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Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept 1987
	ML20151V745
Person / Time
Site:	Millstone
Issue date:	12/31/1987
From:	Mroczka E; NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES, NORTHEAST UTILITIES SERVICE CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8805030174
	Download: ML20151V745 (123)
	v • d • e

{{#Wiki_filter:__ . 1 .s MILLSTONE POINT SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PERIOD JANUARY 1,1987 - DECEMBER 31,1987 3 MILLSTONE UNIT 1, DOCKET NO. 50-245 MILLSTONE UNIT 2, DOCKET NO. 50 336 MILLSTONE UNIT 3, DOCKET NO. 50-423 PREPARED FOR 91E NORTHEAST NUCLEAR ENERGY COMPANY H ARTFORD, CONNECTICUT BY THE NORTHEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT ffLlG'

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-a = e TABLE OF CONTENTS Paae No. 1.0 S u m m a ry....... 1-1 2.0 Prog ra m Descriptio n..................................... 2-1 2.1 Sampling Schedule and Locations............ 2-1 2.2 Samples Collected During Report Period............ 2-8 3.0 Radiochemical Results 31 3.1 Summary Table 3-1 3.2 Data Tables 3-16 4.0 Discussion of Results........... 4-1 5.0 Offsite Dose Equivalent Ccmmitments... 5-1 l 6.0 Discussion 6-1 Appendix A - Cow and Goat Census for 1987..... A-1 t l A pp e ndix B - Q A Prog ra m.................................... B-1 Appendix C - Summary of EPA Interlaboratory Comparisons... C-1 1 I l l l I -.,y,, , v m

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SUMMARY

The radiological environmental monitoring program for the Millstone Nuclear Power Station was continued for the period January through December 1987, in compliance with the Radiological Effluen t Monitoring and Offsite Dose Calculation Manual. This annual reaort was prepared for the Northeast Nuclear Energy Company (NNECO) by tie 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 as an independent check on the primary contractor's laboratory as part of the overall quality assurance program. Sampling and radiological analyses were performed with gamma exposure measuring devices and on air particulates and iodine, milk, pasture grass, broad leaf vegetation, fruits, vegetables, seawater, bottom sediment, aquatic flora, finfish, mussels, oysters, clams, scallops, lobsters, and crabs. 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, seasonal variability of fallout,locational 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 Millstone) sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. In the case of the terrestrial media, the effect from Unit 1 via the direct dose pathway (i.e., scattered radiation, "skyshine', from nitrogen-16 in the turbine building; unique to Boiling Water Reactors) exists in the gamma exposure measurements at some of the onsite locations. Based upon past years, this effect can normally be seen by a decrease in the thei aoluminescent dosimeter (TLD) values during months when Unit 1 is shutdown for refueling. Skyshine's direct dose pathway decreases rapidly with distance, to levels that are undetectable at the offsite locations. The gaseous releases have been reduced such that they are no longer detectable by TLD's at any onsite or offsite location. Gaseous releases of iodine were also very low, such that it was not detectable in milk at the nearest offsite goat location. t l Monitoring of the aquatic environment in the area of the discharge indicated the presence of the following plant related radionuclides: manganese-54, cobalt-58 and cobalt-60 in aquatic flora; manganese 54, cobalt-58, cobalt-60 and silver-110m l in fish; cobalt-58 and cobalt 60 in mussels; manganese-54, cobalt-58, cobalt-60, zinc-65, and silver-110m in oysters; cobalt-58 and cobalt-60 in clams; and l manganese-54, cobalt-58 and cobalt 60 in lobsters and crabs. The levels of these l radionuclides were higher than the levels observed for the last seven years. Generally, releases were greater in 1987. However, doses from the measured levels are still well below those required by each Unit's Safety Technical Specifications (10CFR50 Appendix 1, Design Guidelines). All activity levels were below those of the higher discharge period of 1974-1975 (before the Unit 1 augmented liquid radwaste treatment system). 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 related cesium 134 and strontium 89 which are releasedin about equalorlarger 1-1

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 The maximum whole bcdy dose (station boundary)y in the environmental me utilizes the measured concentrations of radioactivit that could occur to a member of the general public as a result of the plant's discharges was 1.4 millirem and the average dose to a member of the public residing within 50 miles of the plant is 0.0013 millirem. These doses are 5.6 percent and 0.0052 percent of the standards as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the genera! public. These standards are a small fraction (less than 10 percent) of the 270 mrem per year normal background radiation and are designed to be incor.sequentialin regard to public health and safety. Plant 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 conse quences. 1-2

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 2-1 and 2-2 and Figures 2.1 and 2.2. The program as described here is both that which is required by the Radiological Effluent Monitoring and Of(site Dose Calculation Manual and any extra samples. i 1 l l l l l l l l l l l l 2-1

TABLE 2-1 ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The following lists the environmental sampling locations and the types of samples obtained at each location. Location Direction & Distance From Release Point *

Number Name Sample Types 1 -l
On site Old Millstone Rd.

,0.6 Mi, NNW TLD, Air Particulate, lodine, Vegetation 2-1 On-site - Weather Shack 0.3 Mi, S TLD, Air Particulate, lodine 3-1 On-site - Bird Sanctuary 0.3 Mi, NE TLD, Air Particulate, lodine 4-l On site-Albacore Drive 1.0 Mi, N TLD, Air Particulate, lodine 51 Floating Barge 0.2 Mi, SSE TLD 6-1 Quarry Discharge 0.3 Mi, SSE TLD 7-l Fox Island 0.3 Mi, SE TLD 8-l Environmental Lab 0.3 Mi, SE TLD 91 Bay Point Beach 0.4 Mi, W TLD 10 1 Pleasure Beach 1.2 Mi, E TLD, Air Particulate, lodine 11-C New London Country 1.6 Mi, ENE TLD, Air Particulate, lodine Club 12-C Fisher's Island, NY 8.7 Mi, ESE TLD, Air Particulate 12-X Fisher's Island, NY 8.7 Mi, ESE Aquatic Species 13 C Mystic, CT 11.5 Mi, ENE TLD 14-C Ledyard, CT 12.0 Mi, NE TLD 15-C Montville, CT 14.0 Mi, N TLD, Air Particulate, lodine 16-C Old Lyme, CT 8.8 Mi, W TLD 17-l Site Boundary 0.5 Mi, NE Vegetation 18-l New London Country 1.6 Mi, ENE Vegetation Club 19-l Cow Location # 1 6.0 Mi, N Milk 20-1 Cow Location #2 9.5 Mi, WNW Milk 21-1 Cow Location #3 11.0 Mi, NE Milk (13.0 Mi, ENE) 22-C Cow Location #4 16.0 Mi, NNW Milk 23-1 Goat Location # 1 2.0 Mi, ENE Milk 24-C Goat Location #2 14.0 Mi, N E Milk 25-l Fruits & Vegetables Within 10 Miles Vegetation 26-C Fruits & Vegetables Beyond 10 Miles Vegetation 27-l Niantic 1.7 Mi, WNW TLD, Air Particulate, lodine l 28-l Two Tree Island 0.8 Mi, SSE Mussels 29 l West Jordan Cove 0.4 Mi, NNE Clams i 29-X West Jordan Cove 0.4 Mi, NNE Fucus 30-C Golden Spur 4.7 Mi, NNW Bottor.1 Sediment 1 31-1 Niantic Shoals 1.8 Mi, NW Bottom Sediment, Oysters, Scallops 1.5 Mi, NNW Mussels 2-2 l

TABLE 2-1 (Cont'd) Direction & Distance From Number Name Release Point ** Sample Types 31-X Niantic Shoals 1.8 Mi, NW

Fucu, 32-1 Vicinity of Discharge Bottom Sediment, Oysters, Lobster, Fish, Seawater 32-X Vicinity of Discharge Fucus, Mussels 33-1 Seaside Point 1.8 Mi, ESE Bottom Sediment 33-X Seaside Point 1.8 Mi, ESE Fucus 34-1 Thames River Yacht Club 4.0 Mi, EN E Bottom Sediment 34-X Thames River Yacht Club 4.0 Mi, EN E Oysters 35-1 Niantic Bay 0.3 Mi, WNW Lobster, Fish 36-1 Black Point 3.0 Mi, WSW Bottom Sediment, Oysters 36-X Black Point 3.0 Mi, W5W Fucus 37-C Giant's Neck 3.5 Mi, WSW Bottom Sediment, Oysters, Lobster, Seaweter 37-X Giant's Neck 3.5 Mi, WSW Fucus 38-l Waterford 5hellfish Bed #1 1 Mi, NW Clams 39-X jordon Cove Bar 0.8 Mi, N E Clams 40-X Quarry Fish, Oysters, Crabs 41-X Upper fordon Cove 1.2 Mi, NE Mussels 50-X Myrock Avenue 3.2 Mi, ENE TLD 54-X Billow Road 2.4 Mi, WSW TLD 55-X Black Point 2.6 Mi, SW TLD

l = Indicator C - Control X - Extra - nonrequired sample
- For terrestial locations, this is the MP1 stack, for aquatic it is the quarry cut.

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TABLE 2 2 MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling & Exposure Pathway Number of Collection and/or Sample Locations Frecuency Type & Freauency of Analysis Ia. Gamma Dose - Gamma Dose - Monthly 17 Monthly Environmental TLD 1b. Gamma Dose-22 Quarterly (a) N/A(a) Accident TLD 2. Airborne Particulate 8 Continuous sampler - Gross Beta - Weekly weekly filterchange Gamma Spectrum - Monthly on composite (by location), & on individual sample if gross beta is greater than 10 times the mean of the weeky control stations gross beta results 3. Airborne lodine 8 Continuous sampler - l-131 Weekly weekly canister change 4. Vegetation 5 One sample near middle Gamma Isotopic on each sample & one near end of growing season 5. Milk 6 Monthly for all animals Gamma Isotopic,1-131, Sr-89 & Sr 90 on teach except semimonthly for sample goats when on pasture 6. Sea Water 2 Quarterly-Composite Quarterly - Fractional Be ta, Gamma Isotopic. of 6 Weekly Grab Tritium on each composite samples 7. Bottom Sediment 7 Semiannual Gamma Isotopic on each sarnple 8. Fin Fish Flounder and 2 Quarterly Gamma Isotopic on each sample [ one other type of l edible fin fish 9. Mussels 2 Quarterly Gamma Isctopic on eacn sample

10. Oysters 4

Quarterly Gamma Isotopic on each sample l

11. Clams 2

Quarterly Gamma Isotopic on each sample

12. Lobster 3

Quarterly Gamma Isotopic on each sample (a) Accident monitoring TLDs to be dedosed at least quarterly I 2-4

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e-2.2 Sampits Cellected Durina Rep _crt Peritd The following teble summarizes the number of samples of each type collected dunng the present reporting period: Number of Number of Sample Type _ Required Samples Extra Samples Gamma Exposure (TLD) 204 36 Air Particulates 416 47 Air lodine 416 0 Dairy Milk 48 0 Goat Milk 27 0 Pasture Grass 1 0 Fruit & Vegetables S 0 Broad Leaf Vegetation 6 0 Seawater 8 0 Bottom Sediment 14 0 Aquatic Flora 0 14 Fish 16 6 Mussels 8 9 Oysters 16 9 Clams 8 4 i Scallops 0 3 Lobster '! 2 2 Crab 0 3 Total AllTypes 1,208 133 t l l i i 1 l 28 l

3.0 _ RADIOCHEMICAL RESULTS .i.1 Summary Table in accordance with the Radiolocical Effluent Monitorinc. Manual (REMM), Section F.1, a summary table of tie radiochemical results.las been prepared and is presented in Table 3-7. In the determination of the mean, the data was handled as recommended by Health and Safety Laboratory, Idaho: allvalid 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 iri Section 4.0 where a discussion of the variationsin the data explains many aspects that are not evident in the Summary Table because of the basiclimitation of such an approach. l l 3-1

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TtCLE 3-1 PAGE 3-3 EFNIRONNENTAL RADIOLOGICAL NONITORING PROGRAN SUNNARY NILLST0tlE IlUCLEAR PeuER ST ATI0tl. UtIITS 1. 2 Aff0 3 00CKETS 50-245. 50-336 AHO 50-423 JAt#JARY - DECENDER 1987 A?tALYSIS Ate LOWER LItitT ALL ItCICATOR t0C ATI0t3 WITH HTC-HEST ArnftfALNE AN CONTROL 8 OF, t1EDILM OR TOTAL NUMBER OF LOC ATIO'tS LOCATI0fl s. LOCATI0 tis HRH PATHWAY OF Af8ALYSES DETECTIOtt HEAF 4 01 STAT:CE 11EAN NEA?4 (C) Sat 1 PLED PERF0ertEO ( LLD I (A) ( R APP"E l( B ) AtN) OTDECTICH t R AtmE ll B ) (RANGEMB) NILK SR 36.12 0.4 LOC # 21 0.5 0.3 0 (OAIRYI SR-67 (-1.0 - 2.81 11 t1ILES HE (-0.5 - 2.8) (-0.3 - 0.81 (PCI/LI SR-90 4.3 LOC 8 21 5.9 3.5 0 ( 1.6 - 8.31 11 NILES NE ( 3.1 - 8.31 ( 2.7 - 4.41 100THE 36.12 1 0.01 LOC s 19 0.03 0.01 0 I-131 ( -0.21 - 0.18) 6 NILES N ( -0.15 - 0.18) ( -0.18 - 0.203 GE(LII 36.12 15 0.7 LOC 8 22C 1.1 1.1 0 CS-134 ( -1.7 - 3.81 16 NILES t#A4 ( -0.2 - 3.53 ( -0.2 - 3.51 L CS-137 18 7.3 LOC s 19 12.0 4.5 0 ( -2.8 - 30.7) 6 NILES N ( 3.9 - 30.73 ( 1.3 - 6.53 BA-140 70 2 LOC a 20 5 -4 0 ( 191 9.5 NILES Seni ( 181 ( 33 LA-140 25 0.2 LOC 8 22C 1.0 1.0 0 ( -5.8 - 5.78 16 NILES tam ( -3.6 - 7.01 ( -3.6 - 7.03 GOAT HILK SR 13.14 -0.1 LOC S 24C 0.1 0.1 O (PCI/LI SR-89 (-1.7 - 2.43 14 F1ILES NE (-0.6 - 1.33 (-0.6 - 1.38 SR-90 21.1 LOC 8 23 21.1 3.4 0 ( 9.3 - 38.63 2 MILES EHE ( 9.3 - 38.6) ( 1.8 - 5.9) ICOTHE 13.14 1 0.06 LOC 5 23 0.06 -0.01 0 I-131 ( -0.04 - 0.16) 2 MILES Et3E ( -0.04 - 0.163 ( -0.18 - 0.131 GE(LII 13.14 15 -0.0 LOC # 24C 0.6 0.6 0 CS-134 ( -0.9 - 1.03 14 NILES NE ( -1.7 - 3.21 ( -1.7 - 3.23 CS-137 18 53.0 LOC s 23 50.0 5.8 0 ( 17.2 - 112.13 2 NILES EtlE ( 11.2 - 112.13 ( 3.5 - 9.1)

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' O. I O. O. O O. 9 O. f O. > = > wQ "4 E. OO O4 OP OO OM OO ON O4 OO O@ eUV e I se i O e me e me p se O O 6 .=s e O O O. O. O. O. O. O. e O UC O. O. O. e .J w O O O O O O O O O O t I e 4 8 I I e 6 e w w w w w w w w w w w am em = = M M me P sm m N.s O O N s O tJ O N e a N O O

== 2 O. O. O. O. O. O. O. O. O. O. N. N. at am w O O O O O O O O O O O

== M = O M O d = e N M N O O N E 3= 2 ** O O O O O O O O O

== 0 M O. I

t
4 I

l O. 3 O. O. R f 4W D. 8 O. 9 O. 3 O. I O. I O. m 4M e w{ O LA OO ON Od O= O@ P O Q E. O== OO OP O O.e e i ** O e ** 4 O O O O O O M P. Q g O O. O. O. O. O. O. O. O. O. O. O N M at a w O O O O O O O O O O EN t 4 6 8 8 e B e a w w 4 m = w w w w w w w w w h as tJ E w d C nM e e-LMO z M nn P. Q ** O 2 5 g &e e-w e D = w 2 "* % 3 O

=

M M UM M M UM UM M M UM w = > b" @ kw ~W> LA w in w @w LA w Mw @ n.J @w LA w tA w @w O NM N =J N .,J se.J N.J te J N.J to.J ta =J S4 =4 N.J

- O H M ()

b ByU

- H 2w w

w w > M. i - e. n at er er

== or er er er er en m.J ms w M 4 w M M >Oy e ep - W M nn w U at M O UO OO UC UO OO UO U.O UO U O.= U O.a OE UE O== 0.= 0 -= O ** .O a's .O ' * .O ** O. C. .O O .J.J O C U- .O JA JA J V .J y . A J@ .J IA. J v .J V JA .J V ad v OOQ O4Q * -s 4 U W LA I J ee O >= ew 'I d 4 O O tJ > O,J (in 8 2 O4 O cr na 2 -4 O Ist M e4 O O me Pm M 4A d a 4 J >= *1 ' O O O e O O N N f* &UW D O. O. O. O. O. O. O. O. 0 N. gg > go = O O O O O O O O O O en M .J. U 4 *D w O M O d =* M N LA is O N 4A 4 O Ue* - 2* O O

e O

O O O O O

== C* I se. g W** O i I 0 8 0 a 4W l I O. 8 O. C. f C. 0 0 0 O. w5 Q >.r O. O. O M we MU U. O== OO OO OO O LA OO OO Od O ad O =e P 96 M. N M C 4 6 ** O 5 fJ me i O 4 tJ I== 0 C O O O. O. O. .J .J.s CL O. O. O. O. O. O. e O N g.J .J w M M 4 O O O O O O O O O O gE 3 s e e e e a a I w w w w w w w w = w w w w t= .= w =6-o c M ew 4 w .J >=w 6U O O O kOw* O. O 8 i B 4 w >- O I I I I e I I I i 3 w t I I e I O O O O =J J w Q Cr anJ M

L wO M ens C.

M 4 h M 7= E H .4 cx e O in M O M M N t

- N O

4O LA CF O' .= M

== N N th.J Z 6 t 8 8 9 I N f d w(40 O O D Q D I M M 4 2 s W 6 0 w 4-w U U a w U U a N = ass ZObk C4 4 #~ O e i8 B60 4-w&O 4w .J 4 N rtw O>M 5-a 4w HCE 00{ O4= QWw w EL M O> E ^ A.P

-e 4. O g $8 4 1 m mr-o.g u o O O O O O O O O O O O sa LD N 4& = sm a a= sm .m a.m m a en am an n o e o e e e e e e e e C ( O IJ 06 2 % e 8 1 1 8 1 I i i a l 0 4 3 gM a( w =7 w' g e e e N Bo E e UC n.

e 4

e e e e e e e e w w w w w w w w w w me w = mm m en an am an

== s= an O O N P 4 om N P N N N O 2 O. O. - =* O O .= ee O O O .=.e M O. O. O. O. O. O a.s O. O. p e e 6 C O O O O O O O O O O O M w e M se M N N N b E 2* O O

e O

O O

== O ED 4 O I O 1 D. I O I O. i O. O. 8 O. I i O. 3 O. I O. g O. O O. R .J 4W at M w ed wg e Q E. Oe O ** OO O tJ O==' ON OO Oe O4 OO ON

== es O O

=

0 O O O O m o O M Q y*. = Q O. O. O. O. O. O. O. O. O. O. O. N w O O O O O O O O O O O w EN k i e at O w w w w w w w w w w w am w we N 4 G n e.- O a M he z N @ >= Q " e. O T .S e M M M M W 3 W W g g g g 4 8 2 3 W = W = = W = 5 3 gJ<5 - "w" e" = ~ s* M O e s' s M M MS# M N

p. M r3 ZQU me @

M

- O
= M M

ee O

- M M

M@

- M M ME Om w w

w w w w w w w w w w w t N se N.d N =J N =4 N ed N ml N =J B.J N ed N ed N me N .d n 4 f beb >= *e et D. M M

=8 M

M M M o.e eo M M M >= 0V 4 DN 0 0 0 s O qyweI w me 4 s@ ed 4 ee 4 ed @ d4 sO OOQ ad 4 ee 4 =e 4 .J 4 =J @ M et G d 4 O =* me C O O O O O. O O D.t 4 9= M N> QL e k J O et om.m2 m m m s O O 4 4 4

e N

P P N N O w M. et q es e =3 g O O

== == O se me O e.e te to a M O O. O. O. O. O. O. O. O. se. O. O. & hJ w Mg = x J.O et O O O O O O O O O O O C M 4 O Ub

== 0 C 4 O N N 4 4 O N t= W D MM 2 ** O O O O O O O O 4 N O 8 w 6 O. 9 O. 1 O. I O. O. 1 O. s i e,i I Z ** 0 9 w6 Qk et W D. i O. O. O. N .e w g. O n. O p. OM CO OM Oe De os ~ Mu E. nM OO ON t D' O e4 e td O O O M d o et O ees O O N o O. O. O. O. O. O. O. O. O. ad ed.J k. e g.e .a s MM 4 O O O O O O O O O O O = 4E I e 0 e e i e 1 8 g w w w w w = w w w w w >= ee= 5-M M4 A > = = 4U 4 O gow-O. O. O e i 1 4 I i I i I >= c.s w w. e t i i t 8 O O O 4 8 i 3O O ad me w Qkwo e 4 WQ hk M 4 N O m M_so 4 O O m m O M M M ~ ~ at Q m m 4 e p me M se we ed N O e o e e e e se e t I be # >.J = g o o g s E e o i e e 4 w <a <M w E u u - x a w v U n = 064 W. >= Q l hhO E 's' W W 2* 3.s

- \\

5 ;I; 4 M>= E 3 0. .s w4O 'd

E n

qp

e s e a b eM &Ea O O O O O O O O O O O O ogU e 4 Se = O a a we N = 8. m O P M M N ,a e N = g O N e,, =* O N O O e e t c O e O w O M M N e N u O JOD 7-e 4 e e N N O e m. 2 ** 4W as i O 4 O 9 0 0 O 8 O I 4 I t 3 e i e l p o- > wg I e e e C em O ~< c. N m e e e 8 m.* m e .e.e M e 6 e e a e

== e e e.e p D U R O en N I O O a e e = w w I B 6 6 O O O w w me I w w w w w w w w w em = m o e m o e a e c O M d th. O b M M P O e e 4 o. o. 2 se O e e s O e=* N em O

== en W f-O ' th 9 P rJ 4 b 2*- O M M M E N. e O e N 4 O i) {' p1 m .J ew

- I O I O t

== 0 O I O i I l 4 3 e s e 3 4M W w( s t I rs ce O e M b me 4 to P th. C. a E N 4 es v O g g 4 f,* O, t CL O o, e O w w = EN = w w w w w w w D.* M w e=N z O S U mm. E >= O g >< m b Q 'b g v O T-2 2 a = 2 4 3 2 o o s s e s e s o n o = =

x

= 3 a us .e 6n@w a.- os ..Me Me Mo Me Mm Mo Mo Mo Me es o Mo w b 1 (J N N N N N b p 3 u Mo B: w l w " t= M..e.', .s i w w w w w w w w w w e >e a .e ..J .s .s s as .s as M .<. a. -Qu 5,"

s 8**a 85 85.

85 8' 8r 85 85 85 85 8r 85 85 sdOg e a m. so so so ame s e. se sO sO s e. s e. sO m<n. et u.* m m, s >e I4 M M - M M M m 4 82"'s i s O at t .O. a. n g ^ O DwMW O N O O M M ~~7 2 m = m W D e O em O M O O N se O as e=a e r X -{ meP. ( O 8 i O e O u b. M m M M C P O~~

~~== N eg w O e N 4 O~~

~~== O N -m 7 =* >wc 2' QF 4w O* f 0 1 4 O t - l O t - 1 I l 1 d i e l e l e, w $. w p' i i O N O k E. e ew C M M O M 4 4 8 e e N e e e e 6 I e 4 4 N 4* .n j O O N e e J e.J.J Q O~~

~~== (L.J e.J w t i. 6 i e O O gg w w = a e e-w w w w w w w w w w be M =~~

~~6. e M.~~
g = = = = a g p., 2 .J >w 2 2 2 2 2 t l 6o w w w w w = O O O \\ 7gw= O O O i O O N O O >- O.r 6J w. M M M i M 4 M N 4 4 4 3O Qs .J w 4 I g er r M M We w w w B B.e B.e n >r 4 8 O O s 4 e O -= M ,e 8 he N 4 th M sue
~~4 e'e e~~
>= M U U U > eJ r k
== s e .J 4 % a O m e k e 4 < et I W M W U Q w - Z F M k k 4* w
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w w we w W L et F"' O MO i 4w 3s H l% G l i -E i O44 W Ch O E
4 i s I s' 9 4 4 r me-QaU O O O O O D D O O O O W Zw e O 44 i i { = = m = a O e* N N N N b. o. s. O. O. O. 3 O. m. s.
== .2 e e O e O, i O O O .. O O O O O O e O o O O O e O e w f b 7= 0
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~~y y<~~
O O. O. O. O. O N e e e e .e w O me O (u O. O O O O O C O w i 6 I I I w w w w w w w w w w w I c' N N N N 9 N m P 7 C O. O. O. O. O. O. O. e.e. M. ms 4w O O N O O O O O O O O O .= L w N O m m D o 7-O. 4 = 1 N O O O O O. O. O. N. <m wg C O O O O O O O O O c O. a f D. .J et w 3 I
6

i i
I t 1 - t e r. O Ne O N -e 8 -e N O. O. O. O. O. O. O. O. N. t/. Q h O. s 4 a O O O O O O O O e, O O, 4 = w w r~ w w w w w w w w w w w 4 O a.m w me N I 4 C m o. O e a> I MmN e p<e z S e ~ s 1 a a a W z M b E E E E v5 c,. 5 uE E E E v2 u2 8 a -a#w w-e O O O .e .e e me me me me me me no me mn me nn no 5gu
~~W M,M e.~~
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~~p. O U 41 8_, 0 e 8., r 8m" 8 '.~~
~~8, = 85~~
~~8. O.~~
8, s= 8r 8,: 8c 8= 8,.'. = $. s. * *. a 8 **c w ~. s e. e. we _ e. s s. w s. w w ummi m .e .e .M 3, 88s & ed O el omma M. a ^ OwM4 a N N .= f N N a= C h e M7 O C. O. O O. O. O. O. O. C. m. a w O .J. g >g e am at C O N O O O O O O O O O ~ U b. N N O O O se -e m. O pe m 4 w O O O N m M m-2- O. O. O. O. O. O. WD 1 - 4 1 8 3 I = 1
1

I e I 6
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~~e O~~
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~~e. O I~~
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e
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6
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pe 3.. n v n ug 6< c., l ~ U 8o e a o s. w w w w w w l w w N a 4 -e M me d N N e.e M 2 C. D. O. O. O. O. O. O. O. O. 4 W C D M O O O O O O O O O E = N M S O O O
== 0 C O ?~ O 4 O O. O O. O. O. O. O. O 4 e e e p 3 e i t g a 3 g p 3 E J
~~( w 4M 4~~
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~~b M~~
6 g g g ~ M M N N N N N 2 b = = 3 = 1 = h = 3 E*M a ~ a M .h ed V N N N N N N N >= O 4.* w b*w> MM MM MM MM MM MM MM MM MM MM MM MMQ -6 U Q -M w w w w w w w w w w w w .M M _ ciw --<n =a Oa es ea ea m.J e.s as m.s ea as M MOU 4 M t= M M M M ee e-s 88 M M M M M Y.4 O O Q 0 0 0.a M 0 s O U sO me O .4 O me O .a O ed O .6 O =J M .J O a M. V4 4 &
~~e 4UwM i~~
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== 4 N N as M g.J t= 7 }J O. O. O O O O en. c. es. O. O. kUW e e a e gg -{
== O M O O O O O O O O O =J U C 4 0 .J 6
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==. = O. O. c. -e i M i e
~~ea g.~~
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== M .J o e c O lA O M o M dO a Ps O in th IA O P P D' e e e I a= =J = w e e 4 a O w O 4 k.J w a ei J 4 4 n, wM i e og g Q P. U h. U bJ k
~~06a w~~
4 0= 0 O Ct w OMO 4 4w a E 3.s O D L. L Mb t T.J M C44 V =a U W Q. M M( E.n E 6w e n f\\p
m 0 's ,; l# 6* p - e i i._ 6 g- + i ..O. e e N "a" ** M O U O O O O O O p O O O O W Z= 6 O N 4&. = a = a. em
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I e i e I

1

I e e e e e 3 e 3 e t
> = > w{ ~< n. BU8 = e a e e 4 e e o e e e e es w w w w w en w w w w w I I e a a
== een a m = es. Pm N M
== se m ee a p
~~7.l O.~~
O. O O O O N as O O e o e e e er a= e e 4'. I O O O O Oe Oo O M O O C. J8
== 0 O O O N me ck m E 2** O "J f;s O. O. O O O M C. O. j t e e t 1 e s e e e i e g ft .J 4w e w gt O o e O O O O O u O O <M g Q E' O N =*
~~e O~~
se 4 m N O O d s' O. O. O. O. O. O. O. O. 3 gl a.l .e e g e e .e m.e., w ce o O O O O O. O. O. O. 1 i w ra r i w e e w w w w e 4 m ( -.m w .e N Z e. e L" o.e M ~ xl- . O y, H m ~ . 5 m.. m ze e 3 2 2 3 w w De M 2 2 D D D 2 4 3 2 [f. * $ ~ 6@ w w + ee ' u' N' + ~~ c* e me 5 vo c me me me ne me nm me me Um um b y U, -MM e anJ w w 4J u.st =s es es =E w teJ W w 6 .au e.s I >M e* J n er e eu -M < a as ea aa 3., se s res M H M og >= C. U at >a 6 *= M em M M >= 8C 8E '6 8E - 5 8E 8E OE QE QE UE lE (1 E 4 M.e C W tri @ anJ a<a.O 8., n o I I. av n. - ae e;J av*
~~u. e se 80g a~~
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=
~~N me~~
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~~e O~~
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~~e J.~~
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~~C tg.J~~
.J e, O O O O O O O Oe n a e .s g e e e e e e O O MM 4 I e 8 4 I I I w a e w w w w w w w w = = gE W >= M E 8-se M at .J >=w 6O M P'd gowa se we es w >= c l 6 i e 0 0 1 1 6 e 'g W.s l I I O O 4 6 I I i O Q =J O .a w g er _wm <gwO e E M h.m w 4 h 4 O 7= E O. om m M N N as 4 M. Jn O 4D me se M e=e e=e N N N O 2 m
~~p..J = g e~~
~~t se e I e s he I f a f .J < < ct D 0 i M M 4 2 d w e llr E" w >- w gr 4 H U U tr = ED E V w Z O 6 EL 4 >- O O >O -w e-E3s~~
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6

4 e 8

I e 5

I
- s. s.. g 4E_ ud y e e e e w w e. w w w w w w w w w w .= m. a. m. 3t 2 o. o. o. o. o. o. o. o. o. o. o. o. 4 N nA J M
== nh N .e N ew i I d w e o o O o o o o o o o o o 5 L w M o e o o o o o O
== o Z*
o. $

o. 1 of

o. 8

o. t '
ot
o. t

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o. 1 G. - l

o. t o3
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~~t th~~
.a se tJ Z e mM e. C. > c 3 d >4 M Pe-g-.s o e x M se W. W LeJ l.) W ele L.J W taJ j-s.a w-e .a _a a. .r e o r a. .o s o a e n o w o w w-e e e e e e = e c Ne Ne e Ne a.o N e., m.v.,; .m .m ~yu me um me Ne Nm c .- ~ ~. M E., s. w w w w w e t m .s .a .w -w I._ .s .s. n <t a .e -ou >e ,e e ~ ~ 8r 8r 8= 8r 85 8 =e. 8, 5 85 _8, e. 85 8.s = 85 5 S.s a 'a
=
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o. f

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t
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==. EOw-N. N. t 3 e a p
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w w o o o o 8 4 i e I I o o Q =d .J w gawe 4 wO Mw E P. l e -E m .c o e - a e o in in in o o 4 nh o P M M .s (A.J = w e e e e e e e e e t t k D D 0 a e e J44h C w O WW w U w U N 2 M W W =Cua 4 t-O >O <w 3J Zh w-E o4=LC t
a 'O ' t. e' 0 N .= S M bE^ OnU C* O O O O O O O O O O W = = 0 9 4& am am a a= m en .= = .= M tJ a N se O M O 8's. O. O. O. O. O. O. O. a e O O. O M O O O O O e e. N M O e O .JOO 2* Oe a e i O O. O. O. O. O. O. M 4 p p p 3 e t 3 CL M4W
t

1 M r we O
N O O O O O O O a me eN me I M O I m a rJ ~ 4 E* M h. By 0 O. O. O. O. O. O. = .e gg g w w O O O O O O O O I w e I t e e t = w w w w w w w w = mm = .= = .= ,= ,= .= O 4 m f% M M m e.e O. m. O. 2 O. O. sa. D. as. e a w CD O O O M O O C+ O O O L w O M O O 4 O N O N O O. O. M. C. C. O. M. N. O. 1 ** O M 1 3 1 g I e i g 1 l t 2 J ew e t 4M e w (* O O O N O O O O O O O Q T. 2 e ** s's N b I @ O M O F** N O at 4 w O O O O* O. O. O. O. O. O O O. O. O. Q c f4 8'8 O O O O O O a I w e e e EN k w w w w w w w w w w 4 gr.=e M w Q rJ 2 U 4 C. C >/s en-e O I ke e P* Q"ee C Z 5 e M w. w w 2 4 2 s ~b M M N a M m o = u$ g N N O N N O 3 B*4 s = = s >= b @ a tJ N @M MM MO MO w W> c O N is rJ N .*>d MMQ b 2UU NO NM MM M eh MM M@ MM M n w w w w w w w I >M >= 0%w w w w es.mi J mJ ms as s es J es a md aJ M 4 ew > ><n as.J m#
.J
~~>OU 4 ee >e M M >e M M M M ke J U O o < Cr. O aO sO sM O sO aM OJ Og s c. . # e. aO a e. a e. J 4Uwm6 > = >~~
~~4 4~~
O O M O N> 0 e n J O4 Dama M 4 8 M"* M M em = OwMaa 4 .J. > 7 2 N 4 8'* f% Pm w O O. O. O. =.e me. e. O. m. o. a=* pa R *g x >e O O JU c O O O M O O O O 4 O Ub = O N M N N N es N O O O O O O. M. O. O. O. M M 2* O. M gWO l I I I
~~I I~~
~~I 4W I~~
1

I e l Q >4 e
wB we O o O N O O O O O O O l m M M N O N t f t J. y> MUC. 8 N N N O. O. N. N. O. O. O. O. O. 6@ Q g M s Js g Cn.J J w O O O O O O O O O D M we 4 e e I w e e e e a a e gC w w w w w w w w w w O b. >er 6-M 4 6U M M M N. N. Ct O w
~~t w~~
WO I I i 9 I 3 ws I I I 6 O O O O O t .O O.o J Gn .we WO mw M M 7= E C M.JO N N N 4 C D 4O N N O m m m e 4 P H.J = w N, e sw e 4 e e a e e s 6 D J44a 4 T J w s a O w O e g u E U w U N => w a F w 4 e. 6 CL O w O O >O 4w Ma PsJ EO 5 I CL wN ( MFr & >+ O4d @U w CL M > CL E Ow w itn
s' TABLE 3-1 P;GE 3-13 EtNID0tMENTAL RAOIOLOGICAL NOt31TORING PROGRAN SUNNARY NILLSTONE tRJCLE AR POutR STATI0tl. UflITS 1. 2 Ato 3 DOCKETS 50-245, 50-336 AND 50-423 JANUARY - DECE!' DER 1987 At34 LYSIS AND LOWER LINIT ALL INDICATOP LOC ATIOH_WITH HIGtEST AtP8JAL NE At3 C0t4Tp0L 8 DF MEDILM OR TOTAL tRJMOER OF LOCATIO**S LOCA110ts s. LOCATIO'83 PFN PATHWAY OF ANALYSES DETECTI0tt NEAN DISTAffCE HE Att NE Att (C) SAMPLED PEDF0DNEO ( L LO l (Al I R APtCE lt B I APU DIPECTID'1 ( D At!".E s t B I ( p AlfGE lt 0 3 HB-95 -0.01 LOC 8 36 0.00 -0.00 0 t -0.0 7 - 0.01) 3 NILES WSW (-0.01 - 0.01) (-0.01 - 0.018 RU-103 -0.00 LOC 8 31 0.00 -0.01-O t-0.01 - 0.01) 1.6 NILES ind t-0.01 - 0.011 1-0.01 - 0.01) RU-106 0.03 LOC 8 37C 0.04 0.04 0 t-0.09 - 0.331 3.5 NILES WSW E-0.05 - 0.091 t-0.05 - 0.09) AG-110M 0.05 LOC 8 32 0.12 -0.00 O t-0.01 - 0.38) 0 NILES N/A E 0.04 - 0.38) (-0.02 - 0.01) I-131 -0.01 LOC 8 37C 0.01
~~0. 0 t-O t-0.04 - 0.01) 3.5 MILES WSW~~
(-0.01 - 0.03) (-0.01 - 0.03) CS-134 0.13 -0.C0 LOC 8 37C 0.00 0.00 0 t-0.01 - 0.01) 3.5 MILES WSW t-0.01 - 0.023 (-0.01 - 0.02) CS-137 0.15 0.00 LOC 8 37C 0.00 0.00 0 (-0.01 - 0.01) 3.5 NILES WSW E-0.00 - 0.01) 1-0.00 - 0.013 RA-226 0.00 LOC 8 32 0.01 0.00 0 t-0.03 - 0.04) 0 NILES tt/A t-0.03 - 0.04) t-0.01 - 0.011 TH-228 0.02 LOC 8 32 0.04 0.03 0 t-0.03 - 0.201 0 MILES t3/A t-0.01 - 0.20) t 0.01 - 0.07) C LANS GEtLII 8. 0.01 LOC 8 29 0.03 9 (PCI/G) BE-7 t-0.04 - 0.091 0.4 NIlES PJHE t-3.04 - 0.09) ( . I K-40 2.4 LOC
~~38 2.7 O~~
I 1.9 - 3.51 1 NILES HW t I.9 - 3.5) t 3
p. e e
~~e 8~~
+ O.e a e ' Pi AEa ogu O O O O O O O O O O O O w .w O 4E i a em an a= = = = mm en = = m f'15 a C .J w O $.d n w . t . t - e e p . g . g - g . g . g . g . g . g m >= 4.J g ~< E. h1 ub e a me = r w w w w w w w w w w w w t m a en m a. m am m a ,a em O N M m M N me me d tJ ,e 2 O. O. O. O. O. O. O. O. O. O. O. O. sa w O O O O O O
~~m. O O~~
O O O O E = tJ O
== -e M O O O N e
== O. O. O. O. O. O. O. O. O. O 2* O. - t O 1 3 t f l - I 3 p g g 2 .J 4W t
M
= wg O D O O O O O O O O O O g E. I C
== 0
== N eJ O a== sO O O Q h O. O. O. O. O. O. O. O. O. O. O. O. n O at e w O O O O O O O O O O O O e e e a e s I 4 EN g w w w w w w w w w w w w a.M w U ** f J Z O d G tr e. O e L> 3 M m P= Q~gea. 5. as O Z M W W 6J W W W 2 2 2 2 2 E E E E 2 E E g84" -b '""w0 e' c' e' c' e' e-e" e' e' a e- ~ MM MM MM MM MM NM NO fJ M N@ MM NM td @ MMp SgU
==M M _w w w w w w w w w w - w w w M S *< M. e - - w M< o as as m.J ms as as m, as a s.e a s.e as M E >= O U et e= >= M M M >e M M M M 4 M a V e-a.O s r. .J r. s r. a. r. s r. .J OOe s s.* .J.e s-et U w m i .J .= O O O O C O > ** ;C d Q O tJ > g En e a s O *1 0.e = W Q 0 a. m em em e. em am an am a m m g w p ag 4.J>=> R C se tJ M M N s's d N se EUw O O. O. O. O. O. O. O. O. O. O. O. O. 3gg >g a mU 4 C O O O O O O O O O O O O 4 O Vb = M O se O M O O O O M
== O M M Z ** O. O. O. O. O. O. O. O. O. O. O. O. gWQ 1 8 4 t I t 8 I 1 4 8 I w b". pp 4w O O O O O O O O O O O O 24 w e. E se M O M M N M O e~ ae O N g-M O. O. O. O. O. O. O. O. O. O. O. O. O 5o as a O.J e w O O O O O O O O O O O O M M et a e e e I e e 4 4 e w w w w w w w w w w w w gE C >= 2 5-M M( .J 6- = 4U M M 4 M 4 es. tJ. tJ as 2Owa
== 8 8 8 8 8 8 w >. O I 2 Ws 8 O O O O O I t t t 6 i Q =# L.J .A w Q*e .w 4 wO E Mw M 4 O 6. ># nE me e e e O ki th IA O O
== M .et C m M e m 4 4 e e
== M
~~e M~~
MJ=w e e e i e s se s o o w u E v w u 4 0 .e s=<a a o w o m a ~ ~J 0 6 CL 4P O b>C 4w E3d 3 x. G H > E Q4* w&O E ^ v
.'a -e' . p ih se 4M sea OgU O O O O O O O O O O O W
~~a. w~~
'4 O E = a a a = = = m C 4 m m m m O. N. O. O. O. O. O. i e C O N O O O O O 8c N @ a O O O O M 0 6.e=4 W O. O. O. O. O. O. Ee . I e i e t . 8 i e i 0 4 t g l O O O O O O iah C. 5>E. IA. M 4 4 e me i me see N
~~4Ub<~~
~~O. u. o. O. O. O. a O = = O O O O O O I w I e i e s w w w w w w w w w m. = = m a = = = m 4~~
~~e 4~~
~~N 4 to to 2 O.~~
J.
~~O. O. N. P O. O. O. O. as a e W C O O O O O O O O O O 2*.- a O~~
~~e N~~
~~N O mie as M E O. O. O. O. O.~~
~~4. l O.~~
O O O. O. 4 3 1 t t s e i e 3 g p J 4W 4M e W L', O O O O O O O O O O {# E O O se se b am s.s me O tJ Q g O. O. M. O. O. O O. O. e O O s O O O O O O O, O, O, O, 4 4 = O w EN w w w w w w w w w eE O .M m HN Z 4 C amO a> Z e.4 m N e.s e x oe W a a a g.: <, -2; e a a a a s .s s s s ,s ,c c O-r N ~- N -5., N
~~WU M@~~
~~MH MO NO MM MM M@ M@ MM M@ MO m M M. MP 5 5p4w W W a .W . tsJ. W W W W W . teJ, . taJ . hJ, M. L M 4 w a a. .a M W >e e 4~~
~~6. >>~~
>e M M M ke M M M >OU L"a 8 *:0= 8= 8.o = 8= 8,o c= 8J M. 85 8c 8= 8= 85 gr q.. u w w. s , 80c .a M. aO .e ~ .a M. .s - .a C ao aC 4a .o P. >e 4 O O O O e O N h. .O,e E k On Oump 8 *4 h ""D my 4 4 N
== 4 N 4 N k U ase O O. O.. O. O. N. P. O. O s= O. O. .J g g >e = U 4 ** C O O O O O O O O O O 4 O UD O O -e me O M M O N w O O O O O O 4W O. O. M. C.
8

I e l e l
&WD ke M Z* O= 5 e t e t I 0 f 0 E' Q >4 w5 O O O O O O O O wg O O.e 8 ee O O M -e e O N e-u r. O O O O. O O. G. O. O. O. .M C e O e J .J a g R.J me w O O O O O O O O O O MM 4 e e e e I s e a w w w w w w w w w E ue k 5-we= M M4 =J > = = M M M .m.e 6U M N. me me ggWm
==. 1 I i 1 1 w >c 3 W.e O O 4 8 8 4 i O O O O Q Q =d .4 w QM 4 .we 4 WD MW D M >E 4 N 4 C O g kt .J n M M N ed 4 M 4Q me me N N N O m M Us.J = m 8 8 .J ( as a M M 4 2 f W e Cr Z Q' e e e e he i 4 8 W D Q W W L U k. U er > W W W R H w Z O ts. k W 4HO I O B-O WW =- r3a ed O '3 x h M> r eMO{ O =E
~~O tas b O g~~
.J w n ftD
e e' e '6 + e.4 6 m sea OOU O O O O O O O O O O O .Zw laJe .= = m = m m = = N O O O O we m se .= d m O. O. O. O. O. O. O. O. O. O. O. = Je C O O O O O O O O O O O O O O w. O O O O Ob O g e-. 2 a O. O O O O. O. O. O. O. O. 0 1 I 1 8 4 ta/ 8
I t

I e i e i
-- wc O O O O O O O O O O O. S c= r. O e-e- ee o eN O -e N O. O. O. O. O. O. O. O. O. O. = UQ g J w O O O O O O O O O O O .ie w w w w w w w w w a e 1 6 a e I a I I w a = = m m m m. m .m N N O 6h N N .e .=. N m 2 O. O. O. O. O. O. O. O. O. O. O. i q w O O O O O O O O O O O E O O O N me O O O .m N >= Za O. O. O O. O. O O O O O. O. =J 4W 9
6

I 9

I 3
l e i e i l I e sg = wg O O O O O O O O O O O. g z. O N e-O e-O O g e, O. O. O. O. O. O. O. O. O. O. O. n O, O, O, O, O, O, O, O, O. O O 4 m = rN = w w w w w w w w w e O .m w .= N G ko. M EmO I M 6A n Be8 M M 2 a z 2 a -b N N N M N 3.* M u = = = 2 = u us 2 =
~~e. 5 + a~~
~~~- w wn n N N N + N N n n + n B no no me no no no no no no no no -- Mme. s _ u., w.~~
~~e. w w~~
w w w w w w w w w w M m < .a .a M - a. >OU at > p-M M M M M o.e e M M M M 8r 85 8r 8e O 8= gr gr 8r 85 gr 8r w ** 8 **o r n < a,n. s s 8Og s o. aO .4 O , m. in. a m. .a O .J m. s aO ,O -u. >= M F 4 M O m M O O N> Oe 9 G OM O m in a. MM O W M et a a a a a a a a 4w>7 N O m N N O N M O. O. O. O. O. O. O. O. O. O. O. .O. g M tat a x .8
~~4 C~~
~~O O O O O O O O O O O 4 Ub = ee O O C, O me O~~
~~3 WO MM 2a O.~~
~~O. O. O. O O. O. O. O. Oe t O ~ Q>~~
~~( w 1~~
~~l I e 1 l e i t 1 1 I w B. O O O O = wg O. O O O O Oe O. i - m we c. 4 i N i N N O O. O. O. O.~~
e.
O. O. O. O. C. O. M 4 .a .J g k.4 J w O O O O O O O O O O O MM 4 t a e e e e e e e a a gE w w w w = = = w w w aw >= M l C t M e< l a >= w 6U e M 4A R O t.J ~ N
==. I 1 M >0 e 1 i I i 4 I 3 mw O 8 8 e i t e O O t 4 O.J O& w l gk l A wo l 4 WO Mw E o >=J c .O 4 A e O E m e IA th IA O O e m e N N M 4O we es as O..J = m .m og me N N e s e e e p e e 6 e t .d 4 4 4 2 R O D D O t e o 4 2 4 >= w
~~4 N~~
Z k k 4 >4 4.J U k >= ~ O 6 EL N 0= O E>O dw E 3.d l DIE >< >- r 04* i I W Ek th I E 1 I
e 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 of Deviations by 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% probability with a 5% 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 (-A A t) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) sb s the standard deviation of the background counting rate or of i
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 a is the elapsed time between sample collection (or end oi the sample collection period) and time of counting it should be recognized that LLD is defined as a priori (before the fact) limit representing the capability of a measuremer.t 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 HASI.,"letter b the determination of mean.y Leo B. Higginbotham). Negative values were used in C. Nonroutine reported measurements (NRM's). These are results of samples that exceed the report levels of Table E-2 of the Radiological Effluent Monitoring Manual. 3 17
FOOTNOTES (Cent'd) D. First number is the number of indicator measurements, the second is the number of control measurements. 3 E. Assuming 270 m / paper 3 F. Assuming 1080 rn + G. LLD fo leafy vegetables. H. Reduce ;LD by a factor of two if the fractional beta for the sample exceeds 15 pCi/l. I. LLD from the end of the sample period. s i I l 3-18
1 3.2 Datn Tablis 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 valid pieces of data. For the purposes of this report,in order to indicate any background biases, all the valid data are presented. In instanceswhere zeroes are hsted 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. Seawater

15. Bottom Sediment l

16. Aquatic Flora l

17. Fin Fish

18. Mussels i

19. Oysters

20. Clams

21. Scallops 22.
~~Lobster (and Crabs) l~~
~~Since there were no samples taken for these types there are no tables for l~~
them. 3 19
s a. MILLSTONE POINT 1987 Tt3LE 1 PAGE 3-23 1 MONTHLY GAft1A EXPOSURE RATE (UR/HRI a u L0 CATIONS PERIOD 1 2 3 4 5 6 7 8 9 10 11 JAN 87 A 8.7 B 13.3 8.6 8.8 7.5 9.2 10.9 13.5 9.5 9.1 8.4 FE8 87 8.3 13.2 8.4 8.8 7.3 9.0 10.4 13.1 9.2 8.8 7.6 MAR 87 9.3 14.0 8.8 9.2 7.3 9.3 11.0 14.2 9.9 ?.2 8.6 APR 87 8.6 12.8 8.3 9.0 7.3 9.4 10.8 13.2 9.3 8.8 7.8 MAY 87 8.8 13.4 8.4 8.2 7.2 8.8 10.7 13.9 9.6 9.1 8.3 JUN 87 9.6 13.3 8.8 9.2 6.5 9.4 11.1 13.4 9.4 9.3 8.5 JUL 87 9.5 13.3 8.9 9.6 5.8 8.9 11.0 13.4 9.4 9.7 9.2 LUG 87 9.8 11.7 9.2 9.5 6.6 9.7 11.7 14.1 9.6 9.6 9.0 D SEP 87 9.0 13.2 8.3 9.0 7.2 8.6 10.6 13.5 9.5 9.1 9.0 OCT 87 9.4 13.9 8.9 9.6 7.7 9.4 11.5 14.0 9.S 9.4 9.0 POV 8? 9.1 13.0 8.4 9.1 7.0 8.8 10.4 13.5 9.4 9.0 8.9 DEC 87 9.2 13.5 8.8 9.4 7.6 9.4 11.0 14.0 9.5 9.1 8.7 PERIOD 12C 13C 14C 15C 16C 27 50X 54X 55X JAN 87 7.7 8.4 10.5 8.4 7.8 7.8 6.2 8.5 7.6 FE8 87 7.5 8.7 9.2 8.8 7.6 8.2 6.5 9.0 7.4 MAR 87 8.3 C 9.! 11.6 9.1 8.2 8.2 6.3 8.9 7.8 LPR 87 7.6 9.3 11.5 8.3 7.5 8.3 6.6 9.1 7.5 MAY 87 8.1 8.6 11.3 8.8 8.1 7.7 6.5 8.7 7.5 JUN 87 8.2 9.6 11.7 9.8 8.4 8.2 7.0 9.6 7.9 JUL 87 8.6 9.1 11.8 9.5 8.4 7.9 6.8 9.4' 8.2 LUG 87 8.6 10.0 12.1 10.4 8.9 8.6 7.1 9.9 8.1 SEP 87 7.9 8.8 11.2 8.9 8.1 7.9 6.3 8.8 7.5 OCT 87 8.2 9.8 11.9 9.9 8.6 8.8 7.3 9.8 7.9 tCV 87 7.9 8.8 11.3 8.7 8.0 7.9 6.2 8.7 7.5 OEC 87 8.3 9.3 11.4 9.5 8.4 8.6 7.0 9.4 7.7 M A: NOT ACTUAL DATES. TLD'S ADE CHAtGED HEAR THE EPO OF THE teITH. B: RESULTS ARE +/- 10%. C: TLD'S WERE NOT DEDOSED PROIR TO PLACEMEtiT IN FIELO. ESTIMATE BASED ON BACKGROUtO COCRECTION. D: SItCLE TLD RESULT. COMPARES F7VORABLY WIT'1 Q. A. TLD RESULT OF 9.0 UR/HR. SEC0tU TLD READItG WAS 13.8 UR/HR - SUSPECTED AS Att OUTLIER.
e n'*+e s e S me
~~e N to 5 8 N NNNN NNNNN NNNN N N N.=s N N N tJ N N~~
1 O f. ts O OOOO OOOOO OOOO OOOO OOOOO \\, O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. em wOOOO OOOO 90000 0000 0000 60000 tJ 4 O h.m.= MNN== Ms@ N 4 @ M.M N M @GN4 eJ M N. 4 @C N
N e4 N N N N N me =*
.-e. .e .e== . = = e4 .= O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. OOOO OOOO OOOOO OOOO OOOO OOOOO a N N N fJ tJNNN NNNNN NNNN NNNN MNMNN 0 OOOO OOOO OOOOO OOOO OOOO OOOOO N O O. O O. O. O O. O. O O O. O. O. O. O. O. O. O O O. O. O. O. O. O. O. e e e e e e e e g wCOOO OOOO 90000 0000 OO.O 9000O O.N. . O.e e .. N N== m._N N. N =* m ee to N tJ ta 94 ta== N = =* ee =e .=== N eo N m eJ e4 =e O O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. e 'f GOOO OOOO OOOOO OOOO OOOO OOOOO U O CU
~~me. e se~~
== me.= FJ me N
== me
~~a me=~~
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~ .. ~- w ~ a::w w--.h w -mrc ~-- n:o ., a y + MILLSTONE POINT 1967 TABLE 7 PAGE 3-15 DAIRY MILK (FCI/L). 3 COLLECTION 2 LOCATION OATE SR-89 SR-90 I-131 CS-134 'CS-137 BA-140 LA-148, 1+/-) (+/-l t+/-l t+/-l (+/-) (+/-l 1+/-l 19 01/13/87 0.8 1.0 2.8 0.3 -0.15 0.13 1.7 2.4 5.3 2.7 2 9 -3.6 2.7 19 02/10/87 0.9 1.1 5.2 0.4 0.18 0.13 0.5 2.5 8.1 2.8 8 20 -2.7. 5.8 19 03/10/87 0.8 0.8 4.0 0.3 0.01 0.10 1.3 2.4 10.5 2.9 3 11 ' 2.4 3.5-19 04/07/87 -0.1 0.8 3.7 0.3 0.12 0.12 -0.1 2.4 . 3. 9 2.6 -12 19 1.4 5.6 19 05/11/87 0.3 0.7 3.3 0.3 -0.04 0.16' -0.5 2.4 7.5 2.8 -6 15 0.0 4.4 19 06/08/87 0.2 0.8 4.8 0.3 0.02 0.11 -1.0 3.5 14.9 4.5 -11 18 1.6 5.6 19 07/06/87 0.7 1.5 6.8 0.3 0.01 0.12 1.4 2.5 22.1 3.3 4 24 1.3 6.7 - 19 08/03/87 0.6 0.8 4.3 0.3 0.13 0.14 0.1 2.3 30.7 3.4 -14 19 -2.9 5.5 19 09/08/87 0.5 1.2 6.1 0.3 0.05 0.13 0.5 2.6 17.0 3.1 -17 26 2.7 7.7 19 10/05/87 -0.3 2.6 6.4 0.3 -0.01 0.12 0.6 2.5 11.1 3.0 19 22 2.0 6.2 19 11/09/87 0.5 2.0 6.1 0.4 -0.05 0.22 -0.5 2.5 5.7 2.9 -2 27 -1.1 7.6 19 12/07/87 8 1.1 1.6 5.0 0.4 -0.01 0.12 -0.2 2.6 7.4 3.0 0 15 0.0 3.9 l 20 01/13/87 1.2 1.3 2.6 0.3 -0.21 0.18 1.6 2.3 5.6 2.6 1 9 1.1 2.6 20 02/10/87 -0.0 0.9 1.9 0.3 0.02 0.14 3.8 2.6 7.7 2.8 4 13 0.4 4.0 'l 20 03/10/87 -0.2 0.8 2.2 0.2 -0.03 0.13 0.1 2.5 3.9 2.9 2 9 -1.5 2.7 20 04/07/87 -0.3 0.7 2.3 0.3 0.01 0.14 2.5 2.5 6.2 2.9 8 19 -2.3 6.0 i 20 05/11/87 0.3 0.5 1.6 0.3 -S.03 0.21 0.2 2.5 3.4 2.7 -3 14 2.5 4.1 l 20 06/09/87 0.6 0.7 2.0 0.2 -0.08 0.12 0.2 3.9 0.6 4.1 -5 20 0.4 6.7 20 07/07/87 1.0 0.8 2.5 0.2 -0.02 0.13 0.5 2.5 1.1 2.6 10 26 -4.9 7.3 20 08/03/87 0.1 0.6 1.8 0.2 0.00 0.12 -0.3 2.5 4.4 2.7 -3 19 -2.9 5.7 20 09/09/87 0.1 0.9 2.6 0.3 -0.02 0.11 1.4 2.6 3.5 2.7 18 27 5.7 8.0 20 10/05/87 -1.0 1.2 2.7 0.4 -0.03 0.12 0.6 2.5 2.9 2.8 13 23 4.4 6.9 1 20 11/09/87 0.1 0.8 2.8 0.3 0.00 0.22 1.1 2.5 2.6 2.8 12 16 1.5 '4.6 20 17/07/87 0.2 1.6 1.7 0.4 0.03 0.14 -1.7 2.5 1.5 2.7 -2 14 1.5 4.5 21 01/13/87 1.0 1.2 6.4 0.3 0.13 0.17 2.4 2.3 11.0 2.7 3 9 -0.6 2.7 21 02/10/87 A -0.1 0.9 4.7 0.3 -0.01 0.11 0.7 2.4 2.5 2.6 -4 19 1.6 6.1 21 03/10/87 0.4 0.9 4.3 0.3 -0.01 0.10 0.5 2.5 0.8 2.7 4 12 -3.4 3.4 21 04/07/87 0.6 0.8 4.9 0.3 0.07 0.12 2.1 2.5 4.5 2.8 -1 20 1.1 6.1 21 05/11/87 0.0 0.6 3.6 0.3 0.01 0.14 1.7 2.4 4.5 2.7 7 15 3.6 4.3 1 21 06/08/87 0.2 1.0 7.5 0.3 0.03 0.12 1.5 2.5 14.0 3.0 8 13 0.7 3.7 21 07/06/87 0.8 1.2 6.2 0.3 -0.01 0.12 0.4 2.6 12.7 3.1 -10 28 -2.8 8.2 21 08/03/87 0.8 0.9 7.3 0.3 0.04 0.12 -0.6 2.4 9.4 2.9 6 21 -5.8 5.9 21 09/08/87 2.8 4.6 8.3 0.5 -0.04 0.11 1.7 2.6 7.5 3.0 16 29 1.6 8.6 21 10/05/87 0.5 0.8 6.8 0.3 -0.02 0.13 0.0 2.6 5.0 2.9 8 27 -3.4 7.8 21 11/09/87 -0.5 1.0 8.1 0.4 0.02 0.24 -0.7 2.6 5.2 2.7 -10 28 4.3 9.1 21 12/07/87 8 0.0 2.6 3.1 0.3 0.02 0.12 0.2 2.5 -2.6 2.6 9 15 2.2 4.6 A: NEW SAMPLE LOCATION. 8: RESAMPLED ON 12/21/87 TO ANALYZE FOR I-131 DUE TO CONTAt11HATION OF THE Op1GINALS. 1 ( ' 1 - l
e-MILLSTONE POINT 1987 TABLE 7 PAGE 3-3) DAlpY NILK EPCI/LI COLLECTIDH LOCATION DATE SR-89 SD-90 I-131 CS-134 CS 137 BA-140 LA 140 (+/-) (*/-l to/-l (*/-p (*/-l to/-l (*/-l 22C 01/13/87 0.6 1.0 4.4 0.3 -0.18 0.20 0.6 2.4 4.8 2.6 -5 9 -1.9 2.4 22C 02/10/87 0.2 0.8 2.8 0.3 0.06 0.15 3.5 2.5 6.5 2.7 3 13 -1.2 3.9 32C 03/10/87 0.4 1.0 2.7 0.3 -0.04 0.10 1.2 2.4 6.2 2.7 -2 9 -1.0 2.5 22C 04/07/87 0.8 0.9 3.4 0.3 0.00 0.12 1.4 2.5 5.4 2.7 -11 IS -1.1 5.6 22C 05/11/87 0.2 0.6 3.1 0.3 -0.02 0.20 0.1 2.5 4.3 2.7 -2 14 1.9 4.1 2 ?C 06/08/87 0.1 1.2 4.4 0.4 0.00 0.*2 0.3 2.5 5.0 2.7 0 12 1.3 3.7 22 C 07/06/87 0.5 0.7 3.6 0.3 0.03 0.10 0.4 2.6 6.2 3.0 -5 23 7.0 7.6 2 7.; 08/03/87 -0.1 0.7 3.7 0.2 0.01 0.12 -0.2 2.5 5.1 2.8 2 19 -3.6 5.3 22C 09/08/87 0.0 0.9 3.3 0.3 0.07 0.12 1.7 2.6 1.3 2.8 -11 26 6.7 8.0 22d 10/05/87 0.5 2.2 3.4 0.3 -0.04 0.!! 1.2 2.6 3.9 2.8 3 28 -0.6 8.6 22Ci !!/09/87 0.1 1.0 3.2 0.3 0.00 0.25 0.6 2.6 2.9 2.8 -15 16 2.7 4.6 22C3 12/07/87 -0.3 1.2 4.3 0.4 0.20 0.15 .'. 0 2.6 2.3 2.9 -8 14 1.8 4.4 \\ i 1 '\\ 1 1\\ 5 1 s \\ \\ A: NLW SAMPLE LOCATIDH B: RESAMPLED CH 12/21/t TO ANALYZE F00 I-131 DUC TO COPITAHINATIOtt O THE OPIGIHALS. \\ t
.u . ([ =-.- e.; '. _$* * )M ~ 1 V }4 i GOAT'S MILK PACE 3-40 ~+ TA8LE 6 NILLSTONE POINT 1987 , 14 ' I PC1/L I ^ l J COLLECTION LOCATION DATE SR-89 SR-90 I-131 CS-134 C5-137 EA-140 LA-146- ] . - _ = _ _ = = - _ _ _ _ be (*/-) (+/-) (+/-p (+/-l E+/-p (+/-) is/-) i 23 04/13/87 A -0.3 0.9 13.0 0.5 0.00 0.10 0.0 2.6 17.9 3.2 -1 le 1.9 2.9 ) 23 04/27/87 -0.9 3.0 14.3 0.5 0.02 0.12 -0.9 2.3 17.2 3.0 -1 9 144 2.7 23 05/11/87 -0.8 0.8 9.3 0.3 0.01 0.17 -0.2 2.6 23.0 3.5 7 21 6.0 6.0 J> 23 05/26/87 2.4 2.4 24.9 0.6 0.07 0.18 0.0 2.4 55.2 4.3 r 9 1.3 2.8 1 23 06/09/87 0.1 2.1 28.2 0.6 0.06 0.!! 0.4 2.4 61.2 4.2 4 10 .-6.9 2.5 23 06/22/87 0.1 1.4 22.1 0.5 0.16 0.14 -0.2 3.0 86.1 5.2 1 19 -2.1 5.1 23 07/06/87 -0.8 1.6 27.2 0.6 0.12 0.12 0.3 3.0 51.7 4.5 -5 35 C -4.1 9.9 23 07/20/87 -0.3 2.4 21.7 0.5 0.04 0.19 0.4 3.4 50.7 4.9 30 30 1.6 9.0 23 08/03/87 0.6 4.9 28.9 0.7 0.06 0.14 -0.6 2.7 49.2 4.2 6 25 10.6 7.6 I 23 08/17/87 1.8 3.6 38.6 0.8 0.09 0.14 -0.1 3.0 112.1 5.9 17 24 3.1 7.1 23 09/08/87 -1.7 2.3 17.1 0.5 -0.04 0.14 -0.3 2.6 33.0 3.7 -3 13 2.4 3.6 23 09/22/87 -0.2 1.3 17.6 0.5 0.11 0.20 -0.1 2.6 38.9 3.8 -2 13 3.1 3.5 23 10/05/87 F -1.0 1.2 10.9 0.4 0.02 0.14 1.0 2.5 54.0 4.2 -3 15 1.5 4.0 I' 24C 04/27/87 8 -0.6 1.3 3.7 0.3 -0.03 0.08 0.4 3.5 6.9 3.9 0 14 3.8 4.2 24C 05/13/87 0.3 0.6 2.0 0.3 -0.05 0.19 3.2 3.0 5.8 3.1 -6 20 2.1 6.0 24C 05/27/87 -0.3 0.9 5.0 0.3 0.07 0.15 1.6 2.4 3.9 2.6 3 to 1.5 3.3 24C 06/08/87 -0.3 0.6 2.7 0.3 -0.02 0.10 1.7 2.5 4.1 2.8 -5 9 I.6 2.6 24C 06/22/87 -0.3 0.8 4.3 0.3 -0.06 0.11 1.3 2.5 3.8 2.8 -5 15 2.2 4.2 24C 37/06/87 0.5 0.8 3.8 0.3 0.10 0.14 -1.6 3.2 8.8 3.6 7 36 C 1.0 11.0 D 24C 07/20/87 0.3 0.6 2.4 0.2 0.04 0.21 2.7 3.1 5.8 3.5 -20 28 2.7 8.3 24C 08/03/87 0.4 0.9 2.5 0.4 0.11 0.13 -0.8 2.6 5.7 2.9 -6 25 2.2 7.6 24C 08/17/87 0.8 0.7 1.8 0.2 -0.05 0.10 1.1 2.8 6.5 3.1 19 23 2.7 6.5 j 24C 09/08/87 -0.3 1.4 3.8 0.3 0.01 0.13 2.1 2.6 4.5 2.8 1 13 2.4 3.8 l 24C 09/21/87 -0.5 0.8 5.9 0.4 -0.05 0.20 -1.7 2.7 9.1 3.0 -2 14 0.3 4.2 24C 10/05/87 -0.4 1.6 5.2 0.5 -0.06 0.15 -1.3 2.6 8.6 3.0 1 18 2.6 5.5 l 24C 10/26/87 0.2 0.8 3.1 0.3 -0.18 0.37 -0.7 2.5 4.3 2.8 -1 10 1.7 3.3 24C 11/09/87 F 1.3 1.8 2.0 0.2 0.13 0.43 E 0.4 3.6 3.5 4.1 9 13 -0.1 3.9 t q D t A: MILK WAS NOT AVAILABLE IN JANUARY. FEBRUARY Ate MARCH AT LOCATIONS f23) AND ( 24C ). B: NILK WAS ICT AVAILABLF. AT LO"ATION 824Cl Ita E ARLY APRIL. C: 84-140 ftL OF 30 MAS tl0T NET DUE TO EQU1Ft1CNT BREAF0024 DELAVItG COUNT. 0: LA-140 t10L OF 10 NAS TOT t1ET DUE TO EQUIf71EtiT EREAADouH OELAYIfG COUNT. E: 1-131 NDL OF 0.4 WAS PCT NET DUE TO SMALL SAMPLE VOLUME. F: NILK NAS NOT AVAILABLE LATE IN THE YEAR AT BOTH SAMPLItG LOCATIONS.
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MILLSTONE POINT 1987 TJ.BLE 14 PAGE 3-46 SEA WLTER (FCI/L) COLLECTION LOCATION DATE K-40 CR-51 mi-54 CO-58 FE-59 CO-60 (+/-l (+/-) (+/-l (+/-) (+/-I ? 32 01/30/87 393 59 -33 35 0.4 2.5 -0.1 2.8 -1.7 8.4 -0.8 2.7 32 04/25/87 254 60 10 40 0.1 2.5 -1.1 3.0 8.3 9.1 0.1 2.7 32 07/24/87 254 60 -27 43 -0.9 2.5 -0.2 3.2 -0.4 9.5 1.5 2.7 32 10/03/87 251 61 -16 39 1.5 2.5 -0.5 3.0 1.0 9.2 0.2 2.8 37C 01/30/87 205 50 -10 33-1.2 2.2 -1.5 2.6 2.5 7.7 2.2 2.6 37C 04/25/87 199 58 -36 41 0.8 2.4 0.3 3.1 -1.5 9.0 -0.7 2.8 37C 07/24/87 249 59 -38 42 0.7 2.5 -0.3 3.1 -1.1 9.5 -2.4 2.7 37C 10/23/87 245 59 30 41 1.3 2.4 0.3 3.1 0.6 9.4 -0.1-2.7 COLLECTION LOCATION DATE ZH-65 ZR-95 NB-95 RU-103 RU-106 I-131 (+/-) (+/-) (+/-) (+/-I (+/-l (+/-) I 32 01/30/87 2.3 6.0 2.7 5.2 0.9 3.8 0.4 3.6 -7 22 -3 24 32 04/25/87 -0.3 5.7 3.8 5.7 3.6 4.3 1.1 3.8 1 22 4 36 32 07/24/87 -1.3 6.1 0.8 5.7 3.8 4.5 2.9 4.1 1 22 10 47 32 10/23/87 5.1 5.9 -0.5 5.6 2.5 4.2 -2.2 3.8 3 23 28 34 37C 01/30/87 3.6 5.3 2.4 4.9 -0.3 3.4 -1.5 3.2 13 20 7 22 37C 04/25/87 0.7 6.1 -3.0 5.6 0.3 4.4 -0.7 4.0 3 22 -19 39 37C 07/24/87 5.3 5.8 -1.4 5.6 1.5 4.2 -1.5 4.0 -6 23 -17. 42 37C 10/23/87 -0.1 5.7 -2.3 5.6 2.6 4.4 -4.1 4.0 19 22 12 39 i e ~
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~ PtILLSTONE POINT 1987 TLBLE 14 PAGE 3-N SEA WATER (I'CI/L) COLLECTION LOCATION DATE CS-134 CS-137 BA-140 LA-140 RA-226 TM-228 (+/-l (+/-1 (+/-) (+/-l (+/-l (+/-l 32 01/30/87 -0.3 2.3 -0.2 2.4 -3 36 1 4 -6.1 4.9 -10.4 6.8 32 04/25/87 0.8 2.4 -1.2 2.5 -2 48 7 15 3.4 5.0 - 0.8 6.8 32 07/24/87 1.0 2.4 -2.0 2.4 1 56 11 17 1.5 5.0 -0.2 6.8 32 10/23/87 -0.3 2.4 -0.5 2.5 -2 46 -4 13 3.9 5.1 3.3 6.9 37C 01/30/87 -0.9 2.2 -0.5 2.4 1 33 1 11 -0.8 4.7 7.0 6.5 37C 04/25/87 -0.6 2.4 -0.7 2.5 -15 52 -5 16 1.1 4.9 -0.5 7.0 37C 07/24/87 0.1 2.4 0.7 2.5 4 53 -2 16 -3.5 5.0 -3.7 7.1 37C 10/23/87 0.1 2.4 -0.4 2.5 19 50 2 15 3.5 5.1 0.8 7.1 COLLECTION LOCATION DATE H-3 BETA FR I BETA FR II BETA FR III BETA FR IV (+/-) (+/-) i+/-) (+/-) (+/-) i 32 01/30/87 180 90 0.38 0.41 1.34 q.55 0.40 0.42 0.10 0.19 32 04/25/87 410 90 -0.09 0.13 1.29 c.74 -0.42 0.47 0.08 0.35 32 07/24/87 46 73 -0.23 0.35 3.58 0.98 0.27 0.19 0.01 0.11 32 10/23/87 1000 100 -0.45 0.32 5.03 0.e6 0.63 0.36 0.09 0.25 37C 01/30/87 18 64 0.03 0.35 4.09 0.79 0.09 0.41 0.19 0.21 37C 04/25/87 110 60 -0.19 0.11 0.73 0.96 0.31 0.33 0.00 0.48 - 37C 07/24/87 32 69 0.40 0.35 1.32 0.88 0.64 0.18 C.03 0.14 37C 10/23/87 150 50 -0.16 0.33 1.73 0.68 0.50 0.32 0.14 0.27 5 3.
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3 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 radioactivity could be detected and compared the results with previous environmental surveillance data. Few impacts of the plant operation on the environmentwere 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 vegetation 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) The gamma exposure rate is determined from the integrated exposure measured over a time period of approximately one month using CaF,(Mn) thermolumines-cent dosimeters. These glass bulb dosimeters are subject to inherent self-irradiation which has been experimentally measured for each dosimeter. Consequently, the results, shown in Table 1 have been adjusted for self irradiation effects. The range of this correction is 0.4 uR/hr to 1.7 uR/hr, with a mean of approximately 1 UR/hr. The exposure rate measurements exhibit the same trends as those since 1978. These measurements demonstrate the general variations in natural background radiation teetween the various on-site and off site locations and include gamma exposure from all sources including cosmic, terrestrial, and artificial radioactivity. In particular, the Weather Shack (location 02) experiences higher exposure rates due to its proximity to granite beds while the Ledyard location (location 14C) experiences relatively higher background exposure rates than the other control locations at Mystic, Montville, and Old Lyme (locations 13C, TSC, and 16C). During any Unit 1 shutdown, a small decrease in exposure levels is normally observed at on site locations (Weather Shack (02), Navy Laboratory (05), Fox island (7), Millstone Environmental Laboratory (08), and Bay Point Beach (09)). However, during 1987 this decrease is only apparent at location (05). During Unit 1 operation, a small increase in exposure rates is caused by the direct exposure pathway of "skyshine" (i.e., scattered radiation from nitrogen-16 decay in the turbine; this pathway is unique to boiling water reactors). This direct exposure pathway decreases rapidly with distance from the turbine building, to levels that are virtually undetectable at the off-site locations. Special surveys performed during 1980, and this year, with a high pressure ion chamber support this premise. The latest surveys show that the 1980 study predicted exposures that were a factor of two conservative. The maximum off site direct exposure due to Unit 1 was determined to be 0.1 uR/hr. The dose consequence attributable to direct dose is discussed in Section 5.0. With the installation of the augmented off-gas treatment system in May of 1978, the plant gaseous effluents decreased significantly to levels that are essentially undetectable by TLD's, even at the on-site monitoring stations. The ony appreciable effect, aside from that of skyshine, seen in the TLD data is that attributable to the variation in the background radiation which has beeri noted as being consistent with previous years. 41
Air Particulates and lodine (Tabla 2,3,4 A L cnd 5) Air is continuously sampled at seven inner ring and two outer ring locations by passing it through glass fiber particulate filters. These are collected weekly and analyzed for gross beta radioactivity. Results are shown on Figure 4-1 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 measureat'le. Charcoal cartridges are included at all of the Radiological Effluent Monitor:ng Manual required air particulate stations for the collection of atmosaheric iodine. These cartridges are analyzed on a peeky basis for 1-131. This year tae data faited to show the numerous positive values seen at both indicator and control locaticsns attributable to Ra-226 interference on a Nat detector. Starting in 1987, all air iodine cartridges are analyzed on a Geli detector. The resolving capability of ti e Geli detector allows for the separation of the I-131 gamma peak at 36S kev from the Ra-226 daughter gamma peak at 352 kev, which when measured on a Na' detector appears as a single peak. No detectable levels of 1-131 were seen in the 1987 charcoal samples. Thisis confirmed by the absence of I-31 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 air particulate samples that are utilized for the weekly gross beta analyses are composited monthly and analyzed for gamma emitting isotopes. The results, as shown in Tables 4A-4L, 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 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 1982-1986. 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 controllocations and no measurable Sr-89, there are no indications of any plant effects. Soil (Table 6) Soil samples are special samples not required by the Radiological Effluent Monitoring Manual (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. Cow Milk (Table 7) The most sensitive indicator of fission product existence in the terrestrial environment is usually the analysis of milk samples. This in combination with the fact that milk is a widely consumed food results in this pathway being the most critical. This pathway also shows significant amounts of weapons testing fallout. Therefore, this media should be carefully evaluated when trying to determine what are the actual plant effects. 4-2
s. Routina levels of Sr-90 and Cs-137 similar to those of the past were observed. The range of results were 1.6 to 8.3 pCi/l and 0 to 30.7 pCi/l for Sr 90 and Cs-137, respectively. Detailed analysis of this data has concluded that these levels are from weapons testing fallout and are not plant related (see Section 6.0 for details to this argument). In December,'two samples suffered contamination with I-131. Glassware in the laboratory was not sufficiently cleaned after processing control samples of milk spiked with I 131. Milk was resampled at the locations of the respective . contaminated samples. The results of the I-131 analyses on these samples show no detectable 1-131. 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 Goat Milk (Table B) Goat milk samples can be a more sensitive indicator of fission products in the terrestrial environment than cow milk samples. This is dependent on a number of parameters, including: metabolism of these animals, feeding habits, and feed type. Samples taken during weapons testing periods have demonstrated higher uptake of fresh fallout nuclides (Sr-89 and 1-131) at the indicator goat location. This trend helps to explain the usual, higher than normal Sr-90 and Cs-137 concentrations at the indicator location as compared to the control location. Positive indications of Sr-89 and Cs-134 were not observed. Therefore, as with cow milk, detailed analysis of the data has concluded that the Sr-90 and Cs-137 levels are from weapons testing fallout (see Section 6.0 for more details). No plant related 1-131 was seen in this media. For the last three years, no detectable levels of I-131 have been seen in goat milk samples except for the period immediately following 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 either goat location. Pasture grass was also unavailable in late fall, November - December, to substitute for goat milk not available. The results are consistent with previous year's results. No plant effects are seen in this media. Well Water (Table 10) Well water samples are not required by the REMM. Data from 1973-1985 has shown the lack of detectable stition activity in this media. Therefore, the sampling of well water has been discontinued. In the event of widespread plant contamination, these samnles would be collected. Reservoir Water (Tabfe f f) 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. 43 L
1 Fruits and Veaetables (Tabla 12) Consistent with past years, this media did not show any plant effects. Levels remain similar to those observed for the past ten years. Broad Leaf Veaetation (Table 13) Consistent with past years, this media did not show any plant effects. Concentrations of Sr 90 and Cs-137 in these samples existed at levels comparable to past years and is due to fallout. Seawater (Table 14) These quarterly composites of weekly grab samples show similar results to that of the previous ten years..Two of the four indicator samples show that levels of H-3 are slightly elevated near the discharge area (location 32). Thus, station effects are similar to those of past years. Due to the decay characteristics of H-3, the dose consequence of the observed H-3 concentrations is negligible (see Section 5.0 for a discussion of the maximum dose consequences). The values for the Beta Fractions show no significant differences between indicator and control stations, therefore, the observance of H-3 was the only p hifect. Bottom Sediment (Table 15) As in the past, this media did not exhibit any plant related activity. Levels are consistent with arevious observations. Cs-137 was detected at a control location. However, the absence of Cs-134 in this sample and the relative distance and direction of this sample location indicate that this Cs-137 is not plant related. The levels of Cs-137 are comparable to river water sediment (i.e. Connecticut Yankee An n ual Radiological En vironmen tal Op era ting Report). Aquatic Flora (Table 16) Thare were indications of plant effluents in this media. Mn-54, Co-58 and Co-60 were observed at levels higher than those of the last four years. Except for Co-58 these levels are well below those seen in 1975-1976. Sampling of tnis media provides useful information because it is very sensitive to plant discharges. However, since seaweed in this area is not consumed, other media are utilized in the determination of dose consequences (e.g., see Shellfish and fish resulu). Fish Flounde (Table 17A) Plant related Co-60 is shown in one sample from the area within FJO feet of the discharge (location 32). The remaining activity in Flounder is the srme as that seen for the past eleven years. The plant effects on Fish are discussed ir the next section due to the higher levels observed in the "bottom feeder" fish. Fish - Other (Table 17B) Except for the quarry location, these fish samples enibited data similar to that in previous years. For the off-site samples, the only detectable activity seen above the MDL was K 40. However, as in previous years plant related activity was detected in the quarry samples (location 40X). Positive values of Mn44. Co-58, Co-60 and Ag-110m were observed. The quarry location is not accessible to members of the general public and with the dilution of the Long Island Sound, the levels of radioactivity generally become undetectable in these samples outside of the quarry. This can be seen by the difference in Co 60 leveh between the sample from the quarry in April and the 44
.s t.;>. flounder sampled in Apriljust outside the quarry (within 500 feet of the discharge). The differenceis geaterthan a factor of three' Usinc)lution factor of 3 determined the concentrations measured 3-the quarry and diluting them by the near field di for quarry discharges into the Sound, doses to the maximum individual can be calculated. See Section 5.0 for these results. Mussels (Table 78) GeLi analyses indicated the presence of plant related Co 58 and Co 60 at Two Tree Island (location 28), Niantic Shoals (location 31) and the area within 500 feet of the discharge (location 32). The only other detectable activity observed in mussels consisted of naturally occuring K-40. The dose consequence of the plant related radioactivity via this pathway is dicussed in S2ction 5.0. Oysters (Table 19) Native oysters are sampled at the quarry discharge (location 40X); an extra location. The remaining locations utilize stocked oysters; trays are kept at these ' sampling areas to guarantee samples and facilitate sample collection. Plant related acitivity is shown at two locations, the area within 500 feet of the discharge (location 32) and the quarry disharge (location 40X). This activity included Mn-54, Co 58, Co-60, Zn 65, and Ag-110m. These locations are within the plant discharge area, the one within 500 feet is actually at the end of the quarry. 1herefore, these samples tend to show higher levels of activity than the mussel, clam, and lobster samples. Since these two sample locations are on-site and not available for public use, the actual concentration of radionuclides in oysters available for public consumption is much less. The dose consequence of radioactivity via this pathway is discussed in Secion 5.0. Clam.s (Table 20) GeLi analyses indicated the presence of plant related Co-58 and Co-60. These levels correspond to the elevated levels seen in quarry oysters for the same period. However, the reduced levels demonstrate that the activity in the oyster samples decreases rapidly with distance from the station. The dose conecquence of radioactivity via this pathway is discussed in Section 5.0. Scallops (Table 21) Scallops are not required by the REMM. The plant effects for this sampling media are not detectable. Lobsters (and Crabs) (Table 22) Some samples for location 12X (Fisher's Island) and 40X (quarry discharge) are crabs while all others are lobsters. Plant related activity is shown in crabs from the quarry and lobsters from the area within 500 feet of the discharge. The activity included Mn-54, Co-53 and Co-60. The quarry sample is within the plant discharge, and as such, concentrations in food that the public consumes would be much less. See Section 5.0 for a discussion of the dose consequences. 4-5
FIGURE 4-1 COMPRRATIVE MONTHLY VALUES OF RIR PARTICULATE GROSS BETA RADIORCTIVITY 1987 0.030 J 9 ^ 0.029- /\\ \\ 0.028-7/ \\ 0.027-jf \\ 0.02G- / \\ 0.025 - \\ 0.024 - j g ./ \\ / 0.023-b' / C \\ / 2 - / / s / N N g M E 0.020- / 7 N / 7 p E 0. 019 -) / \\ / 's / I 0.018 g S 0.017- \\ 0.016-g 0.015- \\ / g j! O.014 - D 0.013-i i i i i i i i i i i i JAN FEB MAR APR MRT JUN JUL AUG SEP OCT NOV DEC 1987 INNER STAT 10NS 1 = 0= OUTER STATIONS THE ERRh1 IN THESE VALUES IS APPROXIMATELY 0.004
4 5.0 OFFSITE DOSE EQUlVALENT COMMITMENTS The off-site dose consec uences (dose equivalent commitments) of the stations' radioactive liquid and air aorne effluents have been evaluated using two methods. The first method utilizes the stations' measured radioactive discharges as input parameters into conservative models to simulate the transport mechanam through the environment to man. This results in the calculation of the maximum dose consequences to individuals and the O to 50 mile population dose commitment. The results of these computations have been submitted to the NRC in the Annual Radioactive Effluents Dose Report writtca in accordance with the Radiological Effluent Monitoring Manual, Section F.2. This method, which is usually conservative (i.e., computes higher doses than that which actually occur) has the advantage of approximating an upper bound to the dose consequences. This is important in those cases where the actual dose consequence cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques. The second method utilizes the actual measurements of the concentrations of radioactivity in various environmental media (e.g., milk, fish) and then computes the dose consequences resulting from the consumption of these foods. The results of both methods are compared in Table 5.1 for those pathways where a potential dose consequence exists and a comparison is possible. The doses presented in this table are the maximum doses to an individual. 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 for the site boundary location which is not only the nearest but a!so has the greatest directional wind frequency and fish and shellfish doses are calculated assuming they are from an area within 500 feet of the station discharge. As indicated by Table 5.1, there is alsc, a direct gamma dose attributable to the operation of Unit I. This direct dose is inherent to BWR's (Boiling Water Reactors). It is due to direct and scattered radiation (skyshine) of the high energy gamma rays from Nitrogen-16 in the radioactive steam which circulates through the turbine. It should be noted that the indicated dose due to direct radiation is to the maximum individual and is corrected for periods when Unit I is not operating (i.e., there is no direct dose when steam is not generated). Summarizing the data in Table 5.1, the maximum total doses to an individual are: 1.4 mrem whole body to a child, 0.74 mrem to a child's thyroid, and 0.3 mrem to an adult's GI (LLl) (gastrointestinal tract-lowerlarge intestine). Since the maximum dose consequence to an individualis at the location of highest dose consequence, doses will be less for all other locations. The average dose to an individual within 50 miles from the site cannot be calculated using the second method. However, the first method yields the following results for the period January-December 1987 for the average individual: ANNUAL AVERAGE WHOLE BODY DOSE : DUE TO AIRBORNE EFFLUENTS = 0.0012 mrem DUE TO LIQUID EFFLUENTS = 0.000088 mrem Thus,it can be seen that the average whole body dose to an individualis much less than the maximum whole body dose to an individual as shown in Table 5.1. 5-1
c 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 40CFRf 90 as 25 mrem whole body,75 mrem thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation dose of 270 mrem per year and are designed to be inconsequentialin 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. I 52
TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS' MILLSTONE NUCLEAR POWER STATION JANUARY DECEMBER 1987 ANNUAL DOSE (MlLllREM) METHOD _1 W METHOD 20) PATHWAY ORGAN Unit 1 Unit 2 Unit 3 Station (BWR) (IMRl (PWR) Total AIRBORNE EFFLUENTS
1. External Gamma Dose (2) Max. Ind. - Whole Body 0.083 0.013 0.017 0.113 NAD(5)

2. a. Inhalation Max. Ind. - Thyroid 0.0015 0.040 0.014 0.056 ND(3 ', < 0.6

b. Vegetables Max. Ind. - Thyroid 0.0100 0.265 0.038 0.374 ND

c. Goat's Milk Max. Ind. - Thyroid 0.069 0.199 0.106 0.313 NAD, < 1.8 LIQUID EFFLUENTS

1. Fish Max. ind. -Whole Body 0.0024 0.0052 0.0049 0.025 0.018 Max. ind. - Gl (LLI)(4) 0.0086 0.0285 0.0769 0.114 0.154 Max. Ind. - Liver 0.0033 0.013 0.0078 0.012 0.012

2. Shellfish Max. Child. - Whole Body 0.0028 0.0079 0.0085 0.019 0.0093(8)
~~Max. Adult.-Whole Body 0.0027 0.0066 0.0076 0.017 0.0084(8) Max. Ind. - Gl.(LLI) 0.0172 0.0713 0.0677 0.156 0.103(8) DIRECT DOSE - Skyshine~~
~~1. Nearest Residence Max. Ind. - Whole Body 1.3(7)~~
~~N/A(6) N/A 1.3 0.7(9)~~
~~2. Critical Fisherman Max. Ind. - Whole Body N/A N/A N/A N/A 2.6(9)~~
TABLE 5.1 (Cont'd.) .' a (1) Method 1 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 than 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) ND - Not Detectable - No plant related activity could be detected above natural background or above the minimum detectable level (MDL). The value reported is the dose corresponding to the MDL (4) GI(tLI)- Gastro Intestinal Tract - Lower Large Intestine - the organ receiving the maximum dose via the fish and shellfish pathways in an adult. (5) NAD - High pressure ion chamber data was not analyzed for 1987. TLD's cannot detect levels which are such a small fraction of natural background. (6) Not applicable. (7) Based on calculations performed utilizing the computer code, SKYSHINE, developed by Oak Ridge Natiunal Laboratories. (8) Based on measured levels in oysters. Doses due to consumption of clams would be approximately the same. (9) Based on prior measurements performed with a high pressure ion chamber and ratioed to the actual operating power.
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 aispersion, 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 l-131's, therefore it must be remembered that it will remain around for much longer periods of tirre. 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. l 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 l 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 l prove this conclusion wrong. t 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 Section 5.0) show that insufficient quantities (by more than a factor of l 1000) of Sr-90 and Cs-137 have been released from the stations to yield the l 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 l 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 from recent fallout. Similarly, the levels of airborne Sr-90 (and total Cesium) are also generally uniform at all the air sampling locations. However, with the longer half lives of these isoto aes, the same conclusion cannot be made. But, plant related Sr-l 89 has never acen detected in milk, therefore levels of Sr-90 observed must l be attributable to nuclear weapon's testing. l l l 6-1
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 Chernobyl incident. 4. Since dairy milk sampling began in the 1960's, years rior to plant operation, the immediate station areas have always shown h her levels of weapons fallout related Sr-90 and Cs-137 (see Figures 6-1 and -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 19771983 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. Sper.iM studies performed at this and other farms failed to find any link to the plant. 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. 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 poteatial exposure to the population from any plant related activity has been performed and shows that in all cases the exposure is insignificar t. 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 dnvironmental Protection. l l l l t I 6-2
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APPENDIX A COW AND GOAT CENSUS FOR 1987 l 1 i P I A-1
DAIRY CO;S WI'IHIN 15 MILES OF MILLS 7Dt4E POIN'T AS OF APRIL 1987 DIRECTION DISrN;CE NAME NJD ADDRESS
~~10. OF CG7S N~~
6 M. S. Ex4.glas tbrgan 3 16 touglas laru Waterford, Cr 06385 N 7 M. Waterford Country School 2 78 Hunts Brook RI. Quaker Hill, Cr 06375 - Waterford - N 12.5 f t. Conrad telson 98 486 Fitch Hill Rd. Uncasville, CT 06382 - bbntville - 4 r: 14 M. Wauwcus Fam Dairy 40 RFD #2, Wauwcus Hill Rt. Ibrwich, Cr 06360 - Bozrah - NE 12.5 M. Mainwod Fam 32 936 Colon'l Indyard Hwy. e Indyard, Cr 06339 t;E 13.5 II. Henry Ibrgan 62 RFD 67, Box 1114 .r dyard, Cr 06339 e FI;F. 13 H. Charles Perkins 30 RFD # 1 Stonington, Cr 06378 WIM 9.5 f t. J. Ely Harding 55 Ashlawn Fam Old Lym, Cr 06371 - Lym - W!M 11 tl. Tif fany Foms 80 Sterliry City Rd. Old Lym, CT 06371 - Lym - lau 8 f t. Rayrond Muschinsky 22 Grassy Hill Rt. Fast Lym, Cr 06333
1%IRY R1;S WITHIN 15 MILES OF MILLSTONE POItir AS OF APRIL 1987 DIRECTIOli DISTANCE IW1E AND ADDRESS to. OF CDlS tal 11.5 M. Valley View Fam 42 E1xjene Wiczewski Darling RJ. Salem, Cr 06415 In 13 M. Stuart Gadhois 213 Route 82 Salem, Cr 06415 In: 13 M. Garry Vaill 49 Ebrsythe RJ. Salem, Cr 06415 W
1*. ~.,.-*- 4 DAJ,,RY G0ATS WITHIN 20 MILES OF MILLSTONE POINT AS OF JUNE 1987 DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS NN.5 1.8 M. Allen Moran 2 204 Rope Ferry Road Waterford, CT 06385 NE 14 M. Robert Ruest 2 15 Mathewson Mill Road Ledyard, CT 06339 ENE 2 M. Bertram Smith 4 9 Braman Road Waterford, CT 06385 W 16.5 M. Victor Trudeau 6 174 Horse Hill Road l l Westbrook, CT 06498 1 WNW 8 M. Peter LaPolla 3 Town Woods Road Old Lyme, CT 06371 i NW 5 M. Ron Birchall 8 339 Boston Post Road East Lyme, CT 06333 NW 5 M. George Scacciaferro 45 338 Boston Post Road East Lyme, CT 06333 NNW 14 M. Anne B. Henrici 12 Round Hill Road Salem, CT 06415
9 6 s g e e 9 a' APPENDIX B NORTHEAST UTILITIES OA PROGRAM l i I l l l B-1
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, Ed ucation, and Welfare (January 1967). These three quality control methods are: a) Duplicate analyses of actual surveillance sam ales with one laboratory. Th,is 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 Intercomparison Studies Program, and 3) Nuclear Regulatory Commission State of Connecticut Independent Verification Program. METHOD i The number and type of QA samples are given in Table 1. 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 l 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 statistics (1 sigma, a) only(. The standard deviation is divided into the diffe between the two measurements A). The result then should satisfy the acceptance criteria as developed from the above-mentioned U.S. Department of Health, Education, I and Welfare document. For all Geli analyses the acceatance criteria is that No be less than or equal to 3. For chemistry and beta counting, w1ere the overall error is expected to be higher than the calculated error based on counting statistics only, the acceptance criteria is that uo be less than or equal to 4. RESULTS For Precision (Table 2), the requirement is that the unacceptable results be less than 10 percent of the number of measurements for that type of measurement as shown for the totals. General statistics indicate that this value should be approximately 2.5 percent for counting statistics, but 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. Ofthe l~~
B2 t
~,. remaining three, reanalysis results were unavailable at the time of this report. No obvious reasons for these deviations were found. For interlaboratory Comparisons (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 reanalysis, 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 the same as that for Precision, that the unacceptable results be less than 10 percent of the number of measurements for that type of measurement. From the totals at the bottom of Table 4, this requirement is satisfied for I 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 *.he 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 *.welve GeLi water spikes were unaccceptable. Of these, six were caused by problems in spiking / analyzing Ag 110rn. The other two were determined to have been analyzed with the gain slightly off. After adjustment the samples 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 1131 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 l measurements presented in the report are valid. The results of the primary contractor's j l participation in the EPA QA program confirms this conclusion. I l B3
Table 1 Number of Quality Control
~~Samples Number of Number of Sample Type QC Samples Routine Samples,b a~~
TLDs 138 504 Milk 75 144 Well Water' 20 16 Sea Water' 2 8 River Water ( 2 8 Bottom Sediment 4 26 Aquatic Flora 4 14 Fish 4 47 Shellfish 4 69 Lobster / Crab 0 17 Fruits and Vegetables 0 16 Air Particulate Gross Beta 12 827 -lodine 9 780 - Geli 24 192 - Strontiu m 8 64
An additional program is performed by the contractor a - Total for both Millstone and Connecticut Yankee b - Depends on availability c - QC breakdown does notinclude H 3 analysis; total number of tritium QC samples was 20 B-4
~; 7 _ - Table 2 PREClypN Acceptt'n Mumber of Measurements Media Analysis Criteria' J.cr 4ptable Unacceptable Milk Sr90 4 10 6 Sr89 4 26 0 Cs137 (Geli) 3 27 0 Water H3 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
o .T.a.ble 3 INTERLABORATORY COMPARISONS Number of Measurements Acceptance Media Analysis Criteria
~~Acceptable Unacceptable Direct Dose Tl.Ds 20 %~~
~~84 4 Milk Sr90 4 11 2 Sr69 4 13 0 Cs137 (Geli) 3 13 0 Water H3 4 4 0 Geli 3 4 2 Soil & Geli's 3 1 1 Bottorn Sediment Ac;uatic Life Geli's 3 8 0 Total Sr90 4 11 2 H3 4 4 0 Geli 3 26 3~~
~~The acceptance criteria for TLDs is that the delta bc 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 B6
Table 4 ACCURACY (RESULTS OFSPIKES) Number of Measurements Acceptable Unaccentable Acc:ptance Primary Secondary Primary Secondary Media AnaMis Criteria
~~Contractor Contractor Contractor Contractor Direct Oose TLDs 20 %~~
50 0 hiilk 3131 30 % 19 3 1 2 Sr90 4 3 1 3 3 Sr89 4 6 3 0 1 Csl37 3 6 4 0 0 Csl34 3 6 4 0 0 Water Geli 3 4 6 8 0 H3 4 8 4 0 0 Air Particulate G rose, Beta 4 8 4 11 Geli 3 13 Sr90 4 5 3 1131 4 6 3 0 Total TLDs 20 % 50 1131 (milk) 30 % 19 3 1 2 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
~~131 (air) 4 6~~
~~3 4 Gross Beta (air) 4 8~~
~~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 delta / sigma is less than or equal to the values listed below, where: delta = difference between the two values sigma = standard deviation B7
,n O I 4 k APPENDIX C SUMM ARY OF EPA INTERLABORATORY COMPARISONS l l l l l l t I C-1
/ i :M.- 1e 1 nr: 1.,
~~4 N~~
74e 1 - c. sEPA 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 16. ~ 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 l SD, 1 determination. This means that an additional single measurement should yield a result within 1 SD of the mean 66% of the time. l (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. I (yy) This when given is the observed 1 SD, 1 determination for all labs whose results were not deemed outliers. A significant difference between this value and the one above it indicates that the anticipated precision is not bein6 attained by the majority of the laboratorie).
I l' EPA Intercomparison Samples Gross Alpha and Beta Sample N.2. Samole Date Samole Tvoe Gross Alpha 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 1 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 66 Lab Avg. 2(2) 43(2) EPA Known 14(5,9) 43(5,9) EPA Gr. Avg. 15(3) 45(5) 36412 4/20/87 Water (a) 29 Not Required 26 2.1 Lab Avg. 26(3) EPA Known 30(8,14) EPA Gr. Avg. 28(8) 36413 4/20/87 Water (a) Not Required 53 49 19 Lab Avg. 51(2) EPA Known 66(5,9) EPA Gr. Avg. 65(7)
~~g pn -~~
T .. :s .e e EPA Intercomparison Sampl<ts Gross Alpha and Beta Samole No. Samole Date Sa=nle Tvon Gross Aloha Gross Beta 36501 5/22/87 Water (a) 14 6 15 7 11 fi 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 k Lab Avg. 3(1) 6(1) EPA Known 5(5,9) 5(5,9) EPA Gr. Avg. 5(1) 6(2) I 37040 8/28/87 APT (b) LTl 23 LTl 20 LIl 16 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) 33 Not Required 21 r 21 Lab Avg'. 23(2) EPA Known 28(7,12) i EPA Gr. Avg. 28(8) t 202469 10/21/87 Vater (a) Not Required 75 75 11 Lab Avg. 75(0) EPA Known 72(5,9) i EPA Gr. Avg. 75(9) i Note: (a) pCi/1 (b) pC1/ filter s- - -w --,r r-,. +,.-e...-n-.mrw----,p.g., e-~nw-,s awm m,,, ,,---n-,-me wn- .,-w, - - - - -, -, - -. - - ,,,a ,,-n
f., P- ~ EPA Intercomparison Samples Cs 137 Samole No. Samole Date Samole 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 19 Lab Avg. 11(2) EPA Known 10(5,9) EPA Cr. Avg. 11(2) Note: (a) pCi/1 (b) pCi/ filter
L. -,c 3 EPA Intercomparison Sampler Gamma Samnle No. Saggle Date Sample Tvoe 36248 2/6/87 Water Nuclide (pCi/1) 77 Nuclide (pCi/1) 45 Gs 137 84 Co-6Q 50 11 68 Lab Avg. 82(5) Lab Avg. 48(3) EPA Known 87(5,9) EPA Known 50(5,9) EPA Gr. Avg. 87(5) EPA Gr. Avg. 50(4) Nuclide (pCi/1) 87 Nuclide (pci/1) 92 Zn:11 88 Ru-106 91 Eh El Lab Avg. 90(4) Lab Avg. 90(3) EPA Known 91(5,9) EPA Known 109(5,9) EPA Gr. Avg. 94(8) EPA Gr. Avg. 95(16) Nuclide (pCi/1) 55 Cs 134 56 11 Lab Avg. 54(3) EPA Known 59(5,9) EPA Gr. Avg. 55(3) Sample Nc, Sample Date Sample Tvoe 36413 4/20/87 Vater Nuclide (pCi/1) 6 Nuclide (pCi/1) 21 Co-60 7 Co-134 20 1 11 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)
- - _ _ - - ______y, p ::t. ac o , f 'i.. on n-s + a s Mi EPA.Intercomparison Samples' Gamma l Samole No. Egagl dja.tg Saranle Tyne 36413 4/20/87 Water Nuclide (pci/1) 17 Cs-137 16 y. 1% Lab Avg. 16(1) U EPA Known 15(5,9) f EPA Gr. Avg. 16(2) Samole No. Sample Date Samole Tvoe t [ '36578 6/5/87 Water t i Nuclide (pC1/1) LT 90 Nuclide (pci/1) 56 Cr 51 LT 90 C.g-1Q 64 l LT 94 il i Lab Avg. LT 91 -Lab Avg. 61(4) EP/ Known 41(5,9) EPA Known 64(5,9) EPA Cr. Avg. 39(14) EPA Gr. Avg. 65(4) [ Nuclide (pCi/1) 15 Nuclide (pCi/1) 102 Zn 65 16 Ru 10( 85 il 21 Lab Avg. 17(2) Lab Avg. 94(9) l EPA Known 10(5,9) EPA Known 75(5.9) EPA Gr. Avg. 11(2) EPA Gr. Avg. 73(11) l l Nuclide (pci/3) 15 Nuclide (pCi/1) 75 Cs-134 41 Cs-137 74 11 EQ 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) l l l 4
~ ~. 3**. 'f;.. ' k. l ,,(a 'i ^, v w fi. 6 ( ) s A 4 4 EPA Intep omoarison-Samo.lg,3, a 4 Gamna _4 ' 1-. Sample No. Samole Date Samole Tvoe x.C ~# 36649 6/26/8/ Milk Nuclide (p'Ci/1) 73 Nuclide (mg/1) 1119* Cs-137 ~ 72 K 40 1138* fl 1140* p. . Lab Avg. 69(6) Lab Avg. 1132*(12) s - EPA Known* 74(5,9). EPA Known 1525(76,132). . EPA Gr. Avg. -75(6) EPA Gr. Avg. 1577(113) 1 'Samole No. Sarrole Date Samole Tvoe 201998 10/9/87 Water t Nuclide (pCi/1) 41 Nuclide (pCi/1) -14 Cr 51-LT 41 Co 60 16 LT 47 M 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 (pC1/1), 39 Nuclic'e (pCi/1) 35 - Ep 49-Ru-106 56 42 4,,6 m ' ?ab Avg. 43(5) Lab Avg. 46(11) EPA Known 46(5,9) EPA Known 61(5,9) EPA Gr. Avg. 47(5) EPA Gr. Avg. 60(10) Nuclide (pci/1) 20 Nuclide (pci/1) 42 Cs-134 23 CJ-137 51 24 4A Lab Avg. 22(2) Lab Avg. 46(5) EPA Known 25(5,9) EPA Known 51(5.9) EPA Gr. Avg. 24(2) EPA Gr. Avg. 52(3) I
g6 ':? 4 (;;, / ? ~ ~ ~, : [ g of , a*:: ~> =, .l* )_, EPA Intercomparison Samples Gamma 1. s Samole No. Sainole Date ~ Samnie Tvoe-202469 j :,.. 10/21/87 Water e Nuclide (pCi/1) 16 Nuclide (pci/1)- 14-C Go 60 .15 Cs 134 13 e.; y y Lab Avg. 16(2) Lab Avg. 14(1) i:PA Known: 16(5,9) EPA Known 16(5,9) EPA Gr'. Avg. -17(2) EPA Gr. Avg. 16(3) ' Nuclide (pCi/1) 26-Cs 137 26 21 Lab Avg. 25(2) EPA Known 24(5,9) EPA Gr. Avg. 24(2) s i' ,A I
7, C r 4 4 EPA Intercomparison Samples I-131 (pCi/1) Samole No. Sample Date Samole Tvoe Cs-137 36282 2/27/87 Milk 7 7 8 Lab Avg. 7(1) EPA Known 9(1,2) EPA Gr. Avg. 9(2) )- 36374 4/3/87 Water 5 4 5 Lab Avg. 5(1) EPA Known' 7(1,2) EPA Gr. Avg. 7(1) 36649 6/26/87 Milk 70 72 10 l Lab Avg. 71(1) l EPA Known 59(6,10) l EPA Gr. Avg. 62(6) 36893 8/7/87 Water 49 54 Lab Avg. 52(3) i EPA Known 48(6,10) EPA Gr. Avg. 47(5) 8712049 12/4/87 Water 27 28 21 Lab Avg. 27(1) EPA Known 26(6,10) EPA Gr. Avg. 27(3) ?
o , 23 o. ~ EPA Intercomparison Samples Ra 226 and Ra 228(pci/1) Sample No. Sample Date Samnle Tvoe Ra-226 Ra-228 36302 3/13/87 Watit 7.6 8.3 7.1 8.6 6.8 7.5 Lab Avg. 7.2(.4) 8.l(.6) EPA Known 7.3(1,1,1.9) 7.5(1.1,1.9) 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 5Z 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 6/10/87 Water 5.4 14.5 5.5 13.7 4.3 15.2 Lab Avg. 5.l( 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 M 5.0 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 10/21/37 Water 4.6 Not Submitted 4.6 .l.1 a Lab Avg. 3.6(1.8) EPA Known 4.8(.7,1.2) EPA Gr. Avg. 4.7 871214501 12/11/87 Water 3.7 11.2 3.7 9.9 U 8h Lab Avg. 3.4(.5) 9.9(1.3) EPA Known 4.8(.7,1.2) 5.3(.8.1.4) EPA Gr. Avg. 4.71 5.24 0
,7 Y.' ? -. c A L: 1 .s. 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 11 24 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 p Lab Avg. 17(0) EPA Known 17(2,3) EPA Gr. Avg. 18(2). 36413_ 4/20/87 Water (a) 23 10 21 10 M M Lab Avg. 22(1) 10(0) EPA Known 19(5,9) 10(2,3) EPA Gr. Avg. 17(4)- _0(2) 36484 5/8/87 Water (a) 40 18 39 19 H-18 Lab Avg. 39(1) 18(1) EPA Known 41(5,9) 20(2,3) EPA Gr. Avg. 39(7) 20(3) ~36649 6/26/87 Milk (a) 24 9 25 10 2.5 2 Lab Avg. 25(1) 9(1) EPA Known 69(5,9) 36(2,3) EPA Gr. Avg. 64(14) 34(5) 1 -w- +w- -g , e ,-r .,g_
..g . y,.,. 3 _+ EPA Intercomparison Samples Sr 89 and Sr-90.: Samole No. Samole Date Samole Tvoe. Sr-89. Sr 90 37040
~~8/28/87~~
~~' APT (b)- Not Required. 10 10 2~~
~~i Lab Avg...~~
10(1). EPA Known 10(2,3) EPA Gr. Avg. 10(2) 202469 10/21/87 -Water'a) 19 11 19 10 12 U Lab Avg. 19(0) 11(1) EPA Known 16(5,9) 10(2,3) EPA Gr. Avg. 15(4) 10(1) -Note: (a) pCi/1 .(b) pCi/ filter f i l l-l t l~ P l i l l' l [
R> b : ;'.9,';, e. -c .j 4; ge .4.. r 3 - .P EPA.Intercomparison Samples Tritium ,Samole No.+1 - Sample qqLg-
~~Samole Tvoe~~
. Tritium (oCi/ll '36257-2/13/87 Water 3800 s 3700 119.Q. Lab Avg. 3667(153) EPA Known 4209(421,729) EPA Gr. Avg. 4156(418) 36640 6/12'/87-Water 2900 2900 2800 Lab Avg'. 2867(58) EPA (nown 2895(357,618) EPA Gr. Avg. 2785(293) -202028 10/16/87 Water 4109 .1 -4241 M12 -4: Lab Avg. 4187(69) EPA Known .4492(449,778) EPA'Gr. Avg. 4386(299) t a d + 1 g n l H i.. L-1 L i .i L
j!b .,?. J' EPA Intercomparison Samples Uranium (pCi/1) Sample No. Sample Date Sample Tvoe Mxanium 36412 4/20/87 Water 4 4 1 Lab Avg. 4(1) EPA Known 5(6,10) EPA Gr. Avg. 5(2) 202468 10/21/87 Water 3 3 2 Lab Avg. 3(1) EPA Known 3(6,10) EPA.Gr. Avg.4, 3(1) 1
^}v ..g q = ~ q s t! peOR73tEAST UTH.ITIES ceneraiown can street. Berna cane"' Ll u lai r,7%"l.!~"O~2~ bkhb ' ' ~ " ErIr'D CONNECTICUT 0614'@70 I m T (2a' 60N L Aprii 28, 1908 Dgqket N_os. 5,0-1 9 '? E131 10_d23 Ill2MM Re: 10CFRSC.4(ia)(1) U.S. Nuclear Regulatory Comission Atto: Document Control Cask Washington, D.C. 20555 Gentlemen: Millstone Nuclear Power Station, Unit Nos. 1, 2, and 3 Annyal Radiolooie3Movironmental Operatinc Report In accordance with the requirements of the Hillstone Nuclear Power Station P.adiological Effluent Monitoring Manual, an implementing document of the Millstone Unit Nos.1, 2 and 3 Technical Specifications, two (2) copies of the Annual Radiological Enviromnt al Operating Report are herewith submitted. Copies of this report are being distributed in accordance with 10CFR50.4(b)(1). Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY hkhf.Sy:W C.
~~Mroczkar Se for Vice President l~~
cc. W. T. Russell, Region 1 Administrator j H. L. Bey h, NRC Project Manager, Hillstone Unit No. 1 O. H. Jaftc, NRC Project Manager, titlistor,e Unit No.2 R. L. Ferguson, NRC Project Manager, Hillstone Unit Ne. 3 W. J. Ray:nond, Senior Resident Inspector, Millstone Unit ilos.1, 2, and 3 4,- i M 9,8 l I(l 1 w - ~ ~-
NEME.kST UTIE ITlEb Genera; Omces
~~Se! der, S'.teet Berhn. Connecticut~~
.w. ~e. wo..u m u v N "**" POSQXZQ ec.t w..w a sw HARTFORD. CONNECTICUT 061410270 .$ b:.iN[.S$ (203) 665-5000 k k April 28, 1988 Qccket Nos. 50-245 50-336 50-423 B12886 Re: 10CFR50.4(b)(1) U.S. Nuclear Regulatory Comission Attn: Document Control Desk Wshington, D.C. 20555 Gentlemen: Millstone Nuclear Power Station, Unit Nos. 1, 2, and 3 Annilal hdiolocical Environmental Operatina Report In acccrdance with the requirements of the Millstone Nuclear Power Station Radiological Effluent Monitoring Manual, an implementing document of the Hillstone Unit Hos.1. 2 and 3 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, NORTHEAST NUCLEAR ENERGY COMPANY l (Akt+ % 1 Erf. fitoczkaf Senior Vice President cc: W. T. Rossell, Region 1 Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 i D. H. Jaffe, NRC Project Manager, Millstone Unit No.2 R. L. Ferguson, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 .}}

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