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 TEEN LUNG, SKIN 1.58E.02 0.05 15 PARTICULATES 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 EST INATED PERCENT NAXIMHI DOSE OF LINIT EFFLtKNT ()BIEN) LINIT (IBEN)
N/A TOTAL 6.34E-04 0.01 NOBLE GAS BODY N/A SKIN 1.79E-03 0.01 15 NOBLE GAS IODINE AND ADULT, SKIN 1.37E.02 0.05 15 PARTICULATES TEEN 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 ESTINATED PER CHIT NAXIIRN DOSE OF LINIT EFFUKNT (IRBI) LINll'.01 (IBIBI)
NOBLE GAS N/A TOTAL BMY 9.13E-04 NOBLE GAS N/A SKIN 2.57E-03 0.01 15 I(X)INE AND
'EEN SKIN 2.26E-02 0.08 15 PARTICULATES 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 EST I HATED PERCENT NAXIIRSI DOSE OF LIIIIT LINIT'IBW EFFLLKIF (IRIEN)
NOBLE GAS N/A TOTAL BODY 4.69E.03 0.05 NOBLE GAS N/A SKIN 1.32E-02 0.04 15 ICOINE AND PARTICULATES CHILD LUNG 1.10E-01 0.37 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).
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TABLE 24 CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 1 ~ 20 NILES W SECTOR DATA PERIOD: 1/1/92 - 12/31/92 EST INATED PERCENT APPLICABLE NAXIIRM DOSE OF LINIT EFFUKNT ORGAN (iaEN) LINIT (I%EN)
NOBLE GAS N/A TOTAL BtSY 1.52E.03 0.02 NOBLE GAS N/A SKIN 4.29E 03 0.01 15 IODINE AHD TEEN LUNG 1.42E.02 0.05 15 PARTICULATES 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 ESTINATED PERCENT APPLICABLE NAXIIRRI DOSE OF LINIT EFFLIKNT ORGAN (I%EN) LINIT (NREN)
NOBLE GAS N/A TOTAL BODY 1.94E.03 0.02 NOBLE GAS N/A SKIN 5.46E-03 0.02 15 IODINE AND TEEN LUNG 2.07E.02 0.07 15 PART I CULATES 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 EST lllATED PERCENT APPLI CABLE WLXWI DOSE OF LINIT EFFLlKNT ORGAN (I%BI) LTN!T (IRE)I)
NOBLE GAS N/A TOTAL BCOT 1.97E-03 0.02 NOBLE GAS N/A SKIN 5.55E 03 0.02 15 1N)1NE AND TEEH LUNG 2.28E-02 0.08 15 PARTlCULATES 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
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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:
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Nuclide Release Rate Total Release uCi sec Uci Kr-90 2.11E-07 1. 51E-01 Xe-139 2.08E-06 1.48E+00 Kr-89 1.15E-03 1.07E+03 Xe-137 2.33E-03 1.65Ew03 Xe-138 2.47E-03 1.75E+03 Xe-135m 3.95E-04 2.80E+02 Kr-87 2.61E-04 1.85E+02 Kr-83m 4.14E-05 2.94E+01 Kr-88 1.92E-04 1.36E-02 Kr-85m 4. 51E-05 3.20E+01 Xe-135 1.11E-07 7.87E-02 Xe-135m 5.33E-07 3.78E-01 Xe-133 8.18E-06 5.80E+00 Xe-131m 8.88E-09 6.30E-03 Kr -85 4. 67E-10 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 no consequence 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 CALCULATIONMANUAL AND THE SOLID WASTE PROCESS CONTROL PROGRAM 68
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.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.
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PENNSYLVANIA POWER 5 LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL Prepared By Date Reviewed By Date I 2~
Supervisor-Environmental Services Nuclear 02 -/7 Reviewed By Zo A49W ~y'cting o.
Date Approved By Date /I 1S Hanager-Nuclear Technology
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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 Revision
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- 1. 0 INTRODUCTION 12/ll/89 2 2/21/92 3 12/11/89
.2.0 SETPOINTS...........,........ 4 2/21/92 2.1 WATERBORNE EFFLUENT MONITORS. 4 2/21/92 5 12/11/89 6 2/21/92 7 12/11/89 8 12/11/89 2.2 AIRBORNE EFFLUENT MONITORS.. 9 2/21/92 10 12/11/89 11 12/11/89 12 11/25/92 3.0 WATERBORNE EFFLUENT CONCENTRATION MEASUREMENTS 13 2/21/92 14 2/21/92 4.0 AIRBORNE EFFLUENT DOSE RATES 15 2/21/92
- 4. I NOBLE GASES. 15 2/21/92 4.2 RAOIONUCLIOES OTHER THAN NOBLE GASES...... 16 2/21/92 17 2/21/92 18 2/21/92 19 12/11/89 20 2/21/92 5.0 INDIVIDUAL DOSE DUE TO WATERBORNE EFFLUENT.... 21 2/21/92 22 2/21/92 23 12/11/89 24 12/ll/89 6.0 INDIVIDUAL DOSE OUE TO AIRBORNE EFFLUENT...... 25 2/21/92 6.1 NOBLE GASES 25 2/21/92 6.2 RAOIONUCLIOES OTHER THAN NOBLE GASES...... 26 2/21/92 27 2/21/92 7.0 TOTAL DOSE 2& 2/21/92 29 2/21/92 8.0 OPERABILITY OF WASTE TREATMENT SYSTEMS........ 30 2/21/92 8.1 LIQUID WASTE TREATMENT .. 30 2/21/92 8.2 GASEOUS WASTE TREATMENT................... 30 2/21/92 31 2/21/92 32 2/21/92 8.3 SOLID WASTE TREATMENT .................... 32 2/21/92 33 2/21/92
LIST OF TABLES Revision
~Pa e ~0at Table 1 Radiological Effluent Objectives and Standards.. 3 12/11/89 Table 2 Dose Factors for Noble Gases ................... 18 2/21/92 Table 3 Sample Annual Average Relative Concentrations and Deposition Rates............................ 19 12/11/89 Table 4 Dose Factors for Inhalation, Ingestion and Ground Exposure Pathways: Radionuclides Other Than Noble Gases 20 2/21/92 Table 5 Waterborne Effluent Dose Parameters for Adults.. 24 12/11/89 Tabl e 6 Operational Radiological Environmental Honitoring Program......... .. ................ 44 11/25/92 45 ll/25/92 46 11/25/92 Table 7 Detection Capabilities for Environmental Sample Analysis................................. 47 2/21/92 48 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 2 Offgas and Recombiner System Flow Diagram... 35 2/21/92 Figure 3 Solid Waste Management System Flow Diagram.. 36 2/21/92 Figure 4 SSES Dry Contaminated Waste Processing...... 37 2/21/92 Figure 5 Environmental Monitoring Locations Within One Mile of SSES............................ 42 11/25/92 Figure 6 Environmental Monitoring Locations Greater than One Mile from SSES..................... 43 11/25/92
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NDAP-QA-0646 Revision 0 Page 25 of 61 C. Liquid:Oil Waste at concentrations I/ and greate1 may be solidified provided the following are adhered to:
(1) An emulsification agent is added at required concentrations.
(2) The Liner is NOT SHIPPED to Barnwell S.C.
Disposal Facility.
6.2.9 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.
(2) Class 8 and C sources shall be stabilized within an approved solidification or encapsulation media.
6.2.10 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 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 r6.3.1 Radionuclide concentrations of radioactive waste are r used to'classify waste for shipping and disposal.
Radionuclide concentrations should be determined based upon isotopic analysis, volume and weight of final waste form.
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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. 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.
- b. Class B - Physical form and characteristics shall meet both the minimum and stability requirements specified in 10 CFR 61.56.
C. 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.
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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.
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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 samples.
obtain'equired 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. Bead resin processing in liners shall be mixed in accordance with approved operating procedures
- prior<o analysis.
sampling or C. Wet waste to be processed may also be mixed, recirculated and sampled or analyzed from mobi1e processing equipment.
6.3.8 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.
6 3 c 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. Sol'idification processing shall be conducted by qualified SSES or Solidification/Dewatering/
Services. Vendor personnel.
C. 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.
NOAP-gA-0646 Revision 0 Page 29 of 61 Waste Preconditioning 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.
(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' d Waste prec'onditioning shall be performed in accordance with approved procedures to ensure waste is.with'in'"-ttie'cceptable envelope for solidification;
- e. 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 of Hixin'g Ratios
'etermination
- a. Oetermination of 'mixing ratios shall be performed for each waste batch to be processed.
- b. Oeviation from the recommended mixing ratios shall be reviewed by Plant Operations Revie~
Committee (PORC}.
c: Chemistry Group determines:
Oensity of the waste samples.
(2) Specific gravity of Sodium Sulfate Solution in Evaporator Concentrates.
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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.
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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
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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.
NDAP-QA-06<6 Revision 0 Page 32 of 61 PCP Surveillance Specimens
- 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.
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.
- e. 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.
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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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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. A minimum of 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> 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.
b.. The liner may be moved during the first hove
, after solidification but must remain undistUrbed for the'remaining 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />.
c~ Deviations from minimum required curing tim-.
shall be approved by Radwaste Supervisor and Justifications documented in remarks section of Solidification Record.
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NDAP-()A-0646 Revision 0 Page 34 of 61 Solidification Product equality 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.
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NDAP-()A-0646 Revision 0 Page 36 of 61 (3) 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.
(4) The above apply only if the Effluents Hanagement Supervisor determines that waste can be classified as "Class A Unstable" in accordance with 10CFR61 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:
(a) effiuents Management Supervision (b) Solidification Vendor - Operations (c) Solidification Vendor - Engineering (2) Disposal facilities shall be contacted and requirements for receipt of the liner in question shall be defined.
(3) Alternative packaging/processing shall be evaluated.
(4) Recommendations for, final disposition shall be made to the Power Production Engineer-Effluents Management.
(6) Final disposition shall be reviewed by Plant Operations Review Committee (PORC).
(6) Records shall be kept and documentation supportive of final disposition attached to the solidification record package..
(7) The liner may be shipped after g.C. review of documentation is complete and. disposal facility concurrence is received in letter form.
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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:
(1) Cement is acceptable provided the bag containing the cement indicates is Portland Type I. that'ement (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.
- d. 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.
Effluents Management Supervision, Chemistry and Solidification/Oewatering/Services Vendor personnel shall provide and check off the required documentation specified in Part 3.
C. equality Control shall provide review as required for the Solidification Records.
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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.
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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 NDAP-gA-0646 Revision 0 Page 40 of 61 6,6.3 Radioactive Waste Dewatering Records 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.
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NDAP-gA-0646 Revision 0 Page 41 of 6]
Uses of High Integrity Containers
- 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
- Other dewatered and dry material provided concurrence is received by container vendor and disposal facility.
- b. 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.
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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 0.7 to 2.5 gms/cc (2) pH 4 to 11 (3) Loading temperature : <140'F (4) Radlok 100 loaded weight: <10500 lb (5) Radlok 200 loaded weight: <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.
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NOAP-gA-0646 Revision 0 Page 45 of 61 6.8 iRRA01'ATEO HAROWARE PROCESSING ANO DEWATERING 6.8.1 General Requirements
- 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.
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.
6.8.E Oewatered. Product Control Tha fi ~l dowatereA nvnhucf eha) conf > jn )mrs 1
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.
6.9 CONTAINER INSPECTIONS .
6.9.1 guality Control shall inspect containers to be used for solidification, dewatering, and other packaging.
6.9.2 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.
6.9.3 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.
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NOAP-gA-0646 Revision 0 Page 46 of 61 6.10 WASTE CONTAINER SPACE UTILIZATION 6.10.1 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.
6.10.2 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.
6.10.3 Specific waste volumes committed to by the vendor shall be met or otherwise justified as to why waste volumes were not achieved.
6.10.4 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 Radwaste Supervisor shall provide Solidification and/or Oewatering Record sheets that have by equality Control personnel stating that been'eviewed processed waste has been solidified or de-watered in accordance with the Process Control Program and meets the applicable shipping and disposal criteria.
6.11.2 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.
6.11.3 Solidification and Dewatering Records shall be part of the permanent shipping records and adhere to requirements of the Process Control Program.
~ -6.11.4 For materials packaged in a high integrity container, documentation shall be maintained on HIC storage and pre-shipment checklist information.
NOAP-OA-0646 Revision 0 Page 47 of 61 6..5 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. 6.11.6 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. 49CFR100 - 199 Transportation.
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C. Chem-Nuclear Systems Inc. Barnwell S.C. disposal "site operating license number 097 State of South Carolina.
- d. Chem-Nuclear System Inc. NRC Haterial License 12-13536-01.
e.. '"'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 9.'.
operating license WN-1019-2 State of Washington. Scientific Ecology Group Licenses R-73008-E94, R-01052-A91.
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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.
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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. Procedures shall contain Quality Control notifications or hold points. 6.12.3 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 IOACTIVE 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 Dry Active Waste (DAW) should normally be shipped as Type A quantities and therefore do not require specific licensed containers. 6.13.4 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 NDAP-OA-0646 Revision 0 Page 50 of 61 6.13.11 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 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' 6.15.2 ~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 <.hanges in radioactive waste processing or operational changes shall be evaluated to determine any impacts on waste characteristics and/or form. 6.16.2 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," <valuation of isotopic, mix and concentration 4 Radiological surveys oF:
- a. Vehicle upon arrival Package to be shipped
- c. Loaded vehicle prior to shipment 7.4.4 Vehicle Safety inspection 7.4.5 Check-off sheet for loading procedure 7.4.6 Documentation of adherence to Process Control Program (if applicable) 7.4.i . Special instructions to driver
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Attachment A NOAP-gA-0646
'OL IOIF ICATION RECORO SHEET Revision 0 Page 54 of 61 PART I: Liner identification Information PPi!L Liner Number 2. Liner Vendor Serial Number Waste Stream (RWCU Filter Media cannot be entered)
Test Solidification required? YES NO (circle one) PART 2: Container Selection (Refer to WN-PS-100 fHP-TP-800]) Estimated Liner Contact Oose Rates mR/hr Projected Curie Concentration pCi/gm Expected Waste Classification/Stability Liner Iype to be Used 5. Empty height of Liner 'Ibs Expected Cask Type to be Used PART Oocumentation Checklist 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) iyARI c ~ REMARKS': o~ YM&Hf'n / e.'1enol
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~sn FOR(:. SOAP-(}~-0646-1, Rev. 0, Page I of 1 (File R69-1)
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Attachment 8 NOAP-QA-0646 Revision 0 Paae 55 of 6] OEWATERING RECORD SHEET 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 mR/hr Projected Cut'it> Concentration pCijgm Expected Wast,e Classification/Stability
- 4. Liner Type to be Used Empty Weight of Liner lbs.
- 6. Expected Cas): Type to be Used Radwaste Supervisor ate ime FORM NOAP-QA-0646-2, Rev. 0, (DUPLEX}, Page I of 3 (File R69-I)
rP Attachment 6 NDAP-gA-0646 Revision 0 Page 56 of 61 DEWATERING RECORD SHEET PART 3:Sampling and Analysis
- 1. Tank/Liner sampled
- 2. Sample Number
- 3. Waste Stream Oil Content (Check one)
- a. None
- b. less than 1%
Isotopic Analysis attached
- 6. Specific activity of Dewatered Sample pCi/gm
- 7. a. Dewatered Volume
- b. Dewatered Weight 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)
Attachment 8 NOAP-QA-0646 Revision 0 Page 57 of 61 OEWATERING RECORO SHEET pART a: Liner Shipment Information Summary
- 1. PPKL Liner Number 2. Waste Volume
- 3. Form NOAP-QA-0646-2 (original)
- 4. Waste Form Documentation 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 ft 3 = /o Part 4.2 AnatVol ume
>85% Container Volume Utilized YES / NO (Circle one)
Wast.e Form: STABLE UNSTABLE (Circle one)
- 5. Waste Activity Oocumentation CH-RC- Forms (Copy)
Isotopic Analysis (Copy)
- 6. Health Physics Data Liner Radiological Survey (original)
Shipment k PART 5: REHARKS:
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adwaste oper sor y LIIate ~eview Bate oreman gmt. ate FORH NOAP-QA-0646-2, Rev. 0, (OUPLEX), Page 3 of 3 (File R69-1)
4% Attachment C NOAP-gA-0646 Revision 0 Page 58 of 61 SUS UEHANNA GUARANTEED SOLIOIfIEO OEWATEREO WASTE VOLUHE RECORD
- l. Date Liner number Waste '(ype Container Type Burial Volume Useable Con'tainer Volume Guaranteed llinimum Waste Volume Waste Volu::,:.- Attained inches x ft~/inch Wast,e Volun e Cont,ainer Usage 100 x (Wast~ V~i ft'-: Guaranteed Min. Waste Vel'. t'ta) -100 'Y.
Remarks:
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- 10. Signature So idi ication Ven or epresentatsve-II. Signature Radwaste upervisor FORM NDAP-QA-0646 3. Rev. 0, Page
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1 of 1 (file R69-1) r~e;~ ~ .a. ~
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Attachment 0 NOAP-gA-0646 Revision 0 Page 59 of 61 PCP IMPLEMENTING PROCEDURE MATRIX WASTE PROCESSING 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 SEG STD-P-03-010 (HIC) SEG STD-P-22-002 (Steel Liner) (Resin Express)
..' WM-'RP-102 (OP-068-102) WM-RP-101 (OP-068-121) WM-RP-.104 d
CNSI FO-OP-019 (Overpack) WM-PS-230 (HP-TP-875) TFC Nuclear (HIC)
,'4g-RP-107 Page 1 of 3"
Attachment D NOAP-QA-0646 Revision 0 Page 60 of 61 PCP IHPLEHENTING PROCEDURE HATRIX Irradiated Hardware Oewatere Steel Liner None Or Active Waste OAW - Packa in WH-PS-210 (HP-TP-841) Liouid Oil Waste - Solidified I.i uid Oil Waste Decontamination SEG STD-P-05-002 WH-PS-302 (OP-068-135) CH-RC-050 Solid Sealed Sources None WASTE ANALYSIS ANO CLASSIFICATION - IOCFR61 CH-TI-037 WH-PS-100 (HP-TP-800) WH-RP-008 CH-RC-075 WH-PS-110 (HP-TP-801) CH-RC-076 WH- PS-120 '(HP,.-;:.TP,.-.,802) CH-TP-055 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)
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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) SEG STO-P-05-022 .SEG STD-P-05-050
~ WM-RP-205 (OP-068-120) WH-RP-002 (OP-068-132)
SC-068-002 (Test Solidification) Paoe 2 of 3 4~ C 'lp g,.n
D NDAP-gA-0646 Revision 0 GENERAC'ttachment Page 61 of 61 PCP IMPLEMENTING PROCEDURE MATRIX RADIOACTIVE WASTE DEWATERING - SEG STD-P-01-005 (Equipment) SEG STD-P-04-004 WM-RP-001 (OP-068-114) SEG STD-P-03-022 WM-RP-011 (OP-068-128) WM-RP-0!0 (OP-068-129) HIGH INTEGRITY COttTl It<ERS - CLOSURE SEG STD-P-03-"03 SEG STD-P-03-004 Wfl-RP-007 (OP-068- 123) WM-RP-006 (OP-068-124) DISPOSAL FACILITY FEOUIREMENTS WM-PS-}90 (HP-TP-806) PACKAGING WM-PS-310 (HP-TP-826) (HN-142) WM-PS-314 (HP- TP-836) (HN-190-1) WM-PS-311 (HP-TP-827) (LN-142) WM-PS-353 (HP-TP-837) (CNSI 14-170) WM-PS-312 (HN-100 I I I) WM-PS-315 (HP-TP-838) (HN-200) WM-PS-350 (HP- TP-831) (CNSI 14-195) WM-PS-316 (HP-TP-840) (CNSI 14-215) WM-PS-351 (HP-TP-832) (CNSI 21-300) WM-PS-317 (HP-TP-852) (HN 215H) WM-PS-352 (CNS I 8-120A) WM-PS-318 (Wes t inghouse TCT) WM-PS-313 (HP-TP-835) (HN-194) 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 (Eq 6) (5.26E5 min/yr) (Vent Flow Rate, cc/min) 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
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FIGURE 5 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES GOULD I ISLAND I I I I I I g,, Q p 14 LAKE
~TAW I ~ ~ ~ I I
I I 554 T 13 I I r--~ Q 555 I ~ 6Al I T I
~ 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
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1EiF1 SUSQUEHANNA iVANTICOKE RIVER T
~ ~1 GLEN LYON mT T
15F1 SHICKSHINNY 14 I MOCANAQUA 4 1
POND HILL SE2 T
g.,J A WAPVALLOPEN srir BERWICK 7El Q .un MIFFLINVILLE NESCOPECK T, T ~ INN 5 MILES yT 12H2 RLT CON YNGHAM HAZLETON 18 MILES
~m OIInXWC riTZa
~ IIaX szmae
~~ ma THKRMOI.UMINESCKNT INSIMSTIIY 43
Page 1 of 3 TABLE 6 OPERATlONAL RADIOLOGICAL EKVTRONHEKTAL lK)NiTORTKG PROGRAM Exposure Path<<ays Nmaber of Saayles Sasq)ing and Type and a o e ~Olid ochtloAS Collection Fr uenc uenc o Ana s ~raine Continual sampler operation <<ith Radioiodine Canister: analyze Radioiodine and 12S1 (0.4 mi VSV - E.O.F. Building) sample collection weekly.' weekly for l-l3l Particulates 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 mi NE - SSES Backup Het. io<<er Particulate Sample: Lab)'52 (0.5 1554 (0.6 ml NV - Transmission Corridor Analyze for gross beta radioactivity 102 (3.9 mi N - Hocanaqua Substatlon) less than 24 hours following filter 3Dl (3.4 mi HE - Pond Hill) change. Perform isotopic analysis on 12Gl (15 mi 'USU - Bloomsburg Service canposite sample (by location) quarterly. Center)'52 Perimeter Fence - 0.2 mi H Quarterly Gaane Dose: Quarterly. 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 Perimeter Fence - 0.2 NE'S3 mi EHE 4E1 Ruckles Hill Road Pole (I) 46422/H35191 - 4.8 mi EHE 4Gl Hountain Top - industrial Park-14 ml Perimeter Fence - 0.3 mi E EHE'57 SE2 Bloss Farm - 4.5 mi E 654 Perimeter Fence - 0.2 mi ESE 6A4 Former State Police - 0.6 mi ESE
Ã) Page 2 of 3 Exposure Pathways Hmaber of Samples a 0 e Saw@ling and Type and ld
~&&I~~ O&C&&&&&1~0&I&I&& Co ection Fr uenc 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 Perimeter Fence - 0.2 mi SSE SE'52 882 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 Perimeter Fence - 0.4 mi V
'MSV'3S2 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 gaiCr or&& Surface 656 river water intake line'57 Honthly composite Gaaae Isotopic analysis. cooling tower. blowdown discharge line Honthly composite Coayosite tritium analysis at least quarterly. Drinking 12H2 Danville Mater Co. Honthly composite Gross beta and ganma isotopic (Approximately 30 miles downstream) analyses monthly. Composite for tritium analysis at least quarterly. Sediment fran Shoreline 78 Bell Bend - 1.2 mi SE Semi-annually Gamna Isotopic analysis semi-annually.
Page 3 of 3 Exposure Pathways Hmuber of Sax@les San@I Ing and Type and
~ hh ocstlal
- Co lection r uenc o Ana s III1k~'~ 1283 Young Farm - 2.0 mi MSM Semi-monthly <<hen animals are on Galena isotopic and 1-131 analysis IOGI Oavls Fare - 14 mi. pasture, monthly otherwise of each sample.
Stola Farm - 1.8 ml. MNg SSW'481 10D1 Ryman Farm - 3.0 mi. SSM Fish and invertebrates Outfall area Semi-annually. One sample'rom Gaama isotopic on edible portions. 2H Falls. each of t<<o reacreationally PA'Approximately 30 mi HNE) important species from any of the folio<<ing families: bullhead catfish. sunfish, pikes. or perches. Food Products 1101 Zehner Farm - 3.3. mi SM At time of harvest Gamna isotopic on edible portions. vegetable 12F7 Luplni Farm - 8.3 mi MSM vegetable
<<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 loadin study (RHC-TR-81-01) concluded that the assumption of I for the transmission correction factor for gross beta analysis of A dust loading air particulate samples Is valid. Air particulate samples need not be weighed to determine a transmission correction factor. "lf a milk 1 sample s 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 Date (Z ~ Z. Supervisor-Environmental Services Nuclear Reviewed By Date /N+PP ~ eetsng o. Approved By Date a er-Nuclear Technology
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 Revision
~Pa e Date Table 1 Radiological Effluent Objectives and Standards.. 3 12/11/89 Table 2 Dose Factors for Noble Gases ................... 18 2/21/92 Table 3 Sample Annual Average Relative Concentrations and Deposition Rates............................ 19 12/11/89 Table 4 Dose Factors for Inhalation, Ingestion and Ground Exposure Pathways: Radionuclides Other Than Noble Gases . . ... .................. 20 12/4/92 Table 5 Waterborne Effluent Dose Parameters for Adults.. 24 12/11/89 Table 6 Operational Radiological Environmental Monitoring Program....... ................ 44 11/25/92 45 11/25/92 46 11/25/92 Table 7 Detection Capabilities for Environmental Sample Analysis................................. 47 2/21/92 48 2/21/92 Table B-1 Radiological Environmental Monitoring Program Annual Summary.........,........................ B-3 12/11/89 Table B-2 Reporting Levels for Nonroutine Operating R eports ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 4 12/11/89 Table D-1 Dilution Factors and Transit Times for SSES Effluents to Danville, PA... ............. ..... D-3 2/21/92
LIST OF FIGURES Revision
~Pa e ~ate Figure 1 Liquid Radwaste System Flow Oiagram......... 34 3/6/92 Figure 2 Offgas and Recombiner System Flow Oiagram... 35 2/21/92 Figure 3 Solid Waste Management System Flow Oiagram.. 36 2/21/92 Figure Figure Figure 4
5 6 SSES One Mile of SSES... . .'. Ory Contaminated Waste Processing...... Environmental Monitoring Locations Within Environmental Monitoring Locations Greater 37 42 2/21/92 11/25/92 than One Mile from SSES.... 43 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
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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 ADULT O.OOE+00 1.38E+03 1. 38E+03 1.38E+03 1.38E+03 1.38E+03 1.38E+03 N/A MILK TEEN O.OOE+00 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 N/A CHILD O.OOE+00 2.84E+03 2.84E+03 2.84E+03 2.84E+03 2.84E+03 2.84E+03 N/A INFANT O.OOE+00 4.31E+03 4. 31E+03 4. 31E+03 4. 31E+03 4. 31E+03 4. 31E+03 N/A COW ADULT O.OOE+00 6.77E+02 6.77E+02 6.77E>02 6.77E>02 6.77Et02 6.77E+02 N/A MILK TEEN O.OOE+00 8.82E+02 8.82E+02 8.82E+02 8.82E+02 8.82E+02 8.82E+02 N/A CHILD O.OOE+00 1.39E+03 1.39E+03 1.39E+03 1.39E+03 1.39E+03 1.39E+03 N/A INFANT O.OOE+00 2. 11E+03 2. 11E+03 2. 11E+03 2. 11E+03 2. 11E+03 2. 11E+03 N/A MEAT ADULT O.OOE+00 2.89E+02 2.89E+02 2.89E+02 2.89E+02 2.89E+02 2.89Ew02 N/A TEEN O.OOE+00 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 N/A CHILD O.OOE+00 2.08E+02 2.08E+02 2.08E+02 2.08E+02 2.08E+02 2.08E+02 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT O.OOE+00 1.82E+03 1.82E+03 1.82E+03 1.82E+03 1.82E+03 1.82E+03 N/A TEEN O.OOE+00 2. 18E+03 2. 18E+03 2. 18E+03 2. 18E+03 2. 18f+03 2. 18E+03 N/A CHILD O.OOE+00 3.42E+03 3.42E+03 3.42E+03 3.42E+03 3.42E+03 3.42E+03 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT O.OOE+00 4. 17E+03 4.17E+03 4.17E+03 4.17E+03 4.17E+03 4.17E+03 N/A INGEST. TEEN O.OOE+00 5.03E+03 5.03E+03 5.03E+03 5.03E+03 5.03E+03 5.03E+03 N/A CHILD O.OOE+00 7.86E+03 7.86E+03 7.86E+03 7.86E+03 7.86E+03 7.86E+03 N/A INFANT 0.00E+00 6.43E+03 6.43E+03 6.43E+03 6.43E+03 6.43E+03 6.43E+03 N/A INHAL. ADULT O.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 N/A TEEN O.OOE+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 N/A CHILD O.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 N/A INFANT O.OOE+00 6.47E+02 6.47f+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 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
***MAXIMUMVALUES FOR PATHWAYS**~
GROUND: GROUND: GOAT COW TOTAL T.B./ORG. SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL. 0.00000 O.OOE+00 4.31E+03 2.11E+03 2.89E+02 3.42E+03 7.86E+03 1.27E003 PAGE: 4-1
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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 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.OOE+00 CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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 ADULT 1.09E-12 2.96E-12 1.06E-12 5. 13E-11 4.71E-12 0.00E+00 2.58E-15 N/A MILK TEEN 1. 94E-12 5. 13E-12 1. 84E-12 8.55E-11 8.09E-12 O.OOE+00 6.76E-14 N/A CHILD 4.58E-12 8.51E-12 3.92E-12 1.96E-10 1.30E-11 O.OOE+00 5.64E-12 N/A INFANT 7.92E-12 1.95E-11 6.92E-12 4.54E-10 2. 18E-11 0.00E+00 2.01E-11 N/A 1l COW ADULT 5.08E-13 1.38E-12 4.94E-13 2.39E-11 2.20E-12 O.OOE+00 1.20E-15 N/A MILK TEEN 9.03E-13 2.39E-12 8.60E-13 3.99E-ll 3.77E-12 O.OOE+00 3.15E-14 N/A CHILD 2.14E-12 3.97E-12 1.83E-12 9.13f-ll 6.07E-12 O.OOE+00 2.63E-12 N/A INFANT 4.43E-12 9.08E-12 3.23E-12 2.12E-10 1.02E-11 O.OOE+00 9.39E-12 N/A MEAT ADULT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0. 00E+00 N/A TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00000 O.OOE+00 O.OOE+00 N/A CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT TEEN CHILD
- 3. 19E-05 8.65E-05 3. 10E-05 1.50E-03 1.38E-04 2.88E-05 7.63E-05 2.74E-05 1.27E-03 1.20E-04
- 5. 12E-05 9.50E-05 4.37E-05 2.19E-03 1.45E-04 O.OOE+00 7.54E-08 O.OOE+00 1.01E-06 O.OOE+00 6.30E-05
'/A N/A N/A INFANT O.OOE+00 O,OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 3. 19E-05 8.65E-05 3.10E-05 1.50E-03 1.38E-04 O.OOE+00 7.54E-08 INGEST. TEEN 2.88E-05 7.63E-05 2.74E-05 1.27E-03 1.20E-04 O.OOE+00 1 01E-06 N/A
'/A
~
CHILD 5. 12E-05 9.50E-05 4.37E-05 2.19E-03 1.45E-04 O.OOE+00 6.30E-05 N/A INFANT 1.24E-11 2.85E-11 1.02E-11 6.66E-10 3. 19E-11 O.OOE+00 2.95E-11 N/A INHAL. ADULT 6.44E+02 1.73E+03 6. 15E+02 2.98E+04 2.75E+03 O.OOE+00 1. 019 00 N/A TEEN 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+00 2. 04E+01 N/A CHILD 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+00 9.55&02 N/A INFANT 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+00 1. 29E003 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
*~MAXIMUMVALUES 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 ADULT 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 7.92E+09 TEEN 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 7.92E+09 CHILD 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 7.92E+09 INFANT 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79E+09 6.79Et09 7.92E+09 GOAT ADULT 1.06E+10 2.53E+10 2.07E+10 O.OOE+00 8. 19E+09 2.72E+09 4.43E+08 N/A MILK TEEN 1.85E+10 4.35E+10 2.02E+10 O.OOE+00 1.38E+10 5.27E+09 5.41E+08 N/A CHILD 4.26E+10 6.99E+10 1.47E+10 O.OOE+00 2. 17E+10 7.77E+09 3.77E+08 N/A INFANT 2.29E+10 1.28E+11 1.29E+10 O.OOE+00 3.30E+10 1.35E+10 3.48E+08 N/A COW ADULT 2.79E+09 6.63E+09 5.42E+09 O.OOE+00 2. 15E+09 7. 12E+08 1. 16E+08 N/A MILK TEEN 4.84E+09 1. 14E+10 5.28E+09 O.OOE+00 3.62E+09 1.38E+09 1.42E+08 N/A CHILD 1.12E+10 1.83E+10 3.86E+09 O.OOE+00 5.68E+09 2.04E+09 9.87E+07 N/A INFANT 1.80E+10 3.35E+10 3.39E+09 O.OOE+00 8.63E+09 3.54E+09 9. 11E+07 N/A MEAT ADULT 3.59E+08 8.54E+08 6.98E+08 O.OOE+00 2.76E+08 9. 17E+07 1.49E+07 N/A TEEN 2.85E+08 6.71E+08 3. 12E+08 O.OOE+00 2. 13E+08 8. 15E+07 8.35E+06 N/A CHILD 5.03E+08 8.26E+08 1.74E+08 O.OOE+00 2.56E+08 9. 18E+07 4.45E+06 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT 4. 21E+09 1.00E+10 8.19E+09'.OOE+00 3.24E+09 1.08E+09 1.75E+08 N/A TEEN 6.70E+09 1.58E+10 7.31E+09 O.OOE+00 5.01E+09 1.91E+09 1.96E+08 N/A CHILD 1.53E+10 2.52E+10 5.31E+09 O.OOE+00 7.80E+09 2.80E+09 1.36E+08 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 1.80E+10 4.28E+10 3.50E+10 O.OOE+00 1.39E+10 4.60E+09 7.49E+08 N/A INGEST. TEEN 3.03E+10 7.13E+10 3.31E+10 O.OOE+00 2.27E+10 8.65Ew09 8.87&08 N/A CHILD 6.96E+10 1.14E+l1 2.41E+10 O.OOE+00 3.54E+10 1.27E+10 6.16E+08 N/A INFANT 4.09E+10 1.62E+l1 1.63E+10 O.OOE+00 4.16E+10 1.70E+10 4.39E+08 N/A INHAL. ADULT 3.73E+05 8.48E+05 7.28E+05 O.OOE+00 2.87E+05 9.76E+04 1.04E+04 N/A TEEN 5.02E+05 1. 13E+06 5.49E+05 O.OOE+00 3.75E+05 1.46E+05 9.76E+03 N/A CHILD 6.51E+05 1.01E+06 2.25E+05 O.OOE+00 3.30E+05 1.21E+05 3.85E+03; N/A INFANT 3.96E+05 7.03E+05 7.45E+04 O.OOE+00 1.90E+05 7.97E+04 1.33E+03 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. 6.79E+09 7.92E+09 1.28E+ll 3.35E+10 8.'54E+08 2.52E+10 1.62Etll 1. 13E+06 PAGE: 4-30
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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 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.OOE+00 CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00000 O.OOE+00 O.OOE+00 O.OOE+00 INFANT O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 GOAT ADULT 6.93E+03 1.82Et04 6.70E+03 1.20E+06 2.91E+04 O.OOE+00 2.05E+04 N/A MILK TEEN 1.23E+04 3. 17E+04 1. 18E+04 2.04f+06 5.01E+04 O.OOE+00 3.51E+04 N/A CHILD 2.92E+04 5.25E+04 2.48E+04 4.65E+06 8.05E+04 O.OOE+00 4.00E+04 N/A INFANT 5.05E+04 1.21E+05 4.40E+04 1.08E+07 1.34E+05 O.OOE+00 4.37E+04 N/A COW ADULT 3.24f>03 8.47E+03 3. 13E+03 5.59E+05 1.36E+04 O.OOE+00 9.57E+03 N/A MILK . TEEN 5.75E+03 1.48Et04 5.48E+03 9.52Ew05 2.34E+04 O.OOE+00 1.64E+04 N/A CHILD 1.36E+04 2.45E+04 1. 16E+04 2.17E+06 3.75E+04 O.OOE+00 1.87E+04 N/A INFANT 2.83E+04 5.63E+04 2.05E+04 5.05E+06 6.27E+04 O.OOE+00 2.04E+04 N/A HEAT ADULT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 N/A. TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT 1.29E+04 3.37E+04 1.24E+04 2.22E+06 5.40E+04 O.OOE+00 3.80E+04 N/A TEEN 1.16E+04 2.99E+04 1. 11Ew04 1.92E+06 4.73E+04 O.OOE+00 3.32E+04 N/A CHILD 2.06E+04 3.72E+04 1.76E+04 3.29E+06 5.70E+04 O.OOE+00 2.83E+04 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OODOO O.OOE+00 O.OOE+00 N/A TOTAL ADULT 2.30E+04 6.03E+04 2.23E+04 3.98E+06 9.67E+04 O.OOE+00 6.81E+04 N/A INGEST. TEEN 2.97E+04 7.64E+04 2.83E+04 4.92E+06 1.21E+05 O.OOE+00 8.47E+04 N/A CHILD 6.34E+04 1.14E+05 5.40E+04 1.01&07 l.'75E+05 O.OOE+00 8.70E+04 N/A INFANT 7.88E+04 1.77E+05 6.45E+04 1.59E+07 1.97E+05 O.OOE+00 6.40E+04 N/A INHAL. ADULT 2.68E+03 6.98E+03 2.57Et03 4.48E+05 l. 11E+04 O.OOE+00 5.25E003 N/A TEEN 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+00 6.95003 N/A CHILD 4.92E+03 8.73E+03 4. 14E+03 7.92E+05 1.34E+04 0.DOE+00 4.44E+03 N/A INFANT 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 O.OOE+00 1.83003 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
~
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~~~MAXINUN VALUES FOR PATHWAYS***
GROUND'ROUND: GOAT COW TOTAL T.B./ORG. SKIN MILK: MILK: HEAT: VEGTBLE: INGEST-'NHAL O.OOE+00 O.OOE+00 1.08E+07 5.05E+06 O.OOEw00 3.29f+06 1.59E+07 7.92Et05 PAGE: 4-31
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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 1.49E+08 1.49E+08 1.49E+08 1.49B08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 TEEN 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 CHILD 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69BOB INFANT 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 ADULT 3.57E+08 1.41E+09 1.01E+09 O.OOE+00 7.84E+08 1.07E+08 1.60E+08 N/A MILK TEEN 6.07E+08 2.39E+09 1.61E+09 O.OOE+00 1.30E+09 2.05E+08 1.92E+08 N/A CHILD 1.37E+09 3.77E+09 2.44E+09 O.OOE+00 2.01E+09 2.99E+08 1.32E+08 N/A INFANT 8.93E+08 7.88E+09 2.94E+09 O.OOE+00 3. 14E+09 6.42E+08 1.20E+08 N/A COW ADULT 6.69E+07 2.64E+08 1.90E+08 O.OOE+00 1.47E+08 2.02E+07 3.00E+07 N/A MILK TEEN 1. 14E+08 4.48E+08 3.01E+08 O.OOE+00 2.44E+08 3.85E+07 3. 61E+07 N/A CHILD 2.57E+08 7.07E+08 4.58E+08 O.OOE+00 3.77E+08 5.62E+07 2.48E+07 N/A INFANT 5.02E+08 1.48E+09 5.52E+08 O.OOE+00 5.89E+08 1.20E+08 2.24E+07 N/A MEAT ADULT 4.00E+06 1.58E+07 1. 14E+07 O.OOE+00 8.78E+06 1.20E+06 1.79E+06 N/A TEEN 3. 12E+06 1.23E+07 8.24E+06 O.OOE+00 6.68E+06 1.05E+06 9.87E+05 N/A CHILD 5.38E+06 1.48E+07 9.57E+06 O.OOE+00 7.87E+06 1. 17E+06 5.20E005 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT 2.03E+07 8.01E+07 5.76E+07 0.00E+00 4.46E+07 6.11E+06 9. 10E+06 N/A TEEN 2.43E+07 9.58E+07 6.43E+07 O.OOE+00 5.21E+07 8.22E+06 7. 71E+06 N/A CHILD 4.96E+07 1.36E+08 8.82E+07 O.OOE+00 7.26E+07 1.08E+07 4.79E+06 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 " N/A TOTAL ADULT 4.48E+08 1.77Et09 1.27Ew09 O.OOE+00 9.84E+08 1.35E+08 2. 01E+08 N/A INGEST. TEEN 7.49E+08 2.95E+09 1.98E+09 O.OOE+00 1.60Ew09 2.53Ew08 2.37E+08 N/A CHILD 1.68E+09 4.63E+09 2.99E+09 O.OOE+00 2.46E+09 3.67E+08 1.63E+08 N/A INFANT 1.40E+09 9.35E+09 3.49E+09 O.OOE+00 3.73009 7.62E+08 1.42E+08 N/A INHAL. ADULT 3.90E+04 1.46E+05 1.10E+05 O.OOE+00 8.56E+04 1.20E+04 1.17E+04 N/A TEEN 5.15E+04 1.94E+05 1.37E+05 O.OOE+00 1.10E+05 1.78E+04 1.09E+04 N/A CHILD 6.51E+04 1.71E+05 1. 16E+05 O.OOE+00 9.55E+04 1.45E+04 4.18E+03 N/A INFANT 4.83E+04 1.35E+05 5.29E+04 O.OOE+00 5.64E+04 1.18E+04 1.43E+03 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 PAT WAYS~**
GROUND: GROUND: GOAT COW TOTAL T.B./ORG. SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL. 1.49E+08 1.69E+08 7.88E+09 1.48E+09 1.58Et07 1.36E+08 9.35E+09 1.94E<05 PAGE: 4-32.
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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 ADULT 1.42E+10 1.94E+10 1.27E+10 O.OOE+00 6.59E+09 2.19E+09 3.76E+08 N/A MILK TEEN 2.58E+10 3.43E+10 1.19E+10 O.OOE+00 1.17E+10 4.53E+09 4.88E+08 N/A CHILD 6.20E+10 5.94E+10 8.77E+09 O.OOE+00 1.94E+10 6.96E+09 3.72E+08 N/A INFANT 3.30E+10 1.16E+ll 8.22E+09 O.OOE+00 3.11E+10 1'.26E+10 3.62E+08 N/A COW ADULT 3.78E+09 5. 17E+09 3.39E+09 O.OOE+00 1.76E+09 5.84E+08 1.00E+08 N/A MILK TEEN 6.86E+09 9. 12E+09 3. 18E+09 O.OOE+00 3. 10E+09 1.21E+09 1.30E+08 N/A CHILD 1.65E+10 1.58E+10 2.33E+09 O.OOE+00 5.15E+09 1.85E+09 9.90E+07 N/A INFANT 2.64E+10 3.09E+10 2.19E+09 O.OOE+00 8.28E+09 3.35E+09 9.65E+07 N/A MEAT ADULT 4.91E+08 6.71E+08 4.40E+08 O.OOE+00 2.28E+08 7.58E+07 1.30E+07 N/A. TEEN 4.08E+08 5.42E+08 1.89E+08 O.OOE+00 1.85E+08 7.17B07 7.72E+06 N/A CHILD 7.51E+08 7.19E+08 1.06E+08 O.OOE+00 2.34E+08 8.42E+07 4.50E+06 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEw00 O.OOE+00 N/A VEGTBLE ADULT 5.76E+09 7.88E+09 5. 16E+09 O.OOE+00 2.68E+09 8.89E+08 1.53E+08 N/A TEEN 9.58E+09 1.27E+10 4.44E+09 O.OOE+00 4.34E+09 1.69E+09 1.81E+08 N/A CHILD 2.29E+10 2.19E+10 3.24E+09 O.OOE+00 7.15E+09 2.57E+09 1.37008 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 N/A TOTAL ADULT 2.42E+10 3.32E+10 2.17E+10 O.OOE+00 1.13E+10 3.74E+09 08
'.420 N/A INGEST. TEEN 4.26E+10 5.67E+10 1.97E+10 O.OOE+00 1.93E+10 7.49E+09 8.06E+08 N/A CHILD 1.02E+ll 9.79E+10 1.44E+10 O.OOE+00 3.19E+10 1.15E+10 6. 13E+08 N/A INfANT 5.94E+10 1.47E+11 1.04E+10 O.OOE+00 3.94E+10 1.60E+10 4.59E+08 N/A INHAL. ADULT 4.78E+05 6.21E+05 4.28E+05 O.OOE+00 2.22E+05 7.52Et04 8.40E+03 N/A TEEN 6.70E+05 8.48005 3.11Et05 O.OOE+00 3.04E+05 1.21E+05 8.48E+03 N/A CHILD 9.07E+05 8.25Et05 1.28E+05 O.OOE+00 2.82E+05 1.04E+05 3.62E+03 N/A INFANT 5.49E+05 6.12E005 4.55E+04 O.OOE+00 1.72E+05 7.13&04 1.33B.03.- 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. 1.02E+10 1.19E+10 1.16E+ll 3.09E+10 7.51E+08 2.29E+10 1.47E+ll 9.07E+05 PAGE: 4-33
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0 O.D.C.M. MAXIMUM PATHWAY DOSE FACTORS: RADIONUCLIDES OTHER THAN NOBLE GASES* Ba-140 'SOTOPE: PATHWAY AGE GROUP BONE LIVER T.BODY THYROID KIDNEY LUNG G.I. SKIN GROUND ADULT 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.32E+07 TEEN 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.32E+07 CHILD 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.03E+07 2.32E+07 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 GOAT ADULT 1.46E+06 1.83E+03 9.54E+04 O.OOE+00 6.22E+02 1.05E+03 3.00E+06 N/A MILK TEEN 2.63E+06 3.22E+03 1.69E+05 O.OOE+00 1.09E+03 2. 17E+03 4.05E+06 N/A CHILD 6.35E+06 5.56E+03 3.70E+05 O.OOE+00 1.81E+03 3.31E+03 3.22E+06 N/A INFANT 1.09E+08 1.3lf+04 6.73E+05 O.OOE+00 3.10E+03 8.02E+03 3.21E+06 N/A COW ADULT 6.83E+06 8.58E+03 4.47f+05 O.OOE+00 2.92E+03 4.91E+03 1,41E+07 N/A MILK TEEN 1.23E+07 1.51E+04 7.94E+05 O.OOE+00 5. 12E+03 1.02E+04 1.90E+07 N/A CHILD 2.97E+07 2.61E+04 1.74E+06 O.OOE+00 8.48E+03 1.55E+04 1.51E+07 N/A INFANT 6.12E+07 6.12E+04 3. 15E+06 O.OOE+00 1.45E+04 3.76E+04 1.50E+07 N/A MEAT ADULT 9.52E+06 1.20E+04 6.24E+05 O.OOE+00 4.07E+03 6.85E+03 1.96E+07 N/A TEEN 7.87E+06 9.65E+03 5.07E+05 O.OOE+00 3.27E+03 6.49E+03 1.21E+07 N/A CHILD 1.45E+07 1.27E+04 8.48E+05 O.OOE+00 4. 14E+03 7.59E+03 7.36E+06 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT 5.98E+07 7.51E+04 3.92E+06 O.OOE+00 2.55E+04 4.30E+04 1.23E+08 N/A TEEN 7.50E+07 9.19E+04 4.83E+06 O.OOE+00 3.12E+04 6.18E+04 1.16E+08 N/A CHILD 1.62E+08 1.42E+05 9.48E+06 O.OOE+00 4.63E+04 8.48E+04 8.23E+07 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 7.76E+07 9.75E+04 5.08E+06 O.OOE+00 3.31E+04 5.58E+04 1.60E+08 N/A INGEST. TEEN 9.78E+07 1.20E+05 6.31E+06 O.OOE+00 4.07E+04 8.06E+04 1. 51E+08 N/A CHILD 2. 13E+08 1.87E+05 1.24E+07 0.00E+00 6.08E+04 1.11E+05 1.08E+08 N/A INFANT 1.70E+08 7.43E+04 3.83E+06 O.OOE+00 1.76E+04 4.56E+04 1.82E+07 N/A INHAL. ADULT 3.90E+04 4. 90E+01 2.57E+03 O.OOE+00 1.67E+01 1.27B.06 2.18E+05 N/A TEEN 5.47E+04 6.94E+01 3.52Ew03 O.OOE+00 '2.28E+01 2.03E+06 2.29E+05 N/A CHILD 7.40E+04 6.48E+01 4.33E+02 O.OOE+00 2.11E+01 1.74E+06 1.02E+05 N/A INFANT 5.60E+04 5. 60E+01 2.90E+03 0.00E+00 1.34E+Ol 1.60E+06 3.84E+04 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
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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 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.OOE+00 CHILD O.OOE+00 O.OOE+00 O.OOE+00 0:OOE+00 O.OOE+00 O.OOE+00 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 ADULT 2.44E-01 1.23E-01 3.25E-02 O.OOE+00 O.OOE+00 O.OOE+00 9.02E403 N/A MILK TEEN 4.38E-01 2.15E-01 5.72E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.24E+04 N/A CHILD 1.05E+00 3.66E-01 1.23E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.02E+04 N/A INFANT 1.82E+Ol 8.63E-Ol 2.22E-01 O.OOE+00,0.00E+00 O.OOE+00 1. 01E+04 N/A COW ADULT 1.14E+00 5.73E-Ol 1.51E-01 0.00900 O.OOE+00 O.OOE+00 4.21E+04 N/A MILK TEEN 2.04E+00 1.00E+00 2.67E-Ol O.OOE+00 O.OOE+00'.OOE+00 5.76E+04 N/A CHILD 4.89E+00 1.71E+00 5.76E-01 O.OOE+00 O.OOE+00 O.OOE+00 4.76E+04 N/A INFANT 1.02E+01 4.03E+00 1.04E+00 O.OOE+00 O.OOE+00 O.OOE+00 4.73E+04 N/A MEAT ADULT 1.22E-02 6. 16E-03 1.63E-03 O.OOE400 O.OOE+00 O.OOE+00 4.53E+02 N/A TEEN 1.01E-02 4.94E-03 1.32E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.84f+02 N/A CHILD 1.84E-02 6.44E-03 2. 17E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.79E+02 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 N/A VEGTBLE ADULT 6.53Ew02 3.29E+02 8.69E+Ol O.OODOO O.OOE+00 O.OOE+00 2. 41E+07 N/A TfEN 5.96E+02 2.93E+02 7.79E+Ol O.OOE+00 O.OOE+00 O.OOE+00 1.68E+07 N/A CHILD 1.07E+03 3.74E+02 1.26f+02 O.OOE+00 O.OOE+00 O.OOE+00 1.04E+07 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 6.54E+02 3.30E+02 8.71E+Ol O.OOE+00 O.OOE+00 O.OOE+00 2.42Ew07 N/A INGEST, TEEN 5.99E+02 2.94E+02 7.83E+01 O.OOE+00 O.OOE+00 0.00f+00 1.69E+07 N/A CHILD 1.08E+03 3.76E+02 1.27E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.05E+07 N/A INFANT 2.85E+01 4.89E+00 1.26E+00 O.OOE+00 O.OOE+00 O.OOE+00 5.74E+04 N/A INHAL. ADULT 3.44E+02 1.74E+02 4.58E+01 0.00E+00 0.00E+00 1.36E+05 4.58E+05 N/A TEEN 4.79E+02 2.36E+02 6.26E+Ol O.OOE+00 O.OOE+00 2.14E+05 4.87E+05 N/A CHILD 6.44E+02 2.25E+02 7.55E+01 0.00E+00 0.00E+00 1.83E+05 2.26E+05 N/A INFANT 5.05E+02 2.00E+02 5.15E+01 0.00E+00 0.00E+00 1.68E+05 8.48E+04 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
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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 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.52E+07 TEEN 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.52E+07 CHILD 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 1.35E+07 l.'35E+07 1.52E+07
'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 GOAT ADULT 2.78E+02 1.88E+02 2. 13E+01 O.OOE+00 8.73E+Ol O.OOE+00 7.19E+05 N/A MILK TEEN 5. 10E+02 3.40E+02 3.91E+Ol O.OOE+00 1.60E+02 O.OOE+00 9.74E+05 N/A CHILD 1.26E+03 6.26E+02 9.30E+Ol O.OOE+00 2.75E+02 O.OOE+00 7. 81B 05 N/A INFANT 2.07E+04 1.52E+03 1.79E+02 O.OOE+00 4.68E+02 O.OOE+00 7. 84E+05 N/A COW ADULT 1.41E+03 9.51E+02 1.08E+02 O.OOEi00 4.42Ew02 O.OOE+00 3.64E+06 N/A MILK TEEN 2.58E+03 1.72E+03 1.98E+02 O.OOE+00 8.11E+02 O.OOE+00 4.93E006 N/A CHILD 6.35E+03 3. 17E+03 4.70E+02 O.OOE+00 1.39E+03 O.OOE+00 3.95006 N/A INFANT 1.26E+04 7.68E+03 9.04E+02 O.OOE+00 2.37E+03 O.OOE+00 3.97606 N/A MEAT ADULT 5.11E+03 3.46E+03 3.92E+02 O.OOE+00 1.61E+03 O.OOE+00 1.32E+07 N/A'/A TEEN 4.29E+03 2.87E+03 3.29E+02 O.OOE+00 1.35E+03 O.OOE+00 8.20E+06 CHILD 8.08E+03 4.03E+03 5.99E+02 O.OOE+00 1.77E+03 O.OOE+00 5.03E+06 N/A INFANT 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00f+00 N/A VEGTBLE ADULT f
- 1. 49E~OS 1. 0 I >05 1. 14E+04 O.OOE+00 4.69E+04 O.OOE+00 3.86E+08 N/A TEEN 2.38E>05 1.59E+05 1.83E+04 O.OOE+00 7.49E+04 O.OOE+00 4.55E+08 N/A CHILD 5.73005 2.86E+05 4.25E+04 O.OOE+00 1.25E+05 O.OOE+00 3.57E+08 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 1.56E+05 1.06E+05 1.20E+04 O.OOE+00 4.90E+04 O.OOE+00 4.03E+08 N/A INGEST. TEEN 2.46E+05 1.64E+05 1.88&04 0.00E+00 7.72E+04 0.00E+00 4.69E+08 N/A CHILD 5.89E+05 2.94E+05 4.36E+04 O.OOE+00 1.29E+05 O.OOE+00 3.67&08 N/A INFANT 3.33E+04 9.20E+03 1.08E+03 O.OOE+00 2.84E+03 O.OOE+00 4.75E+06 N/A INHAL. ADULT'EEN 1.99E+04 1.35E+04 1.53E+03 O.OOE+00 6.26E+03 3.62005 1.20E+05 N/A 2.84E+04 1.90E+04 2. 17E+03 O.OOE+00 8.88E+03 6.14E+05 1.26Ew05 N/A CHILD 3.92Et04 1.95E+04 2.90E+03 O.OOE+00 8.55E+03 5.44E+05 5.66E+04 N/A INFANT 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 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
*~MAXIMUMVALUES 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
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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 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOBOO TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEw00 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 ADULT 8.57E+00 3.44E+00 4.25E-Ol O.OOE+00 1.98E+00 O.OOE+00 3.75E+04 N/A MILK TEEN 1.57E+01 6.28E+00 7.83E-01 O.OOE+00 3.65E+00 O.OOE+00 5.18E+04 N/A CHILD 3.89E+Ol 1.17E+Ol 1.93E+00 O.OOE+00 6.33E+00 O.OOE+00 4.20E+04 N/A INFANT 6.71E+02 3.01E+Ol 3.99E+00 O.OOE+00 1.12E+Ol O.OOE+00 4.25E+04 N/A COW ADULT 4.02E+01 1.61E+01 1.99E+00 O.OOE+00 9.31E+00 O.OOE+00 1.76E+05 N/A MILK TEEN 7.39E+01 2.95E+Ol 3.68E+00 O.OOE+00 1.71E+Ol O.OOE+00 2.43E+05 N/A CHILD 1.83E+02 5.49E+01 9.07E+00 O.OOE+00 2.97E+Ol O.OOE+00 1.97E+05 N/A INFANT 3.78E+02 1.41E+02 1.87E+01 O.OOE+00 5.26E+Ol O.OOE+00 2.00E+05 N/A HEAT ADULT 6.96E+03 2.79E+03 3.45E+02 O.OOE+00 1.61E+03 O.OOE+00 3.05E+07 N/A TEEN 5.86E+03 2.34E+03 2.92E+02 O.OOE+00 1.36E+03 O.OOE+00 1.93E+07 N/A CHILD l. 11E+04 3.33E+03 5.50E+02 O.OOE+00 1.80E+03 O.OOE+00 1.20E+07 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT 3.04E+04 1.22E+04 1.51E+03 O.OOE+00 7.04E+03 O.OOE+00 1.33E+08 N/A TEEN 4.00E+04 1.60E+04 1.99E+03 O.OOE+00 9.27E+03 O.OOE+00 1.31E+08 N/A CHILD 8.98E004 2.69E+04 4.45E+03 O.OOE+00 1.46E+04 O.OOE+00 9.68E+07 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00f+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 3.74E+04 1.50E+04 1.86E+03 O.OOE+00 8.67E+03 O.OOE+00 1.64E+08 N/A INGEST, TEEN 4.59E+04 1.83E+04 2.28E+03 O.OOE+00 1.07E+04 O.OOE+00 1.51E+08 N/A CHILD 1.01E+05 3.03E+04 5.01E+03 O.OOE+00 1.64E+04 O.OOE+00 1.09E+08 N/A INFANT '.05E+03 1.72E+02 2.27E+Ol O.OOE+00 6.38E+Ol O.OOE+00 2.42E+05 N/A INHAL. ADULT 9.36E+03 3.75E+03 4.64E+02 O.OOE+00 2.16E+03 2.81E+05 2.00E+05 N/A TEEN 1.34E+04 5.31E+03 6.62E+02 O.OOE+00 3.09E+03 4.83E+05 2.14E+05 N/A CHILD 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 N/A INFANT 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 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
***MAXIMUMVALUES FOR PATHWAYS**~
GROUND: GROUND: GOAT COW TOTAL T.B./ORG. SKIN MILK: MILK: HEAT: VEGTBLE: INGEST: INHAL. 0.00E+00 0.00E+00 5.18E+04 2.43E+05 3.05E+07 1.33E+08 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 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 7.96E+07 TEEN 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 7.96E+07 CHILD 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 6.88E+07 7.96E+07 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 GOAT ADULT 2.60E+04 1.09E+04 1.39E+03 O.OOE+00 6.44E+03 O.OOE+00 8.78E+06 N/A MILK TEEN 4.78E+04 1.98E+04 2.57E+03 O.OOE+00 1. 18E+04 O.OOE+00 1.20E+07 N/A CHILD 1. 18E+05 3.69E+04 6.28E+03 O.OOE+00 2.04E+04 O.OOE+00 9.63E+06 N/A INFANT 1.41E+06 6.91E+04 9.46E+03 O.OOE+00 2.79E+04 O.OOE+00 9.68E+06 N/A COW ADULT 1.65E+05 6.91E+04 8.88E+03 O.OOE+00 4.10E+04 O.OOE+00 5.59E+07 N/A MILK TEEN 3.04E+05 1.26E+05 1.63E+04 O.OOE+00 7.52E+04 O.OOE+00 7.65E+07 N/A CHILD 7.50E+05 2.35E+05 4.00E+04 O.OOE+00 1.30E+05 O.OOE+00 6. 13E+07 N/A INFANT 1.07E+06 4.40E+05 6.02E+04 O.OOE+00 1.78E+05 O.OOE+00 6. 17E+07 N/A MEAT ADULT 7.55E+05 3. 16E+05 4.05E+04 O.OOE+00 1.87E+05 O.OOE+00 2.55E+08 N/A TEEN 6.36E+05 2.63E+05 3.42E+04 O.OOE+00 1.57E+05 O.OOE+00 1.60E+08 N/A CHILD 1.20E+06 3.76E+05 6.40E+04 O.OOE+00 2.08E+05 O.OOE+00 9,80E+07 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT 2.94E+07 1.23E+07 1.58E+06 O.OOE+00 7.30E+06 O.OOE+00 9.95E+09 N/A TEEN 4.95E+07 2.05E+07 2.66E+06 O.OOE+00 1.22E+07 O.OOE+00 1.24E+10 N/A CHILD 1.21E+08 3.80E+07 6 '6E+06 O.OOE+00 2. 10E+07 O.OOE+00 9.90E+09 N/A INFANT O.OOE+00 O,OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 3.04E+07 1.27E+07 1.63Et06 O.OOE+00 7.53E+06 O.OOE+00 1.03E+10 N/A INGEST. TEEN 5.05E+07 2.09E+07 2 71E+06 O.OOE+00 1.25E+07 O.OOE+00
~ 1.27E+10 N/A CHILD 1.23E+08 3.86E+07 6.57E+06 O.OOE+00 2.14E+07 O.OOE+00 1.01E+10 N/A INFANT 2.48E+06 5.09E+05 6.97E+04 O.OOE+00 2.06E+05 O.OOEw00 7. 14E+07 N/A INHAL. ADULT 3.43f+06 1.43Et06 1.84E+05 O.OOE+00 8.48E+05 7.78E+06 8.16E+05 N/A TEEN 4.89E+06 2.02E+06 2.62E+05 O.OOE+00 1.2IE+06 1.34E+07 8.64905 N/A CHILD 6.77E+06 2.12E+06 3.61E+05 O.OOE+00 1.17E+06 1.20E+07 3.89E+05 N/A INFANT 3.19E+06 1.21E+06 1.76E+05 O.OOE+00 5.38E+05 9.84606 1.48E+05 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
**>>MAXIMUMVALUES FOR PATHWAYS*>>>>
GROUND: GROUND: GOAT COW TOTAL T.B./ORG. SKIN MILK: MILK: MEAT: VEGTBLE INHAL. INGEST'.27E+10 6.88E+07 7.96E+07 1.20E+07 7.65E+07 2.55E+08 1.24E+10 1.34E+07 PAGE: 4-38 I DAT
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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 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.OOE+00 CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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 ADULT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A MILK TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A COW ADULT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A MILK TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A CHILD O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A MEAT ADULT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 '/A VEGTBLE ADULT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT O.OOE+00 O.OOE+00 0.00f+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INGEST. TEEN O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INFANT O.OOE+00, O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A INHAL. ADULT 3.01E-02 1.25E-02 1.53E-03 O.OOBOO 7.05E-03 1.02E003 2. 15E-08 N/A TEEN 4.30E-02 1.76E-02 2. 18E-03 O.OODOO 1.01E-OZ 1.75E+03 2.35E-04 N/A CHILD 5.96E-OZ 1.85E-02 3.00E-03 O.OOE+00 9.77E-03 1.57E+03 1.97Ew02 N/A INFANT 4.79E-02 1.85E-02 2.41E-03 O.OOE+00 6.72E-03 1.61E+03 4.28Ew03 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
**~MAXIMUMVALUES 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
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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 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 9.97E+06 TEEN 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 9.97E+06 CHILD 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 8.31E+06 9.97E+06 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 GOAT ADULT 5.09E+00 5.89E+00 3.52E-01 O.OOE+00 3.44E+00 O.OOE+00 2.83E004 N/A HILK TEEN 9.80f+00 1.07E+Ol 6.38E-01 O.OOE+00 6.26E+00 O.OOE+00 3.84E+04 N/A CHILD 2.40E+Ol 1.95E+01 1.51E+00 O.OOE+00 1.07E+Ol O.OOE+00 3.09E+04 N/A INFANT 3.97E+02 4.90E+Ol 3.00E+00 O.OOE+00 1.89E+Ol O.OOE+00 3. 10E+04 N/A COW ADULT 2.38E+Ol 2.75E+Ol 1.65E+00 O.OOE+00 1.61E+Ol O.OOE+00 1.32E+05 N/A MILK TEEN 4.58E+01 4.98E+Ol 2.98E+00 O.OOE+00 2.93E+Ol O.OOE+00 1.80E+05 N/A CHILD 1.12E+02 9.11E+01 7.05E+00 O.OOE+00 5.00E+01 O.OOE+00 1.44E+05 N/A INFANT 2.23E+02 2.29E+02 1.40E+01 O.OOE+00 8.82E+Ol O.OOE+00 1.45E+05 N/A HEAT ADULT 2.34E+03 2.70E+03 1.62E+02 O.OOE+00 1.58E+03 O.OOE+00 1.30E+07 N/A TEEN 2.06E+03 2 '4E+03 1.34E+02 O.OOE+00 1.31E+03 O.OOE+00 8.08E+06 N/A CHILD 3.86E+03 3.13E+03 2.42E+02 O.OOE+00 1.72E+03 O.OOE+00 4.96E+06 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A VEGTBLE ADULT 1.39E+04 1.61E+04 9.61E+02 O.OOE+00 9.39E+03 O.OOE+00 7.71E>07 N/A TEEN 1.72Ew04 1.87E+04 1. 12E+03 O.OOE+00 1. 10E+04 O.OOE+00 6,74E+07 N/A CHILD 3.65E+04 2.95E+04 2.29f+03 O.OOEt00 1.62E+04 O.OOE+00 4.68E+07 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 1.63E+04 1.88E+04 1. 12E+03 O.OOE+00 1. 10E+04 O.OOE+00 9.03E+07 N/A INGEST. TEEN 1.93E+04 2. 10E+04 1.26E+03 O.OOE+00 1.23E+04 O.OOE+00 7.57E+07 N/A CHILD 4.05E+04 3.28E+04 2.54E+03 O.OOE+00 1.80E+04 O.OOE+00 5.19E+07 N/A INFANT 6.20E+02 2.78E+02 1.70E+Ol O.OOE+00 1.07E+02 O.OOE+00 1.76E+05 N/A INHAL. ADULT 5.27E+03 6.10E+03 3.65E+02 O.OOEt00 3.56E+03 2.21E+05 1.73005 N/A TEEN 7.86E+03 8.56E+03 5. 13E+02 O.OOE+00 5.02E+03 3.72E+05 1.82Ew05 N/A CHILD 1.08B04 8.73E+03 6.81E>02 O.OOE+00 4.81Et03 3.28E+05 8. 21E+04 N/A INFANT 7.94E+03 8. 13003 5.00E+02 O.OOE+00 3. 15E+03 3.22E+05 3. 12E+04 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
"*~MAXIMUMVALUES 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 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.OOE+00 CHILD O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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 ADULT 1.98E-01 1.95E-02 1.08E-OZ O.OOE+00 6.08E-OZ O.OOE+00 4.00E+03 N/A MILK TEEN 3.79E-01 3.57E-02 1.98E-02 O.OOE+00 1.12E-01 O.OOE+00 5.74E+03 N/A CHILD 9.32E-01 6.69E-02 4.70E-02 O.OOE+00 1.93E-01 O.OOE+00 4.95E+03 N/A INFANT 1.64E+01 9.96E-02 9.96E-02 O.OOE+00 3.51E-01 O.OOE+00 5.09B 03 N/A COW ADULT 9.26E-01 9.10E-OZ 5.02E-02 O.OOE+00 2.84E-01 O.OOE+00 1.87E+04 N/A MILK TEEN 1.77E+00 1.67E-01 9.25E-02 O.OOE+00 5.23E-01 O.OOE+00 2.68E+04 N/A. CHILD 4.35E+00 3.12E-01 2.19E-01 O.OOE+00 9.02E-01 O.OOE+00 2. 31E+04 N/A INFANT 9. 19E+00 8. 22E-0 1 4. 64E-01 0. OOE+00 1. 64E+00 0. OOE+00 2.38E+04 N/A MEAT ADULT 8.54E-02 8.40E-03 4.63E-03 O.OOE+00 2.62E-02 O.OOE+00 1.72E+03 N/A TEEN 7.47E-02 7.04E-03 3.91E-03 O.OOE+00 2.21E-02 O.OOE+00 1.13Ew03 N/A CHILD 1.41E-01 1.01E-02 7.09E-03 O.OOE+00 2.92E-OZ O.OOE+00 7.47E+02 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOBOO N/A VEGTBLE ADULT 4.71E+02 4.63E+01 2.55E+01 O.OOE+00 1.45E+02 O.OOE+00 9.50E+06 N/A TEEN 4.57E+02 4.31Et01 2.40001 O.OOE+00 1.35E+02 O.OOEw00 6.94E+06 N/A CHILD 8.44E+02 6.06E+01 4.26E+Ol O.OOE+00 1.75E+02 O.OOBOO 4.49E+06 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/A TOTAL ADULT 4.72E+02 4.64E+Ol 2.56E+Ol O.OOE+00 1.45E+02 O.OOE+00 9.53E+06 N/A INGEST. TEEN 4.60E+02 4.33E+01 2.41E+01 O.OOE+00 1.36E+02 O.OOE+00 6.97Ew06 N/A CHILD 8.50E+02 6.10E+01 4.29E+Ol 0.00E+00 1.76E+02 0.00E+00 4.52E+06 N/A INFANT 2.56E+01 9.22E-Ol 5.64E-01 O.OOE+00 1.99Ew00 O.OOE+00 2.89E+04 N/A INHAL. ADULT 2.30E+02 2.26E+01 1.24E+Ol O.OOE+00 7.00E+Ol 3.76E+04 1.19E+05 N/A TEEN 3.38E+02 3.19E+01 1.77E+01 0.00E+00 1.00E+02 6.49E+04 1.32E005 N/A CHILD 4.66E+02 3.34E+01 2.35E+01 O.OOE+00 9.73E+01 5.81004 6.40E+04 N/A INFANT 3.71Et02 3.32E+Ol 1.88E+01 O.OOE+00 6.62E+01 5.95E+04 2.49E+04 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
*~*MAXIMUMVALUES FOR PATHWAYS"~
GROUND: GROUND: GOAT COW TOTAL T.B./ORG. SKIN MILK: MILK: MEAT: VEGTBLE: INGEST: INHAL. O.OOE+00 O.OOE+00 5.74E+03 2 '8E+04 1.72E+03 9.50E+06 9.53E+06 1.32E+05 PAGE: 4-41
PAGE 1 OF 2 **DATA C APTURE** REG.GUIDE 1.109
~ ~ TIME: 5. 26E+01
. ISTOPE INPUT DATA ISOTOPE: 1-134 LAMBDA: 2.20E-04 Biv: 2.00E-02 Fm(COW): 6.00E-03 Ff: 2.90E-03 Fm(GOAT) :6.00E-02 E7bone 8.05E-08 E71iver 2.16E-07 E7TB 7.69E-08 E7Thy 3.73E-06 E7Kidn 3.44E-07 E7Lung O.OOE+00 E7GI 1.26E-10 E8bone 1.11E-07 ESliver 2.90E-07 E8TB 1.05E-07 ESThy 4.94E-06 ESKidn 4.58E-07 ESLung O.OOE+00 ESGI 2.55E-09 E9bone 3.17E-07 E91iver 5.84E-07 E9TB 2.69E-07 E9Thy 1.37E-05 E9Kidn 8.92E-07 E9Lung O.OOE+00 E9GI 2.58E-07 DATE RUN: 11/18/92 E10bone 6.58E-07 E101i ver 1.34E-.06 E10TB 4.75E-07
~4 IWC Zf ElOThy 3. 18E-05 II/I I/y2 E10Kidn 1.49E-06 VERIFIED 8:/DATE: E10Lung O.OOE+00 E10GI 9.21E-07
PAGE 2 OF 2 El lbone 1.06E-07 REG.GUIDE 1.109
~ ~ ll El i ver 2.88E-07 ISTOPE INPUT DATA E11TB 1.03E-07 ISOTOPE: I-134 EllThy 4.99E-06 El lKidn 4.58E-07 El lLung O.OOE+00 E11GI 2. 51E-10 E12bone 1.46E-Q7 E121 iver 3.87E-07 E12TB 1.39E-07 E12Thy 6.45E-06 E12Ki dn 6.10E-07 E12Lung 0.00E+00 E12GI 5.10E-09 E13bone 4.19E-07 E131 iver 7.78E-07 E13TB 3.58E-07 E13Thy 1.79E-05 E13Kidn 1. 19E-06 E13Lung O.OOE+00 E13G I 5.16E-07 E14bone 8.69E-07 E14l i ver 1.78E-06 VERIFIEDED E14TB 6.33E-07 E14Thy 4.15E-05 DATE RUN:11/18/92 E14Ki dn 1.99E-06 E14Lung O.OOE+00 E14GI 1.84E-06
'6TB 1.60E-08 7 E6Skin 1.90E-08 rM~/>-
~
ANST 1.00E+00 BY:/DATE: ANST 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 SOLID RADIOACTIVE WASTE NDAP-QA-0646 PROCESS CONTROL PROGRAM Revision 0
~c pe Page 1 of 61
~~rc s<"
EFFECTIVE DATE: PERIODIC REVIEW FREQUENCY: Z PERIODIC REVIEW DUE DATE: 8 -SS- 7 REVISED PERIODIC REVIEW DUE DATE: PROCEDURE TYPE: QA Program (~) YES ( ) NO Plant Procedure (7"j YES ( .) NO APPROVAL METHOD: (
' Alternate
(~) Committee ( PogC.) TYPE Prepared by Date 8/- Z Reviewed by 0 Sgervi s Recommended Pat G . I Date " 14 Functional Unit a ger Committee ZI Date Meeting No.r Approved by +i -' ~Wc'~. FORM NDAP-QA-0002- I. Rev. 0, Page of 1 1 lNBNlBllJIgl!EggggN tISINMSN
NOAP-IIA-0646 Revision 0 Page 2 of 61 PROCEOURE REVISION
SUMMARY
TITLE: SOL 10 RAOIOACTIYE WASTE'OCESS CONTROL PROGRAM
- 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. Incorporated PCAF 1-92-0432 to.add.new high integrity container type, incorporate volume reduction'services offered and update PCP implementing procedures.
- 7. Incorporated PILAF 1-92-0548 to dewatering record sheet to show documentation for 10 CFR 61 composite sample.
- 8. Incorporated PCAF 1-92-0866 to provide analyses guidelines for mixing of waste types/streams within one waste container.
- 9. Incorporated. PCP surveillance specimen requirements to Radioactive Waste Solidification Section, per BTP on Waste Form, Revision 1.
NDAP-QA-0646 Revision 0 Page 3 of 61 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 2.0 POLICY/DISCUSSION
3.0 REFERENCES
4.0 RESPONSIBILITIES 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 10
- 4. 5 RAD's!ASTE SUPERVISOR 10 4.6 CHEt1ISTRY SUPERVISOR 4.7 HP FOREt1AN - EFFLUENTS HANAGEHENT 12 4.8 ttuCLE'R QUALITY ASSURANCE 13 4.9 ~".CILIARY SYSTEMS OPERATOR 13 4.10 SOLIDIFICATION/DEWATERING/SERVICES VENDOR 13 4.11 MANAGER - NUCLEAR PROCUREMENT 14
- 4. 12 tlANAGER - NUCLEAR SYSTEHS ENGINEERING 14
- 4. 13 MAN"GER - NUCLEAR MAINTENANCE- 14 4.14 MANAGER - NUCLEAR REGULATORY AFFAIRS 15
- 4. 15 MANAGER - NUCLEAR TRAINING 15
- 4. I f MANAGER - NUCLEAR SECURI TY 15
- 5. 0 DEF-IN I T Iotas 15
HOAP-QA-0646 Revision 0 Page 4 of 61 TABLE OF CONTENTS CONTINUED SECTION PAGE 6.0 PROC'EDURE 19 6.1 CONTRACTED VENDOR SERVICES 19 6.2 WASTE TYPES 20 6.3 RADIOACTIVE WASTE ANALYSIS AND Cl.ASSIFICATION 25 6.4 T ST it'G "'F."ATt1ENT OF SOLIDIFIED RAOWASTE,FOR 28 COMBUST!BLE GASES 6.5 RADIOACTIVE WASTE SOLIDIFICATION 28 6.6 RADIOACTIVE WASTE DEWATERING 6.7 HIGH }t<TEGRITY CONTAINERS (HIC) 40 6.8 iPF:~DIATED HARDWARE PROCESSING AND DEWATERING 45
- 6. 9 CONTA INER l ASPECT IONS 45
- 6. 10 WASTE COt<TA INER SPACE: UTIL I'ZATION 46 5.'l l STORAGE OF PACKAGED RADIOACTIVE WASTE 46 6.12 TRANSPORTATION, SHIPPING AND:DISPOSAL REGULATIONS 47.
'6.13 SHI PP! ttG OF RADIOACTIVE'ASTE 48
- 6. 14 SH IPtlENT CONF I RUAT ION ,5Q 6.15 CHANGES TO THE SOLID RADIOACTIVE.WASTE PROCESS 50 CONTROL PROGRAM 6.16 EVALUATION OF PROCESS OR OPERATIONAL CHANGES 50 6.17 REPORTING OF HISHAPS INVOLVING LOW LEVEL 51 WASTE FORMS 6.18r IMPLEMENTING PROCEDURES 52 rPCP 7.0 RECORDS 52
NOAP-gA-0646 Revision 0 Page 5 of 61 ATTACHMENTS ATTACHMENT PAGE A Solidification Record Sheet 54 B Oewatering Record Sheet 55 C Susquehanna Guaranteed Solidified/Oewatered Waste 58 Volume Record PCP Implementing Procedure Matrix 59
1
'V Ig
+
NDAP-gA-0646 Revision 0 Page 6 of 61 1,0 PURPOSE 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 o'LRW is accomplished to provide reasonable assurance of 'ackagino 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 NUREG 0800, "Standard Review Plan 11.4 Solid Waste Management Systems" 3.9 Technical Position on Waste .Form Rev. 1, 1991 3.10 Technical Position on Radioactive Waste Classification, Rev. 0, 1983 3.11 '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" 3.12 Regulatory Guide 1. 143, "Design Guidance of Solid Waste Management Systems" 3.13 Regulatory Guide 7.1, "Administrative Guide for Packaaing and Transporting Radioactive Material" 3.14 ANS 40.35, "Volume Reduction of Low Level Radioactive Waste" 3.15 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 Mobile Incontainer Oewatering and Solidification System Pr'ocess Control 'Program (PCP), Report No. STO-PCP-03-003 3.18 Disposal Site Criteria for Barnwell, S.C. 3.1921'HNIDisposal Site Criteria for Richland, Washington 3.20 OHEC-HIC-PL-001 South Carolina Certificate of Compliance for CNSI High Integrity Containers
- 3. 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) 3.33 Generic Letter 91-02, "Reporting Mishaps Involving LLW Forms Prepared for Disposal" A (3) 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
~
Effluents Management Supervisor responsibilities: I'.1 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
t~DAP qr 0646 Revision 0 Paoe 9 of 61 4.1.3 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 - Operations Technology responsibilities: 4.2.1 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. 4.2.2 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 Effluent Release Report per the Semi-annual'adioactive as 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 Ensure procedures are adequate to provide for proper solidification and dewatering of waste. 4.3.2 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. 4.3.3 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.
NOAP-gA-0646 Revision 0 Page 10 of 61 Perform the duties of Radwaste Supervisor as specified in this procedure in his absence. 4.3.5 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 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. 4.4.4 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 Ensure appropriate waste solidification and dewatering records are. generated. 4.5 ' 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 Ensure Solidification and Oewatering operations are carried out in an ALARA manner. 4.5.6 Interface with HP Foreman - Effluents Hanagement for liner and cask selection for solid waste shipping activities. 4.5.7 Ensure proper marking of containers prior to filling. 4.5.8 Ensure solidification/dewatering personnel are adequately trained per NTP-QA-42.3. 4.5.9 Estimate classification of waste for container selection and processing method. 4.5.10 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. 4.5.11 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. 4.5.12 Complete and process High Integrity Container User Jy 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 Provide density of initial and final waste form. 4.6.5 Provide the isotopic mix and concentration of isotopes detected in the material sampled for solidification or dewatering. 4.6.6 Complete Chemistry portion of the Solidification and Oewatering Records. 4.6.7 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. 4.7.3 Storage of packaged radioactive waste outside the
~ ~ radwaste facility.
4.7.4 Oetermine waste classification and description of solidified, dewatered, and other packaged waste. ~ 1 4.7.5 Final disposition of solidified, dewatered and other packaged waste. 4.7.6 Ensures SSES is a registered user of applicable High Integrity Containers at specific disposal facilities.
. 4.7.7 Ensures HP personnel involved with radioactive waste handling have received Radwaste Worker training per NTP-gA-42.3.
4.7.8 Evaluate vendor services provided to ensure efficient and economical methods are used.
C, I'
NOAP-IIA-0646 Revision 0 Page 13 of 61 47~ Complete and process Certification Statement for Disposal of High Integrity Containers as required by applicable regulatory agencies.
- 4. 7.!0 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.." Inspection of Radwaste Containers as required by applicable procedures. 4 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 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. 4.10.3 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 NOAP-(jA-0646 Revision 0 Page 14 of 61 4.10,4 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. 4.10.6 Complete applicable sections of Solidification and Oewatering Records required for each container processed. 4.10.7 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 Obtain waste samples from processing equipment in accordance with approved operating procedures. ln in 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 MA f K 4 A f~ pI
NDAP-OA-0646 Revision 0 Page 15 of 61 4.13.2 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 Submitting to the NRC the Semi-annual Radioactive Effluent Release Report. 4.14.3 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, C' processing, packaging, storage, and r su+ A p )/ l ~ 0p ( ~ Maintaining a record of training, attendees, and
'.15.2 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)
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NDAP-I)A-0646 Revision 0 Page 16 of 61 5.5 CERTI.FICATE OF COMPLIANCE: License requirements established by the Nuclear Regulatory Commission for the use of approved Radioactive Material Shipping Containers. 5.6 CHEMICAL FORM: The chemical content of the Radioactive Material being shipped. 5.7 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]) 5.8 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 CURING TIME: The time allowed for the solidified product to set prioi to its evaluation for product acceptability. 5.11 DECAY HEAT: The heat produced by radioactive decay, usually expressed in Watts or 8TU/hr, but can be related to Curie Content. 5.12 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. 5.13 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]) 5.14 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.
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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 . ..Vl..: I'7$ 1Tv ~ Mate. ial in which the activity is hl 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)
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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
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5.34 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. =.35 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). 5.36 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. 5.37 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. 5.38 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).
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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 Solidification, dewatering and volume reduction services are provided by Scientific Ecology Group (SEG) for waste types included in the Process Control Program.
6.1.2 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.
NOAP-QA-0646 Revision 0 Page 20 of 61 6.1.3 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: ( 1) Condensate Oemineralizer regeneration effluent (2) Oecon Shop draihs (3) Chemistry Laboratory sink drains (4) Auxiliary Boiler blowdown effluent
- b. 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 (7) Negligible amounts of reagent chemicals used for chemistry analysis c~ 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 (6) Various solids and dirt in small concentrations C. 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.
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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 ~ 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.
- .~ fib 'onde'nrate'",demineralizer bead resin should be r
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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.
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NDAP-9A-0646 Revision 0 Page 23 of 61 Cartridge Filters
- 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) Radwaste Filters - including degasifier filters and other fiber or paper filters other than primary system. (4) 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.
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