B12887, Radiological Environ Monitoring Program Annual Operating Rept,1987
| ML20151W264 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1987 |
| From: | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES, NORTHEAST UTILITIES SERVICE CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| B12887, NUDOCS 8805030339 | |
| Download: ML20151W264 (107) | |
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HADDAM NECK STATION RADIOLOGICAL ENVIRONM ENTAL MONITORING PROGRAM ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PERIOD JANUARY 1,1987 - DECEMBER 31,1987 DOCKET NO. 50-213 LICENSE NO. DPR-61 PREPARED FOR THE CONNECTICUT YANKEE ATOMIC POWER COMPANY H ADDAM, CONN ECTICUT BY THE NORTHEAST UTILITIES SERVICE COMPANY
! BERLIN, CONNECTICUT
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TABLE OF CONTENTS Paae No.
1.0 Summary..................................................... 1-1 2.0 Pro g r a m Descri ptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 4
2.1 Sampling Schedula and Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 2.2 Samples Collected During Report Period . . . . . . . . . . . . . . . . . . . . . . . . . 2-7 3.0 R adioch e mical Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 3.1 Summary Table . . . . . .........................................3-1 3.2 D a t a Ta b l e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 - 16 4.0 Discussio n o f Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 S.0 Offsite Dose Equivalent Commitments . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 6.0 Discussion . . . . . . . . . . . .................... .................... 61 Appendix A - Cow and Goat Census for 1987 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 Appendix B - Northeast Utilities QA Prog ram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B1 Appendix C - Summary of EPA Interlaboratory Comparisons . . . . . . . . . . . . . . . . C-1 l
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1.0
SUMMARY
The radiological environmental monitoring 3rogram for the Haddam Neck Plant was continued for the period January throug1 December 1987,in compliance with the Radiological Effluent Monitoring and Offsite Dose Calculation Manual. This annual report was prepared for the Connecticut Yankee Atomic Power Company (CYAPCO) by the Radiological Assessment Branch of the Northeast Utilities Service Company (NUSCO). Gamma exposure measurements were performed by NUSCO and tritium analyses were performed by Teledyne isotopes, Inc. All the remaining analyses were performed by Clean Harbors,Inc. Teledyne Isotopes,Inc.was used to independently check on the primary contractor's laboratory as part of the overall quality assurance program.
I 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. Plant related radioactivity was observed at some of the onsite gamma monitoring locations and in several other environmental samples. These include tritium in well water at the on-site location, tritium in river water near the East Haddam Bridge, cobalt 60 in bottom sediment from near the end of the canal, cobalt-58 and cobalt 60 in shellfish taken at the Mouth of the Salmon River, and cesium 137 in fish caughtin the discharge canal.
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 1960's and not the result of plant operation. This can be concluded based on the facts that: insufficient quantities (at least 1000 times less) of these isotopes have been released by the plant to account for the measured concentrations, chemically similar and plant I
related cesium 134 and strontium 89 which are released in about equal or larger
- quantities from the plant can not be detected and comparable levels of cesium 137 and strontium 90 were detected prior to initial plant operation.
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 radioactivit The maximum whole body dose (stationthat boundary)y could occur toina the environmen member of the general public as a result of the plant's discharges was 1.5 millirem and the
! average dose to a member of the public residing within 50 miles of the plant is 0.00026 millirem. These doses are 6.0 percent and 0.0010 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 70 percent) of the 270 mrem per year normal background radiation and are f
r designed to be inconsequentialin regard to public health and safety. Plant related l 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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, O a e 2.0 PROGRAM DESCRIPTION 2.1 Samplina schedule and Locations The sample locations and the sample types and frequency of analysis are given in Table 21 and 2 2 and Figures 2.7 and 2.2. The program as described here is both that which is required by the Radiological Effluent Monitoring and Offsite Dose Calculation Manualand any extra samples.
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TABLE 21 ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The following lists the environmental sampling locations and the types of samples obtained at each location.
Direction & Distance From Number ,N,,a,m e Release Point *
- Sample Types 1 l* On site Mouth of Discharge Canal 1.1 Mi, ESE TLD 21 Haddam Park Rd. 0.8 Mi, S TLD 31 Haddam Jail Hiil Rd. 0.8 Mi, WSW TLD 41 Haddam Ranger Rd. 1.8 Mi, SW TLD, Air Particulate, lodine 51 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 7-l Haddam 1.8 Mi, SE TLD, Air Particulate, lodine 8-l East Haddam 3.1 Mi, ESE TLD, Air Particulate, lodine 9-l Higganum 3.2 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 We:I Water 16 C Well State Highway Dept. E. Haddam 2.8 Mi, S E Well Water 17-C Fruits & Vegetables Beyond 10 Miles Vegetation 18 l Site Boundary 0.4 Mi, NW Vegetation 19 1 Cow Location # 1 1.5 Mi, NNW Milk 20-1 Cow Location #2 6.0 Mi, NW Milk 21 1 Cow Location #3 4.5 Mi, NE Milk 22-C Cow Location #4 11.0 Mi, N E Milk 23-C Goat Location # 1 16.0 Mi, N E Milk 24 1 Goat Location #2 4.5 Mi, N Milk 25-1 Fruits & Vegetables Within 10 Miles Vegetation 26 1 Conn. River-Near intake 1.0 Mi, WNW Fish 27 C Conn. River Higganum Light 4.0 Mi, WNW Bottom Sediment, Shellfish 28l Co.. %er E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 28 X Conn. River E. Haddam Bridge 1.8 Mi, S E Shellfish 29 1 Vicinity of Discharge - --- Bottom Sediment, Fish 30-C Conn. River Middletown 7.6 Mi, NW River Water, Fish 31 1 Mouth of Salmon River 0 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 Boron Waste Storage Tank Fence 0.1 Mi, NW TLD 43 X Moodus - Rts 149 & 151 2.5 Mi, EN E TLD 44 X Shailerville Horton Rd. 1.0 Mi, S E TLD 22
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- TABLE 2-1 (Ccnt'd)
Location Direction & Distance From Number NA!D.t Release Point *
- Sample Tvoes 45 X Waste Gas Sphere Fence 0.1 Mi, E TLD 46 X Discharge Canal Fence 0.2 Mi, SE TLD 47 X Guard House Fence 0.1 Mi, WNW TLD
- l = Indicator C - Control X - Extra nonreqv, red sample
- The release points are the stack for terrestiallocations and the end of the discharge canal for aquatic locations, i
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_T_AB W 2-2 HADDAM NECK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling &
Exposure Pathway Number of Collection and/or Samole Locations Frecuency Tvoe & Frequency of Analysis ia. Gamma Dose- 14 Monthly Gamma Dose Monthly Environmental TLO 1b. Gamma Dose- 27 Quarterly (a) N/A(a)
Accident TLD
- 2. Airborne Particulate 7 Continuous sampler - Gross Beta Weekly weekly filterchange Gamma Spectrum Monthly on composote (by location), & on individual sample of gross beta is greater than 10 times the mean of the weeky control stations gross beta results
- 3. Airborne lodine 7 Continuous sampler -
l 131 Weekly weekly canisterchange
- 4. Vegetation 3 One sample near middle Gamma Isotopic on each sample
& one near end of growing season
- 5. Milk 6 Monthly Gamma Isotopic,1131, Sr 89 & Sr 90 on each sample
- 6. Well Water 2 Monthly at Indicator Gross Beta, Gamma isotopic, & Tritium on Quarterly at Background each sample
- 7. Bottom 5ediment 3 Quarterly Gamma isotopic
- 8. River Water 2 Quarterly Sample - Quarterly Gross Beta, Gamma isotopse &
Indicator is Continuous Trotium Composite; Background is compasste of Six weeky Grab Samples
- 9. Fish Bullheads 8, 3 Quarterly Gamma Isotopic - Quarterly when available, Perch or other edsble fish 10 Shellfish 2 Quarterly Gamma Isotopic - Quarterly (a) Accident monitoring TLDs to be dedosed at least quarterly 24
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2.2 Samples Collected Durina Report Period The following table summarizes the number of samples of each type collected during the present reporting period:
Sample Type Number of Number of Required Samples Extra Samples Gamma Exposure (TLD) 167 96 Air Particulates 364 0 Air lodine 364 0 Dairy Milk 48 0 Goat Milk 21 0 WellWater 16 0 Fruit & Vegetables 8 0 Broad Leaf Vegetation 2 0 River Water 8 0 Bottom Sediment 12 0 Fish 24 1 Shellfish 12 0 Total AllTypes 1,046 97 i
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3.0 RADIOCHEMICAL RESULTS 3.1 Summary Table in accordance with the Radiological Effluent Monitorinc Manual (REMM),
Section F.1, a summary table of the radiochemical results aas been prepared and is presented in Table 31.
In the determination of the mean, the data was handled as recommended by Health and Safety Laboratory, Idaho: all valid data, including negative values and zeroes were used in the determination of the mean (see Part 3.2).
A more detailed analysis of the data is given in Section 4.0where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of such an approach.
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TABLE 3-1 PAGE 3-3 e ENVIRONMENTAL WADIOLOGICAt. Mot #ITopING PPOGRAM SUPT 18WY -i C0te4ECTICUT YAte(EE ATOt11C POUER COMPANT, MADDAN t8ECK PLANT +,
DOCRET 50-213 JAt4UARY - DECENDER 1987 -
- t4ALY515 Ate LOWER LIMIT
. ALL It101CATOR LOCATIOP8 WITH HIGHEST stP?JAL t'E st8 CC*4 TROL 8 OF MEDILRt OR TOTAL NLRTER OF tOCATIQ85 LOCATIOff 5 LOCATIO'f5 PSPtt PATHWAY OF AtlALYSES DETECTION ME Ate DISTANCE MEAN ME Ate (C)
SAMPLED PEPF O'MED ELtDI (A) (pattr,E tt el 4'30 OIr[CTIC'8 108tfGEttet s par:5E tt B)
MILK SD 36.12 -- -0.0 LOC # 21 0.2 0.9 e tr*IRYI 59-89 t-5.5 - 1.49 4.5 MILES NE t-0.7 - 1.45 t-I.8 - 8.59 (PCI/L3 SR-90 --
3.7 LOC 8 19 4.3 2.7 9
( 2.5 - 6.93 1.5 MILES t#EE t 2.5 - 6.93 I 1.8 - 3.63 10 DINE 36.I2 1 0.01 LOC 9 19 0.04 0.03 9 I-131 E -0.12 - 0.169 1.5 MILES teht ( -0.10 - 0.163 1 -0.04 - 0.119 GEELII 36.12 15 0.7 LOC e 19 1.0 0.6 9 CS-134 ( -1.3 - 3.19 1.5 MILES t#54 4 -0.6 - 3.11 t -1.0 - 2.09 CS-137 18 5.6 LOC 8 19 6.0 4.0 e t 0.1 - 24.19 1.5 MILES te&8 ( 2.2 - 10.99 ( !.9 - 6.39 BA-140 70 1 LOC e 19 4 2 9 i 313 1.5 MILES t#58 i 313 ( -le - til LA-140 25 0.9 LOC 8 19 2.7 1.9 8
( -3.0 - 23.03 1.5 MILES teh8 ( -1.9 - 23.03 ( -4.9 - 7.63 GOAT MILK So 12. 8 --
-0.I LOC s 23C 0.5 0.5 e (PCI/LI SR-89 t-2.4 - 0.83 16 MILES IM: t-0.4 - 1.49 t-9.4 - 1.48 SR-90 -- 6.0 LOC 8 24 6.0 4.1 0 t 2.4 - 8.38 4.5 MILES N ( 2.4 - 8.39 ( 2.3 - 6.01 1021t8E.12. 6 1 0.00 LOC e 23C 0.03 o.03 e I-131 E -0.39 - 0.169 16 MILES DR: I -0.06 - 0.28) i -0.08 - 0.283 GEtti) Its 6 15 1.2 LOC e 24 1.2 0.7 e CS-134 ( -0.5 - 3.88 4.5 MILES H I -0.5 - 3.88 ( -0.6 - 2.29 CS-137 IS 8.3 LDC 8 23C 10.9 10.9 0 t 4.9 - 13.29 16 MILES ttE E 5.2 - 19.09 8 5.2 - 19.03
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TABLE 3-1 PAGE 3-7 ,
ENV!WOPW1 ENTAL PACIOLOGICAL 810'8ITORING STOGRAtt SUPTtary cot #tECTICUT YAtsKEE ATONIC FC'JER CC?tratst. HADDAN 83ECK PLANT .
DOCKET 50-213 JANUApr - DECErfJER 1987 .
AtIALYSIS At1D LOWER LIMIT ALL IPCICATOS ___ tC{ Ayp8_WT TH HIGHEST AtFFJ AL t E Att 00'8TPOt. 8 OF NEDIUtt OR TOTAL t8 UMBER OF t(T A TI(*fS LOCATIOPs e, t0CATIOP85 MRtf PATHWAf CF AtlALYSES DETECTIOPt itE A'4 DISTAtaCE ffEAN ttCAtt (CD
_ SAffPLEO PEPF 0DetED ( Llo t ( 4 8 (PAT EttB) AtF) DIPECTIOP8 (PATEttBI s p AmE tt B)
FA-226 --
0.027 LOC 8 18 0.027 . 9 8.4 NILES NW I E 0.009 - 0.0659 i 0.009 - 0.0459 . -
. 3 TM-228 --
-0.004 LOC e 18 -0.004 . S t-0.030 - 0.0213 9.4 NILES IN t-0.030 - 0.0218 ( . - . I WIVER WATEW EE(LII 4 4 -- 7 LOC e 30C 20 20 0 IFCI/LI K-40 t 231 7.6 t1ILES IM t 1269 4 1269 798- 54 30 (HI -0.3 LOC 8 3cc 0.0 0.0 0 t -1.3 - 0.39 7.6 NILES las 6 -1.5 - 1.45 t -1.5 - 1.45 C0-58 30 (H D 0.6 LOC S 28 0.6 -0.8 9 I -0.1 - 1.49 1.8 NILES SE t -0.1 - 1.49 4 -1.7 - 0.43 CD-60 30 f H) 0.9 LOC 8 30C 1.3 1.3 9 f 0.3 - 1.85 7.6 NILES EM i 9.5 - 2.39 i 0.5 - 2.33 1-131 --
-48 LOC e 30C -15 -15 8 I-220 - 589 7.6 NILES las ( -11 ( -18
, CS-134 30 tHI 0.6 LOC 8 28 9.6 -S.I 9 f 0.0 - 1.13 1.8 NILES SE i 0.0 - 1.19 8 -l.1 - 1.83 C5-137 40 EMI 0.6 LOC 8 28 0.6 0.5 0 t 0.9 - 1.33 1.8 NILES SE E 0.0 - 1.39 f 0.2 - e.81
, BA-149 120 (H.Il -50 LOC e 30C 5 5 e t-190 - 709 7.6 NILES tot 6 333 4 339 LA-140 30 (H,Il -16 LOC 8 30C -2 -2 9 '
t-100 - 339 7.6 NILES 9N i 123 i 128 TPITItP1 4. 4 2000 573 LOC
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FOOTNOTES A. For Ge(Li) measurements the MDL's = 2.33 x LLD. For all others, MDL = 2 x background. These MDL's are based on the absence of lar interfering activity (excluding naturaly occurring radionuclides).ge amounts Deviations by of about factors of 3 to 4 can occur.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95'A probability with a 5'A probability of falsely concluding that a blank observation represents a real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD =
E
- V
- 2.22
- Y
- exp (4 A t) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide 3 si 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 a priori (before the fact) limit representincj the capability of a measurement system and not as a posteriori(after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionaly background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological EnvironmentalOperating Report.
B. Analytical results are handled as recommended by HASL ("Reporting of Analytical Results from HASL,"letter b the c:atermination of mean.y Leo B. Higginbotham). Negative values were used in i
C. Nonroutine reported measurements (NRM's). The ? are results of samples that exceed the report levels of Table E 2 of the Radiological Effluent Monitoring Manual.
3-13
FOOTNOTES (Cont'd)
D. First number is the number of indicator measurements, the second is the number of control measurements.
E. Assuming 270 m 3/ paper i F. Assuming 1080 m 3 e G. LLD for leafy vegetables. i H. Reduce LLD by a factor of two if the fractional beta for the sample exceeds 15 pCill.
- l. LLD from the end of the sample period. '
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- 3.2 Data Tables The data reported in this section are strictly counting statistics. The reported error is two times the standard deviation of the net 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, zeroes and numbers below the Minimum Detectable Level (MOL)are statistically v3 lid 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 zeroes are listed after significant digits, this is an artifact of the computer data handling program.
Data are given according to sample type as indictated below.
- 1. Gamma Exposure Rate
- 2. Air Particulates, Gross Beta Radioactivity
- 3. Air Particulates, Weekly 1 131
- 4. Air Particulates, Monthly Quantitative Gamma Spectra
- 5. Air Particulates, Quarterly Strontium
- 6. Soil'
- 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 I *None of these samples were collected, therefore there are no tables for them.
3 15
e Ctpe8ECTICUT Vasertt 1987 TABLE I Past 3-13 s.
MONTHLY gat 91A tXPOttPt FATE OUp/MRI e -
L3 CATIONS PtpIOD 1 2 3 4 5 6 7 8 9 19 IIC JaN 87 A 6.4 5 6.5 7.1 6.4 8.5 7.5 6.8 7. 3 7.1 8.5 9.5
- EB ST 5.7 6.1 7.9 6.1 7.7 7.5 6.0 7.9 7.I 8.0 9.2 MAN 87 6.7 6.6 7.3 6.5 8.7 8.1 7.1 8.1 7.1 9.2 9.2 Art 87 6.3 6.6 7.3 6.5 8.3 7.7 7.1 8.5 7.3 9.4 9.5 MAY 87 6.7 7.0 7.5 6.6 8.7 8.2 7.1 8.4 7.5 9.3 19.1 JUN 87 6.8 7.3 7.6 7.2 8.6 7.8 6.8 8.9 7.6 8.5 9.8 JUL 87 4.9 7.3 7.6 6.9 9.2 8.6 7.2 8.5 7.7 8.7 18.6 AUG 87 6.5 7.4 7.6 7.1 8.9 8.1 6.5 8.8 7.6 8.8 9.7 SEP 87 6.4 6.8 7.2 6.5 8.5 8.8 6.9 8.3 7.2 8.3 10.8 OCT 87 6.5 7.2 7.4 7.8 8.7 7.9 6.8 8.8 7.4 . C 9.6 ts:TJ 87 6.4 4.7 7.1 6.5 8.3 7.9 6.7 8.2 ,'. 3 8.4 9.8 DEC 87 6.5 6.9 7.3 6.9 8.4 7.8 6.8 8.5 7.4 8.8 9.6 PERIOD 12C 13C 16C 40X 41X 42X 43X 44X 45X 46X 47X JAN 87 6.2 6.4 8.9 7.1 6.1 10.6 7.6 7.0 9.7 7.2 7.3 FEB 87 5.9 6.4 8.0 7.6 6.0 18.2 6.9 6.5 9.9 7.1 7.6 MAR 87 6.6 6.4 8.0 7.7 6.3 11.5 t.4 7.5 19.7 7.8 7.5 Ulf87 4.6 6.5 8.4 7.6 5.4 10.3 6.2 7.5 10.3 7.6 7.5 MAY 87 6.5 6.5 8.8 7. 3 6.3 10.1 4.5 7.6 10.3 7.7 7.3 JUP8 87 7.2 6.8 8.8 7. 7 6.7 19.6 8.7 8.1 II.I 8.9 7.5 JUL 87 6.5 6.7 9.1 7.6 6.2 II.3 9.9 8.1 11.1 8.2 7.7 AUG S7 6.9 6.6 8.4 8.2 6.5 12.1 8.7 3.8 11.5 8.8 R.2 StP 87 6.4 6.8 8.5 7.4 6.4 II.S 8.4 7.4 30.8 7.8 7.7 OCT 87 7.1 6.6 8.3 7.8 6.5 9.8 8.2 7.8 10.6 8.9 7.7 tf0V 87 6.5 6.7 8.2 7.3 4.3 9.7 8.2 7.2 10.4 7.6 7.6 DEC 87 7.5 6.6 8.4 7.7 e.4 9.7 8.1 7.6 10.7 7.9 7.6 As 980T ACTUAL DATES. YlD'S APE CHAW,ED #8t AR TMt END OF TME MONTM.
8: RESULTS APE */- 19Z.
C: TLC'S WEPT #tP0rito MI55trC.
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COPMECTICUT YA*EE 1987 TABLE 7 PASE 3-34 e DATRY HILK (PCI/Lt COLLECTION LOCATION DATE SR-89 SR-90 I-131 CS-134 CS-137 BA-140 LA-140
(+/-) (+/-) (+/-) (+/-) (+/-l (+/-) (+/-)
19 01/13/87 0.5 1.4 4.4 0.3 -0.10 0.13 2.8 2.4 10.9 2.7 0 to -1.9 3.0 19 02/10/87 -0.5 1.5 4.2 0.3 0.05 0.15 1.4 2.6 7.1 2.9 0 11 -1.6 3.3 19 03/10/87 0.4 0.6 2.5 0.3 0.06 0.11 1.6 2.4 4.0 2.6 1 13 2.4 4.1 19 04/07/87 0.2 0.7 2.7 0.3 0.09 0.13 2.6 2.6 4.8 2.7 5 14 2.1 4.2 19 05/11/87 0.5 0.7 2.7 0.3 -0.05 0.18 0.4 2.5 2.2 2.6 2 13 2.0 4.1 19 06/08/87 0.5 1.1 5.3 0.3 0.11 0.15 0.2 2.4 4.1 2.6 -7 11 -1.3 3.0 19 07/06/87 0.1 0.9 4.5 0.3 0.01 0.13 -0.4 2.7 4.8 2.9 31 41 A 4.0 11.0 8 19 08/03/87 0.0 1.3 4.5 0.3 0.04 0.11 3.1 3.0 9.8 3.2 0 100 A 23.0 31.0 B 19 09/08/87 -0.6 0.9 3.1 0.3 0.10 0.15 1.2 2.6 8.6 2.9 -6 18 1.3 5.6 19 10/05/87 -0.2 1.0 5.9 0.3 0.04 0.14 -0.6 2.6 7.6 2.9 10 20 -0.2 6.2 19 11/09/87 0.2 1.0 6.9 0.4 0.16 0.30 -0.4 2.6 4.0 2.8 10 30 2.7 9.1 19 12/07/87 -5.5 4.7 5.2 0.6 -0.04 0.15 0.1 2.5 3.9 2.7 7 17 0.0 4.7 20 01/13/87 -0.2 1.0 2.7 0.3 -0.07 0.12 1.6 2.3 8.2 2.6 5 11 1.8 3.4 20 02/10/87 -0.9 0.9 5.4 0.3 -0.11 0.I6 2.4 2.5 24.1 3.2 -5 12 -0.9 3.6 20 03/10/87 0.0 0.7 2.9 0.2 -0.01 0.11 0.3 2.5 2.6 2.8 -8 14 - -0.3 4.2 20 04/07/87 -0.2 0.7 3.3 0.3 0.07 0.13 1.4 2.4 6.0 2.6 14 13 -3.0 3.9 20 05/11/87 -0.0 0.6 2.6 0.3 -0.02 0.17 0.9 2.3 5.1 2.7 6 11 -1.7 3.6 20 06/08/87 0.6 1.4 3.0 0.5 0.06 0.13 0.2 2.5 5.0 2.7 -5 13 0.4 4.1 20 07/06/87 0.6 1.0 3.4 0.3 0.01 0.12 0.3 2.6 4.9 2.8 -20 43 A 8.0 13.0 8 20 08/03/87 0.5 0.8 3.3 0.3 -0.02 0.13 0.6 2.1 1.3 2.2 -22 87 A 2.0 26.0 8 20 09/09/87 0.4 0.8 2.7 0.3 0.05 c.17 0.2 2.5 4.1 2.8 13 17 -1.9 5.1 20 10/05/87 0.4 0.5 2.5 0.3 -0.01 0.14 0.5 2.5 5.6 2.8 -11 21 -2.7 6.1 20 11/09/87 0.3 1.2 3.6 0.4 -0.02 0.25 -1.3 2.3 0.1 2.6 -11 27 4.0 8.1 20 12/07/87 -1.0 1.1 3.5 0.4 -0.05 0.15 -0.3 2.6 2.3 2.8 -10 17 -0.4 4.8 21 01/13/87 0.4 1.0 4.7 0.3 -0.08 0.17 1.6 2.2 6.1 2.5 -2 9- -1.4 2.5 21 02/10/87 1.4 1.3 5.2 0.4 -0.01 0.15 -0.3 2.4 7.0 2.7 4 10 -2.I 3.0 21 03/10/S7 0.6 0.8 2.5 0.3 0.06 0.11 -0.2 2.5 0.7 2.7 4 13 0.0 4.2 21 04/07/87 0.2 0.6 2.6 0.3 0.03 0.13 1.5 2.3 1.4 2.6 -4 17 -2.9 4.9 -
21 05/11/87 -0.4 0.7 4.1 0.3 -0.02 0.19 1.9 2.4 8.3 2.7 2 12 -1.7 3.8 21 06/08/87 0.3 0.8 2.9 0.3 0.00 0.14 1.2 2.3 4.6 2.7 4 10 0.3 3.0 21 07/06/87 0.8 1.1 4.0 0.3 0.10 0.14 0.7 2.5 9.4 2.9 -12 31 A -0.7 8.9 21 08/03/87 0.2 0.8 3.0 0.3 0.02 0.10 1.4 2.4 4.1 2.6 9 21 -2 1 6.4 21 09/08/87 0.3 0.6 3.0 0.3 0.06 0.11 -0.2 2.5 3.5 2.6 0 17 -0.6 4.7 21 10/05/87 0.2 0.9 2.9 0.3 0.03 0.13 -1.1 2.5 5.7 2.7 2 19 3.1 5.7 21 11/09/87 -0.3 1.1 3.8 0.4 -0.12 0.27 1.8 2.6 4.5 2.8 19 33 C 2.4 8.9 21 12/07/87 -0.7 1.3 2.9 0.4 0.02 0.13 -0.9 2.5 4.7 2.8 -6 11 0.4 3.4 A: 84-140 FOL OF 30 NAS NOT MET DUE TO EQUIPMENT BREAKDOWN DELAYItG COUtiT.
B: LA-140 POL OF 10 WAS #30T MET DUE (O EQUIITTEt3T BREAFDCuti DELAYItG CCUtiT.
C: 84-140 MDL OF 30 NAS tiOT NET DUE TO A DELAY IN SAMPLE COTITIttG.
CONNECTICUT YANKEE 1987 TABLE 7 FAGE 3
=- . ... --
- _ = . -
(+/-) (+/-l (+/-l 1+/-) (+/-) (+/-) (+/-)
22C 01/13/87 0.3 0.9 2.9 0.3 0.08 0.20 2.0 2.3 4.9 2.5 0 9 -2.4 2.8 22C 02/10/87 0.4 0.6 3.0 0.2 0.01 0.31 1.2 2.6 3.6 2.8 -10 10 0.4 3.0 22C 03/10/87 0.3 0.8 2.6 0.3 -0.04 0.10 0.5 2.5 5.0 2.6 10 13 0.2 3.6 220 04/07/87 0.5 0.8 3.6 0.3 0.04 0.12 1.7 2.5 5.7 2.8 11 18 -4.9 5.6 22C 05/11/87 0.2 0.6 3.1 0.3 -0.04 0.17 1.3 2.3 6.3 2.6 -7 13 0.6 3.8 22C 06/08/87 -0.4 0.8 3.5 0.3 0.11 0.13 1.8 3.7 2.9 4.0 7 16 - 1.9 4.5 22C 07/06/87 -1.8 1.8 2.5 0.3 -0.02 0.13 0.4 2.6 3.9 2.8 -10 32 A 7.6 9.9 22C 08/03/87 -0.4 1.2 1.8 0.2 0.11 0.14 -1.0 3.1 4.3 3.2 2 35 A 2.3 10.2 8 22C 09/08/87 0.5 0.7 1.9 0.3 -0.02 0.10 -1.0 2.5 4.4 2.7 5 15 -1.3 4.4 22C 10/05/87 0.4 0.8 2.5 0.2 -0.04 0.13 0.8 2.5 1.9 2.7 2 19 2.5 5.5 22C 11/09/87 -0.1 1.0 3.0 0.3 0.07 0.23 0.1 2.5 2.6 2.8 0 28 1.3 8.7 20C 12/07/87 -0.1 1.7 2.5 0.3 0.09 0.12 -0.5 2.5 2.9 2.6 11 16 3.5 4.7 A: BA-140 PSL OF 30 NAS NOT MET DUE TO EQUIPMENT BREAKD0644 DELAYING COUNT.
Q: LA-140 MOL OF 10 WAS tot MET DUE TO Er2UIPMENT BREAKDOLH DELAYItG COUNT.
C: BA-140 MDL OF 30 WAS HOT MET DUE TO A DELAY IN SAMPLE COUNTING.
^
C0t#4ECTICUT YAtaCEE 1987 TABLE 8 PAGE 3-36 e-GOAT'S MILK IPCI/LI COLLECTION LOCATION DATE SR-89 SR-90 I-131 CS-134 CS-137 BA-140 LA-140
= -
------------- =
(+/-l t+/-l t+/-) (+/-l t+/-l (+/-) (+/-)
23C 04/07/87 A 0.9 1.0 4.7 0.4 0.28 0.15 -0.6 3.5 11.0 4.0 -4 16 -4.1 5.0 23C 05/11/87 0.7 0.8 6.0 0.3 0.01 0.10 1.5 2.4 19.0 3.2 -0 10 3.5 3.0 23C 06/08/87 0.3 0.9 4.4 0.3 0.00 0.15 -0.5 2.5 12.2 3.1 1 9 -0.4 2.8 23C 07/06/87 0.6 2.2 2.5 0.3 -0.08 0.16 2.2 3.3 14.3 3.7 -28 55 B -11.0 '17.0 C 23C 08/03/87 0.4 0.9 2.3 0.9 -0.03 0.14 0.9 3.0 9.3 3.5 24 33 D 7.7 9.5 23C 09/08/87 -0.4 1.1 3.1 0.3 0.02 0.20 1.9 3.2 7.1 3.6 -6 14 5.0 4.6 23C 10/05/87 1.4 1.9 3.8 0.3 0.01 0.13 -0.2 2.6 9.0 3.0 -8 17 3.7 4.9 23C 11/09/87 A 0.5 2.5 6.0 0.3 0.00 0.41 F 0.2 2.7 5.2 3.0 2 10 -1.0 3.1 24 01/13/87 0.8 1.1 7.3 0.7 -0.39 0.48 D 0.5 2.9 10.0 3.3 -3 15 -1.1 4.4 24 02/13/87 -1.0 1.0 8.1 0.4 0.03 0.11 -0.3 2.9 8.5 3.3 1 14 -1.6 4.3 24 03/12/87 0.8 1.0 5.8 0.3 0.11 0.17 2.7 2.7 9.5 3.0 2 11 -4.5 3.1 24 04/07/87 0.5 0.8 7.3 0.4 0.07 0.12 2.3 2.7 5.6 3.1 -3 13 0.5 3.9 24 05/11/87 -0.5 0.9 8.3 0.4 -0.02 0.21 0.7 2.5 7.7 3.0 6 to 0.4 2.6 24 06/08/87 0.2 0.9 5.6 0.3 0.04 0.14 2.4 3.1 12.2 3.5 15 19 -2.6 5.4 24 07/06/87 0.5 1.0 4.6 0.3 0.10 0.14 3.8 3.0 9.6 3.3 43 49 5 -9.0 11.0 C 24 08/03/87 0.5 0.8 2.4 0.2 0.05 0.10 E 0.3 3.0 6.8 3.4 -21 36 B 7.0 11.0 C 24 09/08/87 0.4 1.6 6.1 0.5 -3.07 0.16 0.1 2.6 4.9 2.8 9 12 1.4 3.4 24 10/05/87 0.5 1.0 4.3 0.3 0.03 0.16 -0.4 2.6 5.6 2.9 -1 17 -4.5 5.0 24 11/09/87 -2.4 2.6 G 5.5 0.4 G 0.16 0.33 -0.5 3.0 13.2 3.6 -3 11 0.1 3.2 24 12/07/87 -1.1 1.4 6.6 0.4 -0.06 0.13 2.5 2.6 5.7 2.9 2 9 1.6 2.8 A: t;!ITHER MILK ts0R PASTURE GRASS WERE AVAILABLE DURItG JAts., FEB..NAR. OR DEC. AT LOC.123C).
8: BA-140 t1DL OF 30 WAS NOT NET DUE TO EQUIFTtENT BREAK 005@3 DELAYItG COUlfT.
C: LA-140 MDL OF 10 WAS NOT NET DUE TO EQUIFMENT EREAK00Wri DELAYItG COUttT.
$ D: CHEMISTRY 100It1E PECOVERY MAS VERY L0tt CAUSItG HIGH EPROR.
E: SAMPLE WAS RESAMPLED FOR I-131 ON 08/24/87 DUE TO THE LOSS OF THE ORIGINAL IN CHEMISTRY.
F: l'-131 t1DL OF 0.4 COULD HOT BE NET DUE TO SAMPLE COUNTED LATE WITH INSUFFICIENT COUtif TIME.
G: CHEMISTRY YIELD OF STRotITIUM IS QUESTI0tta8LE, SAMPLE UMDER REAHALYSIS.
u CONNECTICUT TANKEE 1987 TABLE 10 PAGE 3-37 '8'
^
WELL MATER (PCI/LI COLLECTION ., ,
i LOCATION DATE K-40 CR-51 MN-54 CO-58 FE CO-60 ZN-65
(+/-l (+/-) (+/-) (+/-I (+/-) (+/ h (+/h
, 15 01/12/87 A 71 41 -2 19 1.5 2.1 -1.6 2.2 2.9 5.2 0.6 2.5 0.2 5.1 15 02/11/87 8 310 55 1 24 0.5 2.8 -2.2 2.8 3.9 6.5 0.7 3.0 -2.4 6.2 15 03/06/87 92 47 -9 27 -0.8 2.7 -1.0 2.9 -1.4 6.9 1.0 2.9 -1.1 6.3 15 04/10/87 24 50 -5 25 2.1 2.4 2.2 2.6 3.5 6.6 -0.9 2.6 -0.3 5.4 15 05/11/87 16 40 -14 24 1.2 2.1 2.0 2.4 2.0 6.0 1.1 2.4 -2.7 4.8 15 06/11/87 23 53 -14 24 2.8 2.4 0.6 2.5 4.8 6.5 -1.2 2.6 0.1 5.2 15 07/13/87 -45 51 -20 32 -0.9 2.5 -0.5 2.8 0.3 7.4 1.8 2.6 2.7 5.5 f 15 08/07/87 -9 54 -19 31 0.6 2.5 0.9 2.5 -0.8 7.5 -0.2 2.6 0.2 5.6 4 15 09/10/87 -32 53 -16 27 0.2 2.4 -1.1 2.6 -0.1 2.8 0.4 2.7 5.8 5.7
, 15 10/08/87 -8 54 -16 23 -0.7 2.3 1.5 2.5 -0.1 6.5 0.6 2.7 0.9 5.6 l
15 11/10/87 -29 52 -7 25 -0.6 2.3 0.6 2.6 -3.9 6.6 1.4 2.6 2.6 5.5 15 12/03/87 -35 51 4 28 -2.0 2.3 -1.6 2.5 3.6 7.1 1.3 2.7 2.2 5.5
]
16C 03/06/E 7 148 54 -12 22 0.7 2.4 0.0 2.4 0.5 6.1 -1.1 2.7 0.7 5.8 16C 06/11/87 79 55 -4 27 0.0 2.5 -1.1 2.6 -3.9 6.8 1.1 2.8 -5.1 5.8 16C 09/10/87 -48 52 10 26 -0.3 2.3 0.2 2.6 -1.2 6.6 -0.3 2.6 -3.4- 5.5 16C 12/03/87 -26 53 -15 28 -1.8 2.4 0.6 2.8 -1.3 7.3 0.0 2.7 -2.6 5.7 1
i l
4 4'
A: sat 1PLE OF NEW ONSITE WELLS.
S: sat 1FLE OF OLO ONSITE WELLS. DISCONTINUED LEE OF NEW a4 ELLS DUE TO HIGH NINERAL CONTENT.
C BA-140 t1DL OF 2S WAS PIOT t1ET DUE TO EQUIPt1ENT EptAKDCt#8 DELAYItG COU*IT.
D: LA-140 #1DL OF 6 WAS NOT P1ET DUE TO EQU10t1ENT EREuDOW?4 DELAYING COU:IT.
l
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COPE 4ECTICUT YAte(EE 1987 TABLE 10 PAGE 3-38 WELL WATER IPCI/LI COLLECTION
(+/-l (+/-) (+/-l (*/-l (+/-) (+/-) (+/-I 15 01/12/87 A -0.3 3.8 5.4 2.4 -0.2 2.2 -1 20 0 3 -0.3 2.2 0.0 2.4 15 02/11/87 8 -1.1 4.7 1.4 2.7 -0.8 2.6 5 24 1 3 0.7 2.8 1.9 3.0 15 03/06/87 -0.7 4.8 -1.7 3.4 -1.2 2.8 -10 23 -4 5 0.6 2.6 -1.9 3.C 15 04/10/87 -1.0 4.5 2.9 3.0 0.3 2.8 13 22 3 7 1.3 2.4 1.1 2.4 15 05/11/87 -0.8 4.2 -0.3 2.7 0.5 2.6 -4 20 -1 8 0.3 2.2 1.3 2.3
- 15 06/11/87 -3.1 4.5 -0.6 2.8 1.2 2.7 5 21 -1 6 0.0 2.4 1.9 2.5 15 07/13/87 -2.9 5.0 -0.6 3.5 -1.5 3.1 -2 22 -8 17 -0.1 2.3 1.0 2.4 15 08/07/87 -1.7 4.9 1.0 3.5 -1.9 3.2 5 22 -6 13 -I.4 2.4 1.2 2.6 15 09/10/87 1.9 4.9 -0.5 3.2 -1.1 2.9 -5 22 7 9 -0.4 2.4 0.0 2.4 15 10/08/87 2.0 4.5 -2.7 2.9 -1.9 2.6 16 22 4 5 1,1 2.4 -0.3 2.6 15 11/10/67 -1.5 4.6 0.6 2.9 0.2 2.7 -10 21 7 7 1.4 2.3 0.1 2.4 15 12/03/87 -1.9 4.7 3.4 3.2 -1.4 2.9 0 20 -3 to 0.4 2.3 0.0 2.4 16C 03/06/87 2.0 4.3 1.5 2.7 -a.2 2.6 15 21 -2 4 0.5 2.5 -0.2 2.5 16C 06/11/87 3.8 4.8 2.1 3.1 0.0 2.9 -3 22 0 8 2.0 E.5 -1.6 2.6 16C 09/10/87 1.9 4.7 0.3 3.0 -0.6 2.8 0 22 5 8 0.9 2.4 -0.9 2.5 16C 12/03/87 0.0 4.8 2.0 3.3 -1.5 3.1 -18 22 -3 11 -0.4 2.5 -0.9 2.6 l
i A: SAttPLE OF NEW OttSITE WELLS.
8: S&ttPLE OF CLD CtISITE WELLS. DISC 0tiTIPIUED USE OF HEW WELLS DUE TO HIGH NItiERAL C0tITENT.
C: BA-140 t1DL OF 25 WAS TOT ttET DUE TO EQUIFt1ENT BREAKOOWt3 UELAYItn COU'8T.
k D: LA-140 t1DL OF 6 WAS TOT ffET DUE TO EQUIrrtENT BREAKD0t24 DELAVIt#G CO'JtIT.
o
'6 CONNECTICUT TANKCE 1987 TABLE 10 PAGE 3-39 '*
WELL WATER (PCI/L3 COLLECTIDM LOCATION DATE 8A-140 LA-140 BI-214 TH-228 'H-3 GROSS BETA
(+/~5 t+/-l (+/-l f+/-l (+/-l t+/-l 15 01/12/87 A -4 9 2.2 3.0 115.3 7.5 1.3 6.4 6 84 1.05 0.23 15 02/11/87 8 -3 10 2.9 3.4 269.0 11.0 -3.2 8.3 1800 100 1.19 0.22 15 03/06/87 1 14 0.1 4.7 296.0 11.0 3.4 7.9 2700 100 4.48 0.67 15 04/10/87 4 17 1.2 5.5 7.4 5.3 -1.1 6.8 2800 200 1.41 0.24 15 05/11/87 8 18 3.3 5.8 -0.1 4.5 4.0 6.3 4400 100 1.63 0.42 15 06/11/87 -15 15 -4.6 5.0 12.9 5.3 -3.6 6.9 2300 100 1.54 0.55 15 07/13/87 -8 29 C 1.4 8.70 4.9 5.0 -7.7 6.6 7000 600 0.49 0.32 15 08/07/87 -5 26 C 2.6 7.9 D 3.2 5.1 17.6 7.2 7600 300 1.84 0.26 15 09/10/87 11 20 -0.2 6.6 0 0.8 5.1 -0.2 6.9 8700 200 1.31 0.44 15 10/08/87 -9 15 -2.1 4.6 27.7 5.7 10.2 6.9 7000 100 1.57 0.24 15 11/10/87 7 17 0.4 5.3 15.3 5.4 3.1 6.7 3310 73 2.14 0.52 15 12/03/87 18 21 3.9 6.6 10.1 5.2 -0.8 6.8 2000 200 1.60 0.50 16C 03/06/87 4 12 -0.7 3.9 32.9 6.2 -3.4 6.8 120 60 1.33 0.51 16C C6/II/87 -3 IS -0.2 5.7 66.3 6.8 -0.7 7.1 ISO 90 9.e6 0.72 16C 09/10/87 -6 18 3.7 5.8 15.7 5.3 6.8 6.7 130 90 1.87 0.56 16C 12/03/87 11 23 -4.7 6.8 18.9 5.6 7.2 6.9 450 110 4.06 0.62 A: SAFTPLE OF NEW Ot451TE WELLS.
B: SAttPLE OF OLD OriSITE WELLS. DISCCtITIHUED USE OF NEW WCtt_S DUE TO HIGH NINERAL cot 4 TENT.
C: BA-140 t1DL OF 25 WAS t10T NET DUE TO EQUIITtEffT BREAKDOW3 DELATItG COUtiT.
$ 0: LA-140 t1DL OF 6 WAS t10T ttET DUE TO EQUIrrtEt!T CPEAFDOM4 DELAYIts CettlT.
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WIVER WATER trCI/LI COLLECTION LOCATION DATE K-40 CR-51 NH-54 CO-58 FE-59 CO-60
(+/-) (+/-3 (+/-l (+/-) (+/-p (+/-)
28 02/11/87 17 41 -8 47 0.3 2.3 0.2 3.1 -4.0 9.8 1.3 2.4 28 05/18/87 4 52 -56 85 -0.2 2.6 1.4 4.0 4.0 14.0 0.3 2.7 i 28 08/12/87 23 53 -9 58 -0.2 2.5 1.0 3.6 -2.0 11.0 0.3 2.7 28 11/16/87 -16 53 -45 e6 -1.3 2.6 -0.1 3.9 -5.0 13.0 1.8 2.8 30C 01/30/87 126 53 3 32 0.3 2.4 -0.5 2.7 -3.8 7.5 0.5 2.7
! 30C 04/25/87 -10 39 0 26 1.4 2.2 0.4 2.4 0.9 6.6 0.5 2.4 1 30C 07/24e 87 - 34 53 -5 46 -1.5 2.5 -1.7 3.2 -0.9 9.9 1.9 2.7 30C 10/23/87 -4 53 -25 37 0.0 2.5 -1.4 2.9 1.3 8.0 2.3 2.5 COLLECTION LOCATION DATE 2N-65 2R-95 NB-95 RU-103 RU-106 I-131
(+/-) (+/-l (+/-) (+/-l (+/-) (+/-I 28 02/13/87 -2.9 5.6 1.3 5.7 0.6 4.7 1.4 4.3 9 22 58 82 28 05/18/87 -8.3 6.3 -2.8 7.6 8.7 8.0 -2.3 6.5 -6 23 -60 530 28 06/12/87 0.5 6.1 0.3 6.6 -0.5 5.9 -2.3 5.1 1 23 50 140 28 !!/16/87 2.2 6.2 -1,2 7.6 -5.3 7.8 1.7 6.5 -10 24 -220 4 70 30C 01/30/87 -0.7 5.7 3.3 5.0 3.6 3.5 -2.2 3.2 11 21 -4 17 3CC 04/25/87 3.0 5.0 0.0 4.3 -1.2 2.9 0.1 2.8 -11 20 -1 10 30C 07/24/87 3.3 6.2 0.9 5.9 2.6 4.6 -2.4 4.3 -8 23 -53 61 30C 10/23/87 1.0 5.5 -0.2 5.4 4.3 4.0 -1.6 3.5 -2 22 -1 26
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C0petECTICUT VANNEE 1987 TABLE 14 PAGE 3 ' **
RIVER WATER (FCI/LI COLLECTIOpt LOCATIOps DATE C5-134 CS-137 84-140 LA-140 PA-226- TM-228
(+/-) (+/-l t+/-3 (+/-l to/-l to/-l 28 02/13/87 0.7 2.2 1.3 2.3 0 76 3 25 0.1 4.7 8.7 6.4 -
28 05/18/87 0.7 2.4 0.6 2.5 -190 250 -100 77 2.3 5.0 -2.1 6.9 28 08/12/87 1.1 2.4 0.0 2.5 -80 110 -1 36 -0.8 5.0 1.6 7.0 28 11/16/87 0.0 2.4 0.6 2.5 70 250 33 81 -1.8 5.0 7.1 7.3 30C 01/30/87 1.8 2.4 0.8 2.4 1 29 -15 9 -7.1 4.9 -6.6 6.8 30C 04/25/87 -0.5 2.1 0.6 2.3 3 21 7 7 -1.1 4.6 -0.4 6.2 30C 07/24/87 -0.4 2.5 0.2 2.5 33 66 12 22 -2.1 5.0 9.5 7.3 30C 10/23/87 -1.1 2.4 0.5 2.4 -18 39 -12 12 1.9 5.1 6.6 6.8 COLLECTIO>t LOCATION DATE H-3 DETA
(+/-l (+/-l 28 02/13/87 370 90 2.69 0.58 28 05/18/87 730 100 2.12 0.52 28 G8/12/87 630 90 2.44 0.26 28 11/16/G7 560 90 2.35 0.50 30C 01/30/87 120 70 0.58 0.36 3CC 04/25/87 230 140 2.39 0.43 30C 07/24/87 220 60 2.43 0.34 30C 10/23/87 440 110 2.12 0.50 i
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4.0 DISCUSSION OF RESULTS This section summarizes the results of the analyses of environmental media sampled. Northeast Utilities has carefully examined the data throughout the year and has presented in this section all cases where plant related radioactivhy could be detected and compared the results with previous environmental surveillance data. Few impacts of the plant operation on the environment were observed. Sub-sections contained describe each particular media or potential exposure pathway.
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 predominantly in airborne and ve.getation samples. Ra-226 and Th-228 results were 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 detectable levels of Cs-137 and Sr-90 were the result of atmospheric nuclear weapons testing of years past.
Gamma Exposure 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 is 0.4 uR/hr to 1.7 uR/hr,with a mean of approximately 1 uR/hr.
The data for 1987 exhibits the same trends as that of previous years; gamma exposure rates did not differ significantly for the off-site inner and outer ring locations. The on site locations at the boron waste storage tank (location 42X) and the waste gas surge sphere (location 45X) were the only locations showing any plant effects, increases up to 2 uR/hr due to direct radiation from the plant are observed. These locations are within the plant's restricted area and, as such, are away from areas where members of the general public are usually allowed.
Dosimeters located at areas which are accessible to the public, such as the picnic area (location 41X) and the mouth of the discharge canal (location 01), did not indicate any increase in exposure rate due to the plant.
Air Particulates and lodine (Table 2,3,4 A L and S) l Air is continuously sampled at six inner ring and one outer ring location by passing i it through glass fiber particulate filters. These are collected weekly and analyzed for gross beta radioactivity. Results are shown on Figure 4 7 and Table 2.
Gross beta activity remained at levels similar to that seen over the last five years.
inner and outer ring monitoring locations showed no significant variation in
! measured activities. This indicates that any plant contribution is not measurable.
Charcoal cartridges are included at all of the air particulate locations for the collection of iodine. This year the data failed to show the numerous positive values seen at both indicator and controllocations attributable to Ra 226 interference on a Nal detector. Starting in 1987, all air iodine cartridges were analyzed on a GeLi i detector. The resolving capability of the Geli detector allows for the separation of l
the I 131 c amma peak at 365 kev from the Ra-226 daughter gamma peak at 352 kev, whic, when measured on a Nal detector appears as a single peak. No detectable levels of I-131 were seen in the 1987 charcoal samples. This is confirmed by the absence of I-131 in any of the milk samples. Milk from cows and 41
gcats is a much mere sensitive indicator cf I-131 presence in the environment.
The weekly air particulate filters are composited monthly for gamma spectral analyses. The results, as shown in Tables 4A-41., indicate the presence of naturally occurring Be 7, which is produced by cosmic processes. Positive results seen in other months are attributable to statistical fluctuations in counting. These analyses indicate the lack of plant effects.
For the measurement of Sr-89 and Sr-90, the air particulate filters are composited quarterly and analyzed by radiochemical separation and appropriate counting
' techniques. The results presented in Table 5 are much more sensitive indicators of environmental radioactivity than gamma spectrum analyses, because of the larger sample volume as a result of compositing and the higher efficiency of beta counting. The Sr-90 results show the same trend as the gross beta analyses. Levels continued to remain at the fairly constant low values as observed in 1982-1985.
There was no detectable Sr 89 in any of these samples. Since there was no difference in measured levels of Sr 90 between indicator and control locations and no measurable Sr-89, there are no indications of any plant effects.
Soil (Table 6)
Sail samples are special samples not required by the Radiological F' fluent Monitoring Manual (REMM). Previous data has shown the lack of duectable 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.
Cow Milk (Table 7)
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 consum ation of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint. This pathway a'so shows significant amounts of nuclear weapons testing fal!out. Therefore this media needs to be evaluated very carefully when trying to determine if there ar! any plant effects.
Sr-90 was observed in all samples; all results were below 6 p;i/1. Detailed analysis of previous data has concluded that these levels of Sr-90 are from weapons testmg and are not plant related (see Section 6.0 for details to this argument). Sr-89 was not detectec in any of the samples above its MDL. This isotope is usually released from the plant in quantities equal to or greater than those of Sr-90, indicating that Sr 90 is the result of weapons testing 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 1987 are similar to those of the past nine years. Throughout the year, the indicator locations showed Cs-137 activity above the control location. This trend has been observed in past data. However, detailed analysis has concluded that these 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 7, the only other nuclide detected by gamma spectrometry was natually occurring K-40.
All samples showed a lack of I 131 detectable above the MDL of 0.5 pCi/l. These 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 Chernobyl.
42 0
r4 e e Goat Milk (Table 8)
Depending on the feeding habits, goat milk can be a more sensitive indicator than cow 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 of nuclear weapons testing fallout.
Sr-90 and Cs-137 were observed in all samples, with values similar at both locations.
In previous years (1977 - 1983) the control location had significantly higher values than 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 is caused in the by many uptake factors, of fallout including levels feeding among(various habits amount of stored farms. This variability feed, etc.),
soil characteristics, farming practices (tillage and c uality of fertilization and land management), and feed type. For a complete ciscussion of the problem see Section 6.0. As typical of periods lacking fresh fallout, no detectable Sr 89 was seen in these 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.
No plant related 1-131 was seen in this media. No detectable levels of I 131 have been seen in goat milk samples except for periods immediately following fallout from nuclear testing and Chernobyl.
Pasture Grass (Table 9)
When the routine milk samples are unavailable, samples of pasture grass are required as a replacement. These samples may also be taken to further investigate the levels of radioactivity in milk. In the spring, January- March, these samples were not available as a replacement at goat location #1. Pasture grass was again unavailable in December at this location. In samples of past years, no plant effects were seen in this media.
Well Water (Table 10)
Activity in this media results from either soluble plant effluents permeating through the ground or the !eaching of naturally occurring nuclides from the soil and rock. H-3 and Gross Beta were detected in these samples, at levels similar to previous years. Nb 95 was also seen in a few samples, but was observed in both mdicator and control locations. These are probably due to counting statistics and therefore are not real.
Bi 214 is a daughter aroduct of naturally occurring Ra-226. In well water supplies it may not necessarily le in equilibrium with its long lived precursor. Therefore it is not indicative of the Ra-226 concentrations. This effect has been discussed in previous reports. As usual the on-site wells (location 15) exhibited plant related H-3 significantly above 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. Starting in February, a noticeable increase in H-3 levels is apparent due to the resampling of the old onsite wells. This increase is caused by the old wells oeing on the plant side of a hydrologic barrier. In any case, this pathway does not result in any dose consequence since the water from these wells is used only in process streams at the station. Off-site concentrations are much lower than the February - December values (see River Water). The old wells exhibit typical levels of H-3 measured at the plant in the past.
Also consistent with previous years, some gross bete values for the control location at the State Highway Department (location 16C) wre higher than the values for 4-3
the indicator location. This activity is due to the leaching of naturally occurring nuclides. Variations can be caused by different flow patterns of the ground water, variable permeability of the different soil and rock formations, and the usage pattern of the wells. Therefore, the results of this type of analysis are not very indicative of plant effects.
Reservoir Water (Table 17)
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 would be collected.
Fruits and Vegetables (Table 72)
Similar to past years, this media did not show any plant effects. Concentrations of Sr-90 and C5-137 in these samples existed at leveh comparable to past years and is due to fallout. Naturally occurring K-40 was detected in all samples. Since there was no fresh fallout, no other nuclides were detected, Broad Leaf Vegetation (Table f f, Concentrations of Sr-90 and Cs-137 in these samples existed at levels comparable to past years and is due to fallout.
River Water (Table 14)
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 quarter are composited at the control station (Middletown -
location 30C). Continuous samples are utilized at the indicator station (East Haddam Bridge -location 28).
The indicator location showed tritium (H 3) concenrations above the background levels seen at the control location. These elevated levels are attributable to plant operation. They show the effect of plant releases being diluted by the Connecticut River. 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 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 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 results of these analyses indicated that the effluent calculations are conservative. The dose consequences, discussed in Section 5.0, are insignificant.
Gross beta was the only other activity that was consistently seen in these samples.
The gross beta activities are similar to past data. These results are a gross type measurement and are, therefore, not very indicative of plant effects; they are masked by background activities.
Bottom Sediment (Table 15)
Plant related levels of Co 60, similar to those occurring over the past years, were
' observed at one indicator location (Area of Plant Discharge location 29). Cs-137 l
l 4-4
levels remained near those of past years, somewhat higher at both indicator locations, showing a barely discernable plant effect. The Cs 137 levels at the control location are due to fallout activity.
Shellfish (Table 76)
Cs-137 levels remain near those of past years at all locations. Plant related Co-60 and possibly Co-58 was detected in one shellfish sample taken from the Mouth of the Salmon River (location #31). Shellfish from this area is rarely, if ever, consumed. However,if one would consume shellfish with these levels, the dose consequence would be a factor of 25 times less than the maximum individual fish consumption doses shown in Section 5.0.
Fish Bullheads (Table 17A)
As noted in previous years, the levels of Cs 137 are somewhat higher in samples taken from the indicator locations. Even though Cs 134 was not observed, a portion of the Cs-137 in these samples could be due to plant operation. To be conservative, dose consequences were calculated assuming these concentrations resulted from plant effluents. The results of the calculations are shown in Section 5.0.
Fish Perch and other Types (Table 178)
These fish samples exhibit tne same results as the bullhead samples. Cs 137 was detectable at higher levels in samples from the indicator locations. These elevated levels may be plant related and as sur.h, the dose consequence, though very minimal, is discussed in Section 5.0.
I I
45
\
i FIGURE 4-1 -
COMPARATIVE MONTHLY VALUES OF .
AIR PARTICULATE GROSS BETA RADI0 ACTIVITY 1987 0.030-0.029-lq 0.028- , \
/ \
0.027- \
/
0.026- / \
, 0.025-C 0. 024 - \
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! I I i ' 1 JAN FEB MAR RPR MRY JdN JUL AUG SEP GCT NOV DEC 1987 1 = INNER STATIONS 0 = OUTER STATIONS THE ERROR IN THESE VALUES IS RPPROXIMATELY 0.004
5.0 OFFSITE DOSE EQUIVALENT COMMITMENTS The off site dose consequences (dose equivalent commitments) of the station's radioactive liquid and airborne effluents have been evaluated using two methods.
The first method utilizes the station's measured radioactive discharges as input parameters to conservative models that simulate the transport mechanism through the environment to man. This results in the computation of the maximum doses to individuals and the 0 to 50 mile population dose. The results of these computations have been submitted to the NRC in the Annua / Radioactive Effluents Dose Report written in accordance with the Radiological Effluent Monitoring Manual, Section F.2. The.second method utilizes the actual results of the concentrations of radioactivity in,various environmental media (e.g., milk, fish) and then computes the dose consequences from the consumption of these foods.
The first method, which is usually conservative (i.e., computes higher doses than that which actually occur), has the advantage of approximating an upper limit to the dose consequences. This is important in those cases where the actual dose cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques. The results of both methods are compared in Table 5.1. For gaseous releases, no plant related detectable activity was observed in any sampling media. The less-than values given for the second method are the doses which would be calculated if the annual 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 (caught in the discharge canal), shellfish, bottom sediment 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 alant effluents for that pathway and for the critical age group. For example, the c ose via the fish pathway is calculated for fish caught in the discharge canal and the external gamma dose is calculated at the site boundary which has the least meteorological dispersion. The calculations result in maximum total doses to an individual of: 1.5 mrem whole body to an adult, 0.14 mrem to a r child's thyroid, and 1.25 mrem to an adult's liver. The calculated doses for all other locations and other age groups will be less than those shown on Table 5.1.
j 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 for the period January December 1987 for the average individual:
ANNUAL AVERAGE WHOLE BODY DOSE :
DUE TO AIRBORNE EFFLUENTS = 0.00011 mrem DUE TO LIQUID EFFLUENTS = 0.00015 mrem 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 order to provide perspective on the doses in Table 5.1, the standards for 1987 on the allowable maximum dose to an individual of the general public are given in 40CFR190 as 25 mrem whole body,75 mrem thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation of 270 mrem per year and are designed to be inconsequential in regard to public health and safet . Since plant related doses are even a smaller fraction of natural background, the have insignificant public health consequences. In fact, the plant l related doses to the maximum individual are less than 10% of the variation in natural background in Connecticut.
i 51
TABLE 5.1 _
COMPARISON OF DOSE CALCULATION METHODS HADDAM NECK STATION JANUARY-DECEMBER 1987 ANNUAL DOSE (MILLIREM)
PATHWAY ORGAN METHOD 10) METHOD 20)
AIRBORNE EFFLUENTS Max. ind. (2)- Whole Body 0.66 ND(3)
- 1. External Gamma Dose Inhalation M 3x. Ind. - Thyroid 0.059 NAD (4), < 0.6
- 2. a.
- b. Vegetables Max. Ind. -Thyroid 0.073 NAD Goat's Milk Max. Ind. - Thyroid 0.004 NAD, < 1.8 c.
LIQUID EFFLUENTS
- 1. Fish Max. Ind. - Whole Body 0.86 0.059 Max. Ind. - Liver (5) 1.25 0.087 (1) Method 7 uses measured station discharges and meteorological data as input parameters to conservative transport to man models. Method 2 uses actual measured concentrations in environmental media.
(2) Maximum individual- The maximum individual dose is the dose to the most critical 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 individual is much less t'ian the maximum individual dose. The doses for inhalation and vegetable consumption assume that the individual resides at the point of maximum quarterly dose. Therefore, his residence is subject to variation for conservatism.
(3) The plant effects were so small that they could not be distinguished from fluctuations in natural background.
(4) NAD - No activity detected above the minimum detectable level. The less-than value reported is the dose corresponding to the MDL (5) For adult.
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 soil 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 I-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 isotopes are still remaining from the high weapons testing era of the 1960's. This 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 difficult problem.
In reviewing the Sr-90 and Cs-137 measured in cow and goat milk in the areas around the Millstone and Haddam Neck stations, a casual observer could notice that in some cases the levels of these isotopes are higher at farms closer to the station than at those 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.
- 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 Rec;ulatory Commission, concentrations in the environment can be calculateu. These calculations (generally conservative, see Section 5.0) show that insufficient quantities (by more than a factor of 1000) of Sr-90 and Cs-137 have been released from the stations to yield the measured concentrations in milk.
- 2. Based on the ratio of Sr 89 to Sr-90 in the measured releases from the stations and on the similar chemical properties of the two nuclides, plant-related Sr-90 cannot be detected in milk without also detecting plant related Sr-89.
During 1981 (and a few other occassions), Sr-89 has been detected in many of the milk samples. To investigate the source of Sr 89, air particulate data has been evaluated. Evaluation shows that airborne Sr 89 is generally uniform at
. all the indicator and control locations for both the Millstone and Haddam
! Neck stations. Therefore it can be concluded that the Sr-89 seen in milk is i from recent fallout.
Similarly, the levels of airborne Sr 90 (and total Cesium) are also generally i
uniform at all the air sampling locations. However, with the longer half lives l
of these isotopes, the same conclusion cannot be made. But, plant related Sr-l 89 has never been detected in milk, therefore levels of Sr-90 observed must be attributable to nuclear weapon's testing.
l 61
- 3. Similar to Sr-89, Cs-134 can be us:d 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 Chernobyl incident.
- 4. Since dairy milk sampling began in the 1960's, years prior to plant operation, the immediate station areas have always shown higher levels of weapons fallout related Sr 90 and Cs 137 (see Figures 61 and 6 2). The ratio of activity between the locations has not changed with plant operation. All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban Treaty.
- 5. Local variability of Sr 90 and Cs 137 in milk is common through out 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 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.
Based on these facts, the obsersation that the station effluents are responsible is obviously false. The cause must be one or more of the other variables.
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.
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, Env,ronmental i Protection Agency and Connecticut Department of Environmental Protection.
i I
e 62 1
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e .
STRONTIUM-90 IN MILK >
Figure 6-1 -
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CESIUM-137 IN MILK . ,
Figure 6-2 ...
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H = HADDAM NECK AREA--Average of Individual Form Samples M = MILLSTONE AREA--Averoce of Individual Form Samples
4
- O e c
APPENDIX A COW AND GOAT CENSUS FOR 1987 A-1
, n .. ,
e IMIRY COIS WI'DiIN 15 MILFE OF CONNffrICLTr YAf;KEE AS OF APRIL 1987 DIREITIOfJ DISTArJCE fW1E AND ADDREES tJ0. OF COJS N 14 M. Arthur Lord 25 180 Jones Hollow Bd.
Marlborough, CT 06447 N 15 M. Foot liills Fonn 35 Eljwarc! Fotte RFD #2 lbbron, CT 06248 NNE 14 M. Robert K. Gaspur 75 694 Gilead St.
Ibbron, Cr 06248 N!;E 14 M. Hills Fann 73 527 Gilead St.
liebron, Cr 06248
!;t E 14 M. 11apleleaf Farin, Inc. 168 750 Gilead St.
ikbron, CT 06248
!*WE 14 11. Gordon ti. Rathburn 34 l'artin PJ.
Hebron, CT 0624R NNE 14.5 11. Doo;1as Porter 155 RFD # 1 Fubron, Cr 06248 NE 4.5 f t. John Dill 27 Waterhole it.
Colchester, Cr 06415
- East I Ampton -
NE 14 M. Victor Ibtticello 25 Irvita Id.
Irbanon, CT 06249 NE 14 M. Graboer Brothers 51 RFD el Ivbanon, CT 06249 t;;E 6 M. Doris or Oscar Dill 48 Reete Rd .
Fast Haddam, Cr 06423
, e . ,
I%IRY COfS WI'lHIt1 15 MILES OF COfitIECTICUT YAhKER AS OF APRIL 1987 DIRE"rIOff DIS"rN K'E t;N1E At D ADDP,ESS to. OF COJS mE 6.5 M. Grandpa Hill Fam 55 R. S. Cbnu Dox 251 East Hackfam, Cr 06423 Et:E 8 .1 !! . William Smith 58 Tcun Ibad 0)lchester, cr 06415
- East Haddam -
mF 11 ti. Walter Swider 45 Route 85 Cbichester, CT 06415 Et;F 14 f t . Burton Avery 31 Pathburn Hill Pd.
Cbichester, CT 06415
- Salem -
Et;E 14.5 tl. Walter !!akaruvich 16 GtNr N .
Lebanon, CT 06249 E 11.5 T1. Valley View Fam 42 Fugene Wiczewski Darling R1 Salen, cr 06415 E 13 M. Anne B. IMnrici 5 Catawa:rpus rniry Round Hill M.
Salem, cr 06415 E 13 M. Gerry Vaill 49 Fbrsythe Pd, Salem, CT 06415 E 14 M. Stuart Gaarnis 213 Boute 82 Salem, Cr 06415 ESE 14.5 f t. Raymond fluschinsky 22 Grassy Hill Rd.
Fas t Lyr:n , CT 06333 i
, n . .
DAIRY OiS WIDiIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1987 DIRECTION DISTM CE tW1E NJD ADDRESS to. OF ColS SE 11 M. Tiffany Farms 80 Sterling City Rl.
Old Lynn, Cr 06371
- Lyme -
SE 12 M. J. Ely Hardiry) 55 Ashlawn Farn Old Lyne, Cr 06371
- Lyne -
Sd 13 M. Ttanas Haggarty 44 Hoophole Id.
Guilford, CT 06437 SW 14.5 M. Sugarloat Farm 17 154 Beaver Head Rj.
Ibrth Guilford, Cr 06437 WSi 8 fl. Michael Luyer 9 Foute 17 Eurham, CT 06492
- Wallingford -
WS! 8ti. Ibt>2rt Raudat 36 Old D2rham Rl.
Killingworth, CT 06417 US1 11 fl. Ray ond Wimler 204 Guilford R).
Durham, CT 06422 US; 14 11. 0311a Brotters 130 Whirlwirx1 Hill 2 tb. Brandford St.
Wallingford, CT 06492 W.4 14 fl. John Kranyak 55 1349 t.'hirlwind Pd.
Wallingford, Cr 06492 1511. Cn Ag Fam, Inc. 210 WS1 Walter Augur & George Cooke 180 tbrthford Rl.
Wallingford, CT 06492
,n .
DAIRY CO?S WIT 51I!1 15 MILES OF CONNECTICUT YAt.KFJ AS OF APRIL 1987 DIRfX.TIOt1 DISTANCC t;AME A!!D ADDRESS to. OF CuiS
\i 8.5 M. Richard Pow 15 Dox 4, Higganun FU.
Durham, CT 06422 W 11.5 tl. Friendly Aeros fairy Fam 31 lbny Caltabiano Pamalee Hill RJ.
turham, CT 06422
'1
. 12.2 fl. Powder liill Dairy Farm 189 Henry Bugai Powder Hill Rd.
Curham, CT 06422 W 12.5 11. Linus sanstrai, Jr. 36 Strickland R1 Middlefield, Cr 06455
'; 14 M. !Drth Fams 19 Alex Werbiski 1069 Fams Ttj.
Wallingford, CT 06492
'.1 14.5 M. Charles Greenback & Sons, Inc. 162 743 flurdock Ave.
tieriden, Cr 06450 W 14.5 11. R>txert self 79 Fieldstore Fam 63 Grieb Rd.
Wallingford, Cr 06492 R31 7 f t. Calvin Harvey 8 55 Tryon St.
Middletown, CT 06457 W:1. 8 M. E. Leroy Brock 55 796 Ridga RI .
tiiddletown, LT 06457 RA 8 M. George Seifert 33 Kelsey St.
Middletown, Cr 06457 k
!%IRY CDiS WI'IHIN 15 MI!ES OF 00NNEcrICLtr YANKm AS OF APRIL 1987 DIRIX.TICts DIb7ANCF tW1E AND ADDRf5S PJD. OF G 1 S Wtal 12 M. John Kolman 55 thriden 10.
. Middletown, Cr 06457 Wtil 12 H. Walnut liill Farm 131 William & Thanas Mintz Jackson Hill 141.
tiiddlefield, CT 06455 W!ki 15 !!. Bilger Brothers 26 Hickory Grove iarm 705 uastfield 10.
tbriden, Cr 06450
!U 6 M. E1] ward Hills 24 Brooks Id.
Iliadletown, Cr 06457 N., 13 11. liiggins Fam, Inc. 50 837 Ridgem 10.
Middletown, CT 06457 fl. 15 M. Wenceslaus & Jean Backiel 33 kiverside Farm RfD $2 lbrlin, CT 06037
- incky 11i11 -
tai 15 M. Jonn W. tbisterliru 33 fox 385, France St.
Ibexy Hill, CT 06067 tstai 1.5 tl. John Krugsr 20 Quarry Hill 10.
Haddam, Cr 06433 tal; 1311. 01arles Matway, Dst. 14 lirook St.
Ibcky tiill, Cr 06067 ta b' 14 11. Boariry Brook Fam 20 tunry Killam 77 Tryon St.
So. Glastonbury, CT 06073 Glastonbury -
-1 4
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i DAIRY COATS WITHIN 20 MILES OF CONNECTICUT YANKEE -
i 19 c ;
Eif AS OF JUHF 1987 F
6 ii i c;; -
t t :
u s t DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS l 8
t 1
N 4.5 M. Philip Bourdon 6 i 164 Young Street '
East Hampton, CT 06424 I ,
t N 6 M. Jackie Reardon 3 :
55 So. Main Street l East Hampton, CT 06424 :
N 15 M. Joan & Thomas Tamble 3
'- 581 Thompson Street [
Glastonbury, CT 06023 ,
i NNE 12 M. Louise Sage 3 155 Reidy Hill Road l Hebron, CT 06248 ,
NNE 16 M. Joan Bowers 1 i 350 Wall Street L Hebron, CT 06248 i l
r NNE 16 M. Kathy Waters 12 L Burnt Hill Road [
Hebron, CT 06248 ;
NE 16 M Barbara Nadeau 2 t
Clubhouse Road Lebanon. CT 06249 i NE 17 M. Lynn Miller 7 !
Coshen Hill Road }
Lebanon, CT 06249 i I
l r
i w'---"-uir- y 7 -o,-y.,m,m,
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. , ~ . .
DAIRY COATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF JUNE 1987 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COATS E 12 M. Anne B. Henrici 5 Round Hill Road Sales, CT 06415 ESE 16 M. Ron Birchall 8 1 339 Boston Post Road Eas t Lyme , CT 06333 SE 13 M. Peter LaPo11a 3 Town Woods Road Old Lyme, CT 06371 S 11.5 M. Victor Trudeau 6 174 Horse Hill Road l
Westbrook, CT 06498 W 4.8 M. Pat Mannetho 3 Jacoby Road Higganum, CT 06441 i
~
W 12 M. Brian Hogan 3 Route 157 Middlefield, CT 06082 W 14.5 M. Robert Pogomore 1 177 Williams R 'ad Wallingford, CT 06492 i
W 15.3 M. Jt.s & Marf Hall Petlack 8 1000 North Farms Road i
d Wallingford, Cr 06492 1
4
'T 1
,y- ,w. ,, ,.,, , . - , , - - - , , .- , - - - - ,-- -----_--_e..--,-, , .---,----%-, ,--='y
,, ' e* - , _ e-yA DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF JUNE 1987' n
DIRECTION DISTANCE NAME AND' ADDRESS NO. OF GOATS
-WNW' 10.5 M. Roger Kinderman 2 721 Wadsworth Road Middlefield, CT 06082 WNW 19 M. Daniel Nickowski 3 46 Firch Avenue Meriden, CT 06450 NSW 3.5 M.
- Donald Donofrio ,
Injun Mollow Road Haddau Neck, CT 06441 NW 13.2 M. Harry & Dilys McIntyre 1 104 Court Street Cromwell, CT 06416
~ NW 13.5 M. The LaRoche Family 12 South Road Portland, CT 06480 13.5 M. Melvin Granger 3 NW 140 Coles Road Cromwell, CT 60106 NNW 1, M. Dorothy Joba 15 171 Ferry Lane S. Glastonbury, CT 0607' M. Dona]J Reid 4 NNW 15 1654 Main Street Glastonbury, CT 06033
- Unable to contact as of this time.
%eN
e
- s e e
APPENDIX B NORTHEAST UTILITIES QA PROGRAM B1
INTRODUCTION 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 (QA) program of its primary contractor of radiological analyses, Clean Harbors, Inc., (Teledyne for H-3 in water samples). This is accomplished by the use of the three quality control methods that are specified in Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education, and Welfare (January 1967).
These three quality control methods are:
a) Duplicate analyses of actual surveillance samples with one laboratory. This type of quality control allows an evaluation of the contractor's precision or reproducibility of results.
b) Cross-check analyses of actual surveillance samples with more than one laboratory. This intercomparison allows the determination of what agreement the primary contractor has with another laboratory.
c) Analyses of "spiked" samples. This type of quality control allows a check on the contractor's accuracy of results.
Additional QA programs are performed, these include: 1) Clean Harbor's internal QA program,2) Clean Harbor's participation in EPA's Environmental Radioactivity Laboratory l Intercomparison Studies Program, and 3) Nuclear Regulatory Commission - State of Connecticut independent Verification Program.
METHOD The number and type of QA samples are given in Table f. In general, the objective was to obtain between 10 and 20 percent of the samples as QA samples. The results of the program are shown in Tables 2,3, and 4. These three tables correspond to the above methods of quality control.
For 1-131 spikes in milk, the acceptance criteria is based on the requirement that the measured value be within 30 percent of the spike. For TLD's, the difference between the two readings or between the measurement and spike should be less than 20 percent. The acceptance criteria for the remaining QA samples is based on the standard deviation in counting between the statistics (1 sigma, o) two measurements a).only(. The result The then standard deviation should satisfy theisacceptance divided into the difference criteria as developed from the abcse-mentioned U.S. Department of Health, Education, and Welfare document. For all GeLi analyses the acceptance criteria is that A/o be less than or equal to 3. For chemistry and beta counting, where the overall error is expected to be higher than the calculated error based on counting statistics only, the acceptance criteria is that A/o be less than or equal to 4.
RESULTS For Precision (Tabn 2), the requirement is that the unacceptable results be less than 10 percent of the nuir.ber of measurements for that type of measurement as shown for the totals. General stat stics indicate that this value should be approximately 2.5 percent for counting statistics, t.ut other non-counting statistical errors exist such as sample volume, sampling, etc. Hence,10 percent has been found to be reasonable criteria. From the totals at the bottom of Table 2, this requirement is satisfied for all analyses except for Sr-
- 90. Three of the six unacceptable results became acceptable after reanalysis. Of the l B2
l
. ~. .
i remaining three, reanalysis results were unavailable at the time of this report. No obvious reasons for these deviations were found.
For Interlaboratory C^mparisons (Table 3) the requirement is less stringent than both Precision and Accuracy, that is the unacceptable results be less than 20 percent of the number of measurements for that type of measurement. As indicated by the totals on the bottom of Table 3, this requirement is satisfied for Sr-90 and H 3 analyses.
Investigations were performed on the three unacceptable GeLi analyses. After reanalycis, only one sample failed the acceptance criteria.
For the case of Accuracy, only the primary contractor need satisfy the acceptance criteria.
The secondary contractor receives only a small number of samples thus making the evaluation of the secondary contractor difficult. The requirement that need be satisfied by the primary contractor here is tha same~ as that for Precision, that the unacceptable results be less than 10 percent of the number of measurements for that t pe of measurement. From the totals at the bottom of Table 4, this requirement is satis.ied for 1 131 (in milk), H-3 and Sr-89 analyses.
Milk Sr-90 spikes had three of the six results unacceptable. Two of these were potentially caused by a miscalculation of the spike. Analysis of both by the secondary contractor indicated the spike was incorrect and the primary contractor s results were correct. The third unacceptable result was low by only 7 percent. The remaining unacceptable Sr-90 results occurred in air particulates, a media in which reanalysis is not possible since the whole sample is destructively analyzed.
Eight of twelve GeLi water spikes were unaccceptable. Of these, six were caused by problems in spiking / analyzing Ag 110m. The other two were de'. ermined to have been analyzed with the gain slightly off. After adjustment the sa aples were acceptable.
Eleven of twenty-four GeLi air particulate spikes were unacceptable. Of these, nine were caused by problems in analyzing Ce-144, 2n 65 or Cs-137. The remaining two had problems with Cs-134 or Fe-59. These problems are being investigated.
For I-131 in air analyses, three of nine results were unacceptable. After reanalysis, only one result remained unacceptable.
Four of the twelve air particulate beta spikes showed unacceptable results. After reanalysis, only two remained unacceptable,these were high by 9 and 42 percent.
CONCLUSION Based on the results discussed above, it is concluded that the results of the routine measurements presented in the report are valid. The results of the primary contractor's participation in the EPA QA program confirms this conclusion.
l i
B-3
Table 1 Number of Quality Control
- Samples Number of Number of Sample Type QC Samples Routine Samplesa,b TLDs 138 504 Milk 75 144 Well Water' 20 16 Sea Water' 2 8 t
River Water ( 2 8 Bottom Sediment 4 26 Aquatic Flora 4 14 Fish 4 47 Shellfish 4 69 l Lobster / Crab 0 17 Fruits and Vegetables 0 16 l
l Air Particulate - Gross Beta 12 827
-lodine 9 780
- Geli 24 192
- Strontiu m 8 64 l
l l
- An additional program is performed by the contractor a - Total for both Millstone and Connecticut Yankee b - Depends on availability c - OC breakdown does not include H 3 analysis; total number of tritium QC samples was 20 B4
Table 2 PRECISION Acceptance Number of Measurements Media- Analysis Criteria
- Acceptable Unacceptable Milk Sr90 4 20 6 Sr89 4 26 0 Cs137 (Geli) 3 27 0 Water H-3 4 4 0 Soil & Geli's 3 2 0 Bottom Sediment Aquatic Life Geli's 3 4 0 Sr90 4 1 0 Total Sr90 4 21 6 Geli 3 33 0 H3 4 4 0
- The acceptance criteria is defined as: a measurment is acceptable if the delta / sigma is less than or equal to the values listed below, where:
delta = difference between the two values sigma = standard deviation B-S
. ~. .
Table 3 INTERLABORATORY COMPARISONS Acceptance Numberof Measurements Media Analysis Criteria
- Acceptable Unacceptable Direct Dose TLDs 20 % 84 4 Milk Sr90 4 11 2 Sr89 4 13 0 Cs137 (Geli) 3 13 0 Water H-3 4 4 0 Geli 3 4 2 Soil & Geli's 3 1 1 Bottore Sediment Aquatic Life Geli's 3 8 0 Sr90 4 11 2 Total H-3 4 4 0 Geli 3 26 3
- The acceptance criteria for TLDs is that the delta be less than or ec ual to 20%.
For all the other measurements, the measurment is acceptable if tie delta / sigma is less than or equal to the values listed below, where:
delta = difference between the two values sigma = standard deviation 36
a Table 4 ACCURACY (RESULTS OF SPIKES)
Number of Measurements Acceptable Unacceptable I Acceptance Primary Secondary Primary Secondary l Media Analysis Criteria
- Contractor Contractor Contractor Contractor f -
- Direct Dose TLDs 20 % 50 0 Milk i131 30 % 19 3 1 2 4 3 1 3 3 Sr90 Sr89 4 6 3 0 1 Cs137 3 6 4 0 0 Cs134 3 6 4 0 0 Water Geli 3 4 6 8 0 H-3 4 8 4 0 0 Air Particulate Gross Beta 4 8 - 4 -
Geli 3 13 - 11 -
Sr90 4 5 - 3 -
l131 4 6 - 3 -
Total TLDs 20 % 50 - 0 -
19 3 2 1131 (milk) 30 % 1 Sr90 4 8 1 6 3 Sr89 4 6 3 0 1 Geli 3 23 10 19 0 H-3 4 8 4 0 0 i131 (air) 4 6 - 3 -
Groes 8 eta (air) 4 8 - 4 -
- The acceptance criteria for TLDs and 1 131 in milk is that the delta be less than or equal to 20% and 30% respectively. For all the other measurements, the measurement is acceptable if the deha/ sigma is less than or equal to the values listed below,where:
delta = difference between the two values sigma = standard deviation B7
n .
l . .. .
APPENDIX C
SUMMARY
OF EPA INT ERLABORATORY COMPARISONS C1
,- ~ , . . '
e
- EPA DATA The EPA section of the quarterly QC report is cumulative for the year. The table submitted with the last report of the year should be complete for results received and will be updated. finally for results received later.
Results are presented as follow:
Sr-90 17 (xx) 16 H
CHAS Avg. 17 (1.0)
EPA Known 17 (1.5, 2.6)
EPA Gr. Avg. 16 (yy)
(xx) -
This value will be given when the precision (1 SD) of the CHAS measurement due to counting statistics is significantly different from the expected, EPA precision. This should cause different spread in our results.
(1.0) Next to CHAS Avg.- - This is the actual SD of the CHAS data 1.e, 1 SD, 1 determination. This means that an additional single measurement should yield a result within 1 SD of the mean 66% of the time.
(1.5. 2.6) Next to EPA Known - The first number is the anticipated 1 SD as decreed by the EPA. This value can be compared to the figure above to see that the CHAS precision is as expected.
The second number is 3 SD of the mean which is the EPA Control Limit. If the observed mean (i.e. CHAS Avg.) differs from the known by more than this value the result is unacceptable according to the EPA criteria.
(yy) -
This when given is the observed 1 SD, 1 determination for all labs whose results were not deemed outliers. A significant difference Setween this value and the one above it indicates that the anticipated precision is not being attained by the majority of the laboratories.
- i e :.
EPA Intercomparison Samples Gross Alpha and Beta Samole No. - Samole Date Samole Tvoe. Gross Aloha. Gross' beta 36215- 1/23/87 Water (a) 7 _
9 12 12-2 11 Lab Avg. 9(3) 11(2)
EPA Known 11(5,9) 10(5,9)
EPA Gr. Avg. 10(3) 11(2) 36348 3/20/87 Water (a) 4 14 4 13 i 11 Lab Avg. 5(1) 13(1)
EPA Known 3(5,9) 13(5,9)
EPA Gr. Avg. 4(1) 13(3) 36403 4/10/87 APT (b) 4 43 0 41 1 in Lab Avg. 2(2) 43(2)
EPA Known 14(5,9) 43(5,9)
EPA Gr. Avg. 15(3) 45(5) 36 12 4/20/87 Water (a) 29 Not Required 26 21 Lab Avg. 26(3)
EPA Known 30(8.14)
EPA Gr. Avg. 28(8) 36413 4/20/87 Vater (a) Not Required 53 49
. 10 c Lab Avg. 51(2)
EPA Known 66(5.9)
EPA Gr. Avg. 65(7) l l
E I
,. - , ,_..._.-__.,,_.m. . . ~ , . _ . , . . . - . ~ _ - -
.. a. .: : V s .
EPA Intercomparison Samples Gross Alpha ~and. Beta lSamole No. Samole Date- .Samole Tvoe Cross-Aloha Cross Beta 36501- 5/22/87 Water (a) 14- 6
-15 7 11 ft
, Lab Avg. 14(1) 6(1)
EPA Known 11(5,9) 7(5,9)
EPA Gr. Avg. 10(3) 8(2) 36790 7/24/87 Water (a) 4 7 2 6
.1 h Lab Avg. 3(1) 6(1)
EPA Known 5(5,9) 5(5,9)
EPA Gr. Avg. 5(1) 6(2) 37040 8/28/87 APT (b) LT1 23 LT1 20 1T.1 la Lab Avg. LT1 20(3)
EPA Known 10(5,9) 30(5,9)
EPA Gr. Avg. 10(2) 30(4) 37117 9/18/87 Water (a) 4 11 3 11 1 12 Lab Avg. 4(1) 11(1)
EPA Known 4(5,9) 12(5,9)
EPA Gr. Avg. 4(1) 12(2) 202468 10/21/87 Water (a) 23 Not Required 21 11 Lab Avg. 23(2)
EPA Known 28(7,12)
EPA Gr. Avg. 28(8) 202469- 10/21/87 Water (a) Not Required 75 75 11 Lab Avg. 75(0)
EPA Known 72(5,9)
EPA Gr. Avg. 75(9)
Note: (a) pCi/1 (b) pCi/ filter 9
m.
EPA Intercomparison Samples Cs-137 Sample No. Sample Date Sample Tvoe Cs-137 36403 4/10/87 APT (b) 16 15 12 Lab Avg. 16(1)
EPA Known 8(5,9)
EPA Gr. Avg. 9(2) 37040 8/28/87 APT (b) 10 13 12 Lab Avg. 11(2)
EPA Known 10(5,9)
EPA Gr. Avg. 11(2)
Note: (a) pCi/1 (b) pCi/ filter e
. EPA Intercomparison Samples Gamma Sample No. Samole Date -1gmole Tvoe 36248 2/6/87 Water.
Nuclide (pCi/1) 77 Nuclide (pci/1) 45 Cs 137 84 Co-60 50 M 4.t.1 Lab Avg. '82(5) Lab Avg. 48(3)
EPA Known 87(5,9) EPA Knewn 50(5,9)
EPA Gr. Avg. 87(5) EPA Gr. Avg. 50(4)
Nuclide (pCi/1) 87 Nuclide (pci/1) 92 2n 65 88 Ru-106. 91
- 14. . M Lab Avg. 90(4) Lab Avg. 90(3)
EPA Known 91(5,9) EPA Known 100(5,9)
EPA Gr. Avg. 94(8) EPA Gr. Avg. 95(16)
Nuclide (pci/1) 55 Cs-134 56 il Lab Avg. 54(3)
EPA Known 59(5,9)
EPA Gr. Avg. 55(3)
Samole No. Samole Date Sample Tvoe 36413. 4/20/87 Water
.Nuclide-(pci/1) 6 Nuclide (pCi/1) 21 Co 60 7 Co-134 20 a la Lab Avg. 7(1) Lab Avg. 20(2)
EPA Known 8(5,9) EPA Known 20(5,9)
EPA Gr. Avg. 9(2) EPA Gr. Avg. 18(3)
, .s - ; . ., . * /
EPA Intercompariso'n Samples Gamma Samole No. Samole Date Samole Tvoe 36413 4/20/87 , Water Nuclide (pCi/1) 17 Cs 137 16 11 Lab Avg. 16(1) -
EPA Known 15(5,9)
EPA Gr. Avg. 16(2)
Sampla No Sample Date Samole Tvoe 36578 6/5/87 Vacer Nuclide ipci/1) ELT 90- Nuclide (pCi/1) 56 Cr 51 LT 90 .C.2.Ja 64 LT 94 11 Lab Avg. -LT 91 lab Avg. 61(4)
EPA Known 41(5,9) EPA Known 64(5.9)
EPA Gr. Avg. 39(14) EPA Gr. Avg. 65(4) '
Nuclide (pC1/1)' 15 Nuclide (pci/1) 102 Zn-65 16 Ru 106 85 13 El Lab Avg. 17(2) Lab Avg. 94(9)
-EPA Known 10(5.9) EPA Known 75(5.9)
EPA Gr. Avg. 11(2) EPA Gr. Avg. 73(11)
Nuclide (pci/1) 35 Nuclide (pCi/1) 75 Cs-134 41 Cs 137 74 11 LO Lab Avg. 36(4) Lab Avg. 76(3)
EPA Known 40(5,9) EPA Known 80(5,9)
EPA Gr. Avg. 37(3) EPA Gr. Avg. 80(5) in a e . ii s
- , uf, 1. :
EPA Intercomparison Samoles Gamma Sadole No: Sample Date Samole Tvoe 36649 6/26/87 Milk
~
u Nuclide (pCi/1). 73 Nuclide (mg/1) 1119*
Cs-137 72 K 40 1138*-
fl 1149*
Lab Avg. 69(6) Lab Avg. 1132*(12)'
EPA Known 74(5,9) EPA Known 1525(76,132)
EPA Gr. Avg. 75(6) EPA Gr. Avg. 1577(113)
Samole 'to ' Sample Date- Samole-Tvoe 201998 10/9/87 Water Nuclide (pCi/1) 41- Nuclide (pCi/1) 14 Cr-51 LT 41 Co 40 16 LT 47 -11~
Lab' Avg. LT 43 Lab Avg. 15(1)
EPA Known 70(5,9) EPA Known 15(5,9)
EPA Gr. Avg. 69(9) EPA Gr. Avg. 16(2)
^
Nuclide.(pCi/1) 39 Nuclide (pCi/1) 35 Knzil 49 Ru 106 56~
42 is Lab Avg. 43(5) Lab Avg. 46(11)
EPA Known 46(5,9) EPA'Znown 61(5,9)
EPA Gr. Avg. 47(5) EPA Cr. Avg. 60(10)
.Nuclide (pci/1) 20 Nuclide (pCi/1) 42 Cs-134 23 Cs-137 51 2h 4.s +
Lab Avg. 22(2) Lab Avg. 46(5)
EPA Known 25 i,9) EPA Known $1(5.9)
EPA Gr. Avg. 24 2) EPA Gr. Asg. 52(3) ;
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s EPA Intercomparison Samples Gamma
'Sahole No. Samole Date Samole Tvoe 202469 10/21/87 Water-Nuclide'(pCi/1) 16 Nuclide (pCi/1) 14 Co.60- . 15 cs 134- 13 il 14 Lab Avg. 16(2) lab Avg. 14(1)
EPA Known 16(5,9) EPA Known 16(5,9)
EPA Gr. Avg.. 17(2) EPA Gr. Avg. 16(3)
Nuclide-(pC1/1). 26 Cs-137 26 21.
Lab Avg. 25(2)
EPA Known 24(5,9)
EPA Gr. Avg. 24(2) d e.n-- ,.-.- ,,--...--,,,.c., ,- , - . , , , . , - . . - - , , ,,-..,,n, --..n--. . , . , , - , - -
,- s, , e a
EPA Intercomparison Samples I 131 (pci/1)
Samole No. Sample Date Sample Tvoe Cs-137 36282 2/27/87 Milk 7 7
1 Lab Avg. 7(1)
EPA Known 9(1,2)
EPA Gr. Avg. 9(2) 36374 4/3/87 Water 5 4
i Lab Avg. 5(1)
EPA Known 7(1,2)
EPA Gr. Avg. 7(1) 36649 6/26/87 Milk 70 72 20 Lab Avg. 71(1)
EPA Known 59(6.10)
EPA Gr. Avg. 62(6) 36893 8/7/87 Water 49 54 11 Lab Avg. 52(3)
EPA Known 48(6.10)
EPA Gr. Avg. 47(5) 8712049 12/4/87 Water 27 28 12 Lab Avg. 27(1)
EPA Known 26(6,10)
EPA Gr. Avg. 27(3) a
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EPA Intercomparison Samples Ra-226 and Ra 228(pci/1)
Samole'No. ' Sample Date- Sample Tvoe- Ra 226 Ra-228
- 36302 3/13/87 Water 7.6- 8.3 8.6 7 '.1
.L1 7.5 Lab Avg. 7.2(.4) 8.1(.6)
EPA Known 7.3(1,1,1.9) 7.5(1.1,1.9) i EPA Gr. Avg. 7.0(.9) 7.7(2.0) 36412 '4/20/87- Water 3.9 -3.5 4.0 5.0 4.0 5.7 i Lab Avg. 4.0(.1) 4.7(1.1)
EPA Known 3.9(.6,1.0) 4.0(.6,1.0)'
EPA Gr. Avg. 3.8(.4) 4.2(1.0) 36633 6/19/87 Vater 5.4 14.5 5.5 13.7 L.1 .l.L.2 .
Lab Avg. 5.1(.7) 14.5(.8)
EPA Known 7.3(1.1,1.9) 15.2(2.3,4.0)
EPA Gr. Avg. 7.0(1.2) 13.5(3.6) 37097 9/11/87 Water 2.0 5.9 .
8.7 10.1 i 2.3 L.2 Lab Avg. 6.6(4.0) 7.0(2.7)
EPA Known 9.7(1.5.2.6) 6.3(1.0.1.7)
EPA Gr. Avg. 9.0(1.3) 6.6(1.7) 202468 10/21/87 V6ter 4.6 Not Submitted -j 4.6 "
L1 Lab Avg. 3.6(1.8)
EPA Known 4.8(.7,1.2)
EPA Gr. Avg. 4.7 871214501 12/11/87 Vater 3.7 11.2 3.7 9.9 21 Bk Lab Avg. 3.4(.5) 9.9(1.3)
EPA Known 4.8(.7,1.2) 5.3(.8.1.e)
EPA Gr. Avg. 4.71 5.24 i
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EPA Intercomparison Samples Sr-89 and Sr 90 Samole No. Samole Date Samole Tvoe Sr 89 Sr 90 36158 1/9/87 Water (a) 32 24 28 26 H h Lab Avg. 31(3) 25(1) '
EPA Known 25(5.9) 25(2,3)
EPA Gr. Avg. 23(6) 23(3) 36403 4/10/87 APT (b) Not Required 17 17 U
Lab Avg. 17(0)
EPA Known 17(2.3)
EPA Gr. Avg. 18(2) 36413 4/20/87 Water (a) 23 10 21 10 2 U Lab Avg. 22(1) 10(0)
EPA Known 19(5,9) 10(2.3)
EPA Cr. Avg. 17(4) 10(2) 36484 5/8/87 Vater (a) 40 18 39 19 H M Lab Avg. 39(1) 18(1)
EPA Known 41(5,9) 20(2.3)
EPA Cr. Avg. 39(7) 20(3) 36649 Milk (a) 24 9 6/26/87 25 10 21 2 Lab Avg. 25(1) 9(1)
EPA Known 69(5,9) 36(2.3)
EPA Gr. Avg. 64(14) 34(5)
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EPA Intercomparison Samples Sr-89 and Sr 90
~
Samole No. Samole Date Samole Tyne Sr-89 Sr 90 37040 8/28/87 APT (b) Not Required 10
/ 10 2
Lab Avg. 10(1)
EPA Known 10(2,3)-
EPA Cr. Avg. 10(2) 202469 10/21/87 Water (a) -19 11 19 10 H H Lab Avg. 19(0) :1(1)
EPA Known 16(5,9) 10(2,3)
EPA Cr. Avg. 15(4) 10(1)
-Note: (a) pCi/1 (b) pCi/ filter i
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EPA Intercomparison Samples.
Tritium Samole No Samole-Date Samole Tvoe Tritium'(oCi/1) 36257 2/13/87 Water 3800
, 3700 119.Q .
Lab Avg. 3667(153)
EPA Known 4209(421.729)
EPA Gr. Avg. 4156(418) 36640 6/12/87 . Water 2900 2900 23.Q.Q Lab ' Avg . 2867(58)
EPA Known 2895(357,613)
EPA Gr. Avg. 2785(293)-
'202028 10/16/87 Water 4109 4241 4.2.1.2 Lab Avg. 4187(69)
EPA Known 4492(449.778)
EPA Gr; Avg. 4386(299)
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EPA.Intercomparison Samples Uranium _(pCi/1)
-Samole No. Samole' Date ' Samole Tvoe Uranium i 36"412 4/20/87 Water 4 ,
.4 1:
Lab Avg. 4(1) i EPA Known 5(6.10)
EPA Gr. Avg. 5(2) l l
t 202468 10/21/87 Water 3 3
2
. Lab Avg. 3(1)
- EPA Known 3(6,10)
EPA Gr Avg. 3(1) .
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NORTHEAST UTILITIES o.nor.i Orrico . s.ioen street. Beriin. Conn.ciicut I 5 - 57 m es .n= =xa co' ""
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- P.O. BOX 270 H ARTFORD. CONN ECTICUT 06141-0270 k k J "[.7d, C[iU,$.'C[, (203) 665-5000 April 28, 1988 Docket No. 50-213 B1283Z Re: 10CFR50.4(b)(1)
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
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
(
n N E. J4 fir 6czta" f Senr6r Vice President cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shediosky, Senior Resident Inspector, Haddam Neck Plant 50 i
I
O NORTHEAST UTILITIES o.n r.i ott.ces see.n sir..i. s.rnn. connect.cui 9 .. b' *
- 27
[4nrronD. CONNECTICUT 06141-0270l C LlTa5:::'.:;rlLTO'!. <203) ee54000 -
April 28, 1988 Docket No. 50-213 l
B12887 i Re: 10CFR50.4(b)(1) !
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Haddam Neck Plant Annual Radioloaical Environmental ODeratino Report In accordance with the requirements of the Haddam Neck Radiological Effluent Monitoring Manual, an implaenting 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 n W E. J4firdczfa f Seni'6r Vice President cc: W. T. Russell, Region I Administrator
- A. B. Wang, NRC Project Manager, Haddam Neck Plant l J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant l
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