B14829, Annual Radiological Environ Operating Rept for Jan-Dec 1993
| ML20029C956 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1993 |
| From: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES SERVICE CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B14829, NUDOCS 9405030082 | |
| Download: ML20029C956 (88) | |
Text
. NI#"~')Northeast i 7 8 " " 8" " "" h"' Cf
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Utilities System 8
Noriheast uiititie, service company P.O. Box 270 Ilartforal. CT 06141 0270 (203) 665-5000 April 26, 1994 Docket No. 50-213 B14829 Re:
10CFR50. 4 (b) (1)
U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D r.'
20555 Haddam Neck Plant Annual Radioloaical Environmental Operatina Report In accordance with the requirements of the Haddam Neck Radiological Effluent Monitoring Manual, an implementing document of the Haddam Neck Technical Specifications, two (2) copies of the Annual Radiological Environmental Operating Report are herewith submitted.
Copies of this report are being distributed in accordance with 10CFR50.4 (b) (1).
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY 11 J. F. Op6KA)
L Executive Vice President cc:
T. T. Martin, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant
.i W. J..Raymond, Senior Resident Inspector, Haddam Neck Plant 1
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM, CONNECTICUT
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' Utilities System Nonhe.n uso swa company P.O. Box 270 llartford, CT 061410270 (203) 665-5000 April 26, 1994 Docket No. 50-213 B14829 Re:
10CFR50. 4 (b) (1)
U.S. Nuclear Regulatory Commission Attention:
Document Control Desk I-Washington, DC 20555 Haddam Neck Plant Annual Radioloaical Environmental Operatina Reoort In accordance with the requirements of the Haddam Neck I
Radiological Effluent Monitoring Manual, an implementing document of the Haddam Neck Technical Specifications, two (2) copies of-the Annual Radiological Environmental Operating Report _are herewith submitted.
Copies of this report are being distributed I
in accordance with 10CFR50.4 (b) (1).
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY h-11Yr J.
F. OpaKA) _
L I
Executive Vice President cc:
T. T. Martin, Region I Administrator.
A. B. Wang, NRC Project Manager, Haddam Neck Plant W. J. Raymond, Senior Resident Inspector, Haddam Neck Plant I
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HADDAM NECK STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PERIOD JANUARY 1,1993 - DECEMBER 31,1993 DOCKET NO. 50-213 LICENSE NO. DPR-61 e
PREPARED FOR THE CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM, CONNECTICUT c-BY THE -
NORTHEAST UTILITIES SERVICE COMPANY.
BERLIN, CONNECTICUT,
e TABLE OF CONTENTS (4
?
Paae No.
1.0 Summary 1-1 2.0 Program Description 2-1 2.1 Sampling Schedule and Locations 2-1 2.2 Samples Collected During Report Period 2-7 3.0 Radiochemical Results 3-1 3.1 Summary Table 3-1 3.2 Data Tables 3-14
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i 4.0 Discussion of Results 4-1 5.0 Off-Site Dose Equivalent Commitments 5-1
-I 6.0 Discussion 6-1 Appendix A - Cow and Goat Census for 1993 A-1 I
Appendix B - Northeast Utilities QA Program B-1 l
Appendix C - Summary of EPA Interlaboratory Comparisons C-1 I
Ic
L 1.0
SUMMARY
The radiological environmental monitoring program for the Haddam Neck Plant
/
was continued for the period January through December 1993, in compliance with the Radiological Effluent Monitoring and Off-Site Dose Calculation Manual.
This annual report was prepared for the Connecticut Yankee Atomic Power l
Company (CYAPCO) by the Radiological Assessment Branch of the Northeast Utilities Service Company (NUSCO). All sample collections and preparations are performed by the Production Operations Services Laboratory. Gamma exposure measurements were performed by NUSCO at the Production Operations Services Laboratory. Gamma exposure measurements were performed by NUSCO at the Production Operations Services Laboratory.
All remaining laboratory analyses were performed by the primary contractor, Teledyne isotopes, Inc.
Yankee Atomic Environmental Laboratory was used to independently check on the primary contractor's laboratory as cart of the i
overall quality assurance program.
Radiological analyses were performed with gamma exposure measuring devices and on samples of air particulates and iodine, milk, broad leaf vegetation, well water, fruits, vegetables, river water, bottom sediment, shellfish, and fish. In evaluating the results of these analyses it is necessary to consider the variability of radionuclide uptake in environmental media. This variability is dependent on many factors, including plant release rates, meteorology, number and size of nuclear weapon tests, seasonal variability of fallout, soil characteristics, farming practices, and feed type.
Significant variations in measured levels of radioactivity could be caused by any one of these factors. Therefore, these factors need to be considered in order to properly explain any variations.
The predominant radioactivity, indicated by the results, was that from nonplant (not Haddam Neck) sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. As typical of previous years, plant related radioactivity was observed at some of the on-site gamma monitoring locations and in several other enviror4 mental samples. These include tritium in well water at the on-site location, tritium in river water near the East Haddam Bridge, cobalt-60, and cesium-137 in bottom sediment from near the end of the canal, cobalt-58 and cobalt-60 in shellfish downstream of the discharge canal, and cesium-137 in fish.
As usual, cesium-137 and strontium-90 were measured in both cow and goat milk. These levels are a result of nuclear weapons testing in the 1960s and not the result of plant operation. This can be concluded based on the facts that:
insufficient quantities of these isotopes have been released by the plant to I
account for the measured concentrations, chemically similar and plant related cesium-134 and strontium-89 have not been detected and comparable levels of cesium-137 and strontium-90 were detected prior to initial plant operation.
1-1
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The radiation dose (dose equivalent commitment) to the general public from the plant's discharges has been evaluated by two methods. One method utilizes the measured station's discharges and conservative transport models and the other utilizes the measured concentrations of radioactivity in the environmental l
media.
i The maximum whole body dose (station boundary) that could occur to a member of the general public wras 0.55 millirem from airborne effluents, 0.26 millirem from direct exposure, and 0.20 millirem from liquid discharges for a total whole body dose of 1.0 millirem. The average dose to a member of the public residing within 50 miles of the plant is 0.00023 millirem These doses are 4.0 percent and 0.00092 percent of the standards as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the general public. These standards are a small fraction (less than 10 percent) of the 280 mrem per year normal background radiation and are designed to be inconsequential in regard to public health and safety. Plant l
related doses are even a smaller fraction of the natural background; they are less than 10 percent of the variation in natural background in Connecticut.
Therefore, for the above stated reasons, the plant related doses have insignificant public health consequences.
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2.0 PROGRAM DESCRIPTION 2.1 Samolino Schedule and Locations L
The sample locations and the sample types and frequency of analysis are s
given in Table 2-1 and 2-2 and Figures 2.1 and 2.2. The program as I
described here includes both required samples as specified in the Radiological Effluent Monitoring and Off-Site Dose Calculation Manual and any extra samples.
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TABLE 2-1 ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The following lists the environmental sampling locations and the types of samples obtained at each location.
L9&Rti.3 9
Direction & Distance From N_Mmbg Hgmn Release Point *
- Semote Tvpf.s 1 -l
- On-site - Mouth of Discharge 1.1 Mi, ESE TLD Canal 2-1 Haddam-Park Rd.
0.8 Mi,S TLD f
3-1 Haddam-Jail Hill Rd.
0.8 Mi, WSW TLD 4-1 Haddam-Ranger Rd.
1.8 Mi, SW TLD, Air Particulate, lodine 5-1 On-site-Injun Hollow Rd.
0.4 Mi, NW TLD, Air Particulate, lodine 61 On-site-Substation 0.5 Mi, NE TLD, Air Particulate, lodine, Veg.
7-1 Haddam 1.8 Mi, SE TLD, Air Particulate, lodine 8-1 East Haddam 3.1 Mi, ESE TLD, Air Particulate, lodine 9-1 Higganum 3.2 Mi, WNW TLD, Air Particulate, lodine 4.3 Mi, WNW TLD, Air Particulate, lodine 10-1 Hurd Park Rd.
2.8 Mi, NNW TLD 11 C Middletown 9.0 Mi, NW TLD 12 C Deep River 7.1 Mi, SSE TLD 13 C North Madison 12.5 Mi, SW TLD, Air Particulate, lodine 14 C Colchester 10.5 Mi, NE TLD 15-1 On-site Wells 0.8 Mi, ESE Well Water
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16 C Well-State Highway Dept. E. Haddam 2.8 Mi, SE Well Water 17 C Fruits & Vegetables Beyond 10 Miles Vegetation 18-l Site Boundary 0.4 Mi, NW Vegetation 19-1 Cow Location #1 5.5 Mi, ENE Milk 20-1 Cow Location #2 6.0 Mi, NW Milk 21 1 Cow Location #3 8.0 Mi, WNW Milk 22 C Cow Location #4 11.0 Mi, ENE Milk 23-C Goat Location #1 17.0 Mi, NE Milk 24-1 Goat Location #2 4.5 Mi, N Milk 251 Fruits & Vegetables Within 10 Miles Vegetation 26-1 CT River-Near intake 1.0 Mi, WNW Fish 27 C CT River-Higganum Light 4.0 Mi, WNW Shellfish 28-1 CT River-E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 28-X CT River E. Haddam Bridge 1.8 Mi, SE Shellfish 291 Vicinity of Discharge Bottom Sediment, Fish 30-C CT River - Middletown 9.0 Mi, NW River Water, Bottom Sediment 7.6 Mi, NW Fish 31-1 Mouth of Salmon River O.8 Mi, ESE Shellfish 40-X Near intake Structure 0.1 Mi, SSW TLD 41-X Picnic Area 0.3 Mi, WNW TLD 42-X Environmental Trail 0.1 Mi, NW TLD 43-X Moodus - Rts 149 & 151 2.5 Mi, ENE TLD
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2-2 m
IABLE 2-1 (Cont'd)
Location Direction & Distance From Sp_mnple_Tynga Number Name Release Point *
- r 4
44-X Shailerville, Horton Rd.
1.0 Mi, SE TLD 4 5-X Old Waste Gas Sphere Fence 0.1 Mi, E TLD 46-X Discharge Canal Fence 0.2 Mi, SE TLD 47-X info Center 0.1 Mi, WNW TLD k
'l = Indicator C - Control X - Extra - nonrequired sample
- *The release points are the stack for terrestrial locations and the end of the discharge canal for aquatic locations.
5
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4 TABLE 2-2 J
HADDAM NECK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling &
Exposure Pathway Number of Collection and/or Samole Locations Freauency Tvoe & Freauency of Analysis l a.
Gamma Dose -
14 Monthly Gamma Dose Monthly Environmental TLD
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1 b.
Gamma Dose -
27 Quarterly '*)
N/A
L Accident TLD 2.
Airborne 7
Continuous Gross Beta - Weekly Particulate sampler - weekly Gamma Spectrum - Quarterly on filter change composite (by location), & on individual sample if gross beta is greater than 10 times the mean of the weekly control j
stations gross beta results 3.
Airborne lodine 7
Continuous 1-131-Weekly sampler - weekly I
canister change 4.
Vegetation 4
One sample near Gamma Isotopic, Sr-89 and Sr-90 on middle & one near each sample end of growing season 5.
Milk 6
Monthly Gamma Isotopic,1131, Sr-89 & Sr-90 on each sample 6.
Well Water 2
Quarterly Gamma Isotopic & Tritium on each sample 7.
Bottom Sediment 3
Ouarterly Gamma Isotopic 8.
River Water 2
Ouarterly Sample -
Quarterly - Gamma isotopic & Tritium Indicator is Continuous Composite; f
Background is composite of Six weekly Grab l
Samples 9.
Fish - Bullheads &,
3 Quarterly Gamma Isotopic - Quarterly
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when available, Perch or other edible fish 10.
Shellfish 2
Quarterly Gamma Isotopic - Quarterly r
(a) Accident monitoring TLDs to be dedosed at least quarterly l
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L 2.2 Samoles Collected Durina Reoort Period
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I The following table summarizes the number of samples of each type collected during the present reporting period:
I Number of Number of Samole Tymn Reauired Samoles Extra Samoles
[
Gamma Exposure (TLD) 168 96 Air Particulates 364 0
Air lodino 364 0
Dairy Milk 48 0
Goat Milk 24 0
Pasture Grass 0
0 Well Water 8
0 Fruit & Vegetables 8
0 J
Broad Leaf Vegetation 4
12 River Water 7
0 Bottom Sediment 12 0
Fish 24 0
Shellfish 8
4 Total All Types 1,039 112 1
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G 3.0 RADIOCHEMICAL RESULTS i
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3.1 Summary Table in accordance with the Radiological Effluent Monitoring Manual (REMM), Section 1
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F.1, a summary table of the radiochemical results has been prepared and is-LL presented in Table 3-1.
In the determination of the mean, the data was handled as recommended by the-1 Health and Safety Laboratory, Idaho and NUREG/CR-4007 (Sept.1984): all valid '
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data, including negative values and zeros were used in the determination of the mean (see Part 3.2).
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l A more detailed analysis of the data is given in Section 4.0 where a discussion j
of the variations in the data explains many aspects that are not evident in the
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Summary Table because of the basic limitation of data summaries.
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TABLE 3-1 PAGE 3-2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROLRAM
SUMMARY
CONNECTICUT YAPd(EE ATOMIC POWER COMPANY, HAEDAM NECK PLANT DOCKET 50-213 i
JANUARY - DECEMBER 1993
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ANALYSIS AND LOWER LIMIT ALL INDICATOR L ATION WITH HIGHEST ANHUAL MEAN CONTROL W OF NEDIUM OR TOTAL NUMBER OF LOCATIONS
. TINFE LOCAT]ONS NRM PATHWAY OF ANALYSES DETECTION MEAN DISTANCE MEAN MEAN (C)
SAMPLED PERFORMED (LLD) (A)
(RANGE)(B)
AND DIRECTION (RANGE)(B)
(RANGEl(B)
CANMA DOSE 120, 48 (D) 1.5 7.5 LOC # 14C 8.4 7.5 0
(UR/HR)
( 5.5 -
8.91 10.5 MILES NE
( 6.8 -
9.39
( 5.8 -
9.3)
AIR RR 57 0.01 (E) 0.018 LDC # 9 0.011 0.010 0
PARTICULATE BNA (e.000 - 8.825) 3.2 MILES WNW (0.001 - 0.023)
(0.001 - 0.024)
AND 10 DIME EPCI/M3)
GE(LI) 312.52 s.87 8.000 LOC s 6 0.000 e.000 0
(-8.808 -
8.088) 0.5 MILES NE
(-8.008 -
0.908)
(-0.008 -
0.007)
GEtLI) 24, 4 e.103 LOC a 4 0.109 0.107 0
BE-7
( 8.081 - 8.129) 1.8 MILES SW
( 0.896 - 8.129)
( 8.101 - 8.113)
C0-6e 0.0e0 LOC a 6 0.000 0.000 0
( 0.000 -
8.000) 8.5 MILES NE
( 0.000 -
0.000)
( 0.000 -
0.000)
ZR-95 8.808 LOC e 7 0.000 0.000 0
(-0.001 -
0.081) 1.8 MILES SE
( 0.000 -
0.001)
(-0.001 -
0.001)
NB-95 e.000 LOC 8 7 0.000 0.000 0
( 0.000 - 0.000) 1.8 MILES SE
( 0.000 -
0.000)
( e.000 -
0.000) l l
RU-103
-0.000 LOC 5 9 0.000 0.000 0
(-e. eel - e.001) 3.2 MILES WNW
( 0.00s - e.000)
( 0.00s - 0.0:0)
CS-134 0.85 (F) 0.000 LOC 5 5 0.000 0.000 0
(-0.001 -
8.080) 0.4 MILES NW
( 0.000 -
0.000)
( O.000 -
0.080)
CS-137 0.06 e.000 LOC 8 13C e.000 0.000 0
( 0.000 -
0.000) 12.5 MILES SW
( 8.800 -
0.000)
( e.000 - e.000) l l
MILK SR 36.12 G.3 LOC 8 21 0.4 0.2 0
l (DAIRY)
SR-89
(-8.8 -
2.1) 8.0 MILES WNW
(-8.2 - 1.59
(-1.1 -
1.1) l (PC1/L)
SR-90 1.8 LOC 5 29 2.6 2.0 9
( 0.9 -
3.5) 6 MILE *, NW
( 2.1 -
3.5)
( 1.3 -
2.4) i C
_____.__.___m__
TABLE 3-1 PAGE 3-3 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
l COMMECTICUT YANKEE ATOMIC POWER COMPANY, HADDAM NECK PLANT I
DOCKET 50-213 JANUARY - DECEMBER 1993 ANALY5IS AND LOWER LIM 11 ALL INDICATOR IOCATION WITH HIGHEST A)# DUAL MEAN CONTROL 5 0F MEDIUM OR TOTAL NUMBER OF LOCATIONS
~~TDCATION B, LOCAJONS NRM T
PATHWAY OF ANALYSES DETECTION MEAN DISTANCE MEAN
& AN (C)
SAMPLED PERf0RMED (LLD1 (A1 (RANGEI(B)
AND DIRECTION (RANGEI(B)
(RANGEI(BI ig 1
-e.el LOC a 21
-e.se
-e.el o
( -0.16 -
0.08) 8.0 MILES WNW
( -0.16 -
S.08)
( -0.07 -
0.08)
-0.2 LOC 3 21 0.1
-0.2 0
l 05-134
( -3.0 -
1.6) 8.8 MILES WNW
( -2.7 -
1.5)
( -5.8 -
3.0) i CS-137 18 1.8 LOC e 21 2.6 a.7 0
( -5.7 - 11.2) 8.0 MILES WNW
(
-0.8 - 11.23
( -5.5 -
6.5)
BA-140 78
-8 LOC 5 20 0
-1 0
( 7) 6 MILES NW
( 5)
( 5)
LA-149 25 9.4 tcC a 21 1.2
-0.0 8
( -4.4 -
3.0) 8.0 MILES WNW
(
-0.8 -
2.6)
( -3.0 -
2.0) i GOAT MILK SR 12.12 0.1 LOC B 24 0.1
-0.4 0
l (PCI/L)
SR-89
(-1.4 -
1.5) 4.5 MILES M
(-1.4 -
1.5)
(-2.5 -
1.0) l I
SR-98 4.8 LOC e 24 4.8 2.1 0
j
( 3.2 - 11.8) 4.5 MILES M i 3.2 - 11.8)
( 1.3 -
3.8) l IODINE 12.12 1
-0.01 LOC 8 23C
-0.01
-0.01 0
( -0.15 -
8.16) 17 MILES NE
( -0.14 -
8.11)
( -0.14 -
8.11)
GE(LI) 12.12 15 0.8 LOC # 24 0.0
-0.7 0
CS-154
( -2.5 -
1.9) 4.5 MILES N
( -2.5 -
1.9)
( -6.2 -
0.9)
CS-137 18 5.s LOC s 23C 14.s 14.e e
( -S.O - 11.9) 17 MILES NE
(
1.1 -
38.6)
(
1.1 -
38.6)
BA-14e.
78 2
LOC 3 24 2
-0 0
( 11) 4.5 MILES N
( 11)
( 6)
LA-140 25
-0.4 LOC e 23C
-0.1
-0.1 0
( -3.9 -
2.11 17 MILES ME
( -2.0 -
3.2)
( -2.0 -
3.2)
.. V TABLE 3-1 PAGE 3-4 ENVIR0petENTAL RADIOLOGICAL MONITORING PROGRAM SUNMARY C0petECTICUT YAPetEE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1993 ANALYSIS AND LOWER LIMIT ALL INDICATOR LOCATION WITH HIGHEST APW4UAL MEAN CONTROL 8 OF MEDIUM OR TOTAL NUMBER OF LOCATIONS
. LOCATION 5, LOCATIONS NRtt PATHWAY OF ANALYSES DETECTION MEAN DISTANCE MEAN MEAN (C)
SAMPLED PERFORMED tLLD) iAI (RANGEItB)
AND DIRECTION IRANGEIIB) tRANGE)iB)
CROUNDWATER GE f t.t )
- 4. 4 15 0.3 LOC B 15 0.3
-1.5 8
(PCI/L) 194-54 I -8.9 -
1.0) 8.8 MILES ESE E
-8.9 -
1.0)
( -3.4 -
-e.4)
CD-s8 15
-8.5 LOC # 15
-0.5
-2.7 0
t -2.1 -
3.5) 0.8 MILES ESE t -2.1 -
8.3)
( -7.1 -
-e.8)
CD-60 15 0.8 LOC 3 16C 0.5 0.5 8
t -1.1 -
1.2) 2.8 MILES SE t -0.6 -
1.1) t
-0.6 -
1.1)
-3 LOC 8 16C 1
1 e
( 2) 2.8 MILES SE E 4)
( 4)
CS-134 15 0.5 LOC # 16C e.7 0.7 8
t 8.8 -
1.1) 2.8 MILES SE t -0.8 -
2.4)
( -0.8 -
2.4)
CS-137 18
-8.9 LOC # 16C 0.8 0.8 e
t -5.2 -
1.4) 2.8 MILES SE I
0.9 -
1.5) 1 0.0 -
1.5)
BA-149
-68
-3 LOC S 16C 1
1 9
I 3) 2.8 MILES SE I 1) 1 1)
LA-140 68 1
LOC # 15 1
0 0
t 4) 8.8 MILES ESE E 4)
( 1)
- 4. 4 2998 2513 LOC 8 15 2513 49 e
(
889 -
5430)
's.8 MILES ESE E
889 -
5438) t 24 -
115)
FRUITS AND GEtLI)
- 4. 4 8.05 LOC # 25 S.05 0.05 8
VEGETABLES BE-7 I 0.00 - 0.17)
(19 MILES
( 0.00 - S.17)
( 6.80 - 0.14)
(PCI/G)
K-48 2.56 LOC 2 25 2.56 2.18 0
[
t 1.10 -
6.45)
<10 MILES I 1.10 -
6.45)
( 8.95 - 4.64) i l
- )M-54
-0.000 LOC 8 17C 0.881 e.801 e
t-0.002 - 8.998)
>18 MILES 4 0.000 -
8.803)
.t 0.800 - 0.083)
_ i a-
_----_._m__a-___._-___--____________._
_ _ _ _. - _ - _ - - _ _ _ _ _ _ _ - - _ - _ _ - _ _ - - - _ - _ _ _ _ - _ _ _ _ - _ _ - ~ - _ _ - - - - _ _ _.
- w w-v w-w--
r v um.
r-a rm r~ W TABLE 3-1 PACE 3-5 ENVIRONMENTAL RADIOLOGICAL MONITORING PROCRAM
SUMMARY
CONNECTICUT YAMtEE ATOMIC POWER COMPANY, HADDAM MECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1995 ANALYSIS AND LOidER LIMIT ALL INDICATOR LOCATION WITH HIGHE5T ANNUAL HEAN CONTROL 5 OF MEDIUM DR TOTAL NLHBER OF LOCATIONS LOCATION B, LOC A TJONS NRM PATHWAY OF ANALYSES DETECTION HMT DISTANCE MEAN MEAN (C)
SAMPLED PERFORMED (LLD) (A)
(RANGE)(B)
AND DIRECTION (RANGEl(B)
(RANGEl(B)
C0-58
-0.081 LOC 8 17C
-0.001
-e.001 e
j t-0.003 -
9.081)
>10 MILES t-0.004 - 0.003) t-8 084 - S.803)
CO-68
-0.000 LOC 5 ITC 0.001 0.001 e
t-8.003 -
8.892)
>10 MILES
( 0.000 - 9.003)
( 0.000 - 0.093) 2R-95 e.887 LOC s 25 a.807 0.001 e
t 8.994 - 0.010)
<10 MILES
( 0.084 - 8.010)
(-0.001 - 0.004)
NB-95 0.999 LOC B 17C 8.982 8.802 0
(-8.001 -
9.901)
>18 MILES i 9.401 -
0.004) t 0.001 -
0.004)
RU-le3 8.888 LOC 5 17C 0.001 0.001 8
(-8.881 -
0.802)
>10 MILES
( 0.000 -
8.003) t 8.000 -
8.883)
I-131' 9.06 (C)
-0.000 LOC 8 25
-0.008
-0.001 0
(-8.007 - 9.911)
(18 MILES
(-0.007 -
4.011) t-8.007 -
0.001)
CS-134 9.06
-0.801 LOC 8 17C 8.001 0.001 0
(-0.905 - 0.081)
>10 MILES t-0.001 -
0.084)
(-8.801 -
8.004)
CS-137 0.08 0.083 LDC 5 25 0.083 0.001 0
( e.001 -
8.885)
<10 MILES
( 0.001 -
8.005) t 9.000 -
0.001) i RA-226
-0.052 LOC # 17C 0.082 0.982 0
1
(-8.122 - 0.909)
>19 MILES
(-0.027 -
8.059)
(-8.027 - 0.059) l TM-228
-0.007 LOC # 17C 0.001 0.001 0
t-0.924 - 8.000)
>10 MILES t-0.991 -
0.004)
(-0.001 - 0.004) l I
BROADLEAF pf_( LI I 14.
1.21 LOC # 6 1.21 O
VEGETATION BE-7 i 8.21 - 3.20) 0.5 MILES NE t e.43 - 3.20)
{
. I (PCI/G) j 1
K-48 2.68 LOC 8 6 2.85
)
e
( c.93 - 4.69) 0.5 MILES NE t 1.55 - 4.69)
(
-- t rn 1 -- u u -- u-~u ~ W ' U ~ W- ~ U U '~1 J~ U ~~~ W U ~'
TABLE 3-1 PAGE 3-6 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YAPECEE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 58-213 JANUARY - DECEMBER 1993 ANALYSIS AND LOWER LIMIT ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL 8 OF l
MEDIUM OR TOTAL NUMBER OF LOCATIONS LOCATION 5 LOCATIONS NRM l
PATHWAY OF ANALYSES DETECTION MEAN DISTANCE MEAN HUR (C)
SAMPLED PERFORMED (LLD) (A)
(RANGEltB)
AND DIRECTION (RANGEllB)
(RANGEllB)
MH-54 e.001 LOC # 6 0.002
)
e
(-8.805 -
0.006) 8.5 MILES NE t-0.803 -
8.006)
(
CO-58
-0.801 LOC # 18
-0.001 O
t-8.809 - 0.005) 0.4 MILES NW t-8.007 -
0.003)
(
I CD-60 8.881 LOC e 6 8.001
)
a t-8.883 -
8.094) 8.5 MILES NE t-8.001 -
0.804)
(
ZR-95
-0.004 LDC a 6 0.001
)
e t-0.832 -
3.089) 0.5 MILES NE t-8.007 -
0.009)
(
NB-95 8.001 LOC 5 6 0.081 0
1-9.482 -
9.885) 0.5 MILES HE I 8.000 -
0.005)
(
)
RU-183
-0.081 LOC s 6
-e.000
)
O t-8.986 - 8.086) 8.5 MILES NE t-0.881 - e.002)
(
1-131 0.86
-0.001 LOC S 18 8.004
)
8
(-8.015 - 8.813) 8.4 MILES NW I-8.819 - 0.013)
(
CS-134 4.86
-e.sel LOC a 6
-0.081
)
O t-9.812 - 0.005) 8.5 MILES NE t-8.012 -
0.005)
(
CS-137 0.98 0.836 LOC # 18 0.046
)
e
( 8.000 - 8.141) 0.4 MILES NW t 0.008 - 0.141)
(
-0.098 LOC S 18
-0.069
}
O t-8.349 -
0.058) 8.4 MILES NW
(-0.144 -
0.050)
(
TH-228 8.004 LOC # 6 8.006
)
O t-0.013 - 8.e43) 0.5 MILES NE t-0.013 -
0.043)
(
2IVER WATER GEELI)
- 4. 3 6
LOC a 28 6
-25 e
(PCI/L)
( -11)
ll l
Ili lill' I
Il lI il ll ll c
7 3
FM)
ORC s
0 e
0 0
e 0
0 0
0 0
0 E
N(
G 5
A P
)
)
)
)
)
)
1
)
)
)
)
)
7
)
1 1
2 5
5 5
1 9
2 8
8 0
8
)
1 0
0 2
1 2
S B
3 0
e LN t
5 1
3 8
6 8
1 1
0 OON) 7 6
3 1
- 4. -
- 0. -
- 0. -
RIAE 0-0-
0-0-
1-TTEG 9
0 0
1 2
NAHN 8
6 1
9 2
1 2
1 3
1 OC A
1 1
0 0
CO R
0 0
8 s
1 6
L
(
0 0
t
(
(
t
.(
(
t 1
(
(
(
(
)
)
)
3
)
)
8
)
)
0 5
5 5
1
)
)
)
7
)
1 1
N 9
6 8
6 5,
0 0
T A
)
1 2
0 2
1 2
N E
B 0
8 8
A M
(
6 5
3 8
6 6
1 1
0 YL N) 7 4
3 7
- 4. -
- 0. -
- 0. -
RP L
AE 0-0-
0-0-
1-2-
A A
EG 9
0 0
MK U
MN 2
7 1
9 2
1 2
1 5
1 1
2 MC N
A 2
4 8
8 UE N
R 0
0 9
0 1
8 SM A
(
8 0
t t
t t
MM T
i t
t
(
t t
t AA S
t RD E
GD H
OA G
RH I
P H
, 3 GY 9 H
NN 9 T
IA 1 I
N A
W W
RP W
, O E
E W
W W
W E
W E
/
N N
DM3R 5
I S
CN S
N CW CW TO1E N
ET 8
8 0
0 0
0 8
0 8
9 7
7 1IC2B ONCC 2S 2S 3S 3S 3S 3S 2S 3S 2S 2S 2S 2S N
M IONE E
E E
E E
E E
E E
E E
E 3OR0E TIAR
- L aL 2L eL 5L eL BL
- L
- L 8L 5L sL ME5C ATTI I
I I
I I
I I
I I
I I
I E W E CASD CM CM CM CM CM CM CM CM CM CM CM CM LLOTD OCI O
O O
O O
O O
O O
O O
O BAPE LODD L8 L8 L
L L
L L8 L
L8 Le L4 L4 AC K-L M 0
0 8
0 0
TICC A
1 1
1 1
GIOY 9
9 9
9 9
)
D A
)
)
)
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8
)
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9 5
7 3
6 3
)
)
7
)
1 0
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9 6
8 6
6 0
0 K
TS
)
1 2
0 2
1 LN AN B
1 0
0 AA CO l
6 5
2 6
8 6
1 s
1-TY IINl 9
4 2
7 N
DTAE 0-0-
0-2-
e-e-
2-
- 1. -
- e. -
- 0. -
ET NAEG 9
0 0
MU ICMN 2
7 8
9 7
7 2
8 5
9 9
2 NC O
A 4
2 1
4 0
e 0
0 0
5 5
RT L
(
0 0
IC A
t t
t I
VE t
t
(
t 8
(
t NM 1
EN O
C T
I N
M O)
)
I IA H
)
L T(
(
H FC
(
0 ROE) 0 0
E TD 0
0 0
0 e
2 0
0 W EL 3
3 3
3 4
1 3
2 O DL L
(
3 DR NES 4
ABED 4
tSE 8
SWYM 4
7 0
0 INLR 4
8 8
1 3
3 4
4 M
4 8
S AO 5
5 6
3 1
1 1
1 U
)6 5
5 YLNF 1
I3 I4 LAAR M
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S S
A A
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9 AT E
M C
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NOFP R
E ATO T
G P
ROYD T)
AE NG MWL ME/
UHP OMI ITM TIC DAA TDP EPS OE(
M BS llll lf;lI;l
TABLE 3-1 PACE 3-8 EhvIROPetENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YAPGCEE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1993 ANALYSIS AND LOWER LIMIT ALL INDICATOR ATION WITH HIGHEST ANNUAL MEAN CONTROL 5 CF MEDIUM 04 TOTAL NUMBER OF LOCATIONS
' TTDR B, LOCAR ONS NRM PATHWAY OF ANALYSES DETECTION MEAN DISTANCE MEAN MEAN (C)
. SAMPLED PERFORMED fLLDI (A)
(RANGE)(BB AND DIRECTION (RANGEI(B1 (RANGE)fB)
CO-60 8.02 LOC 3 29 8.04 0.81 0
(-8.83 -
0.18) e MILES N/A
(-0.00 -
0.10)
(-0.01 -
0.01)
ZR-95
-8.60 LOC 8 27C 0.00 0.00 8
(-8.04 - 0.93) 4 MILES WNW
(-0.02 -
0.02)
(-0.02 -
0.82) 1 NB-95 0.08 LOC 8 29 8.81 8.01 8
1
(-0.00 -
8.82) 8 MILES N/A
(-8.00 -
0.02)
( 0.00 - 9.81)
I-131 3.01 LOC 8 29 0.02 0.00 0
(-9.01 -
0.82) 8 MILES N/A
( 0.01 -
8.02)
( 0.00 -
0.01)
CS-134 8.15 0.00 LOC s 28 0.00 0.80 0
( 8.00 -
0.02) 1.8 MILES SE
( 0.88 -
0.02)
( 9.80 -
0.00)
CS-137 4.18 0.15 LOC # 29 0.21 0.09 8
( 8.00 -
8.43) e MILES N/A
( 0.00 -
8.45)
( 0.86 - 8.14)
RA-226 9.87 LOC 5 27C 1.31 1.31 0
( 8.00 - 1.69) 4 MILES WNW
( 1.06 -
1.58)
( 1.06 -
1.58)
TH-228 8.60 LOC # 27C 3.64 8.68 0
( e.43 -
8.78) 4 MILES WNW
( 0.48 -
1.00)
( t.48 -
1.00)
SHELLFISH ggfLI)
- 8. 4 9.04 LOC 8 28 0.05 0.05 0
(PCI/C)
DE-7
(-8.08 -
0.13) 1.8 MILES SE E 8.02 -
0.08)
(-0.01 -
8.13)
K-40 8.1 LDC # 31 0.3
-0.0 0
(-9.3 -
0.4) 0.8 MILES ESE
( 9.5 -
0.4)
(-0.3 - e.2)
CR-51
-0.03 LOC 9 31
-0.01
-0.86 9
(-0.08 -
8.06) 8.8 MILES ESE
(-0.98 -
0.06)
(-8.10 -
0.00)
O G
h
e M
WK8 Ogu
.Zw W
G r
.E W
aF. <,.
m m
am m
m m
a s
e.n s.n am p
.4
.4 e4
,4 4
.e4
.4 o.
(
N e
i a
f Q
Tm h p.e d W t
t t
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9 4
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N e M.
i e
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QU te.
yQ g
d t
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u.6
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e s
e
[
w w
e.r r
s w-w
.e w
w i
sm n=
mm m
m.
m am m
an s
am s
['
M.
s.n e
M e
.4 e
.4
,4 N
e.4
.Z p
g
=
T W
W E
e.4 a.e e.4 I
w
>s E *m
/
kL a
aW W
.e t
g t
.e B
g t
I t
.e 6
l 4
t WH u
z N
M u
W x
w 5x w
w w
w w
w w
w w
w w
w M
k W
l I
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A Z
= M Ex>
O.'
Z-
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M<
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W W
m e.
2 w
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W W
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W-
~
r4MUNg 02UU NM NM NM NM NM MM MM NM NM MM NM NM
- L
-02W W
W W
W W
W W
W W
W W
W M
-.W
--<=
.a
.W
.a
.a
.a
.a
.a
.a WHW
<-->4
>4 M
M M
M
>4 M
M M
M M
M d.s$-a 8*ca 8*
8*
8*
85 85 85 85 8,5 85 8*
8*
85 8,0
< W W
s, s.
-Mu s.
s.
s, s.
s.
s s.
s.
s.
s,
<u c.
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0-D M<
z o
m m
m
<W M.
M.
N.
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s m
..e
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m.
-M
=
Q-5W m
4 4
t W-z.W
., M l
B 8x t-
. M.
as a
w Mu gw w
w w
=
w w
w w
w w
=
=
l M
Z E Om H P4 4 A > = =
WW M
M 4
N.
M.4 M
k O W ah e4 e4 s.
N.
.g W
>= O 8
e i
e t
e 7 WJ I
e e
e e
a O Qs a
w Q.
4WM 4
WQ MW g
e M
>E M
4
(
.J w 4
ln 4A M
e
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<O en M
60 se o-4 e4 e
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>.J E b e
s e
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3 e
i M
i e
i 4
e s<<k Z
Q W
O E
a
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b O
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< >= Q NO>O
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M-r O.E M WLM a
K
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FM3.
Vvt J w.
rT TD~v m m r
TABLE 3-1 PAGE 3-18 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SLRetARY CONNECTICUT YAN EE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-233 JANUARY - DECEMBER 1993 AMALYSI5 AND LOWER LIMIT ALL INDICATOR L OC ATION WIIH HIGHEST APMJAL MEAN CONTROL 5 0F MEDIUM CR TOTAL NUMBER GF LOCATIONS N KTION 5 LOCATIONS NRM PATHWAY OF ANALYSES DETECTION MEAN DISTANCF MEAM HEAN (C)
SAMPLED PERFORMED (LLD) (A)
(RANGEl(B)
AND DIRECTION (RANGEl(B)
(RANGEltB)
CS-137 8.15 8.00 LOC e 28 0.00 e.as 0
( 0.es -
0.01) 1.8 MILES SE t 0.00 -
0.01)
(-0.00 -
0.01)
I RA-226 0.28 LCHC 5 28 0.31 0.11 e
t-8.19 -
9.63) 1.8 MILES SE t-0.18 -
0.63)
( 0.00 - e.31)
TH-228 4.21 LDC 8 31 8.22 S.22 e
( 0.13 - 8.27) 0.8 MILES ESE
( 0.16 -
8.27)
( 5.17 -
0.29)
FISH GE(LI) 16. 8 0.01 LOC 8 26 e.02
-0.02 0
(ALL TYPES)
BE-7
(-0.97 -
0.89) 1 MILES WNW
(-9.07 -
0.09)
(-0.08 -
0.06)
(PC1/G)
K-40 3.0 LDC 8 29 3.1 2.9 0
4 1.9 - 4.1)
O HILES N/A
( 2.1 -
4.1) i 2.1 -
3.7)
CR-51 5.00 LDC S 26 9.01
-8.03 0
(-0.10 -
8.06) 1 MILES WNW
(-8.10 -
0.06)
(-0.06 - -0.00) 194-5 4 0.13 0.00 LOC 8 30C e.00 e.00 0
t-8.02 -
9.81) 9.9 MILES NW I-0.80 -
0.01)
(-0.00 -
0.81)
C0-58 0.13
-0.00 LOC 5 26 0.00
-0.00 0
(-0.01 -
0.01) 1 MILES WNW
(-0.01 -
0.01)
(-0.01 -
8.00)
FE-59 8.26
-0.00 LOC # 29 0.00 0.00 0
(-0.02 -
8.02) 8 MILES N/A
(-0.01 -
0.02)
(-0.02 - 0.01)
CO-60 0.13 0.00 LOC 8 30C 0.00 0.00 0
t-0.01 - 0.81) 9.8 MILES NW
( S.80 -
0.01)
( 9.00 -
0.01) l ZN-65 0.26 0.01 LOC 5 26 0.01
-0.00 e
t-0.01 - 0.03) 1 MILES WNW
(-0.01 -
0.83)
(-0.03 -
9.82) l
r IM vv3 Tm
.c D
\\
r-u T F ~Um I VD T1 m
F' TABLE 3-1 PAGE 3-11 ENVIROWtENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT Yale (EE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1993 ANALYSIS AND LOWER LIMIT ALL INDICATOR OCATION WITH HIGHEST AMUAL NEAN CONTROL 5 OF MEDIUM OR TOTAL NUMBER OF LOCATIONS TTON 5, LOCATIONS MRM PATHWAY OF ANALYSES DETECTION MEAN DISTANCE MEAN REIN (C)
SAMPLED PERFORMED (LLD) (A)
(RANGEl(B)
AND DIRECTION (RANGEl(B)
(RANGE)(B)
ZR-95
-0.88 LDC 5 30C 8.00 e.se e
(-0.02 -
9.82) 9.0 MILES NW
(-0.01 -
8.02)
(-0.01 -
0.42)
NS-95
-0.80 LOC 5 30C 9.00 9.00 0
(-0.e5 -
0.81) 9.0 MILES NW
( 0.00 -
8.01)
( e.00 -
9.91)
RU-103 0.88 LOC 8 29 0.99 0.00
(-9.01 -
8.81) 0 MILES N/A
(-0.01 -
0.01)
(-0.00 -
0.00)
RU-les 0.81 LOC a 29 0.01
-0.el 0
(-8.06 -
0.09)
O MILES N/A
(-0.06 -
0.09)
(-9.03 -
8.05' AG-110M
-0.00 LOC 3 30C
-0.00
-0.00 0
(-8.92 -
0.81) 9.8 MILES MW
(-0.01 -
8.01)
(-0.01 -
0.01) 1-131
-0.01 LOC e 30C
-0.00
-0.00 0
(-0.53 -
8.92) 9.8 MILES NW
(-0.01 -
0.81)
(-0.81 -
8.01) l CS-134 s.13
-e.se LOC e sec o.c0 o.00 0
)
(-0.01 - 0.01) 9.8 MILES NW
(-0.00 -
0.01)
(-0.08 -
0.01) l I
CS-137 0.15 0.03 LOC 8 26 0.83 0.02 0
( 9.00 - 8.87) 1 MILES WNW
( 8.81 -
0.07)
( 8.00 -
0.09)
-0.13 LOC e 29
-0.03
-0.15 0
(-8.61 -
0.18) e MILES N/A
(-0.25 - 8.14)
(-8.37 -
0.80)
I TH-228
-0.81 LOC # 26
-0.81
-0.01 0
1
(-0.94 -
8.01) 1 MILES WNW
(-0.03 - e.01)
(-0.04 -
0.01) l l
Em i
r
[
[
EOOTNOTES f
A.
For Ge(Li) measurements the MDL's ~. LLD + 2.33. For all others, MDL = 2 x o background. These MDL's are based on the absence of large amounts of interfering activity (excluding naturally occurring radionuclides). Deviations by about factors of 3 s
to 4 can occur.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal.
L For a particular measurement system (which may include radiochemical separation):
[
s 4.66 S3 LLD =
E
- V
- 2.22
- Y + exp (-A At)
I where LLDis the lower limit of detection as defined above (as pCi per unit mass or volume)
[
S,is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
L Ris the counting efficiency (as counts per transformation)
Fis the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Yis the fractional radiochemical yield (when applicable)
I A is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or end of the sample collection period) and time of counting it should be recognized that LLD is defined as Loriori /before the fact / limit representing the capability of a measurement system and not as a costeriori (after the fact) limit for a particular measurement.
3-12
L.
e L
~
[
FOOTNOTES (Cont'd)
Analyses shall be performed in such a manner that the stated LLDs will be achieved L
under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumsthoces may render these a pliori LLDs unachievable. In such cases, the contributing factors, will y
Q be identified and described in the AnnualRadiologicalEnvironmentalOperating Report.
B.
Analytical results are handled as recommended by HASL (" Reporting of Analyt/ cal g
L Results from HASL, " letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept.1984).
Negative values were used in the determination of mean, e
L C.
Nonroutine reported measurements (NRM's). These are results of samples that exceed the report levels of Yable E-2 of the RadiologicalEffluent Monitoring Manual.
D.
First number is the number of indicator measurements, the second is the number of control measurements.
L E.
Assuming 270 m / paper r
F.
Assuming 1080 m' G.
LLD for leafy vegetables.
lL H.
LLD from the end of the sample period.
w L
fs L
3-13 L
[
[
3.2
[!als Tables The data reported in this section are strictly counting statistics. The reported l
error is two times the standard deviation of the not activity. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed.
Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data. For the
(
purposes of this report, in order to indicate any background biases, all the valid data are presented. In instances where zeros are listed after significant digits, g
this is an artifact of the computer data handling program.
L Data are given according to sample type as indicated below.
1.
Gamma Exposure Rate 2.
Air Particulates, Gross Beta Radioactivity p
3.
Air Particulates, Weekly 1-131 L
4.
Air Particulates, Quantitative Gamma Spectra 5.
Air Particulates, Quarterly Strontium' r
6.
Soil' L
7.
Milk - Dairy Farms 8.
Milk - Goat Farms
[
9.
Pasture Grass
- 10.
Well Water 11.
Reservoir Water
- 12.
Fruits & Vegetables 13.
Broad Leaf Vegetation 14.
River Water 15.
Bottom Sediment 16.
Shellfish 17.
Fish r
N This type of sampling or analysis was not performed, therefore there is no f
table.
L
{
3-14
CONNECTICUT YANKEE 1993 TABLE 1 PAGE 3-15 NONTHLY CAMMA EXPOSURE RATE (UR/HR) a L0 CATIONS PERIOD 1
2 3
4 5
6 7
8 9
le 11C I
JAM 93 6.7
.8 6.4
.1 6.3
.2 6.1
.2 7.8
.I 7.9
.2 6.6
.e 7.5
.2 6.8
.1 8.6
.1 8.2
.1 I
FEB 93 6.3
.e 5.7
.e A 6.1
.1 6.1
.1 7.1
.2 6.9
.2 6.2
.8 7.6
.1 6.4
.e 8.1
.1 7.3
.1 MAR 95 5.6
.8 A 5.5
.e A 5.9
.e 5.6
.2 7.2
.1 6.4
.3 6.1
.1 7.0
.7 6.0
.1 7.6
.1 7.5
.e i
l APR 95 6.3
.e A 6.4
.1 6.4
.1 6.5
.8 7.4
.1 7.2
.1 6.1
.e A 8.1
.1 6e
.1 7.9
.1 A 7.8
.1
]
MAY 93 6.9
.1 6.7
.1 6.7
.2 6.3
.1 8.2
.1 8.e
.3 6.7
.1 S.1
.e 7.0
.1 8.3
.3 8.7
.1 1
JUN 93 7.3
.e 7.e
.3 6.8
.1 6.7
.e 8.2
.1 7.5
.2 6.2
.e 8.6
.1 7.0
.1 8.3
.1 8.4
.1 JUL 93 7.4
.2 7.2
.e 7.1
.2 6.7
.1 8.8
.e 8.3
.3 7.1
.1 8.6
.1 7.5
.2 8.3
.e 9.1
.2 AUG 93 7.3
.1 7.8
.2 6.9
.1 6.8
.e 8.4
.3 7.7
.2 6.6
.8 8.8
.4 7.2
.1 8.3
.1 8.7
.e l
SEP 93 7.7
.2 7.4
.2 7.5
.1 7.9
.e 8.6
.e 8.3
.1 7.1
.2 8.7
.9 7.8
.1 8.6
.2 8.8
.e DCT 93 7.3
.1 7.1
.2 7.3
.1 6.9
.1 8.4
.8 7.8
.2 6.5
.1 8.9
.1 7.3
.e 8.6
.2 8.9
.4 l
NOV 93 7.1
.8 6.9
.1 7.e
.1 e.6
.5 8.4
.e 8.3
.3 7.e
.2 8.5
.e 7.4
.1 8.7
.2 8.9
.e t
I DEC 93 7.2
.e 6.8
.3 7.2
.5 6.9
.1 8.8
.e 7.7
.2 6.5
.1 8.7
.4 7.4
.2 8 8.8
.1 8.6
.2 PERIOD 12C 15C 14C 4eX 41X 42X 43X 44X 45X 46X 47X JAN 93
~E. 8
.4 6.7
.6 8.2
.e 7.9
.e 6.2
.1 18.5
.3 7.7
.e 6.8
.e 9.8
.e 7.1
.2 8.5
.2 FEB 93 6.1
.3 6.e
.1 7.5
.e 6.9
.e A 5.0
.1 9.6
.1 7.1
.e 6.5
.e 9.3
.2 6.8
.e 7.6
.4 i
MAR 93 6.2
.5 5.8
.8 6.8
.e 6.7
.1 5.8
.1 9.4
.2 6.9
.8 6.1
.e 8.7
.e 6.2
.2 7.0
.2 APR 93 6.4
.1 6.1
.e 8.1
.e A 7.1
.e 4.6
.e A 9.7
.2 7.5
.0 6.8
.8 9.4
.e 6.9
.8 8.1
.3 MAY 93 6.4
.4 6.6
.e 8.9
.e 6.8
.e 6.2
.1 18.7
.3 8.2
.1 7.8
.8 18.1
.e 7.5
.e 9.1
.1 JUN 93 7.8
.1 6.4
.e 8.6
.1 18.1
.1 5.8
.2 15.6
.6 8.1
.8 7.2
.1 12.1
.3 8.1
.1 13.3
.2 JUL 93 7.0
.1 6.9
.1 9.3
.e 8.2
.3 5.8
.8 13.5
.3 8.5
.1 7.6
.0 11.4
.3 8.1
.1 11.4
.1 AUG 93 7.1
.e 6.6
.8 8.8
.1 7.5
.e 5.9
.1 11.7 1
8.3
.2 7.6
.1 18.6
.8 7.9
.e 9.9
.2 SEP 93 7.3
.e 7.1
.1 8.S
.8 7.8
.8 6.4
.2 18.9
.4 8.1
.1 7.7
.5 11.1
.6 8.4
.4 8.7
.2 DCT 93 7.1
.2 6.5
.1 8.7
.2 7.7
.e 6.1
.1 11.6 1
8.3
.e 7.7
.1 10.7
.e 7.9
.1 8.9
.2 NOV 93 7.1
.3 6.7
.1 8.8
.1 7.3
.e 5.7
.1 10.5
.1 8.3
.2 7.4
.e 10.6
.1 7.7
.1 8.8
.8 DEC 93 7.3
.3 6.6
.e 8.6
.1 7.7
.e 5.9
.2 18.2
.4 8.2
.1 7.4
.2 18.8
.1 7.8
.1 8.6
.2 l
1 m Values 11 stem are the average of two TLDs.
Errors listed are I sigma.
A: Single TLD result B: Location (9) haa 5een permanenfly changed io 4.3 M1., WNW.
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V
_.F CONNECTICUT YANKEE.1993 TABLE 7 PAGE 3-25 DAIRY MILK (PCI/LI COLLECTION LDCATION DATE SR-89
$R-99 1-131 CS-134 CS-137 8A-140 LA-14e
(+/-)
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t+/.3 19 81/12/93 e.0 1.E 1.4 e.2 0.e3 0.12 1.2 1.9 1.8 2.0 3
6 2.4 2.4 19 82/89/93 0.1 e
1.1 0.1 0.07 8.08
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3.0 2.8 19 93/e9/95
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0.3 2.9 19 e5/le/93
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-1 6
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0.7 2.1 19 10/13/93 e.5 1.6 1.1 0.2 0.88 0.12 1.6 1.9 e.e 1.9 1
6 1.5 2.5 19 11/08/93 e.5 1.2 1.1 e.2 8.81 0.88
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8 3.4 2.4 19 12/14/93 1.3 1.5 1.3 0.2
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5
-0.6 1.6 21 81/12/93 1.4 2.1 1.5 0.2
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2.6 2.5 21 02/89/93 8.2 9.4 1.5 8.2 0.03 e.le 1.3 1.8 e.0 1.9 7
7 2.1 2.6 21 83/09/93
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-0.2 1.7
-0.8 2.5 2
6 2.8 2.6 21 11/e8/93 e.1 1.5 1.6 8.2
-e.86 0.08
-0.5 1.9 1.8 1.9 5
7
-e.8 2.6 21 12/14/93 0.6 1.7 1.4 e.2 0.05 0.13
-0.1 1.8 1.7 2.0
-2 6
2.5 2.8 1
E.
u o
m m
'~~~L-J V
f"'"
CONNECTICUT YANKEE 1993 TABLE 7 PAGE 3-26 DAIRY MILK IPCI/LI COLLECTION LDCATION DATE SR-89 SR-99 I-131 CS-134 CS 137
....-_-140...._..
BA LA-14e
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/.)
22C 01/12/93 9.4 1.5 1.6 e.2
-0.86 0.10
-0.1 1.7 2.3 1.9
-2 5
0.0 2.6 22C 02/e9/93 0.2 e.3 1.3 e.2 0.01 0.99
-0.8 1.7
-5.5 2.1
~5 5
-1.3 2.3 22C 03/09/93
-0.2 1.5 1.8 8.2
-0.07 8.10
-0.5 1.7 0.0 1.8
-3 6
-0.1 2.2 22C 04/06/93 0.1 1.7 2.0 8.2 0.02 0.08 8.8 1.8 1.7 1.8 8
7
-1.0 2.7 22C e5/10/93
-0.5 0.6 2.4 0.2 0.98 8.le 3.0 2.4 6.5 2.4 4
8
-3.0 2.9 22C 06/07/93
-1.1 1.9 2.3 0.2 0.03 0.89 0.9 1.9 0.8 2.0 1
5 0.2 1.9 22C 01/07/93 e.1 1.5 2.4 8.3
-0.83 0.13
-1.7 1.8
-1.8 2.0 5
6 8.8 2.6 22C 88/10/93 1.1 1.5 2.3 0.3
-0.02 e.11 1.8 2.0 2.0 2.1 8
6 1.5 2.5 22C 09/13/93 8.9 2.3 1.6 0.2
-0.04 0.09
-5.8 1.6
-0.8 2.1
-13 6
1.9 2.6 22C 10/13/93 0.2 1.8 2.1 e.2
-0.02 0.10 9.3 1.9 0.9 2.1 8
6 1.1 2.8 22C 11/88/93 0.2 1.3 2.3 8.2
-0.05 0.99
-0.3 1.6 1.8 1.9 2
6
-1.4 2.2 22C 12/14/93 8.6 1.6 1.9 8.2 0.07 0.16 e.8 2.1 2.6 2.3
-0 7
2.0 2.8
{
r L
L A
N N
N N
N O
M E
CONNECTICUT YANKEE 1995 TABLE 8 PACE 3-27 GOAT *$ MILK (PC1/L)
COLLECTIDM LOCATION DATE SR-89
... -- -.- 9 0 SR
---...-154..-----
(+/-)
(+/-)
(+/-)
(+/-)
t+/-)
(+/-)
(+/-)
23C el/12/95
-1.1 2.0 1.3 s.3
-8.e5 9.11
-1.3 1.7 11.s 3.4 6
6
-1.7 2.1 23C 32/09/93
-2.5 s.6 3.8 s.3 e.se 8.e9 8.9 1.5 7.8 2.8 e
4
-e.1 1.4 23C 33/89/95
-e.3 1.2 2.2 8.2 s.11 0.13
-0.9 1.6 1.1 2.1
-2 4
-1.4 1.8 23C e4/s6/93
-e.7 1.7 1.5 0.3 0.02 e.e9 9.4 1.9 11.3 4.0
-9 6
1.3 2.8 23C 85/1s/93 s.1 1.1 1.9 s.1 s.85 0.10
-0.5 1.6 19.7 4.s
-1 6
-0.7 2.6 25C 06/87/93 S.5 1.4 2.7 8.2
-0.82 0.08
-e.2 2.s 9.8 3.2
-0 6
-2.8 1.8 23C 07/07/93
-0.4 1.1 2.s e.2 e.s6 0.18
-6.2 1.7 11.3 3.5
-2 5
0.6 2.2 23C 88/10/93
-8.2 1.5 2.1 0.3
-0.04 s.15 0.2 1.5 16.3 2.9 1
4 1.6 1.8 23C 89/13/93 0.1 1.2 1.4 8.1
-0.83 0.09 e.e 1.9 14.1 4.3
-5 5
-0.7 2.0 23C 1e/13/93
-1.7 2.2 1.5 e.3
-e.83 0.11 0.9 2.8 15.9 4.2
-3 6
3.2 2.8 23C 11/08/93 s.5 2.5 2.5 m.3
-e.14 e.le
-1.3 1.8 13.6 4.2
-e 6
e.4 2.5 23C 12/14/93 los 3.3 1.9 e.3
-e.e9 0.12 e.7 1.6 12.5 2.8 1
4
-1.2 1.4 24 81/12/93 1.2 1.8 3.8 8.3
-e.12 s.le 1.9 2.5 8.8 2.4 11 8
-3.9 2.5 24 e2/89/93
-1.8 8.7 5.9 8.3
-0.08 e.88 e.5 1.7 7.7 3.8 9
5
-2.2 1.6 24 83/09/93 9.s 1.6 4.5 9.3 e.88 8.13
-0.9 1.7 7.1 3.2 6
5
-1.0 1.9 24 e4/96/93
-1.4 2.0 3.5 0.3 0.08 e.e9
-0.1 1.7 18.8 3.7 3
6
-2.6 2.0 24 85/10/95
-e.1 2.4 4.0 e.3 0.02 0.10 1.1 2.1 2.6 2.1 1
7
-1.6 2.3 24 e6/07/93
-e.7 1.8 4.9 e.3 8.81 0.09
-2.5 1.6 4.9 2.3 e
5 2.1 1.7 24 07/97/93
-0.4 1.3 3.5 9.3
-0.15 8.16
-1.6 1.8
-e.0 2.1
-3 6
2.0 2.5 24 08/10/93 8.8 1.3 3.2 0.2
-e.e4 e.11
-0.3 1.3 4.8 2.5
-1 4
0.9 1.6 24 09/13/93 1.5 1.9 4.2 0.5 s.81 8.12
-0.3 14 6.6 2.8
-2 4
1.8 1.5 24 10/13/93 e.5 2.3 4.e 0.3 8.16 e.16 1.6 1.8 S.8 2.1 3
6 8.9 2.2 24 11/e8/93 1.0 2.4 4.5 0.3
-8.12 0.08 8.8 1.7 11.9 3.5 6
6 e.6 2.4 24 12/14/93 e.6 4.7 11.8 s.7
-e.09 e.17
-8.1 1.4 4.6 2.2 4
4
-0.3 1.3
CONNECTICUT YANKEE 1993 TABLE le WELL WATER PAGE 3-28 (PCI/L)
COLLECTION LOCATION DATE K-4e
...... _- 51 HN-54 C0-58 CR FE C0-60 ZM-65
.._____-59_..__.
(+/-)
(+/-)
t+/-)
(+/-)
(+/-)
(+/-)
(+/-)
15 e3/08/93 0
26 8
17 0.6 1.4
-0.1 1.5 2.4 3.4 0.3 1.4
-0.2 2.9 15 96/21/93
-8 24
-17 13
-0.9 1.6
-2.1 1.5 2.8 3.3 1.2 1.7
-1.6 3.4 15 09/28/93
-22 25 8
15 1.0 1.3 8.3 1.4
-0.3 2.9
-0.3 1.3 4.1 3.2 15 12/2e/93
~46 24
-15 14 e.6 1.3
-0.3 1.3 0.5 2.8
-1.1 1.1 1.9 2.8 16C 83/98/93
-62 33
-le 15
-0.8 1.3
-0.8 1.5 8.3 3.1 0.9 1.4 1.9 3.s 16C e6/21/93.
G 45
-19 17
-3.4 1.9
-7.1 2.0 e.e 4.1
-0.6 2.0
-0.8 4.4 lbC 09/29/93 e
29
-le 12
-0.4 1.2
-1.6 1.3
-0.6 2.8 e.7 1.2 0.8 2.7 ItC 12/20/93
-27 36 5
14
-1.4 1.3
-1.4 1.5 1.7 3.3 1.1 1.4 8.8 3.2 COLLECTION LOCATION DATE ZR-95 NS-95 RU RU-le6 1-131 CS-134 CS-137
..._-103_.._.
(+/-)
(+/-)
(+/-)
(*/-)
(+/-)
(+/-)
(+/-)
15 85/08/93
-0.5 3.8 0.0 1.7 9.4 1.9
-4 12
-2 5
1.1 1.5 s.0 1.6 15 06/21/93 0.e 3.3 e.e 2.1 0.0 1.7 5
15 2
2 8.8 1.7
-5.2 2.1 15 09/20/93 1.5 2.8 s.0 1.7 8.4 1.7 e
12
-4 4
s.0 1.4 0.0 3.6 15 12/28/93 e.7 2.8 e.6 1.4 1.3 1.7
-le 11
-8 4
s.3 1.4 1.4 1.5 16C 03/es/93 1.0 3.1 0.0 1.7 8.6 1.8 e
13 1
5 8.e-1.4 1.1 1.4 16C e6/21/93
-3.6 3.9 0.0 2.9 1.3 2.1
-7 18 1
3 2.4 2.2 9.4 2.2 16C 39/28/93 8.8 2.9 0.8 1.4
-0.1 1.5
-8 12
-5 3
-0.8 1.3 1.5 1.4 16C 12/20/93 3.6 3.0 e.e 1.8 0.7 1.7
-23 12 4
4 e.5 1.6 e.8 1.6 a
N NE M
E O'
NE p'
CONNECTICUT YANKEE 1995 TABLE 18 PAGE 3-29 WELL WATER IPCI/L1 COLLECTIOP LOCATION DATE BA-140 LA-140 BI-214 TH H-3
--.....-228..--..
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
15 e3/08/93
-1 8
1.5 3.7
-68.6 35.8
-5.1 2.9 2848 160 15 86/21/93
-7 5
-1.9 1.9
-57.e 36.4 s.8 3.7 5438 240 15 99/28/93
-7 6
3.9 3.1
-87.3 33.7 1.8 2.8 889 130 15 12/20/93 3
6 0.8 2.9
-43.2 38.8 0.0 3.2 893 134 16C 03/08/93
-1 8
a.0 2.9
-lel 27.0 9.9 2.6 115 78 16C e6/21/93 1
6 1.3 2.8
-15.5 45.s a.e 5.0 32 115 16C 09/2e/93 1
6
-0.5 2.3 14.4 26.4 9.0 2.4 24 93 16C 12/28/93 1
7
-0.3 2.7
-1.0 29.4 8.0 2.6 25 97 I
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w u v w-1 CopedECTICUT YApetEE 1993 TABLE 14 PAGE 3-36 RIVER WATER (PCI/L)
COLLECTION CD
....___-59__
._-_-__-60____..
LOCATION DATE K-49 CR-51 P94-54 C0-58
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
28 82/88/93
-38 25 12 42 1.0 1.5 s.8 2.1
-4.3 5.3 8.8 1.7 28 85/1s/93 16 26
-29 34 e.7 1.5
-0.7 1.8 4.4 5.3
-8,5 1.4 28 87/12/93 e
39 64 72
-0.2 1.5 2.5 2.7 5.7 8.2
-9.8 1.2 28 11/08/93 39 22
-48 34 8.9 1.4
-0.7 1.7 4.1 5.1 8.7 1.3 3ec 01/25/93
-34 28
-11 26
-0.8 1.5 0.5 1.8 8.8 4.5 0.1 1.6 3ec S4/19/93
-31 24
-24 28 1.1 1.4
-8.2 1.5
-8.4 3.7 8.5 1.4 39C 10/25/93 m
-11 45
-9 23 1.2 1.7
-8.6 1.9 1.0 4.6 0.4 1.7 COLLECTION RU I-131 ZR NS-95 RU-103
___.___-le6__.___
_....._-95_.
.___.__-65.__...
ZM LOCATION DATE
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
28 02/08/93
-0.4 3.2
-2.9 4.4 1.8 2.4 0.2 3.6 1
14
-49 126 28 05/10/93 9.9 3.4
-5.8 3.7 2.5 2.2 2.3 3.3
-9 13
-38 73 28 87/12/93
-3.2 3.1 2.8 5.8 8.9 2.9 s.e 5.2 le 14 0
1210 28 11/e8/93
-1.6 2.7
-1.1 3.8
-4.5 1.9 1.2 3.8 1
12
-38 119 30C 01/25/93 1.8 3.7 8.8 4.8 0.0 2.1 0.7 4.3 16 16 29 22 1
30C 84/19/93 2.1 3.0
-1.5 3.1 3.2 1.9
-0.6 2.8 0
13 2
13 30C 18/25/93 m 2.3 3.8 3.6 4.3 8.0 2.0
-0.6 2.5
-1 15
-9 15 i
i w Third quarter sample from location (30C) was lost in transport.
- _ _ _______J
CONNECTICUT YANKEE 1995 TA8tE 14 PACE 3-37 RIVER WATER (PCI/L)
COLLECTION LOCATION DATE CS-154 CS
...... _- 137_....
_______-14e__....
BA
....__-148____.__
LA
.._____-226....__
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
28 82/08/93 0.4 1.6 1.6 1.6 8
6 2
26
-37.1 35.9
-0.5 3.0 28 45/10/93 2.3 1.7 e.8 1.5 6
4e 8
19
-15.1 35.8
-4.5 2.9 28 07/12/93
-0.7 1.5 0.2 1.4 e
238
-18 92
-12.1 26.6 0.8 2.4 28 11/08/93 0.2 1.3
-5.7 1.7
-22 52 e
25
-8.4 26.2 4.8 2.4
{
30C el/25/93 0.6 1.6 2.1 1.8
-2 19 8
9 21.9 44.7 3.0 3.8
)
30C 04/19/95 S.2 1.4 1.6 1.5
~3 13 2
6
-71.8 58.1 3.4 3.3 30C 10/25/95 a 1.5 1.8 1.1 1.9
-12 16
-1 7
-25.4 32.9
-3.1 2.9 COLLECTION 1
LOCATION DATE H-3 I
(+/-)
l 28 02/08/93 414 92 28 05/10/93 678 137 1
28 07/12/93 57 95 28 11/08/93
-45 99 30C 01/25/95
-13 74 30C 04/19/93 71 118 30C 10/25/93 m
-5 91 l
u Third quarter sample from location (39C) was lost in transport.
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4.0 plSCUSSION OF RESULTS This section summarizes the results of the analyses of environmental media sampled.
NUSCO has carefully examined the data throughout the year and has presented in this section all cases where plant related radioactivity could be detected and compared the results with previous environmental surveillance data. The fuel failures experienced during the previous two operational cycles which caused positive plant indications have since been cleaned up and eliminated. Thus, few impacts of plant operation were observed in environmental media during 1993. Subsections contained describe each particular media or potential exposure pathway. The dose commitments from these plant-related exposures is insignificant and is explained in Section 5.
Naturally occurring nuclides such as Be-7, K-40, Ra-226 and Th-228 were detected in numerous samples. Be-7, which is produced by cosmic processes, was observed i
predominantly in airborne and vegetation samples. Ra-226 and Th-228 results were i
L variable and are generally at levels higher than plant related radionuclides.
Cs-137 and Sr-90 were observed at levels similar to those of past years. In general, the r
L detectable levels of Cs-137 and Sr-90 were the result of atmospheric nuclear weapons testing of years past.
Gamma Exoosure Rate (Table 1)
)
Gamma exposure from all sources including cosmic and other natural and artificial radioactivity is measured over periods of approximately one month using CaF (Mn)
{
thermoluminescent dosimeters (TLDs). These dosimeters are strategically placed at a number of on-site locations, as well as at inner and outer off-site locations. Glass bulb type TLDs such as these, are subject to inherent self-irradiation which has been experimentally measured for each dosimeter. The results, shown in Table 1 have been adjusted for this effect. The range of this correction for field dosimeters is O.4pR/hr to 2.0 pR/hr, with a mean of approximately 1 pR/hr.
L Examination of the data for 1993 reveals the same trends as that of previous years; gamma exposure rates did not differ significantly for the off-site inner and outer ring locations. Four on-site locations within the plant's site boundary were the only locations showing any plant effects.
The environmental trail (location 42X) shows an average increase of 4.0 pR/hr over its historical normal background for the period June through July. Over this same period, the location near the intake structure (location 40X), the old waste gas sphere fence -
(location 45X) and the info center (location 47X) show average increases of 2.0 R/hr, 4
1.8 R/hc, and 3.9 pR/hr, respectively. These increases were caused by plant refueling activities. During this period the RWST was drained down. The increases were due to the lack of water in the RWST which normally provides shielding from the gamma shine 4-1
ll l
produced by contained crud and deposited radionuclides. The two largest increases g
noted in the environmental program TLDs were both located on the north side of the y
station. The other two locations showed only a slight increase due to their physical location and distance from the RWST source. Because locations 42X and 47X aie areas which are accessible to the public, the possible dose commitment, even though insignificant, from this plant related exposure is explained in Section 5.
Air Particulates and lodine (Table 2,3,4 A-D and 5)
Air is continuously sampled at seven inner ring and two outer ring locations by passing it through glass #iber particulate filters. These are collected weekly and analyzed for gross beta radioactivity. Results are shown on Figure 4-1 and Table 2.
I Gross beta activity remained at levels similar to that seen over the last decade. Inner j
and outer ring monitoring locations showed no si nificant variation in measured
]
C activities. This indicates that any plant contribution is not measurable.
{
1 Charcoal cartridges are included at all of the air particulate locations for the collection of iodine. No detectable levels of I-131 were seen in the 1993 charcoal samples. This l
Is confirmed by the absence of I-131 in any of the milk samples. Milk from cows and goats is a much more sensitive indicator of I-131 presence in the environment.
The weekly air particulate filters are composited quarterly for gamma spectral analyses.
The results, as shown in Tables 4A-4D, indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. Positive results for all the other isotopes are attributable to statistical fluctuations in counting. These analyses indicate the lack of plant offects.
Table 5 in past years was used to report the measurement of Sr-89 and Sr-90 in quarterly composited air particulate filters. These measurements are not required by the Radiological Effluent Monitoring Manual (REMM) V i have been discontinued.
Previous data has shown the lack of detectable station ac, (y in this media. This fact,
{
and the fact that milk samples are a much more sensitive.1dicator of fission product existence in the environment, prompted the decision for discontinuation. In the event of widespread plant contamination or specini event such as the Chernobyl incident, these measurements may be made.
Snil (Table 6)
I Soll samples are special samples not required by the REMM. Previous data has shown the lack of detectable station activity in this media resulting in discontinuing these samples. In the event of widespread plant contamination or special studies, these sample would be collected.
4-2 Il
1 1
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Cow Milk (Table 7) i
/
Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that
{
consumption of milk is significant, results in this pathway usually being the most critical 1
from the plant release viewpoint. This pathway also shows significant amounts of I
nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there are any plant effects.
Sr-90 was observed in nearly all samples; all results were below 4 pCi/l. Detailed analysis of previous data has concluded that these levels of Sr-90 are from weapons testing and are not plant related (see Section 6.0 for details to this argument). Sr-89 L
was not detected ir, any of the samples above its MDL. This isotope is usually released i
from the ment in quantitles similar to those of Sr-90, indicating that Sr-90 is the result I
of weapuns tening and not from the plant. Sr-89 is only detected in these samples during episodes of fresh fallout from weapons testing.
Cs-137 usually shows the same tendencies as Sr-90. Results for 1993 are similar to those of the past fifteen years.
Detailed analysis has concluded that these l
concentrations are most likely the result of fallout from previous weapons testing (see Section 6.0 for details). Cs-134 was not observed above detectable levels in any of the samples, further confirming the absence of plant effects. Although not listed on Table f
7, the only other nuclide detected by gamma spectrometry was naturally occurring K-i 40.
All samples showed a lack of I-131 detectable above the MDL of 0.5 pCi/l. These results are consistent with previous year's results, f
Goat Milk (Table 8) l Depending on the feeding habits, goat milk can be a more sensitive indicator than cow-i i
milk of fission products in the environment. This is due to the metabolism of these animals. Similar to the results of the cow milk samples, these show significant amounts l
l of nuclear weapons testing fallout.
Sr-90 and Cs.137 were observed in most samples, with values similar at both locayuns.
l l
In previous years (1977 - 1983) the controllocation had significantly higher valuet than 1
[
the indicator location.
This difference in results between locations decreased substantially with a change in farms in 1983. The difference in results demonstrate the variability in the uptake of fallout levels among various farms. This variability is caused L
by many factors, including feeding habits (amount of stored feed, etc.), soil L
characteristics, farming practices (tillage and quality of fertilization and land -
management), and feed type. For a comp lete discussion of the problem see Section 6.0. As typical of periods lacking fresh fallout, no detectable Sr-89 was seen in these 4-3 i
l
samples. The absence of Sr-89 and Cs-134 confirm that the levels of Sr-90 and Cs-137 are caused by previous weapons fallout.
All samples showed a lack of I-131 detectable above the MDL of 0.5 pCi/l. These i
results are consistent with previous years' results. The only occasions when this
]
nuclide has been detected are those immediately following atmospheric testing of nuclear weapons and the Chernobyl accident.
Pasture Grass (Table 9)
When the routine mi!k samples are unavailable, samples of pasture grass are required as a replacement. The.ie samples may also be taken to further investigate the levels of radioactivity in milk. In samples of past years, no plant effects were seen in this media.
There were no pasture grass samples taken in 1993.
Well Water (Table 10)
Activity in this media results from either soluble plant evfluents permeating through the -
ground or the leaching of naturally occurring nuclides from the soil and rock. H-3 was detected in these samples, at levels similar to previous years.
i As usual the on-site wells (location 15) exhibited plant ielated H-3 significantly above j
background levels. This plant effect results from the wells being located within an area -
(
influenced by the water in the discharge canal and H-3 having the ability to readily-
)
follow the flow of ground water. Off-site concentrations are much lower. This pathway i
does not result in any dose consequence since the water from these wells is used only in process streams at the station.
1 1
l Reservoir Water (Table 11)
Reservoir water samples are special samples not required by the REMM. Previous data has shown the lack of detectable station activity in this media. This fact and the
[
extremely unlikely possibility of observing routine plant effluents in this media has resulted in discontinuing these samples.
In the event of - widespread plant contamination, these samples may be collected.
Fruits and Veaetables (Table 12)
Similar to past years, this media did not show any plant effects. Concentrations of.
Sr-90 in these samples existed at levels comparable to past years and is due to fallout.
Naturally, occurring K-40 was detected in all samples. Since there was no fresh fallout, l
no other nuclides were detected.
4-4
Broad Leaf Veoetation (Table 13)
Concentrations of Sr-90 and Cs-137 in these samples are at levels comparable to past years and are due to fallout. Historically, this media has shown early indication of I-131 release from the plant from both unplanned releases and normal operations. Therefore, to enhance program monitoring effectiveness, samples of broadleaf vegetation are collected monthly during the growing season, April-October, even though requirements are to collect twice a year.
in May after a small unplanned release of iodine, two special broadleaf smples were taken on site within the predominant wind direction. No indication of plant-related i
radioactivity was observed.
River Water (Table 14) l These samples are collected on a quarterly basis; the sampling procedure is different at the control and indicator locations. Weekly grab samples of the first six weeks of each j
quarter are composited at the control station (Middletown -location 30C). Continuous l
samples, collected for the entire quarter, are utilized at the indicator station (East Haddam Bridge - location 28).
)
Tritium was observed above background levels at the indicator location in the first and second quarter samples. These elevated levels are attributable to plant operation. The levels measured are comparable to those seen in years past. Because this nuclide only emits low energy beta particles and river water is not a source of drinking water, the dose consequence resulting from these levels is insignificant. Fish consumption is the r'
only media through which the population encounters dose from H-3 in liquid effluents.
The dose consequence of the H-3, although not routinely measured in fish, is calculated i
based upon the measured effluents and appropriate dispersion models (NRC approved computer code LADTAP). In order to verify these calculations, a special program of measuring H-3 in fish samples had been performed. The result of these analyses indicated that the effluent calculations are conservative. The dose consequences, discussed in Section 5.0, are insignificant.
Bottom Sediment (Table 15) 7: ant related levels of Co-60 were observad at indicator location (Area of Plant Discharge -location 29). These levels are comparable to those observed in past years.
Cs-137 was observed in both the indicator and the control locations at levels similar to past years. The Cs-137 levels at the control location are due to fallout and are at or lower than levels seen at the indicator locations, a portion of the Cs-137 in the indicator samples is likely due to plant operation.
Shellfish (Table 16) 4-5 i
g
I b
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Plant related Co 58 and Co-60 were observed in one sample taken from East Haddam Bridge (location 28X). No other activity was observed except for the naturally occurring radionuclides. Because this media is not a source of consumption, other media (e.g.,
(
fish results) are utilized in the determination of dose consequences.
Fish Bullheads (Table 17A)
{
Cs-137 was observed in both the indicator and the controllocations at levels similar to past years. Even though Cs-134 was not observed, a portion of the Cs-137 in these
[-
samples could be due to plant operation. No other activity was observed except for the naturally occurring radionuclides. Dose consequences were calculated based on the detected concentrations. The results of the calculations are shown in Section 5.0.
Fish-Perch and Other Tvoes (Table 178)
These fish samples exhibit similar results as the bullhead samples.
Cs-137 was detectable at both indicator and controllocations. The dose consequence, though very l
minimal, is discussed in Section 5.0.
1 4-6 J
wr e
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-Figure 4-1 CY AIR' PARTICULATE Gross Beta fladioactivity pC1/m3
- 0.02 t
l($1ndicators B Controls) 2
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L 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS The off-site dose consequences (dose equivalent commitments) of the statk i
radioactive liquid and airborne effluents have been evaluated using tu methods.
The first method utilizes the stations' measured radioactive discharges as input parameters into conservative models to simulate the transport mechanism through the environment to man. This results in the computation of the maximum doses to individuals and the O to 50 mile population dose. The rest,lts of these computations have been submitted to the L
NRC in the Annual Radioactive Effluent Report written in accordance with the Radiological Effluent Monitoring Manual, Section F.2.
The second method utilizes the actual measurements of the concentrations of radioactivity in y
various environmental media (e.g., milk, fish) and then computes the dose consequences resulting from the consumption of these foods.
The first method, which is usually conservative (i.e., computes higher doses L
than that which actually occur), has the advantage of approximating an upper p
limit to the dose consequences. This is important in those cases vwhere the L
actual dose cannot be measured because they are so small as to be wel, below the capabilities of conventional monitoring techniques. The results of both r
methods are compared in Table 5.1. For gaseous releases, no plant related L
detectable activity was observed in any sampling media. The less-than values given for Method 2 are the doses which would be calculated if the annual r
average activity was equal to the minimum detectable level. Although the liquid releases are also low, traces of plant related activity were detected in fish, shellfish, bottom sediment, well water, and river water samples.
The doses presented in Table 5.1 are the maximum doses to an individual for specific pathways to man. That is, the dose is calculated at the location of
[
maximum effect from the plant effluents for that pathway and for the critical age group. For example, the external gamma dose is calculated at the site A
boundary which has the least meteorological dispersion. The calculations result in maximum total doses to an individual of: 1.0 mrem whole body to an adult, 0.19 mrem to a child's thyrold, and 0.28 mrem to a teen's liver. The calculated doses for all other locations and other age groups will be less than those shown
[
on Table 5.1.
The average dose to an individual within 50 miles from the site cannot be
(
calculated using the second method. However, Method 1 yields the following results fer the period January - December 1993 for the average individual:
I ANNUAL AVERAGE WHOLE BODY DOSE :
DUE TO AIRBORNE EFFLUENTS = 0.00019 mrem DUE TO LIQUID EFFLUENTS = 0.000041 mrem 5-1
E Thus, it can be seen that the average whole body dose to an individual is much less than the maximum whole body dose to an individual as shown in Table 5.1.
In..er to provide perspective on the doses in Table 5.1, the standards for 1993 on the allowable maximum dose to an individual of the general public are I
given in 40CFR190 as 25 mrei.i thole body,75 mrem thyroid, and 25 mrem
[-
any other organ. These standards are a fraction of the normal background I
radiation dose of 280 mrem per year and are designed to be inconsequential in regard to public health and safety. Since plant related doses are even a smaller fraction of natural background, they have insignificant public health consequences, in fact, the plant related doses to the maximum individual are less than 10% of the variation in natural background in Connecticut.
L 1
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TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS HADDAM NECK STATION JANUARY - DECEMBER 1993 ANNUAL DOSE IMILLIREM)
PATHWAY ORGAN METHOD 1"'
METHOD 2"'
AIRBORNE EFFLUENTS 1.
External Gamma Dose Max. In.i28-Whole Body 0.55 ND
Whole Body 'S' N/A 0.26 2.
a.
Inhalation Max. Ind.i2: - Thyroid 0.083 NAD'", < 0.6 b.
Vegetables Max. Ind.i2' - Liver O.15 NAD c.
Goat's Milk Max. Ind." - Thyroid 0.013 NAD, < 1.8 LIQUID EFFLUENTS 1.
Fish Max. Ind. - Whole Body 0.20 0.035 Max. Ind. - Liver 0.28 0.055 (1) Method 1 uses measured station discharges and meteorological data as input parameters to conservative transport to man f
models. Method 2 uses actual measured concentrations in environmental media.
(2) Maximum individual-The maximum individual dose is the dose to the most critica: age group (teen for inhalation, infant for milk, and child for vegetables), at the location of maximum concentration of plant related activity. The dose to the average individualis much less than the maximum individual dose. The doses for inhalation and vegetable consumption assume that the individual rssides at the point of maximum quarterly dose. Therefore, his residence is subject to variation for conservatism.
(3) NAD - No activity detected above the minimum detectable level. The less-than value reported is the yearly dose corresponding to the MDL.
(4) The plant effects were so small that they could not be distinguished from fluctuations in natural background.
(5) The individual dose at the accessible on-site location of maximum measured exposure from plant-related activities, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of-exposure per week during the effected months June through July were assumed.
=
6.0 DISCUSSION The evaluation of the effects of station operation on the environment requires the
(
careful consideration of many factors. Those factors depend upon the media being effected. They include station release rates, effluent dispersion, occurrence of nuclear weapons tests, seasonal variability of fallout, local environment, and locational
(
variability of fallout. Additional factors affecting the uptake of radionuclides in milk include soll conditions (mineral content, pH, etc.), quality of fertilization, quality of land management (e.g., irrigation), pasturing habits of animals, and type of pasturage. Any
[
of these factors could cause significant variations in the measured radioactivity. A failure to consider these factors could cause erroneous conclusions.
Consider, for example, the problem of deciphering the effect of station releases on the.
radioactivity measured in milk samples. This is an important problem because this product is widely consumed and fission products readily concentrate in this media.
Some of these fission products, such as 1-131 and Sr-89 are relatively short-lived.
Therefore they result from either plant effluents, recent nuclear weapons tests or recent nuclear incidents (e.g. Chernobyl). Sr-89's lifetime is longer than 1-131's, therefore it must be remembered that it will remain around for much longer periods of time.
Problems are caused by the long lived fission products, Sr-90 and Cs-137. These r
isotopes are still remaining from the high weapons testing era of the 1960's. This L
results in significant amounts of Sr-90 and Cs-137 appearing in milk samples.
Distinguishing between this " background" of fallout activity and plant effects is a l
difficult problem.
In reviewing the Sr-90 and Cs-137 measured in cow and goat milk in the areas around i
[
the Millstone and Haddam Neck stations, a casual observer could notice that in some l
l cases the levels of these isotopes are higher at farms closer to the station than at those l
further away from the stations. The stations effluents might at first appear to be
{
responsible. However, the investigation of the following facts prove this conclusion wrong.
l
[
1.
The stations accurately measure many fission products, including Sr-90 and Cs-137 in their releases. Based on these measurements and proven models developed by the Nuclear Regulatory Commission, concentrations in the environment can be calculated. These calculations (generally conservative, see 1 Section 5.0) show that insufficient quantities of Sr-90 and Cs-137 have been released from the stations to yield the measured concentrations in milk.
2.
Over the many years of plant operation, Sr-89 has often been released in comparable quantity to Sr-90. Since they are chemically similar, comparable
{
levels should have been detected in milk in the Sr-90 was plant related. No plant related Sr-89 has ever been detected in milk samples.
f 6-1 l
l
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3.
Similar to Sr-89, Cs-134 can be used as an indication of plant related Cs-137.
Although not as conclusive as Sr-89, the lack of any measurable Cs-134 in any of the milk samples suggests that the Cs-137 is not plant related. This is further confirmed by the evaluation of the air particulate data. The only occurrences of detectable Cs-134 in milk resulted from the Chernobylincident.
h 4.
Since dairy milk sampling began in the 1960's, years prior to plant operation, the a immediate station areas have always shown higher lovels of weapons fa!!out j related Sr-90 and Cs-137 (see Figures 6-1 and 6-2).
The ratio of activity l
[
between the locations has not changed with plant operation. All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban j Treaty.
]
5.
Local variability of Sr-90 and Cs-137 in milk is common throughout the United States. Due to the variability in soil conditions, pasturing methods, rainfall, etc.,
it is the rule rather than the exception. Therefore, it is not surprising that certain farms have higher levels of radioactivity than other farms. In fact, there are -
some cases where the farms further from the station have higher Sr-90 and..,
F L
Cs-137 values than the farms that are closer to the station (e.g., see pre-1984 Haddam Neck Goat Milk data.)
6.
The Millstone goat farm with the highest levels of Sr-90 and Cs-137 has also-experienced the highest levels of short-lived activity from the 1976 and 1977 Chinese Tests and the 1986 Chernobyl accident. This indicates that for some unknown reason this farm has the ability for higher reconcentration. Special' studies performed at this and other farms failed to find any link to the plant.
E Based on these facts, the observation that the station effluents are responsible is obviously false. The cause must be one or more of the other variables.
E E
[
6-2
[?
Northeast Utilities has carefully examined the data throughout the year and has -
{
presented in this report all cases where plant related radioactivity can be detected. An-analysis of the potential exposure to the population from any plant related activity has
{
been performed and shows that in all cases the exposure is insignificant.
~
Throughout the year, the Connecticut Department of environmental Protection performs.
p a parallel environmental program under contract with the Nuclear Regulatory.
Commission. On a regular basis, the results of their' analyses are compared to' the results from this program's analyses. The comparisons are tracked and used as a cross-f reference to verify measured plant activity. During 1993, both programs showed similar -
results.
{
As in previous years, this data is being submitted.to, and will be reviewed by the appropriate regulatory bodies such as the Nuclear Regulatory Commission, Environmental Protection Agency and Connecticut Department of Environmental.
(;-
Protection.
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APPENDIX A z
P L
COW AND GOAT CENSUS FOR 1993
(
)
2 t
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A-1
_______.m______
_____m___________
i e
Dairy Cows Within 15 Miles of Connecticut Yankee As of December 1993 Direction Distance Name and Address
- of Cows NNE 14 M Robert K. Gasper 65 694 Gilead Street Hebron, CT 06248 NNE 14 M Hills Farm 125 527 Gilead Street
[
Hebron, CT 06248 NNE 14 M Mapieleaf Farm, Inc.
169 750 Gilead Street Hebron, CT 06248 NNE 14 M Gordon N. Rathburn 36 Martin Road Hebron, CT 06248 1
NNE 14.5 M Douglas Porter 127 RFD #1 Hebron, CT 06248
)
r NE 4.5 M John Dill 14 3
I 127 Waterhole Rd.
l Colchester, CT 06415
-East Hampton-NE 14 M Victor Botticello 28 Levita Road Lebanon, CT 06249 ENE
.5 M Grandpa Hill Farm 40 R.S. Cone Box 251 i
East Haddam, CT 06423 ENE 11 M Richard Swider 40 g
{-
Route 85 Colchester, CT 06415 l
ENE 14 M Robert Avery 27 Rathburn Hill Road Colchester, CT 06415
- Salem -
ENE 14.5 M Walter Makarevich 0
Geer Road Lebanon, CT 06249 (out of business)
Dairy Cows Within 15 Miles of Connecticut Yankee As of December 1993 Direction -
Distance Name and Address
- of Cows E
11.5 M Salem Valley Farm Dairy 35 h'
Eugene Wilczewski Darling Road Salem, CT 06415 E
13 M Garry Vaill 0
Forsythe Road Salem, CT 06415 (call next year)
E 14 M Stuart Gadbois 200 Route 82 Salem, CT 06415 S
2.9 M Norman C. Manning 1
530 Plains Road Haddam, CT 06438 SE 11 M Tiffany Farms 80 Sterling City Road Old Lyme, CT 06371 l
- Lyme -
l SE 12 M J. Ely Harding 50 Ashlawn Farm Old Lyme, CT 06371
- Lyme -
1 SW 14.5 M Sugarloaf Farm 26 154 Beaver Head Road North Guilford, CT 06437 1
WSW 8M Michael Dwyer 34 Route 17 Durham, CT 06492 1
- Wallingford -
WSW 8M Robert Raudat 43 Old Durham Road Killingworth, CT 06417 WSW 11 M Raymond Wimler 191 Guilford Road Durham, CT 06422
~l i
WSW 14 M
- Cella Brothers 98 l
Whirlwind Hill
)
2 No. Brandford Street
(.
Wallingford, CT 06492
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V L'
I Dairy Cows Within 15 Miles of Connecticut Yankeg As of December 1913
(
Direction Dhtanga Name and Address
- of Cows WSW 15 Co Ag Farm, Inc.
220 4
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Walter Augur & George Cooke 180 Northford Road Wallingford, CT 06492 l
W 8.5 M Richard Rowe 28 Box 4, Higganum Road
)
Durham, CT 06422 W
11.5 M Friendly Acres Diary Farm 25-Tony Caltabiano Parmalee Hill Road L
Durhar1, CT 06422 i
W 14 M North Farms 28
[
Walter Werbiski 1069 Farms Road Wallingford, CT 06492 l
W 14.5 M Charles Greenback & Sons, Inc.
118 Box 451, Route 68 Durham, CT 06422 WNW 7M Calvin Harvey 35 55 Tryon Street Middletown, CT 06457 i
WNW 8M Richard Brock 25 787 Ridge Road Middletown, CT 06457 WNW 12 M John Kolman 29 Meriden Road Middletown, CT 06457 WNW 12 M Walnut Hill Farm 90 William & Thomas Mintz Jackson Hill Road Middlefield, CT 06455 WNW 15 M Bilger Brothers 23 Hickory Grove Farm 705 Westfield Road Meriden, CT 06450
.-----____--.__--.-----------_----.--------_-_--,-------------__---_------.------__a.---___
---,.,,-wo,
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I 1
Dairy Cows Within 15 Miles of Connecticut Yankee As of December 1993 I
Direction Distance Name and Address
- of Cows NW 6M Edward Hills 25 Brooks Road Middletown, CT OS457 NW 13 M Higgins Farm, Inc.
62 837 Ridgewood Road Middietown, CT 06457 NW 15 M Wenceslaus & Jean Backiel 31 E-Riverside Farm RFD #2 Berlin, CT 06067
- Rocky Hill -
NW 15 M John W. Meisterling 49 Box 385, France Street Rocky Hill, CT 06067 NNW 14 M Roaring Brook Farm 0
Henry Killam I
77 Tryon Street (sold out)
South Glastonbury, CT 06073
- Glastonbury -
I I
I I
- - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - -
I DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF DECEMBER 1393 I
l DIRECTION DISTANCE NAME AND ADDRESS
- GOATS N
4.5 M Philip Bourdon 23-164 Young Street East Hampton, CT 06424 N
15 M
Joan & Thomas Kemble 5
581 Thompson Street Glastonbury, CT 06033 NNE 12 M Louise Sage
-5 155 Reidy Hill Road Hebron, CT 06248 NNE 16 M
Joan Bowers 2
/
350 Wall Street L-Hebron, CT 06248 NNE 16 M
Kathy Waters 30 Burnt Hill Road Hebron, CT 06248 NE 16 M Barbara Nadeau O'
Clubhouse Road Lebanon, CT 06249 NE 17 M Lynn Miller 70 Goshen Hill Road Lebanon, CT 06249 i
NE 8M Johnathan & Elizabeth Gilman 2
178 Cato Corner Road Colchester, CT. 06415 SSE 10 M Laura Parker
-5 95 Plains Road Essex, CT 06426
.____ ____ u- _ __________-_____
__________________----z--------____--_-:--_-_________z______________;
)
i DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF DECEMBER 1993 DIRECTION DISTANCE NAME AND ADDRESS
- GOATS NE 14.5 M Sharon Stewart 6
Old Colchester Rd.
1 Lebanon, CT l
l l
E 12 M Anne B. Henrici 4
Round Hill Road q
Salem, CT 06415 q
ESE 13 M Dave & Pam Richards 285 Grassy Hill Road Lyme, CT 06371 SE 19.5 M Mrs. John Mingo 7
69 Spithead Road Waterford, CT 06385 l
l SE 15.8 M George Scacciaferro 3
338 Boston Post Road East Lyme, CT 06333 S
11.5 M Victor Trudeau 5
174 Horse Hill Road Westbrook, CT 06498 W
4.8 M Pat Mannetho Jacoby Road Higganum, CT 06441 W
14.5 M Robert Pogomore 0
177 Williams Road Wallingford, CT 06492 W
DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF DECEMBER 1993 DIRECTION DISTANCE NAME AND ADDRESS
- GOATS
[
'l W
15.3 M Jim & Mary Hall Pettack 19 1000 North Farms Road Wallingford, CT 06492 WNW 19 M Daniel Nitkowski 3
46 Fitch Avenue Meriden, CT 06450 NNW 14 M Dorothy Joba 8
171 Ferry Lane S. Glastonbury, CT 06073 NNW 15 M Donald Reid 12 1654 Main Street Glastonbury, CT 06033 4
- UNABLE TO CONTACT AS LY THIS Tntl TOTAL NUMBER Of GOAT ARELMTED FOR THM CENSUS.
y i
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t l..
L-APPENDIX B NORTHEAST UTILITIES QA PROGRAM i
B-1
Northeast Utilities Service Company (NUSCO), acting as the agent for both the Northeast Nuclear Energy Company (NNECO) and the Connecticut Yankee Atomic Power Company (CYAPCO), maintains a quality assurance (OA) program as part of the radiological environ-montal monitoring program (REMP). The OA program consists of contractor appraisals and quality control samples.
Appraisals are conducted of the primary (Teledyne Isotopes) and secondary (Yankee Atomic) radicanalysis contractors, of the Production Operations Support Laboratory (POSL), and of the NUSCO Radiological Engineering Section (RES). A REMP evaluation form is completed for each appraisal and discrepancies are tracked on a separate form until corrective action is taken. Each contractor, POSL, and RES are also audited by other organizations including other customers of the contractors and Northeast Utilities Quality Assessment Services of POSL and RES.
There are three types of quality control samples. They are:
1.
Duplicate analyses of actual surveillance samples and TLDs. For samples this type of quality control allows an evaluation of the contractor's precision or reproducibility of results. Duplicate TLD measurements at eight locations with TLDs of different design are made and readout at the NUSCO Personal Dosimetry Laboratory to verify the l
reliability of POSL's environmental TLD readings.
2.
Cross-check analyses of actual surveillance samples with more than one laboratory; e.g., Yankee Atomic Environmental Laboratory. This intercomparison allows the determination of what agreement the primary contractor has with another laboratory.
4 3.
Analyses of " spiked" samples and TLDs. This type of quality control allows a check on the accuracy of results for contractor's sample radioanalyses and for POSL's TLD readings.
The number and type of quality control samples are given in Table 1. In general, the objective was to obtain between 10 and 20 percent of the samples as quality control samples.
The results should satisfy acceptance criteria as defined in NUSCO Radiological Assessment Branch Procedure RAB 31," Quality Control of the Environmental TLD Monitoring Program,"
and in Procedure RAB 3-2," Quality Control of Radiological Environmental Monitoring Program." An investigation is conducted of any result or trend which does not satisfy acceptance criteria.
The NUSCO OA Program is not the only OA Program which monitors the primary contractor sample radioanalyses performance. Other programs include:
1.
Teledyne isotopes' internal OA program.
2.
Teledyne isotopes' participation in EPA's Environmental Radioactivity Laboratory intercomparison Studies Program.
3.
Nuclear Regulatory Commission State of Connecticut Independent Verification Program.
Primary contractor participation in the EPA Intercomparison Studies Program is required by plant technical specifications and the results of this program are contained in Appendix C.
weisxm B-2
The NUSCO OA Program indicated that, in general, the Teledyne isotopes' environmental radiological analysis program was adequate. Of the fourteen (14) investigations opened in 1993 for analyses which did not satisfy criteria, eight (8) were closed before the end of the year. Because Teledyne isotope has not been retained as the environmental radioanalysis contractor beyond 1993, the remaining open investigations have been closed. The new contractor, Yankee Atomic, had one quality control sample which failed criteria in 1993. The investigation of this quality control sample result has been closed.
The NUSCO QA Program indicated that the environmental TLD results were reliable. For twelve months of measurements the duplicate TLDs averaged 4.0 percent higher than the environmental TLDs with a range of 14.6 percent to -1.8 percent. For ten months (August and December excluded) the spiked TLDs averaged 2.5 percent below the spiked value with a range of -9.4 percent to 0.6 percent. August and December spike results exceeded the acceptance criteria. Investigation of the August test revealed that the TLD reader required a recalibration. Reader calibration was performed shortly after the spike test and it was determined that the normal environmental TLD readout was not affected by the reader j
malfunction. The reason for the December spike test failure has not yet been determined.
)
Preliminary investigation indicates that there may be an error with the spiking of the TLDs and j
not with the POSL readout.
i l
I i
1 j
1
'I Il B-3
{
i
_-------_---a
..I TABLE 1 NUMBER OF QUALITY CONTROL' SAMPLES 1993
.)
. NUMBER OF NUMBER OF SAMPLE TYPE
_OC SAMPLES
_ ROUTINE SAMPLES
108 Vegetation / Aquatic Flora / Bottom Sediment 4
84 Air Particulate Gross Beta 12 830 lodine 9
780 Gamma 8
60 l
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- An additional program is performed by the contractor.
i
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a - Total for both Millstone and Connecticut Yankea y
1 R
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l weisx o.'
B-4
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l r.
L' r
APPENDIX C t
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L
[
SUMMARY
OF EPA INTERLABORATORY COMPARISONS rL.
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c-1 1
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U.S. INTERLABORATORY COMPARISON PROGRAM 1993 (ENVIRONMENTAL)
YANKEE
{
DATE MEDIA NUCLIPE EPA (a)
TELEDYNE(b)
ATOMIC (b) 1/15/93 Water Sr-89 15.012.9 12.7 1.2 12.011.7 Sr-90 10.012.9 8.3 i 1.2 12.3 0.6 1/29/93
. er Beta 44.012.9 52.0 i 1.0(c)
No Result 2/5/93 W ater 1-131 100.015.8 106.7 i 5.8 109.3 i 5.5 3/5/93 Water Ra-226 9.8 i 0.9 7.7i0.1(d)
No Result Ra-228 18.512.7 19.312.3 No Result I
4/20/93 W ater Beta 177 15.6 150.0 i 0.0 No Result Sr-89 41.0 i 2.9 35.311.5 No Result Sr-90 29.012.9 27.3 i 0.6 No Result Co-60 39.0 i 2.9 40.713.5 No Result Cs-134 27.012.9 23.7 i 1.5 No Result Cs-137 32.0 i 2.9 34.312.1 No Result Ra-226 24.9 i 2.1 19.0 i 1.0 (d)
Ra-228 19.0 i 2.8 18.3 i 0.6 6/11/93 W ater Co-60 15.0 i 2.9 16.3 1.5 No Result 2n-65 103.0 5.8 121.312.1(e)
No Result Ru-106 119.0 6.9 106.3 i 15.9 No Result r
Cs-134 5.0 i 2.9 5.7 i 0.6 No Result L
Cs 137 5.0 i 2.9 6.7 i 0.6 No Result Ba 133 99.0 i 5.8 104.3 i 9.3 No Result
[
6/4/93 Water H-3 9844 568 9367 153 106031452 7/16/93 Water Sr 89 34.0 i 2.9 31.7 i 2.5 No Result-Sr 90 25.012.9 24.0 i 0.0 No Result F
7/23/93 Water Beta 43.0 i 2.9 42.712.5 42.712.9
.)
8/27/93 Air Filter Beta 47.012.9 49.0 i 1.7 46.0 i 0.0 Cs 137 9.0 0.6 9.7 iO.6 9.0 1.0 1
9/17/93 Water Ra-226 14.9 i 1.3 15.310.6 No Result
"{
1 Ra 228 20.4 i 2.9 20.711.2 No Result L
9/24/93 Milk Sr-89 30.0 i 2.9 35.7
- 3.5 20.0 i 1.7 Sr-90 25.0 i 2.9 24.0 7.0 22.7 i 1.7
{
l-131 120.0 i 6.9 127.0 i 6.0 119.7 i 2.1 Cs-137 49.0 2.9 50.7 1.2 48.710.6' K
1679i48 1620i17 1692 2.9 10/8/93 W ater 1-131 117.0 i 6.9 103.3 i 5.8 118.7 i 14.1 w eu w' C-2
E U.S. INTERLABORATORY COMPARISON PROGRAM 1993 (ENVIRONMENTAL)
YANKEE
{
DATE MEDIA NUCLIPE EPA (a)
TELEDYNE(b)
ATOMIC (b) 10/19/93 W ater Beta 58.0 i 5.8 51.313.2 No Result Sr-89 15.012.9 15.011.0 12.710.6
(
Sr 90 10.0 2.9 10.0 i 0.0 8.7 i 0.6 Co-60 10.012.9 12.011.0 9.7 1 0.6 Cs-134 12.0 i 2.9 9.0 i 1.0 9.7 0.6
[
Cs-137 10.0 i 2.9 12.7 i 2.5 10.6 i 0.6 10/29/93 W ater Beta 15.012.9 15.712.1 17.3 i 1.5
(
11/5/93 W ater H-3 7398i427 69001100 71641387 11/12/93 W ater Co 60 30.012.9 28.7 i 2.9 30.0 i 1.7 Zn-65 150.0 i 8.7 152.019.2 152.3 i 1.2 Ru-106 201.0 i 11.5 177.3 5.5 165.714.5 Cs-134 59.0
- 2.9 53.314.9 57.3 i 0.6 Cs-137 40.012.9 41.3 i 3.1 42.010.0 Ba-133 79.014.6 69.3 i 3.1 80.0 i 1.7 FOOTNOTES
{
Units are pCl/ liter for water and milk, except K is in mg/iiter. Air particulate filters are in units of total pCI.
l (a)
EP known value i standard error of the mean (1 sigma).
[
(b)
Average of three analyses i one standard deviation of the three analytical results. If the average value is not within the EPA value i three times EPA standard deviations it is outside of EPA control limits.
(c)
By oversight, the special self-absorption curve which had been previously derived using EPA water and Cs-137 standard was not used.
(d)
The counting data and backgrounds were verified. Possibly some efficiencies used were erroneously high, causing low values. A less likely cause is an error in dilution. New Ra 226 standards will be prepared. Closer monitoring of out of control efficiencies will be done and extra care in preparation of the sample will be maintained.
]
('.
(o)
The calculations were checked and found to be correct. The results of six gamma emitting isotopes were reported to the EPA. The results of four were within one (1) normalized deviation; a fifth, within j
two (2) normalized deviations. Only the Zn 65 average was outside the control limits. There is no l
{
reason why one isotope should be outside the control limits, while five other isotopes were within j
control limits.
{
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u m a cei C-3
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