ML021290310
| ML021290310 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/29/2002 |
| From: | Byram R Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-5458 | |
| Download: ML021290310 (158) | |
Text
Robert G. Byram Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC Two North Ninth Street Allentown, PA 18101-1179 Tel. 610.774.7502 Fax 610.774.6092 rgbyram@pplweb.com I
I
%.TM APR 29 2OD2 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP 1-17 Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE EFFLUENT RELEASE REPORT AND OFFSITE DOSE CALCULATION MANUAL PLA-5458 Docket No. 50-387 and 50-388 In accordance with 10CFR50.36a(a)(2) and the Susquehanna SES Unit 1 and 2 Technical Specifications Section 5.6.3, attached is the annual Radioactive Effluent Release Report for SSES Units 1 and 2 covering the period January 1 through December 31, 2001.
Additionally, pursuant to Technical Specification Section 5.5.1.C.3, attached is a copy of the Offsite Dose Calculation Manual as revised through December 31, 2001.
If you have any questions, please contact Mr. Robert D. Kichline at (610) 774-7705.
Sincerely, Attachment copy: NRC Region I Mr. S. L. Hansell, NRC Sr. Resident Inspector, SSES Mr. T. G. Colburn, NRC Sr. Project Manager
<1 Document Control Desk PLA-5458 APR 2 9 2002 bc:
R. L. Doty R. D. Kichline R. D. Pagodin B. E. Rhoads C. H. Saxton R. E. Smith W. F. Tabor T. G. Wales H. D. Woodeshick R. L. Anderson T. G. Bannon B. H. Carson T. L. Harpster D. J. Morgan B. L. Shriver L. K. Vnuk A. J. Wrape NRA Files Config. Mgt.
Attn: P. Brown GENA93 GENA61 GENA63 NUCSA1 NUCSB2 NUCSB2 NUCSA3 GENA63 SSO NUCSB3 GENA12 GENA93 GENA61 GENA63 NUCSB3 NUCSA1 GENA62 GENA61 GENA62 w/attach.
'I If I,
'I w/o attach.
it ti it American Nuclear Insurers Town Center 300S 29 South Main Street West Hartford, CT 06107-2445 Attn.: Mr. Stanley Focht INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 D. J. Allard Bureau of Radiation Protection PA. Dept. of Environmental Protection P.O. Box 2063 Harrisburg, PA 17120
SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL EFFLUENT WASTE DISPOSAL REPORT FOR JANUARY - DECEMBER 2001 PPL Susquehanna, LLC Two North Ninth Street Allentown, Pennsylvania 18101-1179 April 2002
SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT REPORT PERIOD: 01/01/01 - 12/31/01 Prepared by:
Bru~e H. Carson Health Physicist Reviewed by:
Michael B. D~tamore Supervisor - Environmental Services Approved by:
RichAf'd4_. Ib;oty Q*
Supervisor - Operations Technology PPL Susquehanna, LLC Two North Ninth Street, GENA93 Allentown, Pennsylvania 18101
TABLE OF CONTENTS SECTION PAGE
- 1. Introduction and Supplemental Information 1-1
- 2. Effluent and Waste Disposal Data 2-1
- 3. Meteorological Data and Dispersion Estimates 3-1
- 4. Dose Measurements and Assessments 4-1
- 5. Changes to the Offsite Dose Calculation Manual 5-1 and the Solid Radioactive Waste Process Control Program
- 7. Corrections to Doses Reported in Previous 7-1 Semiannual or Annual Effluent and Waste Disposal Reports
LIST OF TABLES Table 1-1 Technical Requirement Limits Table 2-1 Airborne Effluent-Summation of All Releases Table 2-2 Airborne Effluent Table 2-3 Waterborne Effluent - Summation of All Releases Table 2-4 Waterborne Effluent Table 2-5 Annual Effluent and Waste Disposal Report Estimated Total Errors Associated with Effluents Measurements Data Period: January 1, 2001 - December 31, 2001 Table 2-6 Annual Effluent and Waste Disposal Report Solid Waste and Irradiated Fuel Shipments Table 2-7 Dry Active Waste (DAW)
Class A Strong Tight Container (Compacted)
Table 2-8 Bead Resin/Charcoal - Class A HIC (Pyrolysis)
Table 2-9 Condensate Filtration System (CFS) Filters - Class A HIC (Dewatered)
Table 2-10 Liquid Oil - Class A (Fuel Blending for Co-Generation)
Table 2-11 Ultrasonic Resin Cleaning/
Condensate Filtration System (URC/CFS) - Class A HIC (Dewatered)
Table 2-12 Dry Active Waste (DAW) - Class A Strong Tight Container (Incineration)
Table 2-13 Condensate Demineralizer/Radwaste Demineralizer Class A HIC (Pyrolysis)
Table 2-14 LRW Filter Media - Class A HIC (Dewatered) 2-24 PAGE 1-10 2-4 2-5 2-8 2-9 2-12 2-16 2-17 2-18 2-19 2-20 2-21 2-22 2-23
LIST OF TABLES (cont.)
Table 2-15 Table 2-16 Table 2-17 Table 2-18 Table 2-19 Table 2-20 Table 3-1 Table 3-2 Table 3-3 Table 3-4 Table 3-5 Table 3-6 Table 3-7 Table 3-8 Condensate Demineralizer/Radwaste Demineralizer Class B HIC (Pyrolysis)
Cartridge Filters - Class B HIC (Dewatered)
Dry Active Waste (DAW) - Class B HIC (Non-Processed)
Bead Resin/Charcoal - Class B HIC (Pyrolysis)
RWCU Filter Media - Class B (Dewatered)
Condensate Demineralizer/Radwaste Demineralizer Class C HIC (Pyrolysis)
SSES Meteorological Data Recovery for 2001 SSES Joint Frequency Distribution of Wind Speed and Direction 1Oin versus Delta Temperature 60-1Oin for the Period of January 1, 2001 through December 31, 2001 SSES Joint Frequency Distribution of Wind Speed and Direction 60m versus Delta Temperature 60-1 Om for the Period of January 1, 2001 through December 31, 2001 2001 SSES Annual Relative Concentrations No Decay, Undepleted X/Q (sec/n 3) 2001 SSES Annual Relative Concentrations 2.26-Day Decay, Undepleted X/Q (sec/mi3) 2001 SSES Annual Relative Concentrations 8-Day Decay, Depleted X/Q (sec/m3) 2001 SSES Annual Relative Deposition - D/Q (meters2) 2001 Atmospheric Dispersion Estimates for GASPAR Input at Selected Locations PAGE 2-25 2-26 2-27 2-28 2-29 2-30 3-3 3-4 3-12 3-20 3-21 3-22 3-23 3-24
LIST OF TABLES (cont.)
Table 4-1 Site-Specific Parameters Used for Laptap II Calculations (Danville Receiver): for 2001 Table 4-2 Summary of Maximum Individual Offsite Doses and Dose Commitments to Members of the Public Table 4-3 Calculated Collective Doses to Members of the Public Within the Riverlands/Information Center Complex Table 4-4 Calculated Doses for Individuals and Locations within the SSES Site Boundary and Nearest Dairy Table 8-1 Annual Release from Systems Classified as Insignificant Effluent Pathways PAGE 4-2 4-4 4-5 4-6 8-3
LIST OF FIGURES Figure 1-1 Figure 1-2 Figure 2-1 Figure 2-2 Figure 3-1 Figure 3-2 Figure 3-3 Figure 4-1 SSES Airborne Effluent Points SSES Waterborne Effluent Pathway Susquehanna River Monthly Average Flow Rates SSES Monthly Liquid Radwaste Discharge Totals SSES 2001 Annual Wind Rose: 10-Meter Level Primary Tower SSES 2001 Annual Wind Rose: 60-Meter Level Primary Tower SSES Pasquill Stability Class Prevalences Locations for which Airborne Dose Calculations are Performed PAGE 1-5 1-6 2-10 2-11 3-26 3-27 3-28 4-7
SECTION 1 INTRODUCTION AND SUPPLEMENTAL INFORMATION 1-1
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 about 1,100 MW net electrical capacity. The reactor and generating units were supplied by General Electric, while the Bechtel Corporation served as architect-engineer and constructor.
Construction of the Station began in the early 1970s. Fuel load began in Unit 1 in July of 1982. Initial criticality was achieved in the Unit 1 reactor on September 10, 1982.
The reactor reached 100% power for the first time on February 4, 1983. Commercial operation of Unit 1 was declared on June 8, 1983. Initial criticality of Unit 2 occurred on May 8, 1984. Unit 2 was declared commercial on February 12, 1985.
Airborne effluents are released from the Susquehanna Station via five rooftop vents on the reactor building (see Figure 1-1). Each vent is continuously monitored, and a program of periodic sampling and analysis is conducted as specified in the plant Technical Requirements. All waterborne effluents are released in batch mode and are sampled and analyzed prior to release. Waterborne effluents from the site are released into the cooling tower blowdown line for dilution prior to release to the Susquehanna River (see Figure 1-2). Blowdown line flow rates are at least 5,000 gpm during periods of liquid radwaste release. The diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed. The diffuser serves to rapidly and uniformly mix the station discharge with the main flow of the river.
This report presents a summary of the quantities of radioactive materials which were released from the Susquehanna Steam Electric Station during the period from January 1, 2001 to December 31, 2001. In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to the SSES Offsite Dose Calculation Manual (ODCM) and Solid Radioactive Waste Process Control Program (PCP) and documentation of any exceptions to the SSES effluent monitoring program which must be reported per Technical Requirements.
Airborne and waterborne radioactive effluent releases to the environment during the report period were sampled and analyzed in accordance with the Technical Requirements. All radioactive effluent releases were within the concentration and release limits specified in the Technical Requirements. Calculations and terms utilized in this report are those outlined in the SSES ODCM.
Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant. Included are regulatory limits (Table 1-1), sampling and analysis methods, and characterization of the number and duration of batch and abnormal releases, if any.
1-2
Section 2 contains effluent and waste disposal data for the report period. Table 2-1 contains a summation of all airborne releases, grouped into the radionuclide categories of gases, particulates, iodines, and tritium. Average release rates are presented and compared to the applicable limits. Table 2-2 presents the activity totals of specific radionuclides in airborne effluents.
Waterborne effluents are summarized in Table 2-3. Average diluted concentrations are presented and compared to the applicable limits. Table 2-4 presents the release quantities of specific radionuclides in waterborne effluents over the report period.
Figures present the Susquehanna River Monthly Average Flow Rates for 2001 and the SSES Monthly Liquid Radwaste Discharge Totals for 2001.
Table 2-5 contains estimates of the errors associated with the measurements involved in quantifying effluents. Sampling errors, counting errors, and errors associated with determining effluent flow rates and volumes all contribute to the total error of effluent measurements. Error estimates are presented for each category of radionuclide detected in airborne and waterborne effluents and solid wastes during the report period.
Tables 2-7 through 2-20 present a characterization of the solid radioactive waste shipped offsite during the report period. Included are the volumes and curie contents associated with each type of solid waste. An estimate of major nuclide composition is presented for each waste type, as well as the number of waste shipments from the site, how they were transported, and their final destination.
Section 3 presents meteorological data for 2001 including data recovery, joint frequency distribution of wind speed and direction, stability class distribution, and atmospheric dispersion estimates for selected locations.
Section 4 of this report contains an assessment of the calculated doses attributed to the reported radiological effluents for the calendar year. The LADTAP II code was used for calculation of doses from waterborne effluents. Site-specific parameters used in the calculations for the Danville receiver are shown in Table 4-1. The 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 4-2 summarizes maximum calculated doses and dose commitments to members of the public from airborne and waterborne effluents and direct radiation. Table 4-3 presents calculated collective doses to members of the public within the Riverlands/Information Center Complex. Table 4-4 summarizes the calculated doses for residences and other occupied areas within the SSES site boundary and nearest dairy.
Section 5 of this report documents changes to the Offsite Dose Calculation Manual and the Solid Radioactive Waste Process Control Program.
1-3
Section 6 presents a listing of cases (if any) in which airborne or waterborne effluent monitoring instrumentation was declared inoperable and was not restored to operability within the time period specified in Technical Requirements 3.11.1.4, 3.11.1.5 and 3.11.2.6 Action Statements. In addition, this section presents issues (if any) with the collection of milk or fresh leafy vegetables per Technical Requirement 3.11.4.1 and change due to the land use census per Technical Requirement 3.11.4.2.
Section 7 contains corrections (if any) to doses reported in previous Semiannual or Annual Effluent and Waste Disposal Reports.
Section 8 contains information on effluent and offsite dose from the systems classified as insignificant effluent pathways 1-4
UNIT I NIT It REACTOR REACTOR I
BUILDING BUILDING EXHAUST EXHAUST SEVENT VENT TOURBINE TUR IIEAK DEEEXASPLNMBUILDING BUILDING I
C EXHAUST EXHAUSTm
--L GENERATOR BUILDING VENT VENTC U3 74"-
j.3'4 3' 2 V-6" m
m In
-n r
m S-o UNIT T I CO-
FIGURE 1-2 SSES WATERBORNE EFFLUENT PATHWAY
SUPPLEMENTAL INFORMATION
- 1.
Regulatory Limits Technical Requirements 3.11.1 and 3.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively. Concentration of radioactive materials released in liquid effluents and dose or dose commitment resultant thereof are limited in unrestricted areas. Dose and dose rate due to radioactive materials released in gaseous effluents are limited in areas at or beyond the site boundary. Technical Requirement limits are listed in Table 1-1.
- 2.
Maximum Permissible Concentrations in Waterborne Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas is limited to 10 times the concentrations specified in 10 CFR Part 20 Appendix B Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration is limited to 2.OE-04 pCi/ml total activity (TRO 3.11.1.1).
- 3.
Average Energy of Fission and Activation Gas The Calculation of Noble Gas Effluent Average Energies E-Bar Beta and Gamma for 2001 resulted in an Annual E-Bar Beta value of 3.17E-01 and an E-Bar Gamma activity of 2.45E-01.
- 4.
Measurements and Approximations of Total Radioactivity Analyses of specific radionuclides in effluent samples are used to evaluate the radioactive composition and concentration of effluents.
- 5.
Methods of Quantifying Effluents
- a.
Fission and Activation Gases: Gas samples are routinely collected monthly and analyzed with a high resolution (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 1-7
service, manual grab samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).
- b.
lodines: Iodine is continuously collected on charcoal cartridges 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 collected directly from the affected rooftop vent(s) or from alternate sampling ports available on the sample lines.
- d.
Tritium: Airborne tritium is collected monthly via bubbler sampler. The sample is collected for one hour at a flow rate of approximately 1000 cc/min.
Tritium activity in the bubbler sample is determined by liquid scintillation counting. The liquid sample tritium concentration is converted to air concentration by volume proportion, then compared to the Technical Requirement Table (TRO) 3.11.2.1.-I Lower Limit of Detection (1 E-6 pCi/cc).
- 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 (Ge[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 monthly liquid radwaste composite sample is also analyzed offsite for P-32. 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 1-8
nuclide released in each batch. The isotopic totals for each are summed to determine the total source term for the report period.
1-9
TABLE 1-1 TECHNICAL REQUIREMENT LIMITS A.
NOBLE GASES:
- 1.
- <500 mrem/year - TOTAL BODY
_<3000 mrem/year - SKIN dose rate limit at and beyond the site boundary (TRO 3.11.2.1)
- 2.
- <5 mrad - AIR GAMMA
- <10 mrad - AIR BETA quarterly air dose limits per reactor unit at and beyond the site boundary (TRO 3.11.2.2a)
- 3.
- 10 mrad - AIR GAMMA
___20 mrad - AIR BETA annual air dose limits per reactor unit at and beyond the site boundary (TRO 3.11.2.2.b)
B.
AIRBORNE 1-131, 1-133, TRITIUM, PARTICULATES WITH HALF-LIVES > 8 DAYS:
- 1.
- <1500 mrem/year - ORGAN (inhalation pathways only) dose rate limit at and beyond the site boundary (TRO 3.11.2.1.II.A)
- 2.
!!7.5 mrem-ORGAN quarterly dose limit per reactor unit at and beyond the site boundary (TRO 3.11.2.3.a)
- 3.
_!A5 mrem-ORGAN annual dose limit per reactor unit at and beyond the site boundary (TRO 3.11.2.3.b) 1-10
C.
LIQUID EFFLUENTS:
- 1.
- 1.5 mrem - TOTAL BODY
- 2.
- 3.0 mrem - TOTAL BODY
D.
AIRBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLE TECHNICAL REQUIREMENT LIMIT Fission and Activation Gases A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1.I.A) 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 8.51 E+05 pCi/min (1.42E+04 pCi/sec).
lodines A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1.I.A) limit of 1500 mrem/yr from 1-131, 1-133, tritium and particulates with half-lives greater than 8 days was calculated from the annual release quantity of 1-131 provided in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564). The limit is 1.04E+02 pCi/min (1.73E+00 pCi/sec).
Particulates A derived release rate limit based on the Technical Requirement (TRO 3.11.2.1.lI.A) limit of 1500 mrem/yr from 1-131, 1-133, tritium and particulates with half-lives greater than 8 days was calculated based on the expected mix of particulate radionuclides presented in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564). The limit is 7.72E+02 pCi/min (1.29E+01 pCi/sec).
1-11
Tritium A derived release rate was calculated based on the 10 CFR 20, Appendix B, Table 2, Column 1, Effluent Concentration Limit for tritium (1.OE-07 pCi/cc) to unrestricted areas. A relative concentration of 4.1 E-05 sec/m 3 was assumed.
The limit is 1.46E+05 pCi/min (2.44E+03 pCi/sec).
E.
WATERBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLE TECHNICAL REQUIREMENT LIMIT Fission and Activation Products Concentrations of fission and activation products in liquid effluent from radwaste effluent are determined for each batch prior to release. Each isotope concentration is compared to ten times the 10CFR20 Appendix B, Table 2, Column 2 Effluent Concentration Values. No Technical Requirement limit for the total concentration of fission and activation products in liquid effluents is applicable for this category.
Tritium Liquid effluent quarterly tritium concentrations are compared to ten times the 10 CFR 20 Appendix B, Table 2, Column 2, Effluent Concentration value of 1.OE-03 pCi/ml to unrestricted areas.
Dissolved and Entrained Gases Liquid effluent quarterly concentration totals for dissolved and entrained gases are compared to the limiting value for a noble gas of 2.OE-04 pCi/ml.
1-12
SECTION 2 EFFLUENT AND WASTE DISPOSAL DATA 2-1
Airborne Effluents Summaries of the radionuclide total curie activities and average release rates are included in Tables 2-1 and 2-2.
- 1. Number of Batch Releases:
0
- 2. Total Time Period for Batch Release:
NA
- 3. Maximum Time Period for a Batch Release:
NA
- 4. Average Time Period for a Batch Release:
NA
- 5. Minimum Time Period for a Batch Release:
NA Abnormal Releases
- 1. Number of Releases 0
- 2. Total Activity Released NA If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in the SSES Technical Requirement (TRO)
Table 3.11.2.1-1, Radioactive Gaseous Effluent Sampling and Analysis Program. In all cases, these LLDs were less than the levels required by Technical Requirements. The following are typical LLDs.
Radionuclide LLD (piCilcc)
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-i 35m 5.0E-08 Xe-1 38 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-1 34 2.4 E-14 2-2
Radionuclide Cs-1 37 Ce-141 Ce-144 1-131 Sr-89 Sr-90 H-3 Gross Alpha 2.1 E-14 1.5 E-14 7.0 E-14 4.4 E-14 2.0 E-15 3.0 E-16 2.6 E-08 5.0 E-16 2-3 LLD (pCi/cc)
TABLE 2-1 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2001)
AIRBORNE EFFLUENT - SUMMATION OF ALL RELEASES A. Fission and Activation Gas First Second Third Fourth Unit Quarter Quarter Quarter Quarter Total Release Ci 6.78E+00 0
0 0
Average Release Rate for Period pCi/sec 8.71 E-01 0
0 0
% of TRM Limit 6.14E-03 0
0 0
B. lodines Total 1-131 Ci 0
0 0
0 Total 1-133 Ci 0
0 0
0 Average Release Rate for Period tJCi/sec 0
0 0
0 Percent TRM Limit 0
0 0
0 C. Particulate Particulate with Half-Life >8 Days Ci 3.27E-04 9.79E-04 8.62E-05 6.04E-03 Average Release Rate for Period pCi/sec 4.20E-05 1.24E-04 1.08E-05 7.60E-04 Percent TRM Limit 3.26E-04 9.67E-04 8.42E-05 5.91 E-03 Gross Alpha Radioactivity Ci 0
0 0
0 D.
Tritium Total Release Ci 2.08E+01 3.59E+01 4.72E+01 2.53E+01 Average Release Rate for Period pCi/sec 2.67E+00 4.57E+00 5.94E+00 3.1 8E+00 Percent TRM Limit 1.10E-01 1.87E-01 2.43E-01 1.30E-01 2-4
TABLE 2-2 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2001)
AIRBORNE EFFLUENT Releases in Continuous Mode First Second Third Fourth Nuclides Released Unit Quarter Quarter Quarter Quarter A. Fission and Activation Gases Ar-41 Ci 0
0 0
0 Kr-85 Ci 0
0 0
0 Kr-85m Ci 0
0 0
0 Kr-87 Ci 0
0 0
0 Kr-88 Ci 0
0 0
0 Xe-133 Ci 0
0 0
0 Xe-133m Ci 1.27E-01 0
0 0
Xe-1 35 Ci 6.65E+00 0
0 0
Xe-135m Ci 0
0 0
0 Xe-138 Ci 0
0 0
0 Total for Period Ci 6.78E+00 0
0 0
B. lodines 1-131 Ci 0
0 0
0 1-133 Ci 0
0 0
0 1-135 Ci 0
0 0
0 Total for Period Ci 0
0 0
0 C. Particulate Cr-51 Ci 2.81 E-05 4.41 E-04 6.66E-05 5.94E-03 Mn-54 Ci 2.08E-04 3.32E-04 6.66E-06 4.96E-05 Fe-59 Ci 0
6.40E-05 0
0 Co-58 Ci 1.61 E-05 7.51 E-06 0
2.07E-05 Co-60 Ci 7.25E-05 1.21 E-04 1.29E-05 2.07E-05 Zn-65 Ci 0
0 0
0 Sr-89 Ci 0
0 0
0 Sr-90 Ci 0
0 0
0 Cs-134 Ci 0
0 0
0 Cs-137 Ci 0
0 0
0 Ce-141 Ci 1.76E-06 0
0 0
Ce-144 Ci 0
6.97E-06 0
0 AG-11OM Ci 0
6.42E-07 0
1.12E-05 NB-95 Ci 0
5.39E-06 0
0
- AS-76 Ci 1.47E-03 1.12E-03 1.72E-04 3.50E-03
- NA-24 Ci 9.06E-05 0
0 1.61 E-04
- TC-99M Ci 2.86E-04 0
0 7.63E-04 Ba-La-140 Ci 0
0 0
0 Total for Period Ci 3.27E-04 9.79E-04 8.62E-05 6.04E-03 Sr-89, Sr-90 and Gross Alpha values for the fourth quarter 2001 are estimated based on third quarter 2001 sample analyses and fourth quarter 2001 ventilation exhaust rates.
2-5
Waterborne Effluents Summaries of the radionuclide total curie activities, average diluted concentrations, and percent of applicable Technical Requirement limits are included in Tables 2-3 and 2-4.
Batch Releases*
- 1.
Number of Batch Releases
- 2.
Total Time Period for a Batch Release
- 3.
Maximum Time Period for a Batch Release
- 4.
Average Time Period for a Batch Release
- 5.
Minimum Time Period for a Batch Release
- 6.
Average Cooling Tower Blowdown Flow Rate During Periods of Release
- 7.
Susquehanna River Flow Rate Qtr. 1 22 2.70E+03 2.80E+02 1.23E+02 2.60E+01 6.85E+03 Qtr. 2 23 2.11 E+03 2.88E+02 9.17E+01 2.90E+01 8.47E+03 Qtr. 3 10 8.26E+02 2.82E+02 8.26E+01 2.80E+01 1.06E+04 Qtr. 4 10 6.42E+02 8.60E+01 6.42E+01 3.OOE+01 9.01 E+03 6.1 E+06 9.3E+06 1.2E+06 1.9E+06
- Units of time and flow are expressed in minutes and gallons per minute (gpm),
respectively.
- 1.
- 2.
3.
Abnormal Releases Number of Releases Volume Released Total Activity Released 0
N/A N/A 0
N/A N/A 0
N/A N/A If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in the SSES Technical Requirement 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 Requirements. The following are typical LLDs.
Radionuclide Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 1-131 Cs-134 LLD (Ci/ml) 4.5 E-08 5.0 E-08 2.4 E-08 5.4 E-08 4.9 E-08 1.7 E-07 2.0 E-08 2.2 E-08 2-6 Annual 65 6.28E+03 8.33E+03 4.6E+06 0
N/A N/A
Radionuclide Cs-1 37 Ce-1 41 Ce-1 44 Sr-89 Sr-90 Fe-55 H-3 Gross Alpha LLD (uClimi) 2.6 E-08 3.2 E-08 1.3 E-07 4.0 E-08 4.0 E-09 1.0 E-06 4.6 E-06 3.0 E-08 2-7
TABLE 2-3 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2001)
WATERBORNE EFLUENT - SUMMATION OF ALL RELEASES A. Fission and Activation Products Unit 1*
1 First Quarter Second Quarter Third Quarter Fourth Quarter
- 1. Total Release (not including Tritium, Ent.
Gases, Alpha)
Ci 1.31 E-02 9.14E-03 7.02E-04 1.32E-03
- 2. Average Diluted Concentration During Period JCi/ml 1.89E-07 1.42E-07 2.08E-08 5.95E-08 Tritium
- 1. Total Release Ci 1.28E+01 7.35E+00 3.16E+00 1.13E+00
- 2. Average Diluted Concentration During Period IJCi/ml 1.85E-04 1.14E-04 9.34E-05 5.10E-05
- 3. Percent of Applicable Limit (1.OE-2) 1.85E+00 1.14E+00 9.34E-01 5.10E-01 Dissolved and Entrained Gases
- 1. Total Release Ci 7.52E-07 0
0 0
- 2. Average Diluted Concentration ICi/ml 1.09E-11 0
0 0
During Period
- 3. Percent of Applicable Limit (2.OE-4) 5.45E-06 0
0 0
Gross Alpha Radioactivity
- 1. Total Release Ci 0
0 0
1 4.71E-06 E. Volume of Water Released (Prior to Dilution)
F. Volume of Dilution Water Used During Period of Release G. Volume of Dilution Water Used Over Entire Period Gallons I 2.16E+05 1.58E+05 6.11E+04 4.27E+04 Liters 8.16E+05 6.00E+05 2.31E+05 1.62E+05 Gallons I 1.81 E+07 1.69E+07 8.87E+06 I 5.82E+06 Liters 6.84E+07 6.39E+07 3.36E+07 2.20E+07 Gallons 7.37E+08 1.21 E+09 1.49E+09 1.16E+09 Liters 2.79E+09 4.58E+09 5.64E+09 4.39E+09 2-8
TABLE 2-4 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (2001)
WATERBORNE EFFLUENT Releases in Batch Mode Nuclides Unit First Second Third Fourth Released Quarter Quarter Quarter Quarter A. Fission and Activation Products F-18 Ci 9.50E-08 8.48E-08 1.76E-09 0
Na-24 Ci 2.48E-06 0
0 0
P-32 Ci 0
0 6.94E-06 4.85E-06 Cr-51 Ci 7.09E-03 5.36E-03 1.03E-05 0
Mn-54 Ci 1.86E-03 1.07E-03 1.72E-04 3.37E-04 Fe-55 Ci 2.64E-03 9.47E-04 1.81 E-04 1.26E-04 Fe-59 Ci 4.83E-06 2.55E-05 0
0 Co-58 Ci 1.63E-04 2.36E-04 2.32E-05 5.49E-06 Co-60 Ci 1.34E-03 1.42E-03 2.97E-04 8.47E-04 Zn-65 Ci 2.59E-05 7.80E-05 1.56E-05 0
As-76 Ci 0
0 0
0 Rb-86 Ci 0
0 0
0 Sr-89 Ci 0
0 0
0 Sr-90 Ci 0
0 0
0 Sr-92 Ci 0
0 0
0 Nb-95 Ci 0
0 0
0 Mo-99 Ci 0
0 0
0 Ag-110m Ci 0
0 0
0 Sb-1 24 Ci 0
0 9.07E-07 0
Total for Period Ci 1.31 E-02 9.14E-03 7.02E-04 1.32E-03 B Tritium Total for Period Ci 12.8 7.35 3.16 1.13 C. Dissolved and Entrained Gases Ar-41 Ci 0
0 0
0 Kr-85 Ci 0
0 0
0 Kr-86m Ci 0
0 0
0 Kr-87 Ci 0
0 0
0 Kr-88 Ci 0
0 0
0 Xe-131m Ci 0
0 0
0 Xe-133m Ci 0
0 0
0 Xe-133 Ci 0
0 0
0 Xe-135m Ci 0
0 0
0 Xe-1 35 Ci 7.52E-07 0
0 0
Total for Period Ci 7.52E-07 0
0 0
Activity values for composited samples (P-32, Strontium-89, Strontium-90, and Fe-55) reported for the fourth quarter were established based on third quarter sample analyses and fourth quarter discharge volumes.
2-9
Figure 2-1 Susquehanna River Monthly Average Flow Rates Data Period: 2001 25.0 20.0 S15.0 CL 0
,*10.0 5.0 0.0 JAN FEB MAR APR MAY JUN JUL AUG SEPT OCT NOV DEC 2001 2-10
Figure 2-2 SSES Monthly Liquid Radwaste Discharge Totals Data Period: 2001 200 180 160 140 120 100 E
80 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2001 2-11
TABLE 2-5 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT ESTIMATED TOTAL ERRORS ASSOCIATED WITH EFFLUENTS MEASUREMENTS DATA PERIOD: JANUARY 1, 2001 - DECEMBER 31, 2001 ESTIMATED MEASUREMENT TOTAL ERROR
- 1.
Airborne Effluents
- a.
Fission and Activation Gases 15.9%
- b.
1-131 13.3%
- c.
Particulates (incl. Gross Alpha) 15.8%
- d.
Tritium 13.6%
- 2.
Waterborne Effluents
- a.
Fission and Activation Products 5.0%
- b.
Tritium 3.3%
- c.
Dissolved and Entrained Gases 8.4%
- d.
Gross Alpha Activity 6.0%
- e.
Volume of Waste Released 5.0%
(Prior to Dilution)
- f.
Volume of Dilution Water Used During Period 15.0%
ESTIMATED MAXIMUM MEASUREMENT ERROR
- 3.
Solid Wastes
- a.
Dry Active Waste (DAW) -
+/-25%
Class A Strong Tight Container (Compacted)
- b.
Bead Resin/Charcoal - Class A HIC (Pyrolysis)
+/-25%
- c.
Condensate Filtration System (CFS) Filters -
+/-25%
Class A HIC (Dewatered)
- d.
Liquid Oil - Class A
+/-25%
(Fuel Blending for Co-Generation)
- e.
Ultrasonic Resin Cleaning/Condensate Filtration System
+/-25%
(URC/CFS) - Class A HIC (Dewatered)
- f.
Dry Active Waste (DAW) - Class A
+/-25%
Strong Tight Container (Incineration)
- g.
Condensate Demineralizer/Radwaste Demineralizer -
+/-25%
Class A HIC (Pyrolysis) 2-12
ESTIMATED MAXIMUM MEASUREMENT MEASUREMENT ERROR
- 3.
Solid Wastes (cont.)
- h.
LRW Filter Media - Class A HIC (Dewatered)
+/-25%
- i.
Condensate Demineralizer/Radwaste Demineralizer -
+/-25%
Class B HIC (Pyrolysis)
- j.
Cartridge Filters - Class B HIC
+/-25%
(Dewatered)
- k.
Dry Active Waste (DAW) - Class B HIC
+/-25%
(Non-Processed)
- 1.
Bead Resin/Charcoal - Class B HIC
+/-25%
(Pyrolysis)
- m.
RWCU Filter Media - Class B (Dewatered)
+/-25%
- n.
Condensate Demineralizer/Radwaste Demineralizer -
+/-25%
Class C HIC (Pyrolysis) 2-13
SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT SOLID RADIOACTIVE WASTE DATA PERIOD:
PREPARED BY:
APPROVED BY:
JANUARY 1. 2001 - DECEMBER 31, 2001 T. M. KALINOWSKI - HEALTH PHYSICIST CURT SAXTON - SUPERVISOR SERVICES & PROGRAMS 2-14
REPORT NOTES
- 1.
All activities reported in millicuries (mCi) unless otherwise noted.
- 2.
Reported activities, as indicated with the (<) sign, are comprised in whole or part of MDL values.
- 3.
Estimated maximum measurement error is +/-25%.
2-15
TABLE 2-6 WASTE DISPOSITIONS Data Period: January 1, 2001 - December 31, 2001 A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Number of Shipments Mode of Transportation Destination 5
Truck Barnwell LLRW Disposal Facility B. IRRADIATED FUEL SHIPMENTS Number of Shipments Mode of Transportation None Destination 2-16
TABLE 2-7
"/-Jy-lUl Am-241 Ba-133 C-1 4 Cd-1 09 Ce-1 39 Ce-141 Ce 144 Cm-242 Cm-244 Co-57 Co-58 Co-60 Cr-51 Cs-1 34 Cs-1 37 Fe-55 Fe-59 H-3 Hg-203 1-129 1-131 La-140 Mn-54 Nb-95 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Ru-106 Sb-124 Sb-125 Sn-113 Sr-85 Sr-89 Sr-90 Tc-99 Y-88 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME 14.74859049 1.211 E-02 2.043E-06 1.819E+00 7.221 E-06 1.940E-08 6.341 E-1 0 7.591 E+00 2.052E-02 1.017E-02 2.040E-07 2.646E+01 7.975E+02 3.392E+01 7.348E-04 7.697E+00 4.215E+02 1.795E+02 3.550E+00 1.666E-1 1 6.406E-03 1.400E-02 1.OOE-04 1.309E+03 3.434E-01 1.127E+00 1.308E+01 2.413E-02 1.638E-02 3.577E+00 5.534E-03 1.959E-01 9.628E-02 1.037E-08 2.647E-1 3 1.015E-01 2.901 E-02 4.758E-01 1.847E-08 3.600E+01 1.689E-01 2.859 847.160 ft3 U.0z%
0.00%
0.00%
0.06%
0.00%
0.00%
0.00%
0.27%
0.00%
0.00%
0.00%
0.93%
27.90%
1.19%
0.00%
0.27%
14.74%
6.28%
0.12%
0.00%
0.00%
0.00%
0.00%
45.80%
0.01%
0.04%
0.46%
0.00%
0.00%
0.13%
0.00%
0.01%
0.00%
0.00%
0.00%
0.00%
0.00%
0.02%
0.00%
1.26%
0.01%
100.00%
23.989 m3 2-17
TABLE 2-8 Ag-i I um Am-241 Ba-1 40 C-14 Ce-141 Ce-144 Cm-242 Cm-243 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-1 37 Fe-55 Fe-59 H-3 Hf-181 1-129 1-131 1-133 La-140 Mn-54 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-90 Sr-92 Tc-99 Xe-1 33 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME 0.000E+00 0.OOOE+00 0.000E+00 3.41 OE-04 o.000E+00 1.340E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.820E+00 0.OOOE+00 0.OOOE+00 1.630E-04 3.250E+00 0.000E+00 5.230E+01 0.000E+00 2.850E-05 0.000E+00 0.OOOE+00 0.OOOE+00 2.560E+00 2.OOOE-04 5.550E-02 0.000E+00 2.640E-07 7.490E-05 o.000E+00 1.080E-05 0.OOOE+00 2.020E-03 0.000E+00 0.000E+00 0.OOOE+00 0.061 31.210 ft3 0.UUu/o 0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
4.62%
0.00%
0.00%
0.00%
5.33%
0.00%
85.75%
0.00%
0.00%
0.00%
0.00%
0.00%
4.20%
0.00%
0.09%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
100.00%
0.884 m3 2-18
TABLE 2-9 Mg-I iuf 1 Am-241 C-14 CE-1 41 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-137 Fe-55 Fe-59 H-3 1-129 1-131 Mn-54 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME 42.08 4.738E-01 1.031 E+02 1.817E+01 2.672E+02 2.362E-01 2.833E-01 3.289E+02 1.297E+04 3.453E+02 0.OOOE+00 5.761 E+01 1.775E+05 8.600E+01 2.111E+01 2.454E+01 9.250E-02 2.506E+04 1.220E+02 2.847E-01 2.849E-01 1.183E+02 0.OOOE+00 2.290E+00 2.920E+00 1.109E-01 1.718E+03 218.764 1140.860 ft3 U.UZI/o 0.00%
0.05%
0.01%
0.12%
0.00%
0.00%
0.15%
5.93%
0.16%
0.00%
0.03%
81.13%
0.04%
0.01%
0.01%
0.00%
11.46%
0.06%
0.00%
0.00%
0.05%
0.00%
0.00%
0.00%
0.00%
0.79%
100.00%
32.306 m3 2-19
TABLE 2-10 Ag-110m Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 1-129 1-131 Mn-54 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-1 24 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME u
8.440E-06 2.320E-04 8.700E-03 9.560E-06 6.580E-06 0.OOOE+00 5.980E-01 0.000E+00 0.OOOE+00 8.740E-03 2.010E-01 0.000E+00 1.890E+00 1.030E-08 O.OOE+00 2.180E-01 8.920E-04 1.170E-02 2.120E-05 1.240E-05 2.570E-03 O.OOOE+00 0.OOOE+00 0.OOOE+00 3.930E-08 o.OOOE+00 0.003 0.000 ft3 0.00%
0.01%
0.30%
0.00%
0.00%
0.00%
20.34%
0.00%
0.00%
0.30%
6.84%
0.00%
64.29%
0.00%
0.00%
7.42%
0.03%
0.40%
0.00%
0.00%
0.09%
0.00%
0.00%
0.00%
0.00%
0.00%
100.00%
0.000 m3 2-20
TABLE 2-11 Ag-1 lUm Am-241 C-14 CE-141 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-1 37 Fe-55 Fe-59 H-3 1-129 1-131 Mn-54 Nb-95 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME U.UUUf'ruu 7.890E-03 7.360E+01 0.OOOE+00 1.647E+00 8.040E-03 6.950E-03 8.073E+02 1.476E+04 1.187E+03 0.OOOE+00 1.977E+01 1.332E+05 2.627E+03 2.690E+01 3.158E-04 0.000E+00 4.506E+04 7.190E+01 2.450E+00 2.172E+02 1.216E-02 5.040E-03 3.270E+00 1.330E+02 0.000E+00 4.990E-01 1.170E+01 2.600E+02 198.492 136.300 ft3 U.JUj /V 0.00%
0.04%
0.00%
0.00%
0.00%
0.00%
0.41%
7.44%
0.60%
0.00%
0.01%
67.12%
1.32%
0.01%
0.00%
0.00%
22.70%
0.04%
0.00%
0.11%
0.00%
0.00%
0.00%
0.07%
0.00%
0.00%
0.01%
0.13%
100.00%
3.860 m3 2-21
TABLE 2-12 Ag-1 1Om Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-1 37 Fe-55 Fe-59 H-3 1-129 1-131 Mn-54 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME O.O00UL+UU 0.OOOE+00 9.600E-03 7.200E-03 0.OOOE+00 0.OOOE+00 2.939E+00 2.497E+01 8.492E-01 0.OOOE+00 2.300E-03 5.870E-01 2.800E-03 9.260E-02 0.OOOE+00 0.OOOE+00 2.211E+00 1.080E-01 2.351E-01 0.OOOE+00 0.OOOE+00 1.980E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.510 E-02 4.174E+00 0.036 2.594 ft3 0.00%
0.00%
0.03%
0.02%
0.00%
0.00%
8.11%
68.85%
2.34%
0.00%
0.01%
1.62%
0.01%
0.26%
0.00%
0.00%
6.10%
0.30%
0.65%
0.00%
0.00%
0.05%
0.00%
0.00%
0.00%
0.15%
11.51%
100.00%
0.073 m3 2-22
TABLE 2-13 Mg-i 1will Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-137 Fe-55 Fe-59 H-3 Hf-1 81 1-129 1-131 1-133 La-140 Mn-54 Nb-95 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Sr-92 Tc-99 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME 0.OOOE+00 2.359E-02 3.170E+02 7.560E+00 1.301 E-02 2.021 E-02 2.548E+02 7.128E+03 2.547E+02 0.OOOE+00 7.503E+00 1.536E+04 2.263E+02 3.545E+02 1.041 E+00 1.400E+00 8.168E-01 6.47E-09 9.030E-1 0 8.357E+03 7.879E+00 1.221 E+00 1.421 E+02 2.682E-02 1.592E-02 4.779E+00 7.144E+00 0.OOE+00 2.21 E-01 0.OOE+00 3.14E+01 1.44E+02 1.29E+01 32.624 338.00 ft3 U.UUl/o 0.00%
0.97%
0.02%
0.00%
0.00%
0.78%
21.85%
0.78%
0.00%
0.02%
47.09%
0.69%
1.09%
0.00%
0.00%
0.00%
0.00%
0.00%
25.62%
0.02%
0.00%
0.44%
0.00%
0.00%
0.01%
0.02%
0.00%
0.00%
0.00%
0.10%
0.44%
0.04%
100.00%
9.571 m3 2-23
TABLE 2-14 Ag-I1 iUM Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-137 Fe-55 Fe-59 H-3 1-129 1-131 Mn-54 Nb-95 Ni-59 Ni-63 Ni-65 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Sr-92 Tc-99 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME
-. zOUv'rTU I 2.258E-02 5.180E-04 9.370E+00 1.675E-02 2.243E-02 1.298E+03 2.867E+04 2.422E+03 0.000E+00 2.470E+01 1.391 E+03 2.074E+03 6.200E+01 3.450E-04 0.000E+00 5.890E+04 5.030E+01 4.524E+01 2.599E+02 0.000E+00 3.383E-02 3.393E-02 5.590E+00 7.015E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.44E+01 7.950E+02 1.130E+01 96.175 397.200 ft3 V,f-Iu 0.00%
0.00%
0.01%
0.00%
0.00%
1.35%
29.81%
2.52%
0.00%
0.03%
1.45%
2.16%
0.06%
0.00%
0.00%
61.24%
0.05%
0.05%
0.27%
0.00%
0.00%
0.00%
0.01%
0.07%
0.00%
0.00%
0.00%
0.07%
0.83%
0.01%
100.00%
11.248 m3 2-24
TABLE 2-15 Ag-I I um Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-1 37 Fe-55 Fe-59 H-3 Hf-1 81 1-129 1-131 1-133 La-I 40 Mn-54 Nb-95 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Sr-92 Tc-99 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME v.UUUF_-.'Uu 7.747E-03 1.298E+02 3.248E+00 4.948E-03 6.525E-03 5.299E+03 5.758E+04 2.947E+02 0.OOOE+00 3.227E+00 3.061 E+04 4.091 E+00 1.650E+02 0.OOOE+00 6.242E-01 1.196E-01 1.431 E-14 0.OOOE+00 7.637E+03 3.280E-02 2.347E+01 3.732E+02 7.871 E-03 4.791 E-03 5.945E+01 2.620E-02 1.370E-01 1.103E-01 0.OOOE+00 2.725E+01 8.052E+03 0.000E+00 110.261 110.900 ft3 0.00%
0.12%
0.00%
0.00%
0.00%
4.81%
52.22%
0.27%
0.00%
0.00%
27.76%
0.00%
0.15%
0.00%
0.00%
0.00%
0.00%
0.00%
6.93%
0.00%
0.02%
0.34%
0.00%
0.00%
0.05%
0.00%
0.00%
0.00%
0.00%
0.02%
7.30%
0.00%
100.00%
3.140 m3 2-25
TABLE 2-16 Ag-11Um Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 37 Fe-55 Fe-59 H-3 1-129 Mn-54 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sr-90 Tc-99 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME 1.OLu-umvu 2.3320E-03 6.6244E-01 6.3870E-02 1.1211E-04 1.8440E-03 4.5200E-03 2.9511 E+03 0.OOOOE+00 1.3540E-02 3.6880E+02 3.4600E-04 3.5034E-01 3.1105E-03 2.2509E+02 1.5015E+00 5.5270E+01 3.0060E-03 3.0830E-03 7.6540E-01 6.6060E-02 4.7595E-01 2.9457E+01 0.OOOOE+00 3.635 60.690 ft3 U.Ult /0 0.00%
0.02%
0.00%
0.00%
0.00%
0.00%
81.18%
0.00%
0.00%
10.15%
0.00%
0.01%
0.00%
6.19%
0.04%
1.52%
0.00%
0.00%
0.02%
0.00%
0.01%
0.81%
0.00%
100.00%
1.719 m3 2-26
TABLE 2-17 Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-1 37 Fe-55 Fe-59 H-3 1-129 1-131 Mn-54 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99 Zn-65 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME I I.u 2.359E-03 2.861 E-03 2.532E-02 1.01 7E-04 1.776E-03 8.996E-03 2.141 E+03 3.083E-06 0.OOOE+00 6.492E-01 6.430E+02 9.089E-04 3.179E-02 2.894E-02 0.OOOE+00 4.01 OE+02 7.235E+00 5.820E+01 2.814E-03 2.897E-03 7.440E-01 0.OOOE+00 0.OOOE+00 5.480E-02 1.137E+00 1.198E+01 3.277 71.710 ft3 U.3b*/o 0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
65.33%
0.00%
0.00%
0.02%
19.62%
0.00%
0.00%
0.00%
0.00%
12.24%
0.22%
1.78%
0.00%
0.00%
0.02%
0.00%
0.00%
0.00%
0.03%
0.37%
100.00%
2.031 m3 2-27
TABLE 2-18 Ag-11Um Am-241 Ba-140 C-14 Ce-141 Ce-144 Cm-242 Cm-243 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 Hf-181 1-129 1-131 1-133 La-140 Mn-54 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sr-90 Sr-92 Tc-99 Xe-133 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME 4.480E-04 0.OOOE+00 3.920E-02 0.OOOE+00 8.890E-02 6.190E-04 0.OOOE+00 4.470E-04 0.OOOE+00 1.045E+01 0.OOOE+00 0.OOOE+00 2.494E-02 0.OOOE+00 0.OOOE+00 3.493E+01 0.OOOE+00 1.168E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.182E+01 0.OOOE+00 2.056E-01 4.920E-04 4.920E-04 1.168E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.605E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.069 17.810 ft3 U.UU /0 0.00%
0.00%
0.06%
0.00%
0.13%
0.00%
0.00%
0.00%
0.00%
15.06%
0.00%
0.00%
0.04%
0.00%
0.00%
50.34%
0.00%
16.83%
0.00%
0.00%
0.00%
17.03%
0.00%
0.30%
0.00%
0.00%
0.17%
0.00%
0.00%
0.00%
0.05%
0.00%
0.00%
0.00%
100.00%
0.504 m3 2-28
TABLE 2-19 j'
" I I i III Am-241 C-1 4 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-1 34 Cs-1 37 Fe-55 Fe-59 H-3 1-129 1-131 Mn-54 Nb-95 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-124 Sb-I 25 Sn-113 Sr-89 Sr-90 Tc-99 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME
. (t)U_+UZ O.OOOE+00 6.770E+01 4.710E+00 O.O00E+00 O.OOOE+00 6.71 0E+02 1.400E+05 8.970E+01 1.460E+01 8.360E-01 1.430E+06 1.830E+02 5.1 10E+02 1.000E-04 0.000E+00 1.81 0E+05 0.000E+00 1.050E+02 2.300E+03 0.000E+00 0.000E+00 5.530E+01 0.OOOE+00 0.000E+00 0.000E+00 8.750E+00 1.490E+00 6.020E-05 4.720E+03 0.OOOE+00 1760.009 132.400 ft3 U.U/7o 0.00%
0.00%
0.00%
0.00%
0.00%
0.04%
7.95%
0.01%
0.00%
0.00%
81.25%
0.01%
0.03%
0.00%
0.00%
10.28%
0.00%
0.01%
0.13%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.27%
0.00%
100.00%
3.749 m3 2-29
TABLE 2-20 Ag-i IUM Am-241 C-14 Ce 144 Cm-242 Cm-244 Co-58 Co-60 Cr-51 Cs-134 Cs-1 37 Fe-55 Fe-59 H-3 Hf-181 1-129 1-131 1-133 La-140 Mn-54 Nb-95 Ni-59 Ni-63 Pu-238 Pu-239 Pu-241 Sb-1 24 Sr-89 Sr-90 Sr-92 Tc-99 Zn-65 Zr-95 TOTAL ACTIVITY (Ci)
CONTAINER VOLUME U.VUUUF--..U 5.490E-04 2.347E+01 1.596E-01 0.OOOE+00 2.910 E-04 2.029E+03 4.424E+04 4.096E+01 0.OOOE+00 9.120E-01 1.561 E+04 1.879E+01 5.492E+01 0.OOOE+00 1.787E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.132E+03 1.500E-01 4.540E+01 3.122E+02 0.OOOE+00 0.OOOE+00 3.384E+01 1.87E-01 0.OOE+00 2.97E-02 0.OOE+00 1.14E+01 4.88E+03 0.OOE+00 71.435 39.970 ft3 0.00%
0.00%
0.03%
0.00%
0.00%
0.00%
2.84%
61.93%
0.06%
0.00%
0.00%
21.85%
0.03%
0.08%
0.00%
0.00%
0.00%
0.00%
0.00%
5.78%
0.00%
0.06%
0.44%
0.00%
0.00%
0.05%
0.00%
0.00%
0.00%
0.00%
0.02%
6.83%
0.00%
100.00%
1.132 m3 2-30
SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 3-1
METEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the Susquehanna SES (SSES) site since the early 1970s. At the present time, the meteorological system is based on a 300-foot high tower located approximately 1,000 feet to the southeast of the plant. Wind sensors are mounted at the 1Gm and 60m elevations on this tower.
Vertical temperature differential is measured with redundant sensor pairs between the 10m and 60m levels. Sigma theta (the standard deviation of horizontal wind direction) is calculated from wind direction at both levels. Dew point and ambient temperature sensors are present at the 1 Gm level. Precipitation is measured at ground level.
A back-up meteorological tower was erected in 1982. It is a 1Gm tower providing alternate measurements of wind speed, wind direction, and sigma theta. A 10m supplemental downriver meteorological tower is also available. This tower measures wind speed, wind direction, sigma theta, temperature and dew point.
SSES meteorological data are transmitted to the plant Control Room, Technical Support Center, and Emergency Operations Facility for emergency response availability. The data are also transmitted via telephone data line to EQE/PLG's offices in Bethesda, Maryland.
Dispersion modeling for effluents from normal operation of SSES is done using the EQE/PLG MIDAS system XDCALC program, a straight-line Gaussian plume model designed to estimate average relative concentration. The model was developed in accordance with Regulatory Guide 1.111. For periods when the wind speed is calm, the actual wind direction that occurred is used.
XDCALC and the XQINTR program that interpolates X/Q values to exact locations both use terrain correction factors to account for the temporal and spatial variations in the airflow in the region. A straight-line trajectory model assumes that a constant mean wind transports and diffuses effluents in the direction of airflow at the release point within the entire region of interest. The SSES terrain correction factors were taken from SSES FSAR Table 2.3-128.
3-2
TABLE 3-1 SSES METEOROLOGICAL DATA RECOVERY FOR 2001 PERCENT VALID PARAMETER DATA RECOVERY Wind Speed 1Dm - Primary 100.0 Wind Speed 60m - Primary 99.4 Wind Speed 1Om - Backup2)(
99.4 Wind Speed 10m - Downriver(3 )
98.6 Wind Direction 1Dm-Primary 100.0 Wind Direction 60m - Primary 99.3 Wind Direction 1Om - Backup 99.5 Wind Direction 10m - Downriver 98.5 Temperature 10m - Primary 99.9 Dew Point 10m - Primary 98.8 Delta Temperature 60m - Primary 99.3 Sigma Theta 1Dm - Primary 100.0 Sigma Theta 60m - Primary 99.3 Sigma Theta 1Dm-Backup 99.5 Sigma Theta 10m - Downriver 98.5 Precipitation - Primary 100.0 Composite Parameters Wind Speed and Direction 10m, 99.3 Delta Temperature 60-1 Dm Wind Speed and Direction 60m, 99.2 Delta Temperature 60-10m (1)SSES "Primary" meteorological tower (2)SSES "Backup" meteorological tower (3)SSES "Downriver" meteorological tower 3-3
TABLE 3-2 Calculation No.
Rev. 0 C-1030059-201 02/14/2002 Page 6 of 28 Prepared by:
Checked by:
Table 2. SSES Joint Frequency Distribution of Wind Speed and Direction 1Oim Versus Delta Temperature 60-1Om for the Period of January 1, 2001 through December 31, 2001 SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
A DT/DZ ELEVATION:
SPEED:IOM SP DIRECTION:IOM WD LAPSE:DT A WIND SPEED(MPH) 1-3 4-7 8-12 13-18 0
0 0
0 0
0 0
0 0
0 1
1 0
0 0
0 19-24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 TOTAL 6
14 17 11 10 13 23 23 44 51 132 41 4
4 0
3 TOTAL 42 247 105 2
0 0
396 PERIODS OF CALM(HOURS):
1 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 WIND DIRECTION N
NNE NE ENE E
WNW NW NNW 3
3 7
8 5
2 5
4 2
0 0
1 0
0 1 9 10 8
3 5
16 21 34 40 80 14 2
3 0
1 4 4 4
0 0
0 2
0 5
7 49 26 2
0 0
2 3-4
Calculation No.
Rev. 0 C-1030059-201 TABLE 3-2 02/14/2002 (continued)
Page 7of28 Prepared by:
fl Checked by: I Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
B DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
3 3
11 0
0 0
17 NNE 0
18 6
0 0
0 24 NE 5
16 1
0 0
0 22 ENE 10 6
0 0
0 0
16 E
10 4
0 0
0 0
14 ESE 4
5 0
0 0
0 9
SE 5
13 1
0 0
0 19 SSE 2
5 2
0 0
0 9
S 6
15 1
0 0
0 22 SSW 4
27 1
0 0
0 32 SW 6
42 33 0
0 0
81 WSW 1
12 29 6
0 0
48 W
0 6
4 1
0 0
11 WNW 0
0 2
0 0
0 2
NW 0
2 1
0 0
0 3
NNW 0
0 3
0 0
0 3
TOTAL 56 174 95 7
0 0
332 PERIODS OF CALM(HOURS):
1 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 3-5
Calculation No.
Rev. 0 C-1030059-201 TABLE 3-2 02/14/2002 (continued)
Page 8of28 Prepared by:V7 i.m Checked by:
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
C DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 10 21 0
0 0
32 NNE 2
15 12 0
0 0
29 NE 4
8 1
0 0
0 13 ENE 14 8
0 0
0 0
22 E
9 5
0 0
0 0
14 ESE 4
6 0
0 0
0 10 SE 6
8 0
0 0
0 14 SSE 7
8 0
0 0
0 15 S
7 25 2
0 0
0 34 SSW 11 24 0
0 0
0 35 SW 11 51 27 3
0 0
92 WSW 1
22 31 17 0
0 71 W
4 7
12 3
0 0
26 WNW 0
9 5
0 0
0 14 NW 0
11 5
0 0
0 16 NNW 2
7 8
0 0
0 17 TOTAL 83 224 124 23 0
0 454 PERIODS OF CALM(HOURS):
1 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 3-6
Calculation No.
Rev. 0 C-1030059-201 I
TABLE 3-2 02/14/2002 (continued)
Page f 28 Prepared by: *Ii(1Ji IChecked by:
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 01010101-01123124 STABILITY CLASS:
D DT/DZ ELEVATION:
SPEED:10M SP DIRECTION:10M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
29 146 116 1
0 0
292 NNE 80 119 28 0
0 0
228 NE 99 68 13 3
0 0
183 ENE 103 44 8
0 0
0 155 E
90 42 1
0 0
0 133 ESE 69 46 1
0 0
0 116 SE 80 75 14 0
0 0
169 SSE 76 62 7
1 0
0 146 S
85 99 6
4 0
0 194 SSW 69 84 13 0
0 0
166 SW 59 178 121 15 0
0 373 WSW 34 79 106 61 2
0 282 W
8 56 63 24 0
0 151 WNW 8
53 42 4
0 0
107 NW 17 86 145 20 0
0 268 NNW 6
113 148 21 0
0 288 TOTAL 912 1350 832 154 2
0 3251 PERIODS OF CALM(HOURS):
1 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 3-7
Calculation No.
Rev. 0 C-1030059-20 1 TABLE 3-2 02/14/2002 (continued)
Pa e 10f 28 Prepared by:
Checked by:
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
E DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
31 55 3
0 0
0 89 NNE 100 75 6
0 0
0 181 NE 190 35 3
0 0
0 228 ENE 285 17 0
0 0
0 302 E
223 12 0
0 0
0 235 ESE 151 11 1
0 0
0 163 SE 141 18 1
0 0
0 160 SSE 133 29 3
0 0
0 165 S
167 48 7
0 0
0 222 SSW 134 127 7
0 0
0 268 SW 61 130 18 0
0 0
209 WSW 15 23 4
3 1
0 46 W
9 12 5
0 0
0 26 WNW 8
7 2
0 0
0 17 NW 4
27 1
0 0
0 32 NNW 7
35 4
0 0
0 46 TOTAL 1659 661 65 3
1 0
2389 PERIODS OF CALM(HOURS):
1 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 3-8
TABLE 3-2 (continued)
Calculation No.
Rev. 0 C-1030059-201 02/14/2002 Pape 1!4f28 Prepared by:
Checked by:
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
F DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:10M WD LAPSE:DT A WIND SPEED (MPH) 8-12 13-18 19-24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>24 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 9
33 122 522 220 72 44 40 48 30 21 5
1 0
1 5
TOTAL 1113 59 1
0 0
0 1173 PERIODS OF CALM(HOURS):
I VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 WIND DIRECTION N
NNE NE ENE E
WNW NW NNW 1-3 7
21 115 502 219 72 44 37 48 24 16 2
1 0
1 4
4-7 2
12 6
20 1
0 0
3 0
6 5
3 0
0 0
1 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 3-9
C-1030059.201 TABLE 3-2 02/14/2002 (continued)
Pae 12 of 28 Prepared by:
Checked by:
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
G DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:1OM WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
3 0
0 0
0 0
3 NNE 5
1 0
0 0
0 6
NE 67 1
0 0
0 0
68 ENE 429 20 0
0 0
0 449 E
115 1
0 0
0 0
116 ESE 22 0
0 0
0 0
22 SE 12 0
0 0
0 0
12 SSE 6
0 0
0 0
0 6
S 9
0 0
0 0
0 9
SSW 4
0 0
0 0
0 4
SW 4
0 0
0 0
0 4
WSW 0
0 0
0 0
0 0
W 0
0 0
0 0
0 0
WNW 0
0 0
0 0
0 0
NW 1
0 0
0 0
0 1
NNW 1
0 0
0 0
0 1
TOTAL 678 23 0
0 0
0 701 PERIODS OF CALM(HOURS):
1 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 3-10 Calculation No.
Rev. 0 C-1030059-201
Calculation No.
Rev. 0 C-1030059-201 TABLE 3-2 02/14/2002 (continued)
Page 13 of 28 Prepared by:
///
Checked by:
Table 2 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
ALL DT/DZ ELEVATION:
SPEED:1OM SP DIRECTION:10M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
75 217 155 1
0 0
448 NNE 209 249 56 0
0 0
515 NE 483 144 23 3
0 0
653 ENE 1346 123 8
0 0
0 1477 E
673 68 1
0 0
0 742 ESE 330 73 2
0 0
0 405 SE 293 130 18 0
0 0
441 SSE 263 128 12 1
0 0
404 S
327 221 21 4
0 0
573 SSW 250 308 28 0
0 0
586 SW 159 486 248 19 0
0 912 WSW 53 153 196 88 3
0 493 W
22 83 86 28 0
0 219 WNW 17 72 51 4
0 0
144 NW 23 126 152 20 0
0 321 NNW 20 157 165 21 0
0 363 TOTAL 4543 2738 1222 189 3
0 8696 PERIODS OF CALM(HOURS):
1 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
64 3-11
TABLE 3-3 Calculation No.
Rev. 0 C-1030059-201 02/14/2002 Page 14of 28 Prepared by:
Checked by:
Table 3. SSES Joint Frequency Distribution of Wind Speed and Direction 60m Versus Delta Temperature 60-10m for the Period of January 1, 2001 through December 31, 2001 SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
A DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION N
NNE NE ENE E
WNW NW NNW TOTAL 1-3 4-7 8-12 13-18 19-24 0
0 0
6 3
4 0
0 4
0 0
0 0
0 0
0 1
1 2
>24 TOTAL 1
3 5
0 0
9 9
5 2
0 0
16 2
3 2
0 0
17 5
0 0
0 0
11 3
0 0
0 0
6 5
2 1
0 0
12 8
9 1
1 0
19 6
13 3
0 0
22 7
20 14 0
0 45
.8 23 7
2 0
50 1
81 28 1
0 131 5
26 14 0
0 45 1
5 3
0 0
9 0
1 0
0 0
1 0
0 0
0 0
0 0
3 0
0 0
3 17 101 194 80 4
0 396 PERIODS OF CALM(HOURS):
VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
2 71 3-12
TABLE 3-3 (continued)
Calculation No.
Rev. 0 C-i1030059-201 02/14/2002 Pael,5of 28 Prepared by:
iChecked by:
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
B DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION N
NNE NE ENE E
WNW NW NNW 1-3 4-7 8-12 13-18 19-24 6
5 0
0 0
0 1
2 4
3 18 23 2
0 0
2 0
0 0
0 0
0 0
0 0
0 0
4 0
0 0
0
>24 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 TOTAL 15 33 21 14 6
9 17 11 19 34 81 50 12 2
2 6
TOTAL 19 108 135 66 4
0 332 PERIODS OF CALM(HOURS):
2 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
71 3-13 0
2 4
5 2
2 2
0 0
2 0
0 0
0 0
0 3
8 14 8
1 5
5 2
6 20 29 3
1 1
1 1
6 18 3
1 3
2 9
7 9
9 34 20 9
1 1
3
Calculation No.
Rev. 0 TABLE 3-3 C-1030059-201 TABL 3-302/14/2002 (continued)
Pael6 f 28 Prepared by:
Checked by:
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 01010101-01123124 STABILITY CLASS:
C DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 5
21 6
0 0
33 NNE 4
11 11 8
0 0
34 NE 3
9 1
0 0
0 13 ENE 8
8 2
0 0
0 18 E
7 3
2 0
0 0
12 ESE 0
4 2
1 0
0 7
SE 0
5 6
1 0
0 12 SSE 3
6 4
1 0
0 14 S
4 11 9
3 0
0 27 SSW 5
28 13 6
0 0
52 SW 1
30 39 14 0
0 84 WSW 1
6 21 36 13 1
78 W
0 2
13 7
2 0
24 WNW 0
3 11 4
0 0
18 NW 0
1 14 0
0 0
15 NNW 0
1 9
3 0
0 13 TOTAL 37 133 178 90 15 1
454 PERIODS OF CALM(HOURS):
2 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
71 3-14
Calculation No.
Rev. 0 TABLE 3-IC-1030059-201 (continued) 02/14/2002 Page 17 of 28
,Prepared by: I1filp IChecked by: I Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
D DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
16 67 140 28 0
0 251 NNE 48 80 71 26 5
0 230 NE 78 77 37 9
1 0
202 ENE 41 50 12 5
0 0
108 E
31 28 28 1
0 0
89 ESE 25 25 27 5
0 0
82 SE 30 30 58 14 2
0 134 SSE 31 30 51 10 0
0 122 S
52 38 57 10 8
0 165 SSW 45 93 55 26 3
0 222 SW 39 128 99 52 3
0 321 WSW 7
57 120 171 61 12 428 W
3 30 87 48 22 0
190 WNW 3
38 82 40 3
0 166 NW 2
43 147 78 3
0 273 NNW 5
30 151 82 0
0 268 TOTAL 456 844 1222 605 11 12 3251 PERIODS OF CALM(HOURS):
2 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
71 3-15
TABLE 3-3 Calculation No.
Rev. 0 (continued)
C-030059-2012/14/2002 Pag#_ lpf 28 Prepared by:
I 429t1 Checked by:
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
E DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
29 82 38 1
0 0
150 NNE 80 174 42 8
0 0
304 NE 143 73 17 5
0 0
238 ENE 71 27 10 0
0 0
109 E
53 20 9
0 0
0 82 ESE 57 20 14 3
0 0
94 SE 68 29 13 4
1 0
115 SSE 71 52 37 5
1 0
166 S
64 65 36 8
5 0
178 SSW 39 90 104 27 6
0 266 SW 41 97 112 20 0
0 270 WSW 13 57 92 61 5
1 229 W
16 19 9
5 0
0 49 WNW 2
19 9
0 0
0 30 NW 7
28 30 2
0 0
67 NNW 10 11 18 1
0 0
40 TOTAL 764 863 590 150 18 1
2387 PERIODS OF CALM(HOURS):
2 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
71 3-16
TABLE 3-3 (continued)
Calculation No.
Rev. 0 C-1030059-201 02/14/2002 Page,19po 28 Prepared by:
lChecked by:
Table 3 (continued)
SITE:
SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
F DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
18 70 9
1 0
0 98 NNE 111 280 3
0 0
0 394 NE 11 54 2
0 0
0 167 ENE 59 11 0
0 0
0 70 E
53 11 1
1 0
0 66 ESE 31 5
1 0
0 0
37 SE 24 3
0 0
0 0
27 SSE 26 11 4
1 0
0 42 S
24 20 9
0 0
0 53 SSW 15 39 15 0
1 0
70 SW 6
45 28 3
0 0
82 WSW 2
5 17 8
0 0
32 W
4 3
0 0
0 0
7 WNW 1
4 0
0 0
0 5
NW 5
4 2
0 0
0 11 NNW 3
4 0
0 0
0 7
TOTAL 493 569 91 14 1
0 1168 PERIODS OF CALM(HOURS):
VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
3-17 WIND DIRECTION 2
71
TABLE 3-3 Calculation No.
Rev. 0 TABLE 33
-1030059-201 (continued) 520102/14/2002 Prepared by:
lChecked by:
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
G DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
7 69 0
0 0
0 76 NNE 59 171 3
0 0
0 233 NE 84 58 1
0 0
0 143 ENE 42 4
0 0
0 0
46 E
30 2
1 0
0 0
33 ESE 31 1
1 0
0 0
33 SE 19 2
0 0
0 0
21 SSE 9
7 0
0 0
0 16 S
17 16 0
0 0
0 33 SSW 4
13 5
0 0
0 22 SW 0
13 6
0 0
0 19 WSW 2
7 4
0 0
0 13 W
2 1
0 0
0 0
3 WNW 1
1 0
0 0
0 2
NW 0
5 0
0 0
0 5
NNW 0
3 0
0 0
0 3
TOTAL 307 373 21 0
0 0
701 PERIODS OF CALM(HOURS):
2 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
71 3-18
Calculation No.
I Rev. 0 TABLE 3-3 c-1030059-201 (continued) 02/14/2002 Page 21 of 28 Prepared by:
Checked by:
Table 3 (continued)
SITE: SSES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
01010101-01123124 STABILITY CLASS:
ALL DT/DZ ELEVATION:
SPEED:60M SP DIRECTION:60M WD LAPSE:DT A WIND SPEED(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
71 297 217 47 0
0 632 NNE 304 733 153 49 5
0 1244 NE 423 297 64 16 1
0 801 ENE 232 113 25 5
0 0
376 E
179 68 44 2
0 0
294 ESE 150 65 49 10 0
0 274 SE 143 82 95 21 4
0 345 SSE 140 114 116 22 1
0 393 S
165 163 140 39 13 0
520 SSW 110 301 224 69 12 0
716 SW 87 363 399 135 4
0 988 WSW 25 140 300 313 83 14 875 W
25 57 123 65 24 0
294 WNW 7
66 104 44 3
0 224 NW 14 82 194 80 3
0 373 NNW 18 50 184 88 0
0 340 TOTAL 2093 2991 2431 1005 153 14 8689 PERIODS OF CALM(HOURS):
2 VARIABLE DIRECTION 0
HOURS OF MISSING DATA:
71 3-19
TABLE 3-4 2001 SSES ANNUAL RELATIVE CONCENTRATIONS NO DECAY, UNDEPLETED X/Q (sec/m 3)
DATES OF LAST X/Q ACCUMULATION ARE FROM 1 1 1 1 0 TO 1123124 0 X/Q ACCUMULATION FOR GROUND AVERAGE FOR RELEASE POINT 1 0.5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50
- DIRECTION FROM N
4.1689E-06 7.8897E-07
- DIRECTION FROM NNE 6.8874E-06 1.4010E-06
- DIRECTION FROM NE 1.4953E-05 2.8305E-06
- DIRECTION FROM ENE 5.4059E-05 9.9092E-06
- DIRECTION FROM E
2.6447E-05 4.7832E-06
- DIRECTION FROM ESE 1.3836E-05 2.7164E-06
- DIRECTION FROM SE 1.3152E-05
- 2. 6148E-06
- DIRECTION FROM SSE 1.0165E-05
- 2. 0145E-06
- DIRECTION FROM S
- 8. 6064E-06
- 1. 8233E-06
- DIRECTION FROM SSW
- 8. 2432E-06
- 1. 6833E-06
- DIRECTION FROM SW 6.8726E-06 1.3824E-06
- DIRECTION FROM WSW 3.0628E-06 5.8210E-07
- DIRECTION FROM W
1.2899E-06 2.4363E-07
- DIRECTION FROM WNW 1.0586E-06
- 1. 9617E-07
- DIRECTION FROM NW 2.3721E-06 4.3830E-07
- DIRECTION FROM NNW 2.8294E-06 5.3749E-07 3.2723E-07 6.2680E-07 1.2895E-06 4.8060E-06 2.1113E-06 1.2335E-06
- 1. 1969E-06 8.9866E-07 8.9296E-07 7.7952E-07 6.6147E-07 2.7045E-07 1.0482E-07 7.8500E-08 1.7470E-07 2.2865E-07 1.7255E-07 3.3588E-07 7.3290E-07 2.8586E-06 1.2010E-06 6.9096E-07 6.7619E-07 5.0471E-07 5.2072E-07 4.4330E-07 3.8239E-07 1.5902E-07 5.7293E-08 4.0973E-08 8.9319E-08 1.1081E-07 2.1699E-07 4.8639E-07 1.9148E-06 8.0549E-07 4.5943E-07 4.4911E-07 3.3936E-07 3.5782E-07
- 2. 9516E-07 2.5781E-07 1.0859E-07 3.7473E-08
- 2. 6119E-08 5.6657E-08 1.2238E-07 7.7370E-08 4.0997E-08 8.0568E-08 1.9283E-07
- 7. 6120E-07 3.2925E-07 1.8599E-07 1.8352E-07 1.4620E-07 1.6657E-07 1.2360E-07 1.1427E-07 5.1035E-08 1.5263E-08 9.6281E-09 2.0399E-08 2.7102E-08 1.1202E-08 2.2105E-08 5.8612E-08 2.2249E-07 1.0488E-07 5.1785E-08
- 4. 6016E-08 3.8356E-08
- 4. 6411E-08 3.2523E-08 2.9979E-08 1.5899E-08 4.0993E-09 2.6080E-09 5.3609E-09 6.8237E-09 5.4129E-09 1.0869E-08
- 2. 9553E-08 1.0838E-07 5.3303E-08 2.2818E-08 1.7026E-08 1.3745E-08 1.6042E-08 1.2455E-08
- 1. 0173E-08 5.9653E-09
- 1. 6571E-09 1.2325E-09 2.5259E-09 3.2590E-09 3.3976E-09 6.9045E-09
- 1. 9038E-08 7.0327E-08
- 3. 4503E-08 1.4684E-08 1.0894E-08 8.7861E-09 1.0253E-08 7.9443E-09
- 6. 4626E-09 3.0587E-09 1.0308E-09 7.6295E-10 1.5571E-09 2.0291E-09 2.4007E-09 4.9347E-09 1.3853E-08 5.1721E-08 2.5214E-08 1.0638E-08 7.8492E-09 6.3133E-09 7.3684E-09 5.6973E-09 4.6129E-09 1.6740E-09 7.1950E-10 5.3032E-10 1.0792E-09 1.4200E-09 3-20 SEC/M3
TABLE 3-5 2001 SSES ANNUAL RELATIVE CONCENTRATIONS 2.26-DAY DECAY, UNDEPLETED X/Q (see/m3)
DATES OF LAST X/Q ACCUMULATION ARE FROM 1 1 1 1 0 X/Q ACCUMULATION FOR GROUND DECAYED S.AVG SEC/M3 FOR RELEASE POINT 0.5-1 1-2 1
2-3 3-4 4-5 TO 1123124 0 5-10
- DIRECTION FROM N
4.1613E-06 7.8462E-07
- DIRECTION FROM NNE 6.8707E-06 1.3908E-06
"**DIRECTION FROM NE 1.4906E-05 2.8040E-06
- DIRECTION FROM ENE 5.3889E-05 9.8153E-06
"**DIRECTION FROM E
2.6346E-05 4.7283E-06
- DIRECTION FROM ESE 1.3779E-05 2.6828E-06
"**DIRECTION FROM SE 1.3103E-05 2.5857E-06
- DIRECTION FROM SSE 1.0131E-05 1.9942E-06
- DIRECTION FROM S
8.5816E-06 1.8074E-06
- DIRECTION FROM SSW 8.2233E-06 1.6711E-06
- DIRECTION FROM SW 6.8598E-06 1.3746E-06
- DIRECTION FROM WSW 3.0581E-06 5.7940E-07
- DIRECTION FROM W
1.2880E-06 2.4254E-07
- DIRECTION FROM WNW 1.0570E-06 1.9522E-07
- DIRECTION FROM NW 2.3686E-06 4.3640E-07
- DIRECTION FROM NNW 2.8250E-06 5.3496E-07 3.2419E-07 6.1914E-07 1.2695E-06 4.7305E-06 2.0710E-06 1.2081E-06 1.1747E-06 8.8352E-07 8.7996E-07 7.7004E-07 6.5521E-07 2.6834E-07 1.0403E-07 7.7866E-08 1.7343E-07 1.7029E-07 3.3010E-07 7.1695E-07 2.7960E-06 1.1690E-06 6.7109E-07 6.5857E-07 4.9279E-07 5.1009E-07 4.3574E-07 3.7729E-07 1.5728E-07 5.6684E-08 4.0509E-08 8.8397E-08 1.0893E-07 2.1218E-07 4.7280E-07 1.8611E-06 7.7806E-07 4.4250E-07 4.3408E-07 3.2907E-07 3.4844E-07 2.8869E-07
- 2. 5336E-07
- 1. 0706E-07 3.6959E-08 2.5736E-08 5.5900E-08 2.2681E-07 1.2097E-07 7.6218E-08 3.9823E-08 7.7597E-08 1.8392E-07 7.2605E-07 3.1078E-07 1.7468E-07 1.7335E-07 1.3887E-07 1.5933E-07 1.1911E-07 1.1098E-07 4.9835E-08 1.4911E-08 9.3899E-09 1.9939E-08 2.6416E-08 1.0556E-08 2.0492E-08 5.3305E-08 2.0249E-07 9.3464E-08 4.5666E-08 4.1024E-08 3.4590E-08 4.2448E-08 3.0201E-08 2.8259E-08
- 1. 5154E-08 3.9096E-09 2.4781E-09 5.1158E-09 6.4709E-09 4.8990E-09 9.5796E-09 2.5234E-08 9.2678E-08 4.4003E-08 1.8506E-08 1.4059E-08 1.1571E-08 1.3825E-08
- 1. 1011E-08 9.2181E-09 5.5083E-09 1.5306E-09 1.1312E-09 2.3346E-09 2.9793E-09 2.9541E-09 5.7878E-09 1.5267E-08 5.6520E-08 2.6393E-08 1.0955E-08 8.3355E-09 6.9079E-09 8.3292E-09 6.6899E-09 5.6315E-09 2.7371E-09 9.2212E-10 6.7643E-10 1.3941E-09 1.7882E-09 2.0040E-09 3.9345E-09 1.0435E-08 3.9085E-08 1.7880E-08 7.3034E-09 5.5646E-09 4.6373E-09
- 5. 6432E-09 4.5712E-09
- 3. 8655E-09 1.4520E-09
- 6. 2325E-10 4.5402E-10 9.3533E-10 1.2055E-09 3-21 10-20 20-30 30-40 40-50
TABLE 3-6 2001 SSES ANNUAL RELATIVE CONCENTRATIONS 8-DAY DECAY, DEPLETED X/Q (sec/m 3)
DATES OF LAST X/Q ACCUMULATION ARE FROM 1 1 1 1 0 TO X/Q ACCUMULATION FOR DECAYED DEPLETION SEC/M3 FOR RELEASE POINT 0.5-1 1-2 1
2-3 3-4 4-5 1123124 0 5-10
- DIRECTION FROM N
3.8089E-06 6.6828E-07
- DIRECTION FROM NNE 6.2916E-06 1.1861E-06
"**DIRECTION FROM NE 1.3656E-05 2.3949E-06
- DIRECTION FROM ENE
- 4. 9372E-05 8.3840E-06
- DIRECTION FROM E
2.4149E-05 4.0447E-06
- DIRECTION FROM ESE 1.2633E-05 2.2964E-06
- DIRECTION FROM SE 1.2010E-05 2.2113E-06
- DIRECTION FROM SSE 9.2828E-06 1.7041E-06
- DIRECTION FROM S
7.8608E-06 1.5430E-06
- DIRECTION FROM SSW 7.5301E-06
- 1. 4251E-06
- DIRECTION FROM SW 6.2790E-06 1.1709E-06
- DIRECTION FROM WSW 2.7985E-06 4.9318E-07
- DIRECTION FROM W
1.1786E-06 2.0642E-07
- DIRECTION FROM WNW
- 9. 6730E-07 1.6619E-07
- DIRECTION FROM NW 2.1675E-06 3.7137E-07
- DIRECTION FROM NNW 2.5853E-06 4.5538E-07 2.6465E-07 5.0650E-07 1.0410E-06 3.8797E-06 1.7028E-06 9.9435E-07 9.6545E-07 7.2522E-07 7.2110E-07 6.2992E-07 5.3494E-07 2.1882E-07 8.4813E-08 6.3508E-08 1.4137E-07 1.8499E-07 1.3368E-07 2.5991E-07 5.6638E-07 2.2090E-06 9.2682E-07 5.3289E-07 5.2191E-07 3.8983E-07 4.0257E-07 3.4305E-07 2.9623E-07 1.2327E-07 4.4417E-08 3.1758E-08 6.9252E-08 9.4851E-08 8.3000E-08 1.6228E-07
- 3. 6316E-07 1.4296E-06 6.0035E-07 3.4215E-07 3.3479E-07 2.5321E-07 2.6730E-07 2.2076E-07 1.9309E-07 8.1405E-08 2.8094E-08 1.9576E-08 4.2481E-08 5.7985E-08 2.8511E-08 5.5896E-08 1.3342E-07 5.2667E-07 2.2713E-07
- 1. 2813E-07 1.2663E-07
- 1. 0104E-07
- 1. 1534E-07 8.5766E-08 7.9468E-08 3.5545E-08 1.0632E-08 6.7034E-09
- 1. 4211E-08 1.8866E-08 6.8995E-09
- 1. 3551E-08 3.5741E-08 1.3570E-07 6.3590E-08 3.1304E-08 2.7901E-08 2.3332E-08 2.8345E-08 1.9948E-08 1.8466E-08 9.8239E-09 2.5334E-09 1.6101E-09 3.3135E-09 4.2100E-09 2.9078E-09 5.7952E-09 1.5618E-08 5.7305E-08 2.7905E-08 1.1885E-08
- 8. 9124E-09 7.2341E-09 8.5000E-09 6.6467E-09 5.4669E-09 3.2230E-09
- 8. 9540E-10
- 6. 6473E-10 1.3649E-09 1.7554E-09 1.6348E-09 3.2878E-09 8.9546E-09 3.3103E-08
- 1. 6016E-08 6.7675E-09
- 5. 0559E-09 4.1086E-09 4.8402E-09 3.7883E-09 3.1117E-09 1.4839E-09 5.0004E-10 3.6914E-10 7.5540E-10 9.7971E-10 1.0473E-09 2.1249E-09 5.8720E-09 2.1948E-08 1.0509E-08 4.3929E-09 3.2698E-09
- 2. 6561E-09 3.1379E-09 2.4581E-09 2.0148E-09 7.3844E-10 3.1726E-10 2.3304E-10 4.7580E-10 6.2208E-10 3-22 10-20 20-30 30-40 40-50
TABLE 3-7 2001 SSES ANNUAL RELATIVE DEPOSITION - D/Q (meters"2)
DATES OF LAST X/Q ACCUMULATION ARE X/Q ACCUMULATION FOR DEPOSITION FOR RELEASE POINT 1
0.5-1 1-2 2-3 FROM 1 1 3-4
- DIRECTION 2.5767E-08
- DIRECTION 2.7814E-08
- DIRECTION 3.2977E-08
- DIRECTION 7.9425E-08
- DIRECTION 3.8686E-08
- DIRECTION 2.4335E-08
- DIRECTION 3.1654E-08
- DIRECTION 2.7486E-08
"*DIRECTION 2.7865E-08
- DIRECTION 3.4252E-08
- DIRECTION 4.7976E-08
- DIRECTION 2.9623E-08
- DIRECTION 1.1008E-08
- DIRECTION 8.0465E-09
- DIRECTION 1.9288E-08
- DIRECTION 2.1981E-08 FROM N
3.7966E-09 FROM NNE 4.3096E-09 FROM NE 4.9737E-09 FROM ENE 1.2333E-08 FROM E
5.6511E-09 FROM ESE 3.6786E-09 FROM SE 4.8099E-09 FROM SSE 4.1028E-09 FROM S
4.4675E-09 FROM SSW 5.2389E-09 FROM SW 7.6159E-09 FROM WSW 4.5662E-09 FROM W
- 1. 6524E-09 FROM WNW
- 1. 1610E-09 FROM NW 2.8235E-09 FROM NNW 3.2645E-09 1 1 0 TO 1/M2 1123124 0 4-5 5-10 10-20 20-30 30-40 40-50 1.5571E-09 1.8692E-09 2.1267E-09 5.4921E-09 2.3024E-09 1.5684E-09 2.1007E-09 1.7478E-09 2.0981E-09 2.3498E-09 3.5832E-09 2.1326E-09 7.1499E-10 4.6782E-10 1.1313E-09 1.3792E-09 7.3802E-10 8.8906E-10 1.0293E-09 2.6870E-09 1.0993E-09 7.5719E-10 1.0374E-09 8.6301E-10 1.0782E-09 1.1895E-09 1.8540E-09 1.1417E-09 3.5678E-10 2.2358E-10 5.2627E-10 6.6677E-10 4.3616E-10 5.2335E-10 6.1067E-10 1.5874E-09 6.5592E-10 4,5239E-10 6.2271E-10
- 5. 2597E-10
- 6. 7200E-10 7.1999E-10
- 1. 1456E-09 7.2590E-10 2.1745E-10 1.3282E-10
- 3. 1115E-10
- 3. 9057E-10
- 1. 3823E-10 1.6307E-10
- 1. 9672E-10 5.0236E-10 2.1631E-10 1.5001E-10 2.1041E-10 1.8830E-10 2.6009E-10 2.5121E-10 4.3066E-10 2.9937E-10 7.7849E-11 4.3030E-11 9.8781E-11 1.1906E-10
- 3. 3068E-11 3.8014E-11 4.8200E-11
- 1. 1448E-10 5.4769E-11 3.4082E-11 4.3789E-11 4.1308E-11 6.0704E-11 5.5806E-11 9.7292E-11 8.4249E-11 1.8996E-11
- 1. 0629E-11 2.3694E-11 2.6794E-11 1.2175E-11 1.3996E-11 1.7746E-11 4.0140E-11 2.0165E-11 1.1006E-11 1.1985E-11 1.0979E-11 1.5572E-11
- 1. 5925E-11 2.4785E-11 2.4342E-11 5.9517E-12 3.9134E-12 8.7237E-12 9.8651E-12 6.4983E-12 7.4701E-12 9.4718E-12 2.1424E-11 1.0763E-11 5.8746E-12 6.3967E-12 5.8601E-12 8.3114E-12 8.5000E-12
- 1. 3229E-11
- 1. 0657E-11 3.1766E-12 2.0887E-12 4.6561E-12
- 5. 2654E-12 4.0825E-12 4.6930E-12 5.9505E-12 1.3460E-11 6.7616E-12 3.6906E-12 4.0187E-12
- 3. 6815E-12 5.2215E-12 5.3400E-12 8.3108E-12 5.2277E-12 1.9957E-12 1.3122E-12 2.9252E-12 3.3079E-12 3-23
TABLE 3-8 2001 ATMOSPHERIC DISPERSION ESTIMATES FOR GASPAR INPUT AT SELECTED LOCATIONS AFFECTED LOCATION MILES X/Q X/Q DEC X/Q DEC+DEP DEPOSITION SECTOR 14/WNW Maximum (X/Q) Site Boundary 0.6 1.524E-5 1.515E-5 1.372E-5 2.360E-8 9/S Closest (X/Q) Site Boundary 0.38 4.780E-6 4.776E-6 4.451E-6 3.518E-8 14/WNW Maximum (X/Q) Residence 0.8 1.046E-5 1.038E-5 9.243E-6 1.528E-8 16/NNW Maximum (D/Q) Residence 0.6 7.435E-6 7.400E-6 6.704E-6 1.820E-8 12/WSW Maximum (D/Q) Garden 1.1 9.491E-6 9.419E-6 8.206E-6 1.450E-8 12/WSW Maximum (D/Q) Dairy 1.7 5.032E-6 4.977E-6 4.209E-6 7.146E-9 2/NNE Maximum (D/Q) Meat Producer 2.3 1.008E-6 9.954E-7 8.204E-7 2.723E-9 NE Riverlands / EIC 0.7 4.465E-6 4.449E-6 3.985E-6 2.233E-8 WSW Tower's Club 0.5 2.506E-5 2.498E-5 2.289E-5 4.395E-8 NEAREST RESIDENCE WITHIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES XQ X/Q DECQ NUMBER SECTOR DEC+DEP DEPOSITION 1
N H. Burd 1.3 2.041E-6 2.024E-6 1.745E-6 4.744E-9 2
NNE E. Ashbridge III 1.0 3.351E-6 3.33 1E-6 2.918E-6 1.037E-8 3
NE W. Tuggle 0.9 3.111E-6 3.097E-6 2.729E-6 1.466E-8 4
ENE D. Barberi 2.1 5.534E-7 5.493E-7 4.548E-7 3.669E-9 5
E L. Kozlowski 1.4 3.720E-7 3.704E-7 3.167E-7 2.747E-9 6
ESE R. Panetta 0.5 1.315E-6 1.313E-6 1.201E-6 1.055E-8 7
SE J. Futoma 0.5 1.561E-6 1.559E-6 1.427E-6 1.228E-8 8
SSE J. Naunczek 0.6 2.082E-6 2.078E-6 1.878E-6 1.587E-8 9
S S. Slusser 1.0 1.201E-6 1.197E-6 1.046E-6 7.104E-9 10 SSW S. Molnar 0.9 2.467E-6 2.456E-6 2.164E-6 1.003E-8 11 SW F. Michael 1.5 2.009E-6 1.992E-6 1.700E-6 4.509E-9 12 WSW W. Kisner 1.1 9.491E-6 9.419E-6 8.206E-6 1.450E-8 13 W
E. Seely/F. Hummel 1.2 9.286E-6 9.202E-6 7.978E-6 1.169E-8 14 WNW R. Orlando 0.8 1.046E-5 1.038E-5 9.243E-6 1.528E-8 15 NW L. Hidlay 0.8 7.907E-6 7.850E-6 6.987E-6 1.462E-8 16 NNW W. Metzler 0.6 7.435E-6 7.400E-6 6.704E-6 1.820E-8 NEAREST GARDEN WITHIN A 5-MILE RADIUS OF SSES BY SECTOR SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSITION NUMBER SECTOR
_DEC+DEP 1
N J. Wojcik 3.2 5.467E-7 5.357E-7 4.274E-7 1.067E-9 2
NNE R. Chapin 2.3.
1.008E-6 9.954E-7 8.204E-7 2.723E-9 3
NE Yokum 2.7 6.399E-7 6.324E-7 5.122E-7 2.538E-9 4
ENE S. Glova 3.6 2.458E-7 2.427E-7 1.897E-7 1.456E-9 5
E L.Kozlowski/W.Witts 1.4 3.720E-7 3.704E-7 3.167E-7 2.747E-9 6
ESE L. Travelpiece 2.5 8.934E-8 8.864E-8 7.228E-8 5.671E-10 7
SE F. Scholl 0.6 1.195E-6 1.193E-6 1.079E-6 9.033E-9 8
SSE H. Roinick 2.6 1.998E-7 1.982E-7 1.609E-7 1.232E-9 9
S M. Cope 1.1 1.032E-6 1.028E-6 8.933E-7 5.975E-9 10 SSW S. Bodnar 1.2 1.591E-6 1.582E.6 1.368E-6 6.039E-9 11 SW H. Schultz 1.9 1.402E-6 1.387E-6 1.162E-6 3.076E-9 12 WSW W. Kisner 1.1 9.491E-6 9.419E-6 8.206E-6 1.450E-8 13 W
E. Seely/F. Hummel 1.2 9.286E-6 9.202E-6 7.978E-6 1.169E-8 14 WNW P. Moskaluk, Jr.
1.3 4.797E-6 4.744E-6 4.096E-6 6.301E-9 15 NW D. Goff 1.8 2.239E-6 2.206E-6 1.861E-6 3.487E-9 16 NNW P. Culver 4.0 4.370E-7 4.246E-7 3.313E-7 6.742E-10 3-24
TABLE 3-8 (continued)
Calculation No.
Rev. 2 C-1030059-201 02/28/2002 Pa 24 of 28 Prepared by:
I ///l'i Checked by:
NEAREST ANIMAL RAISED FOR MEAT CONSUMPTION WITHIN A 5-MILE RADIUS OF SSES BY SECTOR ALL DAIRY LOCATIONS NEAR SSES SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSITION NUMBER SECTOR DEC+DEP 5
E W. Bloss 4.5 5.114E-8 5.043E-8 3.834E-8 3.180E-10 6
ESE D. Moyer 2.7 7.696E-8 7.630E-8 6.165E-8 4.786E-10 F. Rinehimer 4.2 3.086E-8 3.045E-8 2.335E-8 1.702E-10 10 SSW R. & C. Ryman 3.0 3.572E-7 3.523E-7 2.820E-7 1.178E-9 R. Ryman 3.1 3.320E-7 3.273E-7 2.610E-7 1.083E-9 C. K. Drasher 3.5 2.503E-7 2.464E-7 1.938E-7 7.833E-10 K. Davis 14.0 1.983E-8 1.855E-8 1.232E-8 4.180E-11 13 W
J. & N. Dent 5.0 8.605E-7 8.300E-7 6.318E-7 6.750E-10 16 NNW H. Shoemaker 4.2 4.094E-7 3.972E-7 3.082E-7 6.194E-10 X/Q RELATIVE CONCENTRATION (SEC/M3)
X/Q DEC DECAYED AND UNDEPLETED, HALF-LIFE 2.26 DAYS (SEC/M3)
X/Q DEC+DEP DECAYED AND DEPLETED, HALF-LIFE 8 DAYS (SEC/M3)
DEPOSITION RELATIVE DEPOSITION RATE (1^M 2) 3-25
SSES 2001 ANNUAL WIND ROSE 1 OM LEVEL - PRIMARY TOWER
!0 WIND ROSE iJINDS FROM)
N t kUIND SPEED LESS THAN3.5 MPH
÷WIND SPEED LESS THAN7.5 MPH
,CWIND SPEED LESS THAN12.5 MPH
- WIND SPEED GREATER THAN 12.5 MPH 0.0 PERCENT CALMS (NOT INCLUDED IN PLOT)
This wind rose displays the frequency of hourly average wind direction from a given sector. In 2001, the predominant wind direction occurred 17.0% of the time from the ENE sector. The average wind speed was 4.4 mph. The peak sector wind speed was 8.7 mph from the WSW.
C) 0)
01
$a
SSES 2001 ANNUAL WIND ROSE 60M LEVEL - PRIMARY TOWER 6
1 WIND ROSE (WINDS FROM)
N t
SPEED LESS THN3S.5 MPH SPEED LESS THAN',5 MPH SPEED LESS THRN12.5 MPH SPEED GREATER THAN 12.5 MPH 0.0 PERCENT CALMS (NOT INCLUDED IN PLOT)
This wind rose displays the frequency of hourly average wind direction from a given sector. In
.2001, the predominant wind direction occurred 14.3% of the time from the NNE sector. The average wind speed was 7.3 mph. The peak sector wind speed was 12.3 mph from the WSW.
N4 It AWIND
+WIND xWIND
- WIND
Figure 3-3 SSES Pasquil Stability Class Prevalences Data Period: 2001 SSES Joint Frequency Distributions at 10 Meters Wind Speed and Direction IOM vs. Delta Temperature 60-IOM (Based on 8720 Valid Hours)
G 8.0%
A 4.6%
1 B
3.8%
C 5.2%
1 3D 37.4%
3-28
SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 4-1
Radiollooical Impact on Man Sampling and analysis of airborne and waterborne effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (LLD) outlined in the SSES Technical Requirements.
Radioactive material was detected in some of the airborne and waterborne effluent samples analyzed. Dose calculations using measured effluent activity levels, meteorological data from the current reporting period and average river flow dilution factors resulted in estimated doses to individuals at levels below 10 CFR 20 and 10 CFR 50, Appendix I limits. Direct radiation resulting from plant operation, as measured by environmental thermoluminescent dosimeters located around the plant contributed a maximum of 2.71 E-2 mrem (measured at TLD Location 9S2) at the Protected Area Boundary south of the plant. The maximum organ/total body dose including thyroid from all airborne effluent is 1.90E-1 mrem (child, skin, Table 4-4). The maximum organ/total body dose from liquid effluent is 3.16E-3 mrem (adult GI-LLI: two times the unit dose shown Table 4-2).
Conservatively adding the maximum total body/organ dose from liquid and gaseous effluent (even though different age groups) and the maximum total body dose determined from direct radiation bounds the dose that any member of the public receives from operation of SSES. The result (2.20E-1 mrem) is 0.9% of the 40CFR1 90 limit of 25 mrem to total body/organ (except thyroid) and 0.3% of the 40CFR190 limit of 75 mrem to the thyroid.
Doses to a maximally exposed member of the public from waterborne effluents are calculated for fish ingestion and shoreline exposure at the plant outfall, and drinking water ingestion at Danville, PA. Site specific parameters used in the calculations for the Danville receiver, specific for actual average blowdown and river level for the entire year are shown in Table 4-1.
TABLE 4-1 SITE-SPECIFIC PARAMETERS USED FOR LADTAP II CALCULATIONS (DANVILLE RECEIVER)
FOR 2001 PARAMETER ENTIRE YEAR Cooling Tower Blowdown (CFS) 18.6 Average Net River Level (ft.)
5.5 Dilution Factor at Danville(1) 297.2 Transit time to Danville (hr.)(1) 31.4 (1)From ODCM-QA-005, Att. D 4-2
Summaries of maximum individual doses resulting from airborne and waterborne radioactive effluent releases are given in Table 4-2. Meteorological data from Section 3 were used to calculate the dose from airborne effluents.
Technical Specifications 5.5.4 require 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 doses within the site boundary and selected locations resulting from airborne effluents are presented in Tables 4-3 through 4-4.
SSES Technical Specification 5.5.4 requires that the Annual 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 several areas frequented by members of the public. The SSES Riverlands Energy Information Center is a representative nearby location visited by members of the public. Doses from airborne effluent are calculated for members of the public for this location. The Riverlands, selected residences within the Site Boundary, and the maximum site boundary location for which dose calculations are performed are shown in Figure 4-1.
In the area comprising the Riverlands recreation area, which surrounds the Energy Information Center, three pathways of radiation exposure can be identified: plume, ground, and inhalation. There are no significant exposure pathways from waterborne effluents in this area. There are approximately 100,000 visitors to the Riverlands/Information Center complex each year. For dose calculations, it is assumed the visitor stays in the area for one hour.
Use of the 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 which are averages for the entire year. Taking into account the estimated 100,000 person-hours of occupancy, the collective (person-rem) doses shown in Table 4-3 are calculated.
4-3
TABLE 4-2
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES TO MEMBERS OF THE PUBLIC DATA PERIOD: 1/11/01 TO 12/31/01 ESTIMATED MAXIMUM AGE APPLICABLE DOSE PERCENT LIMIT EFFLUENT GROUP ORGAN (MIEM)
LOCATION OF LIMIT (MREM)(2 )
DIST AFFECTED (MILES)
SECTOR
(')Estimated dose is based on a site total activity release equally divided between Unit I and Unit 2.
(2)10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year for airborne effluent and mrem per year for waterborne effluent from each unit.
(3)Doses from liquid effluent are estimated from fish ingestion and shoreline exposure at the site outfall and from the drinking water pathway at Danville, PA.
(4)Estimated dose is based on the site total activity release.
4-4 Liquid")
Teen Total Body 1.30E-3 (3) 0.04 3
Liquid"l)
Adult GI-LLI 3.16E-3 (3) 0.03 10 Noble Gas N/A Air Dose 9.98E-3 N/A N/A 0.1 10 (Gamnima-MRAD)
Noble Gas N/A Air Dose 1.29E-2 N/A N/A 0.1 20 (Beta-MRAD)
Airborne Child Lung 1.84E-1 1.10 WSW 1.2 15
TABLE 4-3 CALCU LATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/INFORMATION CENTER COMPLEX DATA PERIOD: 111/01 TO 12/31/01 COLLECTIVE APPLICABLE DOSE RATE(')
DOSE("~
EFFLUENT AGE GROUP ORGAN (MREM/HR)
(PERSON-REM)
Noble Gas N/A Total Body 1.66E-05 1.66E-03 Noble Gas N/A Skin 1.79E-05 1.79E-03 Iodine, Tritium and Teen Skin 1.58-05 1.58E-03 Particulates I
(')Estimated dose rate is based on annual site total activity release (Table 4-4).
(2)Collective dose is based on occupancy of 100,000 person-hours.
4-5
TABLE 4-4
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES FROM AIRBORNE EFFLUENT MAXIMUM MAXIMUM MAXIMUM TOTAL BODY ORGAN THYROID DOSE DOSE DOSE LOCATION PATHWAY (MREM)
(MREM)
(MREM)
Maximum site boundary X/Q Plume 3.94E-03 1.05E-02 3.94E-03 Ground 4.34E-03 5.11 E-03 4.34E-04 Inhalation 7.93E-02 8.08E-02 7.93E-02 Total 8.76E-02 (TEEN) 9.64E-02 (TEEN, LUNG) 8.37E-02 (TEEN)
- 2.
Closest site boundary Plume 1.27E-03 3.38E-03 1.27E-03 Ground 6.47E-03 7.60E-03 6.47E-03 Inhalation 2.49E-02 2.54E-02 2.49E-02 Total 3.26E-02 (TEEN) 3.64E-02 (TEEN, LUNG) 3.26E-02 (TEEN)
- 3.
Maximum X/Q Residence Plume 2.68E-03 7.11E-03 2.68E-03 Ground 2.81E-03 3.31 E-03 2.81E-03 Inhalation 5.44E-02 5.44E-02 5.44E-02 Total 5.99E-02 (TEEN) 6.48E-02 (TEEN, SKIN) 5.99E-02 (TEEN)
- 4.
Maximum D/Q Residence Plume 1.94E-03 5.14E-03 1.94E-03 Ground 3.35E-03 3.94E-03 3.35E-03 Inhalation 3.87E-02 3.87E-02 3.87E-02 Total 4.40E-02 (TEEN) 4.78E-02 (TEEN, SKIN) 4.40E-02 (TEEN)
- 5.
Maximum D/Q Garden Plume 2.54E-03 6.75E-03 2.54E-03 Ground 2.66E-03 3.13E-03 2.66E-03 Vegetation 1.36E-01 1.36E-01 1.36E-01 Inhalation 4.37E-02 4.37E-02 4.37E-02 Total 1.85E-01 (CHILD) 1.90E-01 (CHILD, SKIN) 1.85E-01 (CHILD)
- 6.
Maximum D/Q Dairy Plume 1.26E-03 3.35E-03 1.26E-03 Ground 1.32E-03 1.55E-03 1.32E-03 Vegetation 7.23E-02 7.22E-02 7.22E-02 Meat 6.11E-03 6.11E-03 6.11E-03 Cow Milk 4.48E-02 4.48E-02 4.48E-02 Inhalation 2.62E-02 2.62E-02 2.62E-02 Total 1.52E-01 (CHILD) 1.54E-01 (CHILD, SKIN) 1.52E-01 (CHILD)
- 7.
Maximum D/Q Meat Plume 2.50E-04 6.66E-04 2.50E-04 Ground 5.02E-04 5.90E-04 5.02E-04 Vegetation 1.45E-02 1.45E-02 1.45E-02 Meat 8.84E-04 8.82E-04 8.82E-04 Inhalation 4.64E-03 4.64E-03 4.64E-03 Total 2.08E-02 (CHILD) 2.13E-02 (CHILD, SKIN) 2.08E-02 (CHILD)
- 8.
Tower's Club Plume 1.17E-03 3.11E-03 1.17E-03 Ground 4.11E-03 4.83E-03 4.11E-03 Inhalation 2.32E-02 2.32E-02 2.32E-02 Total 2.85E-02 (TEEN) 3.11E-02 (CHILD, SKIN) 2.85E-02 (TEEN)
- 9.
Rivedand/EIC Plume 6.58E-03 1.75E-02 6.58E-03 Ground 8.08E-03 9.50E-03 8.08E-03 Inhalation 1.30E-01 1.30E-01 1.30E-01 I
Total 1.45E-01 (TEEN) 1.57E-01 (CHILD, SKIN) 1.45E-01 (TEEN)
Note: The doses shown above are based on 100% occupancy at the indicated locations.
4-6
FIGURE 4-1 NW SE SW SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN BOUNDARY DISTANCES (DISTANCES IN FEET)
PENNSYLVANIA POWER & LIGHT LEGEND PP&L Properf SyondaWy Sector Wheal 122.1546We)
Roads PuRilroads Locations for rsirmoe done Cale Scale in Feet O
.500 1000 2000 4-7 X
SECTION 5 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL AND THE SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM 5-1
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The only revision to the ODCM that occurred during 2001 was Revision 3 to ODCM-QA-008, titled, "Radiological Environmental Monitoring Program." This revision became effective on May 22, 2001. This revision incorporated the following changes:
- 1.
Milk sampling location 7C1 was replaced with location 10D3 on the map of Attachment B of ODCM-QA-008.
- 2.
The description of milk sampling location 7C1 was replaced with that for location 10D3 in Attachment C.
- 3.
Air sampling locations 5S4, 7S7, 9B1, and 10S3 were deleted from Attachments A, B, and C, as applicable.
- 4.
Section 4.1.1 was revised to assign responsibilities formerly assigned to the Supervisor - Operations Technology to the Supervisor - Environmental Services Nuclear.
- 5.
Additional changes of a minor editorial nature were made to Attachments A and C.
Changes #1 and #2 regarding milk sampling locations were made based on the result of an Annual REMP Milk Sampling Location Evaluation performed in April 2000 as required by ST-099-004 and TRO 3.11.4.2 Action B.1. This evaluation determined that location 1 0D3 could be expected to have a sufficiently higher relative deposition rate than location 7C1, based on 1999 meteorological data, to require that location 10D3 be monitored.
Change #3 regarding air sampling locations did not involve monitoring locations that were required in accordance with TRO 3.11.4.1 and TR Table 3.11.4.1-1. This change was based on an evaluation performed in December 2000 to satisfy the requirements of Section 6.9.5 of NEPM-QA-1014, titled, "Radiological Environmental Monitoring Program." This evaluation made the following conclusions:
- 1.
The highest projected annual doses to a Member of the Public at any of the deleted sampling locations were less than or equal to 10% of the total projected dose for the airborne pathway based on environmental monitoring.
- 2.
The highest total reporting level fraction (RLF) from all radionuclides identified in air and attributable to SSES operation was less than or-equal to 0.10 at each of these locations based on environmental monitoring.
5-2
It should be noted that for the period of at least three years considered in this evaluation, no radionuclide activity was identified in air samples obtained from any of these locations that was attributable to the operation of Susquehanna SES.
Safety Evaluation NR-01-001 was performed to support this ODCM revision. None of the changes listed above reduce the level of effluent control or the accuracy and/or reliability of dose calculations or setpoint determinations as required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I.
Besides the change to ODCM-QA-008, a PCAF (2001-1947) was issued against ODCM-QA-009, Revision 0. Other than clarifications of definitions, this change added the isolated bus duct cooling system as "not an effluent pathway." The PCAF is included in Appendix A.
5-3
CHANGES TO THE SOLID WASTE PROCESS CONTROL PROGRAM The only revision to the "Solid Waste Process Control Program," NDAP-QA-0646 that occurred during 2001 was Revision 6. This revision became effective on June 6, 2001.
This revision incorporated the following changes:
- 1.
Added reference to appropriate FSAR section.
- 2.
Adjusted responsibilities to reflect changes in the distribution of work within the Effluents Management group.
- 3.
Corrected document references in response to changes in the Effluents Management training program.
- 4.
Changed names in Responsibilities section to reflect current titles.
- 5.
Added definition for gross dewatering and description of how/when this process may be used.
- 6.
Changeout waste type descriptions to reflect current processing method.
- 7.
Deleted requirements for guaranteed volume calculations and tracking including Form NDAP-QA-0646-3. Information is no longer required by contracts.
- 8.
Deleted LLRWHF procedures from PCP implementing matrix.
- 9.
Various administrative changes to reflect current company name, etc.
- 10. Clarified references to DOT package specifications to eliminate confusion.
- 11.
Removed restrictions on combining waste of different Waste Class to improve packaging efficiency and flexibility.
NDAP-QA-0646 continues to fully implement the requirements and intent of the following:
- 1.
Sections 11.4 and 13.5 of the FSAR
- 2.
Section 3.7.4 of the Technical Requirements Manual
- 3.
10 CFR 20, 10 CFR 61, 10 CFR71,49 CFR 100-177, and 40 CFR 261.
Compliance with all applicable regulatory requirements listed above continues to be met as the result of these changes to the program. These changes to the Process Control Program will not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.
5-4
PROCESS CONTROL PROGRAM CHANGES The following changes were made to the Process Control Program and implementing procedures during 2001. None of the changes reduce the overall conformance of the solidified waste product to existing criteria for solid wastes. All changes were reviewed and approved by PORC as documented on the attached Procedure Change Process Forms. The following procedures were changed:
- 1.
NDAP-QA-0646, Process Control Program
- 2.
WM-RP-105, Cartridge Filter Processing and Packaging
- 3.
WM-RP-1 07, Transfer and Drying Powdered Resin
- 4.
WM-PS-1 55, 10 CFR 61 Sample Shipping and Correlation Factor Determination
- 5.
WM-PS-210, Packaging and Loading of DAW and Radioactive Material
- 6.
CH-TP-055, Solid Radwaste 10 CFR 61 Correlation Factor Determination - Sample Collection and Preparation. (Note: The change to this procedure was strictly a periodic review and change to the review due date and administrative titles. There were no changes to technical information. The change was not reviewed by PORC.)
5-5
PROCEDURE CHANGE PROCESS FORM FORM NDAP-QA-0002-8. Rev. 7, Page 1 of 2 (Electronic F 5-6
- 1. PCAF NO.
- 12. PAGE I OF L
- 13. PROC. NO.
NDAP-QA-0646 REV. 6
- 4. FORMS REVISED 1 RX. -
2 Rg.
__ R__, -
R-R
- 5. PROCEDURE TITLE Solid Radioactive Waste Process Control Program
- 6. REQUESTED CHANGE 4
PERIODIC REVIEW LI NO Z
YES INCORPORATE PCAFS [
NO F1 YES REVISION Z
PCAF E]
DELETION E]
(CHECK ONE ONLY)
- 7.
SUMMARY
OF I REASON FOR CHANGE The following changes will not reduce the overall conformance of the solidified waste product to existing criteriafor solid wastes:
- 1. Added reference to appropriate FSAR sections.
- 2. Adjusted responsibilities to reflect changes in the distribution of work within the.Effluents Management Group.
- 3.
Corrected document references in response to changes in the Effluents Management Training Program.
- 4. Changed names in responsibilities section to reflect current titles.
- 5. Added definition for gross-dewatering and description of howlwhen this process may be used.
CONT'D ON PAGE 3 Continued [
- 8. DETERMINE COMMITTEE REVIEW REQUIREMENTS (Refer to Section 6.1.4)
PORC REVIEW REQ'D?
El NO 0
YES
- 9.
PORC MTG#
0 /-06'S- ? /
ERC REVIEW REQ'D?
[
NO Li YES
- 10. ERC MTGI N/A BLOCKS 11 THRU 14 ARE ON PAGE 2 OFFORM
- 15.
Thomas Kalinowski
/
254-1940
/
5/23/01
- 16.
COMMUNICATION OF CHANGE REQUIRED?
PREPARER ETN DAyTE NO [I YES (TYPE)
(Print or Type)
I I
PROCEDURE CHANGk.*PROCESS FORM
- 1. PCAF NO.
N/A
- 2. PAGE 2 OF,__3
- 13. PROC. NO. NDAP-QA0 64 REV. 6
- 11.
A 50.59 and 72.48 Evaluation per NDAP-QA-0726 is required to be attached or referenced for all procedure changes except Expedited Reviews and Administrative Corrections. Either 1 la, b, or c mus be checked 'YES" and the appropriate form attached or referenced.
- a. 50.59 and 72.48 Screening Determination (Form NDAP-OA-0726-5)
YES
[] N/A
- b. 50.59 or 72.48 Safety Evaluation (Note: 50.59 Safety Evaluations prepared on Ej YES M N/A Form NDAP-QA-0726-1 Rev. 5 or earlier also require a 50.59 & 72.48 Screening Determination)
Safety Evaluation No.
- c. Expedited Review/Administrative Correction-50.59 and 72.48 Evaluation not
[] YES N/A Required
- 12. Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722?
YES
[
NO
- 13. Is a Special, Infrequent or Complex Test/Evolution Analysis Form required per
[] YES Z
NO NDAP-QA-0320? (SICT/E form does not need to be attached.)
- 14. Reviews may be documented below or by attaching Document Review Forms NDAP-QA-0101-1.
REVIEWED BY WiTH REVIEW NO COMMENTS DATE OADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS
- IST *
- OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (58)
Required for changes to Section XI Inservice Test Acceptance Criteria.
FORM NDAP-QA-0002-8, Rev. 7, Page 2 of 2 (Electronic Form) 5-7
PROCEDURE REVISION
SUMMARY
NDAP-QA-0646, REV 6 Page 3 of.k'3 Continued.
- 6. Change out waste type descriptions to reflect current processing methods.
- 7. Deleted requirements for guaranteed volume calculations and tracking including Form NDAP-QA-0646-3. Information is no longer required by contracts.
- 8. Deleted LLRWUF procedures from PCP implementing matrix.
- 9. Various administrative changes to reflect current Company name, etc.
- 10. Clarified references to DOT package specifications to eliminate confusion.
- 11. Removed restrictions on combining waste of different Waste Classes to improve packaging efficiency and flexibility.
5-8
PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO.
N/A
- 12.
PAGE 1 OF 4_,3.
PROC.NO. WM-RP-105 REV. 4 FORM NDAP-QA-0002-8, Rev. 7, Page 1 of 2 (Electronic Form) v'P1 A
5-9
- 4. FORMS REVISED 1 R_/ 5 -l'R' R_.
R R
R_
- 5. PROCEDURE TITLE CARTRIDGEFILTERPROCESSING AND PACKAGING
- 6. REQUESTED CHANGE PERIODIC REVIEW
[
NO Li YES INCORPORATE PCAFS Li NO
[
YES # 2000-5442 REVISION PCAF Li DELETION []
(CHECK ONE ONLY)
- 7.
SUMMARY
OF I REASON FOR CHANGE Incorporated PCAF #2000-5442.
Incorporated various minor adm'nistrative changes.
Referenced applicable Effluents Management Procedures and Technical Bases.
Added use of Shop Dri as an absorbent and added new CFS filters.
Added note to allow packaging for shipment to a vendor processor. Liquid absorbant for shipment to vendors Is no longer required.
Added combustible gas test lAW NDAP-QA-0646.
Revised FORM WM-RP-105,-t Continued Li
- 8. DETERMINE COMMITTEE REVIEW REQUIREMENTS (Refer to Section 6.1.4)
PORC REVIEW REQ7D?
E] NO
[
YES
- 9.
PORCMTG# t O*--R1 ERC REVIEW REQ'D?
NO Li YES
- 10. ERC MTG#
N/A BLOCKS 11 THRU 14 ARE ON PAGE 2 OFFORM
- 15.
Michael C. Micca
/
1790
/
5/2/01
- 16. COMMUNICATION OF CHANGE REQUIRED?
PREPARER ETN DATE Li NO N YES (TYPE) Non-Routine (Print or Type)
- 17.
SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS CONDUCTED OADR AND TECHNI*A. REVIEW UNLESS OTHERWISE DOCUMENTED IN BLOCK 14 OR ATTACHED REVIEW FORMS.
RESPONSIB LE SUPERVISOR T
CROSS DISCIPLINE REVIEW OF REQUIRED) HAS BEEN COMPLETED BY SIGNATURE IN BLOCK 14 OR ATTACHED REVIEW FORMS.
- 18.
91L.
FUM APPRO'AL
/,JATE
- 19. RESPONSIAPPROVER ENTER N/A IF FUM HAS APPROVAL R
I9 EPNITIALS DAVEVE
PROCEDURE CHANý JE.O CFSS FORM
- 11.
A 50.59 and 72.48 Evaluation per NDAP-QA-0726 is required to be attached or referenced for all procedure changes except Expedited Reviews and Administrative Corrections. Either 11 a, b, or c mU. be checked "YES' and the appropriate form attached or referenced.
a 50.59 and 72.48 Screening Determination (Form NDAP-QA-0726-5)
YES N/A
- b. 50.59 or 72.48 Safety Evaluation (Note: 50.59 Safety Evaluations prepared on
[] YES Z
NIA Form NDAP-QA-0726-1 Rev. 5 or earlier also require a 50.59 & 72.48 Screening Determination)
Safety Evaluation No.
- c. Expedited Review/Administrative Correction-50.59 and 72.48 Evaluation not YES N/A Required
- 12. Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722?
F] YES
[D NO
- 13. Is a Special, Infrequent or Complex Test/Evolution Analysis Form required per YES NO NDAP-QA-0320? (SICT/E form does not need to be attached.)
- 14. Reviews may be documented below or by attaching Document Review Forms NDAP-OA-0101-1.
REVIEWED BY WITH REVIEW NO COMMENTS DATE QADR TECHNICAL REVIEW TOR ENGINEERING/NUCLEAR FUELS
.TIONS EAR SYSTEMS ENGINEERING EAR MODIFICATIONS ENANCE 1-I PHYSICS EAR TECHNOLOGY ISTRY R.
Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (58)
Required for changes to Section XI Inservice Test Acceptance Criteria.
FORM NDAP-QA-0002-8, Rev. 7, Page 2 of 2 (Electronic Form) 5-10 REACT IST *4 OPERA NUCLE NUCLE MAINT HEALTI NUCLE CHEMI OTHEE
- 1. PCAF NO.
N/A
- 12. PAGE2OF _$f2
- 13. PROC. NO. WM-RP-105 REV. 4
PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO.
1-
- 12. PAGE 1 OF "3.
ko*3.
PROC. NO. WM-RP-107 REV..j FORM NDAP-QA-0002ý, Rev. 7, Page 1 of 2 (Electronic Form)
I 5-11
- 4. FORMS REVISED 1...I R.2 2 R 0
-R R
R R
- 5. PROCEDURE TITLE Transfer and Drying'Powdered Resin S. REQUESTED CHANGE PERIODIC REVIEW.
NO L] YES INCORPORATE PC:FS LI NO 0
YES
- 1999-6916 REVISION
[
PCAF nI DELETION [1 (CHECK ONE ONLY)
- 7.
SUMMARY
OF I REASON FOR CHANGE
- 1. Changed "Radwaste Supervisor* references to 'Wet Waste Program Owner' to be consistent with NDAP QA-0640, 'Conduct of Effluents Management.
- 2.
Reorganized procedure steps to be consistent with actual order in which they are performed.
- 3.
Changed Form WM-RP-107-1 sign-offs to be consistent with procedure order. Numbered slgn-offs to reference procedure steps.
- 4. Created Form WM-RP-107-2 to separate temperature/humidity data collection from processing sign-offs.
- 5. Changed valve references to be consistent with actual valve names used on the vendor equipment
- 6. Clarified Fill-head/Fill-plate Installation instructions to ensure a spacer is included.
Continued
- 8. DETERMINE COMMITTEE REVIEW REQUIREMENTS (Refer to Section 6.1.4)
PORC REVIEW REQ'D?
E] NO Z.YES
- 9.
PORCMTG#
ERC REVIEW REQ'D?
[
NO jj YES
- 10. ERC MTG#
BLOCKS 11 THRU 14 ARE ON PAGE 2 OF FORM
- 15.
Tom Kalinowski I
1940
/
4/2101
- 16. COMMUNICATION OF CHANGE REQUIRED?
- PREPARER, ETN DATE
[
NO
[
YES (TYPE)
(Print or Type).
SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS CONDUC*ED QADR AND TECHNICAL REVIEW.
UNLESS OTHERWISE DOCUMENTED IN BLOCK 14 OR ATTACHIED REVIEW FORMS.
CROSS DISC.PUNE REVIEW (IF REQUIRED) HAS BEEN COMPLETED BY SIGNATURE IN BLOCK 14 ORATTACHED REVIEW FORMS.
PROCEDURE CHANGE PROCESS FORM FORM NDAP-OA-0002-8, Rev. 7, Page 2 of 2 (Electronic Form) 5-12
- 1. PCAF NO.
1
- 12. PAGE 2 OF 3
- 13. PROC. NO. WM-RP-107 REV. *'
- 11.
A 50.59 and 72.48 Evaluation per NDAPQA-0726 Is required to be attached or referenced for all procedure changes except Expedited Reviews and Administrative Corrections. Either 11 a, b, or c mutg be checked 'YES" and the appropriate form attached or referenced.
- a. 50.59 and 72.4A8 Screening Determination (Form NDAP-QA-0726-5)
YES 0
N/A
- b. 50.59 or 72.48 Safety Evaluation (Note: 50.59 Safety Evaluations prepared on
'2 YES N/A Form NDAP-QA-0726-1 Rev. 5 or earlier also require a 50.59 & 72.48 Screening Determination)
Safety Evaluation No.
- c. Expedited Review/Administrative Correction-50.59 and 72.48 Evaluation not n'
YES N/A Required
- 12. Is a Surveillance Procedure Review Checklist required per NDAP-QA-07227 LI YES NO
- 13. Is a Special. Infrequent or Complex Test/Evolution Analysis Form required per
'2 YES NO NDAP-QA-0320? (SICT/E form does not need to be attach*td:)
- 14. Reviews may be documented below or by attaching Document Review Forms NDAP-QA:0101-1.
REVIEWED BY WITH REVIEW NO COMMENTS DATE QADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS
- IST **
OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or Impact the thermal power heat balance. (N)
Required for changes to Section XA Inservice Test Acceptance Criteria.
PROCEDURE CHANGE PROCESS FORM WM-RP-107 Rev 5 Page 3 of 33
SUMMARY
OF /REASON FOR CHANGE (continued)
?.
Clarified contamination control instructions to ensure appropriate measures are taken at all times.
- 8. Clarified container preparation requirements and verifications.
- 9. Added container inspection requirements for waste residue in response to CR # 188042, Bead Resin on Liner at Disposal Facility.
5-13
PROCEDURE CHANGE PROCESS FORM 1
PCAF NO. 2001-1488
- 12.
PAGE 1 OF 3
- 13. PROC. NO.
WM-PS-155 I4. FORMS REVISED R
R R-R R
R R
PROCEDURE TITLE 10CFR61 SAMPLE SHIPPING AND CORRELATION FACTOR DETERMINATION REQUESTED CHANGE PERIODIC REVIEW INCORPORATE PCAFS Z NO REVISION
[--
0 NO IE YES Lý YES #
z*
DELETION [--
PCAF
SUMMARY
OF / REASON FOR CHANGE Added step to inform Health Physics Management when 10CFR61 anal, transuranics. This step was added in response to an action item id tifd Control Assessment 1999 Intiffiia Dose 4
- 8.
DETERMINE COMMITTEE REVIEW REQUIIE*
(Refer to Section 6.1.4)
PORC REVIEW REQ'D?
0'NO YES ERC REVIEW REQ'D?
- LII, NO YES BLOCKS 11 THRU 14 ARE& 0 PA GE2.F FORM
- 15.
Michael C. MPI-rý 790 I6/7/01
- 16.
PREPARE.
ETN DATE (Print or Typ.-
- 9.
PORC MhTG#
- 10. ERC MTG#
COMMUNICATION OF C O
-- YES (TYPE)
N/A I
- HANGE REQUIRED?
SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS CONDUCTED QADR AND TECHNICAL REVIEW UNLESS OTHERWISE 4 &71, DOCUMENTED IN BLOCK 14 OR ATTACHED REVIEW FORMS.
"/DATE CROSS DISCIPLINE REVIEW (IF REQUIRED) HAS BEEN COMPLETED BY SIGNATURE IN BLOCK 14 OR ATTACHED REVIEW FORMS.
FORM NDAP-QA-0002-8, Rev. 7, Page 1 of 2 I'
6.
7.
Y) b 1 4.
FORMS REVISED
- -PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO.
2001-1488
- 12. PAGE 2 OF 3
- 3. PROC. NO. WM-PS-155 REV. 2
- 11.
A 50.59 and 72.48 Evaluation per NDAP-QA-0726 is required to be attached or referenced for all procedure changes except Expedited Reviews and Administrative Corrections. Either Ila, b, or c mus-t be checked -YES".'
and the appropriate form attached or referenced.
- a. 50.59 and 72.48 Screening Determination (Form NDAP-QA-0726-5)
Z YES N/A
- b. 50.59 or 72.48 Safety Evaluation (Note: 50.59 Safety Evaluations prepared on
,3 YES N/A Form NDAP-QA-0726-1 Rev. 5 or earlier also require a 50.59 & 72.48 Screening Determination)
Safety Evaluation No.
- c. Expedited Review/Administrative Correction-50.59 and 72.48 Evaluation not
[Y*,S N1A Required
- 12. Is a Surveillance Procedure Review Checkrist required per NDAP-QA-0722?
[3 YEs 0NO
- 13. Is a SpeciaL. Infrequent orComplex Test/Evolution Analysis Eorm requiredper..
-D.YES..
0 NO' NDAP-QA-0320? (SICTIE form does not need to be attached.)
- 14. Reviews may be documented below or by attaching Document Review Forms NDAP-QA-0101-1.
REVIEWED BY WITH REVIEW NO COMMENTS DATE QADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS IST
- OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (58)
"Required for changes to Section XI Inservice Test Acceptance Criteria.
FORM NDAP-QA-0002-8, Rev. 7, Page 2 of 2 (Electronic Form) 5-15
*--
- 1.
PCAF NO. NA
- 4.
FORMS REVISED
- 01
- 5. PROCEDURE TITLE Packaging and Loading of
- 6.
REQUESTED CHANGE PERIODIC REVIEW.
INCORPORATE PCAFS REVISION E]
- 7.
SUMMARY
OF I REASON Reorganized some steps to signatures on forms are rec Description' column on For shipping limits. Clarified lal requirements used for pac6 closure requirements. Rev PCAF #2000-4835.
- 8. DETERMINE COMMITTEE (Refer to Section 6.1.4)
PORC REVIEW REQD?
BLOCKS 11 THRU 16 AREC
- 17.
Mike Micca PREPARER (Print or Type)
FORM NDAP-QA-0002-8, Rev. 8, Page I of 2 (Electronic Form) 5-16 PROCEDURE CHANGE PROCESS FoRM
- 2. PAGE 1 OF 2
- 3. PROC. NO. WM-PS-210 REV. 5 R6,-
02 R 5,
-_03 R3, R_,-
R_
R_
DAW and Radioactive Material Z
NO f] YES
[
NO
[
YES # 2000-4835 PCAF E]
DELETION [] (CHECKONE ONLY)
FOR CHANGE be consistent with practice. Added -s to body of procedure to indicate where luired. Added instructions on what needs to be documented on the 'Material mWM-PS-210-1. Provided guidance for packages with dose rates approaching beling requirements due to Condition Report #220636. Updated absorbent aging liquids due to the intended use of a new brand of absorbent. Updated drum ised all WM-PS-210 forms. Various administrative corrections. Incorporated Continued []
E REVIEW REQUIREMENTS
[]NO Z] YES"
- 9.
PORCMWTG# 0-%"
IN PAGE 2 OF FORM
/
1790 1 09/1312001
- 18. COMMUNICATION OF CHANGE REQUIRED?
ETN DATE 0
NO Z YES (TYPE) Non-Routine Training SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS CONDUCTED OADR AND TECHNICAL REVIEW UNLESS OTHERWISE DOCUME D IN BLOCK 16 OR ATTACHED REVIEW FORMS.
CROSS DISCIPLINE REVIEW (IF REQUIRED) HAS BEEN COMPLETED DRVASOR BY SIGNATURE IN BLOCK 16 OR ATTACHED REVIEW FORMS.
R EENTER NA.IF FUM HAS APPRO DATE
- It((i\\
I
PROCEDURE CHANGE PROCESS FORM FORM NDAP-QA-0002-8, Rev. 8, Page 2 of 2 (Electronic Form) 5-17
- 1. PCAFNO. NA
- 2. PAGE2OF 2
- 13. PROC. NO. WM-PS-210 REV. 5
- 11.
This question documents the outcome of the 50.59 and 72.48 Review required by NDAP-QA-0726. Either I Ia, b, c or d must be checked "YES" and the appropriate form attached or referenced.
- a. This change Is an Administrative Correction for which 50.59 and 72.48 are not
[] YES Z
N/A applicable.
- b. This change is a change to any surveillance, maintenance or administrative Z
YES E] N/A procedure for which 50.59 and 72.48 are not applicable.
A-01-363
- c. This change is bounded by a 50.59/72A8 Screen/Evaluation, therefore, no new E] YES
[D N/A 50,59/72.48 Evaluation is required.
Screen/Evaluation No.
- d. 50.59 and/or 72.48 are applicable to this change and a 50.59/72.48
[] YES N/A Screen/Evaluation is attached.
YES Change Request No.
- 13. Should this change be reviewed for potential effects on Tradining Needs or Material?
j]
YES NO If YES, enter an Action Ilemr @ NIMS/Action/Gen Work Meh/PICN
- 14. Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722?
E] YES Z
NO'
- 15. Is a Special, Infrequent or Complex Test/Evolution Analysis Form required per
[] YES.
Z NO NDAP-OA-0320? (SICT/E form does not need to be attached,)
- 16. Reviews may be documented below or by attaching. Document Review Forms NDAP-QA-0101-1.
REVIEWED BY WITH DATE REVIEW NO COMMENTS OADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS
- 1ST **
OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (l)
Required for changes to Section Xl Inservice Test Acceptance Criteria.
PROCEDURE CHANGE PROCESS FORM
- 1. PCAFNO.a60I-I3a-j
- 12. PAGE1OF 4
- 13. PROC.NO.
CH-TP-055 REV. 5
- 4.
FORMS REVISED R
R_,
R
- R-,
R R
- 5. PROCEDURE TITLE SOLID RADWASTE 10CFR61 CORRELATION FACTOR DETERMINATION - SAMPLE COLLECTION AND PREPARATION
- 6.
REQUESTED CHANGE PERIODIC REVIEW
[E NO Z
YES INCORPORATE PCAFS Z NO El YES REVISION r-PCAF ER DELETION El (C4 CK 0EONLY)
- 7.
SUMMARY
OF / REASON FOR CHANGE Procedure was reviewed and is suitable for use.
Periodic review due date and titles were updated.
This is an administrative correction.
Continued
- 8.
DETERMINE COMMITTEE REVIEW REQU (Refer to Section 6.1.4)
PORC REVIEW REQ'D?
NO YES
- 9.
PORC MTG#
NA ERC REVIEW REQ'D?
NO E
YES
- 10. ERC MTG#
NA BLOCKS 11 THRU 14 ARES tP 7PF FORm
- 15.
Karen Ziolkows A
25 1 3-29-01
- 16. COMMUNICATION OF CHANGE REQUIRED?
PREPARER qW ETN DATE Z NO E] YES (TYPE)
,4A (Print or'T)
- 17.
SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS
/CONDUCTED QADR AND TECHNICAL REVIEW UNLESS OTHERWISE
" DOCUMENTED IN BLOCK 14 OR ATTACHED REVIEW FORMS.
4 ONBLE SUPER VISOR DATE CROSS DISCIPLINE REVIEW (IF REQUIRED) HAS BEEN COMPLETED BY SIGNATURE IN BLOCK 14 OR ATTACHED REVIEW FORMS.
- 18.
A1A
_4_
FUM APPROVAL DATE
- 19. RESPONSIBLE APPROVER ENTER N/A IF FUM HAS APPROVA RITY INITIALS DATE FORM NDAP-QA-0002-8, Rev. 7, Page 1 of 2 (Electronic Form) 5-18
PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO. '1
- 12. PAGE2OF 4 3
PRO NO.
CH-TP-055 REV. 5
- 11.
A 50.59 and 72.48 Evaluation per NDAP-QA-0726 is required to be attached or referenced for all procedure changes except Expedited Reviews and Administrative Corrections. Either 11 a, b, or c must be checked "YES" and the appropriate form attached or referenced.
- a.
50.59 and 72.48 Screening Determination (Form NDAP-QA-0726-5)
[- YES I
N/A
- b. 50.59 or 72.48 Safety Evaluation (Note: 50.59 Safety Evaluations prepared on D] YES N/A Form NDAP-QA-0726-1 Rev. 5 or earlier also require a 50.59 & 72.48 Screening Determination)
Safety Evaluation No.
NA
- c. Expedited Review/Administrative Correction-50.59 and 72.48 Evaluation not YES
[] N/A Required
- 12. Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722?
E] YES Z
NO
- 13. Is a Special, Infrequent or Complex Test/Evolution Analysis Form required per E] YES Z
NO NDAP-QA-0320? (SICT/E form does not need to be attached.)
- 14. Reviews may be documented below or by attaching Document Review Forms NDAP-QA-0101-1.
REVIEWED BY WITH REVIEW NO COMMENTS DATE QADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS IST **
OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER NA Required for changes that affect, or have ootential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (5)
Required for changes to Section Xl Inservice Test Acceptance Criteria.
FORM NDAP-QA-0002-8, Rev. 7, Page 2 of 2 (Electronic Form) 5-19
SECTION 6 MISCELLANEOUS TECHNICAL REQUIREMENTS MANUAL (TRM)
FSAR AND 40CFR190 REPORTING 6-1
- 1. TRM Action 3.11.1.4.F.2 requires the reporting of Liquid Radwaste Effluent Monitoring Instrumentation inoperability not corrected in a timely.
None to report for 2001.
- 2. TRM Action 3.11.1.5.C.1 requires the reporting of Radioactive Liquid Process Effluent Monitoring Instrumentation inoperability not corrected in a timely.
None to report for 2001.
- 3. TRM Action 3.11.2.6.K requires an explanation for Radioactive Gaseous Effluent Monitoring Instrumentation required actions and completion times not met.
None to report for 2001.
- 4. TRM Action 3.11.4.1.F.2 requires reporting the cause of the unavailability of milk or fresh leafy vegetables samples and identify the new locations for obtaining replacements.
None to report for 2001. [Note: Milk samples were acquired at three locations per the requirements of Table 3.11.4.1-1. Milk sampling at a fourth location was discontinued because dairy farming was discontinued.
There was no need to identify a new location because samples were already being gathered from three locations per the requirements]
- 5. TRM Action 3.11.4.2.A requires reporting when land use census identifies a new location which yields a calculated dose or dose commitment greater than the values currently being calculated.
None to report for 2001.
- 6. TRM Action 3.11.4.2.B requires reporting when land use census identifies locations that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained.
None to report for 2001. [Note: The 2000 Land Use Census determined that the relative disposition rate at a dairy farm exceeded those for each of the current milk monitoring locations by more than 20 percent. This would normally mean that the location with the lowest disposition rate be replaced. However, it was determined that samples of milk from the four cows at the new location are not available and no changes were made in milk monitoring locations during 2001.
6-2
- 7. The 40CFR190.10 standard for normal operation for the uranium fuel cycle including annual dose equivalent and total quantities of radioactive material limits were not exceeded by SSES operation. Refer to Page 4-2 for specific values.
- 8. FSAR Section 11.6.11 requires the reporting of airborne radioactivity detected in the Low Level Radwaste Holding Facility. None detected in 2001.
6-3
SECTION 7 CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 7-1
CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENT AND WASTE DISPOSAL REPORTS Sampling of milk at location 10D3, the Drasher Farm, located 3.5 miles SSW of the SSES, was initiated in April 2000. Sampling at this location was begun based on the results of an annual evaluation of 1999 meteorological data for potential milk sampling locations identified by the 1999 Annual Land Use Census. This evaluation looks at the relative sensitivities expected for the detection of any radionuclides that might be released to the air from SSES operation at potential monitoring locations. The purpose of this evaluation is to determine if any of the current REMP milk monitoring locations should be replaced by locations that might be more sensitive for detecting airborne radioactivity attributable to SSES operation. The results of the evaluation, performed in April 2000, indicated that location 10D3 should replace location 7C1 as a milk monitoring location. Since April 24, 2000, milk sampling has been taking place at both locations, 10D3 and 7C1. Milk monitoring at the radiological environmental monitoring program (REMP) location 7C1 was discontinued at the beginning of 2001. The reason for this change was that the Zajac farm (7C1) went out of the dairy farming business and sold all of its cows. Therefore, milk could no longer be obtained from this location.
7-2
SECTION 8 EFFLUENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS 8-1
EFFLUENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS Systems classified as Insignificant Effluent Pathways are evaporation from the Unit I and Unit 2 Condensate Storage Tanks (CSTs) and the common Refueling Water Storage Tank (RWST) and from the Hydrogen Seal Oil and the Main Turbine and RFPT lubrication oil mist eliminators which vent to the turbine building roofs. There are no waterborne effluent pathways classified as insignificant.
These pathways are not continuously monitored. The CSTs and RWST are sampled quarterly to determine the concentration of radionuclides present in these tanks.
Airborne release to the environment from the tanks is estimated based on conservative estimates of the evaporation rates from each of the tanks using a modified method established within Chapter 7 of EPA AP-42. A conservative carry-over fraction of radionuclides from the water to the evaporated liquid is then assumed. Airborne release to the environment from the demisters conservatively assumes the maximum contamination of the oil by condensate (1000 ppm) as it passes through the turbines followed by immediate removal of 100% of the water by the oil mist eliminators. The annual release of tritium and, iodines, and particulates with half-lives greater than 8 days was calculated based on these conservative assumptions; the calculated releases are shown in Table 8-1. All nuclides are negligible compared to the airborne release shown in Tables 2-1 and 2-2 except for tritium. The maximum dose to the public from a release of 29.6 Ci of tritium is calculated to be 4.1 E-2 mrem (child). This is a fraction of the maximum dose from airborne effluent reported in Section 4.
The CST analyses showed concentrations ranging from 3.9E-6 to 1.2E-05 p.Ci/ml of Xe 133 and Xe-135. This range of concentration of dissolved and entrained noble gas in water stored in tanks on site was approximately 9% of the Technical Requirement limit of 2E-4 lCi/ml allowed in water that may be discharged to the environment.
8-2
TABLE 8-1 ANNUAL RELEASE FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS U1-CST and U2-CST and Main Turbine/RFPT Main Turbine/RFPT Nuclide RWST Lube Oil Systems Lube Oil Systems Total (Ci)
(Ci)
(Ci)
(Ci)
H-3 5.95E-02 1.45E+01 1.51E+01 2.96E+01 Mn-54 9.43E-08 1.06E-07 1.07E-06 1.27E-06 Cr-51 4.02E-09 0
0 4.02E-09 Co-58 2.21E-10 0
1.54E-08 1.57E-08 Co-60 6.56E-08 1.37E-07 8.67E-07 1.07E-06 Fe-59 1.01E-09 0
0 1.O1E-09 Cs-137 6.44E-10 3.46E-09 0
4.1OE-09 Xe-133 0
3.89E-06 0
3.89E-06 Xe-135 0
1.19E-05 5.53E-06 1.75E-05 8-3
SUSQUEHANNA STEAM ELECTRIC STATION APPENDIX A SSES ODCM AE&WD REPORT 2001 PPL Susquehanna, LLC Two North Ninth Street Allentown, Pennsylvania 18101-1179 April 2002 I
PROCEDURE COVER SHEET NUCLEAR DEPARTMENT PROCEDURE AN1V
-ODCM INTRODUCTION ODCM-QA-001 Revision 0 Page 1 of 11 QUALITY CLASSIFICATION:
APPROVAL CLASSIFICATION:
0 QA Program r-Non-QA Program 0
Plant sl Non-Plant r-1 Instruction.
EFFECTIVE DATE,.
t- (:= 9 PERIODIC REVIEW FREQUENCY;:
N/A PERIODIC REVIEW DUE DATE.:
N/A RECOMMENDED REVIEWS:
Proc-dure Owner:
R. K. Barclay Responsible Supervisor:
Supervisor - Operations Technology Responsible FUM:
Manager - Nuclear Technology Responsible Approver:
General Manager - SSES FORM NDAP-QA-0002-1, Rev. 2, Page 1 of 1
ODCM-QA-001 Revision 0 Page 2 of 11 PROCEDURE REVISION
SUMMARY
TITLE:
ODCM INTRODUCTION
- 1.
Initial Issue in procedural format.
- 2.
Section 1 of ODCM Revision 7 is reorganized in the format established by NDAP-QA-0002. No revision bars are used since the change was to the entire section.
- 3.
Cover sheet, Revision Summary, and Table of Contents are added.
- 4.
Description of all ODCM sections is provided.
- 5.
Table I of ODCM Revision 7 is deleted because there are no requirements to present this information in the ODCM.
Approval MWS Date see page 1
ODCM-QA-001 Revision 0 Page 3 of 11
- 6.
Section 3 of ODCM Revision 7 is deleted. It essentially duplicates Technical Specification 3.11.1.1 and there are no requirements to present this information in the ODCM.
- 7.
Incorporated Radiological Effluent and Environmental responsibilities appropriate to the ODCM from NEPM-QA-1010 in Section 4. Changed responsibilities formerly assigned to Manager - Nuclear Engineering to Manager - Nuclear Modifications.
Approval MWS Date see page 1
ODCM-QA-001 Revision 0 Page 4 of 11 TABLE OF CONTENTS PAGE 1.0 PURPOSE 2.0 POLICY/DISCUSSION
3.0 REFERENCES
4.0 RESPONSIBILITIES General Manager - SSES Manager - Nuclear Modifications Manager - Nuclear Technology Manager - Nuclear Assessment Services Supervisor - Operations Technology Supervisor - Nuclear Licensing Environmental Services - Health Physicist (Effluent)
Environmental Services - Health Physicist (REMP) 5.0 DEFINITIONS 6.0 PROCEDURE 6.1 Organization 7.0 RECORDS A
Contents of Annual Effluent and Waste Disposal Report Approval MWS Date see page 1 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 5
5 6
7 7
7 7
7 7
8 8
8 8
9 9
10 A TT A M.
t"l I:M*T PAGE 11 ac:%ý I KAM 11ý t.*
- t*-l'l t'* I*.I
ODCM-QA-001 Revision 0 Page 5 of 11 1.0 PURPOSE The purpose of this procedure is to describe the overall purpose and organization of the SSES Offsite Dose Calculation Manual (ODCM).
2.0 POLICY/DISCUSSION The SSES Offsite Dose Calculation Manual (ODCM) is a licensing basis document required by Technical Specifications. It provides the methodology and parameters to be used in calculating offsite doses and effluent monitor setpoints for the Susquehanna Steam Electric Station, Units 1 and 2. Methods are included for determining maximum individual, whole body, and organ doses due to waterbome and airborne effluents to ensure compliance with the dose limitations in the Technical Specifications. Methods are included for performing dose calculations to ensure compliance with the waterbome and airborne treatment system operability sections of the Technical Specifications.
This manual includes the methods used for determining quarterly individual doses for inclusion in Annual Effluent and Waste Disposal Reports.
Approval MWS Date see page 1
ODCM-QA-O01 Revision 0 Page 6 of 11
3.0 REFERENCES
3.1 TS 6.14, Off site Dose Calculation Manual (ODCM) 3.4 NDAP-QA-0152, Quality Assurance for Radiological Environmental Monitoring, Radioactive Effluents, Meteorology, The Environmental Protection Plan, and The Offsite Dose Calculation Manual Approval MWS Date see page 1 A III
ODCM-QA-001 Revision 0 Page 7 of 11 3.10 NDAP-00-1203, Modification Identification and Scoping Process 4.0 RESPONSIBILITIES 4.1 General Manager-SSES 4.1.1 Ensures that the ODCM is used in performance of the surveillance requirements and for compliance with the limiting conditions of operation stated in the Technical Specifications relative to radioactive effluent.
4.1.2 Approves revisions to tne uu'.
4.2 Manager - Nuclear Modifications 4.2.1 Provides modification engineering and support in accordance with NDAP-O0-1203 for equipment and systems involved with the conduct of the effluent and environmental monitoring programs at SSES.
4.3 Manager - Nuclear Technology 4.3.1 Manages the programs for the assessment of the radiological environmental impact of SSES.
4.4 Manager - Nuclear Assessment Services 4.4.1 Periodically assesses the SSES effluent and environmental programs (including meteorological data) for compliance with the requirements of the Technical Specifications and the ODCM.
4.5 Supervisor - Operations Technology 4.5.1 Ensures the adequacy and correctness of methodologies described in the ODCM.
4.5.2 Is responsible for reviewing revisions to the ODCM.
Approval MWS Date see page 1
ODCM-QA-001 Revision 0 Page 8 of 11 4.5.3 Approves both the Annual Effluent and Waste Disposal and the Annual Radiological Environmental Operating Reports submitted to the NRC.
4.6 Supervisor - Nuclear Licensing 4.6.1 Submits the required radiological effluent and environmental reports to the NRC.
4.6.2 Notifies the appropriate groups of NRC licensing requirements.
4.7 Environmental Services - Health Physicist (Effluent) 4.7.1 Develops methodologies used in performance of effluent dose calculations and establishment of setpoints.
4.7.2 Performs dose calculations necessary for fulfillment of SSES Technical Specification Surveillance Requirements.
4.7.3 Prepares and submits the Annual Effluent and Waste Disposal Report to Nuclear Licensing for submittal to the NRC.
4.8 Environmental Services - Health Physicist (REMP) 4.8.1 Prepares and submits the Annual Radiological Environmental Operating Report to Nuclear Licensing for submittal to the NRC.
5.0 DEFINITIONS 5.2.
Site Boundary - Is that line beyond which the land is not owned, leased or otherwise controlled by the licensee. (PPL Drawing C243786, SH1, Rev. 1, "U-1&2 Site Facilities and Boundary Map."
5.3 Unrestricted Area - The area at or beyond the site boundary access to which is neither limited nor controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional and/or recreational purposes.
Approval MWS Date see page 1
ODCM-QA-001 Revision 0 Page 9 of 11 6.0 PROCEDURE 6.1 Organization Environmental Services shall develop and maintain a set of procedures as described in the following sub-sections.
6.1.1 ODCM-QA-001 - ODCM Introduction This procedure describes the overall purpose and organization of the ODCM.
6.1.2 ODCM-QA-002 - ODCM Review And Revision Control This procedure describes the initiation, review and processing of revisions to the ODCM and establishes responsibility for the ODCM.
6.1.3 ODCM-QA-003 - Effluent Monitor Setpoints This procedure describes the policies pertaining to and the methodology used in establishing effluent monitor setpoints.
6.1.4 ODCM-QA-004 - Airborne Effluent Dose Calculations This procedure provides the methodology and parameters used in calculating air dose resulting from noble gas effluent and maximum individual, whole body, and organ doses due to airborne effluents to ensure compliance with the dose limitations in the Technical Specifications.
6.1.5 ODCM-QA-005 - Waterborne Effluent Dose Calculations This procedure provides the methodology and parameters to be used in calculating maximum individual, whole body, and organ doses due to waterborne effluents to ensure compliance with the dose limitations in the Technical Specifications.
Approval MWS Date see page 1
ODCM-QA-001 Revision 0 Page 10 of 11 6.1.6 ODCM-QA-006 - Total Dose Calculations This procedure provides the methodology and parameters to determine the total dose to a member of the public from the fuel cycle in the vicinity of the SSES site.
6.1.7 ODCM-QA-007 - Radioactive Waste Treatment Systems This procedure defines the operability requirements of the radioactive waste treatment systems.
6.1.8 ODCM-QA-008 - Radiological Environmental Monitoring Program This procedure provides the methodology and parameters used to determine doses to the public resulting from inhalation, ingestion, and direct shine from radiologically contaminated environmental sampling media based on measured activity concentrations in those media. This procedure also describes the Radiological Environmental Monitoring Program (REMP), which includes the annual land use census survey and interlaboratory comparison program.
6.1.9 ODCM-QA-009-Dose Assessment Policy Statements The purpose of this procedure is to state dose and effluent policy statements that are not directly associated with any other section of the ODCM.
7.0 RECORDS Except for ODCM-QA-002, no records are specified by the ODCM. Records are generated in performance of other procedures that use the information contained in the ODCM. Control of these records is specified in the controlling procedures.
ODCM-QA-O01 (26)
Approval MWS Date see page 1
Attachment A ODCM-QA-001 Revision 0 Page 11 of 11 Approval MWS Date see page 1 Page 1 of 1
Expires On: \\??
FOR INFORMATION ONLY PROCEDURE COVER SHEET FORM NDAP-QA-0002-1, Rev. 2, Page 1 of 1 Assigned to: ????
I
Assigned to: ????
FOR INFORMATION ONLY Expires On: \\??
ODCM-QA-002 Revision 1 Page 2 of 8 PROCEDURE REVISION
SUMMARY
TITLE:
ODCM REVIEW AND REVISION CONTROL
- 1.
Incorporate ITS related changes.
- 2.
Change responsibilities to recognize Supervisor-Environmental Services position.
- 3.
Revise Section 6.1 to state that changes tracked by other mechanisms (Condition Reports, Modifications) do not require use of Form ODCM-QA-0a2
- 1.
- 4.
Add a Section 6.3.4 to include the revision control requirements of Technical Specifications 5.5.1.C.3.
- 5.
Revise Section 6.6 to allow other members of Operations Technology to present ODCM revisions to PORC.
The above changes to ODCM-QA-002 have been evaluated as to not decrease the level of effluent control or the accuracy andior reliability of dose calculations or setpoint determinations as required by I1CFR20.1302, 40CFR190, 10CFRS0.36a and 10CFR50, App. 1.
In addition, these changes"l' do not alter the conduct of the radiological environmental monitoring program, C2) do not change the radioactive effluent controls and radiological environmental monitoring activities, andC3) do not change the: information to be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports.
Assigned to: '????
FOR INFORMATION ONLY ODCM-QA-002 Revision 1 Page 3 of 8 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 4
2.0 POLICY/DISCUSSION 4
3.0 REFERENCES
4 4.0 RESPONSIBILITIES 5
4.1 General Manager - SSES 5
4.2 Manager - Nuclear Technology 5
4.3 Supervisor - Environmental Services 5
4.4 Environmental Services - Health Physicist (Effluent) 5 4.5 All Personnel 5
5.0 DEFINITIONS 6
6.0 PROCEDURE 6
7.0 RECORDS 7
ATTACHMENTS ATTACHM ENT PAGE A
SSES ODCM CHANGEREQUEST (FORM ODCM-QA-002-1) 8 Expires On: \\??
Assigned to: ????
FOR INFORMATION ONLY Expires On: \\??
ODCM-QA-002 Revision 1 Page 4 of 8 1.0 PURPOSE The purpose of this procedure is to describe the initiation, review, and processing of revisions to the ODCM and to establish responsibility for the ODCM.
This procedure constitutes part of the SSES Offsite Dose Calculation Manual (ODCM),
which is a licensing basis document.
2.0 POLICYIDISCUSSION 2.1 The ODCM is part of the Licensing Basis of SSES and is controlled by ITS 5.5.1, Offsite Dose Calculation Manual (ODCM).
2.2 The ODCM procedures are controlled as Plant Functional Unit Procedures in accordance with the requirements of NDAP-QA-0002, with the following additional guidance and controls:
2.2.1 ODCM procedures shall be numbered as follows: ODCM-QA-nnn, where nnn is a sequential number starting with 001.
2.2.2 0DCM procedures shall be reviewed and accepted by the Manager Nuclear Technology prior to PORC review.:
2.2.3 ODCM procedures shall be approved by the General Manager - SSES.
2.2.4 Changes to the procedures comprising the ODCM-require PORC review prior to approval. Changes which are solely administrative corrections or an expedited review revision are excepted, PORC review will be indicated by recording the PORC meeting number on the Procedure Change Process Form (NDAP-QA-0002-8).
2.2.5 ODCM procedures shall be issued and controlled by Nuclear Records Document Control Services (NR-DCS) in accordance with NR procedures. The distribution list shall be maintained by DCS.
2.3 Changes to the Radioactive Effluent Control Program (RECP) are controlled in accordance with NDAP-QA-0728, but are reported as changes to the ODCM in the Annual Effluent and Waste Disposal Report.
3.0 REFERENCES
3.1 TS 5.5.1, Offsite Dose Calculation Manual (ODCM) 3.2 NDAP-QA-0002, Nuclear Department Procedure Program 3.3 NDAP-QA-0101, Document Review
Assigned to: ????
FOR INFORMATION ONLY ODCM-QA-002 Revision 1 Page 5 of 8 3.4 NDAP-QA-01 52, Quality Assurance for Radiological Environmental Monitoring, Radioactive Effluents, Meteorology, The Environmental Protection Plan, and The Offsite Dose Calculation Manual 3.5 NDAP-QA-0728, SSES Technical Requirements Program 3.6 IOCFR2O.1302, Compliance with Dose Limits for Individual Members of the Public 3.7 40CFRI90, Environmental Radiation Protection Standards for Nuclear Power Operation 3.8 10CFR50.36a, Technical Specifications on Effluents from Power Reactors 3.9 10CFR50, Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet "As Low As Is Reasonably Achievable" for Radioactive Material in Light-Water Cooled Nuclear Power Reactors 4.0 RESPONSIBILITIES 4.1 General Manager - SSES 4.1.1 Approves revisions to the ODCM.
4.2 Manager - Nuclear Technology 4.2.1 Is the Responsible Functional Unit Manager (FUM) 4.3 Supervisor - Environmental Services 4.3.1 Ensures the adequacy and correctness of methodologies described in the ODCM.
4.3.2 Is responsible for reviewing revisions to the ODCM.
4.4 Environmental Services - Health Physicist (Effluent) 4.4.1 Maintains the ODCM.
4.4.2 Processes revisions to the ODCM.
4.5 All Personnel 4.5.1 Submit comments on ODCM contents and proposed revisions to the Environmental Services-Health Physicist (Effluent).
Expires On: \\??
FOR INFORMATION ONLY ODCM-QA-002 Revision 1 Page 6 of 8 5.0 DEFINITIONS None.
6.0 PROCEDURE 6.1 Personnel shall submit proposed ODCM revisions on the SSES Offsite Dose Calculation Manual Change Request Form ODCM-QA-002-1. The submitter shall complete Sections 1 through 5 according to the directions on the form, including sufficient detail of the revision and technical basis of the change to support the rationale for the change and to enable the Environmental Services Health Physicist (Effluent) to proceed. The submitter should provide at least one month lead time between the submittal date and the requested implementation date to permit preparation, review by interested parties, and approval of the ODCM revision. Changes tracked by other mechanisms (eg.,
Condition Reports and Modifications) do not require use of Form ODCM-QA 002-1.
6.2 The Environmental Services Health Physicist (Effluent) shall sign and date Form(s) ODCM-QA-002-1 on receipt, and retain the form(s) in a work file created for this ODCM revision. The Environmental Services - Health Physicist (Effluent) may contact the form submitter to discuss the details of the revision.
6.3 The Environmental Services Health Physicist (Effluent) or designee prepares a draft of the ODCM revision based on information in Form(s) ODCM-QA-002-1.
6.3.1 The preparer shall ensure that the change does not reduce the level of effluent control or the accuracy and/or reliability of dose calculations or setpoint determinations as required by 1OQFR20.1302, 40CFR190, 10CFR50.36a and IOCFR50, Appendix I.
6.3.2 The preparer shall include a statement to this effect in the Procedure Revision Summary.
6.3.3 If compliance to the criterion in §6.3.1 cannot be demonstrated, the preparer shall make appropriate changes to ensure compliance, else the proposed revision shall be dismissed.
6.3.4 Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed. The date the change is implemented is indicated on the Procedure Cover sheet.
6.4 The Environmental Services Health Physicist (Effluent) follows the process described in NDAP-OA-0002, Section 7.0, for plant procedures.
6.4.1 All review comments and resolutions shall be documented according to NDAP-QA-0101.
Expires On: \\??
Assigned to: ????
Expires On: \\77 FOR INFORMATION ONLY oDCM-QA-002 Revision I Page 7 of 8 6.4.2 The review shall sustain that the change does not reduce the accuracy or reliability of dose calculations and/or setpoint determinations.
6.5 The Environmental Services Health Physicist (Effluent) schedules the proposed ODCM revision for PORC review in accordance with PORC procedures.
6.6' The Supervisor - Environmental Services or Environmental Services Health Physicist (Effluent) presents the ODCM revision to PORC, along with originating information (Form(s) ODCM-QA-002-1), review documentation (Form NDAP QA-0101-1), 50.59/72.48 Determination (Form NDAP-QA-0726-5), Safety Evaluation (if required, Forms NDAP-QA-0726-1, -2, -4) any technical material (calculations, studies, etc.) necessary to support the ODCM revision, the evaluation required in Section 6.3.1 and appropriate signature approvals.
6.7 The Environmental Services Health Physicist (Effluent) shall submit to the NRC a complete, legible copy of the revised ODCM in the Annual Effluent and Waste Disposal Report for the period of the report in which any change in the ODCM was made.
7.0 RECORDS The following shall be submitted to Nuclear Records in accordance with NR procedures:
7.1 Form(s) ODCM-QA-002-1, with attachments, if any.
7.2 Review package, assembled in accordance with the requirements of NDAP-QA 0002 and NDAP-QA-0101.
odomqa002(26)
Assigned to: ????
FOR INFORMATION ONLY Attachment A ODCM-QA-002 Revision 1 Page 8 of 8 SSES OFFSITE DOSE CALCULATION MANUAL CHANGE REQUEST
- 1. ODCM-QA-Submit a separate form for each ODCM procedure to be revised.
- 2. Describe proposed revisions to the SSES ODCM below. Include references to sections, figures, tables, parameters, and equations with sufficient detail to convey complete and correct information. If necessary, use additional pages. If proposed revision can be more clearly indicated on marked up copy(s) of the current ODCM, then attach these marked up pages to this form.
- 3. Reason for revision: include references to Condition Reports, Audit Services observations or findings, Licensing Issues, DCPs, etc., as applicable. If necessary, use additional pages.
- 4. Additional pages attached?
Number of additional pages No F1 Yes El
- 5. Requested date for implementation of revision:
Requested by:
Cost Area:
FORM ODCM-QA-002-1, Rev. 0, Page 1 of 1 (File R9-5)
Date To be completed by Environmental Services Received by:
Date: :
Expires On: \\??
-Assigned to: ????
m PROCEDURE COVER SHEET FORM NDAP-QA-0002-1, Rev. 2, Page 1 of 1
ODCM-QA-003 Revision 0 Page 2 of 25 PROCEDURE REVISION
SUMMARY
TITLE:
EFFLUENT MONITOR SETPOINTS
- 1. Section 2 of ODCM Revision 7 is reorganized in the format established by NDAP-QA-0002. No revision bars are used since the change was to the entire section.
- 2. Cover sheet, Revision Summary, and Table of Contents are added.
I Approval MWS Date see page I
ODCM-QA-003 Revision 0 Page 3 of 25
- 3. Policy statement regarding noble gas activity monitor setpoints in Section 4.1 of ODCM Revision 7 is relocated to §2 of this procedure.
- 4. Policy statements provided in Section 10 of ODCM Revision 7 pertaining to setpoints are relocated to §2 (§10.5, and §10.8) and §6.4 (§10.7) of this procedure.
- 5. Sample calculations from Appendix A of ODCM Revision 7 for determining setpoints for waterborne and airborne effluent monitors are deleted. The description of the methodology has been clarified, eliminating the need for sample calculations.
- 6. Added parameters used for determination of airborne effluent monitor setpoints as Attachment A.
- 7.
Procedural step addressing post-release evaluations for liquid releases has been added.
- 8. SDHR Service Water radiation monitor added to §6.1.4.
- 15. Added policy stating liquid effluent monitor setpoints are I
Approval MWS Date see page 1 I
ODCM-QA-003 Revision 0 Page 4 of 25 TABLE OF CONTENTS PAGE SECTION 1.0 PURPOSE 2.0 POLICY/DISCUSSION 2.1 ODCM Setpoints are Upper Limit Values 2.2 Waterborne Effluent Monitors 2.3 Airborne Effluent Monitors 2.4 Selection of Data for Determination of Dose Rate Compliance 2 5 Offgas Hydrogen Analyzers
3.0 REFERENCES
4.0 RESPONSIBILITIES 4.1 Supervisor - Chemistry 4.2 Supervisor - Operations Technology 4.3 Environmental Services - Health Physicist 5.0 DEFINITIONS 6.0 PROCEDURE 6.1 Liquid Effluent Monitoring 6.2 Airborne Effluent Monitoring - Noble Gas 6.3 Airborne Effluent Monitoring - Iodine and Particulate 6.4 Airborne Monitor Line Loss Corrections 7.0 RECORDS ATTACHMENTS A
Parameters Used to Determine Airborne Effluent Monitor Setpoints A.ITS Parameters Used to Determine Airborne Effluent Monitor Setpoints IApproval MWS Date see page I 5
5 5 5 6
7 8
8 9
9 9
9 9
10 10 16 18 22 23 PAGE 24 25 I
II
ODCM-QA-003 Revision 0 Page 5 of 25 1.0 PURPOSE This procedure discusses the methodology to be used in determining effluent monitor alarm/trip setpoints to be used to ensure compliance with the instantaneous release rate limits in Technical Specifications 3.11.1.1 and 3.11.2.1 and provides operational flexibility while giving reasonable assurance of meeting the design objectives of 10CFR50, Appendix I.
This procedure constitutes part of the SSES Offsite Dose Calculation Manual which is a licensing basis document.
2.0 POLICY/DISCUSSION 2.1 ODCM Setpoints are Upper Limit Values 2.1.1 Effluent monitor alarm/trip setpoints calculated in accordance with the ODCM shall be considered upper limit values. Higher (less conservative) setpoints shall not be used, however lower (more conservative) setpoints may be used as required to maximize the utility of the monitor.
2.2 Waterborne Effluent Monitors 2.2.1 A gross radioactivity monitor providing automatic termination of liquid effluent releases is present on the liquid radwaste effluent line. Flow rate measurement devices are also present on the liquid radwaste effluent line and the discharge line (cooling tower blowdown).
2.2.2 Precautions, limitations, and setpoints applicable to the operation of the SSES liquid effluent monitors are provided in the applicable plant procedures.
2.2.3 The liquid effluent monitor setpoints are determined in accordance with the methodology and parameters described in Section 6.1 and controlled as "field set" in accordance with applicable plant procedures.
2.2.4 Setpoint values are to be calculated to ensure that alarm and trip actions occur upon approaching the MPC limits of 10 CFR 20, Appendix B, Table II, Column 2 at the release point to the unrestricted area.
Approval MWS Date see page I
ODCM-QA-003 Revision 0 Page 6 of 25 Airborne Effluent Monitors 2.3.1 Noble gas activity monitors, iodine samplers and monitors, and particulate samplers and monitors are present on the reactor building ventilation system (Units I and 2), the turbine building ventilation system (Units I and 2), and the standby gas treatment system exhaust vents.
Effluent system flow rate and sampler flow rate are measured on all of the systems allowing the vent monitor microprocessor to calculate release rates based on measured flow rates.
2.3.2 Precautions, limitations, and setpoints applicable to the operation of the SSES airborne effluent monitors are provided in the applicable plant procedures.
2.3.3 Setpoints are conservatively established for each effluent monitor so that the instantaneous dose rates from all sources corresponding to annual dose limits in 10 CFR 20.105 for unrestricted areas will not be exceeded.
2.3.4 The general methodology for establishing plant ventilation airborne effluent monitor setpoints is based upon vent release rates derived from site-specific meteorological dispersion conditions, vent flow rates, and measured or expected radionuclide mixtures in the gaseous effluents.
The vent release rate can then be converted to vent concentrations for input as setpoints for the applicable detectors. Since the vent monitors are programmed to calculate concentrations of iodine and particulate being released based on the rate of accumulation of activity on the filters, setpoints can be established for the iodine and particulate channels.
2.3.5 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 Technical Specification 3.11.2.7 noble gas release rate limit of 330 millicurdes/second or less at the motive steam jet condenser discharge.
- Approval MWS Date see page I 2.3
ODCM-QA-003 Revision 0 Page 7 of 25 IT
.~
2.3.6 Noble gas activity monitor setpoints are established at release rates which permit some margin for corrective action to be taken before exceeding offsite dose rates corresponding to the 10 CFR 20 annual dose limits as described herein.
2.4 Selection of Data for Determination of Dose Rate Compliance 2.4.1 Airborne effluent monitor setpoints are maintained in accordance with Section 2.3, to alarm before the dose rate limits of Technical Specification 3.11.2.1 are exceeded. Station alarm response procedures contain instructions for investigation and verification of monitor alarms. Because setpoint calculations must include assumptions about the composition of the monitored effluent, a monitor high alarm does not necessarily indicate that a dose rate limit has been exceeded.
todeermie te ompine statuise of anncient.Oe-miut avrae proies adiinlifraindpnigonsthemagntudeo h
..e s
du..t........
the m
the moni.tors e
.~ed~
Mga 2.4.2 Valid 10-minute averaged data should be the primary information used to determine the compliance status of an incident. One-minute averaged data should also be reviewed if available, but they may or may not provide additional information depending on the magnitude of the release due to the manner in which the monitors update values to be stored and associated statistical considerations. Averages over a longer period should be used only when data with higher resolution is not available. Grab sample analyses should be performed whenever possible to confirm or disprove monitor data, and to provide indication of the nuclide specific composition of the effluent. When grab sample data are available which, based on vent monitor data, are indicative of the period of elevated release, dose rate calculations should be performed I Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 8 of 25 using the actual effluent mix. The determination of compliance status should not be based on monitor data alone when it is possible to collect and analyze a vent sample which will be representative of the period of elevated release.
2.5 Offgas Hydrogen Analyzers The main condenser off gas treatment system explosive monitoring system (offgas hydrogen analyzers) have setpoints to alarm at 1% and 2% hydrogen with automatic isolation occurring at 2%.
REFERENCES 3.1 TS 3.11.2.7, [Radioactive Effluents] Main Condenser 3.2 TS 3.11.1.1, [Radioactive Effluents] Liquid Effluents Concentration 3.3 TS 3.3.7.10, Radioactive Liquid Effluent Monitoring Instrumentation 3.5 TS 3.11.2.1, [Radioactive Effluents] Gaseous Effluents Dose Rate 3.6 TS 3.3.7.11, Radioactive Gaseous Effluent Monitoring Instrumentation 3.7 10 CFR 20.105, Permissible Levels of Radiation in Unrestricted Areas 3.8 10 CFR 20 Appendix B, Concentrations in Air and Water Above Natural
Background
I Approval MWS Date see page 3.0
ODCM-QA-003 Revision 0 Page 9 of 25 3.9 40CFR190, Environmental radiation protection standards for nuclear power operations 3.10 10CFR50 Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low as is Reasonably Achievable" for Radioactive Material in Light-Water Cooled Nuclear Power Reactor Effluents 3.11 NUREG-0564, Final Environmental Statement related to the operation of SSES, Units 1 and 2 3.12 EC-ENVR-1040, Evaluation of Setpoint Methodology for Airborne Iodine and Particulate Monitors 3.13 TS 3.11.2.6, [Radioactive Effluents] Explosive Mixture 3.14 1982 SSES Meteorology Report 4.0 RESPONSIBILITIES 4.1 Supervisor - Chemistr 4.1.1 Is responsible for calibrating, functionally testing, and providing alarm responses for radiological effluent monitoring equipment.
4.2 Supervisor - Operations Technology 4.2.1 Ensures adequacy and correctness of methodology used to establish setpoints.
4.3 Environmental Services - Health Physicist 4.3.1 Is responsible for development of methodology and calculations used to establish setpoints.
5.0 DEFINITIONS 5.1 Actual Tank Activity - The sum of the products of tank concentrations and volume for each isotope.
Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 10 of 25 5.2 Cs-1 37 Equivalent - Concentration equivalent of 2.OOE-05 4Ci/ml MPC for Cs-137.
5.3 MPC - Maximum Permissible Concentration as defined in IOCFR20, Appendix B.
6.0 PROCEDURE 6.1 Liquid Effluent Monitoring Chemistry shall develop procedures implementing the following requirements for Liquid Effluent Monitoring.
6.1.1 Discharge Termination Chemistry shall determine the setpoint concentration for the discharge termination, which limits the maximum concentration being released, as follows:
C7 = XZC, (Eq. 6.1-1) where:
C. =
The setpoint concentration at which the discharge would be terminated (pCi/ml).
X =
A unitless number greater than one that is chosen to prevent spurious alarms that might result from non-uniformity in the activity concentrations of the liquid discharges.
C-f,
= The concentration of isotope n in the contents of the tank to be discharged as determined by pre-release sampling and analyses.
The summation shall include gamma emitting isotopes only (including noble gases).
The setpoint concentration is based on the activity of the isotopes to which the monitor responds, i.e., gamma-emitting isotopes only. It is used to establish the radiation monitor setpoint (count rate) in units of cpm or cps.
Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 11 of 25 6.1.2 Radiation Monitor Setpoint The radiation monitor setpoint is the sum of the background count rate and the count rate equivalent of the setpoint concentration. The count rate equivalent of the setpoint concentration in units of ItCi/ml is determined by dividing the setpoint concentration by the calibration factor (jlCi/ml/cpm).
Chemistry shall determine the radiation monitor setpoint as follows:
SL c B
(Eq. 6.1-2) where:
S =
the radiation monitor setpoint (cpm)
Cy =
the setpoint concentration at which the discharge would be terminated from Eq. 6.1-1 (pLCi/ml)
K
=
the radiation monitor calibration factor (t4Ci/ml/cpm)
B
=
the background radiation level for the radiation monitor (cpm)
The alarm setpoint may be established at a suitable fraction of the setpoint for discharge termination.
6.1.3 Discharge Flow Rate Limit Determination The flow rate below which tank discharges must be maintained depends on the magnitude of the dilution required to ensure compliance with the limits of TS 3.11.1.1.
Chemistry shall establish the maximum Discharge Flow Rate using the following equation:
f F (Eq. 6.1-3) f=(Y*
c, / MPC,) - I n
where:
f
=
the maximum discharge rate from the tank (gpm).
F
=
the minimum dilution flow rate of 5000 gpm provided by the blowdown flow from the Cooling Towers and any overflow from the spray pond.
I Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 12 of 25 Y
=
a unitless number greater than X used in §6.1.1 that is chosen to ensure that the dilution flow is conservatively determined.
Cn
=
The concentration of isotope n in the contents of the tank to be discharged as determined by pre-release sampling and analyses. The summation shall include previous composite sample results for non-gamma emitting radionuclides such as H-3, P-32, Fe-55, Sr-89, and Sr-90 (1iCi/ml).
MPCn =
the maximum permissible concentration for isotope n per 10CFR20, Appendix B, Table I1, column 2 for radionuclides other than noble gases and the values in TS Table 3.11.1.1-1 for dissolved and entrained noble gases.
i Approval MWS Date see page
ODCM-QA-003 Revision 0 Page 13 of 25 N\\'\\\\
110 Selctig alus o Xand Y is a matter of experience and the expected margin needed between the activity concentration and the maximum permissible concentration.
NO\\
Selctngvalues iof X n is aattr of experienc and Nhxpce
~margin neddbetweenthe acivt conentration~dthmaiu 6.1.4 Post-Release Evaluation Chemistry shall perform post-release evaluations when the actual composite sample results for non-gamma-emitting radionuclides exceed pre-selected criteria.
6.1.5 Service Water, SDHR Service Water, and RHR Service Water The Service Water System provides screened water from the cooling tower basin for cooling plant systems and equipment. The supplemental Decay Heat Removal Service Water System (SDHR) provides decay heat removal during refueling outages when the Service Water System is shutdown. The Residual Heat Removal (RHR) Service Water System provides water from the Engineered Safeguard Service Water (ESSW) spray pond to the RHR heat exchangers. In post-accident conditions, RHR Service Water can supply water for vessel and containment flooding. The Service Water, SDHR Service Water, and RHR Service Water Systems are not normal pathways for liquid effluents. Radiation monitors are in place on these systems to provide indication of leaks across heat exchangers into the service water. The high radiation setpoints for these monitors are set at 2E-5 ý.Ci/ml Cs-137 equivalent.
Considering the gamma emitting radionuclides predominant in SSES liquid effluents. e.g., Zn-65, Co-58, Co-60, Fe-59, Mn-54 and Cr-51, use IApproval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 14 of 25 of a setpoint based on the Cs-1 37 MPC is conservative based on the following parameters:
- 1) photon abundance (85%), (0.662 MeV)
Because Service Water, SDHR Service Water, and RHR Service Water systems are not normal release pathways for liquid effluents, no credit should be taken for possible dilution scenarios. All service water should be maintained below 2E-5 ýiCi/ml Cs-137 equivalent.
In order to minimize the chance of a change in the background of a monitor masking a significant trend in monitored activity, the alarm setpoints for the Service Water, SDHR Service Water, and RHR Service Water monitors are determined as follows:
- a. When monitor background < (2E-5)/Cal. Factor:
HI RAD Setpoint = 0.5 Background + (2E-5)/Cal. Factor DOWNSCALE or LOW RAD Setpoint = 0.5 Background
- b. When monitor background>(2E-5)/Cal. Factor I Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 15 of 25 HI RAD Setpoint = Background + 0.5 (2E-5)/Cal. Factor DOWNSCALE or LOW RAD Setpoint = Background - 0.5 (2E-5)/Cal.
Factor Where:
Setpoint
=
alarm threshold value to be entered into monitor (cps for Service Water and SDHR Service Water, cpm for RHR Service Water)
Background
(2E-5)
Cal. Factor
=
monitor background at most recent background determination (cps for Service Water and SDHR Service Water, cpm for RHR Service Water)
Cs-137 Maximum Permissible Concentration (p.Ci/ml) monitor response factor per unit Cs-137 concentration determined during most recent calibration (p.Ci/ml per cps for Service Water and SDHR Service Water, pCi/ml per cpm for RHR Service Water)
The ALERT RAD setpoints for the RHR Service Water monitors are maintained at 80% of the applicable HI RAD setpoint (cpm).
Approval MWS IDate see page I
ODCM-QA-003 Revision 0 Page 16 of 25 6.2 Airborne Effluent Monitoring - Noble Gas Environmental Services shall prepare calculations implementing the following requirements for Airborne Effluent Monitoring of Noble Gas.
6.2.1 Site Limiting Release Rate - Noble Gas
- a.
Environmental Services shall determine the limiting total body and skin release rates calculated as follows:
LRQNG
- DRTE
- k DTB Ls =QNG *DRs *k Ds (Eq. 6.2-1a)
(Eq. 6.2-1b) where:
Lr
=
limiting release rate-noble gas total body (F+/-Ci/min)
=
limiting release rate-noble gas skin (l*.Ci/min)
=
total noble gas source term (Ci)
=
total body dose rate limit for the noble gas effluent (500 mrem/year) (ref. TS 3.11.2.1.a)
DRs
=
total skin dose rate limit for the noble gas effluent (3000 mrem/year) (ref. TS 3.11.2.1.a)
DTB
=
limiting total body offsite dose resulting from the noble gas source term QNG (mrem)
Approval MWS Date see page QNG DRTB
ODCM-QA-003 Revision 0 Page 17 of 25 DS
=
limiting skin offsite dose resulting from the noble gas source term QNG (mrem) k
=
units conversion factor (1 E6 ZCi/Ci) * (1 yr/365 days) * (1 day/ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) * (1 hour/ 60 minutes)
Environmental Services shall determine DTB and Ds in accordance with ODCM-QA-004 using the noble gas source term and dispersion parameters provided in Attachment A.
Note, QNG is the sum of the noble gas activities provided in Attachment A. The ratio of the annual source term to the corresponding total body and skin dose is used in the above equations. Thus, either the total annual release per unit or the total annual release for the site may be used.
6.2.2 Monitor Limiting Concentration - Noble Gas Environmental Services shall determine the limiting noble gas release rate for each vent as follows.
Lv =0.2LNG (Eq. 6.2-2)
Where:
L
=
limiting noble gas release rate per vent (pCi/min)
LNG
=
lesser of LTB and Ls from §6.2.1 (pCi/min)
Environmental Services shall determine the Noble Gas Monitor Limiting Concentration for each monitor as follows:
v (Eq. 6.2-3) where:
CNG-111-V
=
limiting noble gas concentration for vent V (..Ci/cc)
D Approval MWS Date see page 1 I I Approval MWS
ODCM-QA-003 Revision 0 Page 18 of 25 Lv
=
limiting noble gas release rate per vent from Equation 6.2-2 (ICi/min)
=
vent flow high limit for vent V (cc/min) 6.3 Airborne Effluent Monitoring - Iodine and Particulate Environmental Services shall prepare calculations implementing the following requirements for Airborne Effluent Monitoring of iodine and particulates. Note, the methodology for determining the limiting release rate and concentration for airborne iodine and particulates is evaluated in EC-ENVR-1040.
6.3.1 Site Limiting Release Rate - Iodine
- a.
Environmental Services shall determine the limiting 1-131 release rate as follows:
Q, *DRp *k DIP (Eq. 6.3-1) where:
Lf
=
provisional limiting release rate-1-131 (.lCi/min)
Q
=
total 1-131 source term (Ci)
DRIp =
dose rate limit for 1-131, tritium, and particulate effluent (1500 mrem/year maximum organ, inhalation) (ref. TS 3.11.2.1.b)
Approval MWS Date see pgage 1
ODCM-QA-003 Revision 0 Page 19 of 25 Di=
limiting (maximum) organ dose for all age groups resulting from the 1-131 source term (mrem) k
=
units conversion factor (1E6 jtCi/Ci) * (1 yr/365 days) * (1 day/ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
- (1 hour/ 60 minutes)
Environmental Services shall determine Di in accordance with ODCM-QA-004 using the iodine source term and dispersion parameters provided in Attachment A.
Note, Q1 is the 1-131 activity provided in Attachment A. The ratio of the annual source term to the corresponding organ dose is used in the above equations. Thus, either the total annual release per unit or the total annual release for the site may be used.
6.3.2 Monitor Limiting Concentration - Iodine Environmental Services shall determine the limiting 1-131 release rate for each vent as follows:
LI-v = O.2L' (Eq. 6.3-2) where:
Lv
=
limiting 1-131 release rate per vent (pCi/min)
L}
=
limiting 1-131 release rate from §6.3.1 (pCi/min)
Environmental Services shall determine the 1-131 Limiting Concentration for each monitor as follows:
I Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 20 of 25 LI-L Ci_mc*_V Fv (Eq. 6.3-3) where:
Cý.,a-v =
limiting 1-131 concentration for vent V (I+/-Ci/cc)
LI-v
=
limiting 1-131 release rate per vent from Equation 6.3-2 (jiCi/min)
Fv
=
vent flow high limit for vent V (cc/min) 6.3.3 Site Limiting Release Rate - Particulates
- a.
Environmental Service shall determine the limiting release rate for particulates as follows:
L=
- k (Eq. 6.3-4)
Dp provisional limiting release rate-particulates (l.Ci/min) total particulate source term (Ci) dose rate limit for 1-131, tritium, and particulate effluent (1500 mrem/year maximum organ, inhalation) (ref. TS 3.11.2.1.b)
Approval MWS Date see paae 1 where:
Qp
=
DRip
ODCM-QA-003 Revision 0 Page 21 of 25 Dp
=
limiting (maximum) organ dose for all age groups resulting from the source term Qp (mrem) k
=
units conversion factor (1 E6 jLCiICi) * (1 yr/365 days) * (1 day/ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) * (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />! 60 minutes)
Environmental Services shall determine Dp in accordance with ODCM-QA-004 using the particulate source term and dispersion parameters provided in Attachment A.
Note, Qp is the sum of the particulate activities provided in Attachment A. The ratio of the annual source term to the corresponding organ dose is used in the above equations. Thus, either the total annual release per unit or the total annual release for the site may be used.
6.3.4 Monitor Limiting Concentration - Particulates Environmental Services shall determine the limiting particulate release rate for each vent as follows:
LpV = 0.24L where:
LP-v=
(Eq. 6.3-5) limiting particulate release rate per vent (pCi/min)
L, limiting release rate - particulate from §6.3.3 (pCi/min)
Environmental Services shall determine the Particulates Limiting Concentration for each monitor as follows:
Cpm.-V -
L-(Eq. 6.3-6) where:
I Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 22 of 25 where:
Cp.,,,-v=
limiting particulate concentration for vent V (lCi/cc)
Lp-v
=
limiting particulate release rate per vent from Equation 6.3-5
(ýiCi/min)
Fv
=
vent flow high limit for vent V (cc/min) 6.4 Airborne Monitor Line Loss Corrections 6.4.1 Chemistry shall apply the following correction factors to monitor data and sample analysis results in order to correct for airborne effluent monitor sample line loss in accordance with station procedures:
CORRECTION FACTORS Routine Effluent Monitors Reactor Building Unit 1 Reactor Building Unit 2 Turbine Building Unit 1 Turbine Building Unit 2 Standby Gas Treatment Post-Accident Vent Monitors Turbine Building Unit 1 Turbine Building Unit 2 Standby Gas Treatment Iodine 1.5 1.5 1.6 1.6 1.5 Iodine 1.7 1.7 1.6 Particulates 3.2 3.2 3.6 3.6 3.9 Particulates 4.2 4.3 4.4 I Approval MWS Date see page 1
ODCM-QA-003 Revision 0 Page 23 of 25 7.0 RECORDS None.
odcm-qa-003(26)
I Approval MWS Date see page 1
Attachment A ODCM-QA-003 Revision 0 Page 24 of 25 PARAMETERS USED TO DETERMINE AIRBORNE EFFLUENT MONITOR SETPOINTS 1-131 1.2E-01 Cr-51 1.2E-04 Mn-54 3.6E-04 Fe-59 1.6E-04 Co-58 5.8E-05 Co-60
- 1. 1E-03 Zn-65
- 5. IE-06 0S-134
- 1. 3E-04 0S-136
- 1. 3E-03 0S-137
- 2. IE-04 Ba-140 4.2E-05 Ce-141 2.9E-05 Annual Average Dispersion Parameters (2)
Relative Concentration Decayed Relative Concentration Decayed, depleted Relative Concentration Deposition Rate 4.1 E-5 sec/m3 4.1 E-5 sec/m3 3.8E-5 sec/m3 4.2E-8 m-2 Notes:
- 1. Final Environmental Statement Table 4.4.
- 2. SSES 1982 Meteorology Report.
I Approval MWS Date see page 1 Page 1 of 1 Ar-41 2.5E+01 Kr-83m 4.OE+00 Kr-85m
- 1. 7E+03 Kr-85 2.7E+02 Kr-87 3.2E+01 Kr-88 6.6E+02 Xe-131 m
Attachment A.ITS ODCM-QA-003 Revision 0 Page 25 of 25 PARAMETERS USED TO DETERMINE AIRBORNE EFFLUENT MONITOR SETPOINTS 1-131 (2) 1.02E-O1/1.23E-01 1-133(2)
- 1. 14E+O0/1.45E+00 Cr-51 2.08E-05 Mn-54 5.52E-05 Fe-59 7.1OE-06 Co-58 7.OOE-06 Co-60 1.23E-04 Zn-65 6.53E-05 Sr-89 1.25E-05 Sr-90 1.40E-07 Nb-95 1.OOE-04 Zr-95 1.81 E-05 Ru-103 4.21 E-05 Ag-11 Om 2.40E-08 Sb-124 1.40E-06 Cs-134 7.46E-05 Cs-136 7.1OE-06 Cs-137 1.11E-04 Ba-140 2.51 E-04 Ce-141 2.91E-05 Annual Average Dispersion Parameters - Limiting Site Boundary (3)
Relative Concentration 1.46E-5 sec/mr Decayed Relative Concentration 1.46E-5 sec/m 3 Decayed, Depleted Relative Concentration 1.35E-5 sec/m 3 Deposition Rate 3.35E-8 m-2 Notes:
- 1.
Design basis "expected" gaseous effluent releases per EC-RADN-1041 (particulates with half-lives greater than 8 days)
- 2.
Use limiting case Normal Water Chemistry/Hydrogen Water Chemistry
- 3.
1973-76 Meteorological Data Updated to 1996 Land Use Survey per EC-RADN 1041 I Approval MWS Date see page 1 Page 1 of 1 Ar-41 2.60E+01 Kr-83m O.OOE+00 Kr-85m 1.10E+01 Kr-85 2.30E+02 Kr-87 1.42E+01 Kr-88 2.22E+01 Kr-89 1.47E+02 Xe-131m 1.80E+01 Xe-1 33m O.OOE+00 Xe-133 2.23E+03 Xe-135m 6.70E+02 Xe-135 9.73E+02 Xe-137 4.68E+02 Xe-138 2.10E+02