ML17286A734: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(4 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 12/31/1990
| issue date = 12/31/1990
| title = Radiological Environ Monitoring Program 1990 Annual Rept for Nuclear Plant 2. W/910426 Ltr
| title = Radiological Environ Monitoring Program 1990 Annual Rept for Nuclear Plant 2. W/910426 Ltr
| author name = BAKER J W, HOSLER A G, SORENSEN G C
| author name = Baker J, Hosler A, Sorensen G
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:ACCELERATED DI UTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9105030291 DOC.DATE: 90/12/31 NOTARIZED:
{{#Wiki_filter:ACCELERATED DI                         UTION DEMONS               TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
NO , DOCKE FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 050 397 AUTH.NAME AUTHOR AFFILIATION SORENSEN,G.C.
ACCESSION NBR:9105030291             DOC.DATE: 90/12/31   NOTARIZED: NO       ,     DOCKE FACIL:50-397   WPPSS   Nuclear Project, Unit 2, Washington Public           Powe   050   397 AUTH. NAME           AUTHOR AFFILIATION SORENSEN,G.C.       Washington Public Power Supply System BAKER,J.W.           Washington Public Power Supply Syst: em HOSLER,A.G.         Washington Public Power Supply System RECIPIENT AFFILIATION
Washington Public Power Supply System BAKER,J.W.
                                                                                          /     R RECIP.NAME                                                                           /l4q
Washington Public Power Supply Syst: em HOSLER,A.G.
Washington Public Power Supply System/R RECIP.NAME RECIPIENT AFFILIATION
/l4q  


==SUBJECT:==
==SUBJECT:==
"Radiological Environ Monitoring Program 1990 Annual Rept foE Nuclear Plant 2." W/910426 ltr.DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR g ENCL t SIZE: (7+S TITLE: Environmental Monitoring Rept (per Tech Specs)NOTES:\RECIPIENT ID CODE/NAME PD5 LA ENG,P.L.INTERNAL: ACRS NRR/DREP/PRPB11 RGN5 DRSS/RPB EXTERNAL: EG&G SIMPSON, F COPIES LTTR ENCL 3 3 1 1 1 1 2 2 1 1 2 2 RECIPIENT ID CODE/NAME PD5 PD AEO PAB G FILE 01 FILE 02 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
  "Radiological Environ Monitoring Program             1990 Annual Rept foE Nuclear Plant 2." W/910426 ltr.
A D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15 I k%a(
DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR             g ENCL   t   SIZE:     (7 +       S TITLE: Environmental Monitoring Rept (per Tech Specs)
-ii-WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~+3000 George Washington Way~Richland, Washington 99352 April 26, 1991 PS"CJC"91"034 Applicable Regulation:
NOTES:
Washington Public Power Supply System Technical Specification 6.9.1.10 uocket No.50-397 Director, Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
  \
RECIPIENT              COPIES          RECIPIENT           COPIES ID  CODE/NAME            LTTR ENCL      ID CODE/NAME       LTTR ENCL            D PD5 LA                       3    3    PD5 PD                  1      1 ENG,P.L.                     1    1                                                  D INTERNAL: ACRS                         1    1    AEO        PAB          1      1 NRR/DREP/PRPB11             2    2      G  FILE      01      1      1 RGN5     DRSS/RPB           1    1            FILE  02      1      1 EXTERNAL: EG&G SIMPSON, F               2     2     NRC PDR                 1     1 D
A D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR             15   ENCL   15


==Dear Sir:==
I k
  %a(
 
                                                -ii-WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~+ 3000 George Washington Way ~ Richland, Washington 99352 April 26,  1991                                                  Applicable Regulation:
PS"CJC"91"034                                                      Washington Public Power Supply System Technical Specification 6.9.1.10 uocket No. 50-397 Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555
 
==Dear Sir:==


==SUBJECT:==
==SUBJECT:==
1990 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT Enclosed ar e three (3)copies of the 1990 Radiological Environmental Monitor inq Program Annual report.This report fulfills the reporting requirement stated in Washington Public Power Supply System Technical Specification 6.9.1.10.If you have any questions or comments about this report, please contact Catherine J.Card at (509)377-8066.Sincerely G.C.rensen, Manager Regulatory Programs GSC/CJC/lp 10S030291 90123i PDR ADOCK 05000397 R'DR 1'~4 fI'9105030291
1990 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT Enclosed ar e three (3) copies of the 1990 Radiological Environmental Monitor inq Program Annual report.                 This report fulfills the reporting requirement stated in Washington Public Power Supply System Technical Specification 6.9.1.10.
~~~~
If you have any questions or comments                 about   this report, please contact Catherine J. Card at (509) 377-8066.
WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PLANT NUMBER 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT April 1991 Prepared By: C.J.Card Washington Public Power Supply System J.E.HcDonald Washington Public Power Supply System L.S.Schleder Washington Public Power Supply System J.D.Hartin Teledyne Isotopes-Westwood, New Jersey C.A.Hendola Teledyne Isotopes-Westwood, New Jersey Technical Speci f i cation 6,9.1.10 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PLANT NUMBER 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT April 1991 Approvals:
Sincerely G. C. rensen, Manager Regulatory Programs GSC/CJC/lp Enclosure 910S030291 PDR R
Regulatory Programs Manager WNP-2 Plant Manager WNP-2 Licensing Manager WNP-2 Health Physics/Chemistry Manager Plant Services Manager Originator:
          'DR ADOCK 90123i 05000397
2-C G,C.S ensen.W.Baker~A..Hosier J R.G.Graybeal J..Bell C..Card Pg<<r Date Date"j/>wP e I Date Date i9 9/Date P-rP-9i Date TABLE OF CONTENTS 1.0 EXECUTIVE  
 
1
~ 4
 
fI'9105030291
        ~   ~
      ~         ~
 
WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PLANT NUMBER 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT April 1991 Prepared By:       C.J. Card Washington Public Power Supply System J.E. HcDonald Washington Public Power Supply System L.S. Schleder Washington Public Power Supply System J.D. Hartin Teledyne Isotopes   Westwood, New Jersey C.A. Hendola Teledyne Isotopes Westwood,   New Jersey
 
f Technical Speci i cation 6,9.1.10 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PLANT NUMBER 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT April   1991 Approvals:
2-C Regulatory Programs Manager                                       Pg<<r G,C. S    ensen              Date WNP-2 Plant Manager
                                        .W. Baker                    Date WNP-2 Licensing Manager                                           "j/>wP e I
                                    ~A.. Hosier                  Date WNP-2 Health Physics/                                     J Chemistry Manager                 R.G. Graybeal                   Date Plant Services Manager                                              i9  9/
J.   . Bell                     Date Originator:                                                        P-rP-9i C.  . Card                    Date
 
TABLE OF CONTENTS 1.0 EXECUTIVE  


==SUMMARY==
==SUMMARY==
l-l 2.0  TERMINOLOGY                                                2-1


==2.0 TERMINOLOGY==
==3.0   INTRODUCTION==
3-1 3.1  Site Description                                      3-1 3.2  Program Background                                    3-1 3.3  Program Ob]ectives                                    3-3 4.0  PROGRAM DESCRIPTION                                        4-1 4.1  Sample Locations                                      4-1 4'  Land Use Census                                      4-1 4.3  Sampling Methods                                      4-2 4.3.1    Direct Radiation                            4-2 4.3.2    Airborne Particulate/Iodine                  4-3 4.3.3    Hater                                        4-3 4.3.4    Soil,                                        4-5 4.3.5    Shoreline Sediment                          4-5 4.3.6    Fish                                        4-5 4.3,7    Milk                                        4-6 4.3.8    Garden Produce                              4-6 4.4  Analytical Methods                                    4-7 4.4.1    Gross Beta Activity on Particulate Filters  4-7 4.4.2    Measurement of Gamma Emitters                4-7 4.4.3    Gross Beta Activity in Hater                4-8 4.4.4    Iodine-131 in Hater                          4-8 4.4.5    Tritium in Hater                            4-8 4.4.6    Strontium-89 and 90 in Hater, Milk and Soil  4-8 4.4.7    Iodine-131 in Milk                          4-9 4.5  Data Analysis Methods                                4-9 5.0  RESULTS AND DISCUSSION                                      5-1 5.1  Direct Radiation                                      5-2 5.2 Airborne Particulate/Iodine                            5-3 5.3  Hater                                                5-4 5.4  Soil                                                  5-6 5.5  Shoreline Sediment 5.6  Fish                                                  5-7 5.7  Milk                                                  5-7 5.8  Garden Produce                                        5-7 6.0  QUALITY ASSURANCE AND QUALITY CONTROL                      6-1 6.1  Quality Control For the Supply  System Environmental 6-1 TLD Program 6.2  Quality Control For the Analytical Program            6-2 6.2.1    Supply System Quality Control Activities    6-2 6.2.2    Teledyne Isotopes Quality Control Program    6-3


==3.0 INTRODUCTION==
==7.0 REFERENCES==
7-1 APPENDICES:
APPENDIX A    ROUTINE RESULTS                                    A-1 APPENDIX B    TELEDYNE ISOTOPES 1990 EPA INTERCOMPARISON RESULTS B-l APPENDIX C    SPECIAL SAMPLE RESULTS                            C-1 APPENDIX D    SAMPLE DEVIATIONS                                  D-1 DISTRIBUTION


3.1 Site Description
LIST OF TABLES 4-1    Radiological Environmental Monitoring Program Plan      4-11 4-2    REMP Sample Locations By Sector                        4-15 4-3    Distances In Miles to Nearest Points of Interest Within Five Miles of Plant 2 Containment                4-19 5-1    Radiological Environmental Monitoring Program Comparative Summary                                    5-8 5-2    Comparison of Teledyne Lower Limits of Detection With Branch Technical Position Requirements                  5-11 5-3    Radiological Environmental Monitoring Program Summary  5-13 5-4    Mean Quarterly TLD Data Summary For The Preoperational and  Operational Periods                                5-23 5-5    Annual TLD Data Summary For the Preoperational    and Operational Periods                                    5-25 5-6    1990 Mean Quarterly Versus Annual TLD Data              5-27 6-1    1990 Environmental Audit Dosimeter Results              6-7 6-2    Hanford/Columbia River Sampling Intercomparison Results 6-8 6-3    1990 Environmental Measurements Laboratory (EHL)
Quality Assessment Program Results                      6-11 6-4    Comparison of Analytical Results for 1990 Duplicate Milk and Water    Samples                              6-12 6-5    Summary  of  1990  Quality Control Data:  Blanks        6-13 6-6    Summary  of  1990  Quality Control Data:  Spikes        6-14 APPENDI X A:  ROUTINE RESULTS A-1 . 1 1990 Quarterly TLD Results                              A-1 A-1.2  1990 Annual TLD Results                                A-9 A-1.3  1990 TLD Results 'Summary                              A-11 A-2.1  Gross Beta  On Air Particulate Filters                A-12 A-2.2  Gross Beta  On Air Particulate Filters  S ummary      A-36 A-3.1  Gamma  Spectrometry of Particulate Filters              A-37 A-3.2  Gamma  Spectrometry of Particulate Filters  Summary    A-49 A-4.1  I-131 in Charcoal Cartridges                            A-50 A-4.2  I-131 in Charcoal Cartridges    Summary              A-74 A-5.1  Gross Beta in Water                                    A-75 A-5.2  Gross Beta in Water  Summary                          A-77 A-6.1  Tritium in Water                                        A-78 A-6.2  Tritium in Water  Summary                              A-80 A-7.1  Gamma Spectrometry of Water                            A-81 A-7.2  Gamma Spectrometry of Hater-Summary                    A-111 A-8.1  Gamma  Spectrometry of Soil                            A-115 A-8.2  Gamma  Spectrometry of Soil  Summary                  A-116 A-9.1  Gamma  Spectrometry of Sediment                        A-117 A-9.2  Gamma  Spectrometry of Sediment  Summary              A-118 A-10.1  Gamma  Spectrometry of Fish                            A-119 A-10.2  Gamma  Spectrometry of Fish  Summary                  A-124 A-ll,l  I-131 in Milk                                          A-125 A-11.2  I-131 in Milk  Summary                                A-128 A-12.1  Gamma Spectrometry of Milk                              A-129 A-12.2  Gamma Spectrometry of Milk  Summary                    A-146 A-13.1 Gamma Spectrometry of Root                              A-147 A-13.2  Gamma Spectrometry of Root  Summary                    A-148


===3.2 Program===
LIST OF TABLES (Continued)
Background
A-14.1 Gamma  Spectrometry of Fruit                            A-149 A-14.2 Gamma  Spectrometry of Fruit  Summary                  A-150 A-15.1 Gamma  Spectrometry of Vegetables                        A-151 A-15.2 Gamma  Spectrometry of Vegetables  Summary              A-153 APPENDIX B: TELEDYNE ISOTOPES 1990 EPA INTERCOMPARISON RESULTS B-1    1990 EPA Intercomparison Program Results                B-1 APPENDIX C:  SPECIAL SAMPLE RESULTS C-1    Results of Hater Grab Sample Composites                  C-2 C-2    Comparison  of the Air Sampling Results at  a Near-Plant Location and at Station 57                              C-5 C-3    Environmental TLD Fade Test Results                      C-6 APPENDIX D: SAMPLE DEVIATIONS D-1    1990 Sample Deviations                                  D-4


===3.3 Program===
LIST OF FIGURES 3-1      1990 Wind Frequency  Distribution in Percent  From Each Direction Relative to Plant  2                              3-3 3-2      The Monitoring Hierarchy From the Generation    of Liquid P
Ob]ectives
and Gaseous Effluents to the Measurement of    Radioactivity in the Environment                                          3 4 4-1      REHP Sampling Locations Within the 10-Mile Radius            4-20 4-2      REMP Sampling Locations Outside the 10-Mile Radius          4-21 4-3      REMP Sampling Locations in the Sunnyside/Grandview Area      4-22 4 4      Inner Circle TLD Locations                                  4-23 4-5      Near-Plant TLD Locations                                    4-24 4-6      Outlying TLD Locations Within the 10-Mile Radius            4-25 4-7      Air Sampling Locations Within the 10-Mile Radius            4-26 4-8      River/Drinking and Discharge Water Sampling Locations Within the 10-Mile Radius                                    4-27 4-9      Groundwater Sampling Locations                              4-28 4-10    Soil Sampling Locations Within the 10-Mile Radius            4-29 4-11    Sediment Sampling Locations                                  4-30 4-12    Milk Sampling Locations Within the 10-Mile Radius            4-31 5-1      Average Quarterly TLD Results For Near-Plant Locations and the Control Location (Station 9A) For the Preoper-ational Period, 1984-1989, and 1990                          5-29 5-2      Average Quarterly TLD Results For Remote Locations, and the Control Location (Station 9A) For the Preoper-ational Period, 1984-1989, and 1990                          5-30 5-3      Annual TLD Results For Near-Plant Locations and the Control Location (Station 9A) For the Preoperational Period, 1984-1989, and 1990                                  5-31 5-4      Annual TLD Results For Remote Locations and'he Control Location (Station 9A) For the Preoperational Period, 1984-1989, and 1990                                          5-32 5-5      Mean 1990  Quarterly TLD Results For Locations in  Each Meteorological Sector Compared to Preoperational    and Previous Operational Results                                5-33 5-6  ~
Quarterly  TLD Results For Station 46 and the Control Location (Station 9A) For the Period 1982-1990              5-34 5-7      Log Probability Plots of the 1990 and the 1984-1989 Quarterly TLD Results                                        5-35 5-8      Log Probability Plots of the 1990 and the 1984-1989 Annual TLD Results                                          5-36 5-9      Log Probability Plots of the Quarterly TLD Data For Near-Plant Locations (Stations 71-76) and the Control Location (Station 9A) For the Period 1982-1990              5-37 5-10    Mean Weekly 1990 Gross Beta in Air Results                  5-38 5-11    Mean Weekly Gross Beta in Air Results From 1984 to 1990      5-39 5-12    Weekly Gross Beta In Air Results For Near-Plant and Remote Sampling Locations Versus the Results For the Control Location (Station 9A)                            5-40 5-13    1990 Gross Beta in River/Drinking Water Results              5-41 5-14    Gross Beta in  River/Drinking Water  From 1984  to 1990      5-42


===4.0 PROGRAM===
LIST OF FIGURES (Continued) 0 5-15 Gross Beta in Discharge Hater Results from 1986  to 1990 5-43 5-16 1990 Gross Beta in Discharge Hater Results              5 44 5-17 1990 Tritium in'iver/Drinking Hater Results              5-45 5-18 Tritium in Discharge Water from 1986 to 1990            5-46 5-19 1990 Tritium in Discharge Hater Results                  5-47 5-20 Cesium-137 in Sediment Results from 1984 to 1990        5-48 5-21 1990 Iodine-131 in Milk Results                          5-49 6-1  Supply System Environmental TLD Preparation-Use  Cycle  6-15 6-2  Supply System TLD Evaluation                            6-16 6-3  Flow Chart For Teledyne Isotopes Samples                6-17
DESCRIPTION


===4.1 Sample===
~ o
Locations 4'Land Use Census 4.3 Sampling Methods 4.3.1 Direct Radiation 4.3.2 Airborne Particulate/Iodine
~ o


====4.3.3 Hater====
1.0  E  EC  TIVE    MM  Y The  Washington      Public Power Supply System Radiological Environmental Monitoring Program (REMP) activities during 1990 are discussed in this report. The REMP was conducted in accordance with a program plan which involves the collection of air, water, milk, soil, sediment, fish and garden produce samples on a regular basis from the region surrounding the plant.
4.3.4 Soil, 4.3.5 Shoreline Sediment 4.3.6 Fish 4.3,7 Milk 4.3.8 Garden Produce 4.4 Analytical Methods 4.4.1 Gross Beta Activity on Particulate Filters 4.4.2 Measurement of Gamma Emitters 4.4.3 Gross Beta Activity in Hater 4.4.4 Iodine-131 in Hater 4.4.5 Tritium in Hater 4.4.6 Strontium-89 and 90 in Hater, Milk and Soil 4.4.7 Iodine-131 in Milk 4.5 Data Analysis Methods 5.0 RESULTS AND DISCUSSION
In addition, direct radiation from the plant and plant effluents was measured      using thermoluminescent    dosimeters  (TLDs). The objective    of assessing      these samples and the TLDs was to determine the radiological impact,  if  any, of Plant 2 operations on the environment.
Determining whether plant operation affected the environment significantly involved comparison of samples taken in areas near the plant and in other regions which could be potentially affected by Plant 2 effluents to samples taken in an area that is highly unlikely to be affected.             In addition, a to samples taken      't comparison of the samples taken during 1990 at locations of potential impact the same location prior to plant operation and during previous periods of operation provided another mechanism for detecting changes in the environmental radioactivity that could be attributed to Plant 2 operations.       Other methods used to evaluate the REMP results and to bring the results into perspective included comparison of the 1990 results to the lower limits of detection (LLDs) determined for each radionuclide, to the preoperational averages and to the applicable State of Washington or U.S.
Nuclear Regulatory Commission investigation or reporting levels or standards.
Most of the REMP sample results during 1990 were below detection levels.
However, some analyses,        such as the determination of gross (total) beta, generated results that were above the LLD, i.e., detectable results, for nearly all samples of air and water. This was due to the low detection limit for the gross beta analysis and the abundance of naturally-occurring beta-emitting radionuclides in the environment.               Other results    above detection levels, such as cesium-137 in soil and sediment, reflected the effect of past        Hanford  activities or fallout    from past    nuclear weapons testing.
The 1990    thermoluminescent    dosimeter (TLD) results were very consistent with the 1989    results. The  average  of the quarterly TLD results for 1990 was 0.26 mR/day; this        can be compared to an average of 0.24 mR/day for the preoperational period and 0.25 mR/day for the operational period from 1984 through 1989. The techniques used to analyze the TLD results included log probability plotting, plotting the results by distance and location relative to Plant 2, and by comparison of individual TLD station results to the results of the .control station.           Inherent differences in the radiation background at individual locations accounted for variations among the TLD results.     However, no trends were evident in the TLD data that would indicate an impact from Plant 2 on the environment.


===5.1 Direct===
The  1990 RfHP data was consistent with the environmental    data observed during the previous operational and the preoperational years. Based on the extensive comparisons and evaluations performed on the data, no radiological impacts of Plant 2 operations on the environment around the plant were detected by the REMP during 1990.
Radiation 5.2 Airborne Particulate/Iodine
1-2


===5.3 Hater===
Becquerel (Bq):    One  disintegration per second.        One  picocurie (pCi) equals 0.037 becquerel.
5.4 Soil 5.5 Shoreline Sediment 5.6 Fish 5.7 Milk 5.8 Garden Produce 6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6.1 Quality Control For the Supply System Environmental TLD Program 6.2 Quality Control For the Analytical Program 6.2.1 Supply System Quality Control Activities
Blank Sample: A sample of the        same  media as the    field  sample bein'g analyzed but without the radionuclide(s)        being measured.      It  enables  correction for the inherent sample background.
Composite Sample:      A series of single collected portions (aliquots) analyzed as one sample.      The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.
Control Station:      A  background    sampling location, i.e., a location not likely to  be  affected    by  plant effluents due to its distance and/or direction from Plant 2.
Curie (Ci):    3.7  x 10    disintegrations per second.
DOH:  Hashington State Department      of Health.
Grab Sample:    A  single discrete sample drawn at      one    point in time.
Indicator Station: A sampling location that could be affected                  by  plant effluents due to its proximity and/or direction from Plant 2.
Log Probability Plotting:        A technique used to determine whether          a  set of data conforms to the log-normal distribution.
Lower Limit of Detection (LLD): Detection capability.                    The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95/. probability and a 5'/ probability of a false conclusion that a blank observation represents a "real" signal.
Hilliroentgen    (mR):    1/1000 Roentgen;    a  unit of  exposure    to  X or  gamma radiation.
NRC:  U.S. Nuclear Regulatory Commission.
Picocurie (pCi):    lx10      Curie or 2.22 disintegrations per minute.
RBIP:  Radiological Environmental Monitoring Program.
Site Certification Agreement (SCA):          The Plant  2   licensing agreement with the State of Nashington.
Spike Sample:    A sample containing      a  known  concentration    of the radio-nuclide(s) being measured.
2-1


====6.2.2 Teledyne====
Standard Deviation: A measure of the scatter  of a set of observations  (or samples) around their mean value.
Isotopes Quality Control Program
Standard Error: An estimate of the uncertainty associated  with the mean  of observation (or sample) averages.
TLD:  Thermoluminescent dosimeter; A TLD contains a phosphor which stores energy from exposure to radiation and emits that energy in the form of light when heated.
TL:  Thermoluminescence.
                                                                              ~ e 2-2


==7.0 REFERENCES==
The  Radiological Environmental Monitoring Program (REMP) for Washington Public Power Supply System Plant 2 provides for the collection and analysis of samples of various environmental media, in order to assess the radio-logical impact of plant operations.           The environmental  media routinely sampled by the REMP include air, water, milk, soil, river sediment, fish, vegetables, fruits, and root crops. Other sample media, such as vegetation and animal products (for example, eggs and meat) are also sampled under special circumstances when additional information about particular radio-nuclides is needed.        The direct radiation near the plant and at various distances from the plant is assessed through the use of thermoluminescent dosimeters.
This annual report is written to satisfy the requirements of Plant 2 Technical Specification 6.9.1.10.      The results of environmental measurements made dur,ing CY 1990 are presented      in the report. The results are discussed and interpreted by comparing them to similar measurements          made during the preoperational and previous operational periods and to the detection capa-bilities associated with the current methods of analysis. The quality assurance and quality control aspects of the program are also discussed in this report.
Washington    Public Power Supply System Plant 2 is located in a sparsely populated shrub-steppe        region within the Department of Energy-operated Hanford Site in southeastern Washington.          The plant is approximately three miles west of the Columbia River and is surrounded on all sides by uninhabited desert land.          The nearest  population centers are Richland,
'ennewick and Pasco, which are 12 miles south, 21 miles southeast, and 18 miles southeast,      respectively. The  nearest privately-owned lands are located approximately four miles ENE of the plant, across the Columbia River. Given the prevailing wind directions, shown in the 1990 wind frequency distribution in Figure 3-1, the focus of REMP sampling is this farming region across the river.
Because Plant 2 is located on the Hanford Site, other sources of radioactive effluents are in relatively close proximity to Plant 2. For this reason, sampling locations near the plant (near-plant locations) provide useful information for separating the potential environmental effects of Plant 2 from the effects of the other effluent sources on the Hanford Site.
3.2  Pr  r    Ba  r  n The  REMP  is designed    to conform to the regulatory guidance provided by Regulatory Guides 4.1'nd 4.8', including the Radiological Assessment Branch Technical Position (BTP)', while taking into account site specific characteristics.      The quality assurance      aspects of the program and the thermoluminescent dosimetry are conducted in accordance with Regulatory Guides 4.15'nd 4.135.          The REMP also must adhere to the requirements of the Site Certification Agreement (SCA)'ith the State of Washington and 3-1


APPENDICES:
the Plant 2 Technical Specifications.               These requirements cover not only the environmental sampling and sample analysis aspects of the program, but also the reporting and quality assurance aspects of the program.                                 0 The preoperational phase of the program, which extended from March 1978 to January 19, 1984, the date of "initial criticality, provided a baseline of environmental data.           Variability in the background levels of radioactivity due to differences in geologic composition, nuclear weapons test fallout, meteorological       conditions and seasonal           changes   is reflected in that preoperational     data.
APPENDIX A ROUTINE RESULTS APPENDIX B TELEDYNE ISOTOPES 1990 EPA INTERCOMPARISON RESULTS APPENDIX C SPECIAL SAMPLE RESULTS APPENDIX D SAMPLE DEVIATIONS DISTRIBUTION l-l 2-1 3-1 3-1 3-1 3-3 4-1 4-1 4-1 4-2 4-2 4-3 4-3 4-5 4-5 4-5 4-6 4-6 4-7 4-7 4-7 4-8 4-8 4-8 4-8 4-9 4-9 5-1 5-2 5-3 5-4 5-6 5-7 5-7 5-7 6-1 6-1 6-2 6-2 6-3 7-1 A-1 B-l C-1 D-1 4-1 4-2 4-3 5-1 5-2 5-3 5-4 5-5 5-6 6-1 6-2 6-3 6-4 6-5 6-6 APPENDI A-1.1 A-1.2 A-1.3 A-2.1 A-2.2 A-3.1 A-3.2 A-4.1 A-4.2 A-5.1 A-5.2 A-6.1 A-6.2 A-7.1 A-7.2 A-8.1 A-8.2 A-9.1 A-9.2 A-10.1 A-10.2 A-ll,l A-11.2 A-12.1 A-12.2 A-13.1 A-13.2 LIST OF TABLES X A: ROUTINE RESULTS 1990 Quarterly TLD Results 1990 Annual TLD Results 1990 TLD Results-'Summary Gross Beta On Air Particulate Filters Gross Beta On Air Particulate Filters-S Gamma Spectrometry of Particulate Filters Gamma Spectrometry of Particulate Filters I-131 in Charcoal Cartridges I-131 in Charcoal Cartridges
REHP   environmental         samples   have   always been analyzed       by a contract analytical     laboratory.         Since June       1986,   Teledyne Isotopes,   Inc. in Westwood, New Jersey,           has performed the analysis of REMP samples.           The thermoluminescent dosimeters used in the REHP to assess the direct radiation are processed by the Supply System External Dosimetry Laboratory under the Plant Services Department.                                 I 3.3   Pr   r m           iv The   REMP   is   the   final     stage in a series of monitoring programs that characterize     and   analyze the liquid and gaseous effluents from Plant 2.
-Summary Gross Beta in Water Gross Beta in Water-Summary Tritium in Water Tritium in Water-Summary Gamma Spectrometry of Water Gamma Spectrometry of Hater-Summary Gamma Spectrometry of Soil Gamma Spectrometry of Soil-Summary Gamma Spectrometry of Sediment Gamma Spectrometry of Sediment-Summary Gamma Spectrometry of Fish Gamma Spectrometry of Fish-Summary I-131 in Milk I-131 in Milk-Summary Gamma Spectrometry of Milk Gamma Spectrometry of Milk-Summary Gamma Spectrometry of Root Gamma Spectrometry of Root-Summary ummary-Summary Radiological Environmental Monitoring Program Plan REMP Sample Locations By Sector Distances In Miles to Nearest Points of Interest Within Five Miles of Plant 2 Containment Radiological Environmental Monitoring Program Comparative Summary Comparison of Teledyne Lower Limits of Detection With Branch Technical Position Requirements Radiological Environmental Monitoring Program Summary Mean Quarterly TLD Data Summary For The Preoperational and Operational Periods Annual TLD Data Summary For the Preoperational and Operational Periods 1990 Mean Quarterly Versus Annual TLD Data 1990 Environmental Audit Dosimeter Results Hanford/Columbia River Sampling Intercomparison Results 1990 Environmental Measurements Laboratory (EHL)Quality Assessment Program Results Comparison of Analytical Results for 1990 Duplicate Milk and Water Samples Summary of 1990 Quality Control Data: Blanks Summary of 1990 Quality Control Data: Spikes 4-11 4-15 4-19 5-8 5-11 5-13 5-23 5-25 5-27 6-7 6-8 6-11 6-12 6-13 6-14 A-1 A-9 A-11 A-12 A-36 A-37 A-49 A-50 A-74 A-75 A-77 A-78 A-80 A-81 A-111 A-115 A-116 A-117 A-118 A-119 A-124 A-125 A-128 A-129 A-146 A-147 A-148 LIST OF TABLES (Continued)
Figure 3-2 presents this monitoring hierarchy from the generation of the waste liquids and gases to the calculation of doses from these effluents and the measurement of radioactivity in the environment.
A-14.1 Gamma Spectrometry of Fruit A-14.2 Gamma Spectrometry of Fruit-Summary A-15.1 Gamma Spectrometry of Vegetables A-15.2 Gamma Spectrometry of Vegetables
The   REMP   provides       a mechanism     for determining whether the levels of radioactivity in       the plant environs are within established limits and for ensuring that the accumulation of radionuclides in the environment will not become   significant as a result of plant'perations.                       While in-plant monitoring programs are used to ensure that 10CFR20'nd 10CFRSO criteria for releases of radioactive effluents are met, the REHP provides supple-mental verification that the concentrations of radionuclides in the envi-ronment are not greater than anticipated.
-Summary APPENDIX B: TELEDYNE ISOTOPES 1990 EPA INTERCOMPARISON RESULTS B-1 1990 EPA Intercomparison Program Results APPENDIX C: SPECIAL SAMPLE RESULTS C-1 Results of Hater Grab Sample Composites C-2 Comparison of the Air Sampling Results at a Near-Plant Location and at Station 57 C-3 Environmental TLD Fade Test Results APPENDIX D: SAMPLE DEVIATIONS D-1 1990 Sample Deviations A-149 A-150 A-151 A-153 B-1 C-2 C-5 C-6 D-4 3-1 3-2 P 4-1 4-2 4-3 4 4 4-5 4-6 4-7 4-8 4-9 4-10 4-11 4-12 5-1 5-2 5-3 5-4 5-5 5-6~5-7 5-8 5-9 5-10 5-11 5-12 5-13 5-14 LIST OF FIGURES 1990 Wind Frequency Distribution in Percent From Each Direction Relative to Plant 2 The Monitoring Hierarchy From the Generation of Liquid and Gaseous Effluents to the Measurement of Radioactivity in the Environment REHP Sampling Locations Within the 10-Mile Radius REMP Sampling Locations Outside the 10-Mile Radius REMP Sampling Locations in the Sunnyside/Grandview Area Inner Circle TLD Locations Near-Plant TLD Locations Outlying TLD Locations Within the 10-Mile Radius Air Sampling Locations Within the 10-Mile Radius River/Drinking and Discharge Water Sampling Locations Within the 10-Mile Radius Groundwater Sampling Locations Soil Sampling Locations Within the 10-Mile Radius Sediment Sampling Locations Milk Sampling Locations Within the 10-Mile Radius Average Quarterly TLD Results For Near-Plant Locations and the Control Location (Station 9A)For the Preoper-ational Period, 1984-1989, and 1990 Average Quarterly TLD Results For Remote Locations, and the Control Location (Station 9A)For the Preoper-ational Period, 1984-1989, and 1990 Annual TLD Results For Near-Plant Locations and the Control Location (Station 9A)For the Preoperational Period, 1984-1989, and 1990 Annual TLD Results For Remote Locations and'he Control Location (Station 9A)For the Preoperational Period, 1984-1989, and 1990 Mean 1990 Quarterly TLD Results For Locations in Each Meteorological Sector Compared to Preoperational and Previous Operational Results Quarterly TLD Results For Station 46 and the Control Location (Station 9A)For the Period 1982-1990 Log Probability Plots of the 1990 and the 1984-1989 Quarterly TLD Results Log Probability Plots of the 1990 and the 1984-1989 Annual TLD Results Log Probability Plots of the Quarterly TLD Data For Near-Plant Locations (Stations 71-76)and the Control Location (Station 9A)For the Period 1982-1990 Mean Weekly 1990 Gross Beta in Air Results Mean Weekly Gross Beta in Air Results From 1984 to 1990 Weekly Gross Beta In Air Results For Near-Plant and Remote Sampling Locations Versus the Results For the Control Location (Station 9A)1990 Gross Beta in River/Drinking Water Results Gross Beta in River/Drinking Water From 1984 to 1990 3-3 3 4 4-20 4-21 4-22 4-23 4-24 4-25 4-26 4-27 4-28 4-29 4-30 4-31 5-29 5-30 5-31 5-32 5-33 5-34 5-35 5-36 5-37 5-38 5-39 5-40 5-41 5-42 0 5-15 5-16 5-17 5-18 5-19 5-20 5-21 6-1 6-2 6-3 LIST OF FIGURES (Continued)
Any radiological effect of Plant 2 on the environment must be distinguished from the     normal variation in background radiation levels and from the effects of other sources of radioactive effluents in the area.                         The monitoring results obtained during each year of the plant's operation are compared to the preoperational             data and to data from previous operating years, in order to determine whether a significant accumulation of plant-produced radionuclides has occurred in the environment.                     Should a significant accumulation be observed and be attributed to plant operation, steps would be taken to locate the release pathway and to prevent further releases.
Gross Beta in Discharge Hater Results from 1986 to 1990 1990 Gross Beta in Discharge Hater Results 1990 Tritium in'iver/Drinking Hater Results Tritium in Discharge Water from 1986 to 1990 1990 Tritium in Discharge Hater Results Cesium-137 in Sediment Results from 1984 to 1990 1990 Iodine-131 in Milk Results Supply System Environmental TLD Preparation-Use Cycle Supply System TLD Evaluation Flow Chart For Teledyne Isotopes Samples 5-43 5 44 5-45 5-46 5-47 5-48 5-49 6-15 6-16 6-17
3-2
~o~o 1.0 E EC TIVE MM Y The Washington Public Power Supply System Radiological Environmental Monitoring Program (REMP)activities during 1990 are discussed in this report.The REMP was conducted in accordance with a program plan which involves the collection of air, water, milk, soil, sediment, fish and garden produce samples on a regular basis from the region surrounding the plant.In addition, direct radiation from the plant and plant effluents was measured using thermoluminescent dosimeters (TLDs).The objective of assessing these samples and the TLDs was to determine the radiological impact, if any, of Plant 2 operations on the environment.
Determining whether plant operation affected the environment significantly involved comparison of samples taken in areas near the plant and in other regions which could be potentially affected by Plant 2 effluents to samples taken in an area that is highly unlikely to be affected.In addition, a comparison of the samples taken during 1990 at locations of potential impact to samples taken't the same location prior to plant operation and during previous periods of operation provided another mechanism for detecting changes in the environmental radioactivity that could be attributed to Plant 2 operations.
Other methods used to evaluate the REMP results and to bring the results into perspective included comparison of the 1990 results to the lower limits of detection (LLDs)determined for each radionuclide, to the preoperational averages and to the applicable State of Washington or U.S.Nuclear Regulatory Commission investigation or reporting levels or standards.
Most of the REMP sample results during 1990 were below detection levels.However, some analyses, such as the determination of gross (total)beta, generated results that were above the LLD, i.e., detectable results, for nearly all samples of air and water.This was due to the low detection limit for the gross beta analysis and the abundance of naturally-occurring beta-emitting radionuclides in the environment.
Other results above detection levels, such as cesium-137 in soil and sediment, reflected the effect of past Hanford activities or fallout from past nuclear weapons testing.The 1990 thermoluminescent dosimeter (TLD)results were very consistent with the 1989 results.The average of the quarterly TLD results for 1990 was 0.26 mR/day;this can be compared to an average of 0.24 mR/day for the preoperational period and 0.25 mR/day for the operational period from 1984 through 1989.The techniques used to analyze the TLD results included log probability plotting, plotting the results by distance and location relative to Plant 2, and by comparison of individual TLD station results to the results of the.control station.Inherent differences in the radiation background at individual locations accounted for variations among the TLD results.However, no trends were evident in the TLD data that would indicate an impact from Plant 2 on the environment.
The 1990 RfHP data was consistent with the environmental data observed during the previous operational and the preoperational years.Based on the extensive comparisons and evaluations performed on the data, no radiological impacts of Plant 2 operations on the environment around the plant were detected by the REMP during 1990.1-2 Becquerel (Bq): One disintegration per second.One picocurie (pCi)equals 0.037 becquerel.
Blank Sample: A sample of the same media as the field sample bein'g analyzed but without the radionuclide(s) being measured.It enables correction for the inherent sample background.
Composite Sample: A series of single collected portions (aliquots) analyzed as one sample.The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.Control Station: A background sampling location, i.e., a location not likely to be affected by plant effluents due to its distance and/or direction from Plant 2.Curie (Ci): 3.7 x 10 disintegrations per second.DOH: Hashington State Department of Health.Grab Sample: A single discrete sample drawn at one point in time.Indicator Station: A sampling location that could be affected by plant effluents due to its proximity and/or direction from Plant 2.Log Probability Plotting: A technique used to determine whether a set of data conforms to the log-normal distribution.
Lower Limit of Detection (LLD): Detection capability.
The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95/.probability and a 5'/probability of a false conclusion that a blank observation represents a"real" signal.Hilliroentgen (mR): 1/1000 Roentgen;a unit of exposure to X or gamma radiation.
NRC: U.S.Nuclear Regulatory Commission.
Picocurie (pCi): lx10 Curie or 2.22 disintegrations per minute.RBIP: Radiological Environmental Monitoring Program.Site Certification Agreement (SCA): The Plant 2 licensing agreement with the State of Nashington.
Spike Sample: A sample containing a known concentration of the radio-nuclide(s) being measured.2-1 Standard Deviation:
A measure of the scatter of a set of observations (or samples)around their mean value.Standard Error: An estimate of the uncertainty associated with the mean of observation (or sample)averages.TLD: Thermoluminescent dosimeter; A TLD contains a phosphor which stores energy from exposure to radiation and emits that energy in the form of light when heated.TL: Thermoluminescence.
~e 2-2 The Radiological Environmental Monitoring Program (REMP)for Washington Public Power Supply System Plant 2 provides for the collection and analysis of samples of various environmental media, in order to assess the radio-logical impact of plant operations.
The environmental media routinely sampled by the REMP include air, water, milk, soil, river sediment, fish, vegetables, fruits, and root crops.Other sample media, such as vegetation and animal products (for example, eggs and meat)are also sampled under special circumstances when additional information about particular radio-nuclides is needed.The direct radiation near the plant and at various distances from the plant is assessed through the use of thermoluminescent dosimeters.
This annual report is written to satisfy the requirements of Plant 2 Technical Specification 6.9.1.10.The results of environmental measurements made dur,ing CY 1990 are presented in the report.The results are discussed and interpreted by comparing them to similar measurements made during the preoperational and previous operational periods and to the detection capa-bilities associated with the current methods of analysis.The quality assurance and quality control aspects of the program are also discussed in this report.Washington Public Power Supply System Plant 2 is located in a sparsely populated shrub-steppe region within the Department of Energy-operated Hanford Site in southeastern Washington.
The plant is approximately three miles west of the Columbia River and is surrounded on all sides by uninhabited desert land.The nearest population centers are Richland,'ennewick and Pasco, which are 12 miles south, 21 miles southeast, and 18 miles southeast, respectively.
The nearest privately-owned lands are located approximately four miles ENE of the plant, across the Columbia River.Given the prevailing wind directions, shown in the 1990 wind frequency distribution in Figure 3-1, the focus of REMP sampling is this farming region across the river.Because Plant 2 is located on the Hanford Site, other sources of radioactive effluents are in relatively close proximity to Plant 2.For this reason, sampling locations near the plant (near-plant locations) provide useful information for separating the potential environmental effects of Plant 2 from the effects of the other effluent sources on the Hanford Site.3.2 Pr r Ba r nThe REMP is designed to conform to the regulatory guidance provided by Regulatory Guides 4.1'nd 4.8', including the Radiological Assessment Branch Technical Position (BTP)', while taking into account site specific characteristics.
The quality assurance aspects of the program and the thermoluminescent dosimetry are conducted in accordance with Regulatory Guides 4.15'nd 4.135.The REMP also must adhere to the requirements of the Site Certification Agreement (SCA)'ith the State of Washington and 3-1 the Plant 2 Technical Specifications.
These requirements cover not only the environmental sampling and sample analysis aspects of the program, but also the reporting and quality assurance aspects of the program.0 The preoperational phase of the program, which extended from March 1978 to January 19, 1984, the date of"initial criticality, provided a baseline of environmental data.Variability in the background levels of radioactivity due to differences in geologic composition, nuclear weapons test fallout, meteorological conditions and seasonal changes is reflected in that preoperational data.REHP environmental samples have always been analyzed by a contract analytical laboratory.
Since June 1986, Teledyne Isotopes, Inc.in Westwood, New Jersey, has performed the analysis of REMP samples.The thermoluminescent dosimeters used in the REHP to assess the direct radiation are processed by the Supply System External Dosimetry Laboratory under the Plant Services Department.
I 3.3 Pr r m iv The REMP is the final stage in a series of monitoring programs that characterize and analyze the liquid and gaseous effluents from Plant 2.Figure 3-2 presents this monitoring hierarchy from the generation of the waste liquids and gases to the calculation of doses from these effluents and the measurement of radioactivity in the environment.
The REMP provides a mechanism for determining whether the levels of radioactivity in the plant environs are within established limits and for ensuring that the accumulation of radionuclides in the environment will not become significant as a result of plant'perations.
While in-plant monitoring programs are used to ensure that 10CFR20'nd 10CFRSO criteria for releases of radioactive effluents are met, the REHP provides supple-mental verification that the concentrations of radionuclides in the envi-ronment are not greater than anticipated.
Any radiological effect of Plant 2 on the environment must be distinguished from the normal variation in background radiation levels and from the effects of other sources of radioactive effluents in the area.The monitoring results obtained during each year of the plant's operation are compared to the preoperational data and to data from previous operating years, in order to determine whether a significant accumulation of plant-produced radionuclides has occurred in the environment.
Should a significant accumulation be observed and be attributed to plant operation, steps would be taken to locate the release pathway and to prevent further releases.3-2 NW 10.3 NNW 8.2 N 7.2 NNE 4.5 WNW 8.0 NE 3.5 W 5.3 ENE 1.4 E 1.6 WSW 4.3 ESE 2.5 SE 4.8 SW 6.0 SSW 10.6 SSE 10A S 11.3 900182.1 Mar 1991 Figure 3-1 1990 WIND FREQUENCY DISTRIBUTION IN PERCENT FROM EACH DIRECTION RELATIVE TO PLANT 2 3-3 MONITORING HIERARCHY Liqu.id/Gaseous Ef fluent Generation Effluent Monitoring and Sampling Technical Specification Limits Effluent Dose Calculation and Reports Radiological Environmental Monitoring Program FIGURE 3-2 THE MONITORING HIERARCHY FROM THE GENERATION OF LIQUID AND GASEOUS EFFLUENTS TO THE MEASUREMENT OF RADIOACTIVITY TO THE ENVIRONMENT 3-4 4.0 PR RAHD I TI N The REHP plan for Plant 2 is presented in Table, 4-1.It summarizes the sample locations, collection frequency and types of analysis performed on the sample media.The methods of sampling and sampling frequencies utilized in the, program have been determined by such factors as the half-lives and major exposure pathways for the,radionuclides potentially released from the plant to the surrounding environments 4.1 i n Seventy-seven sample locations were included in the 1990 monitoring pro-gram.Seventy indicator and two control, i.e.background, locations were within 10 miles (16 kilometers) of the Plant 2 containment.
Three addi-ti'onal control stations and two indicator stations were outside the 10-mile radius from the plant.Sample stations are listed in Table 4-2 by meteoro-logical sector, sample media and approximate distance from the plant.The numbers and locations of sample stations are based not only on factors such as population distribution and meteorological conditions, but also on station accessibility, security throughout the year and the requirements of applicable regulations.
Haps of the RfHP sampling locations described in Tables 4-1 and 4-2 are presented in Figure 4-1 for sampling locations within the 10-mile radius and Figure 4-2 for sampling locations outside the 10-mile radius.A more detailed presentation of sampling locations in the Sunnyside/Grandview area is given in Figure 4-3.Haps indicating the sampling locations for each specific type of sample media are presented in Section 4.3 as Figures 4-4 through 4-12.4.2 In August the annual land use census was performed, as required by the Plant 2 Technical Specifications.'ne objective of the land use census is to identify the locations of the nearest milk animal, residence and garden greater, than 50 m'500 ft')producing broadleaf vegetation within a distance of 5 miles from the plant.Another objective is to determine whether any site located during the census has a calculated dose or dose commitment greater than the sites currently monitored for the same exposure pathway.If so, routine sampling of that dose pathway, would be initiated at that new site.The results of the 1990 land use census within 5 miles are given in Table 4-3.No milk animals are located within the 5-mile radius.The closest milk locations are at 6.4 miles SE and 7.2 miles ESE.One large garden containing broadleaf vegetation was located within 5 miles of the Plant during the 1990 land use census.Samples were not obtained at this location due to the owner's reluctance to participate in the sampling program.4-1 The collection of environmental samples for the REMP was performed according to the schedule in Table 4-1.All samples were collected by Supply System personnel.
Documented procedures contained in the Environmental Program Instruction Manual were used for sample collection and preparation.
The following sections describe the Supply System's sampling and preparation methods.~o 4.3.1 Direct Radiation, During 1990, thermoluminescent dosimeters (TLDs)were used to determine the direct radiation levels at the fifty-seven (57)monitoring locations shown in Figures 4-4, 4-5 and 4-6.No new TLD locations were added to the program this year.The TLD located at Station 9A in Sunnyside served as the con-trol, or background, TLD.The other 56 TLDs served as indicator TLDs.The environmental dosimeter consists of a card containing CaS04.Dy (251.)phosphor in a Teflon matrix.Following oven annealing at 250'C for 2 hours, the 31.75 mm x 44.75 mm x 0.4 mm thick card was loaded into a plastic case (Teledyne Model EB-2)lined with 0.58 mm copper (520 mg/cm~)to lessen the TLD's over-response to low energy photons." The TLD was prepared for the field by first wrapping the case with aluminum foil, sealing it in,two plastic bags and finally placing it in a cotton bag, which was hung from a metal post at each site.The TLDs were hung approximately three feet above the ground, Two sets of TLDs were employed at each location.One set was exchanged on a quarterly basis and the other exchanged on an annual basis.Exposure of the field TLDs during transport to the TLD sites was monitored by a set of field control, or trip control, dosimeters that accompanied the field dosimeters to and from the field locations.
Another set of TLDs was used as building control TLDs which were used to determine the exposure of the TLDs if they remained in the lead cave during the entire quarter.The TLD exposure during transport to and from the field was determined by subtracting the difference between the building control results and the trip control results.The environmental dosimeters were processed on a Teledyne Isotopes Model 9100 Automatic Reader.Following the initial processing, the field dosimeters were annealed and given a calibration exposure of 100 mR of cesium-137 gamma, in order to determine response (i.e, calibration) factors for each dosimeter.
The calibration factors were then used to determine the total exposure received by each TLD.The exposure values determined for calibration exposures, as well as the exposures of the QA dosimeters (processing control dosimeters) and audit dosimeters (spiked dosimeters), were based on the calculated field strength of the encapsulated cesium-137 source.The calculated field strength of the source was determined from National Institute of Standards and Technology (NIST)-traceable ionization chamber measurements made over a period of 4-2 several years during the routine use and calibration of the source.Ionization chamber measurements made during TLD calibration were used to confirm the calculated exposure.If the calculated exposure and the ionization chamber reading differed by 5%or more, an investigation was done , into the calibration exposure.During 1990 a special test was performed to determine whether a particular set of TLDs that had been used as annual TLDs in the past had a higher TL signal fade rate over time than the other sets of TLDs used in the program.The results of these TLDs when used in the field had indicated that this might be a problem.TLDs from the suspect group were distributed to various TLD stations and left throughout the year.Another set of TLDs which had not shown indications of signal fade were distributed to the same stations and retrieved at the same time as the suspect group.The results of this study are presented in Section 5.1 and Appendix C.Three Reuter Stokes pressurized.
ionization chambers (PICs)provide an additional capability for measuring direct radiation exposure.These units are maintained for use in special monitoring situations or as back-up moni-toring systems and are no longer part of the routine monitoring program.Solar panels provide the power sources for the units in order to prevent equipment problems and damage caused by power surges and lightning.


====4.3.2 Airborne====
NNW 8.2 NW 10.3                                  N 7.2 NNE 4.5 WNW 8.0 NE 3.5 ENE 1.4 W 5.3                                     E 1.6 ESE 2.5 WSW 4.3 SE 4.8 SW 6.0 SSE 10A SSW 10.6 900182.1 S 11.3                  Mar 1991 Figure 3-1 1990 WIND FREQUENCY DISTRIBUTION IN PERCENT    FROM EACH  DIRECTION RELATIVE TO PLANT 2 3-3
Particulate/Iodine Air particulate and air iodine (I-131)samples were obtained through the use of portable, low volume (1.5 cfm)constant flow-rate sampling units at each of twelve locations.
The samples drawn at Station 9A (Figure 4-3)were con-sidered control samples;the ones drawn at the other locations (Figure 4-7)were indicator samples.Air particulates were collected by drawing air through a 47mm-diameter glass fiber filter.Air iodine was collected by drawing air through a 57mm-diameter TEDA*-impregnated charcoal cartridge.
The particulate air filter and charcoal cartridge were placed in tandem, particulate filter first, in a holder that attached to the air inlet of the sampler unit.The sampler units were placed in ventilated metal weather-proof housings mounted on elevated platforms at each air sample location.The air sampler units were run continuously, with the filter and charcoal cartridge exchanged weekly for analysis.The total sample time for each filter and cartridge was recorded from the elapsed time indicator and the sample volume was calculated and recorded.The filters and cartridges were shipped or delivered to the analytical contr'actor within one or two days of collection.


====4.3.3 Water====
MONITORING HIERARCHY Liqu.id/Gaseous Ef fluent Generation Effluent Monitoring and Sampling Technical Specification Limits Effluent Dose Calculation and Reports Radiological Environmental Monitoring Program FIGURE  3-2 THE MONITORING HIERARCHY FROM THE GENERATION OF LIQUID AND GASEOUS EFFLUENTS TO THE MEASUREMENT OF RADIOACTIVITY TO THE ENVIRONMENT 3-4
The water sampling network consisted of seven sampling locations:
 
three for the evaluation of river/drinking water, one for the evaluation of discharge water and three for the evaluation of ground water.The locations of these sampling sites are shown in Figures 4-2 and 4-8.One river/drinking water*TEDA: Triethylene diamine 4-3 location, Station 26, was used for evaluation of the plant intake water, i.e., the river water taken upstream of the plant discharge point.This Station 26 sample can be considered a drinking water sample since the site draws its drinking water from the intake water.It is considered the river/drinking water control sample because of its upstream location.Two addi-tional locations, Stations 28 and 29, were used to evaluate the water at the two nearest drinking water locations, the Department of Energy 300 Area and the Richland Water Treatment Plant.These two stations were considered indicator stations.~o The Technical Specification requirement for a downstream water sample"near but beyond the mixing zone" was met by sampling water from Station 27, the plant discharge line to the Columbia River.This sample reflects the radioactivity present in the plant discharge prior to any river dilution, rather than the concentrations that would be found after dilution in the mixing zone.Water is drawn at this location because it was not feasible to perform the flow-proportional composite sampling required by Technical Specifications in the mixing zone area of the river downstream from the plant discharge point.This Station 27 sample is also considered an indicator sample.tl Collins Model 42 composite samplers are installed at the two drinking water locations (Stations 28 and 29)and the control location (Station 26)to periodically collect 25-ml ali'quots of water at a regular time interval.These aliquots are added to large collection bottles.At the prescribed intervals, the sampler collects, alternately, an aliquot for the sample designated for gross beta and gamma isotopic analyses and an aliquot for the sample designated for tritium analysis.A Collins Model 42-2P6 composite sampler draws samples from the discharge line (Station 27).It operates in a flow-proportional mode through a complex system that adjusts the sampling frequency relative to the flow rate in the discharge line.Prior to the start of each monthly sampling period, concentrated nitric acid was added to the large collection bottles receiving the gross beta and gamma isotopic water samples to inhibit biological growth and plateout of dis-solved ions on the bottle wall.Acid was not added to the collection bottles receiving the water samples for tritium analysis.One gallon of each of the gross beta samples was poured into a clean plastic cubitainer each month.A 250-ml cubitainer was used to hold the monthly sample sub-mitted for the quarterly tritium composite.
4.0    PR  RAHD      I TI N The  REHP plan for Plant 2 is presented      in Table, 4-1. It  summarizes the sample locations, collection frequency and types of analysis performed on the sample media. The methods of sampling and sampling frequencies utilized in the, program have been determined by such factors as the half-lives and major exposure pathways for the,radionuclides      potentially released from the plant to the surrounding environments 4.1                  i  n Seventy-seven sample locations were included in the 1990 monitoring pro-gram. Seventy indicator and two control, i.e. background, locations were within 10 miles (16 kilometers) of the Plant 2 containment. Three addi-ti'onal control stations and two indicator stations were outside the 10-mile radius from the plant. Sample stations are listed in Table 4-2 by meteoro-logical sector, sample media and approximate distance from the plant. The numbers and locations of sample stations are based not only on factors such as  population distribution and meteorological conditions, but also on station accessibility, security throughout the year and the requirements of applicable regulations.
Nonroutine analyses on the water samples include strontium-90 analysis, when the gross beta activity in the drinking water exceeds 8 pCi/liter or ten times the mean of the previous three months'ctivity for a specific loca-tion, and iodine-131 analysis, when the dose calculated for the consumption of water exceeds one mrem per year.Neither of these analyses were required during 1990.The three groundwater stations are located on Supply System property: one well on the Plant 2 site (0.1 mile north of the Reactor Building)and two wells on the WNP-1 site (1.2 miles downgradient from Plant 2).These locations are sho'wn in Figure 4-9.Water from the Plant 2 well can be used 4 4 as a backup source for drinking and fire, protection.
Haps    of the RfHP sampling locations described in Tables 4-1 and 4-2        are presented in Figure 4-1 for sampling locations within the 10-mile radius      and Figure 4-2 for sampling locations outside the 10-mile radius.              A  more detailed presentation of sampling locations in the Sunnyside/Grandview        area is given in Figure 4-3. Haps indicating the sampling locations for            each specific type of sample media are presented in Section 4.3 as Figures          4-4 through 4-12.
Water from the WNP-1 wells supplies thedrinking and fire protection water for the WNP-1 site.All three groundwater samples are considered indicator samples.Quarterly grab samples were'taken from each of these wells.One gallon was'collected from each well for gamma analysis and 250 ml was drawn for tritium analysis.The gamma analysis samples were acidified with nitric acid.The tritium samples were left unacidified.
4.2 In August the annual land use census was performed, as required by the Plant 2 Technical Specifications.'ne objective of the land use census is to identify the locations of the nearest milk animal, residence and garden greater, than 50 m'500          ft') producing broadleaf vegetation within a distance of 5 miles from the plant. Another objective is to determine whether any site located during the census has a calculated dose or dose commitment greater than the sites currently monitored for the same exposure pathway. If so, routine sampling of that dose pathway, would be initiated at that  new  site.
The  results    of the 1990 land use census within 5 miles are given in Table 4-3.      No  milk animals are located within the 5-mile radius.        The closest milk locations are at 6.4 miles SE and 7.2 miles ESE. One large garden containing broadleaf vegetation was located within 5 miles of the Plant during the 1990 land use census.      Samples were not obtained at this location due to the owner's reluctance to participate in the sampling program.
4-1
 
The  collection of environmental to the schedule personnel.
Instruction in Table 4-1.
Documented procedures samples for the REMP was performed according All  samples were collected by Supply System contained in the Environmental Program Manual were used for sample collection and preparation.                  The
                                                                                            ~ o following sections    describe    the    Supply  System's  sampling    and  preparation methods.
4.3.1    Direct Radiation, During 1990, thermoluminescent dosimeters (TLDs) were used to determine the direct radiation levels at the fifty-seven (57) monitoring locations shown in Figures 4-4, 4-5 and 4-6. No new TLD locations were added to the program this year. The TLD located at Station 9A in Sunnyside served as the con-trol, or background, TLD. The other 56 TLDs served as indicator TLDs.
The environmental    dosimeter consists of a card containing CaS04.Dy (251.)
phosphor in a Teflon matrix. Following oven annealing at 250'C for 2 hours, the 31.75 mm x 44.75 mm x 0.4 mm thick card was loaded into a plastic case TLD's over-response to low energy photons.          "
(Teledyne Model EB-2) lined with 0.58 mm copper (520 mg/cm~) to lessen the The TLD was prepared for the field by first wrapping the case with aluminum foil, sealing                    it  in,two plastic bags and finally placing          it  in a cotton bag, which was hung from a metal post at each site. The TLDs were hung approximately three feet above the ground, Two  sets of TLDs were employed at each location. One set was exchanged on a quarterly basis and the other exchanged on an annual basis. Exposure of the field TLDs during transport to the TLD sites was monitored by a set of field control, or trip control, dosimeters that accompanied the field dosimeters to and from the field locations. Another set of TLDs was used as building control TLDs which were used to determine the exposure of the TLDs if they remained in the lead cave during the entire quarter.                    The TLD exposure during transport to and from the field was determined by subtracting the difference between the building control results and the trip control results.
The    environmental    dosimeters      were    processed    on    a  Teledyne    Isotopes Model 9100 Automatic Reader.        Following the initial processing, the field dosimeters were annealed and        given a calibration exposure of 100 mR of cesium-137 gamma, in order to determine response (i.e, calibration) factors for each dosimeter. The calibration factors were then used to determine the total exposure received by each TLD.
The  exposure values determined      for calibration exposures,        as  well  as  the exposures of the QA dosimeters          (processing    control dosimeters) and audit dosimeters (spiked dosimeters), were based on the calculated field strength of the encapsulated cesium-137 source. The calculated field strength of the source  was  determined  from National      Institute of    Standards and Technology (NIST)-traceable    ionization    chamber    measurements    made over a period of 4-2
 
several  years  during  the  routine    use  and    calibration of the      source.
Ionization  chamber  measurements  made  during    TLD  calibration were  used to confirm the    calculated exposure.        If  the    calculated exposure    and the ionization chamber reading differed      by  5%  or more, an investigation    was done into the calibration exposure.
During 1990 a special test was performed to determine whether a particular set of TLDs that had been used as annual TLDs in the past had a higher TL signal fade rate over time than the other sets of TLDs used in the program.
The results of these TLDs when used in the field had indicated that this might be a problem. TLDs from the suspect group were distributed to various TLD stations and left throughout the year.            Another set of TLDs which had not shown indications of signal fade were distributed to the same stations and retrieved at the same time as the suspect group.              The results of this study are presented in Section 5.1 and Appendix C.
Three  Reuter Stokes pressurized.        ionization chambers (PICs) provide an additional capability for measuring direct radiation exposure. These units are maintained for use in special monitoring situations or as back-up moni-toring systems and are no longer part of the routine monitoring program.
Solar panels provide the power sources for the units in order to prevent equipment problems and damage caused by power surges and          lightning.
4.3.2  Airborne Particulate/Iodine Air particulate and air iodine (I-131) samples were obtained through the use of portable, low volume (1.5 cfm) constant flow-rate sampling units at each of twelve locations. The samples drawn at Station 9A (Figure 4-3) were con-sidered control samples;    the ones drawn at the other locations (Figure 4-7) were indicator samples.        Air particulates were collected by drawing air through a 47mm-diameter glass fiber filter. Air iodine was collected by drawing air through a 57mm-diameter TEDA*-impregnated charcoal cartridge.
The particulate air filter and charcoal cartridge were placed in tandem, particulate filter first, in a holder that attached to the air inlet of the sampler unit. The sampler units were placed in ventilated metal weather-proof housings mounted on elevated platforms at each air sample location.
The  air sampler units were run continuously, with the filter and charcoal cartridge exchanged weekly for analysis.            The total sample time for each filter and cartridge was recorded from the elapsed time indicator and the sample volume was calculated and recorded.            The filters and cartridges were shipped or delivered to the analytical contr'actor within one or two days of collection.
4.3.3  Water The water sampling network consisted of seven sampling locations: three for the evaluation of river/drinking water, one for the evaluation of discharge water and three for the evaluation of ground water. The locations of these sampling sites are shown in Figures 4-2 and 4-8. One river/drinking water
  *TEDA:   Triethylene diamine 4-3
 
location, Station 26,   was   used for evaluation of the plant intake water, i.e., the river water taken upstream of the plant discharge point. This Station 26 sample can be considered a drinking water sample since the site draws its drinking water from the intake water. It is considered the river/
drinking water control sample because of its upstream location. Two addi-tional locations, Stations 28 and 29, were used to evaluate the water at the
                                                                              ~ o two nearest drinking water locations, the Department of Energy 300 Area and the Richland Water Treatment Plant.       These two stations were considered indicator stations.
The Technical Specification requirement for a downstream water sample "near but beyond the mixing zone" was met by sampling water from Station 27, the plant discharge line to the Columbia River. This sample reflects the radioactivity present in the plant discharge prior to any river dilution, rather than the concentrations that would be found after dilution in the mixing zone. Water is drawn at this location because   it was not feasible to perform the flow-proportional composite sampling required by Technical Specifications in the mixing zone area of the river downstream from the plant discharge point. This Station 27 sample is also considered an indicator sample.
tl Collins Model 42 composite samplers are installed at the two drinking water locations (Stations 28 and 29) and the control location (Station 26) to periodically collect 25-ml ali'quots of water at a regular time interval.
These aliquots are added to large collection bottles.       At the prescribed intervals, the sampler collects, alternately, an aliquot for the sample designated for gross beta and gamma isotopic analyses and an aliquot for the sample designated for tritium analysis.     A Collins Model 42-2P6 composite sampler draws samples from the discharge line (Station 27). It operates in a flow-proportional mode through a complex system that adjusts the sampling frequency relative to the flow rate in the discharge line.
Prior to the start of each monthly sampling period, concentrated nitric acid was added to the large collection bottles receiving the gross beta and gamma isotopic water samples to inhibit biological growth and plateout of dis-solved ions on the bottle wall. Acid was not added to the collection bottles receiving the water samples for tritium analysis. One gallon of each of the gross beta samples was poured into a clean plastic cubitainer each month. A 250-ml cubitainer was used to hold the monthly sample sub-mitted for the quarterly tritium composite.
Nonroutine analyses on the water samples include strontium-90 analysis, when the gross beta activity in the drinking water exceeds 8 pCi/liter or ten times the mean of the previous three months'ctivity for a specific loca-tion, and iodine-131 analysis, when the dose calculated for the consumption of water exceeds one mrem per year. Neither of these analyses were required during 1990.
The three groundwater stations are located on Supply System property:     one well on the Plant 2 site (0.1 mile north of the Reactor Building) and two wells on the WNP-1 site (1.2 miles downgradient from Plant 2). These locations are sho'wn in Figure 4-9. Water from the Plant 2 well can be used 4 4
 
as a   backup   source   for drinking   and fire, protection. Water from the   WNP-1 wells supplies the drinking and fire protection water for the                 WNP-1 site.
All three groundwater samples are considered indicator samples.
Quarterly grab samples were 'taken from each of these wells. One gallon was
'collected from       each well for gamma analysis and 250 ml was drawn for tritium analysis. The gamma analysis samples were acidified with nitric acid. The tritium     samples   were left unacidified.
All the routine water samples were shipped to the analytical contractor within one to two days of collection.
All the routine water samples were shipped to the analytical contractor within one to two days of collection.
4.3.4 Soil Soil samples were collected once during 1990, as required by the Site Certification Agreement.
4.3.4     Soil Soil   samples     were   collected   once during 1990, as required by the Site Certification       Agreement.     Samples   were   taken from the four indicator locations     (Stations 1, 7,     21 and 23) shown in Figure 4-10.         One sample was taken at the control location, Station 9A (Figure 4-3).                   Each sample was taken from an area of approximately one square foot and a depth of approxi-mately one inch. Approximately two kilograms of soil were used in each sample.     Soil samples were shipped to the analytical contractor within ten working days after collection and analyzed for gamma activity.
Samples were taken from the four indicator locations (Stations 1, 7, 21 and 23)shown in Figure 4-10.One sample was taken at the control location, Station 9A (Figure 4-3).Each sample was taken from an area of approximately one square foot and a depth of approxi-mately one inch.Approximately two kilograms of soil were used in each sample.Soil samples were shipped to the analytical contractor within ten working days after collection and analyzed for gamma activity.If the gamma isotopic analysis indicated that cesium levels in any of the indicator samples exceeded ten (10)times the level in the control sample, a strontium analysis would have been performed on the sample(s).
If   the   gamma   isotopic analysis     indicated that cesium levels in any of the indicator     samples   exceeded ten (10) times the level in the control sample, a strontium analysis would have been performed on the sample(s). During 1990, no strontium analyses were required.
During 1990, no strontium analyses were required.4.3.5 Shoreline Sediment Two shoreline sediment samples were collected twice during 1990 in accor-dance with the routine sampling schedule.The upstream sediment sample (Station 33)was collected from a location approximately two miles up the Columbia River from the plant discharge point.The downstream sample location (Station 34)was collected from a location approximately one mile downstream of the discharge point (Figure 4-11).Samples were scooped from under water near the river shoreline.
4.3.5     Shoreline Sediment Two   shoreline sediment samples were collected twice during 1990 in accor-dance   with the routine sampling schedule.               The upstream sediment     sample (Station 33) was collected from a location approximately two miles up the Columbia River from the plant discharge point.                   The downstream     sample location (Station 34) was collected from a location approximately one mile downstream of the discharge point (Figure 4-11).               Samples were scooped from under water near the river shoreline.               Each sample consisted of approxi-mately two kilograms of the shallow surface sediment.                   The samples were placed in clean plastic bags and shipped to the analytical contractor within a day or two of collection.
Each sample consisted of approxi-mately two kilograms of the shallow surface sediment.The samples were placed in clean plastic bags and shipped to the analytical contractor within a day or two of collection.
4.3.6     Fish Fish sampling was performed during Hay and October, when the likelihood of obtaining anadromous* species was high. Fish samples collected from the Columbia River (Station 30 in Figure 4-1) were indicator samples, while the fish collected on the Snake River (Stations 38 and 38A in Figure 4-2) were control samples.
4.3.6 Fish Fish sampling was performed during Hay and October, when the likelihood of obtaining anadromous*
*Fish, such     as salmonids, which ascend rivers from the sea       for breeding.
species was high.Fish samples collected from the Columbia River (Station 30 in Figure 4-1)were indicator samples, while the fish collected on the Snake River (Stations 38 and 38A in Figure 4-2)were control samples.*Fish, such as salmonids, which ascend rivers from the sea for breeding.4-5 Four separate fish samples, consisting of an anadromous species and three other species generally considered edible or potentially edible (such as carp, catfish and whitefish), were collected at each location.Most of the fish were collected through the use of electro-shock, but samples of the anadromous species were also collected from the Lyons Ferry Fish Hatchery on the Snake River.The fish were filleted to obtain one kilogram of edible flesh per sample.The fillets were placed in clean plastic bags,, frozen until shipment to the analytical contractor.
4-5
Fish samples were Shipped within 14 days of collection.
 
~o 3.3.7 Mi lk Milk samples were collected monthly during January, February, March," October, November and December and semimonthly during the remaining six months when the cows were likely to be grazing.One gallon of raw milk was collected from each sampling location.The milk samples were chilled thoroughly and shipped to the analytical contractor within a day of collection.
Four separate fish samples, consisting of an anadromous species and three other species generally considered edible or potentially edible (such as carp, catfish and whitefish), were collected at each location. Most of the fish were collected through the use of electro-shock, but samples of the anadromous species were also collected from the Lyons Ferry Fish Hatchery on the Snake River. The fish were filleted to obtain one kilogram of edible
Routine samples were collected from five indicator locations (Stations 36, 40, 59, 62 and 63)across the Columbia River in Franklin County, as shown in Figure 4-12.Milk samples were taken from Stations 40, 62 and 63 during only a part of 1990.Station 40 discontinued milk production in April, so Station 62, the Howard farm, (10.9 miles SE), was added., In July, milk sampling began at the Herr farm, Station 63, which is located at 6.4 miles SE.Addition of this sample was necessary to meet Technical Specification requirements for three milk sampling locations within 5 kilometers (9.9 miles)'rom the plant.Samples were also collected at one indicator station (Station 9B)and one control location (Station 96)in the Sunnyside/
                                                                                    ~ o flesh per sample. The fillets were placed in clean plastic bags,, frozen until shipment to the analytical contractor. Fish samples were Shipped within   14 days   of collection.
Grandview area (in Figure 3-3).Station 9B in Grandview continued to serve as an indicator station in 1990 because a portion of the feed for the cows at that location is hay from the north Pasco area of Franklin County.That factor makes it unsuitable for use as a control location.~e 4.3.8 Garden Produce Samples of local garden produce were collected monthly from April to September, when the produce was readily available.
: 3. 3. 7 Mi lk Milk samples         were collected monthly during January,       February, March,"
Nhen possible, three types of produce samples-a root crop, frui't and a leafy vegetable-were collected at each location.The indicator samples were collected from a region in a predominant downwind direction (Station 37 in Figure 4-2)where crops are irrigated with Columbia River water.The control samples were obtained from produce stands.in the Sunnyside area (Station 9C in Figure 4-3), the direction least likely to be affected by plant effluents.
October,     November and December and semimonthly during the remaining six months when the cows were likely to be grazing.         One gallon of raw milk was collected from each sampling location.           The milk samples     were chilled thoroughly and shipped to the analytical contractor within a day of collection.
In addition, apples were collected in August from Station 91, the Rio Vista Farms orchard, which is irrigated with Columbia River water and cherries were collected in June from Station 61, the Haymaker farm.These produce samples were shipped to the analytical contractor within one to two days of collection.
Routine samples were collected from five indicator locations (Stations 36, 40, 59, 62 and 63) across the Columbia River in Franklin County, as shown in Figure 4-12. Milk samples were taken from Stations 40, 62 and 63 during only a part of 1990. Station 40 discontinued milk production in April, so Station 62, the Howard farm, ( 10.9 miles SE), was added., In July, milk sampling began at the Herr farm, Station 63, which is located at 6.4 miles SE. Addition of this sample was necessary to meet Technical Specification requirements for three milk sampling locations within 5 kilometers (9.9 miles)'rom the plant.
4-6 4.4 Anal i 1 P The analytical procedures used for the 1990 REMP samples are described e below.Teledyne Isotopes performed al 1 analyses of REHP samples during 1990."4.4.1 Gross Beta Activity on Particulate Filters The particulate filters were counted in a gas-flow.proportional counter after a delay of five or more days to allow for the radon-222 and radon-220 (thoron)daughter products to decay.An unused air particulate filter was counted as the blank with each weekly set of filters.4.4.2 Measurement of Gamma Emitters~il~a~nW~r A 1-liter Harinelli beaker was filled with a representative aliquot of the sample.The sample was then counted for at least 1000 minutes (16.7 hours)with a shielded Ge(Li)detector.WFZhhZ<t As much of the edible portion of the sample as possible was loaded into a tared Marinelli beaker and weighed.The sample was then counted for at least 1000 minutes (16.7 hours)with a shielded Ge(Li)detector.il n imen A large quantity of the sample was dried at a temperature below 100'C.As much sample as possible was loaded into a tared 1-liter Marinelli beaker and weighed.The sample was then counted for at least 360 minutes (6 hours)with a shielded.Ge(Li)detector.h al ar r r I din~Charcoal filters were counted up to five at a time, with one positioned on the face of a Ge(Li)detector and up to four on the side of the Ge(Li)detector.Each Ge(Li)detector was calibrated for both positions.
Samples     were also collected at one indicator station (Station 9B) and one
The detection limit for iodine-131 on each charcoal cartridge was determined (assuming no positive iodine-131) uniquely from the volume of air which passed through it.In the event that iodine-131 would have been observed in the initial counting of a set,, each charcoal cartridge in the set was then positioned separately on the face of the detector and counted.r i 1 Fil er Four air particulate filters for a quarterly composite for each field station were aligned one in front of another and then counted for at least 360 minutes (6 hours)with a shielded Ge(Li)detector.The shielded Ge(Li)detector was coupled to a mini-computer-based data acquisition system which performed pulse height analysis.A mini-computer software program defined peaks by certain changes in the slope of the spectrum.The program also compared the energy of each peak with a library of peaks for isotope identification and then performed the radioactivity calculation using the appropriate fractional gamma ray abundance, half-life, detector efficiency, and net counts in the peak region.  
                                                                                    ~ e control     location (Station 96) in the Sunnyside/ Grandview area (in Figure 3-3). Station 9B in Grandview continued to serve as an indicator station in 1990 because a portion of the feed for the cows at that location is hay from the north Pasco area of Franklin County. That factor makes it unsuitable for use as a control location.
4.3.8   Garden Produce Samples     of local     garden produce were collected monthly from April to September,     when   the produce was readily available. Nhen possible,   three types   of   produce   samples a root crop, frui't and   a leafy vegetable were collected at each location. The indicator samples were collected from a region in a predominant downwind direction (Station 37 in Figure 4-2) where crops are irrigated with Columbia River water.           The control samples were obtained from produce stands .in the Sunnyside area (Station 9C in Figure 4-3), the direction least likely to be affected by plant effluents.
In addition, apples were collected in August from Station 91, the Rio Vista Farms orchard, which is irrigated with Columbia River water and cherries were collected in June from Station 61, the Haymaker farm.             These produce samples were shipped to the analytical contractor within one to two days of collection.
4-6
 
4.4   Anal       i     1 P The   analytical         procedures used for the 1990         REMP   samples are described e below.     Teledyne Isotopes performed al analyses  1         of REHP samples during 1990.
  "4.4.1     Gross Beta       Activity on Particulate Filters The   particulate filters             were   counted   in a gas-flow. proportional counter after   a delay of five or           more days   to allow for the radon-222 and radon-220 (thoron) daughter products to decay. An unused air particulate filter was counted as the blank with each weekly set of filters.
4.4.2     Measurement       of Gamma   Emitters
  ~il~a~nW~r A 1-liter Harinelli           beaker was filled with a representative aliquot of the sample.       The     sample   was then counted for at least 1000 minutes (16.7 hours) with a   shielded Ge(Li) detector.
WFZhhZ<t As much     of the edible portion of the sample as possible was loaded into a tared Marinelli beaker and weighed.                   The sample was then counted for at least 1000 minutes (16.7 hours) with a shielded Ge(Li) detector.
il     n         imen A large quantity of the sample was dried at a temperature below 100'C. As much sample as possible was loaded into a tared 1-liter Marinelli beaker and weighed.       The sample was then counted for at least 360 minutes (6 hours) with a shielded. Ge(Li) detector.
h     al     ar r               r I din~
Charcoal     filters     were counted     up to five at a time, with one positioned on the face       of   a   Ge(Li) detector and up to four on the side of the Ge(Li) detector.         Each Ge(Li) detector was calibrated for both positions.               The detection limit for iodine-131 on each charcoal cartridge was determined (assuming no positive iodine-131) uniquely from the volume of air which passed through it. In the event that iodine-131 would have been observed in the initial counting of a set,, each charcoal cartridge in the set was then positioned separately on the face of the detector and counted.
r   i   1       Fil er Four   air particulate filters for a quarterly                   composite for each field station were aligned one in front of another and                   then counted for at least 360 minutes       (6 hours) with     a shielded Ge(Li) detector.
The   shielded Ge(Li) detector was coupled to a mini-computer-based data acquisition system which performed pulse height analysis. A mini-computer software program defined peaks by certain changes in the slope of the spectrum.       The program also compared the energy of each peak with a library of peaks for isotope identification and then performed the radioactivity calculation using the appropriate fractional gamma ray abundance, half-life, detector efficiency, and net counts in the peak region.
 
4.4.3    Gross Beta    Activity in    Hater One  liter a stainless then counted of each steel sample was evaporated to a small volume and transferred to planchet. The sample was dried under heat lamps, cooled, on an automatic beta proportional counter.
calculated using empirical self-absorption The results were curves which enabled    the correc-
                                                                                          ~ s tion of effective counting efficiency,          based on the sample residue mass.
4.4.4    Iodine-131 in Water Two  liters of    sample  were  first equilibrated with stable iodide carrier.        A batch treatment with anion exchange resin was used to remove iodine from the sample. The iodine was then stripped from the resin with sodium hypo-chlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free iodine.                It  was then back-extracted    as iodide into sodium        bisulfite solution    and  precipitated as palladium iodide.
The precipitate was weighed for chemical yield and mounted on a nylon planchet for low level beta counting. The chemical yield was corrected by measuring the stable iodide content of the water with a specific ion electrode.      During 1990, this procedure was used only on intercomparison samples, since the doses calculated via ODCM methodology for the consumption of drinking water did not exceed          1 mrem per year (Table 4-1, footnote n).
4.4.5    Tritium in Hater Approximately two milliliters of water were converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 400 C.          The hydrogen was loaded into a one-liter proportional detector and the volume was determined by recording the pressure.                      The
                                                                                          ~ o proportional detector was passively shielded by lead and steel and an electronic, anti-coincidence system provided additional shielding from cosmic rays.
4.4.6    Strontium-89 and      90  in Hater, Milk and Soil During 1990,      strontium analyses      were  not required    for  any routine REMP samples.      They    were  used  for intercomparison      samples  so the analytical techniques are described below.
Hai~r Stable strontium carrier was added to one liter of sample and the volume was reduced by evaporation.          Strontium was precipitated as Sr(NO,), using nitric acid.
Milk Stable strontium carrier was added to one liter of sample.                  The sample was then evaporated and ashed in a muffle furnace.                The ash was dissolved and strontium was precipitated as a phosphate.                It was then redissolved and strontium was precipitated as Sr(NO,)~ using fuming (901) nitric acid.
4-8
 
The    sample    was  first dried under heat lamps and a 10-gram aliquot was taken.      Stable    strontium carrier was added and the sample was leached in hydrochloric acid. The mixture was filtered. Phosphates were then pre-cipitated, collected by filtration and dissolved in nitric acid. Strontium was precipitated as Sr(NO,), using fuming nitric acid.                  A barium chromate scavenge      and an iron (ferric hydroxide) scavenge              were then performed.
Stable yttrium carrier was added and the sample was allowed to stand for 5 days or more for yttrium ingrowth.                  Yttrium was then precipitated as hydroxide, dissolved and reprecipitated as oxalate. The yttrium oxalate was mounted on a nylon planchet and counted in a low-level beta counter to infer strontium-90 activity. Strontium-89 activity was determined by precipitat-ing SrCO, from the sample after yttrium separation.                  This precipitate was mounted on a nylon planchet and covered with an 80 mg/cm'luminum absorber for low-level beta counting.
4..4.7    Iodine-131 in Milk Two  liters of      sample were    first equilibrated with stable iodide carrier.          A batch treatment with anion exchange resin was used to remove iodine from the sample.      The iodine was then stripped from the resin with sodium hypo-chlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free iodine.                It was then back-extracted        as iodide into sodium          bisulfite solution    and  precipitated as palladium iodide.
The precipitate was weighed for chemical yield and mounted on a nylon planchet for low-level beta counting. The chemical yield was corrected by measuring the stable iodide content of the milk with a specific )on electrode.
4.5    D        n  1      M Since    mid-1984, the results of the REMP analyses have been given as net results calculated from the gross or total counts determined for each radionuclide minus the background counts of the counting or detection instrument. Consequently, for several sample types, the results range from negative to positive numbers.            This manner of presenting environmental data prevents the bias and loss of individual results inherent in the use of "less than" (<) values, where the "less than" numbers can have a variety of meanings, such as "less than the lower limit of detection (LLD)" or "less than the two sigma uncertainty."
The    net results for REMP samples are presented              with  an    asterisk    (*) in front,    if  the results are less than the LLD. A          listing of    the LLDs deter-mined for each analysis is provided in Section                  5.0 as    a  reference  when reviewing the sample results.
Plots of the sample results versus            time are used to represent the results for    analyses such as gross beta on air particulate filters, where the results are normally above the lower limits of detection'n such cases, the indicator station results are plotted with the control station results 4-9
 
for  easy  comparison.      Other data  analysis  techniques, such as log proba-bility plotting    and  plotting the  moving average,  are also used to represent the data and to determine        whether trends  that could be attributed to the    ~
effect of Plant    2  operations are evident.
Thermoluminescent dosimeter (TLD) data is presented in terms of the net mR/day  exposure rate.        These results are determined from the total mR exposure calculated for each TLD from its total thermoluminescent output minus the TLD background, minus any transit (or trip) exposure received during distribution and retrieval, and divided by the number of days the TLD was in the field.        Log probability plots and graphs of TLD data by meteoro-logical sector and distance from the plant are used to interpret trends in the results.
TLD  data summaries      include the term "standard error," along with "standard deviation."    The    standard  error, which is the estimate of the precision of.
the mean, is used for mean annual summaries of mean quarterly data.              The standard deviation is used for the TLD data involving a single dosimeter result that has been determined from the four reader areas of the TLD. Both terms simply provide an indicator of the uncertainty associated with the results.
4-10
 
TABLE 4-1 RAD        A    NV R  MNTA  H        I  P  RHPA SAMPLING AND          TYPE AND FREQUENCY
( )
AMPLE TYP              AHPL    TAT  N  N              T N FR    N Y            ANA
: 1. AIRBORNE Particulates and radioiodine (6/12) 1, 4-+, 21, 23, 40, 48, and 57 Continuous sampling; weekly collection P    i  1:
gross be)a        ;
Heck 1 y gamma isotopic'e) of quarterly composite (by location)
                                                                                ~I~1.:    Heekl y gamma analysis.
Sol 1
(") (0/5)        M,  1, 7,  21 and 23      Annually                  Gamma  isotop(c strontium-90 g
: 2. DIRECT RADIATION TLD  " (34/57)        l-M, 10-25, 40-47,        Quarterly, annually        Thermoluminescent out-49-51, 53-56, 6]                                      put; quarterly      and 71-86 (1S-16S) ~                                      annual processing.
PIC(j) (0/3)          1, 21, and 23              Continuous recording      Accumulated on mag as needed                  card and internal memory.
: 3. HATERBORNE Surface/              Z5, 27, 28 and 29          Composite aliquots    ;  Gamma  isotopic, Drinking Hater "                                  monthly collection      =
gross beta, quarterly; (3/4)                                                                        tritium comp~site; s tronti um-$ 0 1 od1ne-131  ~ n)
 
TABLE 4-1  (Cont.)
RAOI            NV    N  T      NI T  I    P SAHPLING AND        TYPE ANO FREQUENCY
( )
AHP E TYP                  HP    TAT      N                    N  FR    Y          F ANA -Y I Ground Hater    (2/3)      31, 32, and 52              Quarterly                  Gamma  isotopic quarterly tritium grab sample Sediment from              33 and 34                  Semiannually              Gamma  isotopic shoreline (1/2)
: 4. INGESTION Hl k 1      (4/6)            9B, 36, 40,                Semimonthly during        Gamma  isotopic 59~ 52, 63 and              grazing season,            iodine-131;
                                ~fp)                        monthly at other times    strontium-90    q Fish      (2/2)            30 and 35                  Semiannually              Gamma  isotopic Garden Produce      (1/3)  K,  91    and 37          Monthly during growing    Gamma  isotopic season in the Riverview area of Pasco and a control near Grandview; annual  collection at Station 91.
The fraction in parentheses  for  each sample type indicates the    ratio of  Technical Specification-required sample locations to the total        number of sample  locations currently being monitored in the surveillance program.
The underlined sample location designates      a control station. None  of the groundwater stations are control locations.
Deviations are permitted  if samples are unobtainable due to hazardous conditions, seasonal availability, malfunction of    automatic sampling equipment, or other legitimate reasons . Such devia-tions are documented in Appendix D.
 
TABLE 4-1  (Cont.)
Particulate sample    filters will be  analyzed  for gross beta after at least    24 to 48 hours to allow for the decay of    radon daughter products. If gross beta activity is greater than 10 times the mean  of  the  result for  the control, Station 9A, gamma isotopic analysis shall be performed on the individual sample.
Gamma isotopic means identification and quantification of gamma-emitting radionuclides that may be  attributable to the effluents of Plant 2.
      " Soil samples are collected to satisfy the requirements of the Site Certification Agreement (SCA)    for Plant 2.
g'Strontium-90 analysis shall be performed on any indicator soil sample having cesium results greater than ten times the results for the control location.
      "  TLD refers to thermoluminescent dosimeter.      For purposes  of the REMP, a TLD is a phosphor card (31.75mm x 44.75mm x 0.4mm) with eight individual read-out        areas (four main dosimeter areas and four back-up dosimeter areas) in each badge case. TLDs used in          the REMP meet the requirements of Regulatory Guide 4.13'nd ANSI N545-1975', except for specified          energy-dependence response.
Correction factors are available for energy ranges with response        outside of the specified tolerances.
        'LD Stations 71-86 are special interest stations and are not included among the 34 routine TLD  stations required by the Plant Technical Specification Table 3.12-1. Their alternate designations are 1S-16S. St'ation 61 is also a special interest location. It was added to the program during the third quarter of 1989.
3  Pressurized  ion chambers (PICs) are no longer required as part of the routine monitoring program. They are used  only as a supplemental or backup system.
The term  "river/drinking water," instead of "surface/drinking water", is      used throughout this report    because  the surface water is taken from the Columbia River. Station 26, Plant 2 makeup water intake from the Columbia River is both an upstream surface, or river, water sample and the drinking water control sample location. Station 28 (300 Area) and Station 29 samples are drinking water samples. The Station 27 sample, which is drawn from the plant discharge line, is taken in place of a "downstream" water sample near but beyond the mixing zone.          It reflects the radioactivity present in the plant discharge prior to any river dilution.
Composite (integrated grab) samples are collected with equipment which collects        an aliquot at time intervals that are short relative to the compositing period.
 
TABLE 4-1  (Cont.)
(m) Nhen the gross  beta  activity in drinking water exceeds  8 pCi/liter,  a strontium-90 analysis is performed.
(n) Nhen the dose calculated via ODCM methodology for consumption oF water exceeds    1 mrem per year, iodine-131 analyses are performed on the drinking water samples.
(o) Milk samples will be obtained from farms or individual milk animals which are located in the most prevalent wind directions from Plant 2. Routine milk samples are collected in areas of high dose potential instead of within 5 kilometers, due to the locations of milk animals.
( P ) Station 96  is the control station for milk samples because it was determined that the cows  at Station      9B in Sunnyside were given feed grown in the Franklin County area across the Columbia River from Plant 2. Stations 62 and 63 at 10.4 miles and 6.4 miles SE of the plant, respectively,.were added during 1990 due to the unavailability of milk from Station 40 for part of the year.
(q)  If cesium-134 or cesium-137 is measured in an individual milk sample in excess of 30 pCi/1, then the strontium-90 analysis will be performed.
(r) There    are no commercially important species in the Hanford Reach of the Columbia River.
Most  recreationally important species in the area are anadromous (primarily salmonids), which ascend rivers from the sea for breeding. Four fish specimen will normally be collected by electroshock technique in the vicinity of the plant discharge (Station 30) and from the Snake River (Station 38).
If electroshocking        produces insufficient anadromous fish samples from the Snake River, samples may be  obtained from the fish trap at Ice Harbor Dam, Lyons Ferry Fish Hatchery, or other similar facility (Station 38A).          If  insufficient anadromous fish samples are produced through electro-shocking on the Columbia River, samples may be obtained at the Ringold Fish Hatchery (Station 39).
(s) Garden produce will routinely be obtained from farms or gardens using Columbia River water for irrigation. One sample of a root crop, leafy vegetable, and a fruit is collected each sample period,      if  available. The variety of the produce obtained will be dependent on seasonal availability.
(t) Station    91 is an apple orchard irrigated by the Columbia River.      The apple crop from Station 91  is sampled annually.
 
TABLE 4-2 MP  AMP        AT  N  BY    T SECTOR    STATION(b)  ESTIMATED    DISTANCE(c)  SAMPLE TYPE(d)
N MB          M            M N    (1)    52          0.1            161        GW 71(1S)      0.3            483        TLD 47            0.5            805        TLD 57            0.8          1201        AP/AI 18                          1770        TLD 53            7.5          12068        TLD NNE  (2)  72(2S)<<)      0.4            644        TLD 2            1.8          2896        TLD 54            6.5          10459        TLD NE    (3)  73(3S)        0.5            805        TLD 19            1.8          2896        TLD 48            4.5          7241        AP/AI 39            4.4          7084        FI 46            5.0          8045        TLD ENE  (4)  74(4S)        0.4            644        TLD 21            1.5          2414        AP/AI/SO/TLD 20            1.9          3057        TLD 11            3.1          4988        TLD 33            3.6          5792        SE 45            4.3          6919        TLD 44            5.8          9332        TLD E    (5)  75(5S)      0.4              644        TLD 22          2.1            3379        TLD 10          3.1            4988        TLD 26          3.2            5149        PW 4-15
 
TABLE  4-2 (Cont.)
MPEL      I    8      T SECTOR(~)      STATION(b) ESTIMATED    DISTANCE(c)  SAMPLE TYPE(d)
NMBR        M            MTR E    (5) Cont. 27        3.2          5149          DN 30        3.3          5311          FI 43        5.8          9332          TLD ESE  (6)        76(6S)    0.4            644          TLD 31                      1770          GW 32        1.2          1931          GW 51        2.1          3379          TLD 23        3.0          4827          AP/AI /SO/TLD 34        3.5          5632          SE 8        4.5          7241          AP/AI/TLD 42        5.6          9010          TLD 36(e)      7.2          11585          HI 5        7.7          12389          AP/AI/TLD 38        26.5          42639          FI 91        4,4          7079          FR SE  (7)        77(7S)    0.5            805          TLD 24        1 ~ 9        3057          TLD 3        2.0          3218          TLD 41        5.8          9332          TLD 40        6.4          10298          AP/AI/HI/TLD 59        9.6          15443          MI 61        6.5          10456          TLD 62        10.9          16730          HI 63        6.4          10298          MI 4-16
 
TABLE  4-2 (Cont.)
EH    AHP E      TI N    Y SECTOR(~) STATION(b)  ESTIMATED      DISTANCE(c) SAMPLE TYPE(0)
N HBER          HIL          HETER SSE  (8)    78(8S)          0.7            1126      TLD 25              1.6            2574      TLD 55              7.0          11263      TLD 28              7.4          11907      PW 4              9.3          14964      AI/AP/TLD 29            11.0          17699      PW 37(e)          16,0        25744        GP S    (9)    79(9S)          0.7            1126      TLD 1              1,3            2092      AP/AI/SO/TLD 6              7.7          12389      AP/AI /TLD
~ SSW  (10)  80(10S)
* 0.8            1287      TLD 50              1.2            1931      TLD 56              7.0        .1 1263      TLD SW  (11)  81(11S)        0.7            1126      TLD 13              1.4            2253      TLD 96            36.0        49250        HI WSW  (12)  82(12S)        0.5            805      TLD 14              1.4            2253      TLD 9A,98,9C(e)    30.0        48270        AP/AI/MI/GP/
TLD/SO W    (13)  83(13S)        0.5            805      TLD 15              1.4            2253      TLD 4-17
 
TABLE  4-2 (Cont.)
SECTOR              STATION R MP    HP ESTIMATED T  N  BY DISTANCE T
SAMPLE  TYPE(d)
                                                                                            ~ o NHBR            H              H T WNW  (14)            84(14S)        0.5              805                TLD.
16            1.4              2253                TLD 7            2~7              4344                AP /AI/SO/TLD NW    (15)            85(15S)        0.5              805                TLD 49            1.2              1931                TLD NNW  (16)            86(16S)        0.4              644                TLD 17            1.2              1931                TLD 12            6.1              9815                TLD (a)  The area    in the vicinity of Plant 2 is separated into 16 separate sectors for reporting purposes.          The 16 sectors cover 360 degrees in equal 22.5 degree sections, beginning with Sector                1 (N) at 348.75 to 11.25 degrees and continuing clockwise through Sector 16 (NNW).
(b)  The  alternate designations for      TLD  Stations 71-86 are given in parentheses,      i.e. 1S-16S.
(c)  Distances are estimated from map position's            for  each  location  as a radial distance from Plant 2 containment.
(d)  Sample Type Key:      TLD  Thermoluminescent          MI  Mi 1 k Dosimeter                PW  Surface    (River)/
AP  - Air Particulate                  Drinking Water AI  Air Iodine                  GW    Ground Water SE    Sediment                  DW    Discharge Water FI  Fish                        GP  Garden Produce SO    Soil                      FR  Fruit Station    9  designates  the Sunnyside-Grandview      control area.      It is actually three separate stations (Stations 9A for TLD, AI/AP and SO,                9B
    'or    milk, and 9C for GP) within a few miles of each other and all within 30-35 miles of Plant 2. Station 96, which is the control station for milk, is also located within the control area. It is 36 miles from Plant 2. Station 9B, which was the control location for milk until 1986, is now an indicator milk location.
(e)  Duplicate samples,      i.e.,  samples  drawn at the same time as the routine samples  and submitted    for analysis    as a quality assurance check, are collected at this location.        The station      designation for the duplicate of Station 27 is Station 72.          The station    designation for the duplicate of Station 36 is Station 37.
4-18
 
TABLE  4-3 D  TAN          N M      T  N  A    T P  NT  F  NT      T NI THIN F V            F P ANT      NTA NMENT SECTOR          NEAREST          GARDEN2            DAIRY PARAMETER      R  ID NT              M            ANIMA        IV NE          4.3              0 ENE          3.9                9(d)
E            4.5              p(e)
ESE          4.2              4 2(f)
SE          4.8 a These  are estimated distances;      slight variations occur    when  the map used for the land    use census  is changed.
Eleven of the sixteen meterological sectors within the five-mile radius of Plant 2 are on the federally-owned Hanford Site; the remaining land is comprised of 4.48 sq. miles of privately-owned farm land. Only those sectors containing points of interest are presented here.
The  closest dairy animal locations are at 6.4 miles, 8.3 miles, 9.6 miles and 10.6  miles SE and 7.2 miles ESE. The dairy at 8.3 miles SE is not used for  milk sample collection due to the owner's reluctance to participate in the sampling program.
Large garden with broadleaf; samples were not available            due  to owner's reluctance to participate in the sampling program.
Large garden    at  5.1 miles E, but no broadleaf vegetation observed.
" Large garden,    but no broadleaf vegetation observed.
g The  closest meat animals observed were at approximately 5.7 miles            ENE.
4-19
 
Ls, 5
                                                                                                  ~) sag    FO                                                  )
SSCSLISSSpSW 10mi. Radius                  ~>I
                                                                                                                                                                    )p
                                                                                                                      ) SSOLLSSQSWQRlM RO.
Os)FDAIT g)4
                                                                                                                      )                                            I                                  BASIN
                                                                                                                                                                    )
RSFS g CITY DASFS  RLL Ros
                                                                                                                      )
ss        )
                                                                                                          )I          )
                                                                                                          "r"~
~    FOYAlossA)ARRscAD2 ROUTE11A 1
                                                                                                                )
5 55    )
                                                                                                                      ~
sss5 ClsST.
                                                                                                                                                                      /                        )
                                                                                                                                                                                                  /
SDSSWOCO RO-
                          +o~                                                                                          4    ssmsssssc wssAsss5
                                                                                                                                                                                                  )
O~                                                                            1SSTCSCSST
                                                                                                                            )
                                                                                                                            )
ssssssss t
ylrry5 r r$~                      i)I      II
                                                                                                                                                                                                  )g
                                                                                                                                                                                          )
                                                                                            ~2
                                                                                  '5            ~ 15                                    )-  ~                          )
0                                                                                                          I ST                                                                                    )
                                                                                                                                                                          )              )
55  $            2'I ~                                                              5I L              )s ss  ss ss sos K CCIA22
                                                                                                                                                                                  )
15 ~                2'$
FS                                                              )
                                                                                                                                                                                  )
                                                                                                    ~ 51                                                                          I 5$
                                                                                                          ~ 51 240 25      02 5  1 ~      ~P  ~ 25                                            Q)                                                    5'SSYFFSFYA)
FFSWY.
g                                )            )
                                                                                                                                    ~ 51                                          )$ 5552VD2 r"~                      w)        )Sll SO.
                                                                                                                                                  ~ sssw  wsswsssw anford                                                                                                                            5'OSSSSL                                      I)
                                                                                                                                                    ,  OOCWOOO mw\sww ite                                      CO Cl sIF E
                                                                                                                                                                          ~ ssssv. I
                                                                                                                                                                                      )
                                                                                                                                                                                                )
                                                                                                                                                                                                )
                                                                                                                                                                                                )
CGER PL                                                                          51 W. $ ACOSOOR      M. )
                                                                                                                                                                                                )
CPA'ASST')LVFF$
                                                                                                                                          '%s ss ~    ~ OSSSSSSS P'sSSSSSOIL
                                                                                                                                                      ~ SsSSS              5        FYA
                                                                                                                                                                                                )
                                                                                                                                                                                                )
WWWWWW SU6$ ASS)                                                                                                            )
s evasw>F sss ts~
ss            ~ s                                                                                          HRwrww~ ALD)R R55s 5%%%%
                                                                                                                                                                                                )
                                                                                                                                                                                                                      )\
                                              ~~ss      \
II
                                                                                                                                                                                                )
Sssssss s1s
                                                                                                                                                                                  ).          } ww ss)
                                  ~o                        j                                                                                                  II                IK            Fs)LO    NL
                                        ~
                                                                                                                                                                                  )
                                          )I)F~                                                                                                                                  )
                                                                                                                                                                                  )
ly@
ROP)RY M.
RICHLAND Franklin AIRPORT
                                                                                                                    )        I                                                  County Benton                              WEST RICHLAND 1)
BENTON County                                                                                                                                ~            LEGEND
                                                                                                                                                                      ~
PAVCD ROAD CITY                                                                            RICHLAND                                                                ~  55PRVD RD OR CRVL ROAD 224                                                                                                          182                FOORDRY LFS)$
FAT SCAL2 12                                                                              PASCO                      ~              ~            215L ssssss.ss FIGURE 4-1 REHP SAMPLING LOCATIOHS                        HITHIH THE 10-MILE RADIUS 4-20
 
o
~ o
 
                                                    ~ Othello                                  WASH(NGTON Lower Granite Dam e Connell                            Lyons            Snake River Priest        Hanford                                                                                ~ Feny Rapids          Reservation Dam                                                                                                            Vttfe Goose Lower                Dam Monumental WNP-2                                                  Dam 10 mile radius                                                            ~ Pomeroy 38A Ctarkston ~
  ~9C                                                462                                                                                                            IDAHO
~ Sunnyside                                                                                                        ~ Dayton ggB +9A                            West    k  fllctdnnd 4 Eureka lttdda>>
Grandvtow    g sfJ        t3onton                Pasco 3 8 96                              ~                        ~            lce Harbor Dam
              ~ Prosser                    37A,B ~
Kennewtck
                                                                                                    ~ Walla Walla McNary Dam                                                OREGON Cotumbia R'v Inch ~ 16 mlles 0        8          16 L Sample Locations 900266 A April 1991 FIGURE 4-2 REMP SAMPLING LOCATIONS                  OUTSIDE THE 10-MILE RADIUS
 
~ s
~ e
 
STATION 9B II INDEPENDENCE RD 0  AIR STATION
                                                                      + TLO SUNNYSIDE                              9A
[                    f  sou.
FACTORY RD      +0                        VEGETABLE STATION I-82 9C STATION            RAY RD g
96g z 00 FORSELL RD                                    McCREADIE RD GRANDVIE I-82 2!
R m            YAK I-82 0
m            22 MABTON PROSSER SCAI E IN MILES 0  1  2 3    4 5    6 880188 FIGURE  4-3 REMP SAMPLING LOCATIONS  IN THE SUNNYSIDE/GRANDVIEH AREA
 
L~BFO
                                                                              $)
10mi Radius SI.                                                                            III CHfSTRUT    I III        I                                          I                              BASIN I          IH                                                                                    CITY SHfFRflD RO. <<m Lgs  ~    I AFCOlYWFR RQ L
TDYAK91AAuRR19AQB                                                                                I                                3 ROUTE I IA I
I                      J Ye  r                                    I I
pf 64                                                          VSSICC I                      I OAYCC CJL WO                          WWWWWW&
RAC 9&#xb9;                                        W. JVHRIR RO.
CHCA4HCC r
I',
WA1ACCCC IMPITHO HATClCAY  I 91  gs                                    rlw                                  )
                                                                                                                                            @r I                                      l~g O
19      ~ 19                                    r      ~                          I I
67            ~ IC                                                              I            I I            I WVC IWCCADI 66        1461          +21 ~ L                                              ~ 49              L~~          L w w a r4 K COAee  RD I
15 ~    1                                                                                                I I
1              91                                                                          I
                                                                                          ~ 51                                                                              I 240                                                                  9S                    no                                                    ACATHIWS 1 ~    ~ 94                                              Ql                                          s$
FRWY.                      wesT F61 RQ, I            II
                                                                                                                                      ~                              I        I
                                                                                                                ~ 91 IIBfcceweoR. s r- ~
KOWH HJCHUI anford                                                                                                              4'1 ~              CCHCCC
                                                                                                                                  . OOCVOCO pwl\Qw DOOWOOOwwww CFA ite                                                                                                                                                CCCCT. I I
I I
HHWWW NY                                          CEDAR I
I 46646IWI
                                                                                                                                                  \wow& rwwf            I w%wwww 61 W.~RQ. I I
r a
                                                                                                                              +IP
                                                                                                                                    ~ ACVAI41N IAHCCQC WW 8        RQ.
WWHW&lfW&AHHH
%AAVIA11\VAhg                                                                                                                                                            I BFA WNKBCVFFS 69 I
SVBSTATIOH                                                                                              RQ. I
                                                                                                                                                          ~ ACDIR&wllwwwwIIw
                                                                                                                                                      <<wwS II              s          I          s 5$
I          s CASSAVA                                                                                                                    s          I          s
                      ~o O~                                                                                                                                    I)
I I
I Og RICHLAND Franklin AIRPORT OfHT County Benton                            WEST RICHLAND BENTON County                                                                                                                        ~          LEGEND 9AYEDROAD CITY                                                                  RICHLAND                                                          mme NFRVDRDOR ODYL ROAD 224                                                                                                    182                  BOVHDRY 191IS FAY 12                                                                            PASCO                                            8L 82 FIGURE 4-4 INNER CIRCLE TLD LOCATIONS 4-23
 
~ o
~ o
 
cll  ~
10mi. Radius                    il I
I HCCANOSWQRTH RO.
I I
lg            I                                                                      BASIN CITY 0414 SASSI Wu.                                        R 170 I
                                                                            /%>                                I II    wIHI, TOYAKSAAAFRCOAOE I
RPIJTE ) ) A                                                    \
                                                                                  ~ ~
J
                                                ~ 12 r
Ts"~r            r gr' I
P RVSSQA                P4' SAWS TN
                                                                                                                                  &0 C
I                      lg I
NR CCHT.                                  W. JNIIPFR RO.
WAIAIHS IHAIIHS                                                        I HAIOCAY    I
                                                                                                                                                        ~ &
I                          Ig I
QD                                                                            I
                                                                                    ~ 14 0          44~            SY I
I IR                                ~4 20 4
I 158 I    2S                                                                                Lag 454    524
                                                                              ~5 I
IS+4                                                  14                                                      I
                                                                                        ~ 31 I
I 240                                                              I    45 4S                  $451 (43 54    QC    ++4      24 WIST FSI RfL I I
I
                                                                                                                          ~ 41                                        ~
I
                                                                                                                                                                        ~~OR            s r-,
anford                                                                                                                                        e CHCCI,
                                                                                                                                        . DOOWOOO wwlo&          &we ite                                                                                                                                                    CVCCT.
                                                                                                                                                                        ~
I I
                                                                                                                                                                                'OOWOTO I
I I
OIOAR I
0                                                                                                                CCKMIIITg 41
                                                                                                                                                        <<444RAH w &wllw&w\wwI W,SAO            RO.
I
                                                                                                                                          ~ MUAAW                                I I  I44444 CR 8        Ro.
ff:                        maemeCg      Pwm                  W\%WW INVbVAS%%%
0, CO                                                                            I L                                              SPA WHffESTVFFS 42 I
Tr"-                  SVSSTATTOH                                                                                                        I
                                  ~4 y"                      4 II
                                                                                                                                                                ~ AIOIRRL wS &we Swww& IA s
2$          I          S CH<<14I                                                                                                                          s            I          s 0~                                                                                                                                          sm I
I I
Og RICHLAND Franklin AIRPORT County Benton                          WEST RICHLAND II                  OFMT BENTON      County                                                                                                                            ~            LEGEND
                                                                                                                                                        ~
PAVED ROAD CITY                                                                        RICHLAND                                                          mme      111PRYOROORORYf ROAD 224                                                                                                          ) 82                SNDORY TDRS FAY 12                                                                                  PASCO 82 FIGURE 4-5 NEAR-PLANT TLO LOCATIONS 4-24
 
Qr~g&D 10mi. RadluS                  <I                                                      Iy I
I I
CHESTHVT I
I      Ig          I                                  I                              BASIN IS ysI                                                                  CITY OATS                                                    m SHEFAELD RO.
WWWW&W LLFLAOWER5E5 TDYAK65ABARRcHK ROUTE 11A                                                                  I I
J  r              I                  I I
pf
                                                                                                                                                      ~ &&WAN RFS eeHT.                              w. ABSFER Ro.
I L    THTR5HCS WAKLKS r      NOeVXOLEL I IIJNTHO HLTDSSY  I 16          ~ 19 0                                                                                                  I 69            67 11                                              I            I eF                        Le                                            I            I 15S I          2+1 ~                                        ~ e5            L            le m w w eAe N. COVLEE RO lee 16 ~      1                                                                                          I
                                                                                  ~ 61 I
I
                                                                                      ~ 51 240                                                              es es
                                                                                  's          n3                                          51ATTRWS
                                                                    ~
25 e                                                                                          sf 1
QI                                        sg
                                                                                                                            'H FFl WY.              WEST FR RLL      I I
                                                                                                                ~9                                      IRuaWeW. I I
r"-
COWN  IAIWIAII anford                                                                                                                                                  w 1\m& wwww ite                            C9
                                                                                                                            )IF E eveeT. I rI I
I 1
aw HW&
I    CEDAR I
0 C
I I wwww
                                      ~ 66                                                                                              ~ %%%        w+
W. AOELMOOR RD.
ws I
                                                                                                                            ~ A9VARVS I
I EC O,
                                                                                                                    & &W +)P ~ARee LFL
                                                                                                                                            ~
B        RLL WWWWW WWWW
%WAWA1WAVA                                                                              TO
                  'AiiWAN BPA WL ITEBLVFFS n SVBSTATIOH z                                                      62 I
                %V                                                                                                                                ~ ALDER        I me                                                                                  Awws            wLED I & wlsw pc'                                                    LLI 1                                          II              s          I        s I
W CO h~                                If s          I I
s sl s
                                                                                                                        ')>
I R
Franklin I
RICHLAND AIRPORT i                                                  County Benton                      WEST RICHLAND BENTON County                                                                                                            ~            LEGEND PAVED ROAD CITY                                                                  RICHLAND                                                  <<we      SFPRVDRDORORYL ROAD 224                                                                                              182              BOVHDRY LS1ES FAY 12                                                                          PASCO 82 FIGURE 4-6 OUTLYING TLD LOCATIONS HITHIN THE 10-MILE RADIUS 4-25
 
clIe ~>>
10ml. Radius                      ~I ly I
I
                                                                                                                                                                                  'RESTNIT I
I                                        I                                    BASIN I        IR I
CITY I,
Eep~eeN SAFIACWWER RO.
To YAKOIAAARNOACE                    A                                                  ~ I~                          I ROuTE    qg
                                                                    ~ 12 s,
I J
200 EAST WWWWWW RAACONT.                                      W. JVMIPER RO.
I SSNWCCO RO.
                                +0~                                                                                                4 emANOI WAFCIACI s
I1400040 O~                                                                                      NATOCW  I I
4p'4 r      +            5                ~i
                                                                                                      ~2 1~          ~ 10 0                1T                                                                                                  I 40
                                                                                                                  ~ 20                                                                  I          I OF                                                                                    I          I 4                                                                                            L            le a a a ebs 153                                                                                                                IE COEEE RO.      ~
                                                                                        '30 620                                                                                              I 15 ~                                                  I                                                              I I
1                  31                                                                              I
                                                                                                                    ~ 61 03 43 240                                                                                                          23
                                                                                                                            ~01 IIATREWS IN 3
QO      ~  ~ 24                                            Ql                                                  s$
                                                                                                                                            ~ 01 FIR WY.
I
                                                                                                                                                              'H~
I WEST Sl RO. I      I I
20544EwEIEE I
I s
                                                                                                                                                                            ~
CONN IIASOOIIN anford                                                                                                                                  41 ~
                                                                                                                                                                      ~ CNOOC OCCWOCO Mal      e        &we ite                                                                                                                                                                  ~ CROT.
r I
I I
I AWWWWW IY                                                  CEOAR I
I IE' 61 I
                                                                                                                                                                                                  +wm Tmmamma W. SAOEMCCR RO.
I
                                                                                                                                                              ~ AOVAVOO I    'ARCOCFC M.
K O,
                                                                                                                                                        ~%P                    W B
WWWWW WWWWWW
          \\\\\eeeeeeeeeee\                                                                                              CO II  I                                          I e epee'bw Lwvw    eeeeee            ~
easel BPA WIEIEECIIIPS SOBSTATSN 0
lt                                ~ AIDER RO.
I I
I&&&\If      w It                  s          I          s
                                                  ~ eeee  1ee I                                                                                                                                                      s 55          )cene wl I 1E          RElO OIL s
I I                                          I Ojg,                                                                                                                                        I RICHLAND Franklin AIRPORT County Benton                              WEST RICHLAND County                                                                                                                                    ~                LEGEND PATES ROAO RICHLAND                                                          w m e SI PAVO RO OR ORYL ROAO 224                                                                                                                182        ~e          BONSRYLJIES FAY 12                                                                                    PASCO 82 FIGURE 4-7 AIR SAMPLING LOCATIONS NITHIN THE 10-MILE RADIUS 4-26
 
~ o lj
 
I ~~
10 mi. Radius lg r            g FSRAWGSWORTH RO.                      II I        Ig          I                                                                    BASIN I                      I                                                                    CITY g          I BAS41 FRA Ra                                    R llo I
                                                                                                  "r"~j I SHEFVTELD RO.
TCY~~              ROUTE 11A                                                                        I BEUFTDWER RR eI  I                      J err I
                                                                                                          ~    s OAVTS IFL
                                                                                                                                                              &WW          WW FHS CONT.                                  W. RBTDER RO.
I 8  SHHWCS WHNJKS rr        aCWWOOO RO.
IMHTHO 154.
HATCHEIIY  I
                                                                                  ~2                                                                          I 14          ~ 19 0        49    17
                                                                                                ~ 24 I
I          I 9P                                                                              I          I        ~
1551      1  2S        2+1 ~                                                                Lwg        le w a m ass 454                                                                                                    . NO0%EERD 15 ~                                                                                                          I I
1                    51 I
R 240                                                          1    95                                                                              WTHEWS 25        3                                                            CORNER 1 ~    +4  ~ 24                                              Qg ARWY.                    WEST F81 RO. I
                                                                                                                                                ~                                    I
                                                                                                                          ~ Ol f W anford                                                                                                                  4, ~              4O9395
                                                                                                                                          . OOOWOCO
                                                                                                                                                                        &W%$ &W ite                            CO
                                                                                                                                      ~ CHOOI IIF E 5H44T.
rI I      I I
WWW&%%
CEDAR O
C.
                                              ~                                                                        ~1                                4 W. SAGEMOMRD.
I
                                                                                                                                            ~ AOHHVS                          I I  ~AH544ll
                                                                                                                                                              .8        RD 1T:                      ww eCg(Law                  w W W&WWW WWW O
Vh'a\I\\\\%\%\%1                                                                              CO  a8                            II I                                    I HD L
SPA W15TEFWFFS AACA                                                                  I I                                                      gSVBSTATQN                                                                                        ~ ATDERRO      I 4                                                                                            HWI      ~
s I                                    5$
I I
I        I I)
                                                                                                                                      ')>                          I I                                  I I
RICHLAND                  H 3
Franklin AIRPORT County Benton                      WEST RICHLAND BENTON      County                                                                                                                        ~          LEGEND
                                                                                                                                                        ~
PAVED ROAD CITY                                                                  RICHLAND                                                          w~ ~    NPRVD RD OR ORVL ROAD 224                                                                                                                          BOOHDRY IBTES FAY 12                                                                                PASCO 1990 880334.63                          82 FIGURE              4-8 RIYER/DRINKING AND DISCHARGE WATER SAMPLING LOCATIONS WITHIN THE 10-MILE RADIUS 4-27
 
IH~>>
10 mi. Radjus I
I I
sg        I                                                                BASIN CITY I      II        I s~      II                                                    R 1 70 To Y~  ~          ROIJTE 11A
                                                ~ 12 B.p I
BGFFOWWER RD.
44  s WWWW            W FHS CONT.                            W. 40IPER    M.
I
                    +o~                                                                                      SHIHAHCS WHCAHS BTOHWOOO RO, SHAITHO u93 O~                                                                                I NATCHOAY
                                                                                                                                              ~W I"";I I s~g
                                                                                  ~2                                                                I 14          ~ 19 0                                                                                                    I 49                ST                                                                      I 4
I 15S I            210L                                                      L~g ASH                                                                                      I 15 ~      1                              22                                                          I
                                                                                            '                                                            I
                                                                                        'T>>                                                              I 240                                                          I      93 SS                                                                EAATHEWS
                                                                            ~
25        3                                                                          sf
                                                                        'I
                                                                                      ~ 24                                      Ql                                    III FFIWY.              WEST FST M. I
                                                                                                                                      ~                          I I
                                                                                                                    ~ 91                                  ~ BE1AEVOE ESE s I
r- ~
anford                                                                                                                '3          SCHOOL p'al 41 COO WOOD ite                                                                                                                                      SCOTT. I rI I
I C3 IY            +'EDAR                  W  I 0                                                                                                        OWNIHTQ CHH\HAN 41 W. SAOEMOOR RO.
I I
I iAHSSCIL          B      RO.
EE                    w m m eJCpPw w                WWW        W    WAWWWW Cl CO II I                                I BPA WHREBENTS 42 I
gSUBSTATICH                                                                                ~ ATOER  RO. I 4                                                                                  HHHI      w%w      gQQAA'lf&
s I
CNNI HA I) s s
sI s
I I                              I Ofg                                                                                                                  I RICHLAND Franktin AIRPORT County Benton                      WEST RICHLAND BENTON County                                                                                                                ~          LEGEND PAVED ROAD CITY                                                                        RICHLAND                                                    ~ BAPRYO RO    OR ORYL ROAD 224                                                                                                182              BOAOBNTY ERIES FAY 12                                                                              PASCO 1990 880334.63                        82 FIGURE              4-9 GROUNDHATER SAMPLING LOCATIONS 4-28
 
I HIaaB 10mi. RadiuS                  ~1 Iy I
I HCEANGSWORTH RD.
CHESTNVT I
I I      Ig            I                                                                        BASIN CITY OATS I      Ig            Pc  aaaa Bc@  aav    I ETAFTDWWER ISA TO VAICSIABAIVHCADE  ROUTE I I A rrr                r                  I I                Oe              /fan I
ac                                          aa FFN CCHT.                                  W. RINIPER RO.
I NINWOOO m.
DIHVHCS WHCAIKC IHwTHS leev HATOCHV  I 0
                                                                                ~2 14        ~ 14 0        44            ST I
I            I I            I 4
Tel                                                                          Lag            I 14SH                                                                                                    N. COIAEE RO.
4SH                                                                                              I 14 ~                                                                                                        I I            I        m 14 21                                                                        I
                                                                                            ~ 41 SS 44 240                                                        JS I                              ISQH QP    ~                                                  Ql                                            45 FSTWV.                            f WEST IR RO.      I
                                                                                                                                          ~                              I I
                                                                                                                    ~ 41                                          IBOAEYVEoa      s I
f
                                                                                                                                  ~ DHH HAICHAH anford                                                                                                                  41 ~
SCHOOA DOGWOOD
                                                                                                                                                                          'lcaa          a ite                                                                                                                              KF'\
                                                                                                                                                          ~ veev, r
I I
I I
ICS iY              +'EDAR r I
aa\
0                                                                                              r'            COUhNIAQ CIWellAH I
I aaaaaa TE
                                              ~                                                                  41 anal W. AGFEMOCR RO.
I cAOVAIHAS                            I I    cAHce DIE K
O a a a eCpia a 8
                                                                                                                                                              \aaaa  RD.
aaaaaa C\%%%C%%CV1\%\a i~                  ~ aaNK BPA WHREBEVFFS gSVBSTATON 4
zlV CO II aa ~
42 AIDER RD. I I
s I
I Iaaaa I        s cAccl Ia                                                                                                                  s          I        s
                          ~o                                                                                                    I Cl P.
I)          }.
hpg                                                                                          s    I>                              I ~
I                                      I I
Cr@
RVPERT RO.
RICHLAND R
Franklin AIRPORT County Benton                        WEST RICHLAND BENTON County                                                                                                                        ~            LEGEND PATED ROAD CITY                                                                    RICHLAND                                                        aa    c BAPRYD RD OR GRYL ROAD 224                                                                                                    182      <<~      SOVNDRY EBIES FAY 12                                                                            PASCO 82 FIGURE 4-10 SOIL SAMPLING IOCATIONS HITHIN THE lOaMILE RADIUS 4-29
 
grigglO 10mi. RadiuS                  <I .                                                              III I
I HCAAWGSWORTH RO.
CHESTNUT I
I                                                                    BASIN CITY To Y~~          ROUTE 11A
                                                                                        +p~~            ~
L ww          w RD.
                                            ~ 12 I
I 1
WWWW W. AMBER RD.
I RCHWOOO Te.
4  THTAAHOS WAKllc4 I
IMJITHO HITOHAY I
                                                                        ~2 14          ~ IS O                                                                                                          I 4S          47
                                                                                      ~ 20                                                            I I
I    I 23$      2+I ~                                                                L~g I
16 ~                                                I                                                      I I
31                                                                        I
                                                                                        ~ ST                                                                            I SS 43 240                                                                                      50                                              IIATHEWS              I$
26        3                                                              CORNEA                Ig I~    ~  ~ 24                                              Ql                                        65 FRWY.                  WEST FR RO. I
                                                                                                                                      ~                            I I
                                                                                                                  ~ SI                                        ~ SIIAEYVSDa    I I
r  ~
SOWN  IWIOIAII anford                                                                                                            41 ~
43 IOHOOl
                                                                                                                                  . DOGWOOD W %\0 W  \
ite    .
                                                                                                                                                      <<44T.
r I
I I
I QRHWHW iY                                        'CEDAR I
0                                                                                                                                  I I
41 W.SAGEMOMTO.
I wwwwww I
                                                                                                                                    ~ AOOAHOS I
K
                                                                                                                                ~ ~AHSSOA              I WP RD. W    ~  &&WAN ES, AVIVA\1%WAVA                                                                                HI                                                                  I SPA WTlESBVFFFS AATA                                                  42 I
gSVSSTATTON                        IIT                                                                        I
                                                                                                                                                        ~ AIDERaRD. Qeaeeila
                                                          'ATTI>>                                                                                  anal
                                                                                                                                            ,II II I
I RICHLAND Franklin AIRPORT County Benton                    WEST RICHLAND BENTON County                                                                                                                    ~          LEGEND SAYED ROAD RICHLAND                                                                ~  SIPRYD RD OR ORYL ROAD 224                                                                                                    182              SOVHTHW TSIES FAY 12                                                                                PASCO 1990 880334.63                      82 FIGURE 4-11 SEDIMENT SAMPLING LOCATIONS 4-30
 
l    ~ie  ERD 10mi. Radius                ~I I
lj        I                                                                        BASIN CITY I          IIII      I R 110 ROUTE 11A                                                                  I I                    J R VSSEEL DAVIS EN I                      sg I
ae                      aaa RHC CCHI,                                W. JNIPER    RL CHIHHHS WIICIAN llAHI440 5555' HAICHQlYI a
Iaal
                                                                              ~2                                                                      I 15        ~ 19 0        49          57 I
I            I 4
I            I 15S
                                                                          \ IS+      21 ~                                                              Lag          I <<aaeAe N. CONES    RL 4Se                                                                                        I 15 ~                                          10                                                    I I
51 I
240                                                                                                                                      NATHEWS DS I~        ~ 24                                            Qs                                        4 FFCWY.                WESTFSIRD.I
                                                                                                                                      ~                                        I
                                                                                                                  ~ 91 I
SRAEVDSOCE          S I
wI      E555 RD.
anford                                                                                                          41 ~
CDHN lQNOWI CCHCCC
                                                                                                                                    . DOGWOOD Ie a%e el a      aaa ite                                                                                                                                        CCeCI. I I
I I
CEDAR
                                                                                                                  ~ 40                                                  I 0                                                                                                      CCWNIRTg                I CHCCCHAH                I 51 aS aaaaaa W.SAGEMOQRM, I
a iiJOUHVCS                            I se  AICCC NC 8      RD.
EE O
a a a eJCge    Ie a a            aaaaa BPA WHlTE8WFFS CO                                                                    I I
eeee\ewA Saveeee eeeeeeeeeee                        gSOSS TATNN 5~                                                              8s,~              aa>>S4~~.            I a Qa a a a II            I            I eeelle I 10 s
I                  a+
RICHLAND R
Frankl n AIRPORT County Benton                  WEST RICHLAND BENTON            County                                                                                                                      LEGEND PAVED ROAD CITY                                                                  RICHLAND                                                        a  e BCPRYD RD OR ORVL ROAD 8              224                                                                                              182              BONIDRY 58CES FAY 12                                                                          PASCO 1890 880334.63                            82 FIGURE 4-12 MILK SAMPLING LOCATIONS HITHIN THE 10-MILE RADIUS 4-31
 
~ o
~ o
 
During 1990 the analyses        of REMP  samples were performed by Teledyne Isotopes in Hestwood,      New  Jersey. The  thermoluminescent      dosimeters were processed by the Supply System        External    Dosimetry    Laboratory. Table 5-1 presents the means and ranges of the 1990 results for each type of sample collected.                    The means and ranges of the preoperational              and the previous operational data from 1984 to 1989 are also included in the table for comparison.
The  data for the preoperational period and the first six months of 1984 included "less than" (<) designations for results below the actual LLD, the contractual LLD or the two sigma error, depending upon the convention employed by the analytical contractor.                  Consequently, the data averages using "less than" values are biased high.
The use    of the "less than" designation          was  discontinued in mid 1984.      Since then,    REMP    data have . been reported as net results, i.e., total (gross) results minus the detector counting background.                    Comparison of the mean results for 1990 to the mean preoperational results is difficult due to the high bias resulting from the "less than" data.                  However, comparison of the range of results observed for each period to determine whether the 1990 results are significantly greater than the results for preoperational and previous operational periods, is a viable approach.                  Careful interpretation of the data ranges for the previous operational                    data    is still required because of the effects of the Chernobyl accident in 1986.                    For this report only the data from the last six months of 1984 were included in the previous operational data in order to eliminate the "less than" values in that category of summary data.
The    1990    REMP  data  compares    well to the      ranges  of data from previous periods.      The quarterly TLD results        for    1990 were    very close to the 1989 results    and slightly lower than the          1987 and 1988      results. These  slight changes      in the TLD results are certainly within the                    normal  range  of uncertainty expected for TLD systems.
The  1990 annual      TLD results were about 5-101. lower than the mean quarterly results.      This relationship between the two TLD distribution types has been observed in nearly all the previous years.                It  is apparently due to slight fading of the TLD signal on        the  TLDs  kept  in  the  field  for the entire year.
The    LLDs generally        determined by Teledyne Isotopes for each analysis performed and each radionuclide of interest are listed in Table 5-2.
Presented alongside the Teledyne )LDs are the LLDs required by the NRC Branch Technical Position          (BTP).('he          LLDs determined for analyses        at Teledyne Isotopes have met the NRC requirements in all cases.
A summary      of the REMP results relative to detection limits is presented in Table 5-3.      If  a particular radionuclide of interest was not detected in the 1990 samples, the term "LLD" is noted in the data mean and range columns.
Aside from some            naturally-occurring radionuclides,            the radionuclides detected in the 1990 sample included cesium-137 in fish, soil and sediment, 5-1


====4.4.3 Gross====
and  cobalt-60 in the discharge        water;  tritium was also detected in some water samples.     Gross    beta results in   air and water were nearly all above the detection  limits.
Beta Activity in Hater One liter of each sample was evaporated to a small volume and transferred to a stainless steel planchet.The sample was dried under heat lamps, cooled, then counted on an automatic beta proportional counter.The results were calculated using empirical self-absorption curves which enabled the correc-tion of effective counting efficiency, based on the sample residue mass.4.4.4 Iodine-131 in Water~s Two liters of sample were first equilibrated with stable iodide carrier.A batch treatment with anion exchange resin was used to remove iodine from the sample.The iodine was then stripped from the resin with sodium hypo-chlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free iodine.It was then back-extracted as iodide into sodium bisulfite solution and precipitated as palladium iodide.The precipitate was weighed for chemical yield and mounted on a nylon planchet for low level beta counting.The chemical yield was corrected by measuring the stable iodide content of the water with a specific ion electrode.
In general, the positive, or detected, 1990 results compare well with the results    from previous years.         Any significant differences or increases evident in the 1990 results are discussed in the following subsections.
During 1990, this procedure was used only on intercomparison samples, since the doses calculated via ODCM methodology for the consumption of drinking water did not exceed 1 mrem per year (Table 4-1, footnote n).4.4.5 Tritium in Hater Approximately two milliliters of water were converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 400 C.The hydrogen was loaded into a one-liter proportional detector and the volume was determined by recording the pressure.The proportional detector was passively shielded by lead and steel and an electronic, anti-coincidence system provided additional shielding from cosmic rays.4.4.6 Strontium-89 and 90 in Hater, Milk and Soil During 1990, strontium analyses were not required for any routine REMP samples.They were used for intercomparison samples so the analytical techniques are described below.~o Hai~r Stable strontium carrier was added to one liter of sample and the volume was reduced by evaporation.
Summaries    of the environmental radiation exposure rates, determined by thermoluminescent dosimeters (TLDs) are presented in Tables 5-4 and 5-5.
Strontium was precipitated as Sr(NO,), using nitric acid.Milk Stable strontium carrier was added to one liter of sample.The sample was then evaporated and ashed in a muffle furnace.The ash was dissolved and strontium was precipitated as a phosphate.
The individual quarterly and annual results for each TLD station are given in Tables A-l.l and A-1.2 of Appendix A. Figures 5-1 and 5-2 show the mean quarterly results for near-plant and remote TLD locations for the preopera-tional period, 1984-1989 and 1990. Figures 5-3 and 5-4 show the annual TLD results for near-plant and remote locations for the same periods.               In general, the quarterly and annual results for the control location (Station 9A) show the same fluctuations over time as the indicator locations and the relationships between the different locations remain very consistent over the three periods.
It was then redissolved and strontium was precipitated as Sr(NO,)~using fuming (901)nitric acid.4-8 The sample was first dried under heat lamps and a 10-gram aliquot was taken.Stable strontium carrier was added and the sample was leached in hydrochloric acid.The mixture was filtered.Phosphates were then pre-cipitated, collected by filtration and dissolved in nitric acid.Strontium was precipitated as Sr(NO,), using fuming nitric acid.A barium chromate scavenge and an iron (ferric hydroxide) scavenge were then performed.
Figure 5-5 presents      th'e mean 1990 results for each of the sixteen meteoro-logical sectors, compared to the sector means for the preoperational and previous operational periods. The relationship of the mean 1990 results to the results for the preoperational and previous operational periods is very similar for each sector. This indicates that there were no significant directional effects observed in the 1990 TLD results.             The annual  TLD results for each sector also follow the same pattern as the mean quarterly results, except they are 5-101. lower.
Stable yttrium carrier was added and the sample was allowed to stand for 5 days or more for yttrium ingrowth.Yttrium was then precipitated as hydroxide, dissolved and reprecipitated as oxalate.The yttrium oxalate was mounted on a nylon planchet and counted in a low-level beta counter to infer strontium-90 activity.Strontium-89 activity was determined by precipitat-ing SrCO, from the sample after yttrium separation.
In Figure 5-5, the apparent increase in the mean 1990 TLD results over the means of the preoperational and previous operational periods is due to the effect of averaging only the four quarters of 1990 data versus averaging numerous quarters for the other two sets of results.               The differences between the data sets are generally within 101., which is within the range of variation normally expected for TLD systems.
This precipitate was mounted on a nylon planchet and covered with an 80 mg/cm'luminum absorber for low-level beta counting.4..4.7 Iodine-131 in Milk Two liters of sample were first equilibrated with stable iodide carrier.A batch treatment with anion exchange resin was used to remove iodine from the sample.The iodine was then stripped from the resin with sodium hypo-chlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free iodine.It was then back-extracted as iodide into sodium bisulfite solution and precipitated as palladium iodide.The precipitate was weighed for chemical yield and mounted on a nylon planchet for low-level beta counting.The chemical yield was corrected by measuring the stable iodide content of the milk with a specific)on electrode.
Station  46  in the Hahluke Reserve      remained the location with the highest mean  exposure  rate, 0.31 mR/day. This is the same mean exposure rate deter-mined for that station for 1989.             Since the preoperational measurement phase, the results for this location have exceeded the results for all other locations. Variations in the ambient background due to variations in the soil and underlying rock composition account for such local differences in the TLD results.     Figure 5-6 compares the Station 46 results to the results of Station 9A, the control location, from 1982 to 1990. The relationship between the results at these two locations has remained fairly consistent from the preoperational period (1982-1983) to the present.
4.5 D n 1 M Since mid-1984, the results of the REMP analyses have been given as net results calculated from the gross or total counts determined for each radionuclide minus the background counts of the counting or detection instrument.
5-2
Consequently, for several sample types, the results range from negative to positive numbers.This manner of presenting environmental data prevents the bias and loss of individual results inherent in the use of"less than" (<)values, where the"less than" numbers can have a variety of meanings, such as"less than the lower limit of detection (LLD)" or"less than the two sigma uncertainty." The net results for REMP samples are presented with an asterisk (*)in front, if the results are less than the LLD.A listing of the LLDs deter-mined for each analysis is provided in Section 5.0 as a reference when reviewing the sample results.Plots of the sample results versus time are used to represent the results for analyses such as gross beta on air particulate filters, where the results are normally above the lower limits of detection'n such cases, the indicator station results are plotted with the control station results 4-9 for easy comparison.
Other data analysis techniques, such as log proba-bility plotting and plotting the moving average, are also used to represent the data and to determine whether trends that could be attributed to the~effect of Plant 2 operations are evident.Thermoluminescent dosimeter (TLD)data is presented in terms of the net mR/day exposure rate.These results are determined from the total mR exposure calculated for each TLD from its total thermoluminescent output minus the TLD background, minus any transit (or trip)exposure received during distribution and retrieval, and divided by the number of days the TLD was in the field.Log probability plots and graphs of TLD data by meteoro-logical sector and distance from the plant are used to interpret trends in the results.TLD data summaries include the term"standard error," along with"standard deviation." The standard error, which is the estimate of the precision of.the mean, is used for mean annual summaries of mean quarterly data.The standard deviation is used for the TLD data involving a single dosimeter result that has been determined from the four reader areas of the TLD.Both terms simply provide an indicator of the uncertainty associated with the results.4-10 RAD TABLE 4-1 A NV R MNTA H I P RHPA AMPLE TYP 1.AIRBORNE AHPL TAT N N SAMPLING AND ()TYPE AND FREQUENCY T N FR N Y ANA Particulates and radioiodine (6/12)1, 4-+, 21, 23, 40, 48, and 57 Continuous sampling;weekly collection P i 1: Heck 1 y gross be)a;gamma isotopic'e) of quarterly composite (by location)~I~1.: Heekl y gamma analysis.Sol 1 (")(0/5)2.DIRECT RADIATION TLD" (34/57)M, 1, 7, 21 and 23 Annually l-M, 10-25, 40-47, Quarterly, annually 49-51, 53-56, 6]71-86 (1S-16S)~Gamma isotop(c strontium-90 g Thermoluminescent out-put;quarterly and annual processing.
PIC(j)(0/3)3.HATERBORNE 1, 21, and 23 Continuous recording as needed Accumulated on mag card and internal memory.Surface/Drinking Hater" (3/4)Z5, 27, 28 and 29 Composite aliquots;Gamma isotopic, monthly collection
=gross beta, quarterly; tritium comp~site; s tronti um-$0 1 od1ne-131~n)
RAOI TABLE 4-1 (Cont.)NV N T NI T I P AHP E TYP HP TAT N SAHPLING AND ()TYPE ANO FREQUENCY N FR Y F ANA-Y I Ground Hater (2/3)Sediment from shoreline (1/2)31, 32, and 52 33 and 34 Quarterly Semiannually Gamma isotopic quarterly tritium grab sample Gamma isotopic 4.INGESTION Hl 1 k (4/6)9B, 36, 40, 59~52, 63 and~fp)Semimonthly during grazing season, monthly at other times Gamma isotopic iodine-131; strontium-90 q Fish (2/2)30 and 35 Garden Produce (1/3)K, 91 and 37 Semiannually Monthly during growing season in the Riverview area of Pasco and a control near Grandview; annual collection at Station 91.Gamma isotopic Gamma isotopic The fraction in parentheses for each sample type indicates the ratio of Technical Specification-required sample locations to the total number of sample locations currently being monitored in the surveillance program.The underlined sample location designates a control station.None of the groundwater stations are control locations.
Deviations are permitted if samples are unobtainable due to hazardous conditions, seasonal availability, malfunction of automatic sampling equipment, or other legitimate reasons.Such devia-tions are documented in Appendix D.
TABLE 4-1 (Cont.)Particulate sample filters will be analyzed for gross beta after at least 24 to 48 hours to allow for the decay of radon daughter products.If gross beta activity is greater than 10 times the mean of the result for the control, Station 9A, gamma isotopic analysis shall be performed on the individual sample.Gamma isotopic means identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents of Plant 2." Soil samples are collected to satisfy the requirements of the Site Certification Agreement (SCA)for Plant 2.g'Strontium-90 analysis shall be performed on any indicator soil sample having cesium results greater than ten times the results for the control location." TLD refers to thermoluminescent dosimeter.
For purposes of the REMP, a TLD is a phosphor card (31.75mm x 44.75mm x 0.4mm)with eight individual read-out areas (four main dosimeter areas and four back-up dosimeter areas)in each badge case.TLDs used in the REMP meet the requirements of Regulatory Guide 4.13'nd ANSI N545-1975', except for specified energy-dependence response.Correction factors are available for energy ranges with response outside of the specified tolerances.
'LD Stations 71-86 are special interest stations and are not included among the 34 routine TLD stations required by the Plant Technical Specification Table 3.12-1.Their alternate designations are 1S-16S.St'ation 61 is also a special interest location.It was added to the program during the third quarter of 1989.3 Pressurized ion chambers (PICs)are no longer required as part of the routine monitoring program.They are used only as a supplemental or backup system.The term"river/drinking water," instead of"surface/drinking water", is used throughout this report because the surface water is taken from the Columbia River.Station 26, Plant 2 makeup water intake from the Columbia River is both an upstream surface, or river, water sample and the drinking water control sample location.Station 28 (300 Area)and Station 29 samples are drinking water samples.The Station 27 sample, which is drawn from the plant discharge line, is taken in place of a"downstream" water sample near but beyond the mixing zone.It reflects the radioactivity present in the plant discharge prior to any river dilution.Composite (integrated grab)samples are collected with equipment which collects an aliquot at time intervals that are short relative to the compositing period.
TABLE 4-1 (Cont.)(m)Nhen the gross beta activity in drinking water exceeds 8 pCi/liter, a strontium-90 analysis is performed.(n)Nhen the dose calculated via ODCM methodology for consumption oF water exceeds 1 mrem per year, iodine-131 analyses are performed on the drinking water samples.(o)Milk samples will be obtained from farms or individual milk animals which are located in the most prevalent wind directions from Plant 2.Routine milk samples are collected in areas of high dose potential instead of within 5 kilometers, due to the locations of milk animals.()P Station 96 is the control station for milk samples because it was determined that the cows at Station 9B in Sunnyside were given feed grown in the Franklin County area across the Columbia River from Plant 2.Stations 62 and 63 at 10.4 miles and 6.4 miles SE of the plant, respectively,.were added during 1990 due to the unavailability of milk from Station 40 for part of the year.()q If cesium-134 or cesium-137 is measured in an individual milk sample in excess of 30 pCi/1, then the strontium-90 analysis will be performed.(r)There are no commercially important species in the Hanford Reach of the Columbia River.Most recreationally important species in the area are anadromous (primarily salmonids), which ascend rivers from the sea for breeding.Four fish specimen will normally be collected by electroshock technique in the vicinity of the plant discharge (Station 30)and from the Snake River (Station 38).If electroshocking produces insufficient anadromous fish samples from the Snake River, samples may be obtained from the fish trap at Ice Harbor Dam, Lyons Ferry Fish Hatchery, or other similar facility (Station 38A).If insufficient anadromous fish samples are produced through electro-shocking on the Columbia River, samples may be obtained at the Ringold Fish Hatchery (Station 39).(s)Garden produce will routinely be obtained from farms or gardens using Columbia River water for irrigation.
One sample of a root crop, leafy vegetable, and a fruit is collected each sample period, if available.
The variety of the produce obtained will be dependent on seasonal availability.(t)Station 91 is an apple orchard irrigated by the Columbia River.The apple crop from Station 91 is sampled annually.
MP AMP TABLE 4-2 AT N BY T SECTOR STATION(b)
ESTIMATED DISTANCE(c)
N MB M M SAMPLE TYPE(d)N (1)52 71(1S)47 57 18 53 0.1 0.3 0.5 0.8 7.5 161 483 805 1201 1770 12068 GW TLD TLD AP/AI TLD TLD NNE (2)72(2S)<<)0.4 2 1.8 54 6.5 644 2896 10459 TLD TLD TLD NE (3)73(3S)19 48 39 46 0.5 1.8 4.5 4.4 5.0 805 2896 7241 7084 8045 TLD TLD AP/AI FI TLD ENE (4)74(4S)21 20 11 33 45 44 0.4 1.5 1.9 3.1 3.6 4.3 5.8 644 2414 3057 4988 5792 6919 9332 TLD AP/AI/SO/TLD TLD TLD SE TLD TLD E (5)75(5S)22 10 26 0.4 2.1 3.1 3.2 644 3379 4988 5149 TLD TLD TLD PW 4-15 TABLE 4-2 (Cont.)MPEL I 8 T SECTOR(~)STATION(b)
ESTIMATED DISTANCE(c)
SAMPLE TYPE(d)NMBR M MTR E (5)Cont.27 30 43 3.2 3.3 5.8 5149 5311 9332 DN FI TLD ESE (6)76(6S)31 32 51 23 34 8 42 36(e)5 38 91 0.4 1.2 2.1 3.0 3.5 4.5 5.6 7.2 7.7 26.5 4,4 644 1770 1931 3379 4827 5632 7241 9010 11585 12389 42639 7079 TLD GW GW TLD AP/AI/SO/TLD SE AP/AI/TLD TLD HI AP/AI/TLD FI FR SE (7)77(7S)24 3 41 40 59 61 62 63 0.5 1~9 2.0 5.8 6.4 9.6 6.5 10.9 6.4 805 3057 3218 9332 10298 15443 10456 16730 10298 TLD TLD TLD TLD AP/AI/HI/TLD MI TLD HI MI 4-16 TABLE 4-2 (Cont.)EH AHP E TI N Y SECTOR(~)STATION(b)
ESTIMATED DISTANCE(c)
N HBER HIL HETER SAMPLE TYPE(0)SSE (8)78(8S)25 55 28 4 29 37(e)0.7 1.6 7.0 7.4 9.3 11.0 16,0 1126 2574 11263 11907 14964 17699 25744 TLD TLD TLD PW AI/AP/TLD PW GP S (9)79(9S)1 6 0.7 1,3 7.7 1126 2092 12389 TLD AP/AI/SO/TLD AP/AI/TLD~SSW (10)50 56 1.2 7.0 80(10S)*0.8 1287 1931.1 1263 TLD TLD TLD SW (11)81(11S)13 96 0.7 1.4 36.0 1126 2253 49250 TLD TLD HI WSW (12)82(12S)0.5 14 1.4 9A,98,9C(e) 30.0 805 2253 48270 TLD TLD AP/AI/MI/GP/
TLD/SO W (13)83(13S)15 0.5 1.4 805 2253 TLD TLD 4-17 SECTOR TABLE 4-2 (Cont.)R MP HP T N BY T STATION ESTIMATED DISTANCE NHBR H H T SAMPLE TYPE(d)~o WNW (14)NW (15)NNW (16)84(14S)16 7 85(15S)49 86(16S)17 12 0.5 1.4 2~7 0.5 1.2 0.4 1.2 6.1 805 2253 4344 805 1931 644 1931 9815 TLD.TLD AP/AI/SO/TLD TLD TLD TLD TLD TLD (a)The area in the vicinity of Plant 2 is separated into 16 separate sectors for reporting purposes.The 16 sectors cover 360 degrees in equal 22.5 degree sections, beginning with Sector 1 (N)at 348.75 to 11.25 degrees and continuing clockwise through Sector 16 (NNW).(b)The alternate designations for TLD Stations 71-86 are given in parentheses, i.e.1S-16S.(c)Distances are estimated from map position's for each location as a radial distance from Plant 2 containment.(d)Sample Type Key: TLD-Thermoluminescent Dosimeter AP-Air Particulate AI-Air Iodine SE-Sediment FI-Fish SO-Soil MI-Mi 1 k PW-Surface (River)/Drinking Water GW-Ground Water DW-Discharge Water GP-Garden Produce FR-Fruit Station 9 designates the Sunnyside-Grandview control area.It is actually three separate stations (Stations 9A for TLD, AI/AP and SO, 9B'or milk, and 9C for GP)within a few miles of each other and all within 30-35 miles of Plant 2.Station 96, which is the control station for milk, is also located within the control area.It is 36 miles from Plant 2.Station 9B, which was the control location for milk until 1986, is now an indicator milk location.(e)Duplicate samples, i.e., samples drawn at the same time as the routine samples and submitted for analysis as a quality assurance check, are collected at this location.The station designation for the duplicate of Station 27 is Station 72.The station designation for the duplicate of Station 36 is Station 37.4-18 TABLE 4-3 D TAN N M T N A T P NT F NT T NI THIN F V F P ANT NTA NMENT SECTOR NEAREST PARAMETER R ID NT GARDEN2 M DAIRY ANIMA IV NE ENE E ESE SE 4.3 3.9 4.5 4.2 4.8 0 9(d)p(e)4 2(f)a These are estimated distances; slight variations occur when the map used for the land use census is changed.Eleven of the sixteen meterological sectors within the five-mile radius of Plant 2 are on the federally-owned Hanford Site;the remaining land is comprised of 4.48 sq.miles of privately-owned farm land.Only those sectors containing points of interest are presented here.The closest dairy animal locations are at 6.4 miles, 8.3 miles, 9.6 miles and 10.6 miles SE and 7.2 miles ESE.The dairy at 8.3 miles SE is not used for milk sample collection due to the owner's reluctance to participate in the sampling program.Large garden with broadleaf; samples were not available due to owner's reluctance to participate in the sampling program.Large garden at 5.1 miles E, but no broadleaf vegetation observed." Large garden, but no broadleaf vegetation observed.g The closest meat animals observed were at approximately


===5.7 miles===
A  comparison  of the  1990 annual  and mean  quarterly TLD results is presented in Table 5-6. The  1990 annual    TLD  results are generally 5-101. lower than the mean quarterly results because of the signal fading characteristics of CaSo4. This difference is not significant, in light of the variability commonly observed    in TLD results.       In most cases, the annual result is within the uncertainty associated with the quarterly TLD results.
ENE.4-19
During 1990, a test was performed to determine whether one set of TLDs that had been used in the past for the annual measurements had a higher TL signal fade rate over time than the other sets used for the same purpose.               The higher fade rate was suspected because during the years when the set was used, e.g. 1988, the mean quarterly results and the annual results differed by approximately 15-201..      As described    in Section 4.0, the test involved collocating nine of the suspect TLDs with nine of the TLDs that had not exhibited a high fade rate. At the end of the year, when these two groups were processed, the mean result of the suspect TLD group was 121. lower than the other group.      As discussed    previously, all the TLD sets appear to exhibit some TL signal fading, normally amounting to about 51.. But the fading of the suspect group was significantly more than that, so the set will no longer be used.
>>
The  log probability plots of the 1990 and previous operational (1984-1989) quarterly TLD results are presented in Figure 5-7. The "slopes" of the lines in both plots are nearly the same, indicating that both sets of data are part of the same distribution.
~FOYAlossA)ARRscAD2 ROUTE11A Ls, sag FO~)10mi.Radius~>I ss)I"r"~1)5)SSOLLSSQSWQRlM RO.)DASFS RLL Ros)))5)SSCSLISSSpSW)p Os)FDAIT g)4 I)RSFS BASIN g CITY+o~O~~2 55~)sss5 ClsST.4 ssmsssssc wssAsss5)ssssssss 1SSTCSCSST
The  log probability plots of the 1990 annual results and the results from previous years of operation are presented in Figure 5-8. The 1990 results are consistent with results observed for the past monitoring periods.            The slopes of the lines determined for this .data are typical for ambient radiation measurements.
))t i)I II)g)/)/SDSSWOCO RO-ylrry5 r r$~))-~240 0 15~5'5 ST 55$2'$5$25 1~~P~15 2'I~~51~51 02~25 FS Q)FFSWY.g~51 I))5I L)))I))s ss ss ss sos K CCIA22 5'SSYFFSFYA)
The  log probability plots of the quarterly data for a near-plant locations, Stations 71-76, and the control location, Station 9A, from 1982 to 1990 are presented in Figure 5-9.        The linearity of the plots indicates that the results are all within the same log normal distribution and that no significant increases or decreases indicating a change in the environmental radiation levels were evident.
)))$5552VD2 anford ite CO Cl PL s ts~evasw>F ss sss~~ss\Sssssss s1s~o j~)I)F~ly@CPA'ASST')LVFF$
The above comparisons of 1990 TLD results to preoperational            and previous operational data and the analysis of results by meteorological sector and distance from the plant demonstrate that Plant 2 operations have not impacted the direct radiation levels in the environment around the plant.
SU6$ASS)~s 51 r"~~sssw wsswsssw 5'OSSSSL , OOCWOOO w))Sll SO.I)mw\sww~ssssv.I))))CGER sIF E W.~OSSSSSSS P'sSSSSSOIL
5.2         r                      n The  results  of the    1990  gross  beta  in air analyses    are  presented  in Tables A-2.1 and A-2.2     of Appendix A. The 1990 mean weekly results of all indicator stations are      plotted in Figure 5-10. The gross beta in air results for  1990 were    within the ranges observed during the preoperational 5-3
~SsSSS'%s ss~II II$ACOSOOR M.))5 FYA WWWWWW))~ALD)R R55)HRwrww s 5%%%%)\))).}ww ss)I K Fs)LO NL)))ssssss.ss BENTON CITY FAT ROP)RY M.Benton County 224 12 WEST RICHLAND RICHLAND AIRPORT)I 1)RICHLAND 182 PASCO Franklin County LEGEND~PAVCD ROAD~55PRVD RD OR CRVL ROAD~FOORDRY LFS)$SCAL2~~215L FIGURE 4-1 REHP SAMPLING LOCATIOHS HITHIH THE 10-MILE RADIUS 4-20 o~o
 
~Othello WASH(NGTON Priest Rapids Dam Hanford Reservation WNP-2 10 mile radius e Connell 38A Lower Monumental Dam Lyons~Feny Vttfe Goose Dam Snake River~Pomeroy Lower Granite Dam Ctarkston~462~9C~Sunnyside ggB+9A West k lttdda>>fllctdnnd g sfJ 3 Grandvtow t3onton Pasco 8 96~Prosser 37A,B~~~Kennewtck 4 Eureka lce Harbor Dam~Dayton IDAHO~Walla Walla McNary Dam OREGON Cotumbia R'v'Inch~16 mlles 0 8 16 L Sample Locations 900266 A April 1991 FIGURE 4-2 REMP SAMPLING LOCATIONS OUTSIDE THE 10-MILE RADIUS
period and during previous operational periods, as shown in Table 5-1 and in Figure 5-11. As observed pr'eviously, gross beta levels increased during periods of inversion occurring in the fall and winter months. In fact, the gross beta results plotted over a period of several years (Figure 5-11) show a cyclic pattern        of'all    and winter increases.      The increase,  which was
~s~e STATION 9B II INDEPENDENCE RD SUNNYSIDE FACTORY RD STATION 9A[+0 0 AIR+TLO f sou.VEGETABLE I-82 STATION g 96g z FORSELL RD STATION 9C RAY RD 0 0 McCREADIE RD GRANDVIE MABTON 2!R m 0 m YAK 22 I-82 I-82 PROSSER SCAI E IN MILES 0 1 2 3 4 5 6 880188 FIGURE 4-3 REMP SAMPLING LOCATIONS IN THE SUNNYSIDE/GRANDVIEH AREA TDYAK91A AuRR19AQB ROUTE I IA 240 L~BFO 10mi Radius SI.$)III CHf STRUT I I BASIN CITY III I SHf FRflD RO.<<m L J I pf 64'VSSICC I I OAYCC CJL WO WWWWWW&W.JVHRI R RO.r rlw@r l~g I r~RAC 9&#xb9;CHCA4HCC WA1ACCCC IMPITHO HATClCAY I I',)91 gs I~19 19 67 1461 1 1 I I I L~~I I I I O WVC IWCCADI 66 I I L w w a r4 K COAee RD~IC+21~L~49 15~91~51 no~94 I ACATHIWS s$wesT F61 RQ, I II I I I IBfcceweoR.
                                                                                      ~ o evident in the results of all the air sampling locations, including the control location at Station 9A, was likely due to an increase in radon and radon daughter concentrations during the inversions.            In Figure 5-12, plots of the weekly gross beta results for near-plant and remote locations and for the control location at Station 9A illustrate the similarity of the results from all locations.
s 9S 1~Ql FRWY.~~91 I IH Lgs~I AFCOlYWFR RQ I 3 I I Ye r I anford ite%AAVIA 11\VAhg~o CASSAVA O~Og BFA WNKBCVFFS SVBSTATIOH 61 r-~KOWH HJCHUI 4'1~CCHCCC.OOCVOCO NY~ACVAI41N r IAHCCQC+IP a II pwl\Qw wwww CFA DOOWOOO CCCCT.I I I I HHWWW CEDAR I I 46646IWI I\wow&rwwf w%wwww W.~RQ.I I 8 RQ.WW WWHW&lf W&AHHH I 69 I~ACDIR RQ.I<<wwS&wllwwwwIIw s I s 5$I s s I s I)I I I BENTON CITY FAY Benton County 224 WEST RICHLAND RICHLAND AIRPORT RICHLAND Of HT Franklin County LEGEND~9AYED ROAD mme NFRVDRDOR ODYL ROAD 182 BOVHDRY 191IS 82 12 PASCO 8L FIGURE 4-4 INNER CIRCLE TLD LOCATIONS 4-23
The  quarterly gamma analyses of the particulate filter composites, in general,    indicated only the presence of beryllium-7 and potassium-40, two naturally-occurring radionuclides, at levels above detection limits at indicator locations and the control location. The results of the gamma analysis of particulate filter composites are presented in Table A-3. and        1 A-3.2 of Appendix A.
~o~o l~cl 10mi.Radius il I TOYAKSAA AFRCOAOE RPIJTE))A~12 I I 0414/%>~\~lg I I wIHI, I SASSI Wu.I I J Ts"~r r I r gr'I HCCANOSWQRTH RO.I R 170 BASIN CITY 240 44~0 IR IS+4 QD SY 4 158 I 2S 454 524~5 I 45 4S 54 QC++4~14~31 (43 24~4 20$451 NR CCHT.WAIAIHS IHAIIHS HAIOCAY I 14~41 I Ig I I I I Lag I I I I WIST FSI RfL I I I~~~OR s I P RVSSQA P4'C lg I I SAWS TN&0 W.JNIIPFR RO.~&I I anford ite INVbVAS%%%
The  results of the gamma analyses of charcoal        cartridges for  iodine-131 are presented in Table A-4.1. All iodine-131 in          air results for    1990 were less than the 0.01 pCi/cubic meter LLD.
L 0~4 Tr"-y" CH<<14I 0~Og SPA WHffESTVFFS SVSSTATTOH 4 ff: 0, CO 41 r-, e CHCCI,.DOOWOOO~MUAAW I I44444 CR maemeCg Pwm II wwlo&&we~'OOWOTO CVCCT.I I I I I OIOAR I CCKMIIITg<<444RAH I w&wllw&w\ww W,SAO RO.I I 8 Ro.W\%WW I 42 I~AIOIRRL I wS&we Swww&IA s 2$I S s I s sm I I I BENTON CITY Benton County 224 WEST RICHLAND RICHLAND AIRPORT RICHLAND OFMT II Franklin County LEGEND~PAVED ROAD mme 111PRYOROORORYf ROAD)82~SNDORY TDRS FAY 82 12 PASCO FIGURE 4-5 NEAR-PLANT TLO LOCATIONS 4-24 TDYAK65ABARRcHK ROUTE 11A Qr~g&D 10mi.RadluS<I I I I I I Ig IS ys I OATS m LLFLAOWER 5E5 I I J r Iy CHESTHVT I I BASIN CITY SHEFAELD RO.WWWW&W I I pf I RFS eeHT.L THTR5HCS WAKLKS I IIJNTHO HLTDSSY I~&&WAN w.ABSFER Ro.I NOeVXOLEL r 69 0 16~15S lee 1 16 67 eF I~19 2+1~~61 11 Le~e5 I I I L I I I I I le m w w eAe N.COVLEE RO 240 anford ite%WAWA1WAVA
No  evidence of any impact of plant operations on the environment was apparent in the particulate filter and charcoal cartridge results for 1990.
%V'AiiWAN C9 1 pc'W 0 C~66 es es 25 1~e BPA WL ITEBLVFFS n SVBSTATIOH me's~51 n3 EC O, TO z 1 LLI CO QI FFl WY.'H~9 r"-COWN IAIWIAII 51ATTRWS sf sg WEST FR RLL I I I IRuaWeW.I)IF E~%%%~A9VARVS I~ARee LFL+)P II&&W h~62 I~ALDER LED I Awws w I&wlsw s I s If I I s I s sl s')>I w 1\m&wwww eveeT.I I I I r aw HW&I CEDAR I I I w+ws wwww W.AOELMOOR RD.I I B RLL~WWWWW WWWW BENTON CITY FAY Benton County 224 82 WEST RICHLAND 12 RICHLAND AIRPORT R i I RICHLAND Franklin County LEGEND~PAVED ROAD<<we SFPRVDRDORORYL ROAD 182 BOVHDRY LS1ES PASCOFIGURE 4-6 OUTLYING TLD LOCATIONS HITHIN THE 10-MILE RADIUS 4-25 To YAKOIA AARNOACE ROuTE q g A 200 EAST Ie~>>cl 10ml.Radius~I I I I I IR I I, Eep~eeN SAFIACWWER RO.~I~I I s, J~12 ly'RESTNIT I I BASIN CITY+0~O~~2 RAA CONT.4 emANOI WAFCIACI I 1400040 NATOCW I WWWWWW W.JVMIPER RO.I SSNWCCO RO.s 4p'4 r+I 5~i 240 anford ite\\\\\eeeeeeeeeee\
5.3  ~W During the first eight months of 1990 there were frequent periods when sampler inoperability prevented the continuous collection of composite water
Lwvw e epee'bw IE'eeeeee~easel~eeee 1ee I Ojg, 40 0 15~1~1T OF 4 153'30 620 1 03 43 QO~BPA WIEIEECIIIPS SOBSTATSN 0~10~20 I 31~61 23~01 3~24 K O, CO 61 Ql FIR WY.~'H~01 I I~CONN IIASOOIIN 41~~CNOOC.OCCWOCO IY~AOVAVOO I'ARCOCFC~%P II I lt It s I I I I L I I I I I I le a a a ebs IE COEEE RO.~IIATREWS IN s$WEST I Sl RO.I I I I 20544EwEIEE s Mal e&we~CROT.I I I I r AWWWWW CEOAR I I I+wm Tmmamma W.SAOEMCCR RO.I B M.W WWWWW WWWWWW I I~AIDER RO.I I&&&\If w s I s s 55)cene wl I 1E RElO OIL I I I FAY Benton County 224 82 WEST RICHLAND 12 RICHLAND AIRPORT RICHLAND Franklin County LEGEND~PATES ROAO w m e SI PAVO RO OR ORYL ROAO 182~e BONSRYLJIES PASCO FIGURE 4-7 AIR SAMPLING LOCATIONS NITHIN THE 10-MILE RADIUS 4-26
                                                                                      ~ s samples from the discharge line (Station 27). The focus of efforts to meet Technical Specification requirements during these periods was to put the composite samplers back in operation, at least by the end of the next sampling period. The ma]or problems plaguing the system were resolved when sludge was cleared from the sampling line, which carries water from the discharge line to the sampler.            From August to mid-'December the sampler operated normally.         The outage periods and corrective actions taken to remedy the equipment failures are presented in the sample deviations listing in Appendix      D.
~o lj TCY~~ROUTE 11A I~~10 mi.Radius r g FSRAWGSWORTH RO.I Ig I I g I I BAS41 FRA Ra I"r"~j I BEUFTDWER RR I eI I J err I~s lg II R llo SHEFVTELD RO.BASIN CITY~2 FHS CONT.8 SHHWCS WHNJKS IMHTHO HATCHEIIY I OAVTS IFL&WW WW W.RBTDER RO.I aCWWOOO RO.rr 154.I 49 0 15~14 17 9P 1551 1 2S 454 1~19~24 2+1~51 I I I Lwg I I I I~I le w a m ass.NO0%EERD 240 1 95 25 1~+4 3~24 Qg ARWY.~~Ol R WTHEWS CORNER WEST F81 RO.I I anford ite CO O C.~~1 f W 4,~4O9395.OOOWOCO~CHOOI 5H44T.IIF E 4&W%$&W I I I I r WWW&%%CEDAR Vh'a\I\\\\%\%\%1 I L SPA W15TEFWFFS gSVBSTATQN 4 1T: O CO a8 HD AACA~AOHHVS I~AH544ll ww eCg(Law w II I I')>I W.SAGEMOMRD.
To  resolve other operational problems associated with the discharge sampling system,    two new samplers which do not rely on an external pump to supply sample water will be installed in the river pumphouses during the 1991 plant maintenance outage.        The use of two samplers at this location will enable the continued collection of flow-proportional samples when one samp'ler is inoperable.        In addition, a schedule will be developed for periodically clearing sludge from the      sample  line.
I I.8 RD W W&WWW WWW I I~ATDERRO I HWI~s 5$I I I I I)I I I 1990 880334.63 BENTON CITY FAY Benton County 224 82 12 WEST RICHLAND RICHLAND AIRPORT RICHLAND H 3 PASCO Franklin County LEGEND~PAVED ROAD w~~NPRVD RD OR ORVL ROAD~BOOHDRY IBTES FIGURE 4-8 RIYER/DRINKING AND DISCHARGE WATER SAMPLING LOCATIONS WITHIN THE 10-MILE RADIUS 4-27  
When  these    composite samplers    were not operational, grab samples were often taken    as  a  matter of "good practice," in order to estimate radionuclide 5-4
 
concentrations    in the water when flow-proportional sampling was not feasible. The  results of the grab samples taken during these periods are presented in Table C-1 of Appendix C.
The  gross beta in river/drinking (including intake) and discharge water results are given in Tables A-5.1 and A-5.2 of Appendix A. All river/
drinking wa'ter results were within the ranges normally observed and less than 8 pCi/liter, the level at which a strontium analysis is performed to verify compliance with the Washington State drinking water standard for strontium-90*. A graph of the gross beta in river/drinking water results during 1990 is presented in Figure 5-13. The gross beta in river/drinking water results from 1984 to 1990 are presented in Figure 5-14. The higher levels observed in the Richland water results in early 1986 and 1987 are due to the use of well water, instead of river water, during the annual maintenance outage of the Richland Water Treatment Plant.
The  1990 gross  beta levels in the discharge water were slightly lower than most    previous levels observed since the last ha'lf of 1986, as shown in Figure 5-15.      The average gross beta result for 1990 was 15,8 pCi/liter, compared to the 1989 average of 30.9 pCi/liter. This lower gross beta level resulted from the current mode of plant operations using less concentrated circulating water, i.e., lower cycles of concentrati'on.            The gross beta levels in the discharge sample reflect the concentrations of naturally-occurring radionuclides, principally potassium-40, and any radionuclides from upstream sources or past Hanford activities present in the makeup water, in addition to radionuclides from Plant 2 discharges.           The discharge sample results are representative          of the radioactivity present in plant discharges before any mixing with river water occurs. Therefore, the sample is not indicative of the actual radionuclide concentrations in the river water downstream from Plant 2.              This conservative approach of flow-proportional composite sampling from the discharge line in lieu of sampling from the river near the downstream edge of the mixing zone (as required by Technical Specifications) was considered to be the most feasible option.
However, careful interpretation of the results from this sampling point is necessary, since they do not represent a true environmental sample.
The    1990 gross beta results      for  the  discharge sample are  presented    in Figure 5-16.      The    temporary,    or    interim, DOH investigation        level (75 pCi/liter) which prompts an investigation into the results is shown for comparison, so that these gross beta levels can be put into perspective.
Also shown is the maximum annual average gross beta level in ~i Qgg              ~w for compliance to the 4 mrem per year state dose limitation, 50 pCi/liter.
The  tritium results for river/drinking water, discharge water and ground-water are presented in Tables A-6.1 and A-6.2 of Appendix A. The tritium levels in the river/drinking water were all at or slightly above the LLD for that analysis, as shown in Figure 5-17. All the results were within the range normally observed in such water and within the range of the pre-operational and previous operational results for the same stations.
*Strontium-90 is assumed to account for the gross beta result.
 
The    tritium levels in the discharge                    water    were higher than the levels observed      for the river/drinking water              samples  because of plant releases.         As shown in Figure 5-18, they were consistent with the levels observed for the.
past several years.               The levels are reasonable          for samples taken directly from the, discharge line prior to any river dilution. Compared to the annual average      concentration of less than 20,000 pCi /liter of tritium for g~Qng r to be in compliance with the state dose limitation, the'esults were
~w
~low.   ")    A graph of the discharge water tritium levels for 1990 alone is presented in Figure 5-19.
The  tritium results for            the quarterly, groundwater samples were            all" below  the LLD. They are presented in Table A-6.1 of Appendix A.
The    results of gamma isotopic analyses on river/drinking water, discharge water and groundwater are listed in Tables A-7.1 and A-7.2 of Appendix A.
The results of grab samples taken during composite sampler inoperabi.lity are presented in Appendix C. All results for the river/drinking water and ground water samples were less than detection limits. All results for discharge water samples were also below the detection levels, except the result for cobalt-60 in the 5/16-6/13 routine composite sample (8.6 pCi/liter) and cobalt-60, zinc-65, cesium-134 and cesium-137 (11.0, 21.0, 7.6 and 9.7 pCi/liter, respectively) in one composite of discharge water grab samples taken during May.                     Although above detection levels, these results were      low  and    did  not  exceed  any reporting levels.
e.
                              \
5.4   5gQ Gamma    spectrometry        was    performed on five soil samples collected in May.
The cesium-137          levels in the samples ranged from 32.9 pCi/kilogram to 493 pCi/kilogram. Aside from cesium-137, the only radionuclides detected in the samples were potassium-40, radium-226 and thorium-228, which are part of the natural radioactivity typically found in soils. As shown in Table 5-1, the cesium-137 levels in the soil samples were well within the range observed during preoperational and previous operational sampling.
The    gamma    spectrometry          results for the        'oil indication samples of are  given of Plant in Tables    A-8.1    and  A-8.2      in  Appendix  A. No                      impact              2 operations on the environment was evident in these results.
5.5     h    1 n        i    n The    results of        gamma spectrometry of shoreline              sediment are presented in Tables    A-9.1 and A-'9.2 in Appendix A. Aside from the naturally-occurring radionuclides (potassium-40, radium-226 and thorium-228), only cesium-137 was detected        downstream of the plant (Station 34).                     Cesium-137 was also detected in the control location                      (Station    33)  sample.     The cesium-137 concentrations upstream              from  the  plant    discharge    point  were  90.8 and 115 pCi/kilogram; the            concentrations      downstream    from  the  discharge    point were 182 and      197    pCi/kilogram.          These  are  consistent      with  the  concentrations observed previously.              A graph of the cesium-137            results in sediment from 1984 to 1990 is presented in Figure 5-20.
5-6
 
Cesium-137    has  been  detected in preoperational samples and in samples taken since plant operation began. 'It has also been previously identified as a component of the Columbia River sediment originating from the operation of the old Hanford Reservation      reactors.~'.
~Fi The gamma    spectrometry results of fish samples collected in the vicinity of the Plant 2 discharge and at the control location on the Snake River are presented in Tables A-10.1 and A-10.2 of Appendix A. All results were below detection limits, except for potassium-40, a naturally-occurring radio-nuclide, and cesium-137.          The detectable  cesium-137 levels for the fish taken from the Columbia River were within the range observed during the preoperational    and  previous operational periods.
: 5. 7  ~Mi 1 All the results of iodine-131 analyses of mi'lk        samples collected during 1990 were less  than detection limits. The routine iodine-131 in milk results are listed in Tables A-l.l.l and A-11.2 of Appendix A. A graph of the 1990 iodine in milk results is presented in Figure 5-21. The gamma spectrometry results for the same milk samples are listed in Tables A-12.1 and A-12.2.
All results for the indicator and control locations were less than the detection limits.
5.8      r n P The gamma  isotopic analysis results for all root, fruit and leafy vegetables were below    detection limits. The results of all produce samples, including the apples collected from Station 91 and the cherries collected from Station 61, are listed in Tables A-13.1 through A-15.2 of Appendix A.
5-7
 
TABLE 5-1 BAD                            T      N  T                            T V          A Y HEDIA/ANALYSIS (a)
P    T A()()                (d)
HEAN      (RANGE)            HEAN        (RANGE)            HEAN          (RANGE)
Air:    pCi/m Gross Beta        <0.02  (<0.003  0. 130)    0.03   (0.00  - 0.74)          0.01   (0.02 - 0.04)
I-131(')          <0.05  (<0.01 - 0.11)      0.01    (-0.04  0.82)          0.00    (-0.07 - 0.02)
Gajnna Cs-134        <0.01 (<0.001  - 0.040)    0.001  (-0.002  - 0.015)      0.0000 (-0.0004  -  0.0003)
Cs-137          <0.01 (<0.001  - 0.040)    0.002  (-0.001  - 0.036)      0.0001 (-0.0004  -  0.0003)
Ru-103        Not Reported                0.001  ( 0.000  - 0.019)      0.0000 (-0.0006  -  0.0004)
River/Drinking Mater:    pCi/1 Gross Beta        <3.0  (<1.0  - <6.0)      2.1    (-0.2  - 9 ~ 1)         1.7    (0.6  2.9)
Gannna Cs-134          <3.8   (<1.0 - <12.0)      0.5    (-3.6  - 5.2)          0.2    (-3.1 - 3.8)
Cs-137          <4.1  (<1.0 - <13.0)      1.2    (-4.0  - 5.1)          1.3    (-5.7 - 5.7)
Co-58          <5.1  (<1.0 - <25.0)      0.0    (-3.3  - 2.9)        -0.2      (-2.4 - 2  ')
Co-60 Fe-59
                      <4.7
                      <13.3
(<1.0  <13.0)
(<2.0  <93.0) 1.1 0.7
(-4.9 (6.4
                                                                  - 7.1)
                                                                - 6.6) 1.0
                                                                                  -1.0
(-4 ' - 5  ')
(-5.5 - 3.9)
Zn-65          <8.3  (<2.0 - <27.0)      2~3    (-16.0  3.9)          -1.5      (-10.5 - 8.2)
H-3              <481.7 (220  <820)        177.0  (-52.0  596.0)          106.9  (-51.0 - 250)
Sr-90            <2.0                        0.4    (0.3 - 0.7)              Not analyzed Groundwater:    pCi/1 Ganvna Cs-134          <4.0  ( <1.0  <12.0)      0.6    (-F 1  - 5.4)          -0.      (-2.2  - 2.9)
                                                                  - 4 ')
1 Cs-137          <3.8  (0.8  <8.0)        1.1    (-3.1                    1.0    (0.0  2-0)
Co-58          <4.7  (<1.0  - <12.0)    -0.1      (-2.7 - 1.9)          -0.5      (-2.8  - 1.1)
Co-60          <4.1  (0. 1  <9.0)        1.3    (-1.7 - 8.4)            0.7    (-2.4  - 2,4)
Fe-59          <11.6  (<2.0  - <33.0)      0.7    (-4.5 - 5 ')            0.1    (-4.1  - 2.7)
Zn-65          <8.6  (<2 '  - 17.0)    -2.3      (-46 ' - 4.4)          -1.9      (-7.3  - 15.0)
H-3                <467.8 (<10.0  2600.0)    80.7    (-516.0 - 470 ')        20.3    (-100.0- 220.0)
Sr-90            <0.4  (<0. 1  0.7)        Not analyzed                    Not analyzed (a)All stations, all years.
(b)Indicator stations only for the years 1984 to 1989. Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.
(c)The data used for these averages does not include the "less than" values reported in 1984.
(d)Indicator stations only.
(e)Charcoal cartridge results.
5-8
 
5-l (Cont.)
                                                                                                                                ~
TABLE RA                  N        N      T                                            V      )4          Y e
HEDIA/ANALYSIS                        T I    A (b)(c)                (d)
HEAN        (RANGE)              HEAN        (RANGE)            HEAN            (RANGE)
Discharge Water:      pCi/1 Gross Beta        <2.8    (<1.9  4.0)            18.2    (0.6  - 48 ')            15.8  (6.1  35.0)
Gawna Cs-134          <3.7    (<1.0  - <8.0)        0.4      (-3.0 - 5.4)              0.8    (-0.9                    4,4)
Cs-137          <4.7    (<1.0  - 16.0)        1.5    (-1.3 - 7.9)              2.2    (-1.6            - 5.6)
Co-58          <1.4    ( I.O - 13.0)          0.1      (-2.6 - 4.6)            -0 '    (-2.3            - 1.3)
Co-60          <5.0    (<1.9 - <13.0)        2.7      (-8.7  28.2)              1.3    (-1.1              8.6)
Fe-59          <11.9    (<3.0 << <38.0)        0.7      (-3.0 - 6 ')              1.3    (-0.4            - 2.7)
Zn-65          <8.6    (<2.0  27.0)          3.4      (-4.9 - 86.7)            -0.6    (-7.5            - 7.9)
H-3                <420.0  (<80.0  700.0)        1040.0  (60.0  4400.0)            1396.3 (55.0  3400.0)
Sr-90              <3.0                            0.8      (0.5 - 1.1)              Not analyzed Sediment:    pCi/kg Gamma Cs-134        <112.5 (<50.0      -  <150.0)  57.7    (7.0  - 172.0)            74,4  (67.9 - 80.8)
Cs-137        <287.0 (<50.0      -  <560.0) 368.0    ( 153.0  - 1890.0)        190.0  (182.0 - 197.0)
                                          -                    (27.1 - 129.0)                    (14.8 - 15.2)
                                                                                                                                ~
Co-60          <254.6 ( 130.0        610.0)    54.8                                15.0 Co-57          Not Reported                    46.0    (34.0  54.0)                0.5  (-11.6 - 12.5)                  o Eu-152        Not Reported                    143.0    ( 140.0 - 146.0)          85.8    (5 6  166.0)
                                                                                                      ~
Soil: pCi/kg Ganma Cs-134        <65.3 (<20.0    -  <150.0)      29.7 (7.1  53.2)                    17.5  (13.9  23.3)
Cs-137        364.3 (<20.0 - <1880.0)        313.0 (9.4    -  735.0)            287.0  (32.9 - 493.0)
Sr-90            Analysis Not Performed          357.5 (260.0 - 455,0)              Analysis not performed Hi 1k:  pCi/1 Gamna Cs-134          <3 '  (<0.9  -  <14.0)          1.3 (-7.4 - 22.6)                    0.4 (-3.3 - 3.0)
Cs-137          <3.8 (<1.0    -  <12.0)          4.0 (-7.4 - 47.3)                    1.6 (-2.5 - 6.8)
Ba-140        <72. 1 (<6.0  <2000.0)            0.5 (-44.3 - 55.0)              -0.6    (-12.0  9.9)
La-140        <33.3 (<5 '    -  <1000.0)      -0.7 (-24.2  9.7)                -0.3    (-4.5  4.1)
I-131              <0.5 (<0. 1  <1.0)              1.6 (-0.8  - 144.0)              0.0  (-0.3 - 0.4)
Sr-90              Not Reported                      2.2 (-1.3  - 3.9)              Not Reported (a)All stations, all years.
(b)Indicator stations only for the years 1984 to 1989. Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.
(c)The data used for these averages does not include the "less than" values reported in stations only.                                                                            1984.'d)Indicator 5-9
 
TABLE 5-1    (Cont.)
RA          A      V      MENT                                R    V    gAAY (d)
HEOIA/ANALYSIS                P  AT  N            PR          P RA  NA HEAN      (RANGE)          HEAN      (RANGE)        HEAN        (RANGE)
Fish:    pCi/kg Gamma Cs-134        <61.2 (<6.0  <130.0)        1.5 (-20,4  - 14,4)        7.5  (0.0  - 24 ')
Cs-137        <88.8 (<10.0 - <130.0)      13.1 (-35.1  - 54.9)      15.3  (2.5  - 31.4)
Co-58          <87.7 (<9.0  <130.0)        1.5 (-16.8  - 25.8)        0.1  (-8.2 - 6.7)
Co-60          <80.6 (<9.0  <130.0)        0.5 (-18.4  - 19.1)      -0.8  (-7. - 7.0) 1 Fe-59        <130.0 (<30.0  <260.0)      -2.1 (-34.6  - 21.1)        7.2  (-10.2 - 30.0)
Hn-54          <88.3 (<8.0  <130.0)        2.0 (-10.3  - 30.9)        1.0 (-7.4 - 7.9)
Produce:    pCi/kg Galena Cs-134        <49.1 (<10.0  - <  140.0) ~ 1.4  (-24.8 - 19.8)      1.3  (-12.0  -  17.0)
Cs-137        <69.8 (<10.0  - < 140.0)    4.3  ( -9.8  20.9)      5.6  ( -3.6  -  15.0)
I-131        <105.6 (<10.0  - <1000.0)    1.2  (-21.3 - 59.0)      -4.0  (-12.0  -            3.5)
TLO:    mR/day
()uarterly        0.24 (0. 11  0.32)        0.24 (0.16  -  0.35)      0.26  (0.23  0.32)
Annual            0.23 (0.20 - 0.31)        0;23 (0.18  -  0.32)      0.24  (0.22  0.29)
(a)A11  stations, all years.
(b)Indicator stations only for the years 1984 to 1989. Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.
(c)The data used for these averages does not include the "less than" values reported in 1984 stations only.                                                                  'd)Indicator 5-10
 
TABLE  5-2 MPA    N    F T    DYN  NMINA l      W  R    I  T F DET T    N WITH BRAN    H T  HNI A  P    T              NT TELEDYNE        BTP REQUIRED M  IA    NIT            ANA Y                            LD              D Air                  Gross Beta                        0.003              0.01 Partic~lates:        Gamma    Spectrometry (pCi/m  )            Cs-134                            0.001              0.05 Cs-137                            0.001              0.06 Air IotIine:          I-131                            0.01              0.07 (pCi/m~)
Water:              Gross Beta                        4                  4 (pCi/1)              Tritium                        100-200            2000 I-131                            1                  1 Sr-90                              1 Gamma    Spectrometry Mn-54                            10                15 Fe-59                          20                30 Co-58                            10                15 Co-60                            10                15 Zn-65                          20                30 Zr-95                            20                30 Nb-95                            10                15 Cs-134                            10                15 Cs-137                            10                18 Ba-140                          20                60 La-140                            10                15 Soil/                Gamma    Spectrometry Sediment:            Co-57                          120 (pci/kg)            Co-60                            30 Cs-134                          30                150 Cs-137                          40                180 Sr-90                            10 Fish:                Gamma    Spectrometry (pCi/kg)            Mn-54                            20                130 Fe-59                            30                260 Co-58                            20                130 Co-60                            20                130 Zn-65                            30                260 Cs-134                          20                130 Cs-137                          20                150 5-11
 
TABLE  5-2 (Cont.)
PAR N  F T  EDYNE N MINAL    HER    IMIT  F D T  TI  N THBANHTEHIA          P  IT      RE    M  T TELEDYNE        BTP REQUIRED M    A  N T                                    L D                D Ml lk:            I-131                        0.5 (pc1/1)          Gamma  Spectrometry Cs-134                      10                  15 Cs-137                      10                  18 Ba-140                      20                  60 La-140                      10                  15 Sr-90                        1 Garden            Gamma  Spectrometry Produce:          Cs-134                      20                  60 (pC1/kg)          Cs-137                      20                  80 I-131                        30                  60 5-12
 
T        5-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                      DOCKET NO. 50.397 HANFORD WASHINGTON                                JANUARY 1  to  DECEHBER  31, 1990 ANALYSIS ANO  LONER  LIHIT                                                                                          NUHBER OF HEOIUH OR PATH'NAY      TOTAL NUHBER        OF                                                                          CONTROL LOCATION    NONROUTINE SAHPLEO            OF ANALYSES    OETECTION          HEAN (b)(a)                  NAHE                HEAN (b)(a)      HEAN (b)(a)    REPORTEO (UNIT OF HEASUREHENT)    PERFORHEO          LLO)          RANGE                  OISTANCE ANO DIRECTION                      RANGE            MEASUREHENTS AIR PARTICULATES      Gross Beta    624 0.003          0.013(563/572)          5                      0.014(52/52)            0.012(51/52)
(pCI/$3)                                                {0.002-0.059)                                  {0.004-0.059)          {0.002-0.03)
Gamma        48 (Ouarterly)
Be-7                0.01          0.055(44/44)            48  4.5  mI  NE      0.068(4/4)              0.047(4/4)
(0.034-0.091)                                  (0.039-0.080)          (0.036-0.060)
K-40                0.01          0.006(6/44)            48  4.5 RI    NE    0.008(1/4)                0.005(l/4)
(0.005-0.008)
Cs-137              0.01          LLD                                                                        LLD Cs-134            0.001          LLO                                                                        LLD AIR IODINE            I-131    624      0.01          LLD                                                                        LLD (pC1/$ 3)
(a) "(b)  ls the ratio of posltlve results above the.ttO to the number of samples analyzed For the parameter of Interest.


To Y~~ROIJTE 11A~12 sg I I II I s~II B.p BGFFOWWER RD.I 44 s 44 IH~>>10 mi.Radjus I I I R 1 70 BASIN CITY+o~O~49 0 4 15S ASH 15~1~2 14 ST I~19 210L 22'T>>'FHS CONT.SHIHAHCS WHCAHS SHAITHO NATCHOAY I I"";I I I I I L~g I I I I WWWW W W.40IPER M.I BTOHWOOO RO, u93~W s~g I 240 I 93 SS 25'I~3~24 Ql FFIWY.~~91 EAATHEWS sf III WEST FST M.I I I I~BE1AEVOE ESE s anford ite C3 0 41 41'3 r-~SCHOOL COO WOOD IY p'al SCOTT.I I I I r W I+'EDAR OWNIHTQ CHH\HAN CNNI HA Ofg BPA WHREBENTS gSUBSTATICH 4 EE Cl CO I iAHSSCIL w m m eJCpPw w II I s I W.SAOEMOOR RO.I I B RO.WWW W WAWWWW I 42 I~ATOER RO.I HHHI w%w gQQAA'lf&s I)I s s sI I I I 1990 880334.63 BENTON CITY FAY Benton County 224 82 WEST RICHLAND 12 RICHLAND AIRPORT RICHLAND Franktin County LEGEND~PAVED ROAD~BAPRYO RO OR ORYL ROAD 182 BOAOBNTY ERIES PASCO FIGURE 4-9 GROUNDHATER SAMPLING LOCATIONS 4-28 TO VAICSIA BAIVHCADE ROUTE I I A I HIaaB 10mi.RadiuS~1 I I HCEANGSWORTH RD.I I Ig OATS I Ig Pc a a a a Bc@aav I ETAFTDWWER ISA rr r I Oe r I Iy CHESTNVT I I I/fan BASIN CITY FFN CCHT.DIHVHCS WHCAIKC IHwTHS HATOCHV I ac aa W.RINIPER RO.I NINWOOO m.leev 0 240 44 0 14~14 4 14SH 4SH~2 14 ST Tel JS I SS 44 QP~~14 21~41 ISQH Ql FSTWV.~~41 I I I Lag I I I I I I I N.COIAEE RO.m I 45 WEST f IR RO.I I I I IBOAEYVEoa s anford ite C\%%%C%%CV1\%\a i~CS I TE~0~aaNK~o cAccl Ia hpg Cr@BPA WHREBEVFFS gSVBSTATON 4 K O CO z lV 41 f~DHH HAICHAH 41~SCHOOA.DOGWOOD KF'\iY r'cAOVAIHAS I cAHce DIE a a a eCpia a II P.I Cl s I>I'lcaa a~veev, I I I I r r aa\+'EDAR I COUhNIAQ I CIWellAH I anal aaaaaa W.AGFEMOCR RO.I I 8 RD.\aaaa aaaaaa I 42 I~AIDER RD.I aa I Iaaaa s I s s I s I)}.I~I I BENTON CITY FAY RVPERT RO.Benton County 224 82 12 WEST RICHLAND RICHLAND AIRPORT RICHLAND R Franklin County LEGEND~PATED ROAD a a c BAPRYD RD OR GRYL ROAD 182<<~SOVNDRY EBIES PASCO FIGURE 4-10 SOIL SAMPLING IOCATIONS HITHIN THE lOaMILE RADIUS 4-29 To Y~~ROUTE 11A~12 I HCAAWGSWORTH RO.I+p~~L ww w~RD.I I grigglO 10mi.RadiuS<I.I III CHESTNUT I BASIN CITY 1 4 THTAAHOS WAKllc4 I MJITHO HITOHAY I WWWW W.AMBER RD.I RCHWOOO Te.I 240 4S O 16~14 47~2 SS 43 26 I~~I I 23$~IS~20 2+I~I 31~ST 50 3~24 Ql FRWY.~~SI I I I L~g I I I I I IIATHEWS I$CORNEA Ig 65 WEST FR RO.I I I~SIIAEYVS Da I I anford ite.AVIVA\1%WAVA 0 SPA WTlESBVFFFS gSVSSTATTON
'ATTI>>K ES, HI IIT AATA 41 41~43 r~SOWN IWIOIAII IOHOOl.DOGWOOD iY~AOOAHOS~~AHSSOA ,II II W%\0 W\<<44T.I I I I r QRHWHW'CEDAR I I I I wwwwww W.SAGEMOMTO.
I I I RD.WP W~&&WAN I 42 I~AIDER RD.I anal a Qeaeeila I I 1990 880334.63 BENTON FAY Benton County 224 82 WEST RICHLAND 12 RICHLAND AIRPORT RICHLAND Franklin County LEGEND~SAYED ROAD~SIPRYD RD OR ORYL ROAD 182 SOVHTHW TSIES PASCO FIGURE 4-11 SEDIMENT SAMPLING LOCATIONS 4-30 ROUTE 11A l~ie ERD 10mi.Radius~I lj I I I IIII I I I J RHC CCHI, CHIHHHS WIICIAN R 110 R VSSEEL sg DAVIS EN I I ae a a a W.JNIPER RL 5555'a Iaal I llAHI440 HAICHQlY I~2 BASIN CITY 49 0 15~4 15S 4Se 15 57\IS+~19 21~51 10 I I I Lag I I I I I I I<<aaeAe N.CONES RL 240 I~DS~24 Qs FFCWY.~~91 NA THEWS 4 WESTFSIRD.I I I SRAEVDSOCE S I anford ite 41~CDHN lQNOWI CCHCCC.DOGWOOD w I E555 RD.Ie a%e el a a a a CCeCI.I I I I CEDAR 0 Saveeee eeeeeeeeeee eeee\ewA 1 0 eeelle BPA WHlTE8WFFS TATNN 5~gSOSS I EE O CO~40 51 a i JOUHVCS se i AICCC NC s I a a a eJCge Ie a a 8s,~II a+I CCWNIRTg I CHCCCHAH I aS aaaaaa W.SAGEMOQRM, I I 8 RD.aaaaa I I 4~~.I aa>>S a Qa a a a I I 1890 880334.63 BENTON CITY 8 FAY Benton County 224 82 WEST RICHLAND 12 RICHLAND AIRPORT RICHLAND R Frankl n County LEGEND PAVED ROAD a e BCPRYD RD OR ORVL ROAD 182 BONIDRY 58CES PASCO FIGURE 4-12 MILK SAMPLING LOCATIONS HITHIN THE 10-MILE RADIUS 4-31
~o~o During 1990 the analyses of REMP samples were performed by Teledyne Isotopes in Hestwood, New Jersey.The thermoluminescent dosimeters were processed by the Supply System External Dosimetry Laboratory.
Table 5-1 presents the means and ranges of the 1990 results for each type of sample collected.
The means and ranges of the preoperational and the previous operational data from 1984 to 1989 are also included in the table for comparison.
The data for the preoperational period and the first six months of 1984 included"less than" (<)designations for results below the actual LLD, the contractual LLD or the two sigma error, depending upon the convention employed by the analytical contractor.
Consequently, the data averages using"less than" values are biased high.The use of the"less than" designation was discontinued in mid 1984.Since then, REMP data have.been reported as net results, i.e., total (gross)results minus the detector counting background.
Comparison of the mean results for 1990 to the mean preoperational results is difficult due to the high bias resulting from the"less than" data.However, comparison of the range of results observed for each period to determine whether the 1990 results are significantly greater than the results for preoperational and previous operational periods, is a viable approach.Careful interpretation of the data ranges for the previous operational data is still required because of the effects of the Chernobyl accident in 1986.For this report only the data from the last six months of 1984 were included in the previous operational data in order to eliminate the"less than" values in that category of summary data.The 1990 REMP data compares well to the ranges of data from previous periods.The quarterly TLD results for 1990 were very close to the 1989 results and slightly lower than the 1987 and 1988 results.These slight changes in the TLD results are certainly within the normal range of uncertainty expected for TLD systems.The 1990 annual TLD results were about 5-101.lower than the mean quarterly results.This relationship between the two TLD distribution types has been observed in nearly all the previous years.It is apparently due to slight fading of the TLD signal on the TLDs kept in the field for the entire year.The LLDs generally determined by Teledyne Isotopes for each analysis performed and each radionuclide of interest are listed in Table 5-2.Presented alongside the Teledyne)LDs are the LLDs required by the NRC Branch Technical Position (BTP).('he LLDs determined for analyses at Teledyne Isotopes have met the NRC requirements in all cases.A summary of the REMP results relative to detection limits is presented in Table 5-3.If a particular radionuclide of interest was not detected in the 1990 samples, the term"LLD" is noted in the data mean and range columns.Aside from some naturally-occurring radionuclides, the radionuclides detected in the 1990 sample included cesium-137 in fish, soil and sediment, 5-1 and cobalt-60 in the discharge water;tritium was also detected in some water samples.Gross beta results in air and water were nearly all above the detection limits.In general, the positive, or detected, 1990 results compare well with the results from previous years.Any significant differences or increases evident in the 1990 results are discussed in the following subsections.
Summaries of the environmental radiation exposure rates, determined by thermoluminescent dosimeters (TLDs)are presented in Tables 5-4 and 5-5.The individual quarterly and annual results for each TLD station are given in Tables A-l.l and A-1.2 of Appendix A.Figures 5-1 and 5-2 show the mean quarterly results for near-plant and remote TLD locations for the preopera-tional period, 1984-1989 and 1990.Figures 5-3 and 5-4 show the annual TLD results for near-plant and remote locations for the same periods.In general, the quarterly and annual results for the control location (Station 9A)show the same fluctuations over time as the indicator locations and the relationships between the different locations remain very consistent over the three periods.Figure 5-5 presents th'e mean 1990 results for each of the sixteen meteoro-logical sectors, compared to the sector means for the preoperational and previous operational periods.The relationship of the mean 1990 results to the results for the preoperational and previous operational periods is very similar for each sector.This indicates that there were no significant directional effects observed in the 1990 TLD results.The annual TLD results for each sector also follow the same pattern as the mean quarterly results, except they are 5-101.lower.In Figure 5-5, the apparent increase in the mean 1990 TLD results over the means of the preoperational and previous operational periods is due to the effect of averaging only the four quarters of 1990 data versus averaging numerous quarters for the other two sets of results.The differences between the data sets are generally within 101., which is within the range of variation normally expected for TLD systems.Station 46 in the Hahluke Reserve remained the location with the highest mean exposure rate, 0.31 mR/day.This is the same mean exposure rate deter-mined for that station for 1989.Since the preoperational measurement phase, the results for this location have exceeded the results for all other locations.
Variations in the ambient background due to variations in the soil and underlying rock composition account for such local differences in the TLD results.Figure 5-6 compares the Station 46 results to the results of Station 9A, the control location, from 1982 to 1990.The relationship between the results at these two locations has remained fairly consistent from the preoperational period (1982-1983) to the present.5-2 A comparison of the 1990 annual and mean quarterly TLD results is presented in Table 5-6.The 1990 annual TLD results are generally 5-101.lower than the mean quarterly results because of the signal fading characteristics of CaSo4.This difference is not significant, in light of the variability commonly observed in TLD results.In most cases, the annual result is within the uncertainty associated with the quarterly TLD results.During 1990, a test was performed to determine whether one set of TLDs that had been used in the past for the annual measurements had a higher TL signal fade rate over time than the other sets used for the same purpose.The higher fade rate was suspected because during the years when the set was used, e.g.1988, the mean quarterly results and the annual results differed by approximately 15-201..As described in Section 4.0, the test involved collocating nine of the suspect TLDs with nine of the TLDs that had not exhibited a high fade rate.At the end of the year, when these two groups were processed, the mean result of the suspect TLD group was 121.lower than the other group.As discussed previously, all the TLD sets appear to exhibit some TL signal fading, normally amounting to about 51..But the fading of the suspect group was significantly more than that, so the set will no longer be used.The log probability plots of the 1990 and previous operational (1984-1989) quarterly TLD results are presented in Figure 5-7.The"slopes" of the lines in both plots are nearly the same, indicating that both sets of data are part of the same distribution.
The log probability plots of the 1990 annual results and the results from previous years of operation are presented in Figure 5-8.The 1990 results are consistent with results observed for the past monitoring periods.The slopes of the lines determined for this.data are typical for ambient radiation measurements.
The log probability plots of the quarterly data for a near-plant locations, Stations 71-76, and the control location, Station 9A, from 1982 to 1990 are presented in Figure 5-9.The linearity of the plots indicates that the results are all within the same log normal distribution and that no significant increases or decreases indicating a change in the environmental radiation levels were evident.The above comparisons of 1990 TLD results to preoperational and previous operational data and the analysis of results by meteorological sector and distance from the plant demonstrate that Plant 2 operations have not impacted the direct radiation levels in the environment around the plant.5.2 r n The results of the 1990 gross beta in air analyses are presented in Tables A-2.1 and A-2.2 of Appendix A.The 1990 mean weekly results of all indicator stations are plotted in Figure 5-10.The gross beta in air results for 1990 were within the ranges observed during the preoperational 5-3 period and during previous operational periods, as shown in Table 5-1 and in Figure 5-11.As observed pr'eviously, gross beta levels increased during periods of inversion occurring in the fall and winter months.In fact, the gross beta results plotted over a period of several years (Figure 5-11)show a cyclic pattern of'all and winter increases.
The increase, which was evident in the results of all the air sampling locations, including the control location at Station 9A, was likely due to an increase in radon and radon daughter concentrations during the inversions.
In Figure 5-12, plots of the weekly gross beta results for near-plant and remote locations and for the control location at Station 9A illustrate the similarity of the results from all locations.
~o The quarterly gamma analyses of the particulate filter composites, in general, indicated only the presence of beryllium-7 and potassium-40, two naturally-occurring radionuclides, at levels above detection limits at indicator locations and the control location.The results of the gamma analysis of particulate filter composites are presented in Table A-3.1 and A-3.2 of Appendix A.The results of the gamma analyses of charcoal cartridges for iodine-131 are presented in Table A-4.1.All iodine-131 in air results for 1990 were less than the 0.01 pCi/cubic meter LLD.No evidence of any impact of plant operations on the environment was apparent in the particulate filter and charcoal cartridge results for 1990.5.3~W During the first eight months of 1990 there were frequent periods when sampler inoperability prevented the continuous collection of composite water samples from the discharge line (Station 27).The focus of efforts to meet Technical Specification requirements during these periods was to put the composite samplers back in operation, at least by the end of the next sampling period.The ma]or problems plaguing the system were resolved when sludge was cleared from the sampling line, which carries water from the discharge line to the sampler.From August to mid-'December the sampler operated normally.The outage periods and corrective actions taken to remedy the equipment failures are presented in the sample deviations listing in Appendix D.To resolve other operational problems associated with the discharge sampling system, two new samplers which do not rely on an external pump to supply sample water will be installed in the river pumphouses during the 1991 plant maintenance outage.The use of two samplers at this location will enable the continued collection of flow-proportional samples when one samp'ler is inoperable.
In addition, a schedule will be developed for periodically clearing sludge from the sample line.When these composite samplers were not operational, grab samples were often taken as a matter of"good practice," in order to estimate radionuclide
~s 5-4 concentrations in the water when flow-proportional sampling was not feasible.The results of the grab samples taken during these periods are presented in Table C-1 of Appendix C.The gross beta in river/drinking (including intake)and discharge water results are given in Tables A-5.1 and A-5.2 of Appendix A.All river/drinking wa'ter results were within the ranges normally observed and less than 8 pCi/liter, the level at which a strontium analysis is performed to verify compliance with the Washington State drinking water standard for strontium-90*.
A graph of the gross beta in river/drinking water results during 1990 is presented in Figure 5-13.The gross beta in river/drinking water results from 1984 to 1990 are presented in Figure 5-14.The higher levels observed in the Richland water results in early 1986 and 1987 are due to the use of well water, instead of river water, during the annual maintenance outage of the Richland Water Treatment Plant.The 1990 gross beta levels in the discharge water were slightly lower than most previous levels observed since the last ha'lf of 1986, as shown in Figure 5-15.The average gross beta result for 1990 was 15,8 pCi/liter, compared to the 1989 average of 30.9 pCi/liter.
This lower gross beta level resulted from the current mode of plant operations using less concentrated circulating water, i.e., lower cycles of concentrati'on.
The gross beta levels in the discharge sample reflect the concentrations of naturally-occurring radionuclides, principally potassium-40, and any radionuclides from upstream sources or past Hanford activities present in the makeup water, in addition to radionuclides from Plant 2 discharges.
The discharge sample results are representative of the radioactivity present in plant discharges before any mixing with river water occurs.Therefore, the sample is not indicative of the actual radionuclide concentrations in the river water downstream from Plant 2.This conservative approach of flow-proportional composite sampling from the discharge line in lieu of sampling from the river near the downstream edge of the mixing zone (as required by Technical Specifications) was considered to be the most feasible option.However, careful interpretation of the results from this sampling point is necessary, since they do not represent a true environmental sample.The 1990 gross beta results for the discharge sample are presented in Figure 5-16.The temporary, or interim, DOH investigation level (75 pCi/liter) which prompts an investigation into the results is shown for comparison, so that these gross beta levels can be put into perspective.
Also shown is the maximum annual average gross beta level in~i Qgg~w for compliance to the 4 mrem per year state dose limitation, 50 pCi/liter.
The tritium results for river/drinking water, discharge water and ground-water are presented in Tables A-6.1 and A-6.2 of Appendix A.The tritium levels in the river/drinking water were all at or slightly above the LLD for that analysis, as shown in Figure 5-17.All the results were within the range normally observed in such water and within the range of the pre-operational and previous operational results for the same stations.*Strontium-90 is assumed to account for the gross beta result.
The tritium levels in the discharge water were higher than the levels observed for the river/drinking water samples because of plant releases.As shown in Figure 5-18, they were consistent with the levels observed for the.past several years.The levels are reasonable for samples taken directly from the, discharge line prior to any river dilution.Compared to the annual average concentration of less than 20,000 pCi/liter of tritium for g~Qng~w r to be in compliance with the state dose limitation, the'esults were~low.")A graph of the discharge water tritium levels for 1990 alone is presented in Figure 5-19.The tritium results for the quarterly, groundwater samples were all" below the LLD.They are presented in Table A-6.1 of Appendix A.The results of gamma isotopic analyses on river/drinking water, discharge water and groundwater are listed in Tables A-7.1 and A-7.2 of Appendix A.The results of grab samples taken during composite sampler inoperabi.lity are presented in Appendix C.All results for the river/drinking water and ground water samples were less than detection limits.All results for discharge water samples were also below the detection levels, except the result for cobalt-60 in the 5/16-6/13 routine composite sample (8.6 pCi/liter) and cobalt-60, zinc-65, cesium-134 and cesium-137 (11.0, 21.0, 7.6 and 9.7 pCi/liter, respectively) in one composite of discharge water grab samples taken during May.Although above detection levels, these results were low and did not exceed any reporting levels.\5.4 5gQ Gamma spectrometry was performed on five soil samples collected in May.The cesium-137 levels in the samples ranged from 32.9 pCi/kilogram to 493 pCi/kilogram.
Aside from cesium-137, the only radionuclides detected in the samples were potassium-40, radium-226 and thorium-228, which are part of the natural radioactivity typically found in soils.As shown in Table 5-1, the cesium-137 levels in the soil samples were well within the range observed during preoperational and previous operational sampling.The gamma spectrometry results for the'oil samples are given in Tables A-8.1 and A-8.2 in Appendix A.No indication of impact of Plant 2 operations on the environment was evident in these results.5.5 h 1 n i n e.The results of gamma spectrometry of shoreline sediment are presented in Tables A-9.1 and A-'9.2 in Appendix A.Aside from the naturally-occurring radionuclides (potassium-40, radium-226 and thorium-228), only cesium-137 was detected downstream of the plant (Station 34).Cesium-137 was also detected in the control location (Station 33)sample.The cesium-137 concentrations upstream from the plant discharge point were 90.8 and 115 pCi/kilogram; the concentrations downstream from the discharge point were 182 and 197 pCi/kilogram.
These are consistent with the concentrations observed previously.
A graph of the cesium-137 results in sediment from 1984 to 1990 is presented in Figure 5-20.5-6 Cesium-137 has been detected in preoperational samples and in samples taken since plant operation began.'It has also been previously identified as a component of the Columbia River sediment originating from the operation of the old Hanford Reservation reactors.~'.
6~Fi The gamma spectrometry results of fish samples collected in the vicinity of the Plant 2 discharge and at the control location on the Snake River are presented in Tables A-10.1 and A-10.2 of Appendix A.All results were below detection limits, except for potassium-40, a naturally-occurring radio-nuclide, and cesium-137.
The detectable cesium-137 levels for the fish taken from the Columbia River were within the range observed during the preoperational and previous operational periods.5.7~Mi 1 All the results of iodine-131 analyses of mi'lk samples collected during 1990 were less than detection limits.The routine iodine-131 in milk results are listed in Tables A-l.l.l and A-11.2 of Appendix A.A graph of the 1990 iodine in milk results is presented in Figure 5-21.The gamma spectrometry results for the same milk samples are listed in Tables A-12.1 and A-12.2.All results for the indicator and control locations were less than the detection limits.5.8 r n P The gamma isotopic analysis results for all root, fruit and leafy vegetables were below detection limits.The results of all produce samples, including the apples collected from Station 91 and the cherries collected from Station 61, are listed in Tables A-13.1 through A-15.2 of Appendix A.5-7 TABLE 5-1 BAD T N T T V A Y HEDIA/ANALYSIS HEAN (RANGE)(a)P T A()()HEAN (RANGE)HEAN (d)(RANGE)Air: pCi/m Gross Beta I-131(')Gajnna Cs-134 Cs-137 Ru-103<0.02 (<0.003-0.130)<0.05 (<0.01-0.11)<0.01 (<0.001-0.040)<0.01 (<0.001-0.040)Not Reported 0.03 0.01 (0.00-0.74)(-0.04-0.82)0.001 (-0.002-0.015)0.002 (-0.001-0.036)0.001 (0.000-0.019)0.01 (0.02-0.04)0.00 (-0.07-0.02)0.0000 (-0.0004-0.0003)0.0001 (-0.0004-0.0003)0.0000 (-0.0006-0.0004)River/Drinking Mater: pCi/1 Gross Beta Gannna Cs-134 Cs-137 Co-58 Co-60 Fe-59 Zn-65 H-3 Sr-90<3.8<4.1<5.1<4.7<13.3<8.3<481.7<2.0 (<1.0-<12.0)(<1.0-<13.0)(<1.0-<25.0)(<1.0-<13.0)(<2.0-<93.0)(<2.0-<27.0)(220-<820)<3.0 (<1.0-<6.0)2.1 0.5 1.2 0.0 1.1 0.7 2~3 177.0 0.4 (-0.2-9~1)(-3.6-5.2)(-4.0-5.1)(-3.3-2.9)(-4.9-7.1)(6.4-6.6)(-16.0-3.9)(-52.0-596.0)(0.3-0.7)1.7 (0.6-2.9)0.2 (-3.1-3.8)1.3 (-5.7-5.7)-0.2 (-2.4-2')1.0 (-4'-5')-1.0 (-5.5-3.9)-1.5 (-10.5-8.2)106.9 (-51.0-250)Not analyzed Groundwater:
Ganvna Cs-134 Cs-137 Co-58 Co-60 Fe-59 Zn-65 H-3 Sr-90 pCi/1<4.0<3.8<4.7<4.1<11.6<8.6<467.8<0.4 (<1.0-<12.0)(0.8-<8.0)(<1.0-<12.0)(0.1-<9.0)(<2.0-<33.0)(<2'-17.0)(<10.0-2600.0)(<0.1-0.7)0.6 (-F 1-5.4)1.1 (-3.1-4')-0.1 (-2.7-1.9)1.3 (-1.7-8.4)0.7 (-4.5-5')-2.3 (-46'-4.4)80.7 (-516.0-470')Not analyzed-0.1 (-2.2-2.9)1.0 (0.0-2-0)-0.5 (-2.8-1.1)0.7 (-2.4-2,4)0.1 (-4.1-2.7)-1.9 (-7.3-15.0)20.3 (-100.0-220.0)Not analyzed (a)All stations, all years.(b)Indicator stations only for the years 1984 to 1989.Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.(c)The data used for these averages does not include the"less than" values reported in 1984.(d)Indicator stations only.(e)Charcoal cartridge results.5-8 RA TABLE 5-l (Cont.)N N T V)4 Y~e HEDIA/ANALYSIS T I A HEAN (RANGE)(b)(c)HEAN (RANGE)HEAN (d)(RANGE)Discharge Water: Gross Beta Gawna Cs-134 Cs-137 Co-58 Co-60 Fe-59 Zn-65 H-3 Sr-90 pCi/1<2.8<3.7<4.7<1.4<5.0<11.9<8.6<420.0<3.0 (<1.9-4.0)(<1.0-<8.0)(<1.0-16.0)(I.O-13.0)(<1.9-<13.0)(<3.0<<<38.0)(<2.0-27.0)(<80.0-700.0)0.4 1.5 0.1 2.7 0.7 3.4 1040.0 0.8 (-3.0-5.4)(-1.3-7.9)(-2.6-4.6)(-8.7-28.2)(-3.0-6')(-4.9-86.7)(60.0-4400.0)(0.5-1.1)18.2 (0.6-48')0.8 (-0.9 2.2 (-1.6-0'(-2.3 1.3 (-1.1 1.3 (-0.4-0.6 (-7.5 1396.3 (55.0 Not analyzed 4,4)-5.6)-1.3)-8.6)-2.7)-7.9)-3400.0)15.8 (6.1-35.0)Sediment: pCi/kg Gamma Cs-134 Cs-137 Co-60 Co-57 Eu-152<112.5 (<50.0-<150.0)<287.0 (<50.0-<560.0)<254.6 (130.0-610.0)Not Reported Not Reported 57.7 368.0 54.8 46.0 143.0 (7.0-172.0)(153.0-1890.0)(27.1-129.0)(34.0-54.0)(140.0-146.0)74,4 190.0 15.0 0.5 85.8 (67.9-80.8)(182.0-197.0)(14.8-15.2)(-11.6-12.5)(5~6-166.0)~o Soil: pCi/kg Ganma Cs-134 Cs-137 Sr-90<65.3 (<20.0-<150.0)29.7 (7.1-53.2)364.3 (<20.0-<1880.0)313.0 (9.4-735.0)Analysis Not Performed 357.5 (260.0-455,0)17.5 (13.9-23.3)287.0 (32.9-493.0)Analysis not performed Hi 1k: pCi/1 Gamna Cs-134 Cs-137 Ba-140 La-140 I-131 Sr-90<3'(<0.9-<14.0)<3.8 (<1.0-<12.0)<72.1 (<6.0-<2000.0)<33.3 (<5'-<1000.0)<0.5 (<0.1-<1.0)Not Reported 1.3 (-7.4-22.6)4.0 (-7.4-47.3)0.5 (-44.3-55.0)-0.7 (-24.2-9.7)1.6 (-0.8-144.0)2.2 (-1.3-3.9)0.4 (-3.3-3.0)1.6 (-2.5-6.8)-0.6 (-12.0-9.9)-0.3 (-4.5-4.1)0.0 (-0.3-0.4)Not Reported (a)All stations, all years.(b)Indicator stations only for the years 1984 to 1989.Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.(c)The data used for these averages does not include the"less than" values reported in 1984.'d)Indicator stations only.5-9 RA TABLE 5-1 (Cont.)A V MENT R V gAAY HEOIA/ANALYSIS P AT N HEAN (RANGE)PR P RA NA HEAN (RANGE)HEAN (d)(RANGE)Fish: pCi/kg Gamma Cs-134 Cs-137 Co-58 Co-60 Fe-59 Hn-54<61.2<88.8<87.7<80.6<130.0<88.3 (<6.0-<130.0)(<10.0-<130.0)(<9.0-<130.0)(<9.0-<130.0)(<30.0-<260.0)(<8.0-<130.0)1.5 (-20,4-14,4)13.1 (-35.1-54.9)1.5 (-16.8-25.8)0.5 (-18.4-19.1)-2.1 (-34.6-21.1)2.0 (-10.3-30.9)7.5 15.3 0.1-0.8 7.2 1.0 (0.0-24')(2.5-31.4)(-8.2-6.7)(-7.1-7.0)(-10.2-30.0)(-7.4-7.9)Produce: pCi/kg Galena Cs-134 Cs-137 I-131<49.1 (<10.0-<140.0)~1.4 (-24.8-19.8)<69.8 (<10.0-<140.0)4.3 (-9.8-20.9)<105.6 (<10.0-<1000.0)1.2 (-21.3-59.0)1.3 (-12.0-17.0)5.6 (-3.6-15.0)-4.0 (-12.0-3.5)TLO: mR/day ()uarterly Annual 0.24 (0.11-0.32)0.23 (0.20-0.31)0.24 (0.16-0.35)0;23 (0.18-0.32)0.26 (0.23-0.32)0.24 (0.22-0.29)(a)A11 stations, all years.(b)Indicator stations only for the years 1984 to 1989.Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.(c)The data used for these averages does not include the"less than" values reported in 1984'd)Indicator stations only.5-10 MPA TABLE 5-2 N F T DYN NMINA l W R I T F DET T N WITH BRAN H T HNI A P T NT M IA NIT Air Partic~lates: (pCi/m)Air IotIine: (pCi/m~)Water: (pCi/1)Soil/Sediment: (pci/kg)Fish: (pCi/kg)ANA Y Gross Beta Gamma Spectrometry Cs-134 Cs-137 I-131 Gross Beta Tritium I-131 Sr-90 Gamma Spectrometry Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Gamma Spectrometry Co-57 Co-60 Cs-134 Cs-137 Sr-90 Gamma Spectrometry Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 TELEDYNE LD 0.003 0.001 0.001 0.01 4 100-200 1 1 10 20 10 1020 20 10 10 10 20 10 120 30 30 40 10 20 30 20 20 30 20 20 BTP REQUIRED D 0.01 0.05 0.06 0.07 4 2000 1 15 30 15 15 30 30 15 15 18 60 15 150 180 130 260 130 130 260 130 150 5-11 TABLE 5-2 (Cont.)PAR N F T EDYNE N MINAL HER IMIT F D T TI N THBANHTEHIA P IT RE M T M A N T Ml lk: (pc1/1)Garden Produce: (pC1/kg)I-131 Gamma Spectrometry Cs-134 Cs-137 Ba-140 La-140 Sr-90 Gamma Spectrometry Cs-134 Cs-137 I-131 TELEDYNE L D 0.5 10 10 20 10 1 20 20 30 BTP REQUIRED D 15 18 60 15 60 80 60 5-12 T 5-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO.50.397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31, 1990 ANALYSIS ANO LONER LIHIT HEOIUH OR PATH'NAY TOTAL NUHBER OF SAHPLEO OF ANALYSES OETECTION (UNIT OF HEASUREHENT)
PERFORHEO LLO)HEAN (b)(a)RANGE NAHE OISTANCE ANO DIRECTION CONTROL LOCATION HEAN (b)(a)HEAN (b)(a)RANGE NUHBER OF NONROUTINE REPORTEO MEASUREHENTS AIR PARTICULATES Gross Beta 624 0.003 (pCI/$3)Gamma 48 (Ouarterly) 0.013(563/572) 5{0.002-0.059) 0.014(52/52)
{0.004-0.059) 0.012(51/52)
{0.002-0.03)
Be-7 0.01 0.055(44/44)
(0.034-0.091) 48 4.5 mI NE 0.068(4/4)
(0.039-0.080) 0.047(4/4)
(0.036-0.060)
K-40 0.01 0.006(6/44)
(0.005-0.008) 48 4.5 RI NE 0.008(1/4) 0.005(l/4)
Cs-137 0.01 LLD LLD Cs-134 0.001 LLO LLD AIR IODINE (pC1/$3)I-131 624 0.01 LLD LLD (a)"(b)ls the ratio of posltlve results above the.ttO to the number of samples analyzed For the parameter of Interest.
TABLE 5-3 (Continued)
TABLE 5-3 (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO.50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31.1990 ANALYSIS AND LONER LIHIT HEDIUH OR PATHWAY TOTAL NUHBER OF SAHPLEO OF ANALYSES DETECTION UNIT OF HEASUREHENT PERFORHEO LLO HEAN (b)(a)RANGE NUHBER OF CONTROL LOCATION NONROUTINE NAHE HEAN (b)HEAN (b)()REPORTED DISTANCE ANO DIRECTION RANGE HEASUREHENTS WATER (River/Drinking)(pC1/liter)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                       DOCKET NO. 50-397 HANFORD WASHINGTON                               JANUARY 1   to DECEHBER 31. 1990 ANALYSIS AND   LONER   LIHIT                                                                                       NUHBER OF TOTAL NUHBER        OF                                                                          CONTROL LOCATION  NONROUTINE HEDIUH OR PATHWAY SAHPLEO             OF ANALYSES   DETECTION           HEAN (b)(a)                 NAHE               HEAN (b)         HEAN (b)( )   REPORTED PERFORHEO          LLO            RANGE                  DISTANCE ANO DIRECTION                     RANGE         HEASUREHENTS UNIT OF HEASUREHENT WATER                 Gross Beta    36                  1.74(20/24)           28  7.4 Illi  SSE    1.93(10/12)             1.78(10/12)
Gross Beta 36 Tritium 12 200 1.74(20/24)
(River/Drinking)                                          (0.64-2.90)                                   (1.3-2.6)             (0.65-4.40)
(0.64-2.90) 210(3/8)(140-250)28 7.4 Illi SSE 1.93(10/12)
(pC1/liter)
(1.3-2.6)28 7.4 m$SSE 245(2/4)(240-250)1.78(10/12)
Tritium      12    200          210(3/8)               28   7.4 m$   SSE     245(2/4)               LLO (140-250)                                     (240-250)
(0.65-4.40)
Gamma         36 Hn-54                 10          LLO                                                                  LLO              0 Fe-59                 20          LLD                                                                  LLD Co-58                 10          LLD                                                                  LLD Co-60                 10          LLO                                                                  LLO Zn-65                 20          LLD                                                                  LLO Zr-95                 20          LLO                                                                  LLD Nb-95                 10          LLD  ~                                                              LLO Cs-134                 10          LLD                                                                  LLO Cs-137                 10          LLD                                                                  LLD Ba-140                 20          LLD                                                                  LLD              0 La-140                 10           LLO                                                                 LLD la) "~   ls the ratio of posit.lve results above the LLO to the number of   les analyzed for the parameter of interest.
LLO Gamma Hn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 36 10 20 10 10 20 20 10 10 10 20 10 LLO LLD LLD LLO LLD LLO LLD~LLD LLD LLD LLO LLO LLD LLD LLO LLO LLD LLO LLO LLD LLD LLD 0 0 la)"~ls the ratio of posit.lve results above the LLO to the number of les analyzed for the parameter of interest.
 
0 0 5-3 (Continued)
0               0 5-3 (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO.50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31.1990 ANALYSIS AHO LOWER LIMIT MEOIUM OR PATHWAY TOTAL NUMBER OF SAMPLED OF ANALYSES OETECTIOH UNIT OF MEASUREMENT PERFORMEO LLO MEAN (b)(a)RANGE NAME OISTAHCE ANO DIRECTION CONTROL LOCATION MEAN (b)(a)MEAN (b)(a)RANGE NUMBER OF NONROUTIHE REPORTED MEASUREMENTS WATER (Discharge)(pCi/liter)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                         DOCKET NO. 50-397 HANFORD WASHINGTON                                 JANUARY 1   to DECEHBER   31. 1990 ANALYSIS AHO   LOWER LIMIT                                                                                       NUMBER OF TOTAL NUMBER      OF                                                                            CONTROL LOCATION NONROUTIHE MEOIUM OR PATHWAY SAMPLED             OF ANALYSES   OETECTIOH         MEAN (b)(a)                   NAME               MEAN (b)(a)       MEAN (b)(a) REPORTED UNIT OF MEASUREMENT    PERFORMEO        LLO            RANGE                   OISTAHCE ANO  DIRECTION                    RANGE        MEASUREMENTS WATER                 Gross Beta     12      12          15.8(12/12)              27  32  mi    E      15.8(12/12)             None (Discharge)                                              (6.1-35)                                          (6.1-35)
Gross Beta 12 12 TritiUm 4 200 15.8(12/12)
(pCi/liter)
(6.1-35)1843(3/4)(130-3400) 27 32 mi E 27 3.2 mi E 15.8(12/12)
TritiUm        4    200          1843(3/4)               27   3.2 mi   E       1843(3/4)               None (130-3400)                                       (130-3400)
(6.1-35)1843(3/4)(130-3400)
Gamma         12 Hn-54                 10          LLD                                                                      LLD Fe-59                 20          LLD                                                                      LLD Co-58                 10          LLD                                                                      LLD Co-60                 10         8.60(1/12)               27   3.2 IAi   E       8.60(1/12)             LLD Zn-65                 20          LLD-                                                                    LLD Zr-95                 20          LLD                                                                      LLD Nb-95                 10        LLD                                                                      LLD Cs-134                 10        LLD                                                                      LLD Cs-137                 10          LLD                                                                    LLD Ba-140                 20          LLD                                                                    LLD La-140                 10         LLD                                                                     LLD ia) (o) is tne ratio of positive results above tne LLO to the number of samples analyzed for the parameter of interest.
None None Gamma Hn-54 Fe-59 Co-58 Co-60 12 10 20 10 10 LLD LLD LLD 8.60(1/12) 27 3.2 IAi E 8.60(1/12)
 
LLD LLD LLD LLD Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 20 20 10 10 10 20 10 LLD-LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD ia)(o)is tne ratio of positive results above tne LLO to the number of samples analyzed for the parameter of interest.
TABLE 5-3 (ContInued)
TABLE 5-3 (ContInued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP.2 DOCKET NO.50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31, 1990 ANALYSIS AND LOWER LIHIT HEDIUH OR PATHWAY TOTAL NUHBER OF SAHPLED OF ANALYSES DETECTION UNIT OF HEASUREHENT PERFORMED LLO HEAN (b)(a)RANGE NAHE DISTANCE AND DIRECTION CONTROL LOCATION HEAN (b)(a)HEAN (b)(a)RANGE NUHBER OF NONROUTINE REPORTED HEASUREHENTS WATER (Ground)(pC)/1)ter)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP.2                    DOCKET NO. 50-397 HANFORD WASHINGTON                              JANUARY 1  to  DECEHBER  31, 1990 ANALYSIS AND  LOWER  LIHIT                                                                                    NUHBER OF HEDIUH OR PATHWAY      TOTAL NUHBER      OF                                                                        CONTROL LOCATION  NONROUTINE SAHPLED          OF ANALYSES  DETECTION        HEAN (b)(a)                  NAHE              HEAN (b)(a)      HEAN  (b)(a) REPORTED UNIT OF HEASUREHENT  PERFORMED        LLO          RANGE                  DISTANCE AND DIRECTION                    RANGE        HEASUREHENTS WATER                Tritium      12    200        220(1/12)            52    O.l  mI    N          220(1/4)            None (Ground)
Gamma 12 Hn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 10 20 10 10 20 20 Tritium 12 200 220(1/12)LLD LLD LLD LLQ LLD LLD 52 O.l mI N 220(1/4)None LLD LLD LLD LLD LLD LLD Nb-95 Cs-134 Cs-137 Ba-140 La-140 10 10-.10 20 10 LLD LLD LLD LLD LLD LLD LLD LLQ LLD LLD T 5-3 (Continued)
(pC)/1)ter)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO.50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31.1990 ANALYSIS AND LOWER LIHIT HEOIUH OR PATHNAY TOTAL NUHBER OF SAHPLEO OF ANALYSES DETECTION (UNIT OF HEASUREHEHT PERFORHEO (LLO)NEAN
Gamma        12 Hn-54                10        LLD                                                                  LLD Fe-59                20        LLD                                                                  LLD Co-58                10        LLD                                                                  LLD Co-60                10        LLQ                                                                  LLD Zn-65                20        LLD                                                                  LLD Zr-95                20        LLD                                                                  LLD Nb-95                10        LLD                                                                  LLD Cs-134              10 -. LLD                                                                  LLD Cs-137              10        LLD                                                                  LLQ Ba-140              20        LLD                                                                  LLD La-140              10        LLD                                                                  LLD
 
T 5-3 (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                        DOCKET NO. 50-397 HANFORD WASHINGTON                                JANUARY 1  to  DECEHBER  31. 1990 ANALYSIS AND  LOWER  LIHIT                                                                                      NUHBER OF HEOIUH OR PATHNAY        TOTAL NUHBER        OF                                    L                                      CONTROL LOCATION NONROUTINE SAHPLEO            OF ANALYSES    DETECTION            NEAN      (b)(a)              HAHE              HEAN (b) )      HEAH (b)(  REPORTED (UNIT OF HEASUREHEHT    PERFORHEO        (LLO)          RANGE                    DISTANCE AND DIRECTION                    RAHGE        HEASUREHENTS SOIL                  Gafina    5 (pC$ /kg dr'y)
K-40                              17825(4/4)              23  3.0  Qi ESE      21400(1/1)        12100(1/1)
(12100-21400)
Cs-134              30            LLD                                                                LLD Cs-137              40            287(4/4)                                        493(l/1)          121(1/1)
(32.9-493)'51(2/4)
Ra-226            400                                                              886(1/1)          1320(1/1)
(615-886)
Th-228              50            725(4/4)                                        837(1/1)          639(1/1)
(553-837)
(a) "(b)" is the ratio of positive results above the LLO  to the number of samples analyzed for the parameter of interest.
 
TABLE S-3    (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                        DOCKET NO. 50-397 HANFORD WASHINGTON                                  JANUARY 1  to  DECEHBER 31, 1990 ANALYSIS ANO LOMER  LIHIT                                                                                      NUHBER OF HEOIUH OR PATHHAY      TOTAL NUHBER    OF                                                                            CONTROL LOCATIOH NONROUTIHE SAHPLEO            OF AHALYSES  OETECTION            HEAR (b)(a)                    NAHE              HEAN (b)        HEAN (b)(a) REPORTEO UNIT OF HEASUREHENT)  PERFORHEO      LLO)            RANGE                  OISTANCE ANO OIRECTION                    RANGE        HEASUREHENTS SEDIHENT              Gamma    4 (pC5/kg dry)
K-40            700              13900(2/2)              33  3.6  mi ENE      15350(2/2)        15350(2/2)
(13800-14000)                                  (14600-16100)      (14600-16100)
S Co-60            30              LLD                                                                LLD Cs-134          30              LLD                                                                LLD Cs-137          40              190(2/2)                34  3.5  IA[ ENE      190(2/2)          115(1/2)
(182-197)                                      (182-197)
Ra-226          400              1665(2/2)                34  3.5  mi ENE      1665(2/2)          1400(2/2)
(1380-1950)                                    (1380-1950)        (1050-1750)
Th-228          50              1875(2/2)                34  3.5  m$  ENE      1875(2/2)          1355(2/2)
(1290-2460)                                    (1290-2460)        (789-1920) the LLO t
to the number of samples analyzed for the parameter of Interest.
0
 
0                0 T      5-3 (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                          DOCKET NO. 50-397 HANFORD WASHINGTON                                  JANUARY 1    to  OECEHBER  31, 1990 ANALYSIS ANO  LOMER  LIHIT                                                                                          NUHBER OF HEOIUH OR PATNMAY        TOTAL NUHBER        OF                                                                              CONTROL LOCATION  NONROUTINE SAHPLEO            OF ANALYSES    OETECTION            HEAN (b)(a)                    NAHE                HEAN (b)(a)      HEAN (b)(a)  REPORTEO (UNIT  OF HEASUREHENT)  PERFORHEO          LLO            RANGE                    OISTANCE ANO DIRECTION                      RANGE          HEASUREHENTS HILK                  I-131    97                        LLO                                                                      LLD (pCI/liter)
Gamma    97 K-40      97                        1270(79/79)              59  6.6  mi SE        1366(18/18)              1340(18/18)
(934-1640)                                      (1200-1640)            (1170-1470)
Cs-134    97        10              LLD                                                                      LLD Cs-137    97        10              LLD                                                                      LLO (a)  (b)" Is the ratio oi pos(t1ve results  above the LLO to the number  of samples analyzed for the parameter of Interest.
 
TABLE 5-3      (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                        DOCKET NO. 50-397 HANFORD WASHINGTON                                  JANUARY 1  to  OECEHBER  31. 1990 ANALYSIS AND  LONER    LIHIT                                                                                      NUHBER OF HEOIUH OR PATHWAY        TOTAL NUHBER        OF                                    L                                      CONTROL LOCATION NONROUTINE SAHPLED            OF ANALYSES    DETECTION            HEAN (b)(a)                    NAHE              HEAN (b)( )      HEAN (b)(a) REPORTED (UNIT  OF HEASUREHENT)  PERFORHED          (LLD)          RANGE                    DISTANCE ANO DIRECTION                    RANGE        HEASUREHENTS FISH                  Gamma    17 (pC$ /kg wet)
K-40            1000              3778(8/8)              -38  26.5  Ali ESE    4133(9/9)          4133(9/9)
(2550-4960)                                    (2850-7710)        (2850-7710)
Hn-54                20            LLO                                                                LLO Fe-59                30            LLD                                                                LLD Co-58                20            LLD                                                                LLD Co-60                20            LLD                                                                LLD Zn-65                30            LLD                                                                LLD Cs-134              20            LLD                                                                LLO Cs-137              20            30.4(1/8)              30    3.3  mi E        30.4(1/8)          LLD (a) "(bl" is  the ratio of positive results  above the LLD to the number of samples analyzed for the parameter of interest.
  ~        0              0              ~                0 00                                0
 
0 T      5-3 (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                      DOCKET NO. 50-397 HANFORD WASHINGTON                                JANUARY 1  to  DECEHBER 31. 1990 ANALYSIS AND    LOWER  LIHIT                                                                                    NUHBER OF HEOIUH OR PATHWAY        TOTAL NUMBER        OF                                  L                                      CONTROL LOCATION NONROUTINE SAMPLED              OF ANALYSES    DETECTION          HEAN (b)(a)                    NAHE              HEAN (b)        MEAN (b)(  REPORTED UNIT  OF HEASUREHENT)    PERFORHEO          LLO)          RANGE                    DISTANCE AND DIRECTION                    RANGE        HEASUREHENTS ROOTS                  Gamma      8 (pCi/kg wet)
I-131                50            LLD                                                                LLD Cs.134              50            LLD                                                                LLD Cs-137              50            LLD                                                                LLD FRUITS                  Gamma      10 (pCI/kg wet)
I-131                50            LLD                                                                LLD Cs-134                50            LLD                                                                LLD Cs-137                50            LLD                                                                LLD VEGETABLES            Gamma      12 (pCi/kg wet)
I-131                50            LLD                                                                LLD Cs-134                50            LLD                                                                LLD Cs-137                50            LLD                                                                LLD (a)  lol  Is toe ratio  Of  Oosltlve results above tne ttO to tne number of samples analyzed for the parameter of interest.
 
TAHLE  5-3 (Continued)
WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2                          DOCKET NO. 50-397 HANFORD WASHINGTON                                  JANUARY 1  to  DECEHBER  31. 1990 ANALYSIS ANO  I.O'WER  LIHIT                                                                                          NUMBER OF HEOIUH OR PATHWAY        TOTAL NUHBER        OF                                                                              CONTROL LOCATION  NONROUTINE SAHPLED            OF ANALYSES    DETECTION              HEAN (b)(a>>                  NAHE                HEAN (b)( )      HEAN (b)(a)  REPORTED (UNIT OF HEASUREHENT)    PERFORMED          (LLO)            RANGE                  DISTANCE ANO DIRECTION                      RANGE          HEASUREHENTS DIRECT RADIATION      TLD      224                        0 '6(223/223)            46  4.7  mi  NE      0.31(4/4)                0.24(4/4)
Quarterly TLD's                                              (0.23-0.32)                                    (0.30-0.32)            (0.23-0.24)
(mR/day)
DIRECT RADIATION      TLD      57                        0.24(56/56)              46  4.7  mi  NE      0.29(1/1)                0.22(1/1)
Annual TLD's                                                (0.22-0.29)
(mR/day)
(a)  (b)" is the ratio of positive results    above the LLO  to the number of samples analyzed for the parameter of interest.
0        0                                ~           
                                                              ~
                                                                            ~                0
 
TABLE  5-4 T    LY      D DAT      H A Y F      H AN    P  AT Results in mR/day 1984 '989
$ TATJgN        P RATI NA                    P        N          P  RAT NA STANDARD                        STANDARD        STANDARD HEAN        ERR R              M  AN      ERR R  MEAN    E    R 1      0.24        0.02              0.25        0.01  0.25      0.01 2      0.23        0.02              0.24        0.01  0.25      0.01 3      0.22        0.01              0.23        0.01  0.25      0.01 4      0.22        0.02              0.22        0.01  0.23      0.01 5      0.23        0.01              0.23        0.01  0.24      0.01 6      0.22        0.01              0.23        0.01  0.24      0.01 7      0.23        0.01              0.24        0.01  0,25      0.01 8      0.26        0.01              0.26        0.01  0.27      0.01 9      0.22        0.01              0.22        0.01  0.24      0.01 10    0.23        0.01              0.23        0.01  0.25      0.01 ll    0.24        0.01              0.24        0.01  0.25      0.00 12    0.25        0.01              0.26        0.01  0.27      0.00 13    0.24        0.01              0.24        0.01  0.25      0.01 14    0.24        0.02              0.24        0.01  0 25      0.01 15    0.25        0.01,            0.26        0.01  0.27      0.01 16    0.24        0.01              0.25        0.01  0.26      0.01 17    0.25        0.01              0.25        0.01  0.26      0.01 18    0.24        0.01              0.25        0.01  0.26      0.01 19    0.24        0.01              0.25        0.01  0.26      0.01 20    0.24        0. 01'.01 0.24        0.01  0.25      0.01 21    0.23                          0.22        0.01  0.24      0.01 22    0.24        0.01              0.24        0 01 F    0.25      0.01 23    0.24        0.01              0.24        0.01  0.25      0.01 24    0.24        0.01              0.24        0.01  0.26      0.01 25    0.25        0.01              0.26        0.01  0.27      0 01 F
40    0.22        0.01              0.23        0.01  0.25      0.01 41    0.26        0.02              0.26        0.01  0.27      0.01 42    0.25        0.01              0.25        0.01  0.26      0.01 43    0.

Latest revision as of 06:47, 4 February 2020

Radiological Environ Monitoring Program 1990 Annual Rept for Nuclear Plant 2. W/910426 Ltr
ML17286A734
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 12/31/1990
From: John Baker, Hosler A, Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
References
PS-CJC-91-034, PS-CJC-91-34, NUDOCS 9105030291
Download: ML17286A734 (329)


Text

ACCELERATED DI UTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9105030291 DOC.DATE: 90/12/31 NOTARIZED: NO , DOCKE FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 050 397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System BAKER,J.W. Washington Public Power Supply Syst: em HOSLER,A.G. Washington Public Power Supply System RECIPIENT AFFILIATION

/ R RECIP.NAME /l4q

SUBJECT:

"Radiological Environ Monitoring Program 1990 Annual Rept foE Nuclear Plant 2." W/910426 ltr.

DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR g ENCL t SIZE: (7 + S TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES:

\

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD5 LA 3 3 PD5 PD 1 1 ENG,P.L. 1 1 D INTERNAL: ACRS 1 1 AEO PAB 1 1 NRR/DREP/PRPB11 2 2 G FILE 01 1 1 RGN5 DRSS/RPB 1 1 FILE 02 1 1 EXTERNAL: EG&G SIMPSON, F 2 2 NRC PDR 1 1 D

A D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15

I k

%a(

-ii-WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~+ 3000 George Washington Way ~ Richland, Washington 99352 April 26, 1991 Applicable Regulation:

PS"CJC"91"034 Washington Public Power Supply System Technical Specification 6.9.1.10 uocket No. 50-397 Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

SUBJECT:

1990 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT Enclosed ar e three (3) copies of the 1990 Radiological Environmental Monitor inq Program Annual report. This report fulfills the reporting requirement stated in Washington Public Power Supply System Technical Specification 6.9.1.10.

If you have any questions or comments about this report, please contact Catherine J. Card at (509) 377-8066.

Sincerely G. C. rensen, Manager Regulatory Programs GSC/CJC/lp Enclosure 910S030291 PDR R

'DR ADOCK 90123i 05000397

1

~ 4

fI'9105030291

~ ~

~ ~

WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PLANT NUMBER 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT April 1991 Prepared By: C.J. Card Washington Public Power Supply System J.E. HcDonald Washington Public Power Supply System L.S. Schleder Washington Public Power Supply System J.D. Hartin Teledyne Isotopes Westwood, New Jersey C.A. Hendola Teledyne Isotopes Westwood, New Jersey

f Technical Speci i cation 6,9.1.10 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PLANT NUMBER 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT April 1991 Approvals:

2-C Regulatory Programs Manager Pg<<r G,C. S ensen Date WNP-2 Plant Manager

.W. Baker Date WNP-2 Licensing Manager "j/>wP e I

~A.. Hosier Date WNP-2 Health Physics/ J Chemistry Manager R.G. Graybeal Date Plant Services Manager i9 9/

J. . Bell Date Originator: P-rP-9i C. . Card Date

TABLE OF CONTENTS 1.0 EXECUTIVE

SUMMARY

l-l 2.0 TERMINOLOGY 2-1

3.0 INTRODUCTION

3-1 3.1 Site Description 3-1 3.2 Program Background 3-1 3.3 Program Ob]ectives 3-3 4.0 PROGRAM DESCRIPTION 4-1 4.1 Sample Locations 4-1 4' Land Use Census 4-1 4.3 Sampling Methods 4-2 4.3.1 Direct Radiation 4-2 4.3.2 Airborne Particulate/Iodine 4-3 4.3.3 Hater 4-3 4.3.4 Soil, 4-5 4.3.5 Shoreline Sediment 4-5 4.3.6 Fish 4-5 4.3,7 Milk 4-6 4.3.8 Garden Produce 4-6 4.4 Analytical Methods 4-7 4.4.1 Gross Beta Activity on Particulate Filters 4-7 4.4.2 Measurement of Gamma Emitters 4-7 4.4.3 Gross Beta Activity in Hater 4-8 4.4.4 Iodine-131 in Hater 4-8 4.4.5 Tritium in Hater 4-8 4.4.6 Strontium-89 and 90 in Hater, Milk and Soil 4-8 4.4.7 Iodine-131 in Milk 4-9 4.5 Data Analysis Methods 4-9 5.0 RESULTS AND DISCUSSION 5-1 5.1 Direct Radiation 5-2 5.2 Airborne Particulate/Iodine 5-3 5.3 Hater 5-4 5.4 Soil 5-6 5.5 Shoreline Sediment 5.6 Fish 5-7 5.7 Milk 5-7 5.8 Garden Produce 5-7 6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6-1 6.1 Quality Control For the Supply System Environmental 6-1 TLD Program 6.2 Quality Control For the Analytical Program 6-2 6.2.1 Supply System Quality Control Activities 6-2 6.2.2 Teledyne Isotopes Quality Control Program 6-3

7.0 REFERENCES

7-1 APPENDICES:

APPENDIX A ROUTINE RESULTS A-1 APPENDIX B TELEDYNE ISOTOPES 1990 EPA INTERCOMPARISON RESULTS B-l APPENDIX C SPECIAL SAMPLE RESULTS C-1 APPENDIX D SAMPLE DEVIATIONS D-1 DISTRIBUTION

LIST OF TABLES 4-1 Radiological Environmental Monitoring Program Plan 4-11 4-2 REMP Sample Locations By Sector 4-15 4-3 Distances In Miles to Nearest Points of Interest Within Five Miles of Plant 2 Containment 4-19 5-1 Radiological Environmental Monitoring Program Comparative Summary 5-8 5-2 Comparison of Teledyne Lower Limits of Detection With Branch Technical Position Requirements 5-11 5-3 Radiological Environmental Monitoring Program Summary 5-13 5-4 Mean Quarterly TLD Data Summary For The Preoperational and Operational Periods 5-23 5-5 Annual TLD Data Summary For the Preoperational and Operational Periods 5-25 5-6 1990 Mean Quarterly Versus Annual TLD Data 5-27 6-1 1990 Environmental Audit Dosimeter Results 6-7 6-2 Hanford/Columbia River Sampling Intercomparison Results 6-8 6-3 1990 Environmental Measurements Laboratory (EHL)

Quality Assessment Program Results 6-11 6-4 Comparison of Analytical Results for 1990 Duplicate Milk and Water Samples 6-12 6-5 Summary of 1990 Quality Control Data: Blanks 6-13 6-6 Summary of 1990 Quality Control Data: Spikes 6-14 APPENDI X A: ROUTINE RESULTS A-1 . 1 1990 Quarterly TLD Results A-1 A-1.2 1990 Annual TLD Results A-9 A-1.3 1990 TLD Results 'Summary A-11 A-2.1 Gross Beta On Air Particulate Filters A-12 A-2.2 Gross Beta On Air Particulate Filters S ummary A-36 A-3.1 Gamma Spectrometry of Particulate Filters A-37 A-3.2 Gamma Spectrometry of Particulate Filters Summary A-49 A-4.1 I-131 in Charcoal Cartridges A-50 A-4.2 I-131 in Charcoal Cartridges Summary A-74 A-5.1 Gross Beta in Water A-75 A-5.2 Gross Beta in Water Summary A-77 A-6.1 Tritium in Water A-78 A-6.2 Tritium in Water Summary A-80 A-7.1 Gamma Spectrometry of Water A-81 A-7.2 Gamma Spectrometry of Hater-Summary A-111 A-8.1 Gamma Spectrometry of Soil A-115 A-8.2 Gamma Spectrometry of Soil Summary A-116 A-9.1 Gamma Spectrometry of Sediment A-117 A-9.2 Gamma Spectrometry of Sediment Summary A-118 A-10.1 Gamma Spectrometry of Fish A-119 A-10.2 Gamma Spectrometry of Fish Summary A-124 A-ll,l I-131 in Milk A-125 A-11.2 I-131 in Milk Summary A-128 A-12.1 Gamma Spectrometry of Milk A-129 A-12.2 Gamma Spectrometry of Milk Summary A-146 A-13.1 Gamma Spectrometry of Root A-147 A-13.2 Gamma Spectrometry of Root Summary A-148

LIST OF TABLES (Continued)

A-14.1 Gamma Spectrometry of Fruit A-149 A-14.2 Gamma Spectrometry of Fruit Summary A-150 A-15.1 Gamma Spectrometry of Vegetables A-151 A-15.2 Gamma Spectrometry of Vegetables Summary A-153 APPENDIX B: TELEDYNE ISOTOPES 1990 EPA INTERCOMPARISON RESULTS B-1 1990 EPA Intercomparison Program Results B-1 APPENDIX C: SPECIAL SAMPLE RESULTS C-1 Results of Hater Grab Sample Composites C-2 C-2 Comparison of the Air Sampling Results at a Near-Plant Location and at Station 57 C-5 C-3 Environmental TLD Fade Test Results C-6 APPENDIX D: SAMPLE DEVIATIONS D-1 1990 Sample Deviations D-4

LIST OF FIGURES 3-1 1990 Wind Frequency Distribution in Percent From Each Direction Relative to Plant 2 3-3 3-2 The Monitoring Hierarchy From the Generation of Liquid P

and Gaseous Effluents to the Measurement of Radioactivity in the Environment 3 4 4-1 REHP Sampling Locations Within the 10-Mile Radius 4-20 4-2 REMP Sampling Locations Outside the 10-Mile Radius 4-21 4-3 REMP Sampling Locations in the Sunnyside/Grandview Area 4-22 4 4 Inner Circle TLD Locations 4-23 4-5 Near-Plant TLD Locations 4-24 4-6 Outlying TLD Locations Within the 10-Mile Radius 4-25 4-7 Air Sampling Locations Within the 10-Mile Radius 4-26 4-8 River/Drinking and Discharge Water Sampling Locations Within the 10-Mile Radius 4-27 4-9 Groundwater Sampling Locations 4-28 4-10 Soil Sampling Locations Within the 10-Mile Radius 4-29 4-11 Sediment Sampling Locations 4-30 4-12 Milk Sampling Locations Within the 10-Mile Radius 4-31 5-1 Average Quarterly TLD Results For Near-Plant Locations and the Control Location (Station 9A) For the Preoper-ational Period, 1984-1989, and 1990 5-29 5-2 Average Quarterly TLD Results For Remote Locations, and the Control Location (Station 9A) For the Preoper-ational Period, 1984-1989, and 1990 5-30 5-3 Annual TLD Results For Near-Plant Locations and the Control Location (Station 9A) For the Preoperational Period, 1984-1989, and 1990 5-31 5-4 Annual TLD Results For Remote Locations and'he Control Location (Station 9A) For the Preoperational Period, 1984-1989, and 1990 5-32 5-5 Mean 1990 Quarterly TLD Results For Locations in Each Meteorological Sector Compared to Preoperational and Previous Operational Results 5-33 5-6 ~

Quarterly TLD Results For Station 46 and the Control Location (Station 9A) For the Period 1982-1990 5-34 5-7 Log Probability Plots of the 1990 and the 1984-1989 Quarterly TLD Results 5-35 5-8 Log Probability Plots of the 1990 and the 1984-1989 Annual TLD Results 5-36 5-9 Log Probability Plots of the Quarterly TLD Data For Near-Plant Locations (Stations 71-76) and the Control Location (Station 9A) For the Period 1982-1990 5-37 5-10 Mean Weekly 1990 Gross Beta in Air Results 5-38 5-11 Mean Weekly Gross Beta in Air Results From 1984 to 1990 5-39 5-12 Weekly Gross Beta In Air Results For Near-Plant and Remote Sampling Locations Versus the Results For the Control Location (Station 9A) 5-40 5-13 1990 Gross Beta in River/Drinking Water Results 5-41 5-14 Gross Beta in River/Drinking Water From 1984 to 1990 5-42

LIST OF FIGURES (Continued) 0 5-15 Gross Beta in Discharge Hater Results from 1986 to 1990 5-43 5-16 1990 Gross Beta in Discharge Hater Results 5 44 5-17 1990 Tritium in'iver/Drinking Hater Results 5-45 5-18 Tritium in Discharge Water from 1986 to 1990 5-46 5-19 1990 Tritium in Discharge Hater Results 5-47 5-20 Cesium-137 in Sediment Results from 1984 to 1990 5-48 5-21 1990 Iodine-131 in Milk Results 5-49 6-1 Supply System Environmental TLD Preparation-Use Cycle 6-15 6-2 Supply System TLD Evaluation 6-16 6-3 Flow Chart For Teledyne Isotopes Samples 6-17

~ o

~ o

1.0 E EC TIVE MM Y The Washington Public Power Supply System Radiological Environmental Monitoring Program (REMP) activities during 1990 are discussed in this report. The REMP was conducted in accordance with a program plan which involves the collection of air, water, milk, soil, sediment, fish and garden produce samples on a regular basis from the region surrounding the plant.

In addition, direct radiation from the plant and plant effluents was measured using thermoluminescent dosimeters (TLDs). The objective of assessing these samples and the TLDs was to determine the radiological impact, if any, of Plant 2 operations on the environment.

Determining whether plant operation affected the environment significantly involved comparison of samples taken in areas near the plant and in other regions which could be potentially affected by Plant 2 effluents to samples taken in an area that is highly unlikely to be affected. In addition, a to samples taken 't comparison of the samples taken during 1990 at locations of potential impact the same location prior to plant operation and during previous periods of operation provided another mechanism for detecting changes in the environmental radioactivity that could be attributed to Plant 2 operations. Other methods used to evaluate the REMP results and to bring the results into perspective included comparison of the 1990 results to the lower limits of detection (LLDs) determined for each radionuclide, to the preoperational averages and to the applicable State of Washington or U.S.

Nuclear Regulatory Commission investigation or reporting levels or standards.

Most of the REMP sample results during 1990 were below detection levels.

However, some analyses, such as the determination of gross (total) beta, generated results that were above the LLD, i.e., detectable results, for nearly all samples of air and water. This was due to the low detection limit for the gross beta analysis and the abundance of naturally-occurring beta-emitting radionuclides in the environment. Other results above detection levels, such as cesium-137 in soil and sediment, reflected the effect of past Hanford activities or fallout from past nuclear weapons testing.

The 1990 thermoluminescent dosimeter (TLD) results were very consistent with the 1989 results. The average of the quarterly TLD results for 1990 was 0.26 mR/day; this can be compared to an average of 0.24 mR/day for the preoperational period and 0.25 mR/day for the operational period from 1984 through 1989. The techniques used to analyze the TLD results included log probability plotting, plotting the results by distance and location relative to Plant 2, and by comparison of individual TLD station results to the results of the .control station. Inherent differences in the radiation background at individual locations accounted for variations among the TLD results. However, no trends were evident in the TLD data that would indicate an impact from Plant 2 on the environment.

The 1990 RfHP data was consistent with the environmental data observed during the previous operational and the preoperational years. Based on the extensive comparisons and evaluations performed on the data, no radiological impacts of Plant 2 operations on the environment around the plant were detected by the REMP during 1990.

1-2

Becquerel (Bq): One disintegration per second. One picocurie (pCi) equals 0.037 becquerel.

Blank Sample: A sample of the same media as the field sample bein'g analyzed but without the radionuclide(s) being measured. It enables correction for the inherent sample background.

Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.

Control Station: A background sampling location, i.e., a location not likely to be affected by plant effluents due to its distance and/or direction from Plant 2.

Curie (Ci): 3.7 x 10 disintegrations per second.

DOH: Hashington State Department of Health.

Grab Sample: A single discrete sample drawn at one point in time.

Indicator Station: A sampling location that could be affected by plant effluents due to its proximity and/or direction from Plant 2.

Log Probability Plotting: A technique used to determine whether a set of data conforms to the log-normal distribution.

Lower Limit of Detection (LLD): Detection capability. The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95/. probability and a 5'/ probability of a false conclusion that a blank observation represents a "real" signal.

Hilliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X or gamma radiation.

NRC: U.S. Nuclear Regulatory Commission.

Picocurie (pCi): lx10 Curie or 2.22 disintegrations per minute.

RBIP: Radiological Environmental Monitoring Program.

Site Certification Agreement (SCA): The Plant 2 licensing agreement with the State of Nashington.

Spike Sample: A sample containing a known concentration of the radio-nuclide(s) being measured.

2-1

Standard Deviation: A measure of the scatter of a set of observations (or samples) around their mean value.

Standard Error: An estimate of the uncertainty associated with the mean of observation (or sample) averages.

TLD: Thermoluminescent dosimeter; A TLD contains a phosphor which stores energy from exposure to radiation and emits that energy in the form of light when heated.

TL: Thermoluminescence.

~ e 2-2

The Radiological Environmental Monitoring Program (REMP) for Washington Public Power Supply System Plant 2 provides for the collection and analysis of samples of various environmental media, in order to assess the radio-logical impact of plant operations. The environmental media routinely sampled by the REMP include air, water, milk, soil, river sediment, fish, vegetables, fruits, and root crops. Other sample media, such as vegetation and animal products (for example, eggs and meat) are also sampled under special circumstances when additional information about particular radio-nuclides is needed. The direct radiation near the plant and at various distances from the plant is assessed through the use of thermoluminescent dosimeters.

This annual report is written to satisfy the requirements of Plant 2 Technical Specification 6.9.1.10. The results of environmental measurements made dur,ing CY 1990 are presented in the report. The results are discussed and interpreted by comparing them to similar measurements made during the preoperational and previous operational periods and to the detection capa-bilities associated with the current methods of analysis. The quality assurance and quality control aspects of the program are also discussed in this report.

Washington Public Power Supply System Plant 2 is located in a sparsely populated shrub-steppe region within the Department of Energy-operated Hanford Site in southeastern Washington. The plant is approximately three miles west of the Columbia River and is surrounded on all sides by uninhabited desert land. The nearest population centers are Richland,

'ennewick and Pasco, which are 12 miles south, 21 miles southeast, and 18 miles southeast, respectively. The nearest privately-owned lands are located approximately four miles ENE of the plant, across the Columbia River. Given the prevailing wind directions, shown in the 1990 wind frequency distribution in Figure 3-1, the focus of REMP sampling is this farming region across the river.

Because Plant 2 is located on the Hanford Site, other sources of radioactive effluents are in relatively close proximity to Plant 2. For this reason, sampling locations near the plant (near-plant locations) provide useful information for separating the potential environmental effects of Plant 2 from the effects of the other effluent sources on the Hanford Site.

3.2 Pr r Ba r n The REMP is designed to conform to the regulatory guidance provided by Regulatory Guides 4.1'nd 4.8', including the Radiological Assessment Branch Technical Position (BTP)', while taking into account site specific characteristics. The quality assurance aspects of the program and the thermoluminescent dosimetry are conducted in accordance with Regulatory Guides 4.15'nd 4.135. The REMP also must adhere to the requirements of the Site Certification Agreement (SCA)'ith the State of Washington and 3-1

the Plant 2 Technical Specifications. These requirements cover not only the environmental sampling and sample analysis aspects of the program, but also the reporting and quality assurance aspects of the program. 0 The preoperational phase of the program, which extended from March 1978 to January 19, 1984, the date of "initial criticality, provided a baseline of environmental data. Variability in the background levels of radioactivity due to differences in geologic composition, nuclear weapons test fallout, meteorological conditions and seasonal changes is reflected in that preoperational data.

REHP environmental samples have always been analyzed by a contract analytical laboratory. Since June 1986, Teledyne Isotopes, Inc. in Westwood, New Jersey, has performed the analysis of REMP samples. The thermoluminescent dosimeters used in the REHP to assess the direct radiation are processed by the Supply System External Dosimetry Laboratory under the Plant Services Department. I 3.3 Pr r m iv The REMP is the final stage in a series of monitoring programs that characterize and analyze the liquid and gaseous effluents from Plant 2.

Figure 3-2 presents this monitoring hierarchy from the generation of the waste liquids and gases to the calculation of doses from these effluents and the measurement of radioactivity in the environment.

The REMP provides a mechanism for determining whether the levels of radioactivity in the plant environs are within established limits and for ensuring that the accumulation of radionuclides in the environment will not become significant as a result of plant'perations. While in-plant monitoring programs are used to ensure that 10CFR20'nd 10CFRSO criteria for releases of radioactive effluents are met, the REHP provides supple-mental verification that the concentrations of radionuclides in the envi-ronment are not greater than anticipated.

Any radiological effect of Plant 2 on the environment must be distinguished from the normal variation in background radiation levels and from the effects of other sources of radioactive effluents in the area. The monitoring results obtained during each year of the plant's operation are compared to the preoperational data and to data from previous operating years, in order to determine whether a significant accumulation of plant-produced radionuclides has occurred in the environment. Should a significant accumulation be observed and be attributed to plant operation, steps would be taken to locate the release pathway and to prevent further releases.

3-2

NNW 8.2 NW 10.3 N 7.2 NNE 4.5 WNW 8.0 NE 3.5 ENE 1.4 W 5.3 E 1.6 ESE 2.5 WSW 4.3 SE 4.8 SW 6.0 SSE 10A SSW 10.6 900182.1 S 11.3 Mar 1991 Figure 3-1 1990 WIND FREQUENCY DISTRIBUTION IN PERCENT FROM EACH DIRECTION RELATIVE TO PLANT 2 3-3

MONITORING HIERARCHY Liqu.id/Gaseous Ef fluent Generation Effluent Monitoring and Sampling Technical Specification Limits Effluent Dose Calculation and Reports Radiological Environmental Monitoring Program FIGURE 3-2 THE MONITORING HIERARCHY FROM THE GENERATION OF LIQUID AND GASEOUS EFFLUENTS TO THE MEASUREMENT OF RADIOACTIVITY TO THE ENVIRONMENT 3-4

4.0 PR RAHD I TI N The REHP plan for Plant 2 is presented in Table, 4-1. It summarizes the sample locations, collection frequency and types of analysis performed on the sample media. The methods of sampling and sampling frequencies utilized in the, program have been determined by such factors as the half-lives and major exposure pathways for the,radionuclides potentially released from the plant to the surrounding environments 4.1 i n Seventy-seven sample locations were included in the 1990 monitoring pro-gram. Seventy indicator and two control, i.e. background, locations were within 10 miles (16 kilometers) of the Plant 2 containment. Three addi-ti'onal control stations and two indicator stations were outside the 10-mile radius from the plant. Sample stations are listed in Table 4-2 by meteoro-logical sector, sample media and approximate distance from the plant. The numbers and locations of sample stations are based not only on factors such as population distribution and meteorological conditions, but also on station accessibility, security throughout the year and the requirements of applicable regulations.

Haps of the RfHP sampling locations described in Tables 4-1 and 4-2 are presented in Figure 4-1 for sampling locations within the 10-mile radius and Figure 4-2 for sampling locations outside the 10-mile radius. A more detailed presentation of sampling locations in the Sunnyside/Grandview area is given in Figure 4-3. Haps indicating the sampling locations for each specific type of sample media are presented in Section 4.3 as Figures 4-4 through 4-12.

4.2 In August the annual land use census was performed, as required by the Plant 2 Technical Specifications.'ne objective of the land use census is to identify the locations of the nearest milk animal, residence and garden greater, than 50 m'500 ft') producing broadleaf vegetation within a distance of 5 miles from the plant. Another objective is to determine whether any site located during the census has a calculated dose or dose commitment greater than the sites currently monitored for the same exposure pathway. If so, routine sampling of that dose pathway, would be initiated at that new site.

The results of the 1990 land use census within 5 miles are given in Table 4-3. No milk animals are located within the 5-mile radius. The closest milk locations are at 6.4 miles SE and 7.2 miles ESE. One large garden containing broadleaf vegetation was located within 5 miles of the Plant during the 1990 land use census. Samples were not obtained at this location due to the owner's reluctance to participate in the sampling program.

4-1

The collection of environmental to the schedule personnel.

Instruction in Table 4-1.

Documented procedures samples for the REMP was performed according All samples were collected by Supply System contained in the Environmental Program Manual were used for sample collection and preparation. The

~ o following sections describe the Supply System's sampling and preparation methods.

4.3.1 Direct Radiation, During 1990, thermoluminescent dosimeters (TLDs) were used to determine the direct radiation levels at the fifty-seven (57) monitoring locations shown in Figures 4-4, 4-5 and 4-6. No new TLD locations were added to the program this year. The TLD located at Station 9A in Sunnyside served as the con-trol, or background, TLD. The other 56 TLDs served as indicator TLDs.

The environmental dosimeter consists of a card containing CaS04.Dy (251.)

phosphor in a Teflon matrix. Following oven annealing at 250'C for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the 31.75 mm x 44.75 mm x 0.4 mm thick card was loaded into a plastic case TLD's over-response to low energy photons. "

(Teledyne Model EB-2) lined with 0.58 mm copper (520 mg/cm~) to lessen the The TLD was prepared for the field by first wrapping the case with aluminum foil, sealing it in,two plastic bags and finally placing it in a cotton bag, which was hung from a metal post at each site. The TLDs were hung approximately three feet above the ground, Two sets of TLDs were employed at each location. One set was exchanged on a quarterly basis and the other exchanged on an annual basis. Exposure of the field TLDs during transport to the TLD sites was monitored by a set of field control, or trip control, dosimeters that accompanied the field dosimeters to and from the field locations. Another set of TLDs was used as building control TLDs which were used to determine the exposure of the TLDs if they remained in the lead cave during the entire quarter. The TLD exposure during transport to and from the field was determined by subtracting the difference between the building control results and the trip control results.

The environmental dosimeters were processed on a Teledyne Isotopes Model 9100 Automatic Reader. Following the initial processing, the field dosimeters were annealed and given a calibration exposure of 100 mR of cesium-137 gamma, in order to determine response (i.e, calibration) factors for each dosimeter. The calibration factors were then used to determine the total exposure received by each TLD.

The exposure values determined for calibration exposures, as well as the exposures of the QA dosimeters (processing control dosimeters) and audit dosimeters (spiked dosimeters), were based on the calculated field strength of the encapsulated cesium-137 source. The calculated field strength of the source was determined from National Institute of Standards and Technology (NIST)-traceable ionization chamber measurements made over a period of 4-2

several years during the routine use and calibration of the source.

Ionization chamber measurements made during TLD calibration were used to confirm the calculated exposure. If the calculated exposure and the ionization chamber reading differed by 5% or more, an investigation was done into the calibration exposure.

During 1990 a special test was performed to determine whether a particular set of TLDs that had been used as annual TLDs in the past had a higher TL signal fade rate over time than the other sets of TLDs used in the program.

The results of these TLDs when used in the field had indicated that this might be a problem. TLDs from the suspect group were distributed to various TLD stations and left throughout the year. Another set of TLDs which had not shown indications of signal fade were distributed to the same stations and retrieved at the same time as the suspect group. The results of this study are presented in Section 5.1 and Appendix C.

Three Reuter Stokes pressurized. ionization chambers (PICs) provide an additional capability for measuring direct radiation exposure. These units are maintained for use in special monitoring situations or as back-up moni-toring systems and are no longer part of the routine monitoring program.

Solar panels provide the power sources for the units in order to prevent equipment problems and damage caused by power surges and lightning.

4.3.2 Airborne Particulate/Iodine Air particulate and air iodine (I-131) samples were obtained through the use of portable, low volume (1.5 cfm) constant flow-rate sampling units at each of twelve locations. The samples drawn at Station 9A (Figure 4-3) were con-sidered control samples; the ones drawn at the other locations (Figure 4-7) were indicator samples. Air particulates were collected by drawing air through a 47mm-diameter glass fiber filter. Air iodine was collected by drawing air through a 57mm-diameter TEDA*-impregnated charcoal cartridge.

The particulate air filter and charcoal cartridge were placed in tandem, particulate filter first, in a holder that attached to the air inlet of the sampler unit. The sampler units were placed in ventilated metal weather-proof housings mounted on elevated platforms at each air sample location.

The air sampler units were run continuously, with the filter and charcoal cartridge exchanged weekly for analysis. The total sample time for each filter and cartridge was recorded from the elapsed time indicator and the sample volume was calculated and recorded. The filters and cartridges were shipped or delivered to the analytical contr'actor within one or two days of collection.

4.3.3 Water The water sampling network consisted of seven sampling locations: three for the evaluation of river/drinking water, one for the evaluation of discharge water and three for the evaluation of ground water. The locations of these sampling sites are shown in Figures 4-2 and 4-8. One river/drinking water

  • TEDA: Triethylene diamine 4-3

location, Station 26, was used for evaluation of the plant intake water, i.e., the river water taken upstream of the plant discharge point. This Station 26 sample can be considered a drinking water sample since the site draws its drinking water from the intake water. It is considered the river/

drinking water control sample because of its upstream location. Two addi-tional locations, Stations 28 and 29, were used to evaluate the water at the

~ o two nearest drinking water locations, the Department of Energy 300 Area and the Richland Water Treatment Plant. These two stations were considered indicator stations.

The Technical Specification requirement for a downstream water sample "near but beyond the mixing zone" was met by sampling water from Station 27, the plant discharge line to the Columbia River. This sample reflects the radioactivity present in the plant discharge prior to any river dilution, rather than the concentrations that would be found after dilution in the mixing zone. Water is drawn at this location because it was not feasible to perform the flow-proportional composite sampling required by Technical Specifications in the mixing zone area of the river downstream from the plant discharge point. This Station 27 sample is also considered an indicator sample.

tl Collins Model 42 composite samplers are installed at the two drinking water locations (Stations 28 and 29) and the control location (Station 26) to periodically collect 25-ml ali'quots of water at a regular time interval.

These aliquots are added to large collection bottles. At the prescribed intervals, the sampler collects, alternately, an aliquot for the sample designated for gross beta and gamma isotopic analyses and an aliquot for the sample designated for tritium analysis. A Collins Model 42-2P6 composite sampler draws samples from the discharge line (Station 27). It operates in a flow-proportional mode through a complex system that adjusts the sampling frequency relative to the flow rate in the discharge line.

Prior to the start of each monthly sampling period, concentrated nitric acid was added to the large collection bottles receiving the gross beta and gamma isotopic water samples to inhibit biological growth and plateout of dis-solved ions on the bottle wall. Acid was not added to the collection bottles receiving the water samples for tritium analysis. One gallon of each of the gross beta samples was poured into a clean plastic cubitainer each month. A 250-ml cubitainer was used to hold the monthly sample sub-mitted for the quarterly tritium composite.

Nonroutine analyses on the water samples include strontium-90 analysis, when the gross beta activity in the drinking water exceeds 8 pCi/liter or ten times the mean of the previous three months'ctivity for a specific loca-tion, and iodine-131 analysis, when the dose calculated for the consumption of water exceeds one mrem per year. Neither of these analyses were required during 1990.

The three groundwater stations are located on Supply System property: one well on the Plant 2 site (0.1 mile north of the Reactor Building) and two wells on the WNP-1 site (1.2 miles downgradient from Plant 2). These locations are sho'wn in Figure 4-9. Water from the Plant 2 well can be used 4 4

as a backup source for drinking and fire, protection. Water from the WNP-1 wells supplies the drinking and fire protection water for the WNP-1 site.

All three groundwater samples are considered indicator samples.

Quarterly grab samples were 'taken from each of these wells. One gallon was

'collected from each well for gamma analysis and 250 ml was drawn for tritium analysis. The gamma analysis samples were acidified with nitric acid. The tritium samples were left unacidified.

All the routine water samples were shipped to the analytical contractor within one to two days of collection.

4.3.4 Soil Soil samples were collected once during 1990, as required by the Site Certification Agreement. Samples were taken from the four indicator locations (Stations 1, 7, 21 and 23) shown in Figure 4-10. One sample was taken at the control location, Station 9A (Figure 4-3). Each sample was taken from an area of approximately one square foot and a depth of approxi-mately one inch. Approximately two kilograms of soil were used in each sample. Soil samples were shipped to the analytical contractor within ten working days after collection and analyzed for gamma activity.

If the gamma isotopic analysis indicated that cesium levels in any of the indicator samples exceeded ten (10) times the level in the control sample, a strontium analysis would have been performed on the sample(s). During 1990, no strontium analyses were required.

4.3.5 Shoreline Sediment Two shoreline sediment samples were collected twice during 1990 in accor-dance with the routine sampling schedule. The upstream sediment sample (Station 33) was collected from a location approximately two miles up the Columbia River from the plant discharge point. The downstream sample location (Station 34) was collected from a location approximately one mile downstream of the discharge point (Figure 4-11). Samples were scooped from under water near the river shoreline. Each sample consisted of approxi-mately two kilograms of the shallow surface sediment. The samples were placed in clean plastic bags and shipped to the analytical contractor within a day or two of collection.

4.3.6 Fish Fish sampling was performed during Hay and October, when the likelihood of obtaining anadromous* species was high. Fish samples collected from the Columbia River (Station 30 in Figure 4-1) were indicator samples, while the fish collected on the Snake River (Stations 38 and 38A in Figure 4-2) were control samples.

  • Fish, such as salmonids, which ascend rivers from the sea for breeding.

4-5

Four separate fish samples, consisting of an anadromous species and three other species generally considered edible or potentially edible (such as carp, catfish and whitefish), were collected at each location. Most of the fish were collected through the use of electro-shock, but samples of the anadromous species were also collected from the Lyons Ferry Fish Hatchery on the Snake River. The fish were filleted to obtain one kilogram of edible

~ o flesh per sample. The fillets were placed in clean plastic bags,, frozen until shipment to the analytical contractor. Fish samples were Shipped within 14 days of collection.

3. 3. 7 Mi lk Milk samples were collected monthly during January, February, March,"

October, November and December and semimonthly during the remaining six months when the cows were likely to be grazing. One gallon of raw milk was collected from each sampling location. The milk samples were chilled thoroughly and shipped to the analytical contractor within a day of collection.

Routine samples were collected from five indicator locations (Stations 36, 40, 59, 62 and 63) across the Columbia River in Franklin County, as shown in Figure 4-12. Milk samples were taken from Stations 40, 62 and 63 during only a part of 1990. Station 40 discontinued milk production in April, so Station 62, the Howard farm, ( 10.9 miles SE), was added., In July, milk sampling began at the Herr farm, Station 63, which is located at 6.4 miles SE. Addition of this sample was necessary to meet Technical Specification requirements for three milk sampling locations within 5 kilometers (9.9 miles)'rom the plant.

Samples were also collected at one indicator station (Station 9B) and one

~ e control location (Station 96) in the Sunnyside/ Grandview area (in Figure 3-3). Station 9B in Grandview continued to serve as an indicator station in 1990 because a portion of the feed for the cows at that location is hay from the north Pasco area of Franklin County. That factor makes it unsuitable for use as a control location.

4.3.8 Garden Produce Samples of local garden produce were collected monthly from April to September, when the produce was readily available. Nhen possible, three types of produce samples a root crop, frui't and a leafy vegetable were collected at each location. The indicator samples were collected from a region in a predominant downwind direction (Station 37 in Figure 4-2) where crops are irrigated with Columbia River water. The control samples were obtained from produce stands .in the Sunnyside area (Station 9C in Figure 4-3), the direction least likely to be affected by plant effluents.

In addition, apples were collected in August from Station 91, the Rio Vista Farms orchard, which is irrigated with Columbia River water and cherries were collected in June from Station 61, the Haymaker farm. These produce samples were shipped to the analytical contractor within one to two days of collection.

4-6

4.4 Anal i 1 P The analytical procedures used for the 1990 REMP samples are described e below. Teledyne Isotopes performed al analyses 1 of REHP samples during 1990.

"4.4.1 Gross Beta Activity on Particulate Filters The particulate filters were counted in a gas-flow. proportional counter after a delay of five or more days to allow for the radon-222 and radon-220 (thoron) daughter products to decay. An unused air particulate filter was counted as the blank with each weekly set of filters.

4.4.2 Measurement of Gamma Emitters

~il~a~nW~r A 1-liter Harinelli beaker was filled with a representative aliquot of the sample. The sample was then counted for at least 1000 minutes (16.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />) with a shielded Ge(Li) detector.

WFZhhZ<t As much of the edible portion of the sample as possible was loaded into a tared Marinelli beaker and weighed. The sample was then counted for at least 1000 minutes (16.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />) with a shielded Ge(Li) detector.

il n imen A large quantity of the sample was dried at a temperature below 100'C. As much sample as possible was loaded into a tared 1-liter Marinelli beaker and weighed. The sample was then counted for at least 360 minutes (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) with a shielded. Ge(Li) detector.

h al ar r r I din~

Charcoal filters were counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector was calibrated for both positions. The detection limit for iodine-131 on each charcoal cartridge was determined (assuming no positive iodine-131) uniquely from the volume of air which passed through it. In the event that iodine-131 would have been observed in the initial counting of a set,, each charcoal cartridge in the set was then positioned separately on the face of the detector and counted.

r i 1 Fil er Four air particulate filters for a quarterly composite for each field station were aligned one in front of another and then counted for at least 360 minutes (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) with a shielded Ge(Li) detector.

The shielded Ge(Li) detector was coupled to a mini-computer-based data acquisition system which performed pulse height analysis. A mini-computer software program defined peaks by certain changes in the slope of the spectrum. The program also compared the energy of each peak with a library of peaks for isotope identification and then performed the radioactivity calculation using the appropriate fractional gamma ray abundance, half-life, detector efficiency, and net counts in the peak region.

4.4.3 Gross Beta Activity in Hater One liter a stainless then counted of each steel sample was evaporated to a small volume and transferred to planchet. The sample was dried under heat lamps, cooled, on an automatic beta proportional counter.

calculated using empirical self-absorption The results were curves which enabled the correc-

~ s tion of effective counting efficiency, based on the sample residue mass.

4.4.4 Iodine-131 in Water Two liters of sample were first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin was used to remove iodine from the sample. The iodine was then stripped from the resin with sodium hypo-chlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free iodine. It was then back-extracted as iodide into sodium bisulfite solution and precipitated as palladium iodide.

The precipitate was weighed for chemical yield and mounted on a nylon planchet for low level beta counting. The chemical yield was corrected by measuring the stable iodide content of the water with a specific ion electrode. During 1990, this procedure was used only on intercomparison samples, since the doses calculated via ODCM methodology for the consumption of drinking water did not exceed 1 mrem per year (Table 4-1, footnote n).

4.4.5 Tritium in Hater Approximately two milliliters of water were converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 400 C. The hydrogen was loaded into a one-liter proportional detector and the volume was determined by recording the pressure. The

~ o proportional detector was passively shielded by lead and steel and an electronic, anti-coincidence system provided additional shielding from cosmic rays.

4.4.6 Strontium-89 and 90 in Hater, Milk and Soil During 1990, strontium analyses were not required for any routine REMP samples. They were used for intercomparison samples so the analytical techniques are described below.

Hai~r Stable strontium carrier was added to one liter of sample and the volume was reduced by evaporation. Strontium was precipitated as Sr(NO,), using nitric acid.

Milk Stable strontium carrier was added to one liter of sample. The sample was then evaporated and ashed in a muffle furnace. The ash was dissolved and strontium was precipitated as a phosphate. It was then redissolved and strontium was precipitated as Sr(NO,)~ using fuming (901) nitric acid.

4-8

The sample was first dried under heat lamps and a 10-gram aliquot was taken. Stable strontium carrier was added and the sample was leached in hydrochloric acid. The mixture was filtered. Phosphates were then pre-cipitated, collected by filtration and dissolved in nitric acid. Strontium was precipitated as Sr(NO,), using fuming nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge were then performed.

Stable yttrium carrier was added and the sample was allowed to stand for 5 days or more for yttrium ingrowth. Yttrium was then precipitated as hydroxide, dissolved and reprecipitated as oxalate. The yttrium oxalate was mounted on a nylon planchet and counted in a low-level beta counter to infer strontium-90 activity. Strontium-89 activity was determined by precipitat-ing SrCO, from the sample after yttrium separation. This precipitate was mounted on a nylon planchet and covered with an 80 mg/cm'luminum absorber for low-level beta counting.

4..4.7 Iodine-131 in Milk Two liters of sample were first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin was used to remove iodine from the sample. The iodine was then stripped from the resin with sodium hypo-chlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free iodine. It was then back-extracted as iodide into sodium bisulfite solution and precipitated as palladium iodide.

The precipitate was weighed for chemical yield and mounted on a nylon planchet for low-level beta counting. The chemical yield was corrected by measuring the stable iodide content of the milk with a specific )on electrode.

4.5 D n 1 M Since mid-1984, the results of the REMP analyses have been given as net results calculated from the gross or total counts determined for each radionuclide minus the background counts of the counting or detection instrument. Consequently, for several sample types, the results range from negative to positive numbers. This manner of presenting environmental data prevents the bias and loss of individual results inherent in the use of "less than" (<) values, where the "less than" numbers can have a variety of meanings, such as "less than the lower limit of detection (LLD)" or "less than the two sigma uncertainty."

The net results for REMP samples are presented with an asterisk (*) in front, if the results are less than the LLD. A listing of the LLDs deter-mined for each analysis is provided in Section 5.0 as a reference when reviewing the sample results.

Plots of the sample results versus time are used to represent the results for analyses such as gross beta on air particulate filters, where the results are normally above the lower limits of detection'n such cases, the indicator station results are plotted with the control station results 4-9

for easy comparison. Other data analysis techniques, such as log proba-bility plotting and plotting the moving average, are also used to represent the data and to determine whether trends that could be attributed to the ~

effect of Plant 2 operations are evident.

Thermoluminescent dosimeter (TLD) data is presented in terms of the net mR/day exposure rate. These results are determined from the total mR exposure calculated for each TLD from its total thermoluminescent output minus the TLD background, minus any transit (or trip) exposure received during distribution and retrieval, and divided by the number of days the TLD was in the field. Log probability plots and graphs of TLD data by meteoro-logical sector and distance from the plant are used to interpret trends in the results.

TLD data summaries include the term "standard error," along with "standard deviation." The standard error, which is the estimate of the precision of.

the mean, is used for mean annual summaries of mean quarterly data. The standard deviation is used for the TLD data involving a single dosimeter result that has been determined from the four reader areas of the TLD. Both terms simply provide an indicator of the uncertainty associated with the results.

4-10

TABLE 4-1 RAD A NV R MNTA H I P RHPA SAMPLING AND TYPE AND FREQUENCY

( )

AMPLE TYP AHPL TAT N N T N FR N Y ANA

1. AIRBORNE Particulates and radioiodine (6/12) 1, 4-+, 21, 23, 40, 48, and 57 Continuous sampling; weekly collection P i 1:

gross be)a  ;

Heck 1 y gamma isotopic'e) of quarterly composite (by location)

~I~1.: Heekl y gamma analysis.

Sol 1

(") (0/5) M, 1, 7, 21 and 23 Annually Gamma isotop(c strontium-90 g

2. DIRECT RADIATION TLD " (34/57) l-M, 10-25, 40-47, Quarterly, annually Thermoluminescent out-49-51, 53-56, 6] put; quarterly and 71-86 (1S-16S) ~ annual processing.

PIC(j) (0/3) 1, 21, and 23 Continuous recording Accumulated on mag as needed card and internal memory.

3. HATERBORNE Surface/ Z5, 27, 28 and 29 Composite aliquots  ; Gamma isotopic, Drinking Hater " monthly collection =

gross beta, quarterly; (3/4) tritium comp~site; s tronti um-$ 0 1 od1ne-131 ~ n)

TABLE 4-1 (Cont.)

RAOI NV N T NI T I P SAHPLING AND TYPE ANO FREQUENCY

( )

AHP E TYP HP TAT N N FR Y F ANA -Y I Ground Hater (2/3) 31, 32, and 52 Quarterly Gamma isotopic quarterly tritium grab sample Sediment from 33 and 34 Semiannually Gamma isotopic shoreline (1/2)

4. INGESTION Hl k 1 (4/6) 9B, 36, 40, Semimonthly during Gamma isotopic 59~ 52, 63 and grazing season, iodine-131;

~fp) monthly at other times strontium-90 q Fish (2/2) 30 and 35 Semiannually Gamma isotopic Garden Produce (1/3) K, 91 and 37 Monthly during growing Gamma isotopic season in the Riverview area of Pasco and a control near Grandview; annual collection at Station 91.

The fraction in parentheses for each sample type indicates the ratio of Technical Specification-required sample locations to the total number of sample locations currently being monitored in the surveillance program.

The underlined sample location designates a control station. None of the groundwater stations are control locations.

Deviations are permitted if samples are unobtainable due to hazardous conditions, seasonal availability, malfunction of automatic sampling equipment, or other legitimate reasons . Such devia-tions are documented in Appendix D.

TABLE 4-1 (Cont.)

Particulate sample filters will be analyzed for gross beta after at least 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to allow for the decay of radon daughter products. If gross beta activity is greater than 10 times the mean of the result for the control, Station 9A, gamma isotopic analysis shall be performed on the individual sample.

Gamma isotopic means identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents of Plant 2.

" Soil samples are collected to satisfy the requirements of the Site Certification Agreement (SCA) for Plant 2.

g'Strontium-90 analysis shall be performed on any indicator soil sample having cesium results greater than ten times the results for the control location.

" TLD refers to thermoluminescent dosimeter. For purposes of the REMP, a TLD is a phosphor card (31.75mm x 44.75mm x 0.4mm) with eight individual read-out areas (four main dosimeter areas and four back-up dosimeter areas) in each badge case. TLDs used in the REMP meet the requirements of Regulatory Guide 4.13'nd ANSI N545-1975', except for specified energy-dependence response.

Correction factors are available for energy ranges with response outside of the specified tolerances.

'LD Stations 71-86 are special interest stations and are not included among the 34 routine TLD stations required by the Plant Technical Specification Table 3.12-1. Their alternate designations are 1S-16S. St'ation 61 is also a special interest location. It was added to the program during the third quarter of 1989.

3 Pressurized ion chambers (PICs) are no longer required as part of the routine monitoring program. They are used only as a supplemental or backup system.

The term "river/drinking water," instead of "surface/drinking water", is used throughout this report because the surface water is taken from the Columbia River. Station 26, Plant 2 makeup water intake from the Columbia River is both an upstream surface, or river, water sample and the drinking water control sample location. Station 28 (300 Area) and Station 29 samples are drinking water samples. The Station 27 sample, which is drawn from the plant discharge line, is taken in place of a "downstream" water sample near but beyond the mixing zone. It reflects the radioactivity present in the plant discharge prior to any river dilution.

Composite (integrated grab) samples are collected with equipment which collects an aliquot at time intervals that are short relative to the compositing period.

TABLE 4-1 (Cont.)

(m) Nhen the gross beta activity in drinking water exceeds 8 pCi/liter, a strontium-90 analysis is performed.

(n) Nhen the dose calculated via ODCM methodology for consumption oF water exceeds 1 mrem per year, iodine-131 analyses are performed on the drinking water samples.

(o) Milk samples will be obtained from farms or individual milk animals which are located in the most prevalent wind directions from Plant 2. Routine milk samples are collected in areas of high dose potential instead of within 5 kilometers, due to the locations of milk animals.

( P ) Station 96 is the control station for milk samples because it was determined that the cows at Station 9B in Sunnyside were given feed grown in the Franklin County area across the Columbia River from Plant 2. Stations 62 and 63 at 10.4 miles and 6.4 miles SE of the plant, respectively,.were added during 1990 due to the unavailability of milk from Station 40 for part of the year.

(q) If cesium-134 or cesium-137 is measured in an individual milk sample in excess of 30 pCi/1, then the strontium-90 analysis will be performed.

(r) There are no commercially important species in the Hanford Reach of the Columbia River.

Most recreationally important species in the area are anadromous (primarily salmonids), which ascend rivers from the sea for breeding. Four fish specimen will normally be collected by electroshock technique in the vicinity of the plant discharge (Station 30) and from the Snake River (Station 38).

If electroshocking produces insufficient anadromous fish samples from the Snake River, samples may be obtained from the fish trap at Ice Harbor Dam, Lyons Ferry Fish Hatchery, or other similar facility (Station 38A). If insufficient anadromous fish samples are produced through electro-shocking on the Columbia River, samples may be obtained at the Ringold Fish Hatchery (Station 39).

(s) Garden produce will routinely be obtained from farms or gardens using Columbia River water for irrigation. One sample of a root crop, leafy vegetable, and a fruit is collected each sample period, if available. The variety of the produce obtained will be dependent on seasonal availability.

(t) Station 91 is an apple orchard irrigated by the Columbia River. The apple crop from Station 91 is sampled annually.

TABLE 4-2 MP AMP AT N BY T SECTOR STATION(b) ESTIMATED DISTANCE(c) SAMPLE TYPE(d)

N MB M M N (1) 52 0.1 161 GW 71(1S) 0.3 483 TLD 47 0.5 805 TLD 57 0.8 1201 AP/AI 18 1770 TLD 53 7.5 12068 TLD NNE (2) 72(2S)<<) 0.4 644 TLD 2 1.8 2896 TLD 54 6.5 10459 TLD NE (3) 73(3S) 0.5 805 TLD 19 1.8 2896 TLD 48 4.5 7241 AP/AI 39 4.4 7084 FI 46 5.0 8045 TLD ENE (4) 74(4S) 0.4 644 TLD 21 1.5 2414 AP/AI/SO/TLD 20 1.9 3057 TLD 11 3.1 4988 TLD 33 3.6 5792 SE 45 4.3 6919 TLD 44 5.8 9332 TLD E (5) 75(5S) 0.4 644 TLD 22 2.1 3379 TLD 10 3.1 4988 TLD 26 3.2 5149 PW 4-15

TABLE 4-2 (Cont.)

MPEL I 8 T SECTOR(~) STATION(b) ESTIMATED DISTANCE(c) SAMPLE TYPE(d)

NMBR M MTR E (5) Cont. 27 3.2 5149 DN 30 3.3 5311 FI 43 5.8 9332 TLD ESE (6) 76(6S) 0.4 644 TLD 31 1770 GW 32 1.2 1931 GW 51 2.1 3379 TLD 23 3.0 4827 AP/AI /SO/TLD 34 3.5 5632 SE 8 4.5 7241 AP/AI/TLD 42 5.6 9010 TLD 36(e) 7.2 11585 HI 5 7.7 12389 AP/AI/TLD 38 26.5 42639 FI 91 4,4 7079 FR SE (7) 77(7S) 0.5 805 TLD 24 1 ~ 9 3057 TLD 3 2.0 3218 TLD 41 5.8 9332 TLD 40 6.4 10298 AP/AI/HI/TLD 59 9.6 15443 MI 61 6.5 10456 TLD 62 10.9 16730 HI 63 6.4 10298 MI 4-16

TABLE 4-2 (Cont.)

EH AHP E TI N Y SECTOR(~) STATION(b) ESTIMATED DISTANCE(c) SAMPLE TYPE(0)

N HBER HIL HETER SSE (8) 78(8S) 0.7 1126 TLD 25 1.6 2574 TLD 55 7.0 11263 TLD 28 7.4 11907 PW 4 9.3 14964 AI/AP/TLD 29 11.0 17699 PW 37(e) 16,0 25744 GP S (9) 79(9S) 0.7 1126 TLD 1 1,3 2092 AP/AI/SO/TLD 6 7.7 12389 AP/AI /TLD

~ SSW (10) 80(10S)

  • 0.8 1287 TLD 50 1.2 1931 TLD 56 7.0 .1 1263 TLD SW (11) 81(11S) 0.7 1126 TLD 13 1.4 2253 TLD 96 36.0 49250 HI WSW (12) 82(12S) 0.5 805 TLD 14 1.4 2253 TLD 9A,98,9C(e) 30.0 48270 AP/AI/MI/GP/

TLD/SO W (13) 83(13S) 0.5 805 TLD 15 1.4 2253 TLD 4-17

TABLE 4-2 (Cont.)

SECTOR STATION R MP HP ESTIMATED T N BY DISTANCE T

SAMPLE TYPE(d)

~ o NHBR H H T WNW (14) 84(14S) 0.5 805 TLD.

16 1.4 2253 TLD 7 2~7 4344 AP /AI/SO/TLD NW (15) 85(15S) 0.5 805 TLD 49 1.2 1931 TLD NNW (16) 86(16S) 0.4 644 TLD 17 1.2 1931 TLD 12 6.1 9815 TLD (a) The area in the vicinity of Plant 2 is separated into 16 separate sectors for reporting purposes. The 16 sectors cover 360 degrees in equal 22.5 degree sections, beginning with Sector 1 (N) at 348.75 to 11.25 degrees and continuing clockwise through Sector 16 (NNW).

(b) The alternate designations for TLD Stations 71-86 are given in parentheses, i.e. 1S-16S.

(c) Distances are estimated from map position's for each location as a radial distance from Plant 2 containment.

(d) Sample Type Key: TLD Thermoluminescent MI Mi 1 k Dosimeter PW Surface (River)/

AP - Air Particulate Drinking Water AI Air Iodine GW Ground Water SE Sediment DW Discharge Water FI Fish GP Garden Produce SO Soil FR Fruit Station 9 designates the Sunnyside-Grandview control area. It is actually three separate stations (Stations 9A for TLD, AI/AP and SO, 9B

'or milk, and 9C for GP) within a few miles of each other and all within 30-35 miles of Plant 2. Station 96, which is the control station for milk, is also located within the control area. It is 36 miles from Plant 2. Station 9B, which was the control location for milk until 1986, is now an indicator milk location.

(e) Duplicate samples, i.e., samples drawn at the same time as the routine samples and submitted for analysis as a quality assurance check, are collected at this location. The station designation for the duplicate of Station 27 is Station 72. The station designation for the duplicate of Station 36 is Station 37.

4-18

TABLE 4-3 D TAN N M T N A T P NT F NT T NI THIN F V F P ANT NTA NMENT SECTOR NEAREST GARDEN2 DAIRY PARAMETER R ID NT M ANIMA IV NE 4.3 0 ENE 3.9 9(d)

E 4.5 p(e)

ESE 4.2 4 2(f)

SE 4.8 a These are estimated distances; slight variations occur when the map used for the land use census is changed.

Eleven of the sixteen meterological sectors within the five-mile radius of Plant 2 are on the federally-owned Hanford Site; the remaining land is comprised of 4.48 sq. miles of privately-owned farm land. Only those sectors containing points of interest are presented here.

The closest dairy animal locations are at 6.4 miles, 8.3 miles, 9.6 miles and 10.6 miles SE and 7.2 miles ESE. The dairy at 8.3 miles SE is not used for milk sample collection due to the owner's reluctance to participate in the sampling program.

Large garden with broadleaf; samples were not available due to owner's reluctance to participate in the sampling program.

Large garden at 5.1 miles E, but no broadleaf vegetation observed.

" Large garden, but no broadleaf vegetation observed.

g The closest meat animals observed were at approximately 5.7 miles ENE.

4-19

Ls, 5

~) sag FO )

SSCSLISSSpSW 10mi. Radius ~>I

)p

) SSOLLSSQSWQRlM RO.

Os)FDAIT g)4

) I BASIN

)

RSFS g CITY DASFS RLL Ros

)

ss )

)I )

"r"~

~ FOYAlossA)ARRscAD2 ROUTE11A 1

)

5 55 )

~

sss5 ClsST.

/ )

/

SDSSWOCO RO-

+o~ 4 ssmsssssc wssAsss5

)

O~ 1SSTCSCSST

)

)

ssssssss t

ylrry5 r r$~ i)I II

)g

)

~2

'5 ~ 15 )- ~ )

0 I ST )

) )

55 $ 2'I ~ 5I L )s ss ss ss sos K CCIA22

)

15 ~ 2'$

FS )

)

~ 51 I 5$

~ 51 240 25 02 5 1 ~ ~P ~ 25 Q) 5'SSYFFSFYA)

FFSWY.

g ) )

~ 51 )$ 5552VD2 r"~ w) )Sll SO.

~ sssw wsswsssw anford 5'OSSSSL I)

, OOCWOOO mw\sww ite CO Cl sIF E

~ ssssv. I

)

)

)

)

CGER PL 51 W. $ ACOSOOR M. )

)

CPA'ASST')LVFF$

'%s ss ~ ~ OSSSSSSS P'sSSSSSOIL

~ SsSSS 5 FYA

)

)

WWWWWW SU6$ ASS) )

s evasw>F sss ts~

ss ~ s HRwrww~ ALD)R R55s 5%%%%

)

)\

~~ss \

II

)

Sssssss s1s

). } ww ss)

~o j II IK Fs)LO NL

~

)

)I)F~ )

)

ly@

ROP)RY M.

RICHLAND Franklin AIRPORT

) I County Benton WEST RICHLAND 1)

BENTON County ~ LEGEND

~

PAVCD ROAD CITY RICHLAND ~ 55PRVD RD OR CRVL ROAD 224 182 FOORDRY LFS)$

FAT SCAL2 12 PASCO ~ ~ 215L ssssss.ss FIGURE 4-1 REHP SAMPLING LOCATIOHS HITHIH THE 10-MILE RADIUS 4-20

o

~ o

~ Othello WASH(NGTON Lower Granite Dam e Connell Lyons Snake River Priest Hanford ~ Feny Rapids Reservation Dam Vttfe Goose Lower Dam Monumental WNP-2 Dam 10 mile radius ~ Pomeroy 38A Ctarkston ~

~9C 462 IDAHO

~ Sunnyside ~ Dayton ggB +9A West k fllctdnnd 4 Eureka lttdda>>

Grandvtow g sfJ t3onton Pasco 3 8 96 ~ ~ lce Harbor Dam

~ Prosser 37A,B ~

Kennewtck

~ Walla Walla McNary Dam OREGON Cotumbia R'v Inch ~ 16 mlles 0 8 16 L Sample Locations 900266 A April 1991 FIGURE 4-2 REMP SAMPLING LOCATIONS OUTSIDE THE 10-MILE RADIUS

~ s

~ e

STATION 9B II INDEPENDENCE RD 0 AIR STATION

+ TLO SUNNYSIDE 9A

[ f sou.

FACTORY RD +0 VEGETABLE STATION I-82 9C STATION RAY RD g

96g z 00 FORSELL RD McCREADIE RD GRANDVIE I-82 2!

R m YAK I-82 0

m 22 MABTON PROSSER SCAI E IN MILES 0 1 2 3 4 5 6 880188 FIGURE 4-3 REMP SAMPLING LOCATIONS IN THE SUNNYSIDE/GRANDVIEH AREA

L~BFO

$)

10mi Radius SI. III CHfSTRUT I III I I BASIN I IH CITY SHfFRflD RO. <<m Lgs ~ I AFCOlYWFR RQ L

TDYAK91AAuRR19AQB I 3 ROUTE I IA I

I J Ye r I I

pf 64 VSSICC I I OAYCC CJL WO WWWWWW&

RAC 9¹ W. JVHRIR RO.

CHCA4HCC r

I',

WA1ACCCC IMPITHO HATClCAY I 91 gs rlw )

@r I l~g O

19 ~ 19 r ~ I I

67 ~ IC I I I I WVC IWCCADI 66 1461 +21 ~ L ~ 49 L~~ L w w a r4 K COAee RD I

15 ~ 1 I I

1 91 I

~ 51 I 240 9S no ACATHIWS 1 ~ ~ 94 Ql s$

FRWY. wesT F61 RQ, I II

~ I I

~ 91 IIBfcceweoR. s r- ~

KOWH HJCHUI anford 4'1 ~ CCHCCC

. OOCVOCO pwl\Qw DOOWOOOwwww CFA ite CCCCT. I I

I I

HHWWW NY CEDAR I

I 46646IWI

\wow& rwwf I w%wwww 61 W.~RQ. I I

r a

+IP

~ ACVAI41N IAHCCQC WW 8 RQ.

WWHW&lfW&AHHH

%AAVIA11\VAhg I BFA WNKBCVFFS 69 I

SVBSTATIOH RQ. I

~ ACDIR&wllwwwwIIw

<<wwS II s I s 5$

I s CASSAVA s I s

~o O~ I)

I I

I Og RICHLAND Franklin AIRPORT OfHT County Benton WEST RICHLAND BENTON County ~ LEGEND 9AYEDROAD CITY RICHLAND mme NFRVDRDOR ODYL ROAD 224 182 BOVHDRY 191IS FAY 12 PASCO 8L 82 FIGURE 4-4 INNER CIRCLE TLD LOCATIONS 4-23

~ o

~ o

cll ~

10mi. Radius il I

I HCCANOSWQRTH RO.

I I

lg I BASIN CITY 0414 SASSI Wu. R 170 I

/%> I II wIHI, TOYAKSAAAFRCOAOE I

RPIJTE ) ) A \

~ ~

J

~ 12 r

Ts"~r r gr' I

P RVSSQA P4' SAWS TN

&0 C

I lg I

NR CCHT. W. JNIIPFR RO.

WAIAIHS IHAIIHS I HAIOCAY I

~ &

I Ig I

QD I

~ 14 0 44~ SY I

I IR ~4 20 4

I 158 I 2S Lag 454 524

~5 I

IS+4 14 I

~ 31 I

I 240 I 45 4S $451 (43 54 QC ++4 24 WIST FSI RfL I I

I

~ 41 ~

I

~~OR s r-,

anford e CHCCI,

. DOOWOOO wwlo& &we ite CVCCT.

~

I I

'OOWOTO I

I I

OIOAR I

0 CCKMIIITg 41

<<444RAH w &wllw&w\wwI W,SAO RO.

I

~ MUAAW I I I44444 CR 8 Ro.

ff: maemeCg Pwm W\%WW INVbVAS%%%

0, CO I L SPA WHffESTVFFS 42 I

Tr"- SVSSTATTOH I

~4 y" 4 II

~ AIOIRRL wS &we Swww& IA s

2$ I S CH<<14I s I s 0~ sm I

I I

Og RICHLAND Franklin AIRPORT County Benton WEST RICHLAND II OFMT BENTON County ~ LEGEND

~

PAVED ROAD CITY RICHLAND mme 111PRYOROORORYf ROAD 224 ) 82 SNDORY TDRS FAY 12 PASCO 82 FIGURE 4-5 NEAR-PLANT TLO LOCATIONS 4-24

Qr~g&D 10mi. RadluS

I R

Franklin I

RICHLAND AIRPORT i County Benton WEST RICHLAND BENTON County ~ LEGEND PAVED ROAD CITY RICHLAND <<we SFPRVDRDORORYL ROAD 224 182 BOVHDRY LS1ES FAY 12 PASCO 82 FIGURE 4-6 OUTLYING TLD LOCATIONS HITHIN THE 10-MILE RADIUS 4-25

clIe ~>>

10ml. Radius ~I ly I

I

'RESTNIT I

I I BASIN I IR I

CITY I,

Eep~eeN SAFIACWWER RO.

To YAKOIAAARNOACE A ~ I~ I ROuTE qg

~ 12 s,

I J

200 EAST WWWWWW RAACONT. W. JVMIPER RO.

I SSNWCCO RO.

+0~ 4 emANOI WAFCIACI s

I1400040 O~ NATOCW I I

4p'4 r + 5 ~i

~2 1~ ~ 10 0 1T I 40

~ 20 I I OF I I 4 L le a a a ebs 153 IE COEEE RO. ~

'30 620 I 15 ~ I I I

1 31 I

~ 61 03 43 240 23

~01 IIATREWS IN 3

QO ~ ~ 24 Ql s$

~ 01 FIR WY.

I

'H~

I WEST Sl RO. I I I

20544EwEIEE I

I s

~

CONN IIASOOIIN anford 41 ~

~ CNOOC OCCWOCO Mal e &we ite ~ CROT.

r I

I I

I AWWWWW IY CEOAR I

I IE' 61 I

+wm Tmmamma W. SAOEMCCR RO.

I

~ AOVAVOO I 'ARCOCFC M.

K O,

~%P W B

WWWWW WWWWWW

\\\\\eeeeeeeeeee\ CO II I I e epee'bw Lwvw eeeeee ~

easel BPA WIEIEECIIIPS SOBSTATSN 0

lt ~ AIDER RO.

I I

I&&&\If w It s I s

~ eeee 1ee I s 55 )cene wl I 1E RElO OIL s

I I I Ojg, I RICHLAND Franklin AIRPORT County Benton WEST RICHLAND County ~ LEGEND PATES ROAO RICHLAND w m e SI PAVO RO OR ORYL ROAO 224 182 ~e BONSRYLJIES FAY 12 PASCO 82 FIGURE 4-7 AIR SAMPLING LOCATIONS NITHIN THE 10-MILE RADIUS 4-26

~ o lj

I ~~

10 mi. Radius lg r g FSRAWGSWORTH RO. II I Ig I BASIN I I CITY g I BAS41 FRA Ra R llo I

"r"~j I SHEFVTELD RO.

TCY~~ ROUTE 11A I BEUFTDWER RR eI I J err I

~ s OAVTS IFL

&WW WW FHS CONT. W. RBTDER RO.

I 8 SHHWCS WHNJKS rr aCWWOOO RO.

IMHTHO 154.

HATCHEIIY I

~2 I 14 ~ 19 0 49 17

~ 24 I

I I 9P I I ~

1551 1 2S 2+1 ~ Lwg le w a m ass 454 . NO0%EERD 15 ~ I I

1 51 I

R 240 1 95 WTHEWS 25 3 CORNER 1 ~ +4 ~ 24 Qg ARWY. WEST F81 RO. I

~ I

~ Ol f W anford 4, ~ 4O9395

. OOOWOCO

&W%$ &W ite CO

~ CHOOI IIF E 5H44T.

rI I I I

WWW&%%

CEDAR O

C.

~ ~1 4 W. SAGEMOMRD.

I

~ AOHHVS I I ~AH544ll

.8 RD 1T: ww eCg(Law w W W&WWW WWW O

Vh'a\I\\\\%\%\%1 CO a8 II I I HD L

SPA W15TEFWFFS AACA I I gSVBSTATQN ~ ATDERRO I 4 HWI ~

s I 5$

I I

I I I)

')> I I I I

RICHLAND H 3

Franklin AIRPORT County Benton WEST RICHLAND BENTON County ~ LEGEND

~

PAVED ROAD CITY RICHLAND w~ ~ NPRVD RD OR ORVL ROAD 224 BOOHDRY IBTES FAY 12 PASCO 1990 880334.63 82 FIGURE 4-8 RIYER/DRINKING AND DISCHARGE WATER SAMPLING LOCATIONS WITHIN THE 10-MILE RADIUS 4-27

IH~>>

10 mi. Radjus I

I I

sg I BASIN CITY I II I s~ II R 1 70 To Y~ ~ ROIJTE 11A

~ 12 B.p I

BGFFOWWER RD.

44 s WWWW W FHS CONT. W. 40IPER M.

I

+o~ SHIHAHCS WHCAHS BTOHWOOO RO, SHAITHO u93 O~ I NATCHOAY

~W I"";I I s~g

~2 I 14 ~ 19 0 I 49 ST I 4

I 15S I 210L L~g ASH I 15 ~ 1 22 I

' I

'T>> I 240 I 93 SS EAATHEWS

~

25 3 sf

'I

~ 24 Ql III FFIWY. WEST FST M. I

~ I I

~ 91 ~ BE1AEVOE ESE s I

r- ~

anford '3 SCHOOL p'al 41 COO WOOD ite SCOTT. I rI I

I C3 IY +'EDAR W I 0 OWNIHTQ CHH\HAN 41 W. SAOEMOOR RO.

I I

I iAHSSCIL B RO.

EE w m m eJCpPw w WWW W WAWWWW Cl CO II I I BPA WHREBENTS 42 I

gSUBSTATICH ~ ATOER RO. I 4 HHHI w%w gQQAA'lf&

s I

CNNI HA I) s s

sI s

I I I Ofg I RICHLAND Franktin AIRPORT County Benton WEST RICHLAND BENTON County ~ LEGEND PAVED ROAD CITY RICHLAND ~ BAPRYO RO OR ORYL ROAD 224 182 BOAOBNTY ERIES FAY 12 PASCO 1990 880334.63 82 FIGURE 4-9 GROUNDHATER SAMPLING LOCATIONS 4-28

I HIaaB 10mi. RadiuS ~1 Iy I

I HCEANGSWORTH RD.

CHESTNVT I

I I Ig I BASIN CITY OATS I Ig Pc aaaa Bc@ aav I ETAFTDWWER ISA TO VAICSIABAIVHCADE ROUTE I I A rrr r I I Oe /fan I

ac aa FFN CCHT. W. RINIPER RO.

I NINWOOO m.

DIHVHCS WHCAIKC IHwTHS leev HATOCHV I 0

~2 14 ~ 14 0 44 ST I

I I I I 4

Tel Lag I 14SH N. COIAEE RO.

4SH I 14 ~ I I I m 14 21 I

~ 41 SS 44 240 JS I ISQH QP ~ Ql 45 FSTWV. f WEST IR RO. I

~ I I

~ 41 IBOAEYVEoa s I

f

~ DHH HAICHAH anford 41 ~

SCHOOA DOGWOOD

'lcaa a ite KF'\

~ veev, r

I I

I I

ICS iY +'EDAR r I

aa\

0 r' COUhNIAQ CIWellAH I

I aaaaaa TE

~ 41 anal W. AGFEMOCR RO.

I cAOVAIHAS I I cAHce DIE K

O a a a eCpia a 8

\aaaa RD.

aaaaaa C\%%%C%%CV1\%\a i~ ~ aaNK BPA WHREBEVFFS gSVBSTATON 4

zlV CO II aa ~

42 AIDER RD. I I

s I

I Iaaaa I s cAccl Ia s I s

~o I Cl P.

I) }.

hpg s I> I ~

I I I

Cr@

RVPERT RO.

RICHLAND R

Franklin AIRPORT County Benton WEST RICHLAND BENTON County ~ LEGEND PATED ROAD CITY RICHLAND aa c BAPRYD RD OR GRYL ROAD 224 182 <<~ SOVNDRY EBIES FAY 12 PASCO 82 FIGURE 4-10 SOIL SAMPLING IOCATIONS HITHIN THE lOaMILE RADIUS 4-29

grigglO 10mi. RadiuS <I . III I

I HCAAWGSWORTH RO.

CHESTNUT I

I BASIN CITY To Y~~ ROUTE 11A

+p~~ ~

L ww w RD.

~ 12 I

I 1

WWWW W. AMBER RD.

I RCHWOOO Te.

4 THTAAHOS WAKllc4 I

IMJITHO HITOHAY I

~2 14 ~ IS O I 4S 47

~ 20 I I

I I 23$ 2+I ~ L~g I

16 ~ I I I

31 I

~ ST I SS 43 240 50 IIATHEWS I$

26 3 CORNEA Ig I~ ~ ~ 24 Ql 65 FRWY. WEST FR RO. I

~ I I

~ SI ~ SIIAEYVSDa I I

r ~

SOWN IWIOIAII anford 41 ~

43 IOHOOl

. DOGWOOD W %\0 W \

ite .

<<44T.

r I

I I

I QRHWHW iY 'CEDAR I

0 I I

41 W.SAGEMOMTO.

I wwwwww I

~ AOOAHOS I

K

~ ~AHSSOA I WP RD. W ~ &&WAN ES, AVIVA\1%WAVA HI I SPA WTlESBVFFFS AATA 42 I

gSVSSTATTON IIT I

~ AIDERaRD. Qeaeeila

'ATTI>> anal

,II II I

I RICHLAND Franklin AIRPORT County Benton WEST RICHLAND BENTON County ~ LEGEND SAYED ROAD RICHLAND ~ SIPRYD RD OR ORYL ROAD 224 182 SOVHTHW TSIES FAY 12 PASCO 1990 880334.63 82 FIGURE 4-11 SEDIMENT SAMPLING LOCATIONS 4-30

l ~ie ERD 10mi. Radius ~I I

lj I BASIN CITY I IIII I R 110 ROUTE 11A I I J R VSSEEL DAVIS EN I sg I

ae aaa RHC CCHI, W. JNIPER RL CHIHHHS WIICIAN llAHI440 5555' HAICHQlYI a

Iaal

~2 I 15 ~ 19 0 49 57 I

I I 4

I I 15S

\ IS+ 21 ~ Lag I <<aaeAe N. CONES RL 4Se I 15 ~ 10 I I

51 I

240 NATHEWS DS I~ ~ 24 Qs 4 FFCWY. WESTFSIRD.I

~ I

~ 91 I

SRAEVDSOCE S I

wI E555 RD.

anford 41 ~

CDHN lQNOWI CCHCCC

. DOGWOOD Ie a%e el a aaa ite CCeCI. I I

I I

CEDAR

~ 40 I 0 CCWNIRTg I CHCCCHAH I 51 aS aaaaaa W.SAGEMOQRM, I

a iiJOUHVCS I se AICCC NC 8 RD.

EE O

a a a eJCge Ie a a aaaaa BPA WHlTE8WFFS CO I I

eeee\ewA Saveeee eeeeeeeeeee gSOSS TATNN 5~ 8s,~ aa>>S4~~. I a Qa a a a II I I eeelle I 10 s

I a+

RICHLAND R

Frankl n AIRPORT County Benton WEST RICHLAND BENTON County LEGEND PAVED ROAD CITY RICHLAND a e BCPRYD RD OR ORVL ROAD 8 224 182 BONIDRY 58CES FAY 12 PASCO 1890 880334.63 82 FIGURE 4-12 MILK SAMPLING LOCATIONS HITHIN THE 10-MILE RADIUS 4-31

~ o

~ o

During 1990 the analyses of REMP samples were performed by Teledyne Isotopes in Hestwood, New Jersey. The thermoluminescent dosimeters were processed by the Supply System External Dosimetry Laboratory. Table 5-1 presents the means and ranges of the 1990 results for each type of sample collected. The means and ranges of the preoperational and the previous operational data from 1984 to 1989 are also included in the table for comparison.

The data for the preoperational period and the first six months of 1984 included "less than" (<) designations for results below the actual LLD, the contractual LLD or the two sigma error, depending upon the convention employed by the analytical contractor. Consequently, the data averages using "less than" values are biased high.

The use of the "less than" designation was discontinued in mid 1984. Since then, REMP data have . been reported as net results, i.e., total (gross) results minus the detector counting background. Comparison of the mean results for 1990 to the mean preoperational results is difficult due to the high bias resulting from the "less than" data. However, comparison of the range of results observed for each period to determine whether the 1990 results are significantly greater than the results for preoperational and previous operational periods, is a viable approach. Careful interpretation of the data ranges for the previous operational data is still required because of the effects of the Chernobyl accident in 1986. For this report only the data from the last six months of 1984 were included in the previous operational data in order to eliminate the "less than" values in that category of summary data.

The 1990 REMP data compares well to the ranges of data from previous periods. The quarterly TLD results for 1990 were very close to the 1989 results and slightly lower than the 1987 and 1988 results. These slight changes in the TLD results are certainly within the normal range of uncertainty expected for TLD systems.

The 1990 annual TLD results were about 5-101. lower than the mean quarterly results. This relationship between the two TLD distribution types has been observed in nearly all the previous years. It is apparently due to slight fading of the TLD signal on the TLDs kept in the field for the entire year.

The LLDs generally determined by Teledyne Isotopes for each analysis performed and each radionuclide of interest are listed in Table 5-2.

Presented alongside the Teledyne )LDs are the LLDs required by the NRC Branch Technical Position (BTP).('he LLDs determined for analyses at Teledyne Isotopes have met the NRC requirements in all cases.

A summary of the REMP results relative to detection limits is presented in Table 5-3. If a particular radionuclide of interest was not detected in the 1990 samples, the term "LLD" is noted in the data mean and range columns.

Aside from some naturally-occurring radionuclides, the radionuclides detected in the 1990 sample included cesium-137 in fish, soil and sediment, 5-1

and cobalt-60 in the discharge water; tritium was also detected in some water samples. Gross beta results in air and water were nearly all above the detection limits.

In general, the positive, or detected, 1990 results compare well with the results from previous years. Any significant differences or increases evident in the 1990 results are discussed in the following subsections.

Summaries of the environmental radiation exposure rates, determined by thermoluminescent dosimeters (TLDs) are presented in Tables 5-4 and 5-5.

The individual quarterly and annual results for each TLD station are given in Tables A-l.l and A-1.2 of Appendix A. Figures 5-1 and 5-2 show the mean quarterly results for near-plant and remote TLD locations for the preopera-tional period, 1984-1989 and 1990. Figures 5-3 and 5-4 show the annual TLD results for near-plant and remote locations for the same periods. In general, the quarterly and annual results for the control location (Station 9A) show the same fluctuations over time as the indicator locations and the relationships between the different locations remain very consistent over the three periods.

Figure 5-5 presents th'e mean 1990 results for each of the sixteen meteoro-logical sectors, compared to the sector means for the preoperational and previous operational periods. The relationship of the mean 1990 results to the results for the preoperational and previous operational periods is very similar for each sector. This indicates that there were no significant directional effects observed in the 1990 TLD results. The annual TLD results for each sector also follow the same pattern as the mean quarterly results, except they are 5-101. lower.

In Figure 5-5, the apparent increase in the mean 1990 TLD results over the means of the preoperational and previous operational periods is due to the effect of averaging only the four quarters of 1990 data versus averaging numerous quarters for the other two sets of results. The differences between the data sets are generally within 101., which is within the range of variation normally expected for TLD systems.

Station 46 in the Hahluke Reserve remained the location with the highest mean exposure rate, 0.31 mR/day. This is the same mean exposure rate deter-mined for that station for 1989. Since the preoperational measurement phase, the results for this location have exceeded the results for all other locations. Variations in the ambient background due to variations in the soil and underlying rock composition account for such local differences in the TLD results. Figure 5-6 compares the Station 46 results to the results of Station 9A, the control location, from 1982 to 1990. The relationship between the results at these two locations has remained fairly consistent from the preoperational period (1982-1983) to the present.

5-2

A comparison of the 1990 annual and mean quarterly TLD results is presented in Table 5-6. The 1990 annual TLD results are generally 5-101. lower than the mean quarterly results because of the signal fading characteristics of CaSo4. This difference is not significant, in light of the variability commonly observed in TLD results. In most cases, the annual result is within the uncertainty associated with the quarterly TLD results.

During 1990, a test was performed to determine whether one set of TLDs that had been used in the past for the annual measurements had a higher TL signal fade rate over time than the other sets used for the same purpose. The higher fade rate was suspected because during the years when the set was used, e.g. 1988, the mean quarterly results and the annual results differed by approximately 15-201.. As described in Section 4.0, the test involved collocating nine of the suspect TLDs with nine of the TLDs that had not exhibited a high fade rate. At the end of the year, when these two groups were processed, the mean result of the suspect TLD group was 121. lower than the other group. As discussed previously, all the TLD sets appear to exhibit some TL signal fading, normally amounting to about 51.. But the fading of the suspect group was significantly more than that, so the set will no longer be used.

The log probability plots of the 1990 and previous operational (1984-1989) quarterly TLD results are presented in Figure 5-7. The "slopes" of the lines in both plots are nearly the same, indicating that both sets of data are part of the same distribution.

The log probability plots of the 1990 annual results and the results from previous years of operation are presented in Figure 5-8. The 1990 results are consistent with results observed for the past monitoring periods. The slopes of the lines determined for this .data are typical for ambient radiation measurements.

The log probability plots of the quarterly data for a near-plant locations, Stations 71-76, and the control location, Station 9A, from 1982 to 1990 are presented in Figure 5-9. The linearity of the plots indicates that the results are all within the same log normal distribution and that no significant increases or decreases indicating a change in the environmental radiation levels were evident.

The above comparisons of 1990 TLD results to preoperational and previous operational data and the analysis of results by meteorological sector and distance from the plant demonstrate that Plant 2 operations have not impacted the direct radiation levels in the environment around the plant.

5.2 r n The results of the 1990 gross beta in air analyses are presented in Tables A-2.1 and A-2.2 of Appendix A. The 1990 mean weekly results of all indicator stations are plotted in Figure 5-10. The gross beta in air results for 1990 were within the ranges observed during the preoperational 5-3

period and during previous operational periods, as shown in Table 5-1 and in Figure 5-11. As observed pr'eviously, gross beta levels increased during periods of inversion occurring in the fall and winter months. In fact, the gross beta results plotted over a period of several years (Figure 5-11) show a cyclic pattern of'all and winter increases. The increase, which was

~ o evident in the results of all the air sampling locations, including the control location at Station 9A, was likely due to an increase in radon and radon daughter concentrations during the inversions. In Figure 5-12, plots of the weekly gross beta results for near-plant and remote locations and for the control location at Station 9A illustrate the similarity of the results from all locations.

The quarterly gamma analyses of the particulate filter composites, in general, indicated only the presence of beryllium-7 and potassium-40, two naturally-occurring radionuclides, at levels above detection limits at indicator locations and the control location. The results of the gamma analysis of particulate filter composites are presented in Table A-3. and 1 A-3.2 of Appendix A.

The results of the gamma analyses of charcoal cartridges for iodine-131 are presented in Table A-4.1. All iodine-131 in air results for 1990 were less than the 0.01 pCi/cubic meter LLD.

No evidence of any impact of plant operations on the environment was apparent in the particulate filter and charcoal cartridge results for 1990.

5.3 ~W During the first eight months of 1990 there were frequent periods when sampler inoperability prevented the continuous collection of composite water

~ s samples from the discharge line (Station 27). The focus of efforts to meet Technical Specification requirements during these periods was to put the composite samplers back in operation, at least by the end of the next sampling period. The ma]or problems plaguing the system were resolved when sludge was cleared from the sampling line, which carries water from the discharge line to the sampler. From August to mid-'December the sampler operated normally. The outage periods and corrective actions taken to remedy the equipment failures are presented in the sample deviations listing in Appendix D.

To resolve other operational problems associated with the discharge sampling system, two new samplers which do not rely on an external pump to supply sample water will be installed in the river pumphouses during the 1991 plant maintenance outage. The use of two samplers at this location will enable the continued collection of flow-proportional samples when one samp'ler is inoperable. In addition, a schedule will be developed for periodically clearing sludge from the sample line.

When these composite samplers were not operational, grab samples were often taken as a matter of "good practice," in order to estimate radionuclide 5-4

concentrations in the water when flow-proportional sampling was not feasible. The results of the grab samples taken during these periods are presented in Table C-1 of Appendix C.

The gross beta in river/drinking (including intake) and discharge water results are given in Tables A-5.1 and A-5.2 of Appendix A. All river/

drinking wa'ter results were within the ranges normally observed and less than 8 pCi/liter, the level at which a strontium analysis is performed to verify compliance with the Washington State drinking water standard for strontium-90*. A graph of the gross beta in river/drinking water results during 1990 is presented in Figure 5-13. The gross beta in river/drinking water results from 1984 to 1990 are presented in Figure 5-14. The higher levels observed in the Richland water results in early 1986 and 1987 are due to the use of well water, instead of river water, during the annual maintenance outage of the Richland Water Treatment Plant.

The 1990 gross beta levels in the discharge water were slightly lower than most previous levels observed since the last ha'lf of 1986, as shown in Figure 5-15. The average gross beta result for 1990 was 15,8 pCi/liter, compared to the 1989 average of 30.9 pCi/liter. This lower gross beta level resulted from the current mode of plant operations using less concentrated circulating water, i.e., lower cycles of concentrati'on. The gross beta levels in the discharge sample reflect the concentrations of naturally-occurring radionuclides, principally potassium-40, and any radionuclides from upstream sources or past Hanford activities present in the makeup water, in addition to radionuclides from Plant 2 discharges. The discharge sample results are representative of the radioactivity present in plant discharges before any mixing with river water occurs. Therefore, the sample is not indicative of the actual radionuclide concentrations in the river water downstream from Plant 2. This conservative approach of flow-proportional composite sampling from the discharge line in lieu of sampling from the river near the downstream edge of the mixing zone (as required by Technical Specifications) was considered to be the most feasible option.

However, careful interpretation of the results from this sampling point is necessary, since they do not represent a true environmental sample.

The 1990 gross beta results for the discharge sample are presented in Figure 5-16. The temporary, or interim, DOH investigation level (75 pCi/liter) which prompts an investigation into the results is shown for comparison, so that these gross beta levels can be put into perspective.

Also shown is the maximum annual average gross beta level in ~i Qgg ~w for compliance to the 4 mrem per year state dose limitation, 50 pCi/liter.

The tritium results for river/drinking water, discharge water and ground-water are presented in Tables A-6.1 and A-6.2 of Appendix A. The tritium levels in the river/drinking water were all at or slightly above the LLD for that analysis, as shown in Figure 5-17. All the results were within the range normally observed in such water and within the range of the pre-operational and previous operational results for the same stations.

  • Strontium-90 is assumed to account for the gross beta result.

The tritium levels in the discharge water were higher than the levels observed for the river/drinking water samples because of plant releases. As shown in Figure 5-18, they were consistent with the levels observed for the.

past several years. The levels are reasonable for samples taken directly from the, discharge line prior to any river dilution. Compared to the annual average concentration of less than 20,000 pCi /liter of tritium for g~Qng r to be in compliance with the state dose limitation, the'esults were

~w

~low. ") A graph of the discharge water tritium levels for 1990 alone is presented in Figure 5-19.

The tritium results for the quarterly, groundwater samples were all" below the LLD. They are presented in Table A-6.1 of Appendix A.

The results of gamma isotopic analyses on river/drinking water, discharge water and groundwater are listed in Tables A-7.1 and A-7.2 of Appendix A.

The results of grab samples taken during composite sampler inoperabi.lity are presented in Appendix C. All results for the river/drinking water and ground water samples were less than detection limits. All results for discharge water samples were also below the detection levels, except the result for cobalt-60 in the 5/16-6/13 routine composite sample (8.6 pCi/liter) and cobalt-60, zinc-65, cesium-134 and cesium-137 (11.0, 21.0, 7.6 and 9.7 pCi/liter, respectively) in one composite of discharge water grab samples taken during May. Although above detection levels, these results were low and did not exceed any reporting levels.

e.

\

5.4 5gQ Gamma spectrometry was performed on five soil samples collected in May.

The cesium-137 levels in the samples ranged from 32.9 pCi/kilogram to 493 pCi/kilogram. Aside from cesium-137, the only radionuclides detected in the samples were potassium-40, radium-226 and thorium-228, which are part of the natural radioactivity typically found in soils. As shown in Table 5-1, the cesium-137 levels in the soil samples were well within the range observed during preoperational and previous operational sampling.

The gamma spectrometry results for the 'oil indication samples of are given of Plant in Tables A-8.1 and A-8.2 in Appendix A. No impact 2 operations on the environment was evident in these results.

5.5 h 1 n i n The results of gamma spectrometry of shoreline sediment are presented in Tables A-9.1 and A-'9.2 in Appendix A. Aside from the naturally-occurring radionuclides (potassium-40, radium-226 and thorium-228), only cesium-137 was detected downstream of the plant (Station 34). Cesium-137 was also detected in the control location (Station 33) sample. The cesium-137 concentrations upstream from the plant discharge point were 90.8 and 115 pCi/kilogram; the concentrations downstream from the discharge point were 182 and 197 pCi/kilogram. These are consistent with the concentrations observed previously. A graph of the cesium-137 results in sediment from 1984 to 1990 is presented in Figure 5-20.

5-6

Cesium-137 has been detected in preoperational samples and in samples taken since plant operation began. 'It has also been previously identified as a component of the Columbia River sediment originating from the operation of the old Hanford Reservation reactors.~'.

6 ~Fi The gamma spectrometry results of fish samples collected in the vicinity of the Plant 2 discharge and at the control location on the Snake River are presented in Tables A-10.1 and A-10.2 of Appendix A. All results were below detection limits, except for potassium-40, a naturally-occurring radio-nuclide, and cesium-137. The detectable cesium-137 levels for the fish taken from the Columbia River were within the range observed during the preoperational and previous operational periods.

5. 7 ~Mi 1 All the results of iodine-131 analyses of mi'lk samples collected during 1990 were less than detection limits. The routine iodine-131 in milk results are listed in Tables A-l.l.l and A-11.2 of Appendix A. A graph of the 1990 iodine in milk results is presented in Figure 5-21. The gamma spectrometry results for the same milk samples are listed in Tables A-12.1 and A-12.2.

All results for the indicator and control locations were less than the detection limits.

5.8 r n P The gamma isotopic analysis results for all root, fruit and leafy vegetables were below detection limits. The results of all produce samples, including the apples collected from Station 91 and the cherries collected from Station 61, are listed in Tables A-13.1 through A-15.2 of Appendix A.

5-7

TABLE 5-1 BAD T N T T V A Y HEDIA/ANALYSIS (a)

P T A()() (d)

HEAN (RANGE) HEAN (RANGE) HEAN (RANGE)

Air: pCi/m Gross Beta <0.02 (<0.003 0. 130) 0.03 (0.00 - 0.74) 0.01 (0.02 - 0.04)

I-131(') <0.05 (<0.01 - 0.11) 0.01 (-0.04 0.82) 0.00 (-0.07 - 0.02)

Gajnna Cs-134 <0.01 (<0.001 - 0.040) 0.001 (-0.002 - 0.015) 0.0000 (-0.0004 - 0.0003)

Cs-137 <0.01 (<0.001 - 0.040) 0.002 (-0.001 - 0.036) 0.0001 (-0.0004 - 0.0003)

Ru-103 Not Reported 0.001 ( 0.000 - 0.019) 0.0000 (-0.0006 - 0.0004)

River/Drinking Mater: pCi/1 Gross Beta <3.0 (<1.0 - <6.0) 2.1 (-0.2 - 9 ~ 1) 1.7 (0.6 2.9)

Gannna Cs-134 <3.8 (<1.0 - <12.0) 0.5 (-3.6 - 5.2) 0.2 (-3.1 - 3.8)

Cs-137 <4.1 (<1.0 - <13.0) 1.2 (-4.0 - 5.1) 1.3 (-5.7 - 5.7)

Co-58 <5.1 (<1.0 - <25.0) 0.0 (-3.3 - 2.9) -0.2 (-2.4 - 2 ')

Co-60 Fe-59

<4.7

<13.3

(<1.0 <13.0)

(<2.0 <93.0) 1.1 0.7

(-4.9 (6.4

- 7.1)

- 6.6) 1.0

-1.0

(-4 ' - 5 ')

(-5.5 - 3.9)

Zn-65 <8.3 (<2.0 - <27.0) 2~3 (-16.0 3.9) -1.5 (-10.5 - 8.2)

H-3 <481.7 (220 <820) 177.0 (-52.0 596.0) 106.9 (-51.0 - 250)

Sr-90 <2.0 0.4 (0.3 - 0.7) Not analyzed Groundwater: pCi/1 Ganvna Cs-134 <4.0 ( <1.0 <12.0) 0.6 (-F 1 - 5.4) -0. (-2.2 - 2.9)

- 4 ')

1 Cs-137 <3.8 (0.8 <8.0) 1.1 (-3.1 1.0 (0.0 2-0)

Co-58 <4.7 (<1.0 - <12.0) -0.1 (-2.7 - 1.9) -0.5 (-2.8 - 1.1)

Co-60 <4.1 (0. 1 <9.0) 1.3 (-1.7 - 8.4) 0.7 (-2.4 - 2,4)

Fe-59 <11.6 (<2.0 - <33.0) 0.7 (-4.5 - 5 ') 0.1 (-4.1 - 2.7)

Zn-65 <8.6 (<2 ' - 17.0) -2.3 (-46 ' - 4.4) -1.9 (-7.3 - 15.0)

H-3 <467.8 (<10.0 2600.0) 80.7 (-516.0 - 470 ') 20.3 (-100.0- 220.0)

Sr-90 <0.4 (<0. 1 0.7) Not analyzed Not analyzed (a)All stations, all years.

(b)Indicator stations only for the years 1984 to 1989. Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.

(c)The data used for these averages does not include the "less than" values reported in 1984.

(d)Indicator stations only.

(e)Charcoal cartridge results.

5-8

5-l (Cont.)

~

TABLE RA N N T V )4 Y e

HEDIA/ANALYSIS T I A (b)(c) (d)

HEAN (RANGE) HEAN (RANGE) HEAN (RANGE)

Discharge Water: pCi/1 Gross Beta <2.8 (<1.9 4.0) 18.2 (0.6 - 48 ') 15.8 (6.1 35.0)

Gawna Cs-134 <3.7 (<1.0 - <8.0) 0.4 (-3.0 - 5.4) 0.8 (-0.9 4,4)

Cs-137 <4.7 (<1.0 - 16.0) 1.5 (-1.3 - 7.9) 2.2 (-1.6 - 5.6)

Co-58 <1.4 ( I.O - 13.0) 0.1 (-2.6 - 4.6) -0 ' (-2.3 - 1.3)

Co-60 <5.0 (<1.9 - <13.0) 2.7 (-8.7 28.2) 1.3 (-1.1 8.6)

Fe-59 <11.9 (<3.0 << <38.0) 0.7 (-3.0 - 6 ') 1.3 (-0.4 - 2.7)

Zn-65 <8.6 (<2.0 27.0) 3.4 (-4.9 - 86.7) -0.6 (-7.5 - 7.9)

H-3 <420.0 (<80.0 700.0) 1040.0 (60.0 4400.0) 1396.3 (55.0 3400.0)

Sr-90 <3.0 0.8 (0.5 - 1.1) Not analyzed Sediment: pCi/kg Gamma Cs-134 <112.5 (<50.0 - <150.0) 57.7 (7.0 - 172.0) 74,4 (67.9 - 80.8)

Cs-137 <287.0 (<50.0 - <560.0) 368.0 ( 153.0 - 1890.0) 190.0 (182.0 - 197.0)

- (27.1 - 129.0) (14.8 - 15.2)

~

Co-60 <254.6 ( 130.0 610.0) 54.8 15.0 Co-57 Not Reported 46.0 (34.0 54.0) 0.5 (-11.6 - 12.5) o Eu-152 Not Reported 143.0 ( 140.0 - 146.0) 85.8 (5 6 166.0)

~

Soil: pCi/kg Ganma Cs-134 <65.3 (<20.0 - <150.0) 29.7 (7.1 53.2) 17.5 (13.9 23.3)

Cs-137 364.3 (<20.0 - <1880.0) 313.0 (9.4 - 735.0) 287.0 (32.9 - 493.0)

Sr-90 Analysis Not Performed 357.5 (260.0 - 455,0) Analysis not performed Hi 1k: pCi/1 Gamna Cs-134 <3 ' (<0.9 - <14.0) 1.3 (-7.4 - 22.6) 0.4 (-3.3 - 3.0)

Cs-137 <3.8 (<1.0 - <12.0) 4.0 (-7.4 - 47.3) 1.6 (-2.5 - 6.8)

Ba-140 <72. 1 (<6.0 <2000.0) 0.5 (-44.3 - 55.0) -0.6 (-12.0 9.9)

La-140 <33.3 (<5 ' - <1000.0) -0.7 (-24.2 9.7) -0.3 (-4.5 4.1)

I-131 <0.5 (<0. 1 <1.0) 1.6 (-0.8 - 144.0) 0.0 (-0.3 - 0.4)

Sr-90 Not Reported 2.2 (-1.3 - 3.9) Not Reported (a)All stations, all years.

(b)Indicator stations only for the years 1984 to 1989. Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.

(c)The data used for these averages does not include the "less than" values reported in stations only. 1984.'d)Indicator 5-9

TABLE 5-1 (Cont.)

RA A V MENT R V gAAY (d)

HEOIA/ANALYSIS P AT N PR P RA NA HEAN (RANGE) HEAN (RANGE) HEAN (RANGE)

Fish: pCi/kg Gamma Cs-134 <61.2 (<6.0 <130.0) 1.5 (-20,4 - 14,4) 7.5 (0.0 - 24 ')

Cs-137 <88.8 (<10.0 - <130.0) 13.1 (-35.1 - 54.9) 15.3 (2.5 - 31.4)

Co-58 <87.7 (<9.0 <130.0) 1.5 (-16.8 - 25.8) 0.1 (-8.2 - 6.7)

Co-60 <80.6 (<9.0 <130.0) 0.5 (-18.4 - 19.1) -0.8 (-7. - 7.0) 1 Fe-59 <130.0 (<30.0 <260.0) -2.1 (-34.6 - 21.1) 7.2 (-10.2 - 30.0)

Hn-54 <88.3 (<8.0 <130.0) 2.0 (-10.3 - 30.9) 1.0 (-7.4 - 7.9)

Produce: pCi/kg Galena Cs-134 <49.1 (<10.0 - < 140.0) ~ 1.4 (-24.8 - 19.8) 1.3 (-12.0 - 17.0)

Cs-137 <69.8 (<10.0 - < 140.0) 4.3 ( -9.8 20.9) 5.6 ( -3.6 - 15.0)

I-131 <105.6 (<10.0 - <1000.0) 1.2 (-21.3 - 59.0) -4.0 (-12.0 - 3.5)

TLO: mR/day

()uarterly 0.24 (0. 11 0.32) 0.24 (0.16 - 0.35) 0.26 (0.23 0.32)

Annual 0.23 (0.20 - 0.31) 0;23 (0.18 - 0.32) 0.24 (0.22 0.29)

(a)A11 stations, all years.

(b)Indicator stations only for the years 1984 to 1989. Some of the data means and ranges are biased high due to the effects of the Chernobyl accident in 1986.

(c)The data used for these averages does not include the "less than" values reported in 1984 stations only. 'd)Indicator 5-10

TABLE 5-2 MPA N F T DYN NMINA l W R I T F DET T N WITH BRAN H T HNI A P T NT TELEDYNE BTP REQUIRED M IA NIT ANA Y LD D Air Gross Beta 0.003 0.01 Partic~lates: Gamma Spectrometry (pCi/m ) Cs-134 0.001 0.05 Cs-137 0.001 0.06 Air IotIine: I-131 0.01 0.07 (pCi/m~)

Water: Gross Beta 4 4 (pCi/1) Tritium 100-200 2000 I-131 1 1 Sr-90 1 Gamma Spectrometry Mn-54 10 15 Fe-59 20 30 Co-58 10 15 Co-60 10 15 Zn-65 20 30 Zr-95 20 30 Nb-95 10 15 Cs-134 10 15 Cs-137 10 18 Ba-140 20 60 La-140 10 15 Soil/ Gamma Spectrometry Sediment: Co-57 120 (pci/kg) Co-60 30 Cs-134 30 150 Cs-137 40 180 Sr-90 10 Fish: Gamma Spectrometry (pCi/kg) Mn-54 20 130 Fe-59 30 260 Co-58 20 130 Co-60 20 130 Zn-65 30 260 Cs-134 20 130 Cs-137 20 150 5-11

TABLE 5-2 (Cont.)

PAR N F T EDYNE N MINAL HER IMIT F D T TI N THBANHTEHIA P IT RE M T TELEDYNE BTP REQUIRED M A N T L D D Ml lk: I-131 0.5 (pc1/1) Gamma Spectrometry Cs-134 10 15 Cs-137 10 18 Ba-140 20 60 La-140 10 15 Sr-90 1 Garden Gamma Spectrometry Produce: Cs-134 20 60 (pC1/kg) Cs-137 20 80 I-131 30 60 5-12

T 5-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50.397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31, 1990 ANALYSIS ANO LONER LIHIT NUHBER OF HEOIUH OR PATH'NAY TOTAL NUHBER OF CONTROL LOCATION NONROUTINE SAHPLEO OF ANALYSES OETECTION HEAN (b)(a) NAHE HEAN (b)(a) HEAN (b)(a) REPORTEO (UNIT OF HEASUREHENT) PERFORHEO LLO) RANGE OISTANCE ANO DIRECTION RANGE MEASUREHENTS AIR PARTICULATES Gross Beta 624 0.003 0.013(563/572) 5 0.014(52/52) 0.012(51/52)

(pCI/$3) {0.002-0.059) {0.004-0.059) {0.002-0.03)

Gamma 48 (Ouarterly)

Be-7 0.01 0.055(44/44) 48 4.5 mI NE 0.068(4/4) 0.047(4/4)

(0.034-0.091) (0.039-0.080) (0.036-0.060)

K-40 0.01 0.006(6/44) 48 4.5 RI NE 0.008(1/4) 0.005(l/4)

(0.005-0.008)

Cs-137 0.01 LLD LLD Cs-134 0.001 LLO LLD AIR IODINE I-131 624 0.01 LLD LLD (pC1/$ 3)

(a) "(b) ls the ratio of posltlve results above the.ttO to the number of samples analyzed For the parameter of Interest.

TABLE 5-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31. 1990 ANALYSIS AND LONER LIHIT NUHBER OF TOTAL NUHBER OF CONTROL LOCATION NONROUTINE HEDIUH OR PATHWAY SAHPLEO OF ANALYSES DETECTION HEAN (b)(a) NAHE HEAN (b) HEAN (b)( ) REPORTED PERFORHEO LLO RANGE DISTANCE ANO DIRECTION RANGE HEASUREHENTS UNIT OF HEASUREHENT WATER Gross Beta 36 1.74(20/24) 28 7.4 Illi SSE 1.93(10/12) 1.78(10/12)

(River/Drinking) (0.64-2.90) (1.3-2.6) (0.65-4.40)

(pC1/liter)

Tritium 12 200 210(3/8) 28 7.4 m$ SSE 245(2/4) LLO (140-250) (240-250)

Gamma 36 Hn-54 10 LLO LLO 0 Fe-59 20 LLD LLD Co-58 10 LLD LLD Co-60 10 LLO LLO Zn-65 20 LLD LLO Zr-95 20 LLO LLD Nb-95 10 LLD ~ LLO Cs-134 10 LLD LLO Cs-137 10 LLD LLD Ba-140 20 LLD LLD 0 La-140 10 LLO LLD la) "~ ls the ratio of posit.lve results above the LLO to the number of les analyzed for the parameter of interest.

0 0 5-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31. 1990 ANALYSIS AHO LOWER LIMIT NUMBER OF TOTAL NUMBER OF CONTROL LOCATION NONROUTIHE MEOIUM OR PATHWAY SAMPLED OF ANALYSES OETECTIOH MEAN (b)(a) NAME MEAN (b)(a) MEAN (b)(a) REPORTED UNIT OF MEASUREMENT PERFORMEO LLO RANGE OISTAHCE ANO DIRECTION RANGE MEASUREMENTS WATER Gross Beta 12 12 15.8(12/12) 27 32 mi E 15.8(12/12) None (Discharge) (6.1-35) (6.1-35)

(pCi/liter)

TritiUm 4 200 1843(3/4) 27 3.2 mi E 1843(3/4) None (130-3400) (130-3400)

Gamma 12 Hn-54 10 LLD LLD Fe-59 20 LLD LLD Co-58 10 LLD LLD Co-60 10 8.60(1/12) 27 3.2 IAi E 8.60(1/12) LLD Zn-65 20 LLD- LLD Zr-95 20 LLD LLD Nb-95 10 LLD LLD Cs-134 10 LLD LLD Cs-137 10 LLD LLD Ba-140 20 LLD LLD La-140 10 LLD LLD ia) (o) is tne ratio of positive results above tne LLO to the number of samples analyzed for the parameter of interest.

TABLE 5-3 (ContInued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP.2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31, 1990 ANALYSIS AND LOWER LIHIT NUHBER OF HEDIUH OR PATHWAY TOTAL NUHBER OF CONTROL LOCATION NONROUTINE SAHPLED OF ANALYSES DETECTION HEAN (b)(a) NAHE HEAN (b)(a) HEAN (b)(a) REPORTED UNIT OF HEASUREHENT PERFORMED LLO RANGE DISTANCE AND DIRECTION RANGE HEASUREHENTS WATER Tritium 12 200 220(1/12) 52 O.l mI N 220(1/4) None (Ground)

(pC)/1)ter)

Gamma 12 Hn-54 10 LLD LLD Fe-59 20 LLD LLD Co-58 10 LLD LLD Co-60 10 LLQ LLD Zn-65 20 LLD LLD Zr-95 20 LLD LLD Nb-95 10 LLD LLD Cs-134 10 -. LLD LLD Cs-137 10 LLD LLQ Ba-140 20 LLD LLD La-140 10 LLD LLD

T 5-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31. 1990 ANALYSIS AND LOWER LIHIT NUHBER OF HEOIUH OR PATHNAY TOTAL NUHBER OF L CONTROL LOCATION NONROUTINE SAHPLEO OF ANALYSES DETECTION NEAN (b)(a) HAHE HEAN (b) ) HEAH (b)( REPORTED (UNIT OF HEASUREHEHT PERFORHEO (LLO) RANGE DISTANCE AND DIRECTION RAHGE HEASUREHENTS SOIL Gafina 5 (pC$ /kg dr'y)

K-40 17825(4/4) 23 3.0 Qi ESE 21400(1/1) 12100(1/1)

(12100-21400)

Cs-134 30 LLD LLD Cs-137 40 287(4/4) 493(l/1) 121(1/1)

(32.9-493)'51(2/4)

Ra-226 400 886(1/1) 1320(1/1)

(615-886)

Th-228 50 725(4/4) 837(1/1) 639(1/1)

(553-837)

(a) "(b)" is the ratio of positive results above the LLO to the number of samples analyzed for the parameter of interest.

TABLE S-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31, 1990 ANALYSIS ANO LOMER LIHIT NUHBER OF HEOIUH OR PATHHAY TOTAL NUHBER OF CONTROL LOCATIOH NONROUTIHE SAHPLEO OF AHALYSES OETECTION HEAR (b)(a) NAHE HEAN (b) HEAN (b)(a) REPORTEO UNIT OF HEASUREHENT) PERFORHEO LLO) RANGE OISTANCE ANO OIRECTION RANGE HEASUREHENTS SEDIHENT Gamma 4 (pC5/kg dry)

K-40 700 13900(2/2) 33 3.6 mi ENE 15350(2/2) 15350(2/2)

(13800-14000) (14600-16100) (14600-16100)

S Co-60 30 LLD LLD Cs-134 30 LLD LLD Cs-137 40 190(2/2) 34 3.5 IA[ ENE 190(2/2) 115(1/2)

(182-197) (182-197)

Ra-226 400 1665(2/2) 34 3.5 mi ENE 1665(2/2) 1400(2/2)

(1380-1950) (1380-1950) (1050-1750)

Th-228 50 1875(2/2) 34 3.5 m$ ENE 1875(2/2) 1355(2/2)

(1290-2460) (1290-2460) (789-1920) the LLO t

to the number of samples analyzed for the parameter of Interest.

0

0 0 T 5-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to OECEHBER 31, 1990 ANALYSIS ANO LOMER LIHIT NUHBER OF HEOIUH OR PATNMAY TOTAL NUHBER OF CONTROL LOCATION NONROUTINE SAHPLEO OF ANALYSES OETECTION HEAN (b)(a) NAHE HEAN (b)(a) HEAN (b)(a) REPORTEO (UNIT OF HEASUREHENT) PERFORHEO LLO RANGE OISTANCE ANO DIRECTION RANGE HEASUREHENTS HILK I-131 97 LLO LLD (pCI/liter)

Gamma 97 K-40 97 1270(79/79) 59 6.6 mi SE 1366(18/18) 1340(18/18)

(934-1640) (1200-1640) (1170-1470)

Cs-134 97 10 LLD LLD Cs-137 97 10 LLD LLO (a) (b)" Is the ratio oi pos(t1ve results above the LLO to the number of samples analyzed for the parameter of Interest.

TABLE 5-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to OECEHBER 31. 1990 ANALYSIS AND LONER LIHIT NUHBER OF HEOIUH OR PATHWAY TOTAL NUHBER OF L CONTROL LOCATION NONROUTINE SAHPLED OF ANALYSES DETECTION HEAN (b)(a) NAHE HEAN (b)( ) HEAN (b)(a) REPORTED (UNIT OF HEASUREHENT) PERFORHED (LLD) RANGE DISTANCE ANO DIRECTION RANGE HEASUREHENTS FISH Gamma 17 (pC$ /kg wet)

K-40 1000 3778(8/8) -38 26.5 Ali ESE 4133(9/9) 4133(9/9)

(2550-4960) (2850-7710) (2850-7710)

Hn-54 20 LLO LLO Fe-59 30 LLD LLD Co-58 20 LLD LLD Co-60 20 LLD LLD Zn-65 30 LLD LLD Cs-134 20 LLD LLO Cs-137 20 30.4(1/8) 30 3.3 mi E 30.4(1/8) LLD (a) "(bl" is the ratio of positive results above the LLD to the number of samples analyzed for the parameter of interest.

~ 0 0 ~ 0 00 0

0 T 5-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31. 1990 ANALYSIS AND LOWER LIHIT NUHBER OF HEOIUH OR PATHWAY TOTAL NUMBER OF L CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION HEAN (b)(a) NAHE HEAN (b) MEAN (b)( REPORTED UNIT OF HEASUREHENT) PERFORHEO LLO) RANGE DISTANCE AND DIRECTION RANGE HEASUREHENTS ROOTS Gamma 8 (pCi/kg wet)

I-131 50 LLD LLD Cs.134 50 LLD LLD Cs-137 50 LLD LLD FRUITS Gamma 10 (pCI/kg wet)

I-131 50 LLD LLD Cs-134 50 LLD LLD Cs-137 50 LLD LLD VEGETABLES Gamma 12 (pCi/kg wet)

I-131 50 LLD LLD Cs-134 50 LLD LLD Cs-137 50 LLD LLD (a) lol Is toe ratio Of Oosltlve results above tne ttO to tne number of samples analyzed for the parameter of interest.

TAHLE 5-3 (Continued)

WASHINGTON PUBLIC POWER SUPPLY SYSTEH WNP-2 DOCKET NO. 50-397 HANFORD WASHINGTON JANUARY 1 to DECEHBER 31. 1990 ANALYSIS ANO I.O'WER LIHIT NUMBER OF HEOIUH OR PATHWAY TOTAL NUHBER OF CONTROL LOCATION NONROUTINE SAHPLED OF ANALYSES DETECTION HEAN (b)(a>> NAHE HEAN (b)( ) HEAN (b)(a) REPORTED (UNIT OF HEASUREHENT) PERFORMED (LLO) RANGE DISTANCE ANO DIRECTION RANGE HEASUREHENTS DIRECT RADIATION TLD 224 0 '6(223/223) 46 4.7 mi NE 0.31(4/4) 0.24(4/4)

Quarterly TLD's (0.23-0.32) (0.30-0.32) (0.23-0.24)

(mR/day)

DIRECT RADIATION TLD 57 0.24(56/56) 46 4.7 mi NE 0.29(1/1) 0.22(1/1)

Annual TLD's (0.22-0.29)

(mR/day)

(a) (b)" is the ratio of positive results above the LLO to the number of samples analyzed for the parameter of interest.

0 0 ~

~

~ 0

TABLE 5-4 T LY D DAT H A Y F H AN P AT Results in mR/day 1984 '989

$ TATJgN P RATI NA P N P RAT NA STANDARD STANDARD STANDARD HEAN ERR R M AN ERR R MEAN E R 1 0.24 0.02 0.25 0.01 0.25 0.01 2 0.23 0.02 0.24 0.01 0.25 0.01 3 0.22 0.01 0.23 0.01 0.25 0.01 4 0.22 0.02 0.22 0.01 0.23 0.01 5 0.23 0.01 0.23 0.01 0.24 0.01 6 0.22 0.01 0.23 0.01 0.24 0.01 7 0.23 0.01 0.24 0.01 0,25 0.01 8 0.26 0.01 0.26 0.01 0.27 0.01 9 0.22 0.01 0.22 0.01 0.24 0.01 10 0.23 0.01 0.23 0.01 0.25 0.01 ll 0.24 0.01 0.24 0.01 0.25 0.00 12 0.25 0.01 0.26 0.01 0.27 0.00 13 0.24 0.01 0.24 0.01 0.25 0.01 14 0.24 0.02 0.24 0.01 0 25 0.01 15 0.25 0.01, 0.26 0.01 0.27 0.01 16 0.24 0.01 0.25 0.01 0.26 0.01 17 0.25 0.01 0.25 0.01 0.26 0.01 18 0.24 0.01 0.25 0.01 0.26 0.01 19 0.24 0.01 0.25 0.01 0.26 0.01 20 0.24 0. 01'.01 0.24 0.01 0.25 0.01 21 0.23 0.22 0.01 0.24 0.01 22 0.24 0.01 0.24 0 01 F 0.25 0.01 23 0.24 0.01 0.24 0.01 0.25 0.01 24 0.24 0.01 0.24 0.01 0.26 0.01 25 0.25 0.01 0.26 0.01 0.27 0 01 F

40 0.22 0.01 0.23 0.01 0.25 0.01 41 0.26 0.02 0.26 0.01 0.27 0.01 42 0.25 0.01 0.25 0.01 0.26 0.01 43 0.25 0.01 0.25 0.01 0,27 0.00 44 0.23 0.01 0.24 0.01 0.25 0.01 45 0.23 0.01 0.24 0.01 0.25 0.00 46 0.28 0.02 0.29 0.02 0.31 0.01 47 0.22 0.02 0.22 0.01 0.24 0.01 49 0.24 0.00 0.24 0.01 0.25 0.01 50 0.22 0.00 0.24 0.01 0.26 0.01 51 0.23 0.01 0.24 0.01 0.25 0.01 53 0.27 0.00 0.27 0.01 0.28 0.02 54 0.26 0.00 0.25 0.01 0.27 0.01 55 0.23 0.00 0.24 0.01 0.25 0.01 56 ,0. 24 0.00 0.24 0.01 0.25 0.01 5-23

TABLE 5-4 (Cont.)

A T D T MMA Y F TH P A N AND PE A NA P D Results in mR/day 1984 1989

//ATE T NA P AT N RT NA STANDARD STANDARD STANDARD MEAN RR R 61 (a) 0-28 0.02 0.27 0.01 71(1S) 0.24 0.02 0.27 0.02 0.28 0.02 72(2S) 0.25 0.01 0.26 0.01 0.28 0.01 73(3S) 0.23 0.01 0.23 0.01 0.25 0.01 74(4S) 0.26 0.01 0.26 0.01 0.28 0.01 75(5S) 0.22 0.02 0.24 0.01 0.26 0.01 76(6S) 0.24 0 01 F 0.24 0.01 0.26 0.01 77(7S) 0.25 0.01 0.25 0.01 0.25 0.01 78(8S) 0.25 0.01 0.24 0.01 0.25 0.01 79(9S) 0.25 0.01 0,25 0.01 0.25 0.01 80(10S) 0.24 0.01 0.24 0.01 0.25 0.01 81(11S) 0.24 0.02 0.24 0.01 0.25 0.00 82(12S) 0.25 0.02 0.25 0.01 0.26 0.01 83(13S) 0.25 0.01 0.25 0.01 0.26 0.01 84(14S) 0.24 0.01 0.24 0.01 0.26 0.01 85(15S) 0.26 0.01 0.26 0.02 0.27 0.01 86(16S) 0.25 0.01 0.27 0.02 0.29 0.02 All 0.24 0.00 0.25 0.00 0.26 0.02 (a) Station 61 was added in 1989.

5-24

TABLE 5-5 D T MMA Y ND P RAT NA P I D Results in mR/day 1984 1989

$ TATJgN PR P RATI NA R T STANDARD STANDARD STANDARD

( )

MEAN R M A E ~DV A~T@2+

1 0.23 0.04 0.23 0.02 0.24 0.02 2 0.22 0.04 0.22 0.02 0.23 0.02 3 0.21 0.04 0.21 0.01 0,22 0.01 4 0.22 0.06 0.20 0.01 0.22 0.02 5 0.22 0.04 0.21 0.01 0.22 0.02 6 0.21 0.04 0.21 0.02 0.22 0.02 7 0.22 0.02 0.01 0.23 0.01 8 0.25 0.04 0.25 (b) 0.02 0.26 0.02 9 0.20 0.02 0.20 0.01 0.22 0.02 10 0.22 0.04 0.22 0.01 0.23 0.03 ll 0.22 0.04 0.22 0.02 0.23 0.02 12 0.24 0.04 0.24 0.02 0.25 0.02 13 0.22 0.04 0.22 0.01 0.24 0.02 14 0.22 0.04 0.22 0.02 0.23 0.01 15 0.23 0.06 0.24 0.02 0.25 0.02 16 0.23 0.04 0.23(b 0.02 0.24 0.02 17 0.23 0.02 0.23 0 '2 0.24 0.01 18 0.25 0.02 0.23 0.02 0.24 0.02 19 0.22 0.04 0.23 0.01 0.24 0 '2 20 0.23 0.04 0.23 0.02 0.24 0.03 21 0.23 0.02 0.21 0.01 0.22 0.02 22 0.22 0.02 0.22 0.02 0.23 0,01 23 0.24 0.02 0.22 0.01 0.23 0.01 24 0.22 0.02 0.23 0.02 0.24 0.01 25 0.24 0.02 0.24 0.02 0.25 0.01 40 0 21(c) 0.02 0.22 0.02 0.23 0.02 41 0 26(c) 0.04 0.24 0.02 0.25 0.02 42 0.24(c) 0.02 0.23 0.02 0.24 0.02 43 0.24(c) 0.02 0.24 0.02 0.25 0,02 44 0.24 0.02 0.22 0.01 0.23 0.01 45 0.24 0.01 0.22 0.02 0.23 0.01 46 0.29 0.01 0.28 0.02 0.29 0.02 47 0.22(c) 0.03 0.21 0.02 0.22 0.01 49 (d) 0.22 0.01 0.23 0.03 50 (d) 0.23 0.02 0.23 0.02 5,1 (d) 0.22 0.02 0.23 0.02 53 (d) 0.25 0.02 0.26 0.03 (a) This preoperational mean i s for 1982 1983 data only.

(b) 1985 TLD missing (c) There was only one annual exchange during the preoperational period.

(d) Stations 49-56 were first monitored during Fourth quarter 1983.

Station 61 was added in 1989.

5-25

TABLE 5-5 (Cont.)

A T D T IJMMA T T A ND P RAT NA P I D Results in mR/day 1984 1989 tLA P A STANDARD STANDARD STANDARD MEAN RR R MEAN R M N DEVIATQQNN.'~

54 (d) 0.24 0.01 0.25 0.02 55 (d) 0.22 0.01 0.23 0.01 56 (d) 0.22 0.01 0.23 0.01 61 (d) 0.27(d) 0.00 0.25 0.02 71 0.24(c) 0.02 0.25 0.02 0.27 0.02 72 0.25(c) 0.02 0.25 0.02 0.26 0.02 73 0.23(c) 0.01 0.22 0.02 0.23 0.01 74 0.24(c) 0.01 0.24 0.02 0.25 0.02 75 0.24(c) 0.01 0.22 0.02 0.24 0.02 76 0.24(c) 0.02 0.23 0.01 0.24 0.02 77 0.25(c) 0.02 0.23 0.01 0.24 0.02 78 0.25(c) 0.04 0.23 0.02 0 '3 0.01 79 0.25(c) 0.02 0.23 0.01 0.23 0.01 80 0.23(c) 0.05 0.22 0.02 0.23 0.01 81 0.23(c) 0.02 0.22 0.02 0.23 0.02 82 0.25(c) 0.03 0.24 0.01 0.24 0.02 83 0.25(c) 0.02 0.24 0.02 0.24 0.02 84 0.23(c) 0.02 0.23 0.02 0.24 0 '2 85 0.26(c) 0.02 0.24 0.02 0.25 0.02 86 0.24 0.02 0.26 0.02 0.27 0.02 Al 1 0.23 0.02 0.24 0.00 0.24 0.03 (a) This preoperational mean is for 1982 1983 data only.

(b) 1985 TLD missing (c) There was only one annual exchange during the preoperational period.

(d) Stations 49-56 were first monitored during Fourth Quarter 1983.

Station 61 was added in 1989.

5-26

TABLE 5-6 1 HAN ART Y V ANN T AT Results in mR/day A T R Y T ANALTD

,'~ATTN STANDARD STANDARD HE N* R HA** DV I 1 0.25 0.01 0.24 0 '2 2 0.25 0.01 0.23 0.02 3 0.25 0.01 0.22 0.01 4 0.23 0.01 0.22 0.02 5 0.24 0.01 0.22 0.02 6 0.24 0.01 0.22 0.02 7 0.25 0.01 0.23 0.01 8 0.27 0.01 0 '6 0.02 9 0.24 0.01 0.22 0.02 10 0.25 0.01 0.23 0.03 11 0.25 0.00 0.23 0.02 12 0.27 0.00 0.25 0.02 13 0.25 0.01 0.24 0.02 14 0.25 0.01 0.23 0.01 15 0.27 0.01 0.25 0.02 16 0.26 0.01 0.24 0.02 17 0.26 0.01 0.24 ,0. 01 18 0.26 0.01 0.24 0.02 19 0.26 0.01 0.24 0.02 20 0.25 0.01 0.24 0.03 21 0.24 0.01 0.22 0.02 22 0.25 0.01 0.23 '0. 01 23 0.25 0.01 0.23 0.01 24 0.26 0.01 0.24 0.01 25 0.27 0.01 0.25 0.01 40 0.25 0.01 0,23 0.02 41 0.27 0.01 0.25 0.02 42 0.26 0.01 0.24 0.02 43 0.27 0.00 0.25 0.02 44 0.25 0.01 0.23 0.01 45 0.25 0.00 0.23 0.01 46 0.31 0.01 0.29 0.02 47 0.24 0.01 0.22 0.01 49 0.25 0.01 0.23 0.03 50 0.26 0.01 0 '3 0.02 51 0.25 0.01 0.23 0.02 53 0.28 0.02 0.26 0.03 54 0.27 0.01 0.25 0.02 55 0.25 0.01 0.23 0.01 56 0.25 0.01 0.23 0.01 61 0.27 0.01 0.25 0.02

  • Hean of the quarterly results
  • 'Hean of four readout areas on each TLD.

5-27

TABLE 5-6 (Cont.)

1 M AN ART R Y V R ANN T D DAT Results in mR/day A T Y NNA TD

~TATJQg STANDARD STANDARD M AN* R M N** D V ATI N 2 )

71 (1S) 0.28 0.02 0.27 0.02 72 (2S) 0.28, 0.01 0.26 0.02 73 (3S) 0.25 0.01 0.23 0.01 74 <4S) 0.28 0.01 0.25 0.02 75 (5S) 0.26 0.01 0.24 0.02 76 <6S) 0.26 0.01 0.24 0.02 77 (7S) 0.25 0.01 0.24 0.02 78 (8S) 0.25 0.01 0.23 0.01 79 (9S) 0.25 0.01 0.23 0.01 80 (10S) 0.25 0.01 0.23 0.01 81 (11S) 0,25 0.00 0.23 0.02 82 (12S) 0.26 0 01 F 0.24 0.02 83 (13S) 0,26 0.01 0.24 0.02 84 (14S) 0.26 0.01 0.24 0.02 85 (15S) 0.27 0.01 0.25 0.02 86 (16S) 0.29 0.02 0.27 0.02

  • Mean of the quarterly mean results.
    • Mean of four readout areas on each TLD.

5-28

mR/DAY mR/DAY 035 030 0 30 025 025 0 '20 020 0 15 0.15 0.10 0.10 005 0.05 O. 00 Pio&p 108l 80 )500 Pf5-Op 108 ~ .80 1000 SAMPLE PERIOD SAMPLE PERIOD C3ST 1 QBST )8 C3ST TO ESST,OA (CONTROL) CIST 10 EZI ST,)1 ~ St.21 EK3 ST,OA (CONTROL) mR/DAY

0. 35
0. 30 0.25 0,20 0 15 0,10 005 000 Pro -Op 138 ~ 83 1000 SAMPLE PERIOD CDST tl EBST 12 C3ST 13 BREST 0* )CONTROL)

FIGURE 5-1 AVERAGE QUARTERLY TLD RESULTS FOR NEAR-PLANT LOCATIONS AND THE CONTROL lOCATION (STATION 9A) FOR THE PREOPERATIONAL PERIOD, 1984-l989, ANO 1990

~ o

~ o

mR/DAY mR/DAY 035 035 030 0 30 025 025 020 020 015 0.15 0.10 0.10 005 005 000 0.00 1081.83 1030 Prp Op 108 ~ -83 1000 SAMPLE PERIOD SAMPLE PERIOD C33T5 %3310 C33T55 MsTSA (corrTRolI MsT,12 KBsT ~ 8 E33T,54 K9sT.OA IcoRTRol.)

mR/DAY 0.35 0 30 0.25 020 0 15 0.10 005 0.00 Pra~ 108 ~ -83 1300 SAMPLE PERIOD CDsT ro EBST il C33T 81 I ST 08 Icorr TRow FIGURE 5-2 AVERAGE QUARTERLY TLD RESULTS FOR REMOTE LOCATIONS AND THE CONTROL LOCATION (STATION 9A) fOR THE PREOPFRATIONAL PERIOD, 1984-1989, AND 1990

~ o

~ o

~ '

mR/DAY mR/DAY 0 33 023 023 020 020 0,13 013 0 10 0.10 003 003 000 P( ~ -Op 108 ~ -80 1000 Pi ~ .Op 138 ~ 80 1000 SAMPLE PERIOD SAMPLE PERIOD CDST.T KIST,T8 COST.TO ERST OA ICONT4OL) CDST.10 EBST 11 CDST-21 EBST. OA 1COtlT4OL) mR/DAY 0-30 023 020 0 16 0.10 0.03 0.00 Pce&p 108A.80 1330 SAMPLE PERIOD EST ll H331 12 CDST13 ERNEST QA (CO014OLI FIGURE 5-3 ANNUAL TLD RESULTS FOR HEAR-PLANT LOCATIONS AHD THE CONTROL LOCATION (STATION 9A) FOR THE PREOPERATIONAL PERIOD, 1984-1989, AND 1990

mR/DAY mR/DAY 0 35 025 025 020 020 0 15 o)a 0,10 0 10 ooa 0,05 000 Pia&p 188 ~ 80 1000 pr ~ Op 1oei.eo )000 SAMPLE PERIOD SAMPLE PERIOD Cats).5 EBST.S C33)aa Q233T 0A )CONTROL) CDsT 12 QBsT ~8 C38).54 msT. OA IcoNTRoL) mR/DAY 035 030 o2a 020 0-15 0 '10 005 000 Pse-Op 108 ~ 80 1000 SAMPLE PERIOD (EST ~0 Pds) ~ 1 C33T 81 QBST oA <coNTRoL)

FIGURE 5-4 ANNUAL TLD RESULTS FOR REMOTE LOCATIONS AND THE CONTROL (STATION 9A)

FOR THE PREOPERATIOHAL PERIOD, 1984-1989, AHD 1990

~.

~ e 0

I I I

l

/

0.27 mR/DAY

/:

0.24 mR/DAY

/

PRE-OP

~@Cy 1984-89

~SS 1990 FIGURE 5-5 MEAN 1990 QUARTERLY TLD RESULTS FOR LOCATIONS IN EACH METEOROLOGICAL SECTOR COMPARED TO THE MEAN PREOPERATIONAL AND PREVIOUS OPERATIONAL RESULTS

~ o

~ i

~,

I ~ ~

~ ~

rr r rr rr r rr rr r rr rr rr rr rr rr

~ ~

rr r rr rr rr rr rr rr rr rr rr rr rr rr rr rr r rrr rr rrr rr rr rr rr rr rr rr rr rr r rr r r rr rr rr rr rr rr

~ ~ rr r rr rr rr rr r r rr r rr rr rr rr r rr rr r r r rr

~ ~

r rr rr rr rr rr rr rr rr rr rr rr rr

~ ~ I

~ ~ ~ ~

~ ~

I ~ a

~ I

~ ~ ~

~

~.

~ o

1.0 0.8 0.6 M OA B

I 0

A Y

0.2 0.1 0.5 2.5 10 2$ 40 50 60 75 90 975995 CUMULATIVEPAOBABIUTY Quarterly 1990 1.0 0.8 0.8 OA I

0 A

Y 0.1 10 25 40 50 60 75 90 974 995 CUMULATIVEPROBABILITY Quarterly 1984-1989 FIGURE 5-7 LOG PROBABILITY PLOTS OF THE 1990 AND 1984-1989 QUARTERLY TLD RESULTS 5-35

0.8 O.e M 0.4 II I

0 A

v 0.1 0.5 28 10 25 40 50 60 75 90 978 995 CUMULATIVEPAOBABtuTY Annual 1990 OAI O.B M 0.4 A

I 0

h Y

0.1 05 2.5 10 25 40 50 60 75 90 978995 CUMUIATIYBPROBABtUTY Annual 1984-1989 FIGURE 5-8 LOG PROBABILITY PLOTS OF THE 1990 AND 1984-1989 ANNUAL TLD RESULTS 5-36

~ o

~ o

1.0 0.6 o.e M

0.1 R

I 0

A Y

0.1 0.5 2.5 10 2S 40 50 60 7S 90 978 995 CUMULATIVEPROBABNJTV Stations 71-76 (Sl-S6) 1.0 OAl o.e M OA 8

I 0

A Y

0.1 0.5 2.5 10 25 40 50 60 75 90 97.5 99.5 CUMULATIVEPROBABIUTY Station 9A FIGURE 5-9 LOG PROBABILITY PLOTS OF THE QUARTERLY TLD DATA FOR NEAR-PLANT LOCATIONS (STATION 71-76) AND THE CONTROL LOCATION (STATION 9A)

FOR THE PERIOD 1982-1990 5-37

PICOCURIF/CUBIC METER P REOP E RAT I ONAL MEAN 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 2 4 6 8 10 12 14 16 18 20 22 24 28 28 30 32 34 36 38 40 42 44 48 48 50 52 WEEK J. + 2SIGMA I - 2SIGMA I MEAN RESULT FIGURE 5-10 MEAN HEEKLY 1990 GROSS BETA IN AIR RESULTS

~ o

~ o

PICOCUAIE/CUBIC ME TEA

0. 70 0.60 Etfeof of Cnornobyl Aooldont 0.50 0.40
0. 30 0.20
0. 10 0.00 1984 1985 1986 YEAR PICQCUAIE/CUBIC METER
0. 70 0.60 0.60 0.40
0. 30 0.20
0. 10 0.00 1987 1988 1989 1990 YEAR FIGURE 5-11 MEAN HEEKLY GROSS BETA IN AIR RESULTS FROM 1984 TO 1990 5-39

PICCCURIE/CUBIC METER 0.04 HEAR PLANT 0.0$

PREOPERATIONAL MEAN O.OI I

2 1

1

~

~

1

~

~

10 Il It1$ I ~ 14 I ~ 'llI ~10tl111$t4141 ~t1tltt$ 0Slll 11 ll $ 4 $ 1 1 ~ ~ I 41 1 ~ ~ 1 4 ~ ~ I 4$

1 ~ $ 0 $ 4 40 ~ 2 1 ~ 1 ~ 4 ~ 40 WEEK 41.1 W ST.S I N)O ~ T,4 1 W ST.OA (CON T104)

PICCCURIE/CUBIC METER NANSORO AREA 0.04 0.0$

PREOPERATIONAL MEAN 0.01 I

t$4 4

~

1

~

~

10 II ltIlI ~ I ~ I ~ 11 I~ I ~202l121114 11 1 ~ Sl $ $ Sl 11 $ 4 ~ I 1$ ~ 4 41 ~ 4 4l 4$

14 1 ~ t0 $ 0 $ 2 $ 4 1 ~ 1 ~ 10 41 ~ I ~ 1 ~ 4 10 41 WEEK

41. ~ + ST.T MST.RS WOT.SA ICCNTAOI)

PICOCURIE/CUBIC METER

0. 04 REMOTE 0.01 0.0$

PRECPERATICNAL MEAN 0,01 0.01 I 1

~

4

~

1

~

~

IO

~ I 11 11 I~

I~ I~

11 14 I~ ll 11 14 10 11 1 ~ 1~

tl14 ~ 0ll$ $ $1 141 ~11$ 11 ~ 0 1

$ 2 ~ ~

11 11 1$ ~4 ~1 44 ll ~1 1~ 4~ 1~ 40 SR WEEK IT ~ ~ST ~ 'BOST,40 W ST 4A ICCN1104)

FIGURE 5-12 WEEKLY GROSS BETA IN AIR RESULTS FOR NEAR-PLANT AND REMOTE SAMPLING LOCATIONS VERSUS THE RESULTS FOR THE CONTROL LOCATION (STATION 9A) 5-40

P I COCUR I ES/L I T E R 10 State Annual Average Concentration Limit' g

OV

':?

X Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH miNTAKE CQ~'00 AREA C3'RICHLAND

  • NOTE: The maximum average annual concentration of stron'tium-90 for compliance to the 4 mrem/year dose limitation for drin~ ~w r is 8 pCi/liter.

FIGURE 5-l3 1990 GROSS BETA IN RIVER/DRINKING HATER RESULTS

~ o

~ s

P I COCUR I ES/L I T E R 10 State Annual Average Concentration Limit" 1984 1985 1986 1987 1988 1989 1990 MONTH miNTAKE (ST 26) EQ300 AREA (ST 28) IRiCHLAND (ST 29)

  • Hell water used, instead of river water, during water treatment plant maintenance outages.
    • Assuming strontion-90, the maximum average annual concentration for compliance to state dose limitations is 8 pCi/liter.

FIGURE 5-14 GROSS BETA IN RIVER/DRINKING HATER FROM 1984 TO 1990

P I COCUR I E S/L I T E R 100 95 90 85 80 DOH Interim Investigation Level 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5

0 1986 1987 1988 1989 1990 MONTH IDISCHARGE (ST. 27)

FIGURE 5-15 GROSS BETA IN DISCHARGE HATER RESULTS FROM 1986 to 1990

P I COCURIES/LI TER 100 9Q 80 DOH Interim Investigation Level 70 60 State Annual Average Concentration 50 Limit'Q 30 20 10 Jan Feb Mar Apr May Jun Jul - Aug Sep Oct Nov Dec MONTH

  • NOTE: For compliance to the 4 mrem/year state dose limitation, the annual average concentration of gross beta in grin~1 ~w e is 50 pCilllter.

FIGURE 5-16 1990 GROSS SETA IN DISCHARGE NTER RESULTS

P I COCUR I E S/L I T E R 350 325 300 275 250 225 Lower Limit of Detection 200 175 150 125 100 75 50 25 0

-25

-'50

-75 F I RST SECOND THIRD FOURTH QUARTER mINTAKE CQ 300 AREA ERB RICHLAND FIGURE 5-1?

1990 TRITIUM IH RIVER/DRINKING HATER RESULTS

~ e e

P I COCUR I ES/L I T E R 5000 4000 3000 2000 DOH Inter lm Invest tgat ton Level 1000 Lower Llml t I Detection 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 I 1986 I 1987 I 1988 I 1989 I 1990 I QUARTER/YEAR FIGURE 5-18 TRITIUH IN OISCHARGE HATER RESULTS FROH 1986 TO 1990

~ o

~ o

P I COCUR I ES/L I T E R 4000 3750 3500 3250 3000 2750 2500 2250 2000 1750 1500 1250 DOH Interim I nves t i gati on Leve I 1000 750 500 250 FIRST SECOND THIRD FOURTH QUARTER

  • NOTE: These i

results ii\i than 20,000

\.ii are low when pCi/liter.

i i iil iiiit considering that for compliance to the 4 mrem/per year state FIGURE 5-19 1990 TRITIUM IN DISCHARGE HATER RESULTS

~ o o

P I COCUR I E/K I LOG R AM 2000 1800 1600 1400 1200 1000 800 NOTE: 40 pCI/kg Is the Lower Llmlt oI Detection.

600 400 200 May Oct Apr Oct Apr Jun Jun Oct Apr Oct Apr Oct Apr Oct Apr Oct I s4 I ss I 86 I 87 I ss I so I oo I SAMPLE PERIOD IST 33 (Control) IST 34

  • Anomalous result obtained in 1985; see reference 12.

FIGURE 5-20 CESIUH-137 IN SEDIHENT RESULTS FROH 1984 TO 1990

~ o

~ o

P I COCUR I E/L I T E R Lower Limit of Detection 1/9 2/6 3/8 4/3 4/17 5/1 5/15 8/12 8/28 7/17 7/31 8/14 8/28 9/10 9/25 10/9 11/8 12/4 SAMPLE PERIOD

~ST 9B K9ST 38 EST 40 ERST 59 EST 62 C3ST 63 RBST 96 (Control)

FIGURE 5-21 1990 IODINE-131 IN MILK RESULTS

~ o 6.0 A TY A RAN E AND A TY NTR The REMP is designed to meet the quality assurance and quality control cri-teria of Regulatory Guide 4.15. To accomplish this, the REMP requires that its analytical contractors meet these criteria also. In-depth audits are performed of the REMP records and activities and the records and activities of its support organizations at least annually by the Supply System Corporate Licensing and Assurance group.

Quality assurance and technical audits of the analytical contractor, Teledyne Isotopes, are also conducted annually to verify their compliance to regulatory and contractual requirements. The adequacy of their quality assurance program is also assessed during the audits.

Intercomparison programs, which involve the comparison of Supply System analytical results for samples containing known concentrations of various radionuclides with the known values and with the results reported by other monitoring programs, are also a major component of the quality assurance activities of the REMP. The program participates in the Environmental Protection Agency (EPA) and Environmental Measurements Laboratory <EML) intercomparison programs. It also participates in local and regional intercomparison studies. The following sections summarize the quality assurance and quality control aspects of the TLD and analytical components of the REMP.

6.1 uali n ro F r he 1 m Envir nm n 1 TLD Pr The Quality Control Program for the environmental TLD preparation, process-ing and evaluation is described in Figures 6-1 and 6-2. QA dosimeters, which are anriealed just prior to being given a known exposure to 100 mR of cesium-137 gamma radiation and processed among the field dosimeters, serve as indicators that the readout, calibration and evaluation of the field dosimeters were properly performed. The number of QA dosimeters used during each processing is generally 101. of the number of field dosimeters. Since 1987 the same QA dosimeters have been used repeatedly throughout the year in order to track their sensitivity and to provide consistency from run to run.

If the mean QA dosimeter results are greater than g 5/ <or 5 mR) of the given exposure, an investigation into the source of the discrepancy is initiated. Evaluation of the 1990 QA dosimeter results indicated only small biases for the four quarters.

Control dosimeters <trip controls) are used for each set of field dosimeters to monitor the contribution of the exposure received by the field TLDs while in transit. The radiation background in the storage area is also monitored by a separate set of conti ol dosimeters (building controls).

control results are significantly gi.eater than tiie building control results, If the ti'ip the diFFei'eiice between the two is subtiacted From the Field dosimeters.

Audit dosimeters, which are exposed to known levels of radiation below the 100 mR given to the QA dosimeters, were processed with the field dosimeters during each run to verify the accuracy of the environmental TLD evalua-tions. The results of these audit dosimeters processed during 1990 are presented in Table 6-1. The close agreement between the given audit exposures and the reported results provided another indication that the dosimeter evaluations were performed accurately.

During each environmental TLD processing, individual calibration factors are determined for each TLD by exposing the TLDs to 100 mR from an encapsulated cesium-137 source. The calibration exposure is determined from the exposure duration and the assessed source strength at 55 centimeters. As a quality control check for each calibration exposure, an NIST-traceable ionization chamber is also used to determine the calibration exposure.

tion chamber measurement does not agree with the calculated exposure to If the ioniza- .

within + 5% of the calculated value, an investigation is performed into the discrepancy and the TLD calibration is repeated, if necessary.

An additional aspect of the Quality Control Program for the TLDs is par-ticipation in intercomparison studies. The Supply System participated in the last International Intercomparison of Environmental, Dosimeters, which was held in 1986 and in a local TLD intercomparison involving other were reported in previous annual reports. "

environmental monitoring programs in the regiop. The Supply System results

' In each comparison, the Supply System environmental TLD performed well. The TLD appears to be quite sensitive to fluctuations in environmental radiation, as eyidpnced by its over-response to lower energy gamma emitters, such as Ra-226.

6.2 1 i n r 1 F r he An 1 i 1 Pr r m

~ s Quality control for the analytical program involves two components: the quality control activities performed by the Supply System and the quality control program of the analytical contractor, Teledyne Isotopes. Both of these components are described in the following sections.

6.2.1 Supply System Quality Control Activities During 1990, several environmental samples were submitted to Teledyne Isotopes for intercomparison with other analytical laboratories. One set of intercomparison samples consisted of ground water, surface water, and water distilled from vegetation collected on the Department of Energy Hanford Site for the 1990 Hanford/Columbia River Sampling Intercomparison. The samples were split among the States of Washington and Oregon, US DOE, the Hanford Education Action League (HEAL), and the Supply System. The results of this intercomparison that are available by the publication of this report are presented in Table 6-2. In general, the Supply System results compared well with the results of the other participants.

6-2

The Supply System has participated in the U.S. Department of Energy Environ-mental Measurements Laboratory (EML) Quality Assessment Program since 1987.

The Supply System results for the samples sent out in March and September of 1990 are listed on Table 6-3. Once again, Supply System results agreed well with the EML expected results. The consistent low bias observed in the air particulate filter results is due to the diffelences in size between the filter used by EML (7 cm) and the filters routinely analyzed at Teledyne (4.7 cm).

In addition to the intercomparison samples, duplicate milk and discharge water samples were submitted to Teledyne Isotopes during the year to check the consistency of the analyses. The results of these duplicate samples taken at the same times and in the same locations as the routine samples are presented in Table 6-4. Most of the gamma isotopic results and the iodine-131 results for milk were below detection limits, so comparison is somewhat difficult. Comparison of the potassium-40 results, however, gives an indication of the consistency of the milk data. In the water samples, the gross beta results are easily compared. Considering the uncertainty associated with the results below detection levels, the milk and water duplicate results compare well.

6.2.2 Teledyne Isotopes Quality Control Program The goal of the quality control program at Teledyne Isotopes is to produce analytical. results which are accurate, precise and supported by adequate documentation. The program is based on the requirements of 10CFR50, Appendix B, Regulatory Guide 4.15 and the program, as described in Quality Assurance Manual INL-0032-395 and Quality Control Manual INL-0032-365.

All measuring equipment is calibrated for efficiency yearly using standard reference material traceable to the National Institute of Standards and Technology (NIST), formerly the National Bureau of Standards (NBS). For beta counting, check sources are prepared and counted every week day except holidays. Control charts are maintained with three-sigma limits specified.

Backgrounds are usually measured at least once per week.

The efficiency of the gamma spectrometers is calibrated yearly with a NIST traceable standard reference material selected to cover the energy range of the nuclides to be monitored and to include all of the geometries measured.

Backgrounds are determined every other week and check sources are counted weekly. The energy resolution and efficiency are plotted at two energy levels (125.1 and 1274.4 Kev) on charts and held within three-sigma control limits.

Efficiency calibration factors of the tritium gas counters are determined monthly by counting a NIST standard. This data is plotted on control charts with three-sigma limits. A background measurement is performed daily.'

The flow-chart of sample control from the time of receipt to reporting of results is presented in Figure 6-3. Several of the quality control check-points are listed below and the corresponding numbers are shown on the flow chart, indicating the hold-points at which results are checked.

~.

1. Check of Sample Receipt Form for completeness and conformance with the program of the customer by supervisor or qualified designate.
2. Preparation of all composites required by customer and designation of analyses by supervisor or qualified designate.
3. Monthly inspection of notebooks of technicians for completeness and any errors in computing yields, etc. by supervisor or quali-fied designate.
4. Review of all worksheets by the quality assurance manager or a qualified designate.
5. Editing of discs to remove all unapproved data before entry into computer.

Inspection of all final reports by quality assurance manager and technical vice president or qualified designates before being signed and mailed to the customer.

Control five-digit of sample identity is maintained by the assignment of a unique number which is maintained throughout the sample's history from sample receipt, log-in number assignment and designation of analysis to reporting the final analytical result. Besides ensuring sample account-

~ o ability, Teledyne procedures also ensure the maintenance of sample integrity by controlling sample storage and taking steps to prevent contamination of samples.

Results and associated parameters, such as decay, background, efficiency, etc. are reviewed internally for reasonableness before being entered into the data system. Any results which are suspect, i.e., which are higher or lower than results in the past, are returned to the laboratory for recount.

If a longer count, decay check, recount on another system or recalculation does not give acceptable results based on experience, a new aliquot is analyzed. The complete information about the sample is contained on the worksheets accompanying the sample results.

No deviations from written procedures occurred during 1990. A summary of the quality control blank and spiked sample results of analyses follows.

Summaries or the results of internal blanks and spike samples are presented in Tables 6-5 and 6-6. A summary of the EPA cross-check samples is presented in Table B-1 of Appendix B. Any results above the + three-sigma normalized deviation from the known is explained, giving the reason for the deviation and the corrective action to be taken.

6-4

I in -1 1 r ri One blank charcoal cartridge was analyzed with each set of cartridges, for a total of fifty-one blanks. The average result was 3.8+12.7E-01 pCi per cartridge. This was calculated from the results of quality control samples without considering detection limits.

One blank filter was measured with each set of filters. Fifty-two blanks were counted. The average activity in total pCi was 9.3+2.9E-01, which indicated a relatively stable background for the filter, including the background of the gross beta proportional counters.

A blank milk was analyzed with each group of samples assayed. The results show that there was no contamination in the laboratory or counting area.

The measurements of the blank samples (Table 6-5)(a) indicated that there was no bias on the low background counters. The average activity for fourteen samples was 7.5+17.0E-02 pCi/liter. This was calculated from quality control samples without considering detection limits. A total of fifty-six in-house blank milk samples were processed throughout 1990, with the highest detection level being 6.0E-01 pCi/liter.

Sr- 0 Milk H er Bimonthly blank and spike milk and weekly water samples were analyzed for strontium-90. The highest detection level of the blank water samples was less than 1.0 pCi/liters Fifty-one spiked water samples were analyzed with an average level of 4.0+0.4E+01 pCi/liter, compared with a spike level of 4.1+0.7E+01 pCi/liter. A total of 26 milk samples were spiked to a level of 4.1g0.7E+01 pCi/liter. The average activity determined for the spikes was 3 9+0 4E+01 pCi/liter, which was within the limits specified by the EPA Intercomparison Studies Program. A total of 24 blank milk samples were analyzed with an average activity of 1.3+0'.4E+00 pCi/liter of strontium-90.

r B -H er Fifty-two blanks were prepared from distilled water. The highest detection level measured was 1.0 pCi/liter. No contamination was indicated and the background level was low and stable. During 1990 fifty-two gross beta spike samples were analyzed. The average result was 1.8+0.1E+01 pCi/liter with a spike level of 2.1+0.5E+01 pCi/liter. This was well within the guidelines of the EPA Intercomparison Studies Program.

6-5

Fifty-two blank samples were analyzed by gas counting. The highest result was less than 200 pCi/liter. A total of 52 spiked tritium samples were analyzed. The average result was 2.6+0.1E+03 pCi/liter, compared with a spike level of 2.7+0.3E+03 pCi/liter.

A blank water sample was analyzed on a weekly basis in the gamma spectroscopy laboratory. All nuclides were less than the normal level of detection, indicating no contamination. Spike samples were measured weekly using the Eu-154 peak at 1274.5 KeV. The average activity of 52 measure-ments was 1.41+0.02E+05 pCi/liter, compared with a spike level of 1.40+0.2E+05 pCi/liter.

6-6

TABLE 6-1 1 ENVIR NMENTAI DIT D MET LT TLD GIVEN REPORTED BIAS TIBTI N P R mR First Quarter 30.0 30.5 1.7 30.4 1.3 29.8 -0.6 Second Quarter 30.0 29.9 -0.3 30.7 2.3 29.0 -3.3 Third Quarter 50.0 47.8 -4.4 47.3 -5.4 42.0 -6.0 Fourth Quarter 25.0 25.0 0.0 25.5 2.0 25.4 2.0 Annual 90.0 91. 7 1.9 90.1 0.3 89 ' -0.2 6-7

~ s

~ o

TABLE 6-2 ANF RD/ V A E PA I N Nell 699-43-3 (pci/1)

Gr.B 9.8+3.3E+01 3.9+0 2E+01

~ 6.9+0.3E+01 H-3 20.9'.lE+04 22.0p0.1E+04 23.0+1.0E+04 Sr-89 NR 0 '+2.0E+00 NA Sr-90 7.0+3.0E-01 2.2+4.5E-01 3.2+5.9E-01 Co-60 6.5+1.7E+00 6.0+2.0E+00 9.0+2.9E+00 Cr-51 NR 0.7+1.4E+00 HR Mn-54 HR 0.el.OE+00 -1.2+2.4E+00 Zn-65 NR 0.0+2.0E+00 0.0+5.9E+00 Ru-103 NR -1.0+2.0E+00 3.3+4.8E+00 Ru-106 NR 0.3g1.0E+01 1.2+2.4E+Ol Sb-125 NR 2.0+3.0E+00 NR Cs-137 NR 1.0gl.OE+00 2.2+2.7E+00 Ra-226 3.9+5.3E+00 6.0+B.OE-02 -5.8/5.5E+01 N-8T (pci/1)

Gr.B 9.2+0.1E+03 10.4'.1E+03 12.el.OE+03 H-3 37.8+0.4E+03 38.9+0.'4E+03 45.0+1.0E+03 Sr-89 NR -1.3+0.8E+03 NA Sr-90 56.0+1.0E+02 52.8'.8E+02 58.0+1.0E+02 Co-60 14.lg1.7E+00 13.023.0E+00 14.0+4.0E+00 Cr-51 HR -1.0+1.7f+01 NR Hn-54 NR -1.0+1.0E+00 3.8+3.0E+00 Zn-65 NR 1.0+3.0E+00 -l.lg0,7E+01 Ru-103 NR 0.0+2.0E+00 3.2g5.3E+00 Ru-106 NR 0.6+1.2E+01 0.1+2.7E+Ol Sb-125 21 . 8+4. 7 E+00 24.0+6.0E+00 HR Cs-137 HR 1.el.OE+00 1.2+2.9E+00 Ra-226 NR NA -3.3+5.7E+01( >>

Nile 42-2 Seep (pci/1)

Gr.B 7.1+0.7E+00 6.0+1.0E+00 8.0+1.2E+00 H-3 1.7+1.2E+02 33.2+8.BE+01 2.9gl.2E+02 Sr-89 NR -0.3+2.4E+03 NA Sr-90 1.5+0.4E+00 2.2+4.7E-01 -2.3+8.7E-01 Co-60 HR 1.0+1.0E+00 0.2+2.6E+00 Cr-51 NR 0.2+1.2E+Ol NR HR - Not reported HA - Not analyzed From gamma isotopic analysis 6-8

TABLE 6-2 (Contd)

NF D V P lN NT A N Mile 42-2 Seep (Contd)

(pci/1)

Mn-54 NR -0.9+1.0E+00 -0.5+2.6E+00 En-65 NR -1.0p2.0E+00 -0.3+6.2E+00 Ru-103 NR 0.0+1.0E+00 3.5+4.BE+00 Ru-106 NR -4.0+9,0E+00 1.0+2.4E+01 Sb-125 NR -F 0+3.0E+00 NR Cs-137 0.3zl.5E+00 0.0zl.OE+00 4 8+2 7E+00 Ra-226 1.7'.3E+00 6.0g9.0E-02 0~5.9E+01(1)

Hanford Ferry Landing (pci/1)

Gr.B 1 . 6pO. SE+00 1 . Og1 . OE+00 2.5+0.BE+00 H-3 NR 2.2'.9E+02 -0.7+3.4E+01 Sr-89 NR 9.0g2.0E-Ol NA Sr-90 5,0+3.0E-01 3.0+4.0E-01 3.9+0.9E+00 Co-60 NR 0.8g1.5E+00 1.1+2.1E+00 Cr-51 NR 0.2+1.5E+Ol NR Mn-54 2. 1+1. 2E+00 -0.1+1.3E+00 0.0+2.1E+00 Zn-65 NR 0.8g2.6E+00 -2.8+4.6E+00 Ru-103 NR -2.0z2.0E+00 3.1+3.9E+00 Ru-106 NR -0.8+1.3E+01 -O.1+1.9E+01 Sb-125 NR 2.024.0E+00 NR Cs-137 NR 0.6gl.4E+00 2.2+2.7E+00 Ra-226 , 3.9+3.0E+00 NA 4.5.4.7E.01( )

Port of Benton (pci/1)

Gr.B 2.420.5E+00 2.0+1.0E+00 2.3+0.BE+00 H-3 1.8g1.2E+02 5.7+0.9E+02 5.1+0.9E+02 Sr-89 NR 0.1+2.6E+00 NA Sr-90 8.0+4.0E-Ol O.1+5.0E-01 3.3%4.9E-01 Co-60 NR 1.0+1.0E+00 1.1+2.0E+00 Cr-51 NR 1.3+1.2E+01 NR Mn-54 NR 1.0+1.0E+00 0.4+1.8E+00 Zn-65 NR -1.0+2.0E+00 3.1+4.2E+00 Ru-103 NR -2.0+1.0E+00 1.1g3.5E+00 Ru-106 NR -4.0+9.0E+00 0.4+1.8E+01 Sb-125 NR 3.023.0E+00 NR Cs-137 NR -4.0+9.0E-01 0.0+1.9E+00 Ra-226 NR NA 0.7+4.1E~Ol ~

NR Not reported NA - Not analyzed From gamma isotopic analysis 6-9

TABLE 6-2 (Contd)

ANF RD/ MB A RIV AMP N NT R MPA N r n W h n n Mile 28.2 Seep (pci/1)

Gr.B 53.9+1.9E+00 29.0g2.0E+00 53.0+3.0E+00 H-3 128.9+0.7E+03 135.0+1 OE+03

~ 14.0+1.0E+04 Sr-89 NR 0.5+2.1E+00 NA Sr-90 NR 0.2+4.3E-Ol 4.0+7.2E-01 Co-60 4.6+1 6E+00

~ 4.022.0E+00 1.2+2.3E+00 Cr-51 NR 0.1+1.7E+01 NR Mn-54 NR 1.0+1.0E+00 2.0+2.1E+00 Zn-65 NR -1.0+3.0E+00 -4.7p5.0E+00 Ru-103 NR -3.0+2.0E+00 0.2+4.1E+00 Ru-106 NR O.ldll.3f+01 1.2+2.1E+01 Sb-125 NR -4.0+5.0E+00 NR Cs-137 NR 2.0+2.0E+00 3.7+2.5E+00 Ra-226 1.3+3.3E+00 7.0+9.0E-02 0.6+4.9E+01 Mile 28.2 Vegetation (pCi/gr dry)

Sr-89 NR -1 . Op 3. OE-01 NA Sr-90 5.0i3.0E-02 4.0+3.0E-02 NA Co-60 NR 3.0g3.0E-02 2.0+3.1E+01 Cr-51 NR -0.6+5.7E+00 NR Mn-54 NR 2.0+4.0E-02 -6.5+3.3E+Ol Zn-65 NR -0.1+1.2E-01 -7.7g9.6E+01 Ru-103 NR 1.0+3.0E-01 -0.4+1.9E+02 Ru-106 NR 2.0+4.0E-01 0.2z3.1E+02 Sb-125 NR -0.2+3.2E-01 NR Cs-137 1. Og0. 3E-01 7.6+5.3E-OZ 8.6+3.3E+01 Ra-226 1.0+1,0E-01 NA 0.7g6.1E+02 Mile 28.2 Vegetation (pCi/1)

H-3 23.5'.3E+03 22.7'.3E+03 22.0+1.0E+03 NR = Not reported NA - Not analyzed From gamma isotopic analysis 6-10

~ o

~%-"Ia-~ A ITYA TABLE H

6-3 P H AB E

T RY T

EHL)

Teledyne Percent Sample Reported Error EHL Ratio 9003 Particulate Filter Be-7 4.66E+01 10 S. 14E+01 0.91 0. 12 (total Bq)( ) Hn-54 9. 10E+01 9 9.60E+00 0.95 0. 10 Co-57 6.00E+00 10 6 SOE+00

~ 0.92 0.11 Co-60 8.30E+00 9 9.40E+00 0.88 0. 10 Cs-134 1.44E+01 9 1.82E+01 0.79 0.10 Cs-137 1.87E+01 10 2.04E+02 0.92 0.10 Ce-144 2.82E+Ol 9 3.12E+02 0.90 0.10 9003 Soil (Bq/kg) K-40 6.40E+02 9 6.08E+02 1.05 0.10 Cs-137 1.95E+04 10 1.75E+04 1.11 0. 11 Sr-90 7.40E+02 5 6.65E+02 1.11 0.06 9003 Vegetation (Bq/kg) K-40 3.25E+02 10 3.23E+02 1.01 0. 13 Cs-137 3.41E+01 9 2.85E+01 1.20 0.13 Sr-90 7.03E+01 5 7.02E+01 1.00 0.06 9003 Water (Bq/1) H-3 1.89E+03 1 1.96E+04 0.96 0.03 Hn-54 1.06E+02 10 1.03E+02 1.03 0.12 Co-57 2.00E+02 9 1.98E+02 1.01 0. 11 Co-60 1.89E+02 10 2.06E+02 0.92 0. 10 Sr-90 9.99E+01 3 1. 11E+02 0.90 0.'05 Cs-134 4.29E+02 10 4.62E+02 0.93 0. 11 Cs-137 2.03E+02 10 1.98E+02 1.03 0. 12 Ce-144 6.18E+02 10 4.03E+02 1.53 0.17 9009 Parti cul ate Fil ter( Hn-54 0.289E+02 10 0.333E+02 0.87 0.09 (total Bq) Co-57 0.880E+01 10 0. 114E+02 0.77 0.08 Co-60 0. 195E+02 10 0.254E+02 0.77 0.08 Cs-134 0.129E+02 10 0. 163E+02 0.79 0.08 Cs-137 0. 137E+02 10 0.157E+02 0.87 0.09 Ce-144 0.122E+02 9 0. 165E+02 0.74 0.08 9009 Soil (Bq/kg) K-40 0.533E+03 9 0.513E+03 1.04 0. 12 Sr-90 0. 100E+02 15 0.833E+01 1.20 0.28 Cs-137 0 '26E+03 10 0.196E+03 1.15 9009 Vegetation (Bq/kg) K-40 0 113 E+04

~ 10 0 '03E+04 1.10 0.13 Cs-137 0.205E+02 9 0. 182E+02 1 ~ 13 0. 13 9009 Water (Bq/1) H-3 0 '44E+04 8 0.390E+04 1.14 0. 14 Mn-54 0.299E+03 10 0.301E+03 0.99 0. 10 Co-57 0.127E+04 9 0. 130E+04 0.98 0. 10 Co-60 0.488E+03 9 0.491E+03 0.99 0.10 Sr-90 0.850E+01 4 0.933E+01 0.86 0.06 Cs-134 0.349E+03 10 0.355E+03 0.98 0.98 Cs-137 0 414 E+03

~ 9 0.390E+03 1.06 F 11 Ce-144 0.870E+03 10 0.923E+03 0.94 0. 10 (1) The EML filter is larger than the standard filter geometry used at difference is believed to account for the bias observed in the results. Teledyne. This (2) Bq = becquerel; the EHL results are now reported in becquere1 s instead of pi co cur i es.

One picocurie equals 0.037 becquerel.

(s) The Cs-.137 result was inadvertently omitted from results submitted to EHL.

6-11

~ o

~ o

TABLE 6-4 LT D AT N W Results in pCi/liter COLLECTION EDIA D T RADI N L D

~TEQN 'K ~TT ~N Mi 1 k 900306 Cs-134

  • 1.2g 2.0E-01
  • 6.3+ 2.3E-01 Cs-137 0.8+ 2.1E-OO 1.5+ 2.3E+00
  • 0.7+ 9.5E-02
  • 2.7+ 9.5E-02 Ba-140
  • 1.7z 6.1E+00 " -0.9+ 6.2E+00 La-140 * -7.2g25.4E-01 * -7.0+25.4E-01 K-40 12.6g 1.3E+02 13.0+ 1.3E+02 900925 Cs-134
  • 8.6+24.7E-01
  • 1.5g24.3E-01 Cs-137 6.8< 2.BE+00
  • 0.3g 2.3E+00 I-131") * -1.9+ 1.1E-Ol * -0.6+ 1.1E-01 Ba-140 La-140
  • -7.9+ 8.4E+00
  • 1.2g 3.6E+00

'l.l+ 8.9E+00

" -0.4+ 3.5E+00 K-40 12.0+ 1.2E+02 11.4+ 1.1E+02 5MLQH~ ~TATI N 2 Water 901107 to Gr-B 1.6+ 0.2E+01 1.9+ 0.2E+01 901205 Mn-54

  • 9.4+18.8E-01
  • 2.02 4.4E+00
  • 2.0+ 3.7E+00 Co-60 * -4.6z23.2E-01 * -1.3+17 'E-01 Co-58 * -2.0+20.0E-Ol
  • 5 '+17.1E-01 Zn-65 * -2.9+ 4.5E+00
  • 1.3+ 3.6E+00 Cs-134 * -6.lg22.1E-01
  • 1.8z 2.1E+00 * -1.2+ 1.8E+00 Ba-140 * -2.8+ 7.2E+00
  • 0.3z 7.3E-:00 La-140
  • 2.2+ 3.5E+00 " -3.4q 3.5E+00 K-40
  • 2.6+ 2.6E+01
  • 3.5+ 2.3E+Ol 900313 to H 3(b) 3.4g 0.1E+03 2.3+ 0.1E+03 900613 Denotes a result less than the detection limit.

(a) Resin Method (b) Station 27 sample was composited at Teledyne; Station 72 sample was com-posited at Supply System. The difference in results was caused by a slight discrepancy in the volume taken from one of the three samples used in the Supply System sample. Because that sample contained much more tritium (8,200 pCi/liter)than the other two samples (210 and 560 pCi/liter), the slight discrepancy had a significant effect on the com-posite result.

6-12

TABLE 6-5 MMARY F 1 A TY NT D TA: BLAN BLANKS AVERAGE N IDE N MBE BLAN NIT I-131 Mi 1 k 14 (a) 7.5z17.0E-02 pCi /1 56 (d) <6.0E-01 pci/1 Sr-90 Milk 24 (d) 1.3+0.4E+00 pCi/1 Sr-90 Hater 48 (d) <2.0E+00 pci/1 H-3 Hater 52 (d) <2.0E+02 pCi/1 (Gas Counting)

Gross Beta Hater 52 (d) <1.0E+00 pci/1 Gamma Water 52 pci /1 Gross Beta AP Filter 52 (c)(b) 9.3+2.9E-01 Total pCi I-131 Charcoal 51 (a) 3.8gl2.7E-01 Total pCi

'All nuclides less than minimum detection level.

(a) This average is calculated from the Supply System quality control samples without considering detection limits.

(b) The in-house weekly quality control blanks for AP filters and charcoals are calculated in total pCi.

(c) This average includes only the blank AP filters analyzed for the Supply System. A blank planchet (counter background) and a blank filter are counted with each set of filters analyzed (approximately 10 sets per week).

(d) The highest detection level was used as the average of these samples.

6-13

~ s TABLE 6-6 MA F 1 LI Y NT D TA' E SPIKED SAMPLES AVERAGE SPIKE LEVEL N D B i 1 Gross Beta Water 52 1.8+0.1E+01 2.1+0.5E+01 H-3 (Gas Counting) Hater 2.6+0.1E+03 2.7+0.3E+03 Sr-90 Hater 51 4.0+0 4E+01

~ 4.1+0.7E+01 Sr-90 Milk 26 3.9+0.4E+Ol 4.lg0.7E+Ol Eu-154 Hater 52 1.4+0.2E+05 1.4+0.2E+05 6-14

ANNEAL FIELD AND CONTROL TLDS LOAD TLDS INTO CASES; SEAL IN FOIL AND BAGS STORE TLDS IN LEAD CAVE Tfl ~ VO CXPOSVRC) I TRIP ~ XPORV RN) (TLO RACXOROVRO)

DISTRIBUTE FIELD TAKE TRIP STORE BUILDING TLDS TO MONITORING CONTROL TLDS CONTROL TLDS IN STATION S ON FIELD TLD LEAD CAVE DISTRIBUTION RETURN TRIP TLDS TO LEAD CAVE ANNEAL QA AND AFTER DISTRIBUTION SPIKE TLDS RETRIEVE TAKE TRIP CONTROL GIVE QA AND FIELD TLDS TLDS TO RETRIEVE SPIKE TLDS FIELD TLDS KNOWN RADIATION EXPOSURES STORE TLDS IN STORE TLDS IN LEAD CAVE LEAD CAVE STORE TLDS IN LEAD CAVE PROCESS TLDS FIGURE 6-1 SUPPLY SYSTEM ENVIRONMENTAL TLD PREPARATION USE CYCLE 6-15

TLD READOUT CALIBRATE AND TEST PREPARE PROCESSING RUN; R EAD FORV/ARD (MAIN)

TLD READER QA AND SPIKE TLDS AREAS REREAD FORWARD AREAS READ BACKUP AREAS REVIEW DATA FOR RESIDUALS TLD CALIBRATION EXPOSE ALL TLDS STORE IN LEAD CAVE READ FORWARD AREAS TO 100 mR LONGER THAN 12 HOURS OF ALL TLDS REPORT GENERATION SUBTRACT TRIP DOSE, CALCULATE INDIVIDUAL CALCULATE INDIVIDUALTLD IF APPLICABLE TLD EXPOSURES CALIBRATION FACTORS PRINT OUT RESULTS REVIEVf DATA VlRITE FINAL REPORT FIGURE 6-2 SUPPLY SYSTEM TLD EVALUATION

CONTRACTOR SAMPLE RECEIPT SAMPLE A ScQfPLE B FORM T. I. SAMPLE RECEI VIiNG FILE SAMPLE RECEIPT SRF FORif (SRF) 1,2 LAB 1 LAB 2 SAMPLES SAMPLES SRF SRF COMPUTER W.0. PAC K ET WORK WORK SHEET SHEET INTERIM REPORT OF OF AiVALYSIS ANALYSIS 3,4 CONTRACTOR ACCOUNi TING REPORT OF AifALYSIS CKVOWLEDGEA~"f QUALITY COiVTROL CHECK ADMINISTRATIOV FOR APPROVAL Counting FILE Roof.

WORK ENV I RONbfENTAL SHEETS ANALYSIS FILE DISTRIBUTION TO W. O. WORK SHEET CONTRACTOR

2. REPORT OF IF REQUESTED ANALYSIS FIGURE 6-3 Flow Chart For Teledyne Isotopes Samples 6-17

~,

~ s

~

7.0 I~Fag JQ U.S. Nuclear Regulatory Commission, "Programs For Monitoring Radioactivity in the Environs of Nuclear Power Plants," Regulatory Guide 4.1, Revision 1, April 1975.

2. U.S. Nuclear Regulatory Commission, "Environmental Technical Specifications For Nuclear Power Plants," Regulatory Guide 4.8, December 1975.

U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program," Assessment Branch Technical Position; Revision 1, November 1979.

4. U.S. Nuclear Regulatory Commission, "Quality Assurance For Radiological Environmental Monitoring Program (Normal Operations), Effluent Streams and the Environment," Regulatory Guide 4.15, Revision I, February 1979.

U.S. Nuclear Regulatory Commi ss ion, "Performance, Testing and Procedural Specifications For Thermoluminescence Dosimetry-Environmental Applications," Regulatory Guide 4.13, Revision 1, July 1977.

6. American National Standard: ANSI N545-1975, "Performance Testing and Procedural Specifications for Thermoluminescent Dosimetry (Environ-mental Applications)."
7. Code of Federal Regulations, Title 10 Part 20, r r r i n
8. Code of Federal Regulations, Title 10 Part 50, D m i Li in f Pr i n iliz i i i i
9. Washington Public Power Supply System Nuclear Plant No. 2, Operating License NSF-21, n fi 3/4.12.1, Table 3.13.1.
10. Attachment I to the Site Certification Agreement Between the State of Washington and the Washington Public Power Supply System, Hay 17, 1972 (with revision dated January 1978).

"Teledyne Isotopes TLD System For Personnel and Environmental Monitoring," Teledyne Isotopes, Westwood, New Jersey, February 2, 1981.

12. Washington Public Power Supply System, 1 nmn 1 ni rin r m nn 1 P , April 1986.
13. Washington n

Public Power Supply System, Q~l~iApril 1987.

nvi m n 1 14, Washington Public Power Supply System, i 1 i 1 nvir n n ni r r 1 1 , April 1988.

15. Washington Public Power Supply System, i 1 i 1 nv r nm n 1 n , April 1989.
16. Washington State f

Department of Health, 1 1 i n f B r H h R r in P i Drinkin W r m , Chapter 246-290, Washington Administrative Code, April 1991.

17. Robertson, li D. E., and J. J. Fix, in f Hnfr ri i n W m v r m , BNWL-2305, August 1977.

~I 7-2

APPENDIX A: 1990 ROUTINE RESULTS o

~,

~ o 0

0'e,

TABLE A-l. 1 Results in mR/day

~ COLLECTION UNCERTAINTY LOCATION PERIOD RESULT 20 891228 to 900329 0.24 0.02 900329 to 900628 0.24 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.00 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.24 0.02 900927 to 901227 0.26 0.01 891228 to 900329 0. 24 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.24 0.02 900927 to 901227 0.25 0.01 891228 to 900329 0.24 0.01 900329 to 900628 0.23 0.00 900628 to 900927 0.23 0.01 900927 to 901227 (a) 891228 to 900329 0.24 0.01 900329 to 900628 0.23 0.01 900628 to 900927 0.24 0.01 900927 to 901227 0.24 0.01 891228 to 900329 0.24 0.01 900329 to 900628 0.23 0.01 900628 to 900927 0.23 0.01 900927 to 901227 0.24 0.01 891228 to 900329 0.24 0.03 900329 to 900628 0.25 0.01 900628 to 900927 0.24 0.01 900927 to 901227 0.25 0.01 891228 to 900329 0.27 0.00 900329 to 900628 0.27 0.01 900628 to 900927 0.27 0.01 900927 to 901227 0.28 0.01 (a) TLD lost in the field.

A-1

TABLE A-l.l (Cont.)

Results in mR/day '

COLLECTION UNCERTAINTY LOCATION PERIOO RESULT 20 9A 891228 to 900329 0.24 0.01 900329 to 900628 0.23 0.01 900628 to 900927 0.23 0.01 900927 to 901227 0.24 0.01 10 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.04 900628 to 900927 0.24 0.01 900927 to 901227 0.25 0.00 891228 to 900329 0.25 0.02 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.25 0.01 12 891228 to 900329 0.27 0.01 900329 to 900628 13 900628 to 900927 900927 to 901227 891228 to 900329 0.27 0.27 0.27

0. 24 0.01 0,01 0.00 ~ o 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.25 0.01 14 891228 to 900329 0.25 0.01 900329 to 900628 0.24 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.01 15 891228 to 900329 0.27 0.02 900329 to 900628 0.27 0.01 900628 to 900927 0.26 0.01 900927 to 901227 0.27 0.01 16 891228 to 900329 0.25 0.02 900329 to 900628 0.27 0.00 900628 to 900927 0.25 0.01 900927 to 901227 0.27 0.01 A-2

TABLE A-1.1 (Cont.)

Results in mR/day COLLECTION UNCERTAINTY LOCATION PERIOD RESULT 2'7 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.26 0.01 900927 to 901227 0.27 0.01 18 891228 to 900329 0.26 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.27 0.01 19 891228 to 900329 0.25 0.01 900329 to 900628 0.26 0.01 900628 to 900927 0.26 0.02 900927 to 901227 0.26 0.01 20 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.01 21 891228 to 900329 0. 24 0.01 900329 to 900628 0.23 0.00 900628 to 900927 0.23 0.01 900927 to 901227 0.24 0.01 22 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.01 23 891228 to 900329 0.25 0.01 900329 to 900628 0.24 0.01 900628 to 900927 0.24 0.01 900927 to 901227 0.25 0.01 24 891228 to 900329 0.26 0.01 900329 to 900628 0.26 0.01 900628 to 900927 0.25 0.02 900927 to 901227 0.26 0.01.

TASLE A-l.l (Cont.)

Results in mR/day COLLECTION UNCERTAINTY LOCATION PERIOD RESULT 20 25 891228 to 900329 0.27 0.03 900329 to 900628 0.26 0.02 900628 to 900927 0.27 0.01 900927 to 901227 0.27 0.01 40 891228 to 900329 0.24 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.02 900927 to 901227 0.25 0.01 41 891228 to 900329 0.27 0.00 900329 to 900628 0.26 0.00 900628 to 900927 0.27 0.01 900927 to 901227 0.27 0.00 42 891228 to 900329 0.26 0.01 900329 to 900628 900628 to 900927 900927 to 901227 0.25 0.25 0.27 0.00 0.01 0.01 ~I 43 891228 to 900329 0.27 0.01 900329 to 900628 0.27 0.01 900628 to 900927 0.27 0.01 900927 to 901227 0.27 0.01 44 891228 to 900329 0.25 0.02 900329 to 900628 0.25 0.00 900628 to 900927 0.24 0.01 900927 to 901227 0.25 0.01 45 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.25 0.01 46 891228 to 900329 0.31 0.02 900329 to 900628 0.30 0.01 900628 to 900927 0.30 0.01 900927 to 901227 0.32 0.01

TABLE A-1.1 (Cont.)

Results in mR/day COLLECTION UNCERTAINTY LOCATION PERIOD RESULT 20 47 891228 to 900329 0.24 0.01 900329 to 900628 0.23 0.01 900628 to 900927 0.23 0.01 900927 to 901227 0.24 0.01 49 891228 to 900329 0.26 0.01 900329 to 900628 0.24 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.01 50 891228 to 900329 0.25 0.01 900329 to 900628 0.26 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.01 51 891228 to 900329 0.25 0.01 900329 to 900628 0.24 0.01'.01 900628 to 900927 0.24 900927 to 901227 0.25 0.01 53 891228 to 900329 0.27 0.02 900329 to 900628 0.28 0.01 900628 to 900927 0.28 0.01 900927 to 901227 0.29 0.00 54 891228 to 900329 0.27 0.00 900329 to 900628 0.26 0.01 900628 to 900927 0. 26. '.01 900927 to 901227 0.27 0.01 55 891228 to 900329 0.25 0.02 900329 to 900628 0.24 0.04 900628 to 900927 0.24 0.01 900927 to 901227 0.25 0.01 56 891228 to 900329 0.26 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.23 0.01 900927 to 901227 0.26 0.01 A"5

TASLE A-l.l (Cont.)

LOCATION COLLECTION PERIOD Results in mR/day UNCERTAINTY

~ o RESULT 26 61 891228 to 900329 0.27 0.02 900329 to 900628 0.27 0.02 900628 to 900927 0.27 0.01 900927 to 901227 0.28 0.01 71 891228 to 900329 0.30 0.02 900329 to 900628 0.26 0.00 900628 to 900927 0.27 0.01 900927 to 901227 0.30 0.01 72 891228 to 900329 0.28 0.04 900329 to 900628 0.27 0.01 900628 to 900927 0.27 0.01 900927 to 901227 0.29 0.01 73 891228 to 900329 0.25 0.02 900329 to 900628 900628 to 900927 900927 to 901227 0.24 0.24 0.25 0.01 0.01 0.00 ~ e 74 891228 to 900329 0.27 0.02 900329 to 900628 0.27 0.01 900628 to 900927 0.27 0.01 900927 to 901227 0.29 0.01 75 891228 to 900329 0.27 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.27 0.01 76 891228 to 900329 0.26 0.00 900329 to 900628 0.26 0.01 900628 to 900927 0.25 0.00 900927 to 901227 0.26 0.01 77 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.01 A-6

TABLE A-l.l (Cont.)

Results in mR/day COLLECTION UNCERTAINTY LOCATION PERIOD RESULT 26 78 891228 to 900329 0. 24 0.01 900329 to 900628 0.24 0.01 900628 to 900927 0.25 0.02 900927 to 901227 0.26 0.01 79 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0. 0'2 900927 to 901227 0.26 0.01 80 891228 to 900329 0.24 0.01 900329 to 900628 0.25 0.00 900628 to 900927 0.24 0.01 900927 to 901227 0.25 0.01 81 891228 to 900329 0.25 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.25 0.01 82 891228 to 900329 0.26 0.01 900329 to 900628 0.26 0.01 900628 to 900927 0.25 0.01

, 900927 to 901227 0.27 0.01 83 891228 to 900329 0.27 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.26 0.01 900927 to 901227 0.27 0.00 84 891228 to 900329 0.26 0.01 900329 to 900628 0.25 0.01 900628 to 900927 0.25 0.01 900927 to 901227 0.26 0.01 85 891228 to 900329 0.26 0.01 900329 to 900628 0.25 0.02 900628 to 900927 0.27 0.02 900927 to 901227 0.28 0.01

TA8LE A-1.1 (Cont.)

LOCATION COLLECTION PERIOO Results in mR/day RESULT UNCERTAINTY 20

~ o 86 891228 to 900329 0.30 0.02 900329 to 900628 0.26 0.03 900628 to 900927 0.28 0.02 900927 to 901227 0.31 0.01

~ o A-8

TABLE A-1.2 Results in mR/day LLE TI N UN ERTAINTY LOCATION PERIOD RESULT 26 1 891228 to 901227 0.24 0.01 2 891228 to 901227 0.23 0.01 3 891228 to 901227 0.22 0.01 4 891228 to 901227 0.22 0.01 5 891228 to 901227 0.22 0.01 6 891228 to 901227 0.22 0.01 7 891228 to 901227 0.23 0.00 8 891228 to 901227 0.26 0.01 9A 891228 to 901227 0.22 0.01 10 891228 to 901227 0.23 0.01 11 891228 to 901227 0.23 0.01 12 891228 to 901227 0.25 0.01 13 891228 to 901227 0.24 0.01 14 891228 to 901227 0.23 0.01 15 891228 to 901227 0.25 0.01 16 891228 to 901227 0.24 0.01 17 891228 to 901227 0.24 0.01 18 891228 to 901227 0.24 0.00 19 891228 to 901227 0.24 0.01 20 891228 to 901227 0.24 0.01 21 891228 to 901227 0.22 0.01 22 891228 to 901227 0.23 0.00 23 891228 to 901227 0.23 0.00 24 891228 to 901227 0.24 0.00 25 891228 to 901227 0.25 0.01 40 891228 to 901227 0.23 0.01 41 891228 to 901227 0.25 0.01 42 891228 to 901227 0.24 0.01 43 891228 to 901227 0.25 0.01 A"9

TABLE A-1.2 (Cont.)

LLE TI Results in mR/day N ERTAINTY

~ o LOCATION PERIOD RESULT 2G 44 891228 to 901227 0.23 0.01 45 891228 to 901227'o 0.23 0.01 46 891228 901227 0.29 0.01 47 891228 to 901227 0.22 0.01 49 891228 to 901227 0.23 0.01 50 891228 to 901227 0.23 0.01 51 891228 to 901227 0.23 0.01 53 891228 to 901227 0.26 0.01 54 891228 to 901227 0.25 0.01 55 891228 to 901227 0.23 0.00 56 891228 to 901227 0.23 0.01 61 71 72 891228 891228 891228 to to to 901227 901227 901227 0.25 0.27 0.26 0.01 0.01 0.01

~ o 73 891228 to 901227 0.23 0.01 74 891228 to 901227 0.25 0.01 75 891228 to 901227 0.24 0.01 76 891228 to 901227 0.24 0.01 77 891228 to 901227 0.24 0.01 78 891228 to 901227 0.23 0.01 79 891228 to 901227 0.23 0.01 80 891228 to 901227 0.23 0.00 81 891228 to 901227 0.23 0.01 82 891228 to 901227 0.24 0.01 83 891228 to 901227 0.24 0.01 84 891228 to 901227 0.24 0.01 85 891228 to 901227 0.25 0.01 86 891228 to 901227 0.27 0.01 A-10

TABLE A-1.3

~ Results in mR/day NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE TLD (I) 0.26 0.23 0.32 223 223 TLD (C) 0. 24 0.23 0.24 TLD (I) 0.24 0.22 0.29 56 TLD (C) 0.22 0.22 0.22 (I) Indicator Stations (C) Control Station

TABLE A-2.1 Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102 1.9 E-02 3.0 E-03 900102 to 900108 6.2 E-03 1.8 E-03 900108 to 900115 1.8 E-02 2.0 E-03 900115 to 900122 3.7 E-02 3.0 E-03 900122 to 900129 4.4 E-03 1.6 E-03 900129 to 900205 5.9 E-03 1.8 E-03 900205 to 900212 (a) 2.3 E-03 1.7 E-03 900212 to 900220 1'. 9 E-02 2.0 E-03 900220 to 900226 1.8 E-02 3.0 E-03 900226 to 900305 2.0 E-02 2.0 E-03 900305 to 900312 5.6 E-03 1.7 E-03 900312 to 900319 1.0 E-02 2.0 E-03 900319 to 900326 2.0 E-02 2.0 E-03 900326 to 900402 1.9 E-02 2.0 E-03 900402 to 900409 1.8 E-02 2.0 E-03 900409 to 900416 1.4 E-02 2.0 E-03 900416 to 900423 6.9 E-03 1.8 E-03 900423 to 900430 6.2 E-03 1.8 E-03 900430 to 900507 (b) 1.2 E-02 2.0 E-03 900507 to 900514 (b) 5.7 E-03 2.1 E-03 900514 to 900521 (b) 1.4 E-02 2.0 E-03 900521 to 900529 6.9 E-03 1.5 E-03 900529 to 900604 (a) 2.6 E-03 1.8 E-03 900604 to 900611 1.4 E-02 2.0 E-03 900611 to 900618 7.1 E-03 1.7 E-03 900618 to 900625 1.1 E-02 2.0 E-03 900625 to 900702 8.3 E-03 1.9 E-03 900702 to 900709 6.0 E-03 1.8 E-03 900709 to 900716 1.8 E-02 2.0 E-03 900716 to 900723 1.2 E-02 2.0 E-03 900723 to 900730 1.3 E-02 2.0 E-03 900730 to 900806 1.8 E-02 2.0 E-03 900806 to 900813 2.2 E-02 2.0 E-03 900813 to 900820 1.0 E-02 2.0 E-03 900820 to 900827 1.0 E-02 2.0 E-03 900827 to 900904 1.2 E-02 2.0 E-03 900904 to 900910 2.3 E-02 3.0 E-03 900910 to 900917 1.7 E-02 2.0 E-03 900917 to 900924 1.7 E-02 2.'0 E-03 (a) Oeposition on filter was light. but there was no equipment malfunction or shortened sampling time.

(b) Power outage; shortened sampling time.

  • Denotes a result less than the detection limit.

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001 2.9 E-02 3.0 E-03 901001 to 901008 1.1 E-02 2.0 E-03 901008 to 901015 1.2 E-02 2.0 E-03 901015 to 901022 1.1 E-02 2.0 E-03 901022 to 901029 1.5 E-02 2.0 E-03 901029 to 901105 7.8 E-03 =

1.8 E-03 901105 to 901112 1.0 E-02 2.0 E-03 901112 to 901119 1.7 E-02 2.0 E-03 901119 to 901126 5.9 E-03 1.7 E-03 901126 to 901203 5.4 E-03 1.6 E-03 901203 to 901210 1.9 E-02 E-03 '.0 901210 to 901217 1.9 E-02 2.0 E-03 901217 to 901226 2.3 E-02 2.0 E-03 A"13

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102 1.6 E-02 3.0 E-03 900102 to 900108 5.7 E-03 1.8 E-03 900108 to 900115 2.0 E-02 2.0 E-03 900115 to 900122 2.9 E-02 3.0 E-03 900122 to 900129 4.5 E-03 1.6 E-03 900129 to 900205 4.6 E-03 1.7 E-03 900205 to 900212 3.3 E-03 1.7 E-03 900212 to 900220 1.7 E-02 2.0 E-03 900220 to 900226 1.2 E-02 2.0 E-03 900226 to 900305 2.4 E-02 3.0 E-03 900305 to 900312 4.7 E-03 1.6 E-03 900312 to 900319 9,4 E-03 1.9 E-03 900319 to 900326 2.3 E-02 3.0 E-03 900326 to 900402 2.0 E-02 2.0 E-03 900402 to 900409 2.1 E-02 2.0 E-03 900409 to 900416 1.3 E-02 2.0 E-03 900416 to 900423 8.9 E-03 1.9 E-03 900423 to 900430 5.7 E-03 1.8 E-03 900430 to 900507 1.3 E-02 2.0 E-03 900507 to 900514 5.9 E-03 1.8 E-03 900514 to 900521 2.1 E-02 3.0 E-03 900521 to 900529 8.6 E-03 1.6 E-03 900529 to 900604 3.5 E-03 1.9 E-03 900604 to 900611 1.3 E-02 2.0 E-03 900611 to 900618 7.2 E-03 1.7 E-03 900618 to 900625 1.3 E-02 2.0 E-03 900625 to 900702 9.4 E-03 2.0 E-03 900702 to 900709 5 4 E-03 1.8 E-03 900709 to 900716 1.7 E-02 2.0 E-03 900716 to 900723 1.1 E-02 2.0 E-03 900723 to 900730 (a) 1.1 E-02 6.0 E-03 900730 to 900806 1.6 E-02 2.0 E-03 900806 to 900813 1.9 E-02 2.0 E-03 900813 to 900820 7.1 E-03 1.9 E-03 900820 to 900827 7.5 E-03 1.9 E-03 900827 to 900904 1.1 E-02 2.0 E-03 900904 to 900910 2.0 E-02 3.0 E-03 900910 to 900917 1.3 E-02 2.0 E-03 900917 to 900924 2.1 E-02 h

2.0 E-03 (a) Sampler malfunction, so low sample volume; result not included in summary.

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001 2.5 E-02 3.0 E-03 .

901001 to 901008 1.0 E-02 2.0 E-03 901008 to 901015 1.2 E-02 2.0 E-03 901015 to 901022 1.1 E-02 2.0 E-03 901022 to 901029 1.6 E-02 2.0 E-03 901029 to 901105 8.0 E-03 1.8 E-03 901105 to 901112 1.0 E-02 2.0 E-03 901112 to 901119 1.6 E-02 2.0 E-03 901119 to 901126 7.9 E-03 1.8 E-03 901126 to 901203 3.9 E-03 1.5 E-03 901203 to 901210 1.1 E-02 2.0 E-03 901210 to 901217 1.2 E-02 2.0 E-03 901217 to 901226 2.5 E-02 2.0 E-03 A-15

TABLE A-2.1 (Cont.)

A PAR Results in pCi/cubic meter COLLECTION OVERALL LOCATION PE RIOO RESULT UNCERTAINTY 891227 to 900102 1.7 E-02 3.0 E-03 900102 to 900108 5.1 E-03 1.7 E-03 900108 to 900115 1.7 E-02 2.0 E-03 900115 to 900122 3.3 E-02 3.0 E-03 900122 to 900129 5.1 E-03 1.7 E-03 900129 to 900205 4,1 E-03 1,7 E-03 900205 to 900212 9.4 E-03 2.0 E-03 900212 to 900220 1.8 E-02 2.0 E-03 900220 to 900226 1.3 E-02 2,0 E-03 900226 to 900305 2.1 E-02 2,0 E-03 900305 to 900312 6.2 E-03 1.7 E-03 900312 to 900319 1.0 E-02 2.0 E-03 900319 to 900326 1.9 E-02 2.0 E-03 900326 to 900402 1,8 E-02 2.0 E-03 900402 to 900409 1.7 E-02 2.0 E-03 900409 to 900416 1.2 E-02 2.0 E-03 900416 to 900423 7.7 E-03 1.9 E-03 900423 to 900430 1,4 E-02 2,0 E-03 900430 to 900507 1.4 E-02 2.0 E-03 900507 to 900514 5.2 E-03 1.8 E-03 900514 to 900521 'o 1.9 E-02 3.0 E-03 900521 900529 7.7 E-03 1.6 E-03 900529 to 900604 3.7 E-03 2.2 E-03 900604 to 900611 1.4 E-02 2.0 E-03 900611 to 900618 5.4 E-03 1.6 E-03 900618 to 900625 1.0 E-02 2.0 E-03 900625 to 900702 9.2 E-03 2,0 E-03 900702 to 900709 5.1 E-03 1.8 E-03 900709 to 900716 1.6 E-02 2.0 E-03 900716 to 900723 1.2 E-02 2.0 E-03 900723 to 900730 1.4 E-02 2.0 E-03 900730 to 900806 1.6 E-02 2.0 E-03 900806 to 900813 2.0 E-02 2.0 E-03 900813 to 900820 8.7 E-03 2.0 E-03 900820 900827 to to 900827 l,l E-02 2.0 E-03 900904 1.2 E-02 2.0 E-03 900904 to 900910 2.0 E-02 3.0 E-03 900910 to 900917 1,7 E-02 2.0 E-03 900917 to 900924 2.5 E-02 3.0 E-03 A-16

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001 3.0 E-02 3.0 E-03 901001 to 901008 5.9 E-02 5.0 E-03 901008 to 901015 1.1 E-02 2.0 E-03 901015 to 901022 1.2 E-02 2.0 E-03 901022 to 901029 1.6 E-02 2.0 E-03 901029 to 901105 8.5 E-03 1.8 E-03 901105 to 901112 1.1 E-02 2.0 E-03 901112 to 901119 1.7 E-02 2.0 E-03 901119 to 901126 3.8 E-03 1.5 E-03 901126 to 901203 5.4 E-03 1.6 E-03 901203 to 901210 2.0 E-02 2.0 E-03 901210 to 901217 9.7 '-03 1.9 E-03 901217 to'01226 2.1 E-02 2.0 E-03 A-17

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102 1.6 E-02 3.0 E-03 900102 to 900108 6.6 E-03 1.8 E-03 900108 to 900115 1.7 E-02 2.0 E-03 900115 to 900122 3.5 E-02 3.0 E-03 900122 to 900129 (a) 1.6 E-03 1.6 E-03 900129 to 900205 4.0 E-03 1.7 E-03 900205 to 900212 4.4 E-03 1.8 E-03 900212 to 900220 1.9 E-02 2.0 E-03 900220 to 900226 1.4 E-02 2.0 E-03 900226 to 900305 2.4 E-02 3.0 E-03 900305 to 900312 4.2 E-03 1.6 E-03 900312 to 900319 8.3 E-03 1.9 E-03 900319 to 900326 1.6 .E-02 2.0 E-03 900326 to 90040Z 1.6 E-02 2.0 E-03 900402 to 900409 1.9 E-02 2.0 E-03 900409 to 900416 1.2 E-02 2.0 E-03 900416 to 900423 7.9 E-03 1.9 E-03 900423 to 900430 5.4 E-03 1.7 E-03 900430 to 900507 1.2 E-02 2.0 E-03 900507 to 900514 4.0 E-03 1.7 E-03 900514 to 900521 1.4 E-02 2.0 E-03 900521 to 900529 7.0 E-03 1.5 E-03 900529 to 900604 3.1 E-03 1.9 E-03 900604 to 900611 1.3 E-02 2.0 E-03 900611 to 900618 6.3 E-03 1.7 E-03 900618 to 900625 1.3 E-02 2.0 E-03 900625 to 900702 9.5 E-03 2.0 E-03 900702 to 900709 7.1 E-03 1.9 E-03 900709 to 900716 1.4 E-02 2.0 E-03 900716 to 900723 1.0 E-02 2.0 E-03 900723 to 900730 1.6 E-02 2.0 E-03 900730 to 900806 1.7 E-02 2.0 E-03 900806 to 900813 2.4 E-02 3.0 E-03 900813 to 900820 8.4 E-03 2.0 E-03 900820 to 900827 1.1 E-02 2.0 E-03 900827 to 900904 1.1 E-02 2.0 E-03 900904 to 900910 2.1 E-02 3.0 E-03 900910 to 900917 1.6 E-02 2.0 E-03 900917 to 900924 2.0 E-02 2.0 E-03 (a) Low sample volume; results not included in averages.

  • Denotes a result less than the detection limit.

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT -

UNCERTAINTY 900924 to 901001 2.6 E-02, 3.0 E-03 901001 to 901008 1.1 E-02 2.0 E-03 901008 to 901015 1.2 E-02 2.0 E-03 901015 to 901022 1.3 E-02 2.0 E-03 901022 to 901029 1.2 E-02 2.0 E-03 901029 to 901105 9.5 E-03 1.8 E-03 901105 to 901112 1.2 E-02 2.0 E-03 901112 to 901119 1.9 E-02 2.0 E-03 901119 to 901126 6.1 E-03 1.7 E-03 901126 to 901203 5.1 E-03 1.6 E-03 901203 to 901210 2.2 E-02 2.0 E-03 901210 to 901217 1.9 E-02 2.0 E-03 901217 to 901226 3.0 E-02 2.0 E-03 A"19

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102 1.4 E-02 3.0 E-03 900102 to 900108 (a) 5.9 E-03 1.9 E-03 900108 to 900115 (a) 1.4 E-02 2.0 E-03 900115 to 900122 3.1 E-02 3.0 E-03 900122 to 900129 3.0 E-03 1.6 E-03 900129 to 900205 3.4 E-03 1.7 E-03 900205 to 900212 2.5 E-03 1.7 E-03 900212 to 900220 1.9 E-02 2.0 E-03 900220 to 900226 1.6 E-02 3.0 E-03 900226 to 900305 2.4 E-02 3.0 E-03 900305 to 900312 5.3 E-03 1.7 E-03 900312 to 900319 1.0 E-02 2.0 E-03 900319 to 900326 1.4 E-02 2.0 E-03 900326 to 900402 1.9 E-02 2.0 E-03 900402 to 900409 1.9 E-02 2.0 E-03 900409 to 900416 1.0 E-02 2.0 E-03 900416 to 900423 7.3 E-03 1.9 E-03 900423 to 900430 4,3 f-03 1.7 E-03 900430 to 900507 1.2 E-02 2.0 E-03 900507 to 900514 3..9 E-03 1.7 E-03 900514 to 900521 9,4 E-03 2.2 E-03 900521 to 900529 7.5 E-03 1.6 E-03 900529 to 900604 3.3 E-03 1.9 E-03 900604 to 900611 9.8 E-03 1.8 E-03 900611 to 900618 6.5 E-03 1.7 E-03 900618 to 900625 1.1 E-02 2.0 E-03 900625 to 900702 7.2 E-03 1.9 E-03 900702 to 900709 6.3 E-03 1.8 E-03 900709 to 900716 1.3 E-02 2.0 E-03 900716 to 900723 (a) 1.3 E-02 3.0 E-03 900723 to 900730 1.2 E-02 2.0 E-03 900730 to 900806 1.5 E-02 2.0 E-03 900806 to 900813 1.9 E-02 2.0 E-03 900813 to 900820 8.6 E-03 2.0 E-03 900820 to 900827 9.5 E-03 2.0 E-03 900827 to 900904 (a) 1.7 E-02 3.0 E-03 900904 to 900910 2.1 E-02 3.0 E-03 900910 to 900917 (a) 1.7 E-02 3.0 E-03 900917 to 900924 2.0 E-02 2.0 E-03 (a) Power outage; shortened sampling time.

A-20

TABLE A-2.1 (Cont; )

Results in pCi/cubic meter COLLECTION OYERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001 2.8 E-02 3.0 E-03 901001 to 901008 1.3 E-02 2.0 E-03 901008 to 901015 1.2 E-02 2.0 E-03 901015 to 901022 1.5 E-02 2.0 E-03 901022 to 901029 1.7 E-02 2.0 E-03 901029 to 901105 1.3 E-02 2.0 E-03 901105 to 901112 1.2 E-02 2.0 E-03 901112 to 901119 1.8 E-02 2.0 E-03 901119 to 901126 5.6 E-03 1.6 E-03 901126 to 901203 7.3 E-03 1.7 E-03 901203 to 901210 2.0 E-02 2.0 E-03 901210 to 901217 (a) 2.2 E-02 3.0 E-03 901217 to 901226 2.5 E-02 2.0 E-03 (a) Power outage. shortened sampling time.

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102 1.4 E-02 3.0 E-03 900102 to 900108 5.1 E-03 1.8 E-03 900108 to 900115 1.7 E-02 2.0 E-03 900115 to 900122 3.0 E-02 3.0 E-03 900122 to 900129 (a)" 1.9 E-03 1.7 E-03 900129 to 900205 3.4 E-03 1.7 E-03 900205 to 900212 2.9 E-03 1.7 E-03 900212 to 900220 1.7 E-02'-03 2.0 E-03 900220 to 900226 9.5 2.2 E-03 900226 to 900305 2.1 E-02 3.0 E-03 900305 to 900312 4.8 E-03 1.6 E-03 900312 to 900319 1.0 E-02 2.0 E-03 900319 to 900326 1.6 E-02 2.0 E-03 900326 to 900402 1.8 E-02 2.0 E-03 900402 to 900409 1.7 E-02 2.0 E-03 900409 to 900416 (c) 1.1 E-02 3.0 E-03 900416 to 900423 (b) 4 5 E-03 2.8 E-03 900423 to 900430 4.2 E-03 1.7 E-03 900430 to 900507 1.1 E-02 2.0 E-03 900507 to 900514 5.2 E-03 1.8 E-03 900514 to 900521 1.1 E-02 2.0 E-03 900521 to 900529 7.0 E-03 1.5 E-03 900529 to 900604 (a) 2.3 E-03 1.8 E-03 900604 to 900611 9.8 E-03 1.9 E-03 900611 to 900618 4.8 E-03 1.6 E-03 900618 to 900625 1.3 E-02 2.0 E-03 900625 to 900702 7.7 E-03 1.9 E-03 900702 to 900709 4.5 E-03 1.7 E-03 900709 to 900716 1.5 E-02 2.0 E-03 900716 to 900723 1.2 E-02 2.0 E-03 900723 to 900730 1.2 E-02 2.0 E-03 900730 to 900806 1.5 E-02 2.0 E-03 900806 to 900813 2.0 E-02 2.0 E-03 900813 to 900820 1.0 E-02 5.0 E-03 900820 to 900827 8.3 E-03 2.0 E-03 900827 to 900904 1.2 E-02 2.0 E-03 900904 to 900910 2.3 E-02 3.0 E-03 900910 to 900917 1.7 E-02 2.0 E-03 900917 to 900924 1.9 E-02 2.0 E-03 (a) Deposition on filter was light, but there was no equipment malfunction or shor tened sampling time.

(b) Shortened sampling time, result not included in averages.

(c) Shortened sampling time.

  • Denotes a result less than the detection limit.

A-22

TASLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001 2.9 E-02 3.0 E-03 901001 to 901008 1.2 E-02 2.0 E-03 901008 to 901015 1.2 E-02 2.0 E-03 901015 to 901022 1.2 E-02 2.0 E-03 901022 to 901029 2.3 E-02 3.0 E-03 901029 to 901105 8.1 E-03 1.8 E-03 901105 to 901112 1.2 E-02 2.0 E-03 901112 to 901119 1.5 E-02 2.0 E-03 901119 to 901126 5.0 E-03 1.6 E-03 901126 to 901203 5.7 E-03 1.6 E-03 901203 to 901210 1.8 E-02 2.0 E-03 901210 to 901217 1.5 E-02 2.0 E-03 901217 to 901226 1.7 E-02 2.0 E-03 A-23

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102 1.2 E-02 2.0 E-03 900102 to 900108 3.1 E-03 1.6 E-03 900108 to 900115 1.5 E-02 2.0 E-03 900115 to 900122 3.2 E-02 3.0 E-03 900122 to 900129 3.4 E-03 1.6 E-03 900129 to 900205 3.9 E-03 1.7 E-03 900205 to 900212 (a) 1.6 E-03 1.6 E-03 900212 to 900220 1.4 E-02 2.0 E-03 900220 to 900226 1.1 E-02 2.0 E-03 900226 to 900305 2.3 E-02 3.0 E-03 900305 to 900312 3 4 E-03 1.6 E-03 900312 to 900319 9.6 E-03 2.0 E-03 900319 to 900326 1;5 E-02 2.0 E-03 900326 to 900402 2.0 E-02 2.0 E-03 900402 to 900409 1.6 E-02 2.0 E-03 900409 to 900416 1.1 E-02 2.0 E-03 900416 to 900423 5.8 E-03 1.8 E-03 900423 to 900430 4.5 E-03 1.7 E-03 900430 to 900507 1.2 E-02 2.0 E-03 900507 to 900514 (b) 4.7 E-03 1.8 E-03 900514 to 900521 1.4 E-02 2.0 E-03 900521 to 900529 (b) 6.9 E-03 2.3 E-03 900529 to 900604 3.3 E-03 1.9 E-03 900604 to 900611 '1. 6 E-02 2.0 E-03 900611 to 900618 5.4 E-03 1.6 E-03 900618 to 900625 9.6 E-03 1.9 E-03 900625 to 900702 5.8 E-03 1.8 E-03 900702 to 900709 5.8 E-03 1.8 E-03 900709 to 900716 1.4 E-02 2.0 E-03 900716 to 900723 (b) 6.0 E-03 1.8 E-03 900723 to 900730 (b) 1.3 E-02 2.0 E-03 900730 to 900806 1.5 E-02 2.0 E-03 900806 to 900813 1.9 E-02 2.0 E-03 900813 to 900820 8.5 E-03 2.0 E-03 900820 to 900827 9.4 E-03 2.0 E-03 900827 to 900904 1.1 E-02 2.0 E-03 900904 to 900910 1.7 E-02 3.0 E-03 900910 to 900917 1.4 E-02 2.0 E-03 900917 to 900924 1.5 E-02 2.0 E-03 (a) Deposition on filter was light, but there was no e qui pment ma 1 functi on or shortened sampling time.

(b) Power outage; shorten ed sampling time.

  • Denotes a result less than the detec tion 1 imi

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001 3.0 E-02 3.0 E-03 901001 to 901008 1.0 E-02 2.0 E-03 901008 to 901015 9.9 E-03 1.8 E-03 901015 to 901022 1.3 E-02 2.0 E-03 901022 to 901029 1.1 E-02 2.0 E-03 901029 to 901105 8.4 E-03 1.8 E-03 901105 to 901112 9.7 E-03 1.8 E-03 901112 to 901119 1.2 E-02 2.0 E-03 901119 to 901126 4.5 E-03 1.6 E-03 901126 to 901203 5.9 E-03 1.6 E-03 901203 to 901210 1.9 E-02 2.0 E-03 901210 to 901217 1.8 E-02 2.0 E-03 901217 to 901226 3.0 E-02 2.0 E-03 A-25

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 21 891227 to 900102 1.3 E-02 2.0 E-03 900102 to 900108 5.0 E-03 1.8 E-03 900108 to 900115 1.2 E-02 2.0 E-03 900115 to 900122 2.9 E-02 3.0 E-03 900122 to 900129 2.7 E-03 1.5 E-03 900129 to 900205 2.4 E-03 1.6 E-03 900205 to 900212 (a)

  • 2.5 E-03 1.8 E-03 900212 to 900220 1.7 E-02 2.0 E-03 900220 to 900226 1.0 E-02 2.0 E-03 900226 to 900305 1.8 E-02 2.0 E-03 900305 to 900312 4.0 E-03 1.6 E-03 900312 to 900319 7.8 E-03 1.9 E-03 900319 to 900326 1.4 E-02 2;0 E-03 900326 to 900402 1.5 E-02 2.0 E-03 900402 to 900409 1.5 E-02 2.0 E-03 900409 to 900416 8.6 E-03 2.0 E-03 900416 to 900423 6.5 E-03 1.8 E-03 900423 to 900430 3.2 E-03 1.6 E-03 900430 to 900507 9.3 E-03 1.8 E-03 900507 to 900514 3.6 E-03 1.7 E-03 900514 to 900521 1.0 E-02 2.0 E-03 900521 to 900529 6.8 E-03 1.5 E-03 900529 to 900604 (b)
  • 2.6 E-03 1.8 E-03 900604 to 900611 8.8 E-03 1.8 E-03 900611 to 900618 7.1 E-03 1.7 E-03 900618 to 900625 1.2 E-02 2.0 E-03 900625 to 900702 7.5 E-03 1.9 E-03 900702 to 900709 4.1 E-03 1.7 E-03 900709 to 900716 1.3 E-02 2.0 E-03 900716 to 900723 9.5 E-03 2.0 E-03 900723 to 900730 1.2 E-02 2.0 E-03 900730 to 900806 1.5 E-02 2.0 E-03 900806 to 900813 2.1 E-02 2.0 E-03 900813 to 900820 7.5 E-03 1.9 E-03 900820 to 900827 9.0 E-03 2.0 E-03 900827 to 900904 1.0 E-02 2.0 E-03 900904 to 900910 1.8 E-02 3.0 E-03 900910 to 900917 1.4 E-02 2.0 E-03 900917 to 900924 1.7 E-02 2.0 E-03 (a) Oeposition on filter was light, but there w as no e quipment malfunction or shortened sampling time, (b) Power outage; shorten ed sampling time. =
  • Oenotes a result less than t'e d etection limit.

A-26

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 21 900924 to 901001 2.6 E-02 3.0 E-03 901001 to 901008 1.1 E-02 2.0 E-03 901008 to 901015 8.9 E-03 1.8 E-03 901015 to 901022 1.1 E-02 2.0 E-03 901022 to 901029 1.2 E-02 2.0 E-03 901029 to 901105 8.1 E-03 1.8 E-03 901105 to 901112 1.3 E-02 2.0 E-03 901112 to 901119 1.5 E-02 2.0 E-03 901119 to 901126 5.9 E-03 1.6 E-03 901126 to 901203 6.1 E-03 1.6 E-03 901203 to 901210 2.0 E-02 2.0 E-03 901210 to 901217 1.6 E-02 2.0 E-03 901217 to 901226 2.3 E-02 2.0 E-03 A-27

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 23 891227 to 900102 1.6 E-02 3.0 E-03 900102 to 900108 6.5 E-03 1.9 E-03 900108 to 900115 1.6 E-02 2.0 E-03 900115 to 900122 3.5 E-02 3.0 E-03 900122 to 900129 3.8 E-03 1.6 E-03 900129 to 900205 4.6 E-03 1.7 E-03 900205 to 900212 (a) 2.3 E-03 1.7 E-03 900212 to 900220 1.9 E-02 2.0 E-03 900220 to 900226 1.6 E-02 3.0 E-03 900226 to 900305 2.5 E-02 3.0 E-03 900305 to 900312 5.4 E-03 1.7 E-03 900312 to 900319 (b) 9.5 E-03 2.0 E-03 900319 to 900326 1.7 E-02 2.0 E-03 900326 to 900402 1.8 E-02 2.0 E-03 900402 to 900409 1.8 E-02 2.0 E-03 900409 to 900416 1.3 E-02 2.0 E-03 900416 to 900423 7.3 E-03 1.8 E-03 900423 to 900430 5.3 E-03 1.7 E-03 900430 to 900507 1.1 E-02 2.0 E-03 900507 to 900514 4.4 E-03 1.7 E-03 900514 to 900521 1.4 E-02 2.0 E-03 900521 to 900529 8,.3 E-03 1.6 E-03 900529 to 900604 3.0 E-03 1.9 E-03 900604 to 900611 9.7 E-03 1.9 E-03 900611 to 900618 5.3 E-03 1.6 E-03 900618 to 900625 1.2 E-02 2.0 E-03 900625 to 900702 8.8 E-03 2.0 E-03 900702 to 900709 3.9 E-03 1.7 E-03 900709 to 900716 1.6 E-02 2.0 E-03 900716 to 900723 1.2 E-02 2.0 E-03 900723 to 900730 1.2 E-02 2.0 E-03 900730 to 900806 1.7 E-02 2.0 E-03 900806 to 900813 2.3 E-02 3.0 E-03 900813 to 900820 9.0 E-03 2.0 E-03 900820 to 900827 9.9 E-03 2.0 E-03 900827 to 900904 1.1 E-02 2.0 E-03 900904 to 900910 2.4 E-02 3.0 E-03 900910 to 900917 1.5 E-02 2.0 E-03 900917 to 900924 1.9 E-02 2.0 E-03 (a) Deposition on filter was light. but there wa s no eq uipment malfunction or shortened samplin g time.

(b) Sampler malfunction; shortened s ampling time.

  • Denotes a result les s than the d etection limit.

A-28

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 23 900924 to 901001 3.0 E-02 3.0 E-03 901001 to 901008 (a) 1.5 E-02 5.0 E-03 901008 to 901015 1.1 E-02 2.0 E-03 901015 to 901022 1.1 E-02 2.0 E-03 901022 to 901029 1.5 E-02 2.0 E-03 901029 to 901105 9.7 E-03 1.8 E-03 901105 to 901112 1.3 E-02 2.0 E-03 901112 to 901119 1.6 E-02 2.0 E-03 901119 to 901126 5.0 E-03 1.6 E-03 901126 to 901203 6.1 E-03 1.6 E-03 901203 to 901210 2.1 E-02 2.0 E-03 901210 to 901217 , 1.9 E-02 2.0 E-03 901217 to 901226 2.8 E-02 2.0 E-03 (a) Shortened sampling time; result not included in averages.

A-29

TABLE A-2.1 (Cont. )

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 40 891227 to 900102 2.1 E-02 3.0 E-03 900102 to 900108 6.3 E-03 1.8 E-03 900108 to 900115 2.0 E-02 2.0 E-03 900115 to 900122 3.7 E-02 3.0 E-03 900122 to 900129 2.6 E-03 1.5 E-03 900129 to 900205 5.1 E-03 1.8 E-03 900205 to 900212 3.8 E-03 1.7 E-03 900212 to 900220 1.9 E-02 2.0 E-03 900220 to 900226 1.5 E-02 3.0 E-03 900226 to 900305 2.7 E-02 3.0 E-03 900305 to 900312 8.0 E-03 1.8 E-03 900312 to 900319 1.2 E-02 2.0 E-03 900319 to 900326 1.4 E-02 2.0 E-03 900326 to 900402 2.0 E-02 2.0 E-03 900402 to 900409 2.1 E-02 2.0 E-03 900409 to 900416 1.5 E-02 2.0 E-03 900416 to 900423 8.8 E-03 1.9 E-03 900423 to 900430 (a) 5.5 E-03 1.9 E-03 900430 to 900507 7.5 E-03 1.6 E-03 900507 to 900514 6.1 E-03 1.8 E-03 900514 to 900521 1.6 E-02 2.0 E-03 900521 to 900529 6.9 E-03 1..5 E-03 900529 to 900604 4.3 E-03 1.9 E-03 900604 to 900611 (b) 7.6 E-03 2.2 E-03 900611 to 900618 9.0 E-03 1.8 E-03 900618 to 900625 1.4 E-02 2.0 E-03 900625 to 900702 8.9 E-03 2.0 E-03 900702 to 900709 7.0 E-03 1.9 E-03 900709 to 900716 1.8 E-02 2.0 E-03 900716 to 900723 1.2 E-02 2.0 E-03 900723 to 900730 1.3 E-02 2.0 E-03 900730 to 900806 1.9 E-02 2.0 E-03 900806 to 900813 2.5 E-02 3.0 E-03 900813 to 900820 9.6 E-03 2.1 E-03 900820 to 900827 1.0 E-02 2.0 E-03 900827 to 900904 1.8 E-02 2.0 E-03 900904 to 900910 2.3 E-02 3.0 E-03 900910 to 900917 1.4 E-02 2.0 E-03 900917 to 900924 2.2 E-02 2.0 E-03 (a) Brief power outage: shortened sampling time.

(b) Sampler malfunction; shortened sampling time.

A 30

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 40 900924 to 901001 3.0 E-02 3.0 E-03 901001 to 901008 1.1 E-02 2.0 E-03 901008 to 901015 1.1 E-02 2.0 E-03 901015 to 901022 1.3 E-02 2.0 E-03 901022 to 901029 2.1 E-02 2.0 E-03 901029 to 901105 9.8 E-03 1. 9 E-03 901105 to 901112 1.5 E-02 2.0 E-03 901112 to 901119 1.5 E-02 2.0 E-03 901119 to 901126 (a) 1.2 E-02 2.0 E-03 901126 to 901203 (a) *-7 0 E-03 8.5 E-02 901203 to 901210 (a) 1.8 E-02 3.0 E-03 901210 to 901217 1.7 E-02 2.0 E-03 901217 to 901226 4.3 E-03 1.4 E-03 (a) Sampler mal function: shortened sampling time.

Denotes a result less than the detection limit.

TABLE A-2.1 (Cont,)

~ Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERI00 RESULT UNCERTAINTY 48 891227 to 900102 1.8 E-02 3.0 E-03 900102 to 900108 5.3 E-03 1.8 E-03 900108 to 900115 1.8 E-02 2.0 E-03 900115 to 900122 3.2 E-02 3.0 E-03 900122 to 900129 2.7 E-03 1.7 E-03 900129 to 900205 4.7 E-03 1.7 E-03 900205 to 900212 2.8 E-03 1.7 E-03 900212 to 900220 2.3 E-02 2.0 E-03 900220 to 900226 1.5 E-'02 3.0 E-03 900226 to 900305 (a) 2.4 E-02 4.0 E-03 900306 to 900312 (b) 5.4 E-03 1.9 E-03 900312 to 900319 1.0 E-02 2.0 E-03 900319 to 900326 2.0 E-02 2.0 E-03 900326 to 900402 2.1 E-02 2.0 E-03 900402 to 900409 2.0 E-02 2.0 E-03 900409 to 900416 1.4 E-02 2.0 E-03 900416 to 900423 (b) 9.1 E-03 1.9 E-03 900423 to 900430 5.6 E-03 1.8 E-03 900430 to 900507 1.3 E-02 2.0 E-03 900507 to 900514 5.7 E-03 1.8 E-03 900514 to 900521 1.3 E-02 2.0 E-03 900521 to 900529 8.2 E-03 1.6 E-03 900529 to 900604 4.8 E-03 2.6 E-03 900604 to 900611 1.1 E-02 2.0 E-03 900611 to 900618 7.9 E-03 1.8 E-03 900618 to 900625 1.3 E-02 2.0 E-03 900625 to 900702 8.7 E-03 2.0 E-03 900702 to 900709 4.6 E-03 1.7 E-03 900709 to 900716 1.7 E-02 2.0 E-03 900716 to 900723 1.3 E-02 2.0 E-03 900723 to 900730 1.2 E-02 2.0 E-03 900730 to 900806 1.8 E-02 2.0 E-03 900806 to 900813 2.3 E-02 3.0 E-03 900813 to 900820 9.3 E-03 2.0 E-03 900820 to -900827 1.0 E-02 2.0 E-03 900827 to 900904 1.4 E-02 2.0 E-03 900904 to 900910 2.1 E-02 3.0 E-03 900910 to 900917 1.4 E-02 2.0 E-03 900917 to 900924 1.8 E-02 2.0 E-03 (a) Shortened sampling time; result not included in averages.

(b) Equipment inoperability: shortened sampling time.

A-32

TABLE A-2.1 (Cont.)

Res ul ts i n pCi /cubi c meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 48 900924 to 901001 2.6 E-02 3.0 E-03 901001 to 901008 8.3 E-03 1.9 E-03 901008 to 901015 1.1 E-02 2.0 E-03 901015 to 901022 1.0 E-02 2.0 E-03 901022 to 901029 1.2 E-02 2.0 E-03 901029 to 901105 8.7 E-03 1.8 E-03 901105 to 901112 1.1 E-02 2.0 E-03 901112 to 901119 1.6 E-02 2.0 E-03 901119 to 901126 3.8 E-03 1.5 E-03 901126 to 901203 6.5 E-03 1.7 E-03 901203 to 901210 1.9 E-02 2.0 E-03 901210 to 901217 1.7 E-02 2.0 E-03 901217 to 901226 5.1 E-03 1.4 E-03 A-33

TABLE A-2.1 (Cont.)

B T P AT I R Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 57 891227 to 900102 1.9 E-02 3.0 E-03 900102 to 900108 5.8 E-03 1.8 E-03 900108 to 900115 1.7 E-02 2.0 E-03 900115 to 900122 3 4 E-02 3.0 E-03 900122 to 900129 2.8 E-03 1.5 E-03 900129 to 900205 4.5 E-03 1.7 E-03 900205 to 900212 3.8 E-03 1.7 E-03 900212 to 900220 1.9 E-02 2.0 E-03 900220 to 900226 1.8 E-02 3.0 E-03 900226 to 900305 2.8 E-02 3.0 E-03 900305 to 900312 6.2 E-03 1.7 E-03 900312 to 900319 1.0 E-02 2.0 E-03 900319 to 900326 1.8 E-02 2.0 E-03 900326 to 900402 2.1 E-02 2.0 E-03 900402 to 900409 2.1 E-02 2.0 E-03 900409 to 900416 1.1 E-02 2.0 E-03 900416 to 900423 8.2 E-03 1.9 E-03 900423 to 900430 4.7 E-03 1.7 E-03 900430 to 900507 1.1 E-02 2.0 E-03 900507 to 900514 5.7 E-03 1.8 E-03 900514 to 900521 1.1 E-02 2.0 E-03 900521 to 900529 8.4 E-03 1.6 E-03 900529 to 900604 3.8 E-03 1.9 E-03 900604 to 900611 9.9 E-03 1.9 E-03 900611 to 900618 6.2 E-03 1.7 E-03 900618 to 900625 1,3 E-02 2.0 E-03 900625 to 900702 9.0 E-03 2.0 E-03 900702 to 900709 6.3 E-03 1.8 E-03 900709 to 900716 1.6 E-02 2.0 E-03 900716 to 900723 1.4 E-02 2.0 E-03 900723 to 900730 1.4 E-02 2.0 E-03 900730 to 900806 2.0 E-02 2.0 E-03 900806 to 900813 2.4 E-02 3.0 E-03 900813 to 900820 1.1 E-02 2.0 E-03 900820 to 900827 1.1 E-02 2.0 E-03 900827 to 900904 1.4 E-02 2.0 E-03 900904 to 900910 2.4 E-02 3.0 E-03 900910 to 900917 1.8 E-02 2.0 E-03 900917 to 900924 2.3 E-02 2.0 E-03 A-34

TABLE A-2.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 57 900924 to 901001 2.9 E-02 3.0 E;03 901001 to 901008 1.2 E-02 2.0 E-03 901008 to 901015 ,1.2 E-02 2.0 E-03 901015 to 901022 1.2 E-02 2.0 E-03 901022 to 901029 2.3 E-02 3.0 E-03 901029 to 901105 8.1 E-03 1.8 E-03 901105 to 901112 1.2 E-02 2.0 E-03 901112 to 901119 1. 5 E-02 2.0 E-03 901119 to 901126 4.8 E-03 1.6 E-03 901126 to 901203 5.9 E-03 1.6 E-03 901203 to 901210 1.7 E-02 2.0 E-03 901210 to 901217 2.1 E-02 2.0 E-03 901217 to 901226 2.6 E-02 2.0 E-03 A-35

TABLE A-2.2 Results in pCi/cubic meter NUMBER NUMBER NUCLIOE AVERAGE LOW HIGH SAMPLES POSITIVE Gr-Beta ( I) 1.30E-02 1.60E-03 5.90E-02 572 563 Gr - Beta (C) 1. 18E-02 1.60E-03 3.20E-02 52 51

( I) Indicator Stations (C) Control Station A-36

TABLE A-3.1 Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 900102 to 900402 (a) Be-7 4.66 E-02 3.40 E-03 K-40 *-1 55 E-01 4. 11 E-03 Ru-103

  • 3.26 E-06 2.27 E-04 RU-106 *-9.60 E-05 1.38 E-03 Cs-134
  • 5.07 E-05 1.55 E-04 Ra-226 *-4.18 E-03 2.56 E-03 Th-228 *-4 18 E-04 2.20 E-04 900402 to 900702 (a) Be-7 4.22 E-02 3.97 E-03 K-40
  • 2.39 E-03 2.65 E-03 Ru-103
  • 2.42 E-05 2.18 E-04 Ru-106 *-5.82 E-04 1.62 E-03 Cs-134 *-4 15 E-05 1.86 E-04 Cs-137
  • 8.39 E-06 2.02 E-04 Ra-226 *-5 41 E-05 3.59 E-03 Th-228 *-1.11 E-05 2.96 E-04 900702 to 901001 Be-7 7.21 E-02 4.23 E-03 K-40
  • 2.93 E-03 2.30 E-03 Ru-103 *-4.96 E-05 1.82 E-04 Ru-106
  • 7.45 E-04 1.30 E-03 Cs-134
  • 3 43 E-04 2.34 E-04 901001 to 901231 Be-7 5.24 E-02 6.89 E-03 K-40
  • 2.31 E-03 2.86 E-03 Ru-103
  • 2.30 E-04 5.76 E-04 RU-106 *-7.12 E-04 1.77 E-03 Cs-134 *-8.55 E-05 1.76 E-04 Cs-137
  • 6.41 E-04 3.15 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

A-37

TABLE A-3.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 4 900102 to 900402 Be-7 5.23 E-02 5.43 E-03 K-40

  • 1.90 E-03 3.04 E-03 RU-103
  • 4.90 E-05 3.11 E-04 Ru-106 *-2.66 E-03 1.70 E-03 Cs-134 *-1.25 E-05 1.86 E-04 Cs-137 *-3.64 E-06 2.05 E-04 Ra-226
  • 3.79 E-04 3.24 E-04 900402 to 900702 Be-7 4.44 E-02 3.83 E-03 K-40 8.03 E-03 2.88 'E-03 RU-103 *-6.50 E-05 1.91 E-04 Ru-106 *-8 45 E-04 1.28 E-03 Cs-134
  • 2.36 E-04 2.50 E-04 900702 to 901001 (a) Be-7 7.06 E-02 3.45 E-03 K-40 *-2.91 E-03 4.38 E-03 Ru-103 *-4.46 E-05 2.11 E-04 RU-106
  • 3.67 E-04 1.52 E-03 Cs-134
  • 7.27 E-05 1.62 E-04 Ra-226 *-6.02 E-03 2.69 E-03 Th-228 *-6.85 E-04 2.29 E-04 901001 to 901231 Be-7 3.88 E-02 6.75 E-03 K-40
  • 7 33 E-04 3.56 E-03 RU-103 *-1.07 E-04 6.34 E-04 RU-106 *-1.61 E-03 2.07 E-03 Cs-134
  • 9.14 E-05 2.49 E-04 Cs-137 *-4.14 E-04 2.07 E-04 Ra-226 *-1.69 E-03 3.44 E-03 Th-228 *-3.48 E-04 3.31 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

A"38

TABLE A-3.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 5 900102 to 900402 Be-7 4.45 E-02 5.10 E-03 K-40 *-2 72 E-03 3.90 E-03 RU-103 *-1 77 E-05 3.45 E-04 Ru-106 *-3.30 E-04 2.08 E-03 Cs-134

  • 5.73 E-05 2.58 E-04 Cs-137 *-4 67 E-05 2.29 E-04 Ra-226 *-2 04 E-03 3.99 E-03 Th-228 *-3.52 E-04 3.57 E-04 900402 to 900702 Be-7 3.40 E-02 3.60 E-03 K-40 *-1 02 E-02 3.22 E-03 Ru-103 *-1.60 '-04 2.34 E-04 RU-106 *-6.89 E-04 1.77 E-03 Cs-134 *-6.93 E-05 2.32 E-04 Cs-137
  • 1.66 E-04 3.17 E-04 900702 to 901001 Be-7 6.66 E-02 3.61 E-03 K-40 6.50 E-03 3.20 E-03 RU-103
  • 1.60 E-05 1.94 E-04 RU-106
  • 5 54 E-04 1.40 E-03 Cs-134
  • 1.33 E-04 1.56 E-04 Ra-226 *-1 04 E-03 2.74 E-03 Th-228 *-3.86 E-04 2.46 E-04 901001 to 901231 Be-7 4.66 E-02 6.83 E-03 K-40
  • 4.28 E-03 3.91 E-03 Ru-103 *-1 01 E-04 6.19 E-04 Ru-106
  • 0.00 E+00 1.89 E-03 Cs-134
  • 9.05 E-05 3.01 E-04
  • Denotes a result less than the detection limit.

A-39

TABLE 'A-3.1 (Cont.)

AM A Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 900102 to 900402 (a) Be-7 4.39 E-02 4. 68 E-03 K-40 *-4 05 E-03 3.97 E-03 Ru-103

  • 8.65 E-06 3.32 E-04 RU-106
  • 6.89 E-04 1.93 E-03 Cs-134 *-8.80 E-06 2.24 E-04 Cs-137
  • 1.43 E-03 4.06 E-03 TI1-228 *-9 41 E-05 3.29 E-04 900402 to 900702 Be-7 3.47 E-02 3.43 E-03 K-40 *-8.03 E-03 3.12 E-03 RU-103
  • 9.83 E-05 2.37 E-04 RU-106 *-2.11 E-03 1.64 E-03 Cs-134 *-7.70 E-05 1.85 E-04 Cs-137
  • 2.78 E-04 2.84 E-04 900702 to 901001 Be-7 7.16 E-02 3.49 E-03 K-40
  • 2.45 E-03 3.05 E-03 Ru-103 *-5.70 E-05 1.92 E-04 Ru-106 *-1.60 E-04 1.35 E-03 Cs-134
  • 5.35 E-05 1.55 E-04 Ra-226 *-5.52 E-03 2.67 E-03 Th-228 *-1 59 E-04 2.18 E-04 901001 to 901231 Be-7 5.34 E-02 6.60 E-03 K-40
  • 2.74 E-03 2.55 E-03 Ru-103
  • 2.09 E-04 4.11 E-04 Ru-106 *-7.36 E-04 1.30 E-03 Cs-134
  • 1.65 E-04 2.27 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

A-40

TABLE A-3.1 (Cont.)

AHHA PE T ME RY F PARTI T F T R

~ Res ul ts in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 900102 to 900402 (a) Be-7 5.73 E-02 4.89 E-03 K-40

  • 3.48 E-03 3.07 E-03 RU-103 *-1 13 E-05 2.25 E-04 Ru-106
  • 6.68 E-04'-05 1.39 E-03 Cs-134
  • 1.05 E-03 2.52 E-03 Th-228 *-1.78 E-05 2.28 E-04 900402 to 900702 Be-7 3.86 E-02 3.78 E-03 K-40
  • 2.12 E-03 2.47 E-03 RU-103 *-1.23 E-04 1.58 E-04 Ru-106 *-6.63 E-04 1.17 E-03 Cs-134 *-3.87 E-05 1.32 E-04 Cs-137
  • 2.76 E-05 2.06 E-04 900702 to 901001 (a) Be-7 7.13 E-02 3.75 E-03 K-40 *-1.58 E-03 1.78 E-03 Ru-103 *-4 77 E-05 1.49 E-04 RU-106
  • 2.28 E-04 9.96 E-04 Cs-134 *-5 97 E-05 1.04 E-04 Cs-137
  • 2.35 E-04 1.83 E-04 901001 to 901231 (a) Be-7 5.30 E-02 7.63 E-03 K-40
  • 4.59 E-03 7.51 E-03 Ru-103
  • 1.06 E-04 7.72 E-04 Ru-106
  • 2.67 E-04 2.49 E-03 Cs-134 *-3 49 E-04 2.69 E-04 Cs-137
  • 9 73 E-05 2.58 E-04 Ra-226 *-5.67 E-03 4.84 E-03 Th-228 *-9.03 E-04 4.11 E-04 (a) Shortened sampling time during par t of this period.
  • Denotes a result less than the detection limit.

A-41

TABLE A-3.1 (Cont.)

P T T F PART LT Results in pCi/cubic meter COLLECTION OVERALL LOCATION 'ERIOD NUCLIDE RESULT UNCERTAINTY 8 900102 to 900402 Be-7 4.69 E-02 5.35 E-03 K-40

  • 2.29 E-03 3.19 E-03 Ru-103
  • 3.45 E-05 2.73 E-04 Ru-106 *-7.61 E-04 1.53 E-03 Cs-134
  • 1.53 E-05 2.86 E-04 900402 to 900702 (a) Be-7 4.22 E-02 4.61 E-03 K-40 *-8.10 E-03 7.67 E-03 Ru-103
  • 1.42 E-04 3.12 E-04 Ru-106
  • 8.29 E-04 2.31 E-03 Cs-134 *-8.13 E-05 2.72 E-04 Cs-137 *-] 97 E-04 2.81 E-04 Ra-226 *-5.86 E-03 4.99 E-03 Th-228 *-7.47 E-04 4.08 E-04 900702 to 901001 (a) Be-7 7.74 E-02 4.46 E-03 K-40
  • 9.56 E-03 3.29 E-03 Ru-103
  • 9.85 E-06 2.65 E-04 Ru-106 *-6 20 E-04 1.80 E-03 Cs-134 *4 08 E-05 2.14 E-04 Cs-137
  • 8.86 E-05 2.13 E-04 Ra-226 *-4 28 E-03 4.07 E-03 Th-228 *-6 94 E-04 3.31 E-04 901001 to 901231 Be-7 5.00 E-02 6.84 E-03 K-40
  • 6.91 E-03 3.11 E-03 RU-103
  • 9.80 E-05 5.47 E-04 RU-106
  • 6.78 E-04 1.62 E-03 Cs-134 *-4:14 E-05 1.80 E-04 Cs-137
  • 8.21 E-06 1.73 E-04 Ra-226 *-6.31 E-04 2.89 E-03 Th-228 *-2.31 E-04 2.56 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

TABLE A-3.1,(Cont.)

ANN P TR M TRY AR I AT F R Resul ts in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 9 900102 to 900402 Be-7 4. 68 E-02 5.40 E-03 K-40

  • 5.00 E-03 3.44 E-03 RU-103 *-8 74 E-05 2.75 E-04 Ru-106
  • 1.80 E-04 1.72 E-03 Cs-134
  • 3.15 E-04 3.31 E-03 Th-228 *-5 68 E-05 3.09 E-04 900402 to 900702 (a) Be-7 3. 57 E-02 3.98 E-03 K-40
  • 2.62 E-03 2.97 E-03 Ru-103 *-6.17 E-05 1.96 E-04 Ru-106 *-7.76 E-04 1.41 E-03 Cs-134
  • 1.49 E-04 2.54 E-04 900702 to 901001 (a) Be-7 5.98 E-02 3.58 E-03 K-40 4.84 E-03 2.32 E-03 RU-103
  • 8.36 E-05 1.63 E-04 Ru-106 *-3 13 E-04 1.17 E-03 Cs-134
  • 6.86 E-04 2.43 E-03 Th-228 *-5.31 E-04 2.03 E-04 901001 to 901231 Be-7 4.68 E-02 6.20 E-03 K-40 *-6.51 E-04 2.23 E-03 Ru-103 *-3.11 E-04 4.55 E-04 RU-106 *-6.99 E-04 1.47 E-03 Cs-134
  • 4.22 E-04 2.49 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

A-43

TABLE A-3.1 (Cont.)

A N TR H F P FI T R Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 21 900102 to 900402 (a) Be-7 4.13 E-02 5.07 E-03 K-40

  • 3.99 E-03 3.18 E-03 Ru-103
  • 0.00 E+00 2.35 E-04 RU-106 *-4.60 E-04 1.42 E-03 Cs-134 *-5.23 E-05 1.77 E-04 Cs-137
  • 2.30 E-04 3.14 E-03 Th-228 *-3 35 E-05 2.90 E-04 900402 to 900702 Be-7 3.49 .E-02 3.75 E-03 K-40 3.06 E-03 2.99 E-03 RU-103 7.87 E-06 2.10 E-04 Ru-106 6.82 E-05 1.52 E-03 Cs-134 0.00 E+00 1.65 E-04 Cs-137 6.52 E-05 1.83 E-04 Ra-226 5.26 E-04 2.91 E-03 TI1-228 2.45 E-04 2.74 E-04 900702 to 901001 Be-7 6.85 E-02 3.61 E-03 K-40
  • 1.73 E-03 2.00 E-03 RU-103
  • 6.12 E-05 1.52 E-04 Ru-106
  • 7.63 E-04 1.03 E-03 Cs-134
  • 3.46 E-05 1.25 E-04 Cs-137 0.00 E+00 1.23 E-04 Ra-226 2.09 E-03 2.32 E-03 Th-228 1.74 E-04 1.96 E-04 901001 to 901231 Be-7 4. 60 E-02 7.43 E-03 K-40
  • 1.87 E-03 3.22 E-03 Ru-103 *-3.17 E-04 5.97 E-04 Ru-106 *-5.99 E-04 1.83 E-03 Cs-134
  • 9.75 E-05 2.01 E-04 Ra-226 *-3.09 E-03 3.79 E-03 Th-228 4.26 E-04 3.43 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

A-44

TABLE A-3.1 (Cont.)

ANN P TR M TR PAR LATE I T R Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 23 900102 to 900402 (a) Be-7 3.39 E-02 4.49 E-03 K-40

  • 6.93 E-04 2.59 E-03 Ru-103
  • 8.28 E-05 2.19 E-04 Ru-106 *-8 37 E-04 1.51 E-03 Cs-134
  • 3 34 E-04 2.88 E-03 Th-228 *-2.40 E-04 2.53 E-04 900402 to 900702 Be-7 4.03 E-02 3.96 E-03 K-40
  • 4.25 E-03 2.87 E-03 RU-103
  • 1.32 E'-04 2.26 E-04 RU-106 *-1 14 E-03 1.61 E-03 Cs-134 *-1.01 E-05 1.82 E-04 Cs-137
  • 8.79 E-04 3.52 E-03 Th-228 *-3 21 E-04 2.85 E-04 900702 to 901001 Be-7 7.47 E-02 4.71 E-03 K-40
  • 2.81 E-03 2.56 E-03 RU-103 *-4.76 E-05 1.88 E-04 RU-106 *-4 59 E-04 1.27 E-03 Cs-134 *-2.44 E-05 1.41 E-04 Cs-137
  • 8.83 E-04 2.90 E-04 901001 to 901231 (a) Be-7 7.91 E-02 9.51 E-03 K-40
  • 1.51 E-03 3.82 E-03 RU-103 *-1.77 E-04 8.31 E-04 Ru-106 *-1.32 E-03 2.47 E-03 Cs-134 *-9.90 E-05 2.58 E-04 Cs-137
  • 5.72 E-04 4.37 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

A-45

TABLE A-3.1 (Cont.)'

R A T A Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 40 900102 to 900402 Be-7 5.20 E-02 4. 59 E-03 K-40 4.90 E-03 2.23 E-03 RU-103 *-9.02 E-05 2.01 E-04 Ru-106 *-2.61 E-04 1.32 E-03 Cs-134

  • 2.80 E-04 2.16 E-03 Th-228 *-4.23 E-05 1.89 E-04 900402 to 900702 (a) Be-7 4.92 E-02 4.18 E-03 K-40
  • 4 53 E-03 2.65 E-03 RU-103 *-7.75 E-06 1.92 E-04 Ru-106 *-1.99 E-04 1.37 E-03 Cs-134
  • 1.82 E-04 2.58 E-04 900702 to 901001 Be-7 7.86 E-02 4.06 E-03 K-40 *-1 72 E-03 4.80 E-03 RU-103
  • 0.00 E+00 2.20 E-04 Ru-106
  • 7.91 E-04 1.63 E-03 Cs-134 *-1.81 E-04 2.00 E-04 Cs-137
  • 1.61 E-04 1.39 E-04 901001 to 901231 (a) Be-7 4.88 E-02 7.59 E-03 K-40
  • 1.27 E-02 3.69 E-03 Ru-103
  • 2.40 E-05 6.45 E-04 RU-106 *-1 64 E-03 2.06 E-03 Cs-134 *-8.62 E-05 2.37 E-04 Cs-137
  • 9.65 E-05 2.62 E-04 Ra-226 *-3.82 E-04 3.44 E-03 Th-228 *-2.80 E-03 3.35 E-04 (a) Shortened sampling time during part of this period.
  • Denotes a result less than the detection limit.

TABLE A-3.1 (Cont.)

AMMA P TR M TR T AT F T R Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 48 900102 to 900402 (a) Be-7 8.01 E-02 7.03 E-03 K-40 6.57 E-03 3.47 E-03 Ru-103 *-1.27 E-05 3.37 E-04 Ru-106 *-1 57 E-03 2.00 E-03 Cs-134

  • 2.62 E-04 3.28 E-04 900402 to 900702 (a) Be-7 3.88 E-02 4.21 E-03 K-40 *-9.56 E-03 3.05 E-03 RU-103
  • 1.44 E-04 2.49 E-04 RU-106
  • 3.70 E-04 1.85 E-03 Cs-134 *-2.02 E-04 2.16 E-04 Cs-137 *-4.14 E-05 2.09 E-04 Ra-226
  • 1.61 E-03 3.49 E-03

~ Th-228 *-3.29 E-04 3.04 E-04 900702 to 901001 Be-7 7.61 E-02 4. 04 E-03 K-40 6.34 E-03 2.60 E-03 RU-103

  • 2.19 E-05 1.77 E-04 RU-106 *-4.13 E-04 1.11 E-03 Cs-134
  • 1.92 E-04 2.24 E-04 901001 to 901231 Be-7 7.85 E-02 1.21 E-02 K-40 *-1.48 E-02 7.12 E-03 Ru-103 *-5 49 E-04 1.21 E-03 Ru-106 *-5.20 E-04 3.13 E-03 Cs-134
  • 2.84 E-05 3.30 E-04 Ra-226 *-7 35 E-03 4.68 E-03 Th-228 *-1.55 E-03 4.67 E-04 (a) Shortened sampling time during part of this period.
  • Oenotes a result less than the detection limit.

A-47

TABLE A-3.1 (Cont.)

Results in pCi/cubic meter o

COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 57 900102 to 900402 Be-7 5.77 E-02 4.02 E-03 K-40 *-1.47 E-03 3.55 E-03 RU-103 *-1.62 E-04 2.55 E-04 RU-106 *-9.88 E-04 1.55 E-03 Cs-134

  • 5.80 E-05 1.79 E-04 Ra-226 *-2 43 E-03 2.37 E-03 Th-228 *-1.80 E-04 2.23 E-04 900402 to 900702 Be-7 4.40 E-02 3.99 E-03 K-40 6.22 E-03 3.28 E-03 Ru-103
  • 1.14 E-05 2.46 E-04 Ru-106
  • 4 90 E-05 1.73 E-03 Cs-134 *-1 18 E-04 1.90 E-04
  • -2.61 E-03
  • 1.38 E-04 2.00

'3.50 2.84 E-04 E-03 E-04 ~ s 900702 to 901001 Be-7 9.12 E-02 4.06 E-03 K-40 *-2.52 E-03 3.87 E-03 Ru-103 *-3 70 E-05 2.28 E-04 RU-106 *-2.39 E-04 1.51 E-03 Cs-134 *-1 30 E-05 1.84 E-04 Cs-137

  • 1.90 E-04 2.65 E-04 901001 to 901231 Be-7 5.12 E-02 7.70 E-03, K-40 *-4 23 E-04 6.04 E-03 RU-103
  • 3.65 E-04 6.69 E-04 Ru-106 *-2.75 E-04 2.22 E-03 Cs-134 *-2.77 E-05 2.44 E-04 Cs-137
  • 4.63 E-03 3.34 E-03 Th-228 *-4.33 E-05 3.14 E-04
  • Denotes a result less than the detection 1 imi t.

TABLE A-3.2 Results in pCi/cubic meter NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE Ru-103 (I) 6.25E-06 -5.49E-04 6.78E-04 44 RU-103 (C) -9.41E-05 -3. 11E-04 8.36E-05 RU-106 (I) -3.99E-04 -2. 66E-03 8.29E-04 44 Ru-106 (C) -4.02E-04 -7. 76E-04 1.80E-04 Cs-134 (I) 9.11E-06 -3.49E-04 3.44E-04 44 Cs-134 (C) 5.27E-05 6.46E-06 8.77E-05 Cs-137 (I) 5.98E-05 -4. 14E-04 2.75E-04 44 Cs-137 (C) 4.79E-05 3.15E-05 6.85E-05 Be-7 ( I) 5.46E-02 3.39E-02 9.12E-02 44 44 Be-7 (C) 4.73E-02 3.57E-02 5.98E-02 K-40 ( I) -2.28E-03 -1. 55E-01 1. 27E-02 K-40 (C) 2.95E-03 -6. 51E-04 5.00E-03

( I) Indicator Stations (C) Control Station A"49

e.

TABLE A-4.1 Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102

  • 7.84 E-03 ,1. 11 E-02 900102 to 900108
  • 5.38 E-03 1.70 E-02 900108 to 900115
  • 1.49 E-03 7.91 E-03 900115 to 900122 *-6 84 E-03 1.02 E-02 900122 to 900129
  • 6.76 E-03 1.08 E-02 900129 to 900205
  • 1.63 E-03 9.14 E-03 900205 to 900212
  • 1.53 E-03 9.26 E-03 900212 to 900220 *-4.38 E-03 8.05 E-03 900220 to 900226 *-4 53 E-03 1.73 E-02 900226 to 900305
  • 4.81 E-03 9.15 E-03 900305 to 900312
  • 7.81 E-04 7.71 E-03 900312 to 900319
  • 1.66 E-03 1.01 E-02 900319 to 900326 *-6.58 E-03 9.09 E-03 900326 to 900402
  • 1.88 E-03 1.02 E-02 900402 to 900409
  • 1.42 E-03 9.22 E-03 900409 to 900416
  • 5.69 E-03 9.79 E-03 900416 to 900423
  • 2.92 E-03 9.34 E-03 900423 to 900430 *-4.76 E-03 8.74 E-03 900430 to 900507 (a) *-4.25 E-04 9.10 E-03 900507 to 900514 (a)
  • 4.04 E-04 1.21 E-02 900514 to 900521 (a)
  • 1.35 E-03 1.24 E-02 900521 to 900529 *-3 53 E-03 7.09 E-03 900529 to 900604 *-4.61 E-03 1.19 E-02 900604 to 900611 *-5.82 E-03 8.32 E-03 900611 to 900618 *-2.83 E-03 1.01 E-02 900618 to 900625
  • 0.00 E+00 1.13 E-02 900625 to 900702 *-3.88 E-04 8.33 E-03 900702 to 900709
  • 1.93 E-03 9.32 E-03 900709 to 900716
  • 6.34 E-03 1.08 E-02 900716 to 900723 *-6.53 E-03 1.07 E-02 900723 to 900730 *-3 10 E-03 1.18 E-02 900730 to 900806
  • 4.09 E-03 1.01 E-02 900806 to 900813
  • 1.04 E-02 1.08 E-02 900813 to 900820 *-4.25 E-03 1.02 E-02 900820 to 900827
  • 6.30 E-04 1.07 E-02 900827 to 900904 *-4 05 E-03 6.12 E-03 900904 to 900910
  • 1.02 E-03 1.10 E-02 900910 to 900917 *-1.35 E-03 8.00 E-03 900917 to 900924
  • 4.56 E-03 1.62 E-02 (a) Power outage; shortened sampling time.
  • Denotes a result less than the detection limit.

A-50

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001

  • 1.30 E-02 1.34 E-02 901001 to 901008
  • 8.55 E-03 1.47 E-02 901008 to 901015 *-4.39 E-03 '1.27 E-02 901015 to 901022 *-1.54 E-03 1.88 E-02 901022 to 901029
  • 1. 51 E-03 1.50 E-02 901029 to 901105 *-1. 05 E-02 1.43 E-02 901105 to 901112
  • 6. 31 E-03 1.47 E-02 901112 to 901119
  • 1.55 E-03 1.43 E-02 901119 to 901126 *-3.18 E-03 1.32 E-02 901126 to 901203 *-3.20 E-03 1.28 E-02 901203 to 901210 *-4.02 E-03 1.42 E-02 901210 to 901217
  • 1.39 E-03 1.49 E-02 901217 to 901226 *-8.97 E-03 1.55 E-02 Denotes a result less than the detection limit.

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102

  • 7.71 E-03 1.09 E-02 900102 to 900108
  • 5.24 E-03 1.66 E-02 900108 to 900115
  • 1.47 E-03 7.76 E-03 900115 to 900122 *-6.71 E-03 9.97 E-03 900122 to 900129
  • 6.64 E-03 1.06 E-02 900129 to 900205
  • 1.61 E-03 9.01 E-03 900205 to 900212
  • 1.49 E-03 9.00 E-03 900212 to 900220 *-4 34 E-03 7.96 E-03 900220 to 900226 *-4.42 E-03 1.69 E-02 900226 to 900305
  • 4.74 E-03 9.01 E-03 900305 to 900312
  • 7.67 E-04 7.57 E-03 900312 to 900319
  • 1.63 E-03 9.93 E-03 900319 to 900326 *-6.44 E-03 8.88 E-03 900326 to 900402
  • 1.85 E-03 1.00 E-02 900402 to 900409
  • 1.39 E-03 9.06 E-03 900409 to 900416
  • 5.58 E-03 9.60 E-03 900416 to 900423
  • 2.88 E-03 9.22 E-03 900423 to 900430 *-4.66 E-03 8.56 E-03 900430 to 900507 *-3 90 E-04 8.34 E-03

~ 900507 to 900514

  • 3.29 E-04 9.89 E-03 900514 to 900521
  • 1.25 E-03 1.14 E-02 900521 to 900529
  • 3 47 E-03 6.95 E-03 900529 to 900604 *-4 51 E-03 1.16 E-02 900604 to 900611 *-5 73 E-03 8.19 E-03 900611 to 900618 *-2 77 E-03 9.91 E-03 900618 to 900625
  • 0.00 E+00 1.12 E-02 900625 to 900702 *-3 81 E-04 8.18 E-03 900702 to 900709
  • 1.88 E-03 9.09 E-03 900709 to 900716
  • 6.09 E-03 1.04 E-02 900716 to 900723 *-6.46 E-03 1.06 E-02 900723 to 900730 (a) *-1.18 E-02 4.52 E-02 900730 to 900806
  • 4 QQ E-03 9.84 E-03 900806 to 900813
  • 1.02 E-02 1.06 E-02 900813 to 900820 *-4.16 E-03 9.97 E-03 900820 to 900827
  • 6.17 E-04 1.05 E-02 900827 to 900904 *-3.97 E-03 6.00 E-03

'900904 to 900910

  • 1.01 E-03 1.09 E-02 900910 to 900917 *-1.32 E-03 7.84 E-03 900917 to 900924
  • 4.51 E-03 1.60 E-02 (a) Sampler malfunction, so low sample volume; result not included in summary.

Oenotes a result less than the detection limit.

A-52

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 4 900924 to 901001

  • 1.27 E-02 1.31 E-02 901001 to 901008
  • 8.35 E-03 1.44 E-02 901008 to 901015 *-4.33 E-03 1.25 E-02 901015 to 901022 *-1. 51 E-03 1.85 E-02 901022 to 901029
  • 1.60 E-03 1.60 E-02 901029 to 901105 *-1.04 E-02 1.41 E-02 901105 to 901112
  • 6.18 E-03 1.44 E-02 901112 to 901119
  • 1.52 E-03 1.40 E-02 901119 to 901126 *-3.12 E-03 1.30 E-02 901126 to 901203 *-3.13 E-03 1.26 E-02 901203 to 901210 *-4.98 E-03 1.76 E-02 901210 to 901217
  • 1.37 E-03 1.46 E-02 901217 to 901226 *-8.83 E-03 1.52 E-02
  • Denotes a result less than, the detection limit.

A-53

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102

  • 7.78 E-03 1.10 E-02 900102 to 900108
  • 5,26 E-03 1.66 E-02 900108 to 900115
  • 1.47 E-03 7.80 E-03 900115 to 900122 *-6 75 E-03 1.00 E-02 900122 to 900129
  • 6.68 E-03 1.07 E-02 900129 to 900205
  • 1.62 E-03 9.06 E-03 900205 to 900212 * ] 49 E-03 9.03 E-03 900212 to 900220 *-4 36 E-03 8.00 E-03 900220 to 900226 *-4 48 E-02 1.71 E-01 900226 to 900305
  • 4.74 E-03 9.02 E-03 900305 to 900312 *, 7.71 E-04 7.61 E-03 900312 to 900319
  • 1.64 E-03 9.99 E-03 900319 to, 900326 *-6.47 E-03 8.93 E-03 900326 to 900402
  • 1,86 E-03 1.01 E-02 900402 to 900409
  • 1 40 E-03 9.10 E-03 900409 to 900416
  • 5.61 E-03 9.65 E-03 900416 to 900423
  • 2,90 E-03 9.27 E-03 900423 to 900430 *-4 68 f-03 8.61 E-03 900430 to 900507 *-3.92 E-04 8.38 E-03 900507 to 900514
  • 3.31 E-04 9.94 E-03 900514 to 900521
  • 1.26 E-03 1.15 E-02 900521 to 900529
  • 3 49 E-03 6.99 E-03 900529 to 900604 *-4 53 E-03 1.17 E-02 900604 to 900611 *-5 76 E-03 8.23 E-03 900611 to 900618 *-2.80 E-03 1.00 E-02 900618 to 900625
  • 0.00 E+00 1.12 E-02 900625 to 900702 *-3 84 E-04 8.24 E-03 900702 to 900709
  • 1.89 E-03 9.15 E-03 900709 to 900716
  • 6.12 E-03 1.05 E-02 900716 to 900723 *-6 49 E-03 1.06 E-02 900723 to 900730
  • 3 07 E-03 1.17 E-02 900730 to 900806
  • 4.04 E-03 9.94 E-03 900806 to 900813
  • 1.03 E-02 1.07 E-02 900813 to 900820
  • 4 19 E-03 1.00 E-02 900820 to 900827
  • 6.21 E-04 1.06 E-02 900827 to 900904 *-3 98 E-03 6.02 E-03 900904 to 900911
  • 1.01 E-03 1.09 E-02 900911 to 900917 *-1.33 E-03 7.90 E-03 900917 to 900924
  • 4.52 E-03 1.61 E-02
  • Denotes a result less than the detection limit.

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001

  • 1.28 E-02 1.32 E-02 901001 to 901008
  • 9.15 E-03 1.57 E-02 901008 to 901015 *-4.35 E-03 1.26 E-02 901015 to 901022 *-1. 52 E-03 ,1.86 E-02 901022 to 901029
  • 1.48 E-03 1.48 E-02 901029 to 901105 *-1. 04 E-02 1.42 E-02 901105 to 901112
  • 6.23 E-03 1.45 E-02 901112 to 901119
  • 1.53 E-03 1.40 E-02 901119 to 901126 *-3. 14 E-03 1.31 E-02 901126 to 901203 *-3. 15 E-03 1.26 E-02 901203 to 901210 *-3.99 E-03 1.41 E-02 901210 to 901217
  • 1.37 E-03 1.47 E-02 901217 to 901226 *-8.89 E-03 1.53 E-02
  • Oenotes a result less than the detection limit.

A-55

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 891227 to 900102

  • 7.83 E-03 1.11 E-02 900102 to 900108
  • 5.33 E-03 1.69 E-02 900108 to 900115
  • 1.49 E-03 7.88 E-03 900115 to 900122 *-6.82 E-03 1.01 E-02 900122 to 900129 (a)
  • 9.61 E-03 1.53 E-02 900129 to 900205
  • 1.63 E-03 9.15 E-03 900205 to 900212
  • 1.53 E-03 9.21 E-03 900212 to 900220 *-4 39 E-03 8.05 E-03 900220 to 900226 *-4.47 E-03 1.71 E-02 900226 to 900305
  • 4.80 E-03 9.14 E-03 900305 to 900312
  • 7.81 E-04 7.70 E-03 900312 to 900319
  • 1.65 E-03 1.01 E-02 900319 to 900326 *-6.58 E-03 9.09 E-03 900326 to 900402
  • 1.87 E-03 1.02 E-02 900402 to 900409
  • 1.41 E-03 9.20 E-03 900409 to 900416
  • 5.65 E-03 9.73 E-03 900416 to 900423
  • 2.92 E-03 9.33 E-03 900423 to 900430 *-4.74 E-03 8.71 E-03 900430 to 900507 *-3.96 E-04 8.47 E-03 900507 to 900514
  • 3.34 E-04 1.00 E-02 900514 to 900521
  • 1.27 E-03 1.16 E-02 900521 to 900529 *-3.52 E-03 7.06 E-03 900529 to 900604 *-4.61 E-03 1.19 E-02 900604 to 900611 *-5.80 E-03 8.29 E-03 900611 to 900618 *-2.82 E-03 1.01 E-02 900618 to 900625
  • 0.00 E+00 1.13 E-02 900625 to 900702 *-3.88 E-04 8.32 E-03 900702 to 900709
  • 1.91 E-03 9.25 E-03 900709 to 900716
  • 6.31 E-03 1.08 E-02 900716 to 900723 *-6.52 E-03 1.07 E-02 900723 to 900730 *-3.08 E-03 1.18 E-02 900730 to 900806
  • 4.08 E-03 1.00 E-02 900806 to 900813
  • 1.04 E-02 1.08 E-02 900813 to 900820 *-4.25 E-03 1.02 E-02 900820 to 900827
  • 6.26 E-04 1.07 E-02 900827 to 900904 *-4 03 E-03 6.10 E-03 900904 to 900910
  • 1.02 E-03 1.10 E-02 900910 to 900917 *-1.35 E-03 7.98 E-03 900917 to 900924
  • 4.55 E-03 1.62 E-02 (a) Low sample volume: results not included in average.
  • Denotes a result less than the detection limit.

A-56

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001

  • 1.29 E-02 1.33 E-02 901001 to 901008
  • 8.48 E-03 1.46 E-02 901008 to 901015
  • 4 39 E-03 1.27 E-02 901015 to 901022 *-1 53 E-03 1.87 E-02 901022 to 901029
  • 1.49 E-03 1.49 E-02 901029 to 901105 *-1.05 E-02 1.43 E-02 901105 to 901112
  • 6.28 E-03 1.46 E-02 901112 to 901119
  • 1.54 E-03 1.42 E-02 901119 to 901126 *-3.17 E-03 1.32 E-02 901126 to 901203 *-3 19 E-03 1.28 E-02 901203 to 901210 *-4.02 E-03 1.42 E-02 901210 to 901217
  • 1 39 E-03 1.48 E-02 901217 to 901226 *-8 97 E-03 1.55 E-02 Denotes a result less than the detection limit.

A-57

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD . RESULT UNCERTAINTY 891227 to 900102

  • 6.59 E-03 9.32 E-03 900102 to 900108 (a)
  • 3.93 E-03 1.24 E-02 900108 to 900115 (a)
  • 1.16 E-03 6.14 E-03 900115 to 900122
  • 5 74 E-03 8.53 E-03 900122 to 900129
  • 5.68 E-03 9.06 E-03 900129 to 900205
  • 1.35 E-03 7.60 E-03 900205 to 900212
  • 1.27 E-03 7.65 E-03 900212 to 900220 *-3.70 E-03 6.80 E-03 900220 to 900226 *-3 75 E-03 1.43 E-02 900226 to 900305
  • 4.04 E-03 7.69 E-03 900305 to 900312
  • 5.49 E-04 5.42 E-03 900312 to 900319
  • 1.39 E-03 8.48 E-03 900319 to 900326 *-5 54 E-03 7.65 E-03 900326 to 900402
  • 1.57 E-03 8.54 E-03 900402 to 900409
  • 1.19 E-03 7.75 E-03 900409 to 900416
  • 4.77 E-03 8.21 E-03 900416 to 900423
  • 2.42 E-03 7.75 E-03 900423 to 900430 *-3 94 E-03 7.24 E-03 900430 to 900507 *-3.29 E-04 7.03 E-03 900507 to 900514
  • 2.81 E-04 8.45 E-03 900514 to 900521
  • 7.27 E-04 6.66 E-03 900521 to 900529 *-2 92 E-03 5.87 E-03 900529 to 900604 *-3.88 E-03 9.99 E-03 990604 to 900611 *-4.82 E-03 6.88 E-03 900611 to 900618 *-2.83 E-03 1.01 E-02 900618 to 900625
  • 0.00 E+00 9.55 E-03 900625 to 900702 *-3.22 E-04 6.91 E-03 900702 to 900709
  • 1.59 E-03 7.68 E-03 900709 to 900716
  • 5.31 E-03 9.07 E-03 900716 to 900723 (a) *-7.16 E-03 1.17 E-02 900723 to 900730 *-2.56 E-03 9.80 E-03 900730 to 900806
  • 3.43 E-03 8.45 E-03 900806 to 900813
  • 7.57 E-03 7.86 E-03 900813 to 900820 *-3 57 E-03 8.56 E-03 900820 to 900827
  • 4.56 E-04 7.76 E-03

. 900827 to 900904 (a) *-3.65 E-03 5.52 E-03 900904 to 900911

  • 8.50 E-04 9.14 E-03 900911 to 900917 (a) *-1.15 E-03 6.84 E-03 900917 to 900924
  • 3.83 E-03 1.36 E-02 (a) Power outage; shortened sampling time.
  • Denotes a result less than the detection limit.

A-58

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001

  • 1.07 E-02 1.11 E-02 901001 to 901008
  • 7.13 E-03 1.23 E-02 901008 to 901015 *-3.64 E-03 1.05 E-02 901015 to 901022 *-8.78 E-04 1.07 E-02 901022 to 901029
  • 1.26 E-03 1.25 E-02 901029 to 901105 *-7.64 E-03 1.04 E-02 901105 to 901112
  • 5.29 E-03 1.23 E-02 901112 to 901119
  • 1.12 E-03 1.03 E-02 901119 to 901126 *-2.30 E-03 9.58 E-03 901126 to 901203 *-2.61 E-03 1.05 E-02 901203 to 901210 *-2.92 E-03 1.03 E-02 901210 to 901217 (a)
  • 1.18 E-03 1.26 E-02 901217 to 901226 *-7 35 E-03 1.27 E-02 (a) Power outage: shortened sampling time.
  • Denotes a result'less than the detection limit.

A"59

TABLE A-4.1 (Cont.)

Resul ts in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102

  • 5.54 E-03 1.00 E-02 900102 to 900108
  • 0.00 E+00 3.01 E-02 900108 to 900115
  • 9.49 E-04 1.39 E-02 900115 to 900122 *-1.72 E-03 9.18 E-03 900122 to 900129 *-2.56 E-03 9.86 E-03 900129 to 900205 *-1.50 E-03 7.91 E-03 900205 to 900212 *-2.94 E-03 1.36 E-02 900212 to 900220 *-5.46 E-04 7.30 E-03 900220 to 900226
  • 9.17 E-03 1.53 E-02 900226 to 900305
  • 2.20 E-03 8.71 E-03 900305 to 900312
  • 1.34 E-02 1.36 E-02 900312 to 900319
  • 2.90 E-03 9.21 E-03 900319 to 900326
  • 2.40 E-03 8.56 E-03 900326 to 900402
  • 6.65 E-03 9.52 E-03 900402 to 900409
  • 3.75 E-04 8.29 E-03 900409 to 900416 (a) *-2.46 E-03 9.99 E-03 900416 to 900423 (a) *-1.03 E-02 1.36 E-02 900423 to 900430 *-4.88 E-03 7.61 E-03 900430 to 900507
  • 1.23 E-03 7.11 E-03 900507 to 900514 *-1.38 E-04 8.72 E-03 900514 to 900521
  • 5.74 E-03 9.80 E-03 900521 to 900529
  • 1.28 E-03 5.83 E-03 900529 to 900604 *-4.11 E-03 1.02 E-02 900604 to 900611 *-4.14 E-03 7.36 E-03 900611 to 900618 *-7.07 E-03 1.20 E-02 900625 to 900702 *-1.19 E-03 1.26 E-02 900702 to 900709
  • 6.92 E-03 7.94 E-03 900709 to 900716 *-3.48 E-04 9.31 E-03 900716 to 900723 *-1.35 E-03 9.24 E-03 900723 to 900730
  • 9.68 E-04 9.86 E-03 900730 to 900806 *-6.31 E-04 8.51 E-03 900806 to 900813
  • 1.42 E-03 7.43 E-03 900813 to 900820 (a)
  • 4.51 E-03 2.26 E-02 900820 to 900827
  • 3.69 E-03 1.06 E-02 900827 to 900904
  • 2.15 E-03 1.09 E-02 900904 to 900911 *-6.81 E-03 9.60 E-03 900911 to 900917 *-2.68 E-03 1.38 E-02 900917 to 900924 *-7 07 E-04 1.35 E-02 (a) Sampler malfunction; shortened sampling time.
  • Denotes a result less than the detection limit.

A-60

TABLE A-4.1 (cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 900924 to 901001

  • 8.47 E-03 1.13 E-02 901001 to =901008 *-7.33 E-02 1.15 E-01 901008 to,901015 *-4.25 E-03 1.58 E-02 901015 to 901022 *-5.99 E-03 1.28 E-02 901022 to 901029
  • 1.11 E-02 1.19 E-02 901029 to 901105 *-4.65 E-02
  • 1.22 E-02 901105 to 901112 *-1. 13 E-02 1.24 E-02 901112 to 901119 *-6.22 E-03 1.46 E-02 901119 to 901126 *-1. 03 E-02 1.33 E-02 901126 to 901203
  • 4.28 E-03 1.59 E-02 901203 to 901210 *-1. 53 E-04 1.48 E-02 901210 to 901217 *-4.35 E-03 1.31 E-02 901217 to 901226
  • 0.00 E+00 1.31 E-02
  • Denotes a result less than the detection limit.

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 891227 to 900102

  • 5.57 E-03 1.01 E-02 900102 to 900108
  • 0.00 E+00 3.01 E-02 900108 to 900115
  • 9.56 E-04 1.40 E-02 900115 to 900122 *-1.73 E-03 9.24 E-03 900122 to 900129 *-2.58 E-03 9.92 E-03 900129 to 900205 *-1.51 E-03 7.95 E-03 900205 to 900212 *-2.98 E-03 1.38 E-02 900212 to 900220 *-5 47 E-04 7.31 E-03 900220 to 900226
  • 9.22 E-03 1.54 E-02 900226 to 900305
  • 2.21 E-03 8.76 E-03 900305 to 900312
  • 1.34 E-02 1.37 E-02 900312 to 900319
  • 2.92 E-03 9.28 E-03 900319 to 900326
  • 2.41 E-03 8.59 E-03 900326 to 900402
  • 6.69 E-03 9.58 E-03 900402 to 900409
  • 3.77 E-04 8.34 E-03 900409 to 900416 *-2.19 E-03 8.88 E-03 900416 to 900423 *-6.08 E-03 8.02 E-03 900423 to 900430 *-4.91 E-03 7.65 E-03 900430 to 900507
  • 1.24 E-03 7.16 E-03 900507 to 900514 <b) *-1.44 E-04 9.08 E-03 900514 to 900521
  • 5.78 E-03 9.87 E-03 900521 to 900529 (a)
  • 2.11 E-03 9.59 E-03 900529 to 900604 *-4.19 E-03 1.04 E-02 900604 to 900611 *-4 15 E-03 7.37 E-03 900611 to 900618 *-7.18 E-03 1.22 E-02 900618 to 900625 *-8.67 E-04 9.12 E-03 900625 to 900702 *-1.20 E-03 1.27 E-02 900702 to 900709
  • 6.95 E-03 7.97 E-03 900709 to 900716 *-3.58 E-04 9.55 E-03 900716 to 900723 (a) *-1.36 E-03 9.27 E-03 900723 to 900730 (a)
  • 1.12 E-03 1.14 E-02 900730 to 900806 *-6.36 E-04 8.58 E-03 900806 to 900813
  • 1.42 E-03 7.45 E-03

'00813.to 900820

  • 1.65 E-03 8.25 E-03 900820 to 900827
  • 3.70 E-03 1.07 E-02 900827 to 900904
  • 2.17 E-03 1.10 E-02 900904 to 900911 *-6 74 E-03 9.51 E-03 900911 to 900917 *-2.68 E-03 1.38 E-02 900917 to 900924 *-7.11 E-04 1.36 E-02 (a) Sampler malfunction; shortened sampling time.

(b) Power outage: shortened sampling time.

  • Denotes a result less than the detection limit.

A-62

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 900924 to 901001

  • 8.52 E-03 1.14 E-02 901001 to 901008 *-7.83 E-03 1.23 E-02 901008 to 901015 *-4.26 E-03 1.59 E-02 901015 to 901022 *-6.03 E-03 1.29 E-02 901022 to 901029
  • 1.03 E-02 1.10 E-02 901029 to 901105 *-4.67 E-03 1.22 E-02 901105 to 901112 *-1.13 E-02 1.24 E-02 901112 to 901119 *-6.30 E-03 1.48 E-02 901119 to 901126 *-1.03 E-02 1.34 E-02 901126 to 901203
  • 4.32 E-03 1.61 E-02 901203 to 901210 *-1. 58 E-04 1. 53 E-02 901210 to 901217 *-4.38 E-03 1.31 E-02 901217 to 901226
  • 0.00 E+00 1.32 E-02
  • Denotes a result less than the detection limit.

A-63

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 21 891227 to 900102

  • 5.60 E-03 1.02 E-02 900102 to 900108
  • 0.00 E+00 3.06 E-02 900108 to 900115
  • 9.65 E-04 1.42 E-02 900115 to 900122 *-1 75 E-03 9.32 E-03 900122 to 900129 *-2 60 E-03 1.00 E-02 900129 to 900205 *-1 53 E-03 8.03 E-03 900205 to 900212 (a) *-3 18 E-03 1.47 E-02 900212 to 900220 *-5 54 E-04 7.41 E-03 900220 to 900226
  • 9.33 E-03 1.55 E-02 900226 to 900305
  • 2.22 E-03 8.82 E-03 900305 to 900312
  • 1.36 E-02 1.38 E-02 900312 to 900319
  • 2.96 E-03 9.39 E-03 900319 to 900326
  • 2.45 E-03 8.75 E-03 900326 to 900402
  • 6.73 E-03 9.63 E-03 900402 to 900409
  • 3.82 E-04 8.46 E-03 900409 to 900416 *-2 21 E-03 8.98 E-03 900416 to 900423 *-6.11 E-03 8.07 E-03 900423 to 900430 *-4 97 E-03 7.75 E-03 900430 to 900507
  • 1.26 E-03 7.24 E-03 900507 to 900514 *-1 39 E-04 8.80 E-03 900514 to 900521
  • 5.88 E-03 1.00 E-02 900521 to 900529
  • 1.30 E-03 5.92 E-03 900529 to 900604 *-4.20 E-03 1.04 E-02 900604 to 900611
  • 4 20 E-03 7.46 E-03 900611 to 900618 *-7 18 E-03 1.22 E-02 900618 to 900625 *-8 73 E-04 9.18 E-03 900625 to 900702 *-1 21 E-03 1.28 E-02 900702 to 900709
  • 7.05 E-03 8.09 E-03 900709 to 900716 *-3 61 E-04 9.64 E-03 900716 to 900723 *-1.37 E-03 9.32 E-03 900723 to 900730
  • 9.78 E-04 9.96 E-03 900730 to 900806 *-6.42 E-04 8.67 E-03 900806 to 900813
  • 1 43 E-03 7.50 E-03 900813 to 900820
  • 1.67 E-03 8.35 E-03 900820 to 900827
  • 3.75 E-03 1.08 E-02 900827 to 900904
  • 2.19 E-03 1.11 E-02 900904 to 900911 *-6 75 E-03 9.52 E-03 900911 to 900917 *-2 72 E-03 1.41 E-02 900917 to 900924 *-7.15 E-04 1.37 E-02 (a) Power outage; shortened sampling time.
  • Denotes a result less than the detection limit.

A-64

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 21 900924 to 901001

  • 8;62 E-03 1.16 E-02 901001 to 901008 *-7.94 E-03. 1.25 E-02 901008 to 901015 *-4.30 E-03 1.60 E-02 901015 to 901022 *-6.06 E-03 1.30 E-02 901022 to 901029 ~ 1.04 E-02 1.11 E-02 901029 to 901105 ~-4.70 E-03 1.23 E-02 901105 to 901112 "-1.14 E-02 1.26 E-02 901112 to 901119 *-6.35 E-03 1.49 E-02 901119 to 901126 *-1.04 E-02 1.35 E-02 901126 to 901203
  • 4.36 E-03 1.62 E-02 901203 to 901210 *-1. 54 E-04 1.50 E-02 901210 to 901217 *-4.42 E-03 1.33 E-02 901217 to 901226
  • 0.00 E+00 1.32 E-02
  • Denotes a result less than the detection limit.

A-65

TABLE A-4.1 (Cont,)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 23 891227 to 900102

  • 5.60 E-03 1.01 E-02 900102 to 900108
  • 0.00 E+00 3.06 E-02 900108 to 900115
  • 9.64 E-04 1.41 E-02 900115 to 900122 *-1 75 E-03 9.32 E-03 900122 to 900129 *-2.60 E-03 1.00 E-02 900129 to 900205 *-1.53 E-03 8.05 E-03 900205 to 900212 *-3.01 E-03 1.39 E-02 900212 to 900220 *-5 54 E-04 7.40 E-03 900220 to 900226
  • 9.32 E-03 1.55 E-02 900226 to 900305
  • 2.22 E-03 8.82 E-03 900305 to 900312
  • 1.36 E-02 1.38 E-02 900312 to 900319 (a)
  • 2.99 E-03 9.49 E-03 900319 to 900326
  • 2.45 E-03 8.73 E-03 900326 to 900402
  • 6.72 E-03 9.63 E-03 900402 to 900409
  • 3.82 E-04 8.45 E-03 900409 to 900416 *-2.21 E-03 8.97 E-03 900416 to 900423 *-6.08 E-03 8.02 E-03

'00423 to 900430 *-4 97 E-03 7.74 E-03 900430 to 900507

  • 1.25 E-03 7.22 E-03 900507 to 900514 *-1 40 E-04 8.82 E-03 900514 to 900521
  • 5.85 E-03 9.98 E-03 900521 to 900529
  • 1.30 E-03 5.92 E-03 900529 to 900604 *-4.19 E-03 1.04 E-02 900604 to 900611 *-4 20 E-03 7.46 E-03 900611 to 900618 *-7 17 E-03 1.22 E-02 900618 to 900625 *-8.72 E-04 9.18 E-03 900625 to 900702 *-1.21 E-03 1.28 E-02 900702 to 900709
  • 7.05 E-03 8.08 E-03 900709 to 900716 *-3.61 E-04 9.64 E-03 900716 to 900723 *-1 37 E-03 9.31 E-03 900723 to 900730
  • 9.77 E-04 9.95 E-03 900730 to 900806 *-6 41 E-04 8.64 E-03 900806 to 900813
  • 1.43 E-03 7.50 E-03 900813 to 900820
  • 1.67 E-03 8.34 E-03 900820 to 900827
  • 3.75 E-03 1.08 E-02 900827 to 900904
  • 2.19 E-03 1.11 E-02 900904 to 900910 *-6.75 E-03 9.52 E-03

, 900910 to 900917 *-2.72 E-03 1.40 E-02 900917 to 900924 *-7 15 E-04 1.37 E-02 (a) Sampler malfunction; shortened sampling time.

  • Oenotes a result less than the detection limit.

A-66

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 23 900924 to 901001

  • 8.61 E-03 1.15 E-02 901001 to 901008 *-2.62 E-02 4.12 E-02 901008 to 901015 (a) *-4.29 E-03 1.60 E-02 901015 to 901022 *-6.06 E-03 1.30 E-02 901022 to 901029
  • 1.04 E-02 1.12 E-02 901029 to 901105 *-4.70 E-03 1.23 E-02 901105 to 901112 *-1. 14 E-02 1.25 E-02 901112 to 901119 *-6.34 E-03 1.49 E-02 901119 to 901126 *-1. 04 E-02 1.35 E-02 901126 to 901203
  • 4.36 E-03 1.62 E-02 901203 to 901210 *-1. 54 E-04 1.49 E-02 901210 to 901217 *-4.43 E-03 1.33 E-02 901217 to 901226
  • 0.00 E+00 1.32 E-02 (a) Shortened sampling time; results not included in average.
  • Denotes a result less than the detection limit.

A-67

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 40 891227 to 900102

  • 4.61 E-03 8.35 E-03 900102 to 900108
  • 0.00 E+00 1.72 E-02 900108 to 900115
  • 5.45 E-04 7.99 E-03 900115 to 900122 *-1 43 E-03 7.63 E-03 900122 to 900129 *-2.13 E-03 8.19 E-03 900129 to 900205 *-1.06 E-03 5.56 E-03 900205 to 900212 *-1.68 E-03 7.77 E-03 900212 to 900220 +-4.53 E-04 6.06 E-03 900220 to 900226
  • 7.62 E-03 1.27 E-02 900226 to 900305
  • 1.82 E-03 7.24 E-03 900305 to 900312
  • 7.66 E-03 7.80 E-03 900312 to 900319
  • 2.41 E-03 7.66 E-03 900319 to 900326
  • 1.99 E-03 7.12 E-03 900326 to 900402
  • 5.52 E-03 7.90 E-03 900402 to 900409
  • 3.12 E-04 6.89 E-03 900409 to 900416 *-1.81 E-03 7.33 E-03 900416 to 900423 *-4.25 E-03 5.61 E-03 900423 to 900430 (a) *-3 76 E-03 5.86 E-03 900430 to 900507
  • 8.68 .,E-04 5.01 E-03 900507 to 900514 *-1.15 E-04 7.24 E-03 900514 to 900521
  • 4.84 E-03 8.26 E-03 900521 to 900529
  • 9.03 E-04 4.11 E-03 900529 to 900604 *-3 42 E-03 8.49 E-03 900604 to 900611 (b) *-3.83 E-03 6.81 E-03 900611 to 900618 *-4.05 E-03 6.87 E-03 900618 to 900625 *-7.14 E-04 7.52 E-03 900625 to 900702 *-6.83 E-04 7.22 E-03 900702 to 900709
  • 4.86 E-03 5.57 E-03 900709 to 900716 *-2.89 E-04 7.74 E-03 900716 to 900723 *-1 13 E-03 7.68 E-03 900723 to 900730
  • 6.80 E-04 6.93 E-03 900730 to 900806 *-5.25 E-04 7.08 E-03 900806 to 900813
  • 9.96 E-04 5.21 E-03 900813 to 900820
  • 1.36 E-03 6.81 E-03 900820 to 900827
  • 3.11 E-03 8.94 E-03 900827 to 900904
  • 1.23 E-03 6.24 E-03 900904 to 900911 *-4.72 E-03 6. 66. E-03 900911 to 900917 *-1.54 E-03 7.92 E-03 900917 to 900924 *-5.88 E-04 1.12 E-02 e (a) Brief power outage; shor tened sampling time.

(b) Sampler malfunction; shortened sampling time.

  • Denotes a result less than the detection limit.

A-68

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 40 900924 to 901001

  • 5.96 E-03 7.99 E-03 901001 to 901008 *-7.03 E-03 1.11 E-02 901008 to 901015 *-3.09 E-03 1.15 E-02 901015 to 901022 *-4.38 E-.03 9.37 E-03 901022 to 901029
  • 7.19 E-03 7.69 E-03 901029 to 901105 *-2.56 E-03 6.70 E-03 901105 to 901112 *-9.22 E-03 1.01 E-02 901112 to 901119 *-5.24 E-03 1.23 E-02 901119 to 901126 (a) *-9.54 E-03 1.23 E-02 901126 to 901203 (a)
  • 2.21 E-02 8.22 E-02 901203 to 901210 (a) *-1.48 E-04 1.44 E-02 901210 to 901217 *-3.57 E-03 1.07 E-02 901217 to 901226
  • 0.00 E+00 9.21 E-03 (a) Sampler malfunction; shortened sampling time.
  • Denotes a result less than the detection limit.

A-69

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 48 891227 to 900102

  • 6.62 E-03 1.14 E-02 900102 to 900108 *-1.40 E-02 3.72 E-02 900108 to 900115
  • 1.05 E-02 1.49 E-02 900115 to 900122
  • 1.72 E-03 7.83 E-03 900122 to 900129 *-1.75 E-03 8.26 E-03 900129 to 900205
  • 1.15 E-02 1.42 E-02 900205 to 900212
  • 3.48 E-03 9.02 E-03 900212 to 900220
  • 2.15 E-03 6.03 E-03

. 900220 to 900226

  • 5.12 E-04 2.27 E-02 900226 to 900305
  • 3.55 E-03 1.53 E-02 900306 to 900312 (a)
  • 8.34 E-03 1.10 E-02 900312 to 900319
  • 5.24 E-03 7.51 E-03 900319 to 900326
  • 1.38 E-03 9.64 E-03 900326 to 900402 *-6 54 E-04 7.84 E-03 900402 to 900409
  • 1.04 E-03 5.08 E-03 900409 to 900416
  • 6.22 E-04 1.30 E-02 900416 to 900423 (a)
  • 1.30 E-02 1.34 E-02 900423 to 900430
  • 6.40 E-04 1.28 E-02 900430 to 900507
  • 6.80 E-03 1.23 E-02 900507 to 900514 *-2.18 E-04 7.23 E-03 900514 to 900521 *-4 90 E-04 8.50 E-03 900521 to 900529
  • 4.86 E-03 1.03 E-02 900529 to 900604 *-1.69 E-03 9.22 E-03 900604 to 900611 *-6.88 E-03 1.23 E-02 900611 to 900618
  • 5 54 E-03 7.69 E-03 900618 to 900625
  • 4.48 E-03 1.40 E-02 900625 to 900702 *-4.86 E-03 8.88 E-03 900702 to 900709 *-6.41 E-03 1.34 E-02 900709 to 900716 *-2.47 E-03 7.71 E-03

.900716 to 900723 *-1.87 E-03 7.60 E-03 900723 to 900730 *-8.95 E-03 1.75 E-02 900730 to 900806

  • 2.12 E-03 7.20 E-03 900806 to 900813 *-5.08 E-03 1.07 E-02 900813 to 900820 *-1 03 E-03 7.02 E-03 900820 to 900827 *-3.25 E-03 1.36 E-02 900827 to 900904
  • 2.51 E-03 1.62 E-02 900904 to 900910 *-2.88 E-03 1.60 E-02 900910 to 900917
  • 4.10 E-03 9.09 E-03 900917 to 900924
  • 1.72 E-03 1.09 E-02 (a) Sampler malfunction; shortened sampling time.
  • Denotes a result less than the detection limit.

A-70

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 48 900924 to 901001

  • 2.50 E-03 2.08 E-02 901001 to 901008
  • 1.26 f-02 1.90 E-02 901008 to 901015 "-8.02 E-03 1.60 E-02 901015 to 901022 *-2.68 E-03 1.47 E-02 901022 to 901029 *-1.16 E-03 1.46 E-02 901029 to 901105 *-5.99 E-03 1.09 E-02 901105 to 901112
  • 1.46 E-04 1.04 E-02 901112 to 901119 *-1. 15 E-02 1.37 E-02 901119 to 901126
  • 7.72 E-03 1.02 E-02 901126 to 901203
  • 1.06 E-02 1.42 E-02 901203 to 901210 *-8.52 E-03 1.86 E-02 901210 to 901217 *-6.04 E-03 1.60 E-02 901217 to 901226 *-6.17 E-03 1.23 E-02
  • Denotes a result less than the detection limit.

TABLE A-4.1 (Cont.)

AR Results in pCi/cubic meter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 57 891227 to 900102

  • 6.70 E-03 1.15 E-02 900102 to 900108 *-1.44 E-02 3.81 E-02 900108 to 900115
  • 1.07 E-02 1.52 E-02 900115 to 900122
  • 1.76 E-03 7.97 E-03 900122 to 900129 *-1 78 E-03 8.40 E-03 900129 to 900205
  • 1.16 E-02 1.44 E-02 900205 to 900212
  • 3.59 E-03 9.29 E-03 900212 to 900220
  • 2.19 E-03 6.14 E-03 900220 to 900226
  • 5.27 E-04 2.34 E-02 900226 to 900305
  • 1.75 E-03 7.56 E-03 900305 to 900312
  • 7.48 E-03 9.86 E-03 900312 to 900319
  • 5.35 E-03 7.67 E-03 900319 to 900326
  • 1.41 E-03 9.86 E-03 900326 to 900402 *-6.63 E-04 7.94 E-03 900402 to 900409
  • 1.23 E-03 7. 23. E-03 900409 to 900416
  • 6.34 E-04 1.32 E-02 900416 to 900423
  • 1.31 E-02 1.36 E-02 900423 to 900430
  • 6.54 E-04 1.31 E-02 900430 to 900507
  • 6.95 E-03 1.26 E-02 900507 to 900514 *-2.21 E-04 7.34 E-03 900514 to 900521 *-5.02 E-04 8.70 E-03 900521 to 900529
  • 4.95 E-03 1.05 E-02 900529 to 900604 *-1.73 E-03 9.43 E-03 900604 to 900611 *-6.99 E-03 1.25 E-02 900611 to 900618
  • 5.63 E-03 7.82 E-03 900618 to 900625
  • 4.56 E-03 1.42 E-02 900625 to 900702 *-4 97 E-03 9.07 E-03 900702 to 900709 *-6.54 E-03 1.37 E-02 900709 to 900716 *-2.56 E-03 8.00 E-03 900716 to 900723 *-1.89 E-03 7.68 E-03 900?23 to 900730 *-9.06 E-03 1.77 E-02 900730 to 900806
  • 2.15 E-03 7.33 E-03 900806 to 900813 *-5.14 E-03 1.08 E-02 900813 to 900820 *-1.05 E-03 7.18 E-03 900820 to 900827 *-3.31 E-03 1.38 E-02 900827 to 900904
  • 2.57 E-03 1.65 E-02 900904 to 900910 *-2.91 E-03 1.61 E-02 900910 to 900917
  • 4.18 E-03 9.27 E-03 900917 to 900924
  • 1.74 E-03 1.10 E-02
  • Denotes a result less than the detection limit.

A"72

TABLE A-4.1 (Cont.)

Results in pCi/cubic meter I

COLLECTION OVERALL LOCATION PERIOO RESULT UNCERTAINTY 57 900924 to 901001

  • 2.34 E-03 1.95 E-02 901001 to 901008
  • 1.29 E-02 1.95 E-02 901008 to 901015 *-8.12 E-03 1.62 E-02 901015 to 901022 *-2.68 E-03 1.46 E-02 901022 to 901029 *-1.19 E-03 1.49 E-02 901029 to 901105 *-6.07 E-03 1.11 E-02 901105 to 901112
  • 1.49 E-04 1.06 E-02 901112 to 901119 "'-9.92 E-03 1.18 E-02 901119 to 901126
  • 7.84 E-03 1.03 E-02 901126 to 901203
  • 1.08 E-02 1.45 E-02 901203 to 901210 *-8.64 E-03 1.89 E-02 901210 to 901217 *-6.15 E-03 1.63 E-02 901217 to 901226 *-6.20 E-03 1.23 E-02
  • Denotes a result less than the detection limit.

TABLE A-4.2 Results in pCi/cubic meter NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POS ITIVE 1-131 ( I) 1. 06E-02 -7.33E-02 6. 18E+00 572 I-131 (C) -2.87E-04 -1.13E-02 1. 34E-02 52

( I) Indicator Stations (C) Control Station

TABLE A-5.1 Results in pCi/liter COLLECTION OVERALL LOCATION PERI00 RESULT UNCERTAINTY 26 891213 to 900110 (a) 3.8 E+00 9.0 E-01 900110 to 900213 9.0 E-01 6.5 E-01 900213 to 900313 1.5 E+00 7.0 E-01 900313 to 900418 1.6 '+00 7.0 E-01 900418 to 900516 1.5 E+00 7.0 E-01 900516 to 900613 1.0 E+00 7.0 E-01 900613 to 900702 (a) 1.7 E+00 9.0 E-01 900702 to 900815 (a) E+00 1.0 E+00 900815 to 900912 6.5 E-Ol 6.0 E-01 900912 to 9Q1010 1.5 E+00  ?.0 E-01 901010 to 901107 1.3 E+00 6.0 E-01 901107 to 901205 1.5 E+00 7.0 E-01 891213 to 900110 2.2 E+00 7.0 E-01 90Q110 to 900213 6.4 E-01 6.2 E-01 900213 to 900313 1.5 '+OQ 7.0 E-01 900313 to 900418 2.2 E+00 7.0 E-01 900418 to 900516 1.8 E+00 7.0 E-01 900516 to 900613 2.6 E+00 8.0 E-01 900613 to 900710 1.9 E+00 9.0 E-01 900710 to 900815 1.7 E+QO 8.Q E-01 900815 to 900912 1.3 E+00 7.0 E-01 900912 to 901010 2.0 E+00 7.0 E-01 901010 to 901107 2.1 E+00 7.0 E-Ol 901107 to 901205 9.4 E-01 6.7 E-01 29 891213 to 900110 1.8 E+00 7.0 E-Ol 900110 to 900213 1.6 E+00 7.0 E-01 900213 to 900313 2.9 E+00 8.0 E-01 900313 to 900418 2.0 E+00 7.0 E-01 900418 to 900516 1.? E+00 7.0 E-01 900516 to 900613 1.4 E+00 7.0 E-01 900613 to 900711 8.1 E-01 8.1 E-01 900710 to 900815 9.5 E-Ol 7.1 E-01 900815 to 900912 2.0 E+00 7.0 E-01 90091Z to 901010 1.7 E+00 7.0 E-01 901010 to 901107 2.2 f+00 7.0 E-01 901107 to 901205 1.8 E+00 8.0 E-01 (a) Sampler not operational during part of the period.

  • Denotes a result less than the detection limit.

TABLE A-5.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 27 891213 to 900110 3. 5 E+01 3.0 E+00 900110'o 900213 (a) 1.4 E+01 2.0 E+00 900213 to 900313 (a) 1. 3 E+01 2.0 E+00 900313 to 900418 (a) 1. 4 E+01 2.0 E+00 900418 to 900516 (a) 1. 2 E+01 2.0 E+00 900516 to 900613 (a) 6. 1 E+00 1. 1 E+00 900613 to 900710 1.1 E+01 1. 0 E+00 900710 to 900807 (a) 7.0 E+00 1. 2 E+00 900815 to 900912 (a) 1.7 E+01 2.0 E+00 900912 to 901010 2.4 E+Ol 3.0 E+00 901010 to 901107 2.0 E+01 2.0 E+00 901107 to 901205 (a) 1. 6 E+01 2.0 .E+00 (a) Sampler not operational during part of the period.

  • Denotes a result less than the detection limit.

TABLE A-5.2 Results in pCi/liter NUMBER NUMBER NUCLIOE AVERAGE LOM HIGH SAMPLES POSITIVE Gr-Beta ( I) 1.74E+00 6.40E-01 2.90E+00 24 20 Gr-Beta (C) 1.78E+00 6. 50E-01 4.40E+00 12 10 (a)

Gr-Beta (I) 1.58E+01 6. 10E+00 3.50E+Ol 12 12 (a) Duplicate station 72 not included in averages.

(I) Indicator Stations (C) Control Station A-77

TABLE A-6.1

~ Qs Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY 26 891213 to 900313 (b)

  • 1.3 E+02 9. 2 E+01 900313 to 900613
  • 1.3 E+00 8. 0 E+02 900613 to 900912
  • 3.8 E+01 1. 4 E+02 900912 to 901205 *-5.5 E+00 7. 3 E+01 28 891213 to 900313 2.4 E+02 1. 3 E+02 900313 to 900613
  • 1.1 E+01 8. 7 E+01 900613 to 900912 2.5 E+02 8. 0 E+01 900912 to 901205 (b) *-5.1 E+01 1. 3 E+02 29 891213 to 900313
  • 4.5 E+Ol 9. 3 E+01 900313 to 900613
  • 1.1 E+02 1. 1 E+02 900613 to 900912 1.4 E+02 7. 0 E+01 900912 to 901205
  • 1.1 E+02 1. 2 E+02 27 891213 to 900313 (b)
  • 5.5 E+01 1. 2 E+02 900313 to 900613 (a ) (b) 3. 4 E+03 1. 0 E+02 900613 to 900912 (b) 2.0 E+03 1. 0 E+02 900912 to 901205 (b) 1.3 E+02 7. 0 E+01 (a) Confirmed by recount.

(b) Sampler not operational during part of this period.

  • Oenotes a result less than the detection limit.

A-78

TABLE A-6.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD RESULT UNCERTAINTY EiLkllEi 31 900313

  • 1.6 E+01 1. 2 E+02 (Well 1) 900614 *-1. 9 E+00 1.0 E+02 900912
  • 1.5 E+02 1.2 "E+02 901205 *-1. 7 E+01 8. 4 E+01 32 900313 *-6. 7 E+01 8. 3 E+01 (Well 2) 900614 *- 5. 3 E+01 1. 5 E+02 900912 ",-1. 0 E+02 9. 0 E+01 901205
  • 2.8 E+Ol 1. 5 E+02 33 900313
  • 7.0 E+01 1. 0 E+02 (Well 3) 900613 *-3. 2 E+01 7.7 E+01 900912 3.1 E+01 9.0 E+01 901205 2. 2 E+02 1. 1 E+02
  • Denotes a result less than the detection limit.

A-79

TABLE A-6.2 Results in pCi/liter NUMBER NUMBER NUCLIOE AVERAGE LOW HIGH SAMPLES POSITIVE H-3 (I) 1. 07E+02 - 5. 10 E+01 2.50E+02 H-3 (C) 4. 10E+01 -5.50E+00 1.30E+02 (a)

H-3 ( I) 1.40E+03 5.50E+01 3. 40E+03 H-3 ( I) 2. 03E+01 -1. OOE+02 2.20E+02 12

( a) Duplicate station 72 not included in averages.

( I) Indicator Stations (C) Control Station A-80

TABLE A-7.1 Results in pCi/liter COLLECTION OVERALL LOCATION PERIOO NUCLIDE RESULT UNCERTAINTY 26 891213 to 900110 (a) Be-7 *-3.96 E+00 1.66 E+01 K-40

  • 9.31 E+Ol 2.29 E+Ol Mn-54
  • 9.35 E-02 1.58 E+00 Co-58 *-1.15 E+00 1.70 E+00 Fe-59
  • 9.91 E-01 3.62 E+00 Co-60 *-8.46 E-01 1.67 E+00 Zn-65
  • 1.70 E+00 3.74 E+00 Zr-95
  • 5.68 E+00 3.73 E+00 Nb-95
  • 2.32 E+00 1.84 E+00 Cs-134 *-5.01 E-01 1.73 E+00 Cs-137 *-2.17 E-01 1.89 E+00 Ba -140 *-3 04 E+00 7.45 E+00 La-140 *-7.74 E-01 3.46 E+00 Ra-226
  • 1.08 E+01 3.00 E+00 900110 to 900213 Be-7 *-3.50 E+00 1.81 E+01 K-40 *-1.42 E+01 2.29 E+01 Nn-54
  • 1.19 E+00 1.76 E+00 Co-58
  • 8.21 E-01 1.99 E+00 Fe-59 *-3.58 E+00 4.46 E+00 Co-60
  • 1.09 E+00 2.00 E+00 Zn-65 *-8.00 E-01 4.36 E+00 Zr-95 *-2.42 E+00 4.11 E+00 Nb-95
  • 0.00 E+00 2.06 E+00 Cs-134 *-1.41 E+00 2.13 E+00 Cs-137
  • 1.18 E-Ol 1.97 E+00 Ba -140 *-1 54 E+00 8.90 E+00 La-140
  • 2.00 E+00 3.03 E+00 (a) Sampler not operational during part of this period,
  • Oenotes a result less than the detection limit.

TABLE A-7.1 (Cont.)

COLLECTION Results in pCitliter OVERALL

~ o LOCATION PER IOD NUCLIDE RESULT UNCERTAINTY 26 900213 to 900313 Be-7

  • 0.00 E+00 1.71 E+01 K-40 *-5 92 E+00 2.34 E+01 Mn-54
  • 2.96 E-01 1.58 E+00 Co-58
  • 1.05 E-01 1.71 E+00 Fe-59
  • 2.86 E+00 3.87 E+00 Co-60
  • 1.33 E+00 1.73 E+00 Zn-65 *-3 69 E+00 3.65 E+00 ZI -95
  • 3.29 E+00 3.59 E+00 Nb-95
  • 2.00 E-01 1.70 E+00 Cs-134 *-5.29 E-01 1.76 E+00 Cs-137
  • 2.30 E-01 1.81 E+00 Ba-140
  • 7.49 E+00 7.91 E+00 La-140 *-1 61 E-01 3.55 E+00 Ra-226 *-3 82 E+01 3.89 E+01
  • 3.59 900313 to 900418 Th-228 Be-7
  • 6.92 E+00 E+00 3.24 1.70 E+00 E+01

~ o K-40 *-3 03 E+Ol 2.40 E+01 Mn-54

  • 2.17 E-01 1.69 E+00 Co-58
  • 6.08 E-01 1.77 E+00 Fe-59
  • 3.17 E+00 3.75 E+00 Co-60 *-1.10 E+00 1.79 E+00 Zn-65 *-1.69 E+00 4.08 E+00 Zr-95
  • 6 97 E-01 3.93 E+00 Nb-95
  • 2.88 E-01 1.83 E+00 Cs-134
  • 6.76 E-02 1.82 E+00 Ba-140 *-6 89 E+00 6.88 E+00 La-140 *-3 23 E+00 3.32 E+00 Ra-226
  • 1.03 E+01 3.97 E+01 Th-228 *-2.93 E+00 3.32 E+00
  • Denotes a result less than the detection limit.

A-82

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 26 900418 to 900516 Be-7 *-5.45 E+00 1.68 E+01 K-40

  • 3.43 E+01 2.42 E+01 Mn-54
  • 1.82 E+00 1.68 E+00 Co-58 *-6.77 E-01 1.69 E+00 Fe-59
  • 2.30 E+00 3.80 E+00 Co-60
  • 3.68 E-01 1.83 E+00 Zn-65 *-3.81 E-01 3.57 E+00 Zr-95
  • 7.66 E-01 3.58 E+00 Nb-95
  • 6.91 E;01 1.79 E+00 Cs-134
  • 2.40 E+00 1.82 E+00 Ba-140 *-2.89 E+00 7.26 E+00 La -140 *-1 67 E+00 2.94 E+00 Ra-226 *-6.38 E+01 3.88 E+01 Th-228 *-2.50 E+00 3.25 E+00 900516 to 900613 (a) Be-7 *-3 13 E+00 1.63 E+01 K-40
  • 2.91 E+00 2.26 E+Ol Nn-54
  • 2.33 E-01 1.50 E+00 Co-58
  • 8.94 E-01 1.68 E+00 Fe-59
  • 2.42 E-Ol 3.64 E+00 Co-60
  • 4.11 E-Ol 1.78 E+00 Zn-65 *-3.69 E+00 3.61 E+00 Zr-95
  • 8.27 E-01 3.40 E+00 Nb-95
  • 1.18 E+00 1.66 E+00 Cs-134
  • 8.79 E-01 1.80 E+00 Ba-140
  • 3.55 E+00 7.63 E+00 La -140
  • 2.93 E-01 3.42 E+00 Ra-226 *-1.75 E+Ol 4.02 E+Ol Th-228 *-3 34 E+00 3.22 E+00 (a) Sampler not operational during part of this period.
  • Denotes a result less than the detection limit.

A-83

TABLE A-7.1 (Cont.)

COLLECTION Results in pCi/liter OVERALL

~ o LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 26 900613 to 900702 (a) Be-7 *-4.49 E+00 1.95 E+Ol K-40

  • 2.65 E+00 2.65 E+01 Mn-54
  • 6.54 E-01 1.94 E+00 Co-58 *-1 95 E+00 1.96 E+00 Fe-59 *-3 70 E-Ol 4.25 E+00 Co-60
  • 1.95 E-01 2.21 E+00 Zn-65 *-1.19 E+00 4.44 E+00 Zr-95 *-3.20 E+00 4.28 E+00 Nb-95
  • 1.93 E+00 2.22 E+00 Cs-134 *-6 97 E-02 1.95 E+00 Cs-137
  • 5.51 E-01 2.18 E+00 Ba -140 *-2.02 E+00 1.10 E+Ol La-140 *-2.51 E+00 5.23 E+00 Ra-226 *-1 44 E+01 4.07 E+01 Th-228 *-4 89 E+00 3.52 E+00 900710 to 900815 Be-7
  • 1.22 E+01 1.73 E+O1 K-40
  • 9 49 E-01 2.47 E+01 Mn-54
  • 8.30 E-01 1.94 E+00 Co-58 *-3.35 E-01 1.98 E+00 Fe-59
  • 4 03 E+00 4.33 E+00 Co-60
  • 8.42 E-01 2.15 E+00 Zn-65
  • 3.25 E-01 4.07 E+00 Zr-95 *149 E+00 3.83 E+00 Nb-95 3.18 E-Ol 1.93 E+00 Cs-134 *-1.31 E+00 2.15 E+00 Cs-137
  • 1.58 E+00 2.15 E+00 Ba -140 *-6.00 E-01 7.53 E+00 La-140 *-1 79 E+00 3.66 E+00 Ra-226
  • 7.85 E-01 3.16 E+00 (a) Sampler not operational during part of this period.
  • Denotes a result less than the detection limit.

A-84

TABLE A-?.1'(Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 26 900815 to 900912 Be-7

  • 3.93 E-01 2.64 E+01 K-40 *-1.41 E+02 4.10 E+01 Nn-54
  • 5.05 E-01 2.35 E+00 Co-58 *-6.16 E-01 2.64 E+00 Fe-59
  • 3.08 E-Ol 5.40 E+00 Co-60
  • 2.21 E+00 2.52 E+00 Zn-65
  • 1.01 E+00 5.30 E+00 Zr-95
  • 2.75 E+00 5.29 E+00 Nb-95
  • 1 37 E+00 2.67 E+00 Cs-134
  • 4.24 E+00 2.75 E+00 Ba -140 *-1 90 E+01 1.40 E+01 La-140 *-2 4Q E+00 5.3? E+00
  • -1.02 Ra-226 Th-228 '-4 62 E+02 E+00 5.57 4.50 E+Ol E+00 900912 to 901010 Be-7
  • 1.55 E+00 2.17 E+01 K-40 *-8 63 E+00 3.00 E+01 Mn-54
  • 7 54 E-01 2.05 E+00 Co-58
  • 1.32 E+00 2.30 E+00 Fe-59
  • 1.04 E+00 4.92 E+00 Co-60
  • 1.68 E+00 2.37 E+00 Zn-65 *-2 34 E+00 4.58 E+00 Zr-95
  • 7.65 E-01 4.75 E+00 Nb-95
  • 0.00 E+00 2.24 E+00 Cs-134
  • 9.65 E-01 2.21 E+00 Cs-137 * ] 40 E+00 2.39 E+00 Ba-140 *-6 37 E+00 1.19 E+01 LB -140
  • 2.86 E+00 4.09 E+00 Denotes a result less than the detection limit.

A"85

TABLE A-7.1 (Cont.)

Results in pCi/liter o COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 26 901010 to 901107 Be-7 *-3.52 E+00 1.52 E+01 K-40 *-4 50 E+Ol 2.26 E+01 Mn-54

  • 6.77 E-01 1.57 E+00 Co-58
  • 4 38 E-01 1.64 E+00 Fe-59 *-2.02 E+00 3.39 E+00 Co-60 *-2.75 E-01 1.74 E+00 Zn-65 *-4 78 E+00 3.65 E+00 Zr-95
  • 1.18 E+00 3.42 E+00 Nb-95
  • 1.55 E+00 1.74 E+00 Cs-134 *-1.21 E-01 1.82 E.+00 Cs-137 *-1.72 E-01 2.09 f+00 Ba-140 *-2 38 E+00 6.89 E+00 La-140 *-3.27 E+00 3.18 E+00 Ra-226 *-4 57 E+01 3.63 E+01 Th-228
  • 5.32 E+00 3.06 E+00 901107 to 901205 Be-7
  • 2.85 E+00 2.59 E+01 K-40 *-8.83 E+Ol 6.33 E+01 Mn-54
  • 1.24 E+00 2.70 E+00 Co-58 *-1 75 E+00 2.75 E+00 Fe-59
  • 3.26 E+00 5.86 E+00 Co-60
  • 9.13 E-02 2.90 E+00 Zn-65 *-4 42 E+00 6.45 E+00 Zr-95 *-4 79 F-01 5.75 E+00 Nb-95
  • 4.37 E+00 2.91 E+00 Cs-134 *-1.48 E+00 2.96 E+00 Cs-137
  • 4.38 E+00 2.93 E+00 Ba-140
  • 1.04 E+01 1.07 E+01 La-140 *-8.33 E-01 4.39 E+00 Ra-226
  • 2.69 E+00 4.76 E+00
  • Denotes a result less than the detection limit.

A-86

TABLE A-7.1 (Cont,)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 27 891213 to 900110 Be-7 *-3 81 E+00 1.79 E+Ol K-40

  • 1.34 E+02 2.61 E+01 Mn-54
  • 1.04 E+00 1.79 E+00 Co-58
  • 0.00 E+00 1.76 E+00 Fe-59
  • 2.72 E+00 4.03 E+00 Co-60 .
  • 1.15 E+00 1.90 E+00 Zn-65
  • 6.65 E-Ol 3.92 E+00 Zr-95
  • 0.00 E+00 3.69 E+00 Nb-95
  • 1.63 E+00 1.90 E+00 Cs-134
  • 7.25 E-01 1.87 E+00 Cs-137 *-1 46 E-01 1.81 E+00 Ba-140
  • 3.08 E+00 8.24 E+00 La -140
  • 1.10 E+01 3.41 E+00 900110 to 900213 (a) Be-7
  • 6.63 E+00 1.93 E+01 K-40 *-3.01 E+01 2.46 E+01 Mn-54 *-5.52 E-01 1.66 E+00 Co-58 *-4.12 E-01 1.75 E+00 Fe-59
  • 1.44 E-01 3.95 E+00 Co-60
  • 0.00 E+00 1.98 E+00 Zn-65 *-9.91 E-01 4.14 E+00 Zr-95
  • 8.70 E-01 3.88 E+00 Nb-95
  • 1.79 E+00 2.01 E+00 Cs-134 *-8.60 E-01 1.93 E+00 Cs-137 *-1.56 E-01 1.98 E+00 Ba-140
  • 1.91 E+00 8.30 E+00 La-140 *-3.53 E+00 3.70 E+00 Ra-226
  • 4.03 E+01 4.33 E+01 Th-228 *-3 37 E+00 3.57 E+00 (a) Sampler not operational during part of this per iod.
  • Denotes a result less than the detection limit.

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 27 900213 to 900313 (a) Be-7

  • 4.82 E+00 2.35 E+01 K-40 *-1.92 E+02 5.72 E+01 Mn-54
  • 1.68 E+00 2.42 E+00 Co-58 *-2.28 E+00 2.54 E+00 Fe-59
  • 1.98 E+00 5.74 E+00 Co-60
  • 1.48 E-01 2.59 E+00 Zn-65
  • 7.89 E+00 5.89 E+00 Zr-95 *-5 84 E+00 5.29 E+00 Nb-95
  • 8.78 E-01 2.65 E+00 Cs-134 *-5 47 E-02 2.67 E+00 Cs-137
  • 3.12 E+00 2.73 E+00 Ba-140 *-2.68 E+00 1.10 E+Ol La-140 *-3.20 E+00 4.55 E+00 Ra-226 *-6.63 E+01 4.80 E+01 Th-228 *-7 45 E+00 3.97 E+00 900313 to 900418 (a) Be-7
  • 5.13 E+00 2.04 E+01 K-40 *-1.47 E+Ol 2.87 E+01 Mn-54
  • 5.07 E-01 2.13 E+00 Co-58 *-3.80 E-Ol 2.01 E+00 Fe-59
  • 1.48 E+00 4.60 E+00 Co-60
  • 3.26 E-01 2.13 E+00 Zn-65 *-1.12 E+00 4.75 E+00 Zr-95
  • 0.00 E+00 4.16 E+00 Nb-95
  • 6.48 E-Ol 2.10 E+00 Cs-134
  • 2.31 E+00 2.33 E+00 Ba-140
  • 1.79 E+00 8.55 E+00 La -140 *-1.27 E+00 4.28 E+00 Ra-226
  • 4.16 E+01 4.78 E+Ol Th-228 *-7.73 E+00 3.95 E+00 (a) Sampler not operational during part of this period.
  • Denotes a result less than the detection limit.

A-88

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 27 900418 to 900516 (a) Be-7

  • 5 57 E+00 1.60 E+01 K-40
  • 1.21 E+01 2.16 E+01 Mn-54
  • 1.58 E-00 1.59 E+00 Co-58 *-4 93 E-01 1.56 E+00 Fe-59 *-3 59 E-01 3.29 E+00 Co-60
  • 3.42 E-01 1.76 E+00 Zn-65 *-2.73 E+00 3.55 E+00 Zr -95 *-6.38 E-01 3.25 E+00 Nb-95
  • 1.64 E+00 1.62 E+00 Cs-134
  • 1.93 E+00 1.83 E+00 Ba-140
  • 3 40 E+00 7.01 E+00 La-140
  • 4.08 E+00 3.25 E+00

. 900516 to 900613 (a) Be-7 "-1.10 E+Ol 1.76 E+01 K-40 *-4.76 E+01 2.48 E+01 Mn-54

  • 1.81 E+00 1.76 E+00 Co-58
  • 1.26 E+00 1.81 E+00 Fe-59
  • 0.00 E+00 .3 73 E+00 Co-60 8.60 E+00 3.38 E+00 Zn-65
  • 2.88 E+00 4.40 E+00 Z0-95 *-1.11 E+00 3.59 E+00 Nb-95
  • 1.26 E+00 2.02 E+00 Cs-134
  • 5.55 E+00 2.23 E+00 Ba-140
  • 1.57 E+00 7.92 E+00 La-140
  • 3.26 E-01 3.77 E+00 (a) Sampler not operational during part of this period.
  • Denotes a result less than the detection limit.

A-89

TABLE A-7.1 (Cont.)

Results in pCi/liter ~ o COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 27 900613 to 900710 Be-7 *-2.30 E+00 1.98 E+01 K-40

  • 1.53 E+Ol 2.88 E+01 Mn-54
  • 6.42 E-01 1.98 E+00 Co-58 *-7 44 E-01 2.16 E+00 Fe-59
  • 2.15 E+00 4.29 E+00 Co-60
  • 3.81 E+00 2.57 E+00 Zn-65 *-3.29 E+00 4.74 E+00 Zr-95
  • 1.92 E+00 4.19 E+00 Nb-95
  • 1.20 E+00 2.16 E+00 Cs-134
  • 2.50 E+00 2.39 E+00 Ba -140 *-6.36 E+00 8.11 E+00 La-140
  • 4.37 E+Ol 4.99 E+01 900710 Th-228 to 900807 (a) Be-7 K-40
  • 2.75
  • -2.95
  • -7 77 E+00 E+00 E+00 3.98 1.92 2.27 E+00 E+01 E+01

~ o Mn-54 *-5.21 E-01 1.78 E+00 Co-58

  • 1.17 E+00 2.05 E+00 Fe-59
  • 1.15 E+00 4.46 E+00 Co-60
  • 3.00 E+00 2.41 E+00 Zn-65 *-1.18 E+00 4.25 E+00 Zi -95
  • 3.63 E+00 4.42 E+00 Nb-95
  • 1.37 E+00 2.08 E+00 Cs-134
  • 1.94 E+00 2.01 E+00 Ba-140 *-1.04 E+01 1.19 E+01 La-140
  • 2.95 E-01 3.09 E+00 (a) Sampler not operational during part of this period.
  • Denotes a result less than the detection limits A-90

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 27 900815 to 900912 (a) Be-7 *-9.61 E+00 1.90 E+01 K-40 *-1.72 E-01 2.48 E+01 Mn-54

  • 1.49 E-01 1.72 E+00 Co-58
  • 7.35 E-01 1.95 E+00 Fe-59
  • 1.87 E+00 4.36 E+00 Co-60
  • 1.23 E+00 2.24 E+00 Zn-65
  • 2.52 E+00 4.04 E+00 Zr-95
  • 1.36 E+00 4.14 E+00 Nb-95
  • 1.17
  • 7 95 E+00 '.06 E+00 Cs-134 E-02 1.89 E+00 Cs-137
  • 1.03 E+00 1.97 E+00 Ba-140
  • 3.11 E+00 1.02 E+01 La-140 *-1.20 E+00 4.67 E+00 Ra-226 *-6 07 E+00 4.13 E+01 Th-228 *-4 64 E+00 3.50 E+00 900912 TO 901010 Be-7
  • 2.21 E+01 2.88 E+01 K-40 *-1 39 E-02 6.54 E+01 Mn-54
  • 1.73 E+00 2.88 E+00 Co-58 *-2 04 E+00 2.93 E+00 Fe-59
  • 1.05 E+00 6.80 E+00 Co-60 *-1 11 E+00 2.76 E+00 Zn-65 *-1 31 E+00 6.55 E+00 Zr-95 *-2 62 E-01 6.18 E+00 Nb-95
  • 2.02 E+00 3.08 E+00 Cs-134 *-2 74 E-01 3.01 E+00 Cs-137
  • 3.78 E+00 3.08 E+00 Ba-140 *108 E+01 1.53 E+01 La-140 *-4 70 E+00 6.59 E+00 Ra-226
  • 1.20 E+Ol 5.49 E+01 Th-228 *-9.12 E+00 4.67 E+00 (a) Sampler not operational during pact of this period.
  • Oenotes a result less than the detection limit.

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 27 901010 TO 901107 Be-7

  • 5.99 E+00 2.29 E+01 K-40 *-8.31 E+01 5.55 E+01 Mn-54 *-5.36 E-01 2.28 E+00 Co-58
  • 6.15 E-01 2.43 E+00 Fe-59
  • 1.15 E+00 5.26 E+00 Co-60 *-9.15 E-01 2.35 E+00 Zn-65 *-7 50 E+00 5.51 E+00 Zr-95
  • 5.00 E+00 5.09 E+00 Nb-95
  • 2.88 E+00 2.54 E+00 Cs-134 *-6 74 E-01 2.56 E+00 Cs-137
  • 2.45 E+00 2.49 E+00 Ba-140
  • 3.29 E+00 9.97 E+00 La =140 *-3.61 E+00 4.44 E+00 Ra-226 *-3 49 E+01 4.70 E+01 Th-228 *-2 49 E+00 4.02 E+00 901107 to 901205 (a) Be-7
  • 4.08 E+00 1. 80 E+Ol K-40
  • 2.60 E+01 2.56 E+01 Mn-54
  • 9.35 E-01 1.88 E+00 Co-58 *-1.95 E-01 2.00 E+00 Fe-59
  • 2.02 E+00 4.40 E+00 Co-60 *-4 58 E-01 2.32 E+00 Zn-65 *-2.85 E+00 4.48 E+00 Zr-95 *-9.60 E-01 3.77 E+00 Nb-95
  • 6.17 E-01 1.97 E+00 Cs-134 *-6.06 E-01 2.21 E+00 Cs-137
  • 1.78 E+00 2.12 E+00 Ba-140 *-2.80 E+00 7.16 E+00 La-140
  • 1.86 E+00 3.35 E+00 (a) Sampler not operational during part of this period.
  • Denotes a result less than the detection limit.

A-92

TABLE A-7.1 (cont.)

P Results in pCi/liter COLLECTION OVERALL LOCATION 'ERIOD NUCLIDE RESULT UNCERTAINTY 28 891213 to 900110 Be-7

  • 3.31 E+00 2.57 E+01 K-40
  • 2.82 E+02 3.65 E+01 Mn-54
  • 6.97 E-01 2.48 E+00 Co-58
  • 0.00 E+00 2.59 F+00 Fe-59
  • 9.13 E-01 5.39 E+00 Co-60
  • 4 5Q E+00 ,2.58 E+00 Zn-65 *-1.02 E+00 5.36 E+00 Zr-95
  • 2.55 E+00 5.74 E+00 Nb-95
  • 7.57 E-01 2.72 E+00 Cs-134
  • 7.46 E-01 2.78 E+00 Ba -140 *-1.14 E+01 1.20 E+01 La-140 *-1.12 E+00 4.84 E+00 Ra-226
  • 6.28 E+01 5.33 E+00 900110 to 900213 Be-7
  • 1.65 E+01 2.63 E+01 K-40 *-9 71 E+01 3.70 E+01 Mn-54 *-5.29 E-02 2.45 E+00 Co-58
  • 1.30 E+00 2.56 E+00 Fe-59
  • 3.32 E+00 5.66 E+00 Co-60
  • 5.41 E+00 2.84 E+00 Zn-65 *-1.22 E+00 5.35 E+00 Z0-95
  • 6.87 E+00 5.81 E+00 Nb-95
  • 6'.43 E-01 2.77 E+00 Cs-134
  • 2.38 E+00 2.88 E+00 Ba -140
  • 6.03 E+00 1.22 E+01 La-140 *-3 39 E+00 4.92 E+00 Ra-226 *-4 44 E+01 5.66 E+01 Th-228 *-1 79 E+01 5.40 E+00
  • Denotes a result less than the detection limit.

A-93

TABLE A-7.1 (Cont.)

COLLECTION Results in pCi/liter OVERALL

~ o LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY n

28 900213 to 900313 Be-1

  • 9 94 E+00 1.65 E+Ol K-40 *-2 67 E+01 2.43 E+01 Mn-54
  • 2.21 E-01 1.60 E+00 Co-58
  • 1.23 F+00 1.?5 E+00 Fe-59
  • 4.32 E-01 3.69 E+00 Co-60
  • 1.14 E+00 1.79 E+00 Zn-65
  • 3 53 E+00 3.61 E+00 Zr-95
  • 1.85 E+00 3.66 E+00 Nb-95
  • 2.57 E+00 1.81 E+00 Cs-134 *-5 33 E-01 1.71 E+00 CG-137
  • 7.77 E-01 1.74 E+00 Ba-140 *-2.8? E+00 7. 80 E+00 La-140
  • 7 04. E-01 3.22 E+00 Ra-226 *-4.11 E+00 4.26 E+01 T}1-228
  • 2.90 E+00 3.42 E+00 900313 to 900418 Be-7 *-1 10 E+00 1.91 E+01 K-40 *-2.50 E+01 3.10 E+01

~n-54 *-2 49 E-01 1.96 E+00 Co-58 * ] 74 E-01 2.11 E+00 Fe-59

  • 2.10 E-01 4.30 E+00 Co-60
  • 1.83 E+00 2.18 E+00 Zn-65 *-4.01 E+00 4.61 E+00 Zr-95 *-2 74 E+00 4.25 E+00 Nb-95
  • 1.08 E+00 2.10 E+00 Cs-134
  • 2.36 E-01 2.21 E+00 Ba-140 *-2.61 E-01 8.67 E+00 La -140 *-2.59 E+00 3.43 E+OA Ra-226 *-4.73 E+00 5.35 E+01 Th-228
  • 3.85 E+00 4.36 E+00
  • Denotes a result less than the detection limit.

0

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 28 900418 to 900516 Be-7 *-1.92 E+01 1.63 E+01 K-40 *-1 96 E+01 2.61 E+01 Mn-54

  • 1.32 E+00 1.66 E+00 Co-58 *-1.65 E+00 1.71 E+00 Fe-59
  • 2.21 E+00 3.62 E+00 Co-60
  • 2.53 E+00 1.92 E+00 Zn-65 *-2.05 E+00 4.09 E+00 Zr-95
  • 1.01 E+00 3.48 E+00 Nb-95
  • 1.45 E+00 1.83 E+00 Cs-134 *-1 24 E+00 1,83 E+00 Cs-137
  • 3.81 E-01 1.77 E+00 Ba-140 *-4 20 E+00 7.41 E+00 La-140
  • 3.95 E+01 4.52 E+01 Th-228 *-8 89 E+00 3.64 E+00 900516 to 900613 Be-7
  • 6.78 E+00 2.18 E+01 K-40
  • 1.10 f+01 5.47 E+01 Hn-54
  • 5.44 E-01 2.32 E+00 Co-58 *-6 24 E-01 2.30 E+00 Fe-59 * '5.42 f-01 5.23 E+00 Co-60 *-6.11 E-01 2.32 E+00 Zn-65 *-4.05 E+00 5.30 E+00 Zr-95 *-6.61 E-01 4.82 E+00 Nb-95
  • 1.78 E+00 2.43 E+00 Cs-134
  • 5.66 E+00 2.57 E+00 Ba -140
  • 4.51 E+00 1.05 E+01 La -140
  • 4.43 E-01 3.85 E+00
  • Denotes a result less than the detection limit.

A-95

TABLE A-7.1 (Cont.)

Results in T Y pCi/liter o COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 28 900613 to 900710 Be-7

  • 9.24 E+00 1.71 E+01 K-40 *-3.96 E+01 2.45 E+01 Nn-54
  • 0.00 E+00 1.78 E+00 Co-58 *-9.93 E-01 1.78 E+00 Fe-59
  • 1.49 E+00 3.61 E+00 Co-60
  • 1.11 E+00 1.72 E+00 Zn-65
  • 0.00 E+00 3.58 E+00 Zr-95
  • 5.60 E-Ol 3.45 E+00 Nb-95
  • 9.39 E-01 1.86 E+00 Cs-134 * / 90 E-01 1.77 E+00 Cs-137
  • 8.24 E-Ol 1.92 E+00 Ba-140
  • 1.07 E+00 6.79 E+00 La-140 *-2.89 E+00 3.00 E+00 Ra-226
  • 1.56 E+00 3.96 E+01 900710 to 900815 Th-228 Be-7 K-40
  • 4.17
  • 5.86
  • -1 61 E+00 E+00 E+01 3.44 2.13 2.61 E+00 E+01 E+01

~.

Mn-54 *-2 85 E-01 1.92 E+00 Co-58 *-3.85 E-01 2.01 E+00 Fe-59

  • 2.47 E+00 4.29 E+00 Co-60
  • 1.88 E+00 2.16 E+00 Zn-65
  • 5 47 E+00 4.32 E+00 Zr-95 *-1 00 E+00 4.33 E+00 Nb-95
  • 8.82 E-Ol 2,15 E+00 Cs-134
  • 6.69 E-01 2.22 E+Oo Ba-140
  • 1.65 E+00 9.96 E+00 La -140
  • 4 75 E+00 4.00 E+00
  • Denotes a result less than the detection limit.

A-96

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 28 900815 to 900912 Be-7 *-6.99 E-01 2.54 E+01 K-40 *-1.58 E+02 6.63 F+01 Mn-54 *-3.00 E-01 2.40 E+00 Co-58

  • 1.10 E-Ol 2.61 E+00 Fe-59 *-5.47 E+00 5.71 E+00 Co-60
  • 2.62 E+00 2.42 E+00 Zn-65 ~
  • 8.18 E+00 5.99 E+00 Zr-95 *-5.10 E+00 5.69 E+00 Nb-95
  • 2.79 E-01 2.84 E+00 Cs-134
  • 3.54 E+00 2.79 E+00 Ba -140 *-7.68 E+00 1.40 E+01 La-140 *-5 43 E+00 5.18 E+00 Ra-226 *-7.50 E+01 5.94 E+01 Th-228 *-2.45 E+01 4.79 E+00 900912 TO 901010 Be-7
  • 1.51 E+Ol 2.07 E+01 K-40
  • 2.43 E+00 2.64 E+01 Mn-54 *-2.66 E-01 1.98 E+00 Co-58 *-9 54 E-01 2.1Z E+00 Fe-59
  • 2.44 E+00 4.73 E+00 Co-60 *-1.19 E+00 2.34 E+00 Zn-65 *-1.21 E+00 4.53 E+00 Zr-95
  • 5 97 E+00 4.47 E+00 Nb-95 *-1.40 E+00 2.23 E+00 Cs-134
  • 4.10 E-01 Z.19 E+00 Ba-140 *-1.17 E+00 1.19 E+01 La-140 *-5 37 E+00 5.28 E+00 Ra-226 *-4.56 E+Ol 4.17 E+Ol Th-228 *-7 97 E+00 3.56 E+00
  • Denotes a result less than the detection limit.

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 28 901010 TO 901107 Be-7 *-1.19 E+00 1.58 E+01 K-40

  • 9.62 E-01 2.12 E+01 Mn-54
  • 7.14 E-01 1.68 E+00 Co-58
  • 0.00 E+00 1.72 E+00 Fe-59
  • 2.97 E+00 3.82 E+00 Co-60
  • 2.28 E+00 1.94 E+00 Zn-65 *-3 52 E+00 4.12 E+00 Zr-95 *-2.62 E-01 3.47 E+00 Nb-95
  • 9 44 E-01 1.73 E+00 Cs-134 *-1 10 E+00 1.86 E+00 Cs-137
  • 2.74 E+00 1.89 E+00 Ba-140
  • 8.49 E+00 6.99 E+00 La-140 *.0.00 E+00 3.35 E+00 Ra-226
  • 3.22 E+01 3. 2? E+O1 901107 to 901205 Th-228 Be-7 K-40
  • 3.69
  • -5 72
  • -8 13 E+00 E+00 E+01 2.87 2.60 6.36 E+00 E+Ol E+01

~ o Mn-54 *-1 42 E+00 2.57 E+00 Co-58 *-2 40 E+00 2.77 E+00 Fe-59

  • 1.09 E+00 6.10 E+00 Co-60 *-4.52 E-01 2.80 E+00 Zn-65 *-3.61 E+00 6.44 E+00 Zr-95 *-1.08 E+00 5.72 E+00 Nb-95
  • 3.08 E-01 2.84 E+00 Cs-134 *-1.13 E+00 2.90 E+00 Cs-137
  • 1.76 E+00 2.93 E+00 Ba-14O
  • 3.90 E+00 1.13 E+01 La-14O *-4 19 E+00 4.69 E+00 Ra-226 *-7 12 E+00 5.50 E+01 Th-228 *-2.87 E+00 4.70 E+00
  • Denotes a result less than the detection limit.

A-98

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIOE RESULT UNCERTAINTY 29 891213 to 900110 Be-7

  • 7.84 E+00 2.18 E+01 K-40
  • 4.14 E+02 3.54 E+01 Mn-54
  • 2.45 E+00 2.10 E+00 Co-58 *-1.29 E-01 2.20 E+00 Fe-59
  • 3.88 E+00 4.43 E+00 Co-60
  • 5.32 E-01 2.08 E+00 Zn-65 *-1 05 E+01 4.79 E+00 Zr-95 *-1 75 E+00 4.45 E+00 Nb-95
  • 8.98 E-01 2.21 E+00 Cs-134
  • 1.93 E+00 2.28 E+00 Ba-140
  • 0.00 E+00 9.85 E+00 La-140
  • 1.52 E+01 4.05 E+00 900110 to 900213 Be-7 *-1 87 E+01 2.26 E+Ol K-40 *-1 52 E+02 3.46 E+01 Mn-54
  • 1.16 E+00 2.10 E+00 Co-58 *-1.73 E+00 2.21 E+00 Fe-59 *-1 45 E+00 4.81 E+00 Co-60 *-9.00 E-01 2.18 E+00 Zn-65 *-6 34 E+00 4.82 E+00 Zr-95 *-6.75 E-Ol 4.76 E+00 Nb-95
  • 1.52 E+00 2.32 E+00 Cs-134 *-4 60 E-02 2.37 E+00 Cs-137
  • 1.65 E+00 2.48 E+00 Ba-140
  • 4.17 E+00 1.03 E+Ol La-140 *-6 77 E-01 4.10 E+00 Ra-226 *-1.70 E+01 5.20 E+01 Th-228 *-3.46 E+00 4.21 E+00
  • Denotes a result less than the detection limit.

A-99

TABLE A-7.1 (Cont.)

COLLECTION Results in pCi/liter OVERALL

~.

LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 29 900213 to 900313 Be-7

  • 6.57 E+00 1.65 E+01 K-40 *-3 77 E+00 2.31 E+01 Mn-54 *-3.12 E-01 1.57 E+00 Co-58 *-3 98 E-01 1.71 E+00 Fe-59 *-1.64 E-01 3.72 E+00 Co-60
  • 6.49 E-01 1.62 E+00 Zn-65
  • 4.82 E-01 3.70 E+00 Zi -95
  • 0.00 E+00 3.41 E+00 Nb-95
  • 2.14 E+00 1.68 E+00 Cs-134
  • 1.11 E+00 1.71 E+00 Ba -140
  • 5.37 E+00 7.45 E+00 La-140 *. 0.00 E+00 3.16 E+00 Ra-226 *-2.05 E-01 3.96 E+01 900313 to 900418 Th-228 Be-7 K-40
  • -9.95 f+00
  • 1.02 E+01
  • -2.20 E+02 3.18 2.64 6.25 E+00 E+01 E+01

~ s Mn-54

  • 2.46 E+00 2.66 E+00 Co-58
  • 1.81 E+00 2.?7 E+00 Fe-59 *-4 66 E-01 5.84 E+00 Co-60
  • 2.25 E+00 2.79 E+00 Zn-65
  • 7 97 E+00 6.18 E+00 Zr-95
  • 5.73 E+00 5.97 E+00 Nb-95
  • 2.88 E+00 2.84 E+00 Cs-134 *-3.32 E-01 2.91 E+00 Cs-137 *309 E+00
  • 1.94 E-01 3.01 E+00 Ba -140 1.10 E+01 La-140 *-4 51 E+00 4.31 E+00 Ra-226
  • 6.19 E+Ol 5.36 E+01 Th-228 *-1.38 E+01 4.48 E+00 Denotes a result less than the detection limit.

A-100

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOO NUCLIDE RESULT UNCERTAINTY n

29 900418 to 900516 Be-?

  • 1.26 E+01 2.19 E+01 K-40 *-1.80 E+02 5.22 E+01 Mn-54 *9 '0 E-01
  • 2.03 E+00 2.16 E+00 Co-58 2.35 E+00 Fe-59
  • 3.21 E+00 5.04 E+00 Co-60
  • 2.20 E+00 2.34 E+00 Zn-65
  • 4.14 E+00 5.47 E+00 Zr-95
  • 6.87 E+00 4.83 E+00 Nb-95
  • 6.73 E-01 2.37 E+00 Cs-134 *-3.60 E-01 2.41 E+00 Cs-137
  • 2.29 E+00 2.43 E+00 Ba-140 *-1.80 E+00 9.39 E+00 La -140 *-3.23 E+00 4.07 E+00 Ra-226 *-6 31 E+01 4.40 E+01 Th-228 *-9.31 E+00 3.70 E+00 900516 to 900613 Be-7 *-1.98 E+00 1.44 E+01 K-40
  • 2.97 E+00 1.94 E+01 MA-54 *-5 03 E-01 1.54 E+00 Co-58 *-7.58 E-01 1.59 E+00 Fe-59
  • 1.08 E+00 3.63 E+00 Co-60
  • 4 89 E-01 1.78 E+00 Zn-65
  • 2.13 E-01 3.53 E+00 7r-95 *-2 48 E-01 3.22 E+00 Nb-95
  • 3.82 E-01 1.70 E+00 Cs-134 *-5.86 E-01 1.70 E+00 Cs-137
  • 1.03 E+00 1.64 E+00 Ba-140
  • 1.89 f+00 6.85 E+00 La-140 *-2.48 E+00 3.21 E+00 Ra-226 *-2 31 E+01 2.97 E+01 Th-228
  • 9.02 E-01 2.55 E+00
  • Oenotes a result less than the detection limit.

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 29 900613 to 900710 Be-7 + 4.42 E+00 2.32 E+01 K-40 *-2.03 E+02 6.59 E+01.

Mn-54

  • 1.47 E-01 2.39 E+00 Co-58 *-1.37 F+00 2.43 E+00 Fe-59 *-7.27 E-01 5.17 E+00 Co-60 *-4 68 E+00 2.42 E+00 Zn-65
  • 4 50 F+00 5.75 E+00 Zr-95 *-2.04 E+00 5,14 E+00 Nb-95
  • 1.20 E+00 2.48 E+00 Cs-134 *-5 30 E-02 2.67 E+00 Cs-137
  • 5 74 E+00 2.69 E+00 Ba-140
  • 1.39 E+00 9.20 E+00 La-140
  • 0.00 E+00 3.36 E+00 Ra-226 *-6 40 E+Ol 5.91 E+01 900710 to 900815 Th-228 Be-7
  • -1.11 E+01
  • 8.84 E-01 4.73 1.85 E+00 E+01 4o K-40 *-7.62 E+00 2.43 E+01 Nn-54
  • 5.13 E-01 1.92 E+00 Co-58 *-7.62 E-01 2.13 E+00 Fe-59
  • 1.53 E+00 4.63 E+00 Co-60
  • 7 45 E-01 2.09 E+00 Zn-65
  • 0.00 E+00 4.27 E+00 Zr-95 *-3.86 E+00 4.02 E+00 Nb-95
  • 1.45 E+00 2.15 E+00 Cs-134 *-4 12 E-01 2.15 E+00 Cs-137
  • 0.00 E+00 2.05 E+00 Ba-140 *-3 47 E+00 9.50 E+00 La-140
  • 1.55 E+00 4.76 E+00 Ra-226 *-3 28 E+01 3.67 E+01 Th-228 *-1 71 E-01 3.25 E+00
  • Denotes a result less than the detection limits A-102

TABLE A-7.1 (Cont.)

~ Results in pCi/liter COLLECTION OVERALL LOCATION PER IOO NUCLIOE RESULT UNCERTAINTY 29 900815 to 900912 Be-7

  • 5.92 E+00 2.26 E+01 K-40
  • 1.28 E+01 3.20 E+01 Mn-54
  • 1.22 E-01 1.96 E+00 Co-58
  • 1.11 E+00 2.18 E+00 Fe-59
  • 1.15 E+00 4.57 E+00 Co-60
  • 9.77 E-01 2.21 E+00 Zn-65 i'-4. 73 E+00 4.71 E+00 Zr-95 *-1 37 E+00 4.54 E+00 Nb-95 *-2.65 E-01 2.39 E+00 Cs-134
  • 2.60 E+00 2.35 E+00 Ba-140 *-3.61 E-01 1.23 E+01 La-140 *-1 95 E+00 5.21 E+00 Ra-226 *-4 13 E+01 5.41 E+01 Th-228
  • 3.14 E-01 4.51 E+00 900912 TO 901010 Be-7 *-5 19 E+00 2.15 E+01 K-40 *-2.69 E+01 2.87 E+01 Mn-54 *-7.38 E-02 1.89 E+00 Co-58
  • 8.16 E-02 2.13 E+00 Fe-59
  • 4.12 E-01 4.80 E+00 Co-60 *-2.16 E-01 2.09 E+00 Zn-65
  • 4.93 E+00 4.48 E+00 Zr-95
  • 1.97 E+00 4.58 E+00 Nb-95
  • 3.12 E-01 2.19 E+00 Cs-134 *-7 88 E-01 2.13 E+00 Cs-137
  • 1.51 E+00 2.23 E+00 Ba -140 *-8.95 E+00 1.19 E+01 La-140 *-5.80 E+00 5.59 E+00 Ra-226 *-1 41 E+01 4.79 E+01 Th-228 *-2.81 E+00 3.86 E+00
  • Oenotes a result less than the detection limit.

A-103

TABLE A-7.1 (Cont.)

COLLECTION Results in pCi/1 i ter OVERALL

~ o LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 29 901010 TO 901107 Be-7

  • 8.14 E+00 1.64 E+01 K-40 *-3.65 E+01 2.17 E+01 Mn-54
  • 1 40 E-01 1.61 E+00 Co-58 *-5.96 E-01 1.61 E+00 Fe-59
  • 1.82 E+00 3.56 E+00 Co-60
  • 8.22 E-01 1.78 E+00 Zn-65
  • 0.00 E+00 3.62 E+00 Zr-95
  • 7.36 E-Ol 3.43 E+00 Nb-95
  • 4 73 E-01 1.65 E+00 Cs-134
  • 4.39 E-02 1.66 E+00 Ba-140 *-1 62 E+00 7.26 E+00 La-140
  • 1.18 E+00 3.25 E+00 Ra-226 *-5 07 E+01 3.95 E+01
  • 6.09 E+00
  • -2.15 E+02
  • -6.01 E-01 3.23 2.11 4.88 E+00 E+01 E+01

~ e 2.16 E+00 Co-58 *-4 77 E-01 2.14 E+00 Fe-59

  • 1.91 E-01 4.95 E+00 Co-60
  • 9.26 E-01 2.23 E+00 Zn-65 *-5 13 E+00 5.03 E+00 Zr-95
  • 9.18 E-01 4.74 E+00 Nb-95
  • 3.86 E+00 2.30 E+00 Cs-134 *-3.06 E+00 2.31 E+00 Cs-137
  • 1.57 E+00 2.39 E+00 Ba-140
  • 3.91 E+00 9.68 E+00 La -140
  • 8.87 E-01 3.75 E+00 Ra-226 *-1 46 E+02 4.66 E+01 Th-228 *-3 27 E+01 3.85 E+00
  • Denotes a result less than the detection limit.

A-104

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION,. OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY Gcuurui 31 900313 Be-7

  • 1.36 E+01 1.64 E+01 K-40
  • 1.75 E+01 2.28 E+01 Mn-54
  • 1.46 E+00 1.55 E+00 Co-58
  • 1.05 E+00 1.66 E+00 fe-59 *-5 37 E-01 3.38 E+00 Co-60
  • 1.86 E+00 1.69 E+00 Zn-65 *-1.99 E+00 3.52 E+00 Zr-95
  • 2.13 E+00 3.47 E+00 Nb-95
  • 1.69 E+00 1.73 E+00 Cs-134 *-5.23 E-02 1.75 E+00 Cs-137
  • 3.21 E-01 1.74 E+00 Ba-140 *-7'.13 E-01 7.61 E+00 La-140 *-4.86 E-01 3.32 E+00 Ra-226 *-3 53 E+Ol 4.01 E+01 Th-228
  • 8.82 E+00 3.36 E+00 31 900614 Be-7 *-1 09 E+01 2.69 E+01 K-40 *-1.31 E+02 4.02 E+01

'Mn-54

  • 5.04 E-01 2.43 E+00 Co-58 "-2.81 E+00 2.62 E+00 fe-59 *-1.06 E+00 5.42 E+00 Co-60 *-2.40 E+00 2.48 E+00 Zn-65 *-7 31 E+00 5.51 E+00 Zr-95
  • 3 40 E-01 5.45 E+00 Nb-95
  • 7.57 E-01 2.60 E+00 Cs-134
  • 3.00 E-01 2.61 E+00 CG-137
  • 4.72 E-01 2.68 E+00 Ba -140 *-4 32 E+00 1.33 E+01 La -140 " 2.90 E+00 5.00 E+00 Ra-226
  • 4 7] E+01 5.84 E+01 Th-228 *-1.02 E-02 4.73 E+00
  • Oenotes a result less than the detection limit.

A"105

TABLE A-7.1 (Cont.)

Results in pCi/liter e.

COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY i'zQ!llEi 31 900912 Be-7

  • 1.37 E+01 2.12 E+01 K-40
  • 1.14 E+OQ 2.68 E+01 Mn-54 *-6.45 E-01 1.96 E+00 Co-58
  • 7.93 E-02 2.15 E+00 Fe-59
  • 2.59 E+00 4.37 E+00 Co-60
  • 9.38 E-01 2.05 E+00 Zn-65 *-7.16 E+00 4.37 E+00 Zr-95
  • 1.47 E-01 4.20 E+00 Nb-95
  • 1.97 E+00 2.27 E+00 Cs-134 *-9.95 E-01 1.98 E+00 Cs-137
  • 1.47 E+00 2.29 E+00 Ba-140 *-3.25 E-01 1.14 E+Ol LG-140 *-1.77 E+00 5.15 E+00 Ra-226
  • 1.18 E+00 4.01 E+00 9Q1205 Be-7 *-6.18 E,+00 2.11 E+01 K-40 *-1.38 E+02 3.44 E+01 Nn-54
  • 6.13 E-01 2.02 E+00 Co-58 *-1.06 E+00 2.12 E+00 Fe-59 *-1 30 E+00 4.53 E+00 Co-60
  • 5 Q7 E-01 2.09 E+00 Zn-65 *-6.76 E+00 4.63 E+00 Zr-95
  • 7.56 E-01 4.46 E+00 Nb-95
  • 1.67 E+00 2.16 E+00 Cs-134 *-4.12 E-01 2.18 E+00 Cs-137
  • 1.48 E+00 2.21 E+00 Ba-140 *-1 20 E+00 9.70 E+00 La-140
  • 1.61 E+00 3.94 E+00
  • Oenotes a result less than the detection limit.

A"106

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY GLELHUi 32 900313 Be-7

  • 3.22 E+00 1.75 E+01 K-40 *-2.34 E+01 2.57 E+01 Mn-54
  • 7 09 E-01 1.55 E+00 Co-58
  • 4.44 E-01 1.78 E+00 Fe-59 *-1.86 E+00 3.81 E+00 Co-60
  • 3.45 E-01 1.87 E+00 Zn-65 *-4.52 'E+00 4.09 E+00 Zr-95 *-4.70 E-01 3.47 E+00 Nb-95
  • 4.23 E-01 1.83 E+00 Cs-134
  • 6.34 E-01 1.89 E+00 Cs-137 ", 6 12

~ E-Ol 1.79 E+00 Ba -140

  • 7.37 E+00 8.27 E+00 La -140 *-1.17 E+00 3.72 E+00 Ra-226
  • 3.55 E+00 4.52 F+01 Th-228 *-5.18 E-01 3.79 E+00 32 900614 Be-7 *-1 50 E+01 1.73 E+01 K-40 *-2.64 E+00 2.64 E+01 Mn-54 *-?.44 E-01 1.80 E+00 Co-58
  • 8.09 E-01 1.94 E+00 Fe-59
  • 1.02 E+00 4.26 E+00 Co-60
  • 0.00 E+00 1.93 F+00 Zn-65
  • 5.80 E-01 4.22 E+00 Zr -95 *-2.09 E+00 3.69 E+00 Nb-95
  • 7 70 E-02 1.89 E+00 Cs-134
  • 0.00 E+00 1.99 E+00 Ba-140
  • 0.00 E+00 9.43 E+00 La-140 *-2 85 E-01 E+00 '.38 Ra-226
  • 4.96 E+00 4.02 E+01 Th-228 *-2 45 E+00 3.36 E+00
  • Oenotes a result less than the detection limit.

A"107

TABLE A-7.1 (Cont.)

COLLECTION Results in pCi/liter OVERALL

~.

LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY GDL~llKUi 32 900912 Be-7

  • 1.11 E+01 1.77 E+01 K-40
  • 1.35 E+01 2.29 E+01 Mn-54
  • 1.02 E+00 1.51 E+00 Co-58 *-2.42 E-01 1.66 E+00 Fe-59 *-1 55 E-01 3.87 E+00 Co-60
  • 2.36 E+00 1.89 E+00 Zn-65
  • 4 03 E+00 3.48 E+00 Zr-95 *-1.91 E+00 3.40 E+00 Nb-95
  • 9.24 E-01 1.77 E+00 Cs-134 *-1 14 E+00 1.70 E+00 Cs-137
  • 5 44 E-01 1.69 E+00 Ba -140
  • 8.91 E+00 1.07 E+01 La -140
  • 9 54 3.78

~

E+00 E+01 Th-228 *-1 69 E+00 3.13 E+00 o 901205 Be-7 *-3.31 E-01

  • -4 76 E-01
l. 51 E+01 K-40 2.06 E+01 Mn-54
  • 3.06 E-01 1.51 E+00 Co-58
  • 1.08 E-Ol 1.54 E+00 Fe-59
  • 2.69 E+00 3.61 E+00 Co-60
  • 0.00 E+00 1.59 E+00 Zn-65
  • 2.51 E+00 3.69 E+00 Zr -95
  • 3.09 E+00 3.37 E+00 Nb-95
  • 1.54 E+00 1.64 E+00 Cs-134
  • 8.52 E-01 1.64 E+00 Ba -140
  • 2 77 E+00 7.02 E+00 La-140
  • 1.31 E+01 3.41 E+01 Th-228 *-1 38 E+00 2.89 E+00
  • Denotes a result less than the detection limit.

A-108

TABLE A-7.1 (Cont.)

T Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 52 900313 Be-7

  • 1.20 E+01 2.27 E+Ol K-40 *-2.13 E+02 5.33 E+01 Mn-54 *-8 75 E-02 2.23 E+00 Co-58
  • 3.76 E-01 2.38 E+00 Fe-59
  • 2.42 E+00 5.33 E+00 Co-60
  • 1.08 E+00 2.39 E+00 Zn-65 *-4 46 E-01 5.44 E+00 Zr-95 *-3.09 E+00 4.93 E+00 Nb-95
  • 1.61 E+00 2.40 E+00 Cs-134 *-5 17 E-01 2.44 E+00 Cs-137
  • 2.02 E+00 2.57 E+00 Ba -140 *-1.25 E+01 1.09 E+Ol La-140 *-2 47 E+00 4.22 E+00 Ra-226 *-1.01 E+02 4.53 E+Ol Th-228 *-2 48 E+00 3.87 E+00 900613 Be-7
  • 1.40 E+00 2.58 E+01 K-40 *-7 86 E+01 6.54 E+01 Mn-54
  • 6.49 E-01 2.41 E+00 Co-58 *-1.26 E+00 2.67 E+00 Fe-59 *-4 1] E+00 5.94 E+00 Co-60
  • 2.26 E+00 2.65 E+00 Zn-65 *-3 07 E+00 5.77 E+00 Zr-95 *-3.32 E+00 5.60 E+00 Nb-95
  • 4.98 E+00 2.80 E+00 Cs-134 *-2.20 E+00 2.60 E+00 Cs-137
  • 4.36 E-01 2.76 E+00 Ba -140
  • 1.72 E+00 1.44 E+01 La-140 *-5 86 E+00 5.50 E+00 Ra-226 *-1 86 E+01 5.96 E+01 Th-228 *-] 40 E+01 4.83 E+00
  • Oenotes a result less than the detection limit.

A-109

TABLE A-7.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 52 900912 Be-7

  • 2.09 E+01 2.19 E+Ol K-40
  • 2.71 E+01 2.80 E+01 Mn-54
  • 1.62 E+00 2.18 E+00 Co-58 *-5.12 E-01 2.31 E+00 Fe-59
  • 2.14 E+00 5.26 E+00 Co-60 *-3.35 E-01 2.23 E+00 Zn-65 *-5 51 E+00 4.76 E+00 Zr-95 *-3.18 E+00 4.43 E+00 Nb-95
  • 9.80 E-01 2.50 E+00 Cs-134 *-1 73 E+00 2.36 E+00 Cs-137
  • 1.?3 E+00 2.33 E+00 Ba-140
  • 2.45 E+00 1.15 E+01 La-140 *-6.28 E'-Ol 5.69'+00 Ra-226
  • 7.09 E+00 4.12 E+01 901205 Th-228 Be-7
  • -2.78
  • 7.33 E+00 E+00 3.56 2.11 E+00 E+01

~.

K-40 *-1.59 E+02 5.42 E+01 Mn-54

  • 1.36 E+00 2.04 E+00 Co-58 *-2.66 E+00 2.11 E+00 Fe-59 *-1 07 E+00 4.89 E+00 Co-60
  • 1.40 E+00 2.19 E+00 Zn-65
  • 1.47 E+01 5.11 E+00 Zr-95 *-1.13 E+00 4.63 E+00 Nb-95
  • 5.02 E+00 2.31 E+00 Cs-134
  • 1.32 E+00 2.24 E+00 Cs-13?
  • 1.96 E+00 2.29 E+00 Ba-140
  • 5 97 E-01 9.81 E+00 La-140
  • 2.39 E+00 3.62 E+00 Ra-226 *-4 44 F+01 5.04 E+01 Th-228 *-3.19 E+01 4.00 E+00
  • Denotes a result less than the detection limit.

TABLE A-7.2 Results in pCi/liter NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE Co-60 (I) 1.04E+00 -4.68E+00 5. 41E+00 24 Co-60 (C) 5. 00E-01 -1.10E+00 2. 21E+00 12 Co-58 (I) -2.39E-01 -2.40E+00 2.03E+00 24 Co-58 (C) -1. 91E-Ol -1. 95E+00 1.32E+00 12 Cs-134 (I) 1.82E-Ol -3.06E+00 3.79E+00 24 Cs-134 (C) -1.07E-01 -1. 48E+00 1.32E+00 12 0

Cs-137 (I) 1. 30E+00 -5.74E+00 5.66E+00 24 Cs-137 (C) 1.29E+00 -2.17E-01 4.38E+00 12 Nb-95 (I) 1. 07 E+00 -1.40E+00 3.86E+00 24 Nb-95 (C) 1. 18E+00 O.OOE+00 4.37E+00 12 Zr-95 (I ) 5.94E-01 -5. 10E+00 6. 87 E+00 24 Zr-95 (C) 9.46E-01 -3.20E+00 5. 68E+00 12 Zn-65 ( I) -1.46E+00 -1. 05E+01 8. 18E+00 24 Zn-65 (C) -1.66E+00 -4.78E+00 1. 70E+00 12 (I) Indicator Stations (C) Control Station

TABLE A-7.2 (Cont.)

Results in pCi/liter ~ e

'UMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE Fe-59 ( I) 9. 62E-01 -5.47E+00 3.88E+00 24 Fe-59 (C) 1.02E+00 -3.58E+00 4.03E+00 12 Ba-140 (I) -5.03E-02 -1. 14E+01 8.49E+00 24 Ba-140 (C) -1.94E+00 -1. 90E+01 1. 04E+01 12 La-140 (I) -1.56E+00 -5.80E+00 1.55E+00 24 0 La-140 (C) -1.13E+00 -3.27E+00 1. 81E+00 12 0

( I) Indicator Stations (C) Control Station

TABLE A-7.2 (Cont.)

Results in pCi/liter NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE (a)

Co-60 (I) 1.34E+00 -1.11E+00 8.60E+00 12 Co-58 (I) -2.30E-01 -2.28E+00 1.26E+00 12 Cs-134 (I) 7.81E-01 -8. 60E-01 4.38E+00 12 Cs-137 (I) 2. 17 E+00 -1. 56E-01 5.55E+00 12 Nb-95 ( I) 1.43E+00 6.17E-01 2.88E+00 12 Zr-95 (I) 3.31E-Ol -5.84E+00 5.00E+00 12 Zn-65 (I) -5.85E-01 -7.50E+00 7.89E+00 12 Fe-59 ( I) 1.28E+00 -3. 59E-01 2.72E+00 12 Ba-140 (I) -7.50E-03 -1. 04 E+0 1 1.08E+Ol 12 La-140 (I) -7.90E-01 -4.70E+00 2.34E+00 12

( a) Duplicate station 72 not included in averages.

( I) Indicator Stations (C) Control Station

TABLE A-7.2 (Cont.)

Results in pCi/liter ~.

NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE fizQ!REi Co-60 (I) 6. 68E-01 -2.40E+00 2.36E+00 12 Co-58 (I) -4. 73E-01 - 2. 81E+00 1.05E+00 12 Cs-134 (I) -1,.11E-Ol -2.20E+00 2.86E+00 12 Cs-137 (I) 9.91E-01 0.00E+00 2.02E+00 12 Nb-95 (I) 1.80E+00 7.70E-02 5.02E+00 12'2 Zr-95 (I) -7. 27E-01 -3.32E+00 3.09E+00 Zn-65 FB-59

(

(

I)

I)

-1. 92E+00 6.40E-02

-7. 31E+00

-4. 11E+00 1.47E+01 2.69E+00 12 12 ~ o Ba-140 (I) -1. 65E-01 -1. 25E+0 1 8.91E+00 12 La -140 (I) -1.98E-01 -5.86E+00 2.90E+00 12

( I) Indicator Stations (C) Control Station

TABLE A-8.1 Resul ts in pCi /ki 1 ogram LLE TI N OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 900508 K-40 2.00 E+04 6.93 E+02 Cs-134

  • 1.46 E+01 1.65 E+01 Cs-137 2.99 E+02 3.17 E+01 Ra-226 *-1.66 E+02 2.67 E+02 Th-Z28 7.23 E+02 4.39 E+01 900508 K-40 1.78 E+04 5.44 E+02 Cs-134
  • 2.33 E+01 1.60 E+01 Cs-137 4.93 E+02 3.25 E+01 Ra-226 8.86 E+02 3.46 E+02 Th-228 8.37 E+02 4 '6 E+01 9A 900508 K-40 1.21 E+04 4.03 E+OZ Cs-134
  • 2.75 E+01 1.39 E+01 Cs-137 1.21 E+02 2.18 E+01 Ra-226 1.32 E+03 3.19 E+02 Th-228 6.39 E+02 2.62 E+01 21 900508 K-40 1.21 E+04 3.44 E+02 Cs-134
  • 1.82 E+01 1.09 E+01 Cs-137 3.29 E+01 1.79 E+01 Ra-226 6.15 E+02 2.37 E+02 Th-228 5.53 E+02 2.81 E+01 23 900508 K-40 2.14 E+04 7.44 E+02 Cs-134
  • 1.41 E+02 2.92 E+02 Th-228 7.85 E+02 4.75 E+01 Denotes a result less than the detection limit.

TABLE A-8.2 Results in pCitkilogram NUMBER NUMBER NUCLIOE AVERAGE LOW HIGH SAMPLES POS ITIVE K-40 (I) 1.78E+04 1. 21 E+04 2. 14E+04 K-40 (C) 1.21E+04 '1 . 21E+04 1.21E+04 Cs-134 (I) 1. 75E+01 1. 39E+01 2.33E+0'1 Cs-134 (C) 2. 75E+01 2. 75E+01 2. 75E+01 Cs-137 (I) 2.87E+02 3.29E+01 4. 93E+02 Cs-137 (C) 1. 21E+02 1. 21E+02 1. 21E+02 Ra-226 (I) 3. 69E+02 -1. 66E+02 8.86E+02 o Ra-226 (C) 1. 32E+03 1.32E+03 1.32E+03 Th-228 (I)

(C)'.25E+02 5.53E+02 8.37E+02 Th-228 6.39E+02 6.39E+02 6.39E+02 I) Indicator Station

(

(C) Control Station

. ~

TABL'E A-9.1 T

Resul ts in pCi /ki l ogram COLLECTION OVERALL LOCATION PERIOD NUCLIOE RESULT UNCERTAINTY 33 900419 K-40 1.61 E+04 4.46 E+02 (Upstream) Co-57

  • 5.63 E+00 9.25 E+00 Co-60
  • 3.68 E+00 1.17 E+01 Cs-134
  • 3.26 E+01 1.20 E+01 Cs-137 1.15 E+02 1.91 E+01 Ra-226 1.05 E+03 2.76 E+02 Eu-152 7.91 E+01 1.16 E+02 Th-228 7.89 E+02 2.50 E+01 34 900419 K-40 1.40 E+04 3.37 E+OZ (Downstream) Co-57
  • 1.25 E+01 8.79 E+00 Co-60
  • 1.52 E+01 9.53 E+00 Cs-134
  • 6.79 E+01 1.05 E+01 Cs-137 1.82 E+02 1.70 E+O1 Ra-226 1.38 E+03 2.48 E+OZ Eu-152
  • 5 60 E+00 2.78 E+01 Th-228 1.29 E+03 2.47 E+01 33 901016 K-40 1.46 E+04 7.00 E+02 (Upstream) Co-57 *-1.47 E+00 1.74 E+01 Co-60
  • 2.09 E+00 2.05 E+01 Cs-134
  • 9.08 E+01 3.65 E+01 Ra-226 1.75 E+03 5.61 E+02 Eu-152
  • 1.55 E+02 1.04 E+02 Th-228 1.92 E+03 7.37 E+01 34 901016 K-40 1.38 E+04 7.40 E+02 (Oownstream) Co-57 *-1.16 E+01 3.29 E+01 Co-60
  • 1.48 E+01 2.26 E+01 Cs-134
  • 8.08 E+01 2.84 E+01 Cs-137 1.97 E+02 5.01 E+01 Ra-226 1.95 E+03 7.90 E+02 Eu-152
  • 1.66 E+02 1.25 E+02 Th-228 2.46 E+03 1.03 E+02 Denotes a result less than the detection limit.

TABLE A-9.2 Results in pCf/kilogram NUMBER NUMBER

~ o NUCLIDE AVERAGE LOW HIGH SAMPLES POSITI VE K-40 ( I) 1.39E+04 1.38E+04 1.40E+04 K-40 (C) 1.54E+04 1.46E+04 1. 61E+04 Co-57 (I) 4.50E-01 -1.16E+01 1. 25E+01 Co-57 (C) 2.08E+00 - 1.47E+00 5.63E+00 Co-60 (I) 1.50E+01 1. 48E+01 1. 52E+Ol Co-60 (C) 2.89E+00 2.09E+00 3.68E+00 Cs-134 (I) 7. 44E+01 6. 79E+01 8. 08E+01

~

C Cs-134 (C) 5.93E+01 3.26E+01 8. 59E+01 0 Cs-137 (I) 1.90E+02 1.82E+02 1.97E+02 Cs-137 (C) 1.03E+02 9. 08E+01 1. 15E+02 Ra-226 (I) 1.67E+03 1. 38E+03 1.95E+03 Ra-226 (C) 1.40E+03 1. 05E+03 1.?5E+03 Eu-152 (I) 8. 58E+01. 5.60E+00 1. 66E+02 Eu-152 (C) 1. 17 E+02 7.91E+01 1.55E+02 Th-228 (I) 1.88E+03 1.29E+03 2.46E+03 Th-228 (C) 1.35E+03 7.89E+02 1.92E+03 (I) Indicator Station (C) Control Station

TABLE A-10.1 (Cont.)

Results in pCi/kilogram

/

COLLECTION OYERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 30 900924 K-40 3.54 E+03 3.42 E+02 Sucker Mn-54 *-7 35 E+00 1.15 E+01 Co-58

  • 4 54 E-01 1.37 E+01 Fe-59
  • 8.78 E+00 3.67 E+01 Co-60 *-2.64 E+00 1.20 E+01 Zn-65 *-3.83 E+00 2.83 E+01 Cs-134
  • 4.61 E+00 1.24 E+01 Cs-137 3.04 E+01 1.72 E+01 Ra-226 *-9.32 E+Ol 2.24 E+02 Th-228 *-2 48 E+01 2.01 E+01 Carp 900924 K-40 2.55 E+03 2.58 E+02 Mn-54
  • 1.86 E+00 8.84 E+00 Co-58 *-3.83 E-01 1.07 E+01 Fe-59 *-2.11 E+00 2.81 E+01 Co-60
  • 0.00 E+00 8.35 E+00 Zn-65 *-8 05 E-01 2.26 E+01 Cs-134
  • 2.51 E+00 9.36 E+00 Ra-226 *-5 35 E+01 1.87 E+02 Th-228 *-1 85 E+01 1.60 E+01 Steel head 901002 K-40 3.80 E+03 2.90 E+02 Mn-54
  • 7.87 E+00 1.16 E+01 Co-58
  • 2.75 E+00 1.30 E+01 Fe-59
  • 1.86 E+01 3.23 E+01 Co-60 *-4 08 E+00 1.27 E+01 Zn-65 *-2 81 E+01 2.74 E+01 Cs-134
  • 1.12 E+01 1.28 E+01 Ra-226 *-1.83 E+02 2.22 E+02 Th-228 *-8 49 .E+01 2.22 E+01 Whitefish 900924 K-40 3.82 E+03 3.26 E+02 Mn-54
  • 3.76 E+00 1.10 E+01 Co-58
  • 4.68 E+00 1.28 E+01 Fe-59 " 6.49 E+00 3.39 E+01 Co-60
  • 6.99 E+00 1.21 E+01 Zn-65
  • 1.37 E+01 2.75 E+01 Cs-134
  • 2.61 E+01 2.01 E+0!
  • Denotes a result less than the detection l imi t.

TABLE A-10.1 Resul ts in pCi/kilogram LOCATION COLLECTION PERIOD NUCLIDE RESULT OVERALL UNCERTAINTY

~.

30 900430 K-40 4.96 E+03 3.59 E+02 Steelhead Nn-54 *-1.50 E+00 1.15 E+01 Co-58 *-8 22 E+00 1.19 E+01 Fe-59 *-1 02 E+01 2.64 E+01 Co-60

  • 7 07 E+00 1.14 E+01 Zn-65
  • 3.83 E+00 2.62 E+01 Cs-134
  • 9.16 E+01 2.35 E+02 Th-228 *-2.17 E+01 2.21 E+01 Whi tefl sh 900430 K-40 4.44
  • 5.32 E+03 2.82 E+02 Nn-54 E+00 9.06 E+00 Co-58
  • 6.72 E+00 1.00 E+01 Fe-59
  • 4.35 E+00 2.43 E+01 Co-60
  • 1.92 E+00 1.01 E+01 Zn-65
  • 9 47 E+00 2.09 E+01 Cs-134
  • 2.35

" 3.32

  • 1.99 E+01 E+Ol E+01 1.03 E+01 2.10 E+02 1.78 E+01 ~ o Carp 900430 K-40 3.00 E+03 2.66 E+02 Nn-54 *-5.39 E+00 9.09 E+00 Co-58
  • 7.01 E-01 1.02 E+01 Fe-59
  • 1.76 E+00 2.43 E+01 Co-60
  • 3.68 E+00 1.01 E+01 Zn-65 *-4 05 E+00 2.13 E+01 Cs-134
  • 4.74 E+00 1.04 E+0!

Cs-137

  • 3.64 E+01 2.05 E+C2 Th-228 +-1.52 E+Ol 1.88 E+01 Sucker 900430 K-40 4.11 E+03 2.37 E+02 Nn-54
  • 3.18 E+00 1.05 E+0'.

Co-58 *-5.61 E+00 1.14 E+0!

Fe-59

  • 3.00 E+01 2.55 E+C:

Co-60 *-5 06 E+00 1.10 E+01 Zn-65 *-3 00 E+01 2.60 E~O:

Cs-134

  • 9.93 E-01 1.13 E+C:.

Cs-137

  • 1.20 E+Ol 2.21 E+02 Th-228 *-2 94 E+Ol 1.96 E+01
  • Oenotes a result less than the detection 1 imi t, A-3.20

TABLE A-10.1 (Cont.)

HM T Resul ts in pCi /ki 1 ogr am COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 38 900504 K-40 4.80 E+03 2.67 E+02 Sucker Mn-54 *-5.19 E+00 1.18 E+01 Co-58

  • 1.52 E+00 1.28 E+01 Fe-59
  • 1.46 E+01 2.87 E+01 Co-60 *-1. 24 '+01 1.24 E+01 Zn-65 *-4.18 E+01 2.77 E+01 Cs-134
  • 6.39 E-Ol 1.28 E+01 CG-137
  • 1.09 E+01 2.52 E+02 Th-228 *-7.42 E+00 2.25 E+01 Carp 900504 K-40 3.67 E+03 2.81 E+02 Mn-54 " 3.12 E+00 9.21 E+00 CG-58
  • 2.04 E+00 1.05 E+01 Fe-59
  • 5.89 E+00 2.34 E+01 Co-60
  • 5.00 E+00 1,05 E+01 Zn-65 *-1.35 E+01 2.20 E+01 Cs-134
  • 1.17 E+Ol 1.12 E+01 Ra-226 *-1 57 E+02 2.06 E+02 Th-228 *-7.77 E+00 1.96 E+01 Salmon 900504 K-40 3.95 E+03 2.64 E+02 Mn-54
  • 2.12 E+00 8.53 E+00 Co-58 *-3 34 E+00 8.45 E+00 Fe-59
  • 5 07 E+00 2.11 E+01 Co-60
  • 0.00 E+00 8.74 E+00 Zn-65 *-4 20 E+00 1.98 E+01 Cs-134
  • 2.20 E+01 1.59 E+01 Bass 900504 K-40 7.71 E+03 4.72 E+02 Mn-54 *-8 04 E-01 1.26 E+01 Co-58 *-1.22 E+01 1.42 E+01 Fe-59
  • 1.85 E+Ol 3.37 E+01 Co-60
  • 1.48 E+01 1.53 E+01 Zn-65 *-1.14 E+01 3.57 E+0 1 Cs-134
  • 1.87 E+01 2.38 '+01 r
  • Denotes a result less than the detection limit.

TABLE A-10.1 (Cont.)

Results in pCi/kilogram LOCATION COLLECTION PER IOO NUCLIOE RESULT OVERALL UNCERTAINTY

~ o 38 900925 K-40 3.65 E+03 2.93 E+02 Bass Mn-54

  • 1.06 E+01 9.50 E+00 Co-58
  • 3 47 E+00 1.11 E+01 Fe-59 *-8 48 E+00 2.. 94 E+01 Co-60
  • 8.00 E+00 1.03 E+01 Zn-65 *-1 30 E+01 2.33 E+01 Cs-134
  • 1.91 E+01 1.73 E+01 Squawfish 900926 K-40 2.85 E+03 3.24 E+02 Mn-54 * ] 04 E+01 1.35 E+01 Co-58
  • 1.91 E+00 1.56 E+01 Fe-59
  • 1.72 E+00 3.92 E+01 Co-60
  • 5 07 E+00 1.25 E+01 Zn-65 *-2 79 E+01 3.29 E+01 Cs-134
  • 8.72 1.39

~.

E+00 E+01 Cs-137

  • 1.00 E+01 2.84 E+O1 Steel head 901003 K-40 3.19 E+03 2.93 E+02 Mn-54
  • 1.71 E+01 1.48 E+01 Co-58 *-1.50 E+01 1.60 E+Ol Fe-59 *-9 81 E-01 4.13 E+01 Co-60
  • 1.20 E+01 1.50 E+01 Zn-65 *-8.28 E+00 3.59 E+01 Cs-134
  • 6.22 E+00 1.55 E+01 Ra-226 *-3 61 E+01 2.58 E+02 Th-228 *-2 04 E+01 2.27 E+01 Carp 900925 K-40 3.50 E+03 2.10 E+02 Mn-54
  • 1.86 E+00 6.84 E+00 Co-58 *-6.52 E+00 8.62 E+00 Fe-59
  • 8.04 E+00 2.17 E'+01 Co-60 " 9.36 E-01 7.28 E+00 Zn-65 *-2.42 E+01 1.62 E+01 Cs-134
  • 1.10 E+01 1.32 E+01
  • Denotes a result less than the detection 1 imi t.

A-122

TABLE A-10.1 (Cont.)

Results in pCi/kilogram COLLECTION OVERALL LOCATION PERIOO NUCLIOE RESULT UNCERTAINTY 38 900925 K-40 3.88 E+03 2.41 E+02 Sucker Nn-54

  • 7.35 E+00 6. 81 E+00 Co-58
  • 4.08 E+00 8.80 E+00 Fe-59 *-5.90 E-01 2. 27 E+01 Co-60 *-2.24 E+00 6.92 E+00 Zn-65 *- 1. 45 E+01 1. 71 E+01 Cs-134
  • 2.14 E+01 1.32 E+01
  • Denotes a result less than the detection limit.

A-123

TABLE A-10.2 Res ul ts in pCi /ki 1 og ram

~ o NUMBER NUMBER NUCLIOE AVERAGE LOW HIGH SAMPLES POSITIVE K-40 ( I) 3.78E+03 2.55E+03 4.96E+03 K-40 (C) 4. 13E+03 2.85E+03 7. 71E+03 Co-60 (I) -7.83E-01 -7.07E+00 6.99E+00 Co-60 (C) 3.46E+00 -1. 24E+01 1. 48E+01 Fe-59 (I) 7. 21E+00 -1. 02E+01 3. 00E+01 Fe-59 (C) 4.86E+00 -8. 48E+00 1. 85E+01 Zn-65 ( I) -7.34E+00 -3.00E+01 1. 37 E+01 0 Zn-65 (C) -1.76E+01 -4.18E+01 -4. 20E+00

~ e Co-58 (I) 1.37E-Ol -8.22E+00 6.72E+00 Co-58 (C) -2.67E+00 -1. 50E+01 4.08E+00 Cs-134 (I) 7.51E+00 0.00E+00 2. 40E+01 Cs -134 (C) 5. 03E+00 6. 39E-01 9.90E+00 Cs -137 ( I) 1. 53E+01 2. 51E+00 3.14E+01 Cs-137 (C) 1.44E+Ol 5.95E+00 2. 41E+01 Nn-54 ( I) 9. 69E-01 -7.35E+00 7.87E+00 Mn-54 (C) 5.17E+00 -5. 19E+00 1. 71E+01

( I) Indicator Stations (C) Control Station

TABLE A-11.1 Results in pCi/1 i ter LLE TI N VERALL LOCATION DATE RESULT UNCERTAINTY 9B 900109 *7 7 E-02 1.26 E-01 900206 *7 4 E-02 2.04 E-01 900306 *-3 2 E-01 1.96 E-01 900403 *7 3 E-02 1.78 E-01 900417 *-1 8 E-02 2.22 E-01 900501

  • 2 ] E-01 1.60 E-01 900515
  • 5 ] E-02 9.78 E-02 900612
  • 9 5 E-03 1.38 E-Ol 900626
  • 7 9 E-02 1.02 E-01 900717 *-2 1 E-01 2.93 E-01 900731 * ] E-02 2.18 E-01 900814 *3 P E-02 9.83 E-02 900828 *] p E-01 1.42 E-Ol 900910 *14 E-01 1.38 E-01 900925 ] 5 E-01 . 1.20 E-01 901009
  • 7 8 E-02 2.81 E-01 901106
  • 3 4 E-02 1.67 E-01 901204 * ] 8 E-01 3.00 E-01 36 900109
  • 1.8 E-02 1.27 E-01 900206 *2 5 E-01 2.19 E-01 900306
  • 6.9 E-03 9.49 E-02 900403 *4 2 E-02 8.96 E-02 900417 *7 P E-02 1.36 E-01 900501
  • 1.1 E-01 1.00 E-01 900515
  • 1.1 E-01 1.18 E-01 900612 *-4 7 E-02 1.13 E-01 900626
  • 9 7 E-02 3.30 E-01 900717 *-1 8 E-Ol 2.42 E-01 900731 *-2 3 E-01 3.10 E-01 900814 *-6 2 E-02 1.09 E-01 900828
  • 3.2 E-01 2.19 E-01 900910 *9 5 E-02 1.28 E-01 900925 * ] 9 E-01 1.06 E-01 901009
  • 3 0 E-02 1.86 E-01 901106 *3 9 E-01 2.70 E-01 901204
  • 2.0 E-01 2.74 E-01
  • Denotes a result less than the detection limit.

A-125

TA8LE A-11.1 (Cont.)

ResUlts in pCI/liter t LL LOCATION DATE RESULT UNCERTAINTY 40 900109 + 1.0 E-02 1.13 E-01 900206 ~ 3.5 E-02 l. 59 E-01 900306

  • 1.2
  • 1.4 E-01 1.70 f -01 900403 E-01 1.43 E-01 900417 *-5.8 E-02 1.68 E-01 (a) 59 900109 2 E-02 1.06 E-01 900206 * ] 3 E-Ol 1.38 E-01 900306 9 6 E-02 1.82 900403 '2.3 E-01 E-0>

E-0'.47 900417 Q Q E+00 3.32 E-Oi 900501 7 5 E-02 1.73 E-01 900515

  • 7 4 E-02 1.19 E-01 900612 ~ 2.0 E-01 1.75 E-01 900626
  • 1.5 E-02 1.03 E-01 900717 * ,E-02 2.91 E-01 900731 *-]5 7 E-01 Z.30 E-Cl 900814 E-02 1.07 f-01 900828 1.2 E-01 1.75 E-01 900910
  • f -01 8.41 E-02 900925 "'-2 9 E-02 9. 21 E-02 901Q09 2 Q E-02 2.78 f -01 901106 3 3
  • 2.2 E-02 l. 22 E-01 901204 E-01 3,27 E-01 (a) Supolier suspended milk sampling: replaced by location 62.

Denotes' result less than the detection limit.

A-126

TABLE A-ll.l (Cont.)

Results in pCi/liter OLLE TI VERALL LOCATION DATE RESULT UNCERTAINTY 62 (a) 900515 *-6.8 E-02 1.33 E-01 900612

  • 7 3 E-03 1.40 E-01 900626
  • 1.2 E-01 2.34 E-01 "900717 *-1.8 E-Ol 3.13 E-01 900731 * ] 8 E-01 1.60 E-01 900814 *-] 8 E-01 1.72 E-Ol 900828 *-5 2 '-02 2.54 E-01 900910 *-2 0 E-01 9.32 E-02 900925 *-4 5 E-02 1.07 E-01 901009
  • 9 0 E-02 3.22 E-01 901106 *8 3 E-02 1.57 E-01 901204
  • 7 4 E-02 2.22 E-01 63 900717 *-1.6 E-01 2.11 E-01 900731
  • 1.0 E-02 1.16 E-01 900814 *6 7 E-02 9.38 E-02 900828 *-1 8 E-02 1.25 E-01 900925 *-2 0 E-03 7. 84 E-02 901009 *-1.8 E-01 2.55 E-01 901106 *9 E-02 1.23 E-01 901204 *] 7 E-01 2.71 E-01 96 900109 *-1 3 E-02 1.81 E-01 900206 *-7 2 E-02 1.46 E-01 900306
  • 1.0 E-01 1.80 E-01 900403
  • 9 E-02 1.52 E-01 900417 *-6 2 E-02 1.90 E-01 900501
  • 8.9 E-02 1.32 E-01 900515
  • 9 E-02 9.90 E-02 900612
  • 5 9 E-02 9.15 E-02 900626 *15 E-01 1.35 E-01 900717 4.8 E-02 2.13 E-01 900731
  • 9 0 E-03 1.61 E-01 900814
  • 6.1 E-03 1.32 E-01 900828
  • 1 3 E-01 1.59 E-01 900910
  • 9 3 E-02 1.12 E-01 900925 * ] 4 E-01 1.00 E-Ol 901009
  • 4 9 E-Ol 3.60 E-01 901106
  • 2.4 E-02 1.97 E-01 901204 *-7 2 E-02 2.22 E-01 (a) Station 62 replaces station 40; supplier suspended milk sampling.
  • Denotes a result less than the detection limit, A-127

TABLE A-11.2 Results in pCi/liter

~ o NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE I-131 (I) -8.2E-03 -3.2E-01 3.9E-01 79 I -131 (C) 4. 7E-02 -1.3E-01 3.9E-01 18

~I (I) Indicator Stations (C) Control Station A-128

TABLE A-12.1 Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 9B 900109 K-40 1.13 E+03 7.21 E+01 Cs-134 *-5 51 E-01 2.25 E+00 Cs-137

  • 3.84 E+00 2.35 E+00 Ba-140 *-3 51 E+00 7.40 E+00 La-140
  • 0.00 E+00 2.99 E+00 900206 K-40 1.33 E+03 7.57 E+Ol Cs-134 *-3 52 E-01 2.21 E+00 Cs-137
  • 2.60 E+00 2.34 E+00 Ba-140 *-1 63 E+00 8.20 E+00 La-140 *-2 22 E+00 3.36 E+00 900306 K-40 1.29 E+03 7.71 E+01 Cs-134 *-8.95 E-01 2.31 E+00 Cs-137
  • 5.91 E-01 2.31 E+00 Ba -140 *-1 55 E+00 7.79 E+00 La-140 * ] 4] E+00 3.13 E+00 900403 K-40 1.22 E+03 7.38 E+01 Cs-134
  • 3.92 E+00 2.44 E+00 Ba-140 *-2 23 E+00 7.19 E+00 La-140 *-1.82 E+00 2.71 E+00 900417 K-40 1.31 E+03 7.99 E+01 Cs-134
  • 2.69 E-Ol 2.38 E+00 Ba-140 *-3 76 E+00 8.64 E+00 La-140 *-3 55 E+00 3.50 E+00 900501 K-40 9.97 E+02 6.95 E+01 Cs-134 *-1 19 E+00 2.95 E+00 Cs-137
  • 2.90 E+00 3.07 E+00 Ba-140
  • 7 09 E+00 1.02 E+01 La-140 *-1.46 E+00 4.19 E+00 900515 K-40 1.20 E+03 7.56 E+01 Cs-134 *-9 67 E-01 2.27 E+00 Cs-137
  • 6.61 E-01 2.28 E+00 Ba -140
  • 7.39 E+00 7.23 E+00 La-140 *-1.36 E+00 3.31 E+00
  • Oenotes a result less than the detection limit.

A-129

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 9B 900612 K-40 1.06 E+03 7.25 E+01 Cs-134 1.48 E+00 2.36 E+00 Cs-137 3.13 E+00 2.36 E+00 Ba-140 6.45 E+00 8.41 E+00 La-140 5.84 E-Ol 3.54 E+00 900626 K-40 1.25 E+03 7.71 E+01 Cs-134 4.22 E-01 2.39 E+00 Cs-137

  • 1.66 E+00 2.31 E+00 Ba-140 *-2 87 E+00 7.94 E+00 La-140 *-] 45 E+00 3.44 E+00 900717 K-40 1.21 E+03 7.90 E+01 Cs-134 3.09 E-Ol 2.41 E+00 Cs-137 3.03 E+00 2.56 E+00 Ba-140
  • 0.00 E+00 9.09 E+00 La-140 *-6.60 E-01 3.65 E+00 900731 K-40 1.22 E+03 7.92 E+01 Cs-134 1.16 E+00 2.35 E+00 Cs-137 5.40 E-01 2.39 E+00 Ba-140 4,. 63 E+00 8.57 E+00 La-140 2.91 E+00 3.65 E+00 900814 K-40 1.30 E+03 8.54 E+01 Cs-134 *-1.68 E+00 2.39 E+00 Cs-137
  • 5.14 E-Ol 2.34 E+00 Ba-140
  • 3.68 E+00 7.56 E+00 La-140
  • 4.06 E-01 3.13 E+00 900828 K-40 1.29 E+03 9.22 E+01 Cs-134 *-4.13 E-01 2.51 E+00 Cs-137 1.58 E+00 2.48 E+00 Ba-140 6.76 E+00 9.29 E+00 La-140 2.60 E+00 4.25 E+00 900910 K-40 1.19 E+03 8.31 E+01 Cs-134 *-7.65 E-01 2.33 E+00 Cs-137
  • 1.47 E+00 2.40 E+00 Ba-140 *-4 42
  • 1.58 E+00 '.02 E+01 La-140 E+00 3.95 E+00
  • Oenotes a result less than the detection limit.

A"130

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 9B 900925 K-40 1.06 E+03 7.91 E+01 Cs-134 *-1 80 E+00 . 2.35 E+00 Cs-137

  • 0.00 E+00 '.36 E+00 Ba-140 *-2.03 E+00 8.68 E+00 La -140 ~ *-1 87 E+00 '.66 E+00 901009 K-40 1.19 E+03 7. 34 E+01 Cs-134
  • 6 34 E-01 2.08 E+00 Cs-13?
  • 1.22 E-01 ~

1.99 E+00 Ba-140 *-5 33 E+00 8.43 E+00 La-140 *-1 72 E+00 . 3.66 E+00 901106 K-40 1.26 E+03 I 6.90 E+01 Cs-134

  • 1.84 E+00 . ~

2,21 E+00 Cs-137 *-1 38 E+00 '2.45 E+00 Ba -140 *-1 69 E+00 1.07 E+01 La-140

  • 1 14 E+00 '.46 E+00 901204 K-40 1.30 E+03 7. 67 E+01 Cs-134
  • 2.13 E+00 2.25 E+00 Ba-140 *-1.65 E+00 8.44 E+00 La-140 *-1 52 E+00 3.55 E+00
  • Denotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOO NUCLIOE RESULT UNCERTAINTY 36 900109 K-40 1.19 E+03 7.72 E+01 Cs-134 6.9Q E-01 2.37 E+00 Cs-137 1.21 E+00 2.43 E+00 Ba -140 1.19 E+00 7.78 E+00 La-140 2.01 E+00 2.99 E+00 900206 K-40 1.41 E+Q3 8.62 E+01 Cs-134 1.96 E+00 2.53 E+00 Cs-137 6.01 E-01 2.47 E+00 Ba-140 3.72 E+00 8.93 E+00 La-140 2.46 E+00 3.?4 E+00 900306 K-40 1.26 E+03 6.95 E+01 Cs-134

  • 7.73 E-01 2.09 E+00 Ba -140
  • 1.69 E+00 6.13 E+00 La-140 *-7.18 E-01 2.54 E+00 900403 K-40 1.25 E+03 8.01 E+01 Cs-134
  • 1.08 E+00 2.21 E+00 Cs-137 *-3 34 E-01 2.19 E+00 Ba-140
  • 4.50 E+00 6.94 E+00 La -140 *-4 16 E+00 3.00 E+00 90Q417 K-40 1.30 E+03 7.83 E+01 Cs-134
  • 7.71 E-01 2.33 E+00 Ba-140 *-1.21 E+00 7.84 E+00 La-140
  • 3.65 E-01 3.50 E+00 9.00501 K-40 1.37 E+03 7.90 E+01 Cs-134
  • 2.76 E+00 2.30 E+00 Ba-140 *-1 91 E+00 7.50 E+00 La-140
  • 1.23 E+00 3.23 E+00 900515 K-40 1;27 E+03 8.00 E+01 Cs-134
  • 2.54 E+00 2.19 E+00 Ba-140
  • 1.61 E+00 7.05 E+00 La-140 *-9 71 E-01 2.95 E+00
  • Qenotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 36 900612 K-40 1.19 E+03 8.18 E+Ol Cs-134

  • 1.62 E+00 2.25 E+00 Cs-137 *-2 81 E-01 2.27 E+00 Ba -140
  • 4.16 E+00 7.80 E+00 La-140 *-4 47 E-01 3.35 E+00 900626 K-40 1.35 E+03 8.48 E+01 Cs-134
  • 3 54 E+00 2.29 E+00 Ba -140
  • 2.65 E+00 7.61 E+00 La-140 *-1.60 E+00 3.33 E+00 900717 K-40 1.39 E+03 7.77 E+01 Cs-134
  • 8.11 E-01 2.31 E+00 Cs-137 *-7.46 E-01 2.30 E+00 Ba-140 *-5.65 E+00 8.89 E+00 La-140 *-1.17 E+00 3.72 E+00 900731 K-40 1.38 E+03 7.91 E+01 Cs-134
  • 7.95 E-01 2.35 E+00 Ba-140 *-4.51 E+00 7.94 E+00 La-140 *-1.07 E+00 3.11 E+00 900814 K-40 1.30 E+03, 8.62 E+01 Cs-134
  • 1.61 E+00 2.47 E+00 Ba-140 *-3 37 E+00 7.83 E+00 La -140 *-1.26 E+00 3.09 E+00 900828 K-40 1.35 E+03 7.99 E+Ol Cs-134
  • 1.88 E+00 2.41 E+00 Ba -140
  • 4.80 E+00 9.21 E+00 La-140 *-2.11 E+00 4.00 E+00 900910 K-40 1.12 E+03 7.21 E+01 Cs-134 *-3 97 E-01 2.19 E+00 Cs-137
  • 2.24 E+00 2.29 E+00 Ba-140
  • 9.89 E+00 8.52 E+00 La-140
  • 0.00 E+00 3.47 E+00
  • Denotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION -PERIOD NUCLIDE RESULT UNCERTAINTY 36 900925 K-40 1.22 E+03 8. 02 E+01 Cs-134

  • 6.78 E+00 2.82 E+00 Ba -140 *-7.87 E+00 8.39 E+00 La-140
  • 1.21 E+00 3.63 E+00 901009 K-40 1. 23 E+03 7. 82 E+01 Cs-134
  • 1.58 E+00 2.22 E+00 Ba-140 *-4.06 E+00 8.29 E+00 La-140 *-2.24 E-Ol 3.33 E+00 901106 K-40 1.33 E+03 7. 92 E+01 Cs-134
  • 2.11 E+00 2.25 E+00 Cs-137 *-8. 68 E-Ol 2.33 E+00 Ba-140 *-7.06 E+00 1.08 E+01 La-140 *-1.46 E+00 4.20 E+00 901204 K-40 1.30 E+03 7. 57 E+01 Cs-134
  • 2.91 E+00 2.29 E+00 Ba-140 *-1. 29 E+00 8.97 E+00 La-140
  • 1.78 E+00 4.04 E+00
  • Denotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 40 900109 K-40 1.17 E+03 7.93 E+01 Cs-134

  • 0.00 E+00 3.38 E+00 Ba-140
  • 3.04 E+00 1.15 E+01 La-140 *-1.76 E-01 4. 07 E+00 900206 K-40 1.16 E+03 6.97 E+01 Cs-134
  • 2.90 E+00 3.04 E+00 Ba-140
  • 6.44 E+00 1.09 E+01 La-140 *-4 45 E+00 4.31 E+00 900306 K-40 1.20 E+03 6.66 E+01 Cs-134 *-1.20 E-01 1.85 E+00 Cs-137
  • 2.15 E+00 1.84 E+00 Ba -140
  • 3 54 E+00 5.30 E+00 La-140
  • 3.80 E-01 2.39 E+00 900403 K-40 1.14 E+03 7.68 E+01 Cs-134
  • 2.01 E+00 2.47 E+00 Ba-140 *-3.16 E+00 7.76 E+00 La-140
  • 1.87 f-Ol 3.35 E+00 900417 K-40 1.01 E+03 8.15 E+01 Cs-134 *-1.33 E+00 2.50 E+00 Cs-137
  • 7.81 E-01 2.39 E+00 Ba -140
  • 9 77 E-01 8.60 E+00 La-140
  • 1.32 E+00 3.71 E+00 900501 (a)

~ 'a)* Supplier suspended Denotes a milk program.

result less than the detection limit.

A-135

TABLE A-12.1 (Cont.)

Results in pCi /l i ter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 900109 K-40 1.31 E+03 7.25 E+01 Cs-134

  • 4.13 E+00 2.86 E+00 Ba -140 *-2 78 E+00 9.28 E+00 La-140 *-1'.41 E-01 3.50 E+00 900206 K-40 1.23 E+03 7.31 E+01 Cs-134 *-1.36 E-01 2.16 E+00 Cs-137
  • 2.69 E+00 2.20 E+00 Ba -140 *-3 93 E+00 7.83 E+00 La'-140
  • 3.61 E-01 3.23 E+00 900306 K-40 1.41 E+03 7.44 E+01 Cs-134
  • 7.90 E-01 2.19 E+00 BQ-140 *-5.29 E-01 6.10 E+00 La-140
  • 1.37 E+00 2.43 E+00 900403 K-40 1.37 E+03 7.88 E+01 Cs-134 *-7 29 E-02 2.47 E+00 Cs-137
  • 2.95 E+00 2.36 E+00 Ba-140 *-2.28 E+00 7.60 E+00 La-140
  • 1.21 E+00 2.96 E+00 900417 K-40 1.40 E+03 7.63 E+01 Cs-134
  • 1.16 E+00 2.18 E+00 Ba -140
  • 3.61 E+00 7.65 E+00 La-140 *-5.24 E-01 3. 34 E+00 900501 K-40 1.20 E+03 7.79 E+01 Cs-134
  • 9.67 E-01 2.28 E+00 Ba-140 "-1.93 E+00 7.52 E+00 La-140
  • 1 41 E+00 3.03 E+00 900515 K-40 1.33 E+03 7.98 E+01 Cs-134
  • 1.84 E+00 2.44 E+00 Ba-140 *-9 72 E-01 7.98 E+00 La-140 *-1.59 E+00 3.14 E+00
  • Denotes a result less than the detection limit.

A-136

TABlE A-12.1 (Cont.)

Results in pCi ll i ter COLLECTION OVERALL LOCATION PERIOD NUCLIOE RESULT UNCERTAINTY 59 900612 K-40 1.32 E+03 8.06 E+01 Cs-134

  • 1.95 E+00 2.33 E+00 Ba -140 *-2.91 E+00 8.62 E+00 la-140 *-4 07 E-01 3.78 E+00 900626 K-40 1.35 E+03 7.77 E+01 Cs-134 1.37 E-01 2.25 E+00 Cs-137 1.26 E+00 2.34 E+00 Ba-140 7.51 E-01 8.21 E+00 la-140 1.38 E+00 3.38 E+00 900717 K-40 1.64 E+03 8.44 E+01 Cs-134
  • 1.05 E+00 2.49 E+00 CG-137
  • 8.56 E-01 2.49 E+00 Ba -140 *-1.12 E+01 9.38 E+00 la-140
  • 3 79 E+00 3.90 E+00 900731 K-40 1.43 E+03 8.95 E+01 Cs-134
  • 2.74 E+00 2.65 E+00 CG-137
  • 1.61 E-01 2.49 E+00 Ba-140
  • 9.55 E-01 8.45 E+00 la-140
  • 0.00 E+00 3.40 E+00 900814 K-40 1.42 E+03 9.29 E+01 Cs-134 *-3.28 E+00 2.57 E+00 Cs-137
  • 3.01 E+00 2.52 E+00 Ba-140
  • 5 55 E+00 8.36 E+00 la-140 *-2.17 E-01 3.50 E+00 900828 K-40 1.38 E+03 8.71 E+01 Cs-134
  • 3.38 E+00 2.80 E+00 Ba-140
  • 4 45 E+00 9.99 E+00 La -140 *-2 96 E+00 3.69 E+00 900910 K-40 1.42 E+03 8.13 E+01 Cs-134
  • 5.90 E-01 2.47 E+00 Cs-13?
  • 2.00 E+00 '2.36 E+00 Ba -140 *-4 48 E-01 ~
9. 57 E+00 la-140
  • 2 47 E+00 3.82 E+00
  • Oenotes a result less than the detection l imi t.

A-137

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOO NUCI IOE RESULT UNCERTAINTY 59 900925 K-40 1.33 E+03 9.08 E+01 CG-134 *-2.18 E+00 3.20 E+00 Cs-137 *-2.50 E+00 3.33 E+OQ Ba -140

  • 4.51 E+00 1.10 E+01 La-140
  • 1.23 E+00 4.82 E+00 901009 K-40 1. 31 E+03 7.40 E+01 Cs-134
  • 8. 56 E-01 2.21 E+00 Ba-140 *-8. 17 E+00 8.92 E+00 La-140 *-1.31 E+QQ 3.96 E+00 901106 K-40 1.42 E+03 8.41 E+01 Cs-134 *-4.67 E-01 2. 36 E+00 Cs-137
  • 2.36 E+00 2.33 E+00 Ba-140 *-7.49 E+00 1.07 E+Ol La -140 *-4. 17 E+00 4.56 E+00 9012Q4 K-40 1. 32 E+03 8.50 E+01 Cs-134 *-7. 26 E-01 2.36 E+00 Cs-137 *-5.64 E-01 2.22 E+00 Ba -140
  • 2.55 E+00 8.76 E+00 La-140
  • 4.12 E+00 3.98 E+00
  • Denotes a result less than the detection limit.

A-138

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 62 (a) 900515 K-40 1.28 E+03 8.07 E+01 Cs-134

  • 2.05 E+00 2.49 E+00 Cs-137 *-4.82 E-Ol 2.42 E+00 Ba-140 *-4.05 E-01 8.19 E+00 La-140
  • 5.75. E-01 3.52 E+00 900612 K-40 1.23 E+03 8.05 E+01 Cs-'134
  • 9.69 E-01 2.44 E+00 Cs-137 *-7.04 E-02 2.45 E+00 Ba -140
  • 5 54 E+00 9.37 E+00 La -140
  • 2.18 E-01 3.88 E+00 900626 K-40 1.20 E+03 7.89 E+01 Cs-134
  • 5.51 E-Ol 2.16 E+00 Ba -140
  • 2.27 E+00 6.98 E+00 La-140 *-9.16 E-01 3.38 E+00

~

900717 K-40 1.32 E+03 8.34 E+01 Cs-134 1.70 E+00 2.18 E+00 Cs-137 3.02 E+00 2.16 E+00 Ba-140 1.38 E+00 7.74 E+00 La-140 0.00 E+00 3.38 E+00 900731 K-40 1.29 E+03 7.80 E+01 Cs-134 *-3.21 E+00 2.29 E+00 Cs-137

  • 1.69 E+00 2.35 E+00 Ba -140
  • 3.53 E+00 7.71 E+00 La-140 *-2.34 E+00 3.50 E+00 900814 K-40 1.42 E+03 8.00 E+Ol Cs-134
  • 4.70 E+00 2.37 E+00 Ba-140 *-3.86 E-01 7.72 E+00 La-140 *-2.84 E+00 3.22 E+00 (a) New station added to replace discontinued station 40.
  • Denotes a result less than the detection limit.

A"139

TABLE A-12.1 (Cont.)

COLLECTION Results in pCi/liter OVERALL

~ o LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 62 900828 K-40 1.28 E+03 8.42 E+01 Cs-134

  • 3 44 E+00 2.38 E+00 Ba-140 *-1 50 E+00 8.93 E+00 La -140
  • 2.41 E+00 3.91 E+00 900910 K-40 1.24 E+03 7.74 E+01 Cs-134 9.63 E-Ol 2.18 E+00 Cs-137 1.25 E+00 2.31 E+00 Ba-140 4.34 E-01 9.03 E+00 La-140 6.28 E-01 4.28 E+00 900925 K-40 1.29 E+03 7.91 E+01 Cs-134 *-1.55 E+00 2 33 E+00 Cs-137
  • 2.02 E+00 2.36 E+00 Ba-140 *-3.99 E+00 8.21 E+00 901009 La-140 K-40 Cs-134
  • -2 70

] 44

  • 6.89 E+00 E+03 E-01 3.74 8.42 2.19 E+00 E+01 E+00

~ o Cs-137

  • 4.17 E+00 2.37 E+00 Ba-140 *-2.99 E-01 1.09 E+01 La-140 *-2.89 E+00 5.05 E+00 901106 K-40 1. 23 E+03 8.63 E+Ol Cs-134
  • 1.49 E+00 2.50 E+00 Ba-140 *-5.52 E+00 1.17 E+Ol La -140 *-2.74 E+00 4.75 E+00 901204 K-40 1.24 E+03 8.06 E+Ol Cs-134
  • 2.37 E+00 2.38 E+00 Ba-140 *-1.19 E+01 1.35 E+Ol La-140
  • 2.44 E+00 5.68 E+00
  • Denotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 63 900717 K-40 1. 24 E+03 8.26 E+Ol Cs-134 *-3 01 E+00 2.42 E+00 Cs-137

  • 2.34 E+00 2.51 E+00 Ba-140 *-1.63 E+00 9.87 E+00 La-140
  • 0 00 E+00 3.97 E+00 900731 K-40 1.32 E+03 8.17 E+Ol Cs-134 *-1.49 E-01 2.38 E+00 Cs-137
  • 1.70 E+00 2.24 E+00 Ba-140 *-3.25 E+00 8.34 E+00 La-140
  • 1.18 E+00 3.59 E+00 900814 K-40 1.09 E+03 7.73 E+Ol Cs-134 *-3.83 E-01 2.31 E+00 Cs-137
  • 2.08 E+00 2.29 E+00 Ba -140
  • 2.57 E+00 8.98 E+00 La-140
  • 2.13 E-01 3.46 E+00 900828 K-40 1.31 E+03 8.53 E+01 Cs-134
  • 3.25 E-01 2.51 E+00 Ba -140 *-2.06 E+00 1.03 E+01 La-140
  • 5.29 E-01 4.52 E+00 900910 (a) 900925 K-40 1.29 E+03 9.10 E+01 Cs-134
  • 2.30 E+00 2.51 E+00 Ba-140
  • 1.45 E+00 9.44 E+00 La-140 *-1 14 E+00 4.05 E+00 901009 K-40 1.18 E+03 7.80 E+O1 Cs-134
  • 5.29 E-01 2.22 E+00 Ba-140 *-5 41 E+00 8.91 E+00 La-140 2.75 E+00 3.63 E+00 (a) Hilk sample not available.
  • Denotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

COLLECTION Results in pCi/liter OVERALL

~ o LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 63 901106 K-40 1. 07 E+03 6.84 E+01 Cs-134

  • 1.90 E+00 2.27 E+00 Ba-140
  • 3.18 E+00 1.10 E+01 La-140 *-3. 16 E+00 4. 29 E+00 901204 K-40 9.34 E+02 7.36 E+Ol Cs-134
  • 7.90 E-01 2.56 E+00 Ba-140
  • 1.65 E+00 9.25 E+00 La-140 *-9.93 E-01 3.80 E+00

~ o

  • Denotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 96 900109 K-40 1.44 E+03 9.17 E+01 Cs-134

  • 2.67 E+00 2.28 E+00 Ba -140
  • 2.00 E+00 7.15 E+00 La -140
  • 2.52 E+00 3.07 E+00 900206 K-40 1.35 E+03 7.65 E+01 Cs-134 *-7.44 E-01 2.23 E+00 Cs-137
  • 2.41 E+00 2.25 E+00 Ba-140 +-2.02 E-01 8.65 E+00 La-140
  • 9.76 E-01 3.88 E+00 900306 K-40 1.44 E+03 7.37 E+01 Cs-134
  • 6.92 E-01 2.09 E+00 Cs-137 *-1.52 E-01 2.03 E+00 Ba-140 *-1 54 E+00 5.82 E+00 La-140
  • 1.17 E-01 2.15 E+00 900403 K-40 1.27 E+03 8.29 E+Ol Cs-134
  • 7.01 E-01 2.54 E+00 Ba-140 *-6.93 E+00 8.1? E+00 La-140
  • 2.08 E+00 3.57 E+00 900417 K-40 1.30 E+03 8.00 E+01 Cs-134 *-4 71 E-01 2.22 E+00 Cs-137
  • 1.72 E+00 2.17 E+00 Ba-140
  • 1.49 E+00 7.86 E+00 La-140 *-1.20 E+00 3.25 E+00 900501 K-40 1.22 E+03 7.41 E+01 Cs-134 *-2 97 E+00 2.18 E+00 Cs-137
  • 2.90 E-01 2.28 E+00 Ba-140 "-1.09 E+00 7. 27 E+00 La-140 *-3.92 E+00 3.55 E+00 900515 K-40 1.26 E+03 8.61 E+01 Cs-134
  • 9.95 E-01 2.54 E+00 Cs-137 *-1.12 E+00 2.50 E+00 Ba -140
  • 2.36 E-01 8.14 E+00 La-140 *-8.51 E-01 3.53 E+00
  • Denotes a result less than the detection limit.

TABLE A-12.1 (Cont.)

.Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 96 900612 K-40 1.32 E+03 8.48 E+01 Cs-134 *-1 85 E-01 2.80 E+00 Cs-137

  • 1.30 E+00 2.51 E+00 Ba-140 *-1 63 E+00 9.31 E+00 La-140
  • 2.44 E-01 3.68 E+00 900626 K-40 1.17 E+03 8. 13 E+Ol Cs-134
  • 1.42 E-01 2.42 E+00 Ba -140 *-2 24 E+00 8.16 E+00 La -140 *-4 02 E-01 3.66 E+00 900717 K-40 '.42 E+03
  • 7.31 E-02 8.20 E+Ol Cs-134 2.32 E+00 Cs-137
  • 2.37 E+00 2.51 E+00 Ba-140
  • 4 69 E+00 8.86 E+00 La-140 *-1.22 E+00 3.77 E+00 900731 K-40 1.36 E+03 8.52 E+01 Cs-134
  • 2.37 E+00 2.31 E+00 Cs-137 " 1.31 E+00 2.08 E+00 Ba -140 *-2.55 E+00 7.82 E+00 La-140 *-4 11 E-01 3.35 E+00 900814 K-40 1.38 E+03 9.45 E+01 Cs-134
  • 1.74 E+00 2.58 F+00 Ba-140
  • 4.12 E+00 9.60 E+00 La-140
  • 1.73 E+00 3.73 E+00 900828 K-40 1.30 E+03 8.26 E+01 Cs-134 * ] 49 E+00 2.45 E+00 Cs-137 *-2.06 E-01 2.43 E+00 Ba -140 *-2 89 E+00 9.84 E+00 La -140 *-1 97 E+00 3.89 E+00 900910 K-40 1.34 E+03 8.15 E+01 Cs-134
  • 3.95 E+00 2.31 E+00 Ba-140 *-1.98 E+00 9.02 E+00 La-140
  • 1.68 E+00 4.09 E+00 Denotes a result less than the detection imi t.

1 A-144

TABLE A-12.1 (Cont.)

Results in pCi/liter COLLECTION OVERALL LOCATION PERIOD NUCLIDE RESULT UNCERTAINTY 96 900925 K-40 1.33 E+03 8.65 E+01 Cs-134 8.00 E-02 2.21 E+00 Cs-137

  • 5. 56 E-01 2.38 E+00 Ba-140 *-3. 11 E+00 8.65 E+00 La-140
  • 4. 62 E-01 3.64 E+00 901009 K-40 1.31 '+03  ?.86 E+01 Cs-134
  • 6.75 E-01 2.38 E+00 Ba -140 *-6.05 E+00 9.75 E+00 La-140 *-8.47 E-01 4.37 E+00 901106 K-40 1.43 E+03 7.13 E+01 Cs-134 *-3.33 E+00 2.96 E+00 Cs-137 *. 7.05 E-01 3.04 E+00 Ba-140
  • 4.26 E-01 1.47 E+01 La-140 *-6. 19 E+00 5.27 E+00 901204 K-40 1.47 E+03 8. 27 E+01 Cs-134
  • 8.28 E-01 2.33 E+00 Cs-137 *-1.32 E+00 2.37 E+00 Ba-140 *-1.53 E+00 1.13 E+01 La-140
  • 7.39 E-01 4. 90 E+00 Denotes a result less than the detection limit.

A-145

TABLE A-12.2 Results in pCi/liter NUMBER NUMBER

~ o NUCLIOE AVERAGE LOW HIGH SAMPLES POSITIVE K-40 ( I) 1. 27E+03 9. 34E+02 1. 64E+03 79 79 K-40 (C) 1. 34E+03 1. 17 E+03 1'. 47 E+03 18 18 Cs-134 (I) 3.86E-Ol -3.28E+00 3.03E+00 79 Cs-134 (C) -4.49E-02 -3.33E+00 2.37E+00 18 Cs -137 ( I) 1. 60E+00 -2;50E+00 6.78E+00 79 Cs-137 (C) 9.86E-Ol -1.32E+00 3.95E+00 18 (I)

~

Ba-140 -5.88E-Ol - 1. 19E+01 9.89E+00 79 o

Ba-140 (C) -1.56E+00 -6.93E+00 4. 12E+00 18 La -140 ( I) -3. 31E-01 -4. 45E+00 4. 12E+00 79 La-140 (C) -3.59E-01 -6.19E+00 2.52E+00 18

( I) Indicator Stations (C) Control Station

TABLE A-13.1 Results in pCi/kilogram (wet)

COLLECT ION OVERALL LOCATION DATE NUCLIDE RESULT UNCERTAINTY 9B 900626 Cs-134 *-1.96 E+00 7.48 E+00 Onion Cs-137

  • 2.55 E+00 7.54 E+00 I-131 *-5.94 E+00 1.29 E+01 9B 900718 Cs-134 *-9.10 E-01 4.20 E+00 Potatoes Cs-137
  • 3.10 E+00 4.10 E+00 I-131 *-3 01 E+00 8.68 E+00 9B 900814 Cs-134 *-2 52 E-01 6.15 E+00 Potatoes Cs-137
  • 2.64 E+00 6.06 E+00 I-131 *-1.29 E+01 1.95 E+01 9B 900910 Cs-134
  • 8.73 E+00 . 7.56 E+00 Onion Cs-137
  • 8.69 E+00 7.87 E+00 I-131
  • 1.39 E+01 1.45 E+01 37 900626 Cs-134 *-1 20 E+01 6.42 E+00 Onion Cs-137
  • 7.13 E+00 6.61 E+00 I-131 *-4 19 E+00 1.11 E+01 37 900718 Cs-134 *-9.88 E+00 7.19 E+00 Potatoes Cs-137
  • 2.91 E+00 7.13 E+00 I-131 *-3 37 E+00 1.40 E+01 37 900814 Cs-134
  • 5 47 E+00 5.43 E+00 Carrots Cs-137
  • 3.16 E+00 5.55 E+00 I-131 *-9.35 E+00 1.53 E+01 37 900910 Cs-134
  • 4.45 E+00 6.01 E+00 Onion Cs-137
  • 3.33 E+00 5.89 E+00 I-131 *-9 15 E+00 1.19 E+Ol Denotes a result less than the detection limit.

TABLE A-13.2 Results in pCi/kilogram (wet)

NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITI VE Cs-134 (I) -2.99E+00 -1. 20E+01 5. 47 E+00 Cs-134 (C) 1.40E+00 -1. 96E+00 8. 73E+00 Cs-137 (I) 4.13E+00 2. 91E+00 7. 13E+00 Cs -137 (C) 4. 25E+00 2.55E+00 8.69E+00 I-131 (I) -6.52E+00 -9.35E+00 -3.37E+00 0.

I-131 (C) -1.99E+00 -1. 29E+01 1. 39E+01

~ o

( I) Indicator Stations (C) Control Station

TABLE A-14.1 Results in pCi/kilogram (wet)

LLE TI N VERALL LOCATION DATE NUCLIDE RESULT UNCERTAINTY 9B 900626 Cs-134

  • 1.58 E+00 3.13 E+00 Raspberries Cs-137 *-4.78 E-01 3.01 E+00 I-131
  • 1.24 E+00 4.94 E+00 9B 900718 Cs-134
  • 3 43 E-Ol 2.87 E+00 Apricot Cs-137
  • 3.32 E+00 2.85 E+00 I-131 *-1.84 E+00 5.86 E+00 9B 900814 Cs-134 0.00 E+00 3. 53 E+00 Nectarine Cs-137 3.95 E+00 3.49 E+00 I-131 4.22 E-01 1.02 E+01 9B 900910 Cs-134 *-1 67 E+00 4.06 E+00 Plum Cs-137
  • 4 05 E+00 4.15 E+00 I-131
  • 1.12 E+00 7.82 E+00 37 900626 Cs-134
  • 1.51 E+00 3.67 E+00 Raspberries Cs-137 *-4 44 E-02 3. 61 E+00 I-131
  • 8.40 E+00 6.01 E+00 37 900718 Cs-134
  • 1.41 E+00 4. 20 E+00 Apricot Cs-137 *-3 55 E+00 4. 26 E+00 I-131 *-1.42 E+00 8. 38 E+00 37 900814 Cs-134 *-6.32 E-01 3. 14 E+00 Peaches Cs-137 *139 E+00 2.89 E+00 I-131 *-2.01 E+00 7.10 E+00 37 900910 Cs-134 *-2 48 E+00 6.95 E+00 Plums Cs-137
  • 6.40 E+00 7.29 E+00 I-131 *-7 79 E+00 1.54 E+01 61 900612 Cs-134 3.97 E-01 6.02 E+00 Cherries Cs-137 1.13 E+01 6.07 E+00 I-131 1.56 E+00 2.19 E+01 91 900918 Cs-134
  • 7.86 E-01 5.24 E+00 Apples Cs-137
  • 4.46 E+00 5.55 E+00 I-131 *-6 63 E+00 1.05 E+01 Denotes a result less than the detection limit.

TABLE A-14.2 Res ul ts in pCi /ki 1 ogr am (wet)

NUMBER NUMBER NUCLIDE AVERAGE LOW HIGH SAMPLES POSITIVE Cs-134 (I) 1.65E-Ol - 2. 48E+00 1. 51E+00 Cs-134 (C) 6.33E-02 -1.67E+00 1.58E+00 Cs-137 ( I) 3.33E+00 -3.55E+00 1. 13E+01 Cs -137 (C) 2. 71E+00 -4. 78E-01 4.05E+00 4

I-131 (I) -1.32E+00 -7. 79E+00 8.40E+00 I-131 (C) 2.36E-01 -1. 84E+00 1.24E+00

~I

( I) Indicator Stations (C) Control Station A-150

TABLE A-15.1 Results in pCi/kilogram (wet)

COLLE T ION OVERALL LOCATION DATE NUCLIDE RESULT UNCERTAINTY 9B 900417 Cs-134

  • 1.18 E+00 4.78 E+00 Asparagus Cs-137
  • 5.45 E+00 4. 57 E+00 I-131 *-1 47 E+00 9.16 E+00 9B 900626 Cs-134 2.92 E+00 4.05 E+00 Beet Top Cs-137 7.14 E-01 4. 14 E+00 I-131 1.87 E+00 7.49 E+00 9B 900515 Cs-134 *-2.13 E+00 8.37 E+00 Asparagus Cs-137 *-1.09 E+00 8.54 E+00 I-131 *-6.14 E+00 1.51 E+01 9B 900718 Cs-134
  • 1.40 E+00 7.39 E+00 Cabbage Cs-137
  • 1.28 E+01 7.43 E+00 I-131 *-1.14 E+01 1.66 E+01 9B 900814 Cs-134
  • 3.33 E+00 9.84 E+00 Cabbage Cs-137 *-2 55 E-01 1.02 E+01 I-131 *-3.82 E+01 2.97 E+01 9B 900910 (a) Cs-134 1.53 E+00 5.57 E+00 Green Beans Cs-137 8.36 E-01 5.64 E+00 I-131 9.12 E+00 1.08 E+01 37 900417 Cs-134
  • 3.74 E+00 3.67 E+00 Asparagus Cs-137
  • 2.75 E+00 3.62 E+00 I-131 *-1 10 E+00 7.68 E+00 37 900626 Cs-134
  • 8.69 E+00 7,89 E+00 Beet Top Cs-137
  • 1.01 E+Ol 7.89 E+00 I-131 *-9.52 E+00 1.30 E+O1 37 900515 Cs-134
  • 1.65 E+01 1.06 E+01 Asparagus Cs-137
  • 1.51 E+01 1.11 E+01 I-131 *-4 04 E+00 1.89 E+01 37 900718 Cs-134 *-6.91 E-01 1.07 E+O1 Cabbage Cs-137
  • 1.03 E+01 1.08 E+Ol I-131 *-1.19 E+01 2.22 E+Ol (a) Substitute for leafy vegetables which are unavailable.
  • Denotes a result less than the detection limit.

A-151

TABLE A-15.1 (Cont.)

Results in pCi/kilogram (wet)

LLE TI N VERALL LOCATION DATE NUCLIDE RESULT UNCERTAINTY 37 900814 Cs-134

  • 7.28 E+00 8.99 E+00 Cabbage Cs-137
  • 8.46 E+00 8.84 E+00 I-131
  • 3.49 E+00 3.06 E+01 37 900910 (a) Cs-134 *-4.49 E+00 5.05 E+00 Tomatoes Cs-137
  • 7.24 E+00 5.01 E+00 I-131 *-2.77 E+00 1.02 E+Ol (a) Substitute for leafy vegetables which are unavailable.
  • Denotes a result less than the detection limit.

A-152

TABLE A-15.2 Results in pCi/kilogram (wet)

NUMBER NUMBER NUCLIDE AVERAGE LOW HIG H SAMPLES POSITIVE Cs-134 (I) 5. 17E+00 -4.49E+00 1. 65E+01 Cs-134 (C) 1. 37 E+00 -2. 13E+00 3.33E+00 Cs-137 (I) 8.99E+00 2.75E+00 1. 51E+01 Cs-137 (C) 3.08E+00 -1. 09E+00 1.28E+01 I -131 ( I) -4. 31E+00 -1.19E+01 3. 49E+00 I-131 (C) -7.70E+00 -3. 82E+01 9. 12E+00 (I) Indicator Stations (C) Control Station A-153

~,

~ o

APPENDIX B: TELEDYNE ISOTOPES 1990 EPA INTERCOMPARISON RESULTS

TABLE B"1 COLLECTION EPA ISOTOPE OATE TI RESULTS (a) RESULTS (b) OTHER LABS (c)

Gr -Beta 900126 12.33 2 l. 53 12.0 5.00 14.96 2 11.6 Gr-Beta 900417 53.33 2 l. 53 52.0 5.0 49.06 1 6.39 Gr -Beta Gr-Beta 900511 17.00 1 1.00 15.0 5.0 5.0 16.16 10.91 1 t 3.85 2.25 900921 11.00 2 1.00 10.0 GR-Beta 901030 51.00 2 2.31 53.0 5.0 50.78 2 6.32 Sr-89 900112 24.00 2 1.73 25.00 5.00 25.14 2 7.22 Sr-90 19.67 2 2.52 20.00 1.50 19.66 2 3.69 Sr-89 900417 10.67 2 1.15 10.0 5.0 12.71 2 25.09 Sr-90 9.67 2 0.58 10.0 1.5 9.50 2 0.99 Sr-89 900504 6.67 2 0.58 7.0 5.0 7.64 + 2.26 Sr-90 6.67 2 0.58 7.0 5.0 7.02 1 1.71 Sr-89 900914 8.67 2 0.58 10.0 5.0 9.89 2 2.72 Sr-90 9.0 2 1.00 9.0 5.0 9.30 1 1.98 Co-60 900209 15.00 1 3.46 15.00 5.00 15.31 2 2.28 Zn-65 131.33 1 9.07 139.00 14.00 138.93 2 9.60 Ru-106 N 113.67 2 4.04 139.00 14.00 133.60 1 14.22 II Cs-134 15.33 2 2.31 18.00 5.00 17.00 2 2.14 Cs-137 N 19.33 2 3.21 18.00 5.00 18.76 2 2.40 Ba -133 N

66.00 2 3.46 74.00 7.00 72.49 2 6.21 H-3 900223 4900.00 1 100.00 4976.00 2 498.00 4839.04 2 929.23 Ra-226 900309 4.73 2 0.47 4.9 0.7 5.20 k 0.88 Ra-228 13.00 2 1.00 12.7 1.9 12.25 2 2.66 Ra-226 900417 5.67 2 0.15 5.0 0.8 . 4.96 + 0.83 Ra-228 9.37 2 1.44 10.2 1.5 10.43 2 2.39 Ra-226 901109 7.27 2 0.38 7.4 1.1 7.11 2 1.10 Ra-228 7.57 2 0.32 7.7 1.9 8.10 2 1.99 Cs-134 900417 12.67 a 1.53 15.0 5.0 14.44 2 1.77 Cs-137 16.33 1 1.15 15.0 5.0 15.80 2 1.88 Co-60 900608 25.33 2 2.52 24.0 5.0 25.12 k 2.69 Zn-65 149.18 2 12.30 Ru-106 Cs-134 N

II 148.67 2 3.06 196.00 2 20.66 23.67 1 2.89 148.0 210.0 24.0 15.0 21.0 5.0 201.0 23.26 2 i 17.01 2.10 Cs-137 N 24.67 2 2.08 25.0 5.0 26.21 2 2.61 Ba-133 N 93.00 l. 6.08 99.0 10.0 96.37 2 8.16 H-3 900622 2900. 2 100.00 2933.0 358.0 2966.81 1 285.64 Ra-226 900713 11.37 2 0.60 12.1 1.8 11.44 1 1.85 Ra-228 4.20 1 0.75 5.1 1.3 5.50 2 1.40 I-131 900810 36.00 1 3.00 39.0 6.0 40.26 1 4.10 Co-60 901015 21.00 2 1.00 20.0 5.0 20.53 2 2.53 Zn-65 115.00 2 11.53 115.0 12.0 116.25 2 9.89 Ru-106 142.00 2 8.66 151.0 15.0 140.39 1 15.33 Cs-134 11.00 1 0.00 12.0 5.0 11.89 z 2.09 B" 1

TABLE B-1 (Co nt. )

COLLECTION EPA ISOTOPE OATE TI RESULTS (a) RESULTS (b) OTHER LABS (c)

Cs-137 901015 16.33 2 2.52 12.0 2 5.0 13.11 2 2.17 Ba-133 94.67 1 5.13 110.0 2 11.0 107.73 2 9.22 (e)

H-3 901019 7133.33 2 251.66 7203.0 2 720.0 7125.08 + 671.93 Gr-Beta 900330 31.67 2 0.58 31.0 1 5.0 32.19 2 3.68 Sr-90 9.33 2 0.58 10.0 2 1.5 9.69 2 1.36 Cs-137 N 10.67 1 1.15 10.0 2 5.0 11.S6 2 2.05 Gr-Beta 900831 63.33 2 1.53 62.0 2 5.0 64.66 2 6.77 Sr-90 18.00 1 1.00 20.0 2 5.0 19.45 2 2.51 Cs-137 18.33 2 3.21 20.0 2 5.0 22.70 1 3.91 Sr-89 900427 24.67 2 1.53 23.0 5.0 23.14 5.10 Sr-90 24.00 2 0.00 23.0 5.0 22.33 3.38 I-131 89.67 2 3.21 99.0 10.0 98.49 8.13 Cs-137 27.33 2 2.52 24. 0 5.0 24.65 3.03 K 1483.33 2 75.06 1550.0 78.0 1548.38 117.33 Sr-89 900928 9.0 2 2.65 16.0 5.0 13.53 a 4.28 (f)

Sr-90 15.33 2 0.58 20.0 5.0 17.57 3.25 I-131 54.67 2 1.53 58.0 6.0, 58.88 4.67 Cs-137 23.00 2 1.73 20.0 5.0 21.47 2.35 K 1710.00 2 65.51 1700.0 85.0 1713.52 124.69 Footnotes:

(a) Teledyne Results - Average a one sigma. Units are pCi/liter for water and milk except K is in mg/liter. Units are total pCi for air particulate filters (b) EPA Results - Expected laboratory precision ( 1 sigma). Units are pCi/liter for water, and milk except K is in mg/liter. Units are total pCi for air particulate filters (c) Average concentration plus or minus one sigma, based on range of values encountered.

B-2

TABLE B-1 (Cont.)

COLLECTION EPA ISOTOPE DATE TI RESULTS (a) RESULTS (b) OTHER LABS (c)

Footnotes: (Cont.)

(d) No apparent cause for the low results were found. Three aliquots of the sample were counted on three separate detectors. The results of all three were similar. The calibration curve fit is good (0.997). Ru- 106 was obtained from the EPA. Results from the EPA did not exceed two normalized standard deviations. No additional follow-up is necessary, but we will continue to monitor the results. New calibrations were completed in March 1991.

(e) There is no apparent reason for the deviation between the EPA and Teledyne Isotopes values. Other isotopes in the sample were measured accurately . The calculations were reviewed and activities calculated from other Ba-133 gamma rays. Results were reproduced as reported.

(f) Incomplete removal of calcium, lead to erroneously high strontium yields. More care is being taken in the strontium nitrate and strontium sulfate precipitation steps to ensure a final volume of at least 20 ml in the strontium sulfate step.

Reanalysis of internal QC samples produced good results after implementing the corrective action.

B-3

O.

APPENDIX C: 1990 SPECIAL SAHPLE RESULTS

~.

~.

The analytical results presented in Appendix C are for samples collected outside the routine monitoring program. They include the results of grab samples taken from the plant intake and discharge lines, as well as the results of air samples taken at a nonroutine monitoring locat'ion near the plant.

During periods of composite water sampler inoperability, efforts are focused on correcting the problem(s) and fixing the sampler before the start of the next sampling period. In addition, if repair is not expected to be com-pleted within a few days, grab samples are taken from the intake or dis-charge lines as a matter of "good practice." The results of these composites of the grab samples are presented in Table C-1. The special Station 27 sample for the period 5/10/90 to 5/ll/90 included detectable levels of cobalt-60 and zinc-65 resulting from releases associated with plant outage activities.

During February, March and April 1990, special air samples were collected at the training facility near the turbine generator building, in order to determine whether there was a plant effect that was not apparent from the air sampling results for the routine monitoring stations. The gross beta and iodine-131 results for these samples are presented in Table C-2, along with the results for samples taken at the nearest routine air sampling station, Station 57, during the same periods. There were no significant differences between the results for the Station 57 and the results for the special station.

A test of the environmental TLD fade characteristics for the annual distri-bution was also conducted during 1990 (see Section 5.1). As described in Sections 4.0 and 5.0, none of the TLDs from a batch suspected to have a higher than usual signal fade rate were collected with nine TLDs from a batch having a normal 'fade rate. The two sets of TLDs remained at field locations for the year, then were retrieved and processed. The results of the two batches are presented in Table C-3. The results for the set with the suspected higher signal fade rate were approximately 12% lower than the results for the other TLD set. The set with the apparent higher fade rate i.e., the 600 series, will, therefore, no longer be used.

TABLE C-1 F WAT R RA AMP MP Results in pCi/liter COLLECTION OVERALL L ATI N P D N IDE N TAINTY 26 900120 to 900125 Gr-B 1.3 E+00 7.0 E-01 Be-7

  • 6 1 E+00 1.6 E+01 K-40 1.2 E+02 2.0 E+01 Mn-54 1.1 E+00 1.S E+00 Co-58 4.6 E-01 1.7 E+00 Fe-59 1.5 E-01 3.9 E+00 Co-60 8.9 E-01 1.7 E+00 Zn-65 * -3.1 E+00 3.6 E+00 Zr-95 3.2 E+00 3.3 E+00 Nb-95 1.8 E+00 1.7 E+00 Cs-134 1.3 E+00 1.6 E+00 Cs-137 1.4 E+00 1.7 E+00 Ba-140 2.8 E+00 7.7 E+00 La-140 9.8 E-01 4.0 E+00 Ra-226 8.0 E+Ol 3.5 E+01 Th-228 1.1 E+01 3.0 E+00 26 900703 to 900710 Gr-B 1.7 E+00 9.0 E-01 A

Be-7 5 E+00 2.0 E+01 K-40 * -1.1 E+01 2.8 E+01 Mn-54 -1.1 E+00 1.9 E+00 Co-58

  • 3 E-01 2.0 E+00 Fe-S9
  • 3 E-01 2.3 E+OC Zn-65
  • 3.8 E-01 4.7 E+00 Zr-95 4.9 E+00 4.4 E+00 Nb-95
  • 1 5 E-01 2.0 E+00 Cs-134
  • 8 7 E-01 2.1 E+00 Cs-137 -3.7 E+00 2.3 E+00 Ba-140 * -6.5 E-01 7.9 E+00 La-140
  • 2.0 E-01 3.7 E+00 Ra-226 * -6.3 E+01 4' E+01 Th-228 -2.1 E+00 3.9 E+00
  • Denotes a result less than the detection limit.

C-2

TABLE C-1 (Cont.)

T F HATER RAB A Results in pC)/liter COLLECTION OVERALL A I N P I D N E INTY 27 900120 to 900125 Gr-B 1.6 E+Ol 2.0 E+00 Be-7 * -1.4 E+01 2.0 E+01 K-40

  • 7 9 E+00 2.2 E+01 Hn-54
  • 1 8 E-01 1.6 E+00 Co-58
  • 3 E-01 1.9 E+00 Fe-59
  • 4 6 E+00 5.2 E+00 Co-60 * -2.6 E-01 1.8 E+00 Zn-65
  • 1.3 E+00 3-8 E+00 Zr-95
  • 3 9 E+00 4.1 E+00 Nb-95
  • 2.2 E+00 2.0 E+00 Cs-134 8.1 E-01 1.8 E+00 Cs-137 1.9 E+00 1.7 E+00 Ba-140 -2.2 E+00 2.1 E+01 La-140 * -8.8 E+00 9.7 E+00 Ra-226
  • 7 4 E F00 3.1 E+00 27 900510 to 900511 Gr-B 5.4 E+01 4.0 EIOO Be-7
  • 2.0 E+00 2.3 E+01 Hn-54 2.9 E+00 1.8 E+00 Co-58 -2.3 E-01 1.9 E+00 Fe-59 * -1.4 E+00 4.4 E+00 Co-60 1.1 E+01 3.0 E+00 Zn-65 2.1 E+01 7.0 E+00 Zr-95 * -2.S E+00 3.9 E+00 Nb-95
  • 1.3 E+00 1.9 E+00 Cs-134 7.6 E+00 3.0 f+00 Cs-137 9.7 E+00 3.0 E+00 Ba-140
  • 5 1 E+00 1.0 E+01 La-140
  • 6 1 E+00 3.S E+00
  • Denotes a result less than the detection limit.

C-3

TABLE C-1 (Cont.)

R T F WAT R RAB AMP MP E Results in pCi/liter COLLECTION OVERALL ATI N P I 27 900808 to 900815 Gr-B 5.6 E+00 1.2 E+00 Be-7 * -9.0 E+00 2.6 E+01 K-40 * -2.7 E+01 6.9 E+01 Hn-54 2.9 E+00 2.5 E+00 Co-58 1.2 E+00 2.7 E+00 Fe-59

  • 1.7 E+00 2.7 E+00 Zn-65 * -2.6 E-01 6.0 E+00 Er-95
  • 2.6 E+00 6.0 E+00 Nb-95
  • 2.4 E+00 2.8 E+00 Cs-134 * -2.5 E+00 2.8 E+00 Cs-137 8.5 E-01 2,9 E+00 Ba-140 1.8 E+00 1.3 E+01 La-140 * -1.4 E+00 4.9 E+00 Ra-226 * -3.5 E+01 6.3 E+01 Th-228 * -1.3 E+01 5.0 E+00
  • Denotes a result less than the detection limit.

C-4

~ o o

TASLE C-2 MPA N F TH AMP R T T N A -P ANT I N AND AT T TI Results in pCi/cubic meter COLLECTION GROSS OVERALL OVERALL OA N NT N -1 1 N T NTY 900212 to 900220 Hear-Plant Station 2.6 E-02 2.0 E-03 2.4 E-03 6.8 E-03 Station 57 1.9 E-02 2.0 E-03 2.2 E-03 6. 1 E-03 900220 to 900226 Near-Plant Station 2.2 E-02 3.0 E-03 5.3 E-04 2.3 E-02 Station 57 1.8 E-02 3.0 E-03 5.3 E-04 2.3 E-02 900226 to 900305 Near-Plant Station 2.9 E-02 3.0 E-03 1.8 E-03 7.6 E-03 Station 57 2.8 E-02 3.0 E-03 1.8 E-03 7.6 E-03 900305 to 900312 Near-Plant Station 1.1 E-02 2.0 E-03 7.5 E-03 9.9 E-03 Station 57 6.2 E-03 1.7 E-03 7.5 E-03 9.9 E-03 900312 to 900319 Near-Plant Station 1.2 E-02 2.0 E-02 5.4 E-03 7.7 E-02 Station 57 1.0 E-02 2.0 E-03 5.4 E-03 7.7 E-02 900416 to 90042 Near-Plant Station 8.3 E-03 1.9 E-03 1.3 E-02 1.4 E-02 Station 57 8.2 E-03 1.9 E-03 1.3 E-02 1.4 E-02 C-5

TABLE C-3 V NHENTA TLD FAD

  • Results in mR/day 1 0646 0.215 0200 0.236 8 0647 0.234 0207 0.256 2 0648 0.208 0201 0.232 40 0650 0.200 0226 0.225 9 0651 0 '90 0208 0.216 10 0652 0.204 0209 0.232 47 0653 0.198 0235 0.224 46 0654 0.261 0234 0.290 53 0655 4 0240 ~24 Hean - 0.217 Hean - 0.242 Standard Deviation 0.024 Standard Deviation - 0.024
  • TLDs at one station were lost so only nine sets of results were evaluated.

C-6

APPENDIX D: 1990 SAMPLE DEVIATIONS

~ o

~ o i

ml 0vi i n During 1990, the majority of deviations from the sampling requirements of Table 3.12-1 of the Technical Specifications and Table 1 of the Site Certification Agreement involved the frequent periods of inoperability of the flow-proportional composite water sampler at Station 27 (discharge line) during the first eight months of the year and occasional periods of inopera-bility of various air samplers. These deviations are listed in Table D-l.

The composite water sampler at Station 27 was frequently inoperable during part of 1990 because some components of this complex flow-proportional sampling system were prone to failure under the conditions of low flow and intermittent sampling. The sample line from the discharge line also became plugged with sediment, which then caused sampler operational problems. In accordance with Plant 2 Technical Specifications, the sampler was returned to service before an entire sampling period had elapsed. The corrective actions taken to resolve these sampler operability problems included purchasing two new composite samplers for installation on the discharge line during the 1991 outage 'nd clearing the debris from the sampling line.

Since the sampling line was cleared in August, the sampler has operated consistently. In conjunction with the installation of the new samplers, a schedule will be determined for periodically clearing out the sampling line.

The most frequent causes of air sampler failures were power outages and stalled pumps resulting from gummy lubicating oil or oil leaks. The frequency of air sampler failures observed during 1990 appears to be fairly typical, considering the continuous operation of the samplers. Measures taken to prevent air sampler outages due to pump failures include adding oil when needed during weekly filter exchanges and preventive maintenance every six months.

The problems encountered during fish sampling were, in general, related to the unavailability of fish, inclement weather and high river water level.

These problems are mostly unpreventable.

~ s

~ o

TABLE D-1

~l AMP V AT N SAMPLE M DIA DATE ATI N P 8 M Air Particulate/ 900102 to 900108 Station 7 Power outage due to Iodine extremely high winds; shortened sampling time.

900102 to 900108 All Stations Air samples sent to wrong laboratory and not received at Teledyne until 1/18/90, 12 days after collection; LLDs range) from 0.02 to 0.03 pCi/m~ for iodine-131.

900108 to 900115 Station 7 Power outage due to high winds; shortened sampling time.

900122 to 900129 Station 6 Power outage due to repair work at White Bluffs substation.

900205 to 900212 Station 21 Power outage; shortened sampling time.

900226 to 900305 Station 48 Blown fuse; shortened sampling time.

900305 to 900306 Station 48 Location without sampler due to unavailability of replacement unit. Brought out replacement unit March 6.

900312 to 900319 Station 23 Sampler malfunction; shortened sampling time.

900409 to 900416 Station 8 Relay fuse on power pole burned out; shortened sampling time.

900416 to 900423 Station 8 Power outage; shortened sampling time.

900416 to 900423 Station 48 Relay fuse not repaired until 4/19/90; shortened sampling time.

D-2

TABLE D-1 (Cont.)

D V N SAMPLE M DIA DATE Air Particulate/ 900423 to 900430 Station 40 Brief power outage; Iodine slightly shortened sampling time.

900430 to 900507 Station 1 Power outage due to plant outage work; shortened sampling time.

II'00507 to 900514 Station 1 Power outage; shortened sampling time.

900507 to 900514 Station 9 Power outage due to work by PPSL; slightly shortened sampling time.

900514 to 900521 Station 1 Brief power outage; slightly shortened sampling time.

900521 to 900529 Station 9 Sampler failure; shortened sampling time.

900604 to 900611 Station 40 Sampler pump failure; shortened sampling time.

900716 to 900723 Station 7 Power outage due to DOE relocation of meteorological tower; shortened sampling time.

900716 to 900723 Station 9 Volume measurement indicator low; shortened sampling time since no replacement until 7/24/90.

900723 to 900730 Station 9 Shortened sampling time since no replacement unit until 7/24/90.

900723 to 900730 Station 4 Blown fuse; short sampling time.

900813 to 900820 Station 8 Pump failure; short sampling time..

D-3

TABLE D-1 (Cont.)

1 AMP D I N SAMPLE

~MDIA DAT L AT Air Particulate/ 900827 to 900904 Station 7 Power outage due to DOE Iodine equipment relocation activities; shortened sampling time.

900910 to 900917 Station 7 Power outage due to DOE equipment relocation activities; shortened sampling time.

901001 to 901008 Station 23 Blown fuse; short sampling time.

901119 to 901126 Station 40 Blown fuse; shortened sampling time.

901126 to 901203 Station 40 Blown fuse; short sampling time.

901203 to 901210 Station 40 Pump failure; shortened sampling time.

901210 to 901217 Station 7 Power outage due to DOE relocation activities; shortened sampling time.

Fish 900430 to 900508 Station 38 Bass sample from the Snake River was about one-half kilogram short due to lack of availability of the sample.

900924 to 901004 Station 38 The required 1.0 kg. of flesh from a third resi-dent species was not obtained due to lack of availability of fish.

Two smaller samples, one of squaw fish weighing 0.5 kg and one of bass weighing 0.5 kg, were each submitted for analysis to cover this requirement.

D-4

TABLE D-1 (Cont,)

1 AMP V T N SAMPLE M D D T T N Sediment 900410 Stations 33, Sediment sampling delayed 34 one week due to unavaila-bility of staff.

Milk 900501 to 900717 Station 40 Milk production stopped at this station. Another source of milk was sought within 5 kilometers (9.9 miles). None became available until July when Station 63, the Herr farm (6.4 miles SE), was added.

In the meantime, sampling at the other milk source available, the Howard farm, Station 62, began 5/15.

e.

on TLD 900928 to 901228 Station 4 This TLD was found missing in the field during the fourth quarter collection.

Vegetation 900417 Stations 9, No roots, fruits, or leafy 37 vegetables available; collected asparagus only.

900515 Stations 9, No roots, frui ts, or leafy 37 vegetables available; collected asparagus only.

900910 Stations 9, Leafy vegetables not 37 available.

Water 900102 to 900109 Station 26 Sampler inoperable due to a leak.

900112 to 900115 Station 27 Sampler inoperable, but began operating again before IKC shop could repair it.

900118 to 900128 Station 27 Sampler not operational due to failure of the positive displacement pump.

D-5

TABLE D-1 (Cont.)

P V T SAHPLE H 0 A TIN P BEH Water 902001 to 900204 Station 27 Electrical line grounded, causing sampling system outage.

900215 to 900216 Station 27 Sampler not operational due to failure of the positive displacement pump.

900401 to 900406 Station 27 Sampler not operational due to disconnection of the supervisory signal for the flow-proportional sampling mode.

900409 Station 27 Sampler not operational due to flow testing to determine if there was a sampling line restriction.

900415 to 900417 Station 27 Sampler not operational due to plugged sample line.

900417 to 900515 Station 27 Sampler not operating due to loss of the super-visory signal and outage work.

900602 Station 27 Sampler not operational due to a blown fuse.

900629 to 900710 Station 26 Sampler not operational because the potable water pump was out.

900714 to 900717 Station 27 Sampler not operational, but cause not determined.

0-6

TABLE D-1 (Cont.)

AM D V AT N SAMPLE DIA DAT AT N P 8 M Water 900731 to 900817 Station 27 Sampler not operational due to sampling line restriction. Problem Evaluation Request (PER) issued on 8/03/90 to document continued operational problems.

901213 to 901226 Station 27 Sampler not operational due to line restriction and valve misalignment.

D-7

No. of Copies No. of Copies m:

J.W. Baker A.L. Oxsen WNP-2 Plant Manager Deputy Hanaging Director Hail Drop 927M Hail Drop 1023 J.C. Bell, Manager B.A. Rathbone Plant Services Senior Health Physicist Mail. Drop 1020 Hail Drop 1020 T.E. Chapman G.C. Sorensen, Manager Principle Health Physicist Regulatory Programs Mail Drop 1020 Mail Drop 280 J.P. Chasse Supply System Library Senior Env. Licensing Engineer Mail Drop 330 Hail Drop 280 S.R. Telander, Manager A.I. Davis General Services Principle Health Physicist Mail Drop 185 Mail Drop 927K J.H. Thomas Environmental Programs Library Senior NP Engineer Mail Drop 1020 Mail Drop 927S (3) R.G. Graybeal, Manager G.A. Tupper, Manager WNP-2 Health Physics/Chemistry Communications and Mail Drop 927 External Affairs Hail Drop 325 A.G. Hosier, Manager WNP-2 Plant Licensing Ron Wardlow, Supervisor Hail Drop 955 Radiological Services Hail Drop 1020 W.A. Kiel Senior State Liaison WNP-2 Files Mail Drop 280 Mail Drop 964Y D.E. Larson, Manager Emergency Planning Hail Drop 1020 A.C. Harzette Risk Management Hail Drop 130 Clay Madden Senior QA Engineer Hail Drop 956B

D T BTI N No. of Copies No. of Copies Qf f~ie:

Administrator, Region V (3) J.E. Erickson U.S. Nuclear Regulatory Commission Head, Environmental Radiation 1450 Maria Lane, Suite 210 Section Walnut Creek, CA 94596-5368 Washington State Department of R.F. Brich Health'adiation Protection Division U.S. Department of Energy Thurston Airdustrial Center Richland Operations Office Bldg. 5, LE-13 P.O. Box 550 Olympia, WA 98504, Richland, WA 99352 J.C. Harrington E. Cowan Water Division Supervisor Environmental Protection Agency Water & Waste Utilities Region X Department 1200 6th Avenue City of Richland Seattle, WA 98101 505 Swift Boulevard P.O. Box 190 D. Denham Richland, WA 99352 Environmental Monitoring Battelle, PNL A. Haymaker 2400 Stevens Building 1721 Cottonwood Drive K5-09 Pasco, Washington 99301 P.O. Box 999 Richland, WA 99352 Mr. & Mrs. D.L. Howard 6470 Alder Road Alan Danielson Pasco, WA 99301 Washington State Department of Health D. Johnson Radiation Protection Division 7840 Alder Road P. O. Box 1311 Pasco, WA 99301 Richland, WA 99352 G. Kephart R.L. Dirkes, Supervisor Clinton Power Station Occupational & Env. Protection P.O. Box 678 Battelle, PNL Clinton, IL 01727 2400 Stevens Building P.O. Box 999 Manager, Nuclear Reactor Richland, WA 99352 Regulation U.S. Nuclear Regulatory (18)Document Control Desk Commission Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 (3) Dr. J.D. Martin Technical Vice President Teledyne Isotopes '0 VanBuren Avenue Westwood, NJ 07675

ITIS I No. of Copies No. of Copies Qff~i<~:

Meeker Brothers Dairy M.W. Tiernan Route 2, Box 2366 U.S. Department of Energy Sunnyside, WA 98944 Richland Operations Officer Federal Building R.D. Paris 825 Jadwin Avenue Radiation Control Section Richland, WA 99352 Oregon State Health Div.

P.o. Box 231 G.L. Toombs Portland, OR 97207 Oregon State Health Div.

Environmental Radiation W.J. Pettet Surveillance 1850 Cottonwood Drive 1400 SW 5th Avenue Pasco, WA 99301 Portland, OR 97201 K.R. Price J. Witczak Senior Research Scientist Washington State Department Occupational & Env. Protection of Ecology Battelle, PNL Mail Stop PV-ll 2400 Stevens Building Olympia, WA 98504-8711 P.O. Box 999 Richland, WA 99352 R. Woodruff, Project Manager Environmental Surveillance D. Ramerman Project Route 1, Box 1508-A Battelle, PNL Grandview, WA 98930 Battelle Boulevard P.O. Box 999 G.K. Samide Richland, WA 99352 Nuclear Engineering Department American Nuclear Insurers G. Yuhas The Exchange Suite 245 U.S. Nuclear Regulatory 270 Farmington Avenue Commission Farmington, CT 06032 Region V 1450 Maria Lane, Suite 210 M. Silverstone Walnut Creek, CA 94596-5368 Washington State Department of Health (3) J.J. Keller Public Health Laboratory Manager 1610 NE 150th EFSEC Seattle, WA 98155 Mail Stop FA-11 Olympia, WA 98504-1211 TER. Strong Director of the Division of Radiation Protection Washington State Department of Health Airdustrial Center Bldg. 6, LE-13 Olympia, WA 98504