B12012, Semiannual Radioactive Effluent & Waste Disposal Rept, Jul-Dec 1985
| ML20214V977 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1985 |
| From: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| B12012, NUDOCS 8612100032 | |
| Download: ML20214V977 (43) | |
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- CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT SEMIANNUAL RADI0 ACTIVE EFFLUENT AND WASTE DISPOSAL REPORT FOR THE PERIOD OF JULY 1, 1985 - DECEMBER 31, 1985 -
DOCKET NO, 50-213 h LICENSE DPR-61 ;
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TABLE OF CONTENTS Supplemental Information . . . . . . . . . . . . . . . . . . . . . 1-9 Gaseous Effluents - Summation of all Releases .......... 10 Gaseous Effluents - Mixed Mode Release (Partially Elevated and Partially Groundl . . . . . . . . . . . . . . . . . . . . . 11 Liquid Effluents - Summation of all Releases . . . . . . . . . . . 12 Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . 13 Solid Waste ........................... 14-16 Offsite Dose Estimates . . . . . . . . . . . . . . . . . . . . . . 17-23 Meteorological Data . . . . . . . . . . . . . . . . . . . . . . 24-40
,. s f1) SEGULATORY LIMITS Specifications for Caseous Waste Effluents (1) The ralease rate limit of noble gases from the site shall be:
Q iy 1 N iy
+ MI ig i1
. g 1
where Qv = release rate from all roof and unit vents in C1/sec (ground release) i = The ich individual nuclide.
If = the average gamma energy per disintegration for nuclide i
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E id = the average beta energy per disintegration for nuclide i Refer to Table 2.4-5 for IY'and I values to be used.
(2) The release rate limit of all radiciodines and radioactive materials in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site shall be:
1.2x10 6 gy <g &, e S5 m CAo where Q, is defined above.
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l (3) The average release rate of noble gases from the site during any calendar quart'er shall be:. -
l E gg 1450 Q gy 11 i
and. -
3 I 590 Q <1 e iv ,_
tvg -
(a) The average release rate of noble gases from the site during any 12 I consecutive months shall be:
1 E 2900 Q iv <1 if ,
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f- y 1130 Q iv 41
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(5) The cvarass ecleasa rata of oil iodinas and radioactivs maccrialo in particulcea form per sito with half-livoo gr:cter than eight daya during any calendar quarter shall be:
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1.5 x 10 Qy 11 Wf C /"*
I (6) The average release rate of all iodines and radioactive materials per site in particulate form with half-lives greater than eight days during any period ,
of 12 consecutive months shall be: l 3.0 x 108 Q, $ 1 3 5 , ,, 9 (7) The amount of iodine-131 released during any calander quarter shall not exceed 2 C1/ reactor.
(8) The amount of iodine-131 released during any period of 12 consecutive months shall not exceed 4 C1/ reactor.
Reporting Requirements:
Should any of the conditions of 2.4.3.3 (1), (2) or (3) listed below exist, the licenses shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release races to design objective levels listed in Section 2.4 and report these actions to the Commaission within 30 days from the and of the quarter during which the releases occurred.
(1) If the average release rate of noble gases from the site during any calandei quarter is:
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igg 5800 Qg > 1
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= s L
l or, Y 2400 Q , y l 1 (2) If the average release rate of all iodines and radioactive aterials in particulate form per site with half-lives greater than eight days during any calendar quarter is: ,
8 ,g 5.9 x 10 g y i
, (3) If the amount of iodine-131 released during any calendar quarter is greater than 0.5 C1/ reactor.
Spreifiention9 for Liquid (Jven Ef fluenen The concentration of radioactive materials released in liquid waste effluents at the site shall not exceed the values specified in 10 CFR Part 20 .Appedix 3.
Table II, Column 2. for unrestricted areas.
The cumulative release of radioactive materials in liquid waste offluents, excluding tritium and dissolved gases, shall not exceed 10 C1/ calendar quarter.
The cumulative release of radioactive materials in liquid waste ef fluents.
excluding tritium and dissolved gases, shall not exceed 20 C1 in any 12 consecutive months.
During release of radioa.tive wastes, the affluent control monitor shall be set to alarm and to initiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in 2.4.1.1.
The operability of each automatic isolation valve in the liquid radwaste discharge -
lines shall be demonstrated quarterly.
The equipment installed in the liquid radioactive vaste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected cumulative release could exceed 1.25 Ci/ calendar quarter, excluding tritium and dissolved gases.
The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 C1. excluding tritium and dissolved gases.
Recorting Requirement:
If the cumulative release of radioactive materials in liquid ef fluents, excluding tritium and dissolved gases, exceeds 2.5 C1/ calendar quarter, che ' licensee shall make an investigation to identify the causes for such releases, define and initiate a program of action to reduce such releases to the design objective levels listed in Section 2.4, and report these actions to the Commission within 30 days from the end of the quarter during which the release occurred.
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.- #2) Maximum Pcrmis:1blo Concentrations (Micro Curies /al)
,s. Fission and Activation Gases Kr - 85 3.0 E-07 Kr - 85m 1.0 E-07 Kr - 87 2.0 E-08 Kr - 88 2.0 E-08 ;
Ia - 133 3.0 E-07 Ze - 135 1.0 E-07 Is - 135m 3.0 E-08 Ia - 138 3.0 E-08 Ar - 37 1.0 E-04
- b. Iodinas I - 131 1.0 E-10 I - 133 4.0 E-10 I - 135 1.0 E-09
- c. Particulates, Half-Lives > 8 Days Sr - 89 3.0 E-10 Sr - 90 3.0 E-11 Cs - 134 4.0 E-10 Cs - 137 5.0 E-10 Ba - 140 1.0 E-09 La - 140 ,
4.0 E-09 i
- d. Liquid Effluents Sr - 89 3.0 E-06 Sr - 90 3.0 E-07 Cs - 134 4.0 E-05 Cs - 137 2.0 E-05 I - 131 3.0 E-07 1
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Liquid Effluent 9 (Conr.)
Co - 58 9.0 E-05 Co - 60 3.0 E-05 Fe - 59 5.0 E-05 Zn - 65 1.0 E-04 )
Mn - 54 1.0 E-04 )
Cr - 51 2,.0 E-03 Zr - 95 6.0 E-05 Nb - 95 1.0 E-04 Mo - 99 4.0 E-05 Tc - 99m 3.0 E-03 at - 140 2.0 E-05 La - 140 2.0 E-05 Ce - 141 9.0 E-05 Eu - 154 2.0 E-05 Be - 7 2.0 E-03 Ru - 106 1.0 E-05 Ag - 110m 3.0 E-05 Sb - 124 2.0 E-05 Sb - 125 1.0 E-04 Co - 57 4.0 E-04 Ie - 133 3.0 E-06 Xe - 135 3.0 E-06 Ar - 37 3.0 E-06 Kr - 85 3.0 E-06 i
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Third Qutrter 1985 Fourth Quarter 1985 E Beta E Gamma 5 Beta 5 Gamma 2.31E-01 1.14E-01 2.30E-01 8.7E-02
- 3. Average Energy (E)
For Fission and Activation Gases Measurements and Ap'proximation of Total Radioactivity
- 4. a. Fission and Activation Gases: An in-line G. M. detector monitors stack effluent. Gas samples are collected on the stack and are analysed for low level fission and activation gases.
- b. Iodines: Continuous in-line charcoal filter on main stack effluent.
Charcoal filters are then analysed for iodines.
- c. Particulates: Ccntinuous in-line particulate filter on main stack effluent.
Particulate samples are then counted for Gross if . A monthly composite is made from weekly samples. The monthly composite is checked for gross alpha and 89Sr - 90Sr.
- d. Liquid Effluents: In-line scintillation detector monitors waste liquid being released. Prior to discharge a sample is taken. Principal gamma emitters, entrained gases and tritium analyses are performed. A, monthly composite is made from the weekly samples. Gross Alpha, 89Sr, and 90Sr are determined.
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- 45) Batch Releases
- a. Liquid
- 1) Number of batch releases: 1.26E+02
- 2) Total time period for batch release: 7.32E+02 Hours
- 3) Maximum time period for a batch release: 1.25E+01 Hours
- 4) Average time period for batch releases: 5.81E+00 Hours
- 5) Minimum time period for a batch release: 1.30E+00 Hours
- 6) Average stream flow during periods of 15,800 Cubic feet release of effluent into a flowing per second stream:
- b. Gaseous
- 1) Number of batch releases: 1.47E+02
- 2) Total time period for batch releases: 1.61E+03 Hours
- 3) Maximum time period for a batch release: 3.76E+01 Hours
- 4) Average time period for batch releases: 1.09E+01 Hours
- 5) Minimum time period for a batch release: 1.67E-02 Hours
- 6) Abnormal Releases 7/7/85 0500-0535 G-145 Isotope. Curies Released Met Data Xe135 5.14E-01 Xe135m 1.41E-01 Wind Speed: 3.8 mph Xe133m 2.94E-02 Wind direction: 240' Kr85 3.98E-03 Wind Variance: 26.8*
Kr85m 6.92E-04 Delta T: +0.54*F Kr88 3.96E-04 7/13/85 2255-2300 G-136 i
Isotope Curies Released Met Data Xe133 5.63E-01 Xe135 6.85E-02 Wind Speed: 2.24 mph Xe133m 1.86E-02 Wind Direction: 327' Kr85 6.76E-03 Wind variance: 30.8*
Kr85m 3.11E-03 Delta T: v1.98'F KrS7 6.85E-05 Kr88 1.43E-03
g .*
- 6) Abnormal Releases Cont.
7/14/85 1400-1415 G-137 Isotope Curies Released Met Data Xe133 5.63E-01 Xe135 6.85E-02 Wind Speed: 13.19 mph Xe133m 1.86E-02 Wind Direction 187.8*
Kr85 6.78E-03 Wind Variance: 13.5*
Kr85m 3.11E-03 Delta T:-1.44*F Kr87 6.85E-05 Kr88 1.43E-03 7/28/85 0115-0200 G-146 Isotope Curies Released- Met Data Xe133 2.96E-01 Wind Speed: 0.8 mph Xe135 2.43E-02 Wind Direction:- 225*
Xe133m 6.89E-02 Wind Variance: 31' Kr85 2.59E-03 Delta T: +1.08'F Kr85m 7.02E-04 Kr88 3.43E-02 7/28/85 0315-0400 G-147 Isotope Curies Released Met Data Xe133 2.67E-01 Xe135 2.19E-02 Wind Speed: 1.4 mph Xe133m 6.20E-03 Wind Direction: 295.8*
Kr85 2.33E-03 Wind Variance: 8' Kr85m 6.32E-03 Delta T: +0.9'F Kr88 3.09E-04 8/20/85 to 8/21/85 2315-0200 G-167 - G-170 Isotope Curies Released Met Data Xe133 , 1.808E+00 Wind Speed: 3.08 mph Xe135 6.090E-01 Wind Direction: 214*
Xe135m 1.004E-01 Wind Variance: 31' Xe137 4.530E-01 Delta T: +0.54*F Xe138 3.671E-01 Kr85 2.692E-03 Kr85m 1.271E-01 Kr87 1.891E-01 Kr88 2.256E-01
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' #6)' Abnormal-Releases Cont.
9/7/85 0000-0200 G-188 - G-194 Isotope Curies Released Met Data Xe131m 1.500E-01 Xe133 4.695E-01 Wind Speed: 5.06 mph Xe135 2.456E-01 Wind Direction: 371*
Xe135m 2.683E-02 Wind Variance: 26.5*
Xe137 1.795E-02 Delta T: +0.0*F Xe138 1.153E-01 Kr85 2.330E-03 Kr85m 4.331E-02 Kr87 6.792E-02 Kr88 7.980E-02 10/17/85 0230-0430 G-253 Isotope Curies Released Met Data Xe131m 4.29E-01 Xe133 2.740 Wind Speed: 6.2 mph I Xe135 6.86E-01 Wind Direction: 301*
Xe135m 1.04E-01 Wind Variat.ce: 10*
Xe137 4.05E-01 Delta T: +0.8'F Xe138 3.96E-01 Kr85 7.14E-02 Kr85m 1.55E-01 Kr87 2.40E-01 Kr88 2.56E-01 Ar41 2.07E-01 11/1/85 1340-1441 G-276 - G-277 Isotope Curies Released Met Data j Xe131m 1.656E-01 Xe133 1.007E+00 Wind Speed: 1.52 mph
, Xe135 2.913E-01 Wind Direction: 281.6*
Xe135m 3.326E-02 Wind variance: 9.4*
Xe137 7.244E-02 Delta T: -1.08'F Xe138 , 1.193E-01 Kr85 4.258E-04 Kr85m 6.446E-02 Kr87 8.249E-02 Kr88 1.023E-01 Ar41 5.16E-02
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- 6)' Abnormal Releases Cont.
11/21/85 0950-1200 G-285 Isotope Curies Released Met Data Xe131m 1.522E-01 !
Xe133 9.705E-01 Wind Speed: 11.88 mph Xc135 '
2.871E-01 Wind Direction: 304.6*F Xe135m 3.848E-02 Wind variance: 3.1*
Xe138 1.181E-01 Delta T: -1.08'F Kr85 1.411E-03 Kr85m 6.279E-02 Kr87 8.480E-02 Kr88 1.015E-01 Ar41 3.714E-02 12/28/85 1436-1541 G-314 Isotope Curies Released Met Data Xe133 3.22E-01 Xe135 1.89E-01 Wind Speed: 3.8 mph Xe135m 1.92E-02 Wind Direction: 286.9*
Xe138 6.12E-02 Wind Variance: 10.2' Kr85 8.02E-03 Delta T: -0.4*F Kr85m 4.17E-02 Kr87 5.21E-02 Kr88 6.34E-02 Xe131m 1.08E-01 Xe133m 9.11E-03 Ar41 8.16E-03 12/11/85 0852-0923 G-317 - G-318 1
1 Isotope Curies Released Met Data Xe133 1.59E+00 Xe135 4.00E-01 Wind Speed: 2 mph Xe131m 5.53E-01 Wind Direction: 189.2*
Xe133m 4.13E-02 Wind Variance: 5.5*
Kr85 4.25E-02 Delta T: +0.39'F Kr85m i 3.45E-02 Kr87 3.76E-04 KrE8 1.79E-02 Ar41 4.62E-04 9-i EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT' .1985 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES THIRD FOURTH UNIT QUARTER EST TOTAL QUARTER ERROR % i A. FISSION & ACTIVATION GASES 1
- 1. Total release ci 7.52E+02 7.99E+02 1.40E+01
- 2. Average release rate for period uCi/sec 9.56E+01 1.02E+02
- 3. Percent of Technical Specifica-tion limit g 2.89E+00 3.08E+00 B. 10 DINES s
- 1. Total iodine Ci 2.01E-04 7.5E-04 I 1.30E+01
- 2. Average release rate for period uCi/see 2.56E-05 9.54E-05 '
f
- 3. Percent of Technical Specifica-i tion limit % 3.84E-01 1.43E+00 C. PARTICULATES M#"
- 1. Particulates with half-lives
> 8 days C1 8.32E-06 5.69E-06 1.40E+01
- 2. Average release rate for period uC1/see 1.06E-06 7.24E-07
- 3. Percent of Technical Specifica-tion % 1.59E-02 1.09E-02
- 4. Gross alpha radioactivity Ci A EL 4 EL ,
D. TRITIUM b #" "* *
- 1. Total release C1 3.92E+01 1.55E+01 8.00E+00
- 2. Average release rate for period uC1/sec 4.98E+00 1.97E+00 o.
i 3. Percent of Technical Sp,ecifica-tion limit % 1.02E-01 4.02E-02 9 9 vu 3 v. 4 x / o '
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r ~ EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 19 85' -
GASEOUS EFFLUENTS- MIXED Mnrir an RASE i
, CONTINUOUS MODE BATCH MODE THIRD FOURTH THIRD FOURTH
, NUCLIDES RELEASED UNIT OUARTER OUARTER OUARTER OHARTER FISSION GASES i Krypten-85 Ci 7.98E-02 ZMDL 3.59E+01 1.20E+02
- Krypten-85m C1 4MDL 4 MDL 8.63E+00 5.85E+00 Krypton-87 C1 4 MDL 4 MDL 4.08E+00 3.27E+00 Krypten-88 C1 4MDL 4MDL 8.34E+00 5.94E+00 X n:n-133 Ci 9.94E-01 4 MDL 5.14E+02 5.55E+02 Xrnon-135 C1 1.94E-02 4 MDL 1.21E+02 7.02E+01 Xen:n-135m C1 4.MDL 4 MDL 5.49E+00 1.29E+00 Xenon-138 C1 4MDL 4 MDL 3.43E+00 4.66E+00
! 3H C1 1.48E+01 1.11E+01 2.44E+01 :4.45E+00 l
Argin 41 C1 6.44E-04 4 MDL 4MDL 4 MDL
-Xenon 131M Ci 4MDL 4 MDL 1.20E+01 7.45E+00 Xcn n 133M C1 3.56E-03 4 MDL 3.34E+01 1.91E+01
,'X'nen 137 C1 4MDL 4 MDL 4.32E+00 5.07E+00
., TOTAL FOR PERIOD C1 1.09E+00 4MDL 7.51E+02 7.99E+02 I Iedint-131 Ci 1.94E-04 4.50E-04 *
- l Iodint-133 Ci 7.88E-06 3.00E-04 * *
, Iodini-135 Ci 4 MDL 4MDL *
- i TOTAL FOR PERIOD C1 2.01E-04 7.5E-04 * *
, PARTICULATES Ci Alphn C1 4MDL 4 MDL * *
! Strontium-89 C1 4MDL 4 MDL *
- i Strontium-90 C1 4 MDL 4MDL *
- C271us-137 C1 1.73E-06 2.04E-06 *
- Barium-lanthanum-140 C1 4MDL 4MDL *
- C3rium-144 Ci 4. MDL 4 MDL *
- Ccbnit-60 Ci 6.58E-06 3.65E-06 *
- Mangrnese-54 Ci 4 MDL 4MDL *
- i Ccbalt-58 C1 2 MDL 4MDL *
- Ruth ;n:.um-103 C1 4MDL 4MDL * *
, Zirconium / Niobium-95 C1 4 MDL 4MDL *
- i Ruth':nium-106 C1 4MDL 4MDL *
- TOTAL FOR PERIOD C1 8.32E-06 5.69E-06 * * -
l
}DL Iodines: 1.0E-12uCl/cc MDL Gases: 1.0E-04 u c i/cc
( MDL Particulates: 1.0E-ll uC l /cc MDL ALPHA: 1.0E-IluC1/cc
' *Raported under continuous releases. _1;_
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EFFLUENT'AND WASTE DISPOSAL SEMI-ANNUAL REPORT 19 85 i
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES THIRD FOURTH EST. TOTAL ,
UNIT QUARTER QUARTER ERROR % l' A. FISSION AND ACTIVATION PRODUCTS
- 1. . Total release (not including tritium, gases, alpha). Ci 1.56E-02 3.76E-02 1.10E+01'
- 2. Average diluted concentration during period uCi/ml 8.20E-11 1.98E-10
- 3. Percent of applicable limit 1.56E-01
% 3.76E-01 I
B. TRITIUM
- 1. Total release C1 1.85E+03 1.33E+03 3.50E+00
- 2. Average diluted concentration during period 9.73E-06 6.99E-06 uCi/mi 3.
{ Percent of applicable limit % 3.20E-01 2.33E-01
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DISSOLVED AND ENTRAINED GASES 4
- 1. Total release Ci 4.46E-01 1.97E+00 1.90E+01
- 2. Average diluted concentration during period pC1/ml 2.34E-09 1.04E-08
- 3. Percent of applicable limit : 7.80E-02 3.45E-01 1
, D.
GROSS ALPHA RADIOACTIVITY
- 1. Total release C1 1.26E-06 2.51E-01 8.00E+00 t
E. . Volume of waste released (prior i
to dilution) Liters 3.46E+07 4.01E+07 3.00E+00
!F.- Vclume of dilution water used during period Liters 1.87E+11, 1.90E+11 2.50E+00 i
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. - . . _ _ _ _ _ _ . _ _ . ~ _ _ . _ . _ . _ , , , , _ _ _ , _ _ _ _ , . . , _ _ _ . _ _ _ _ _ _ _ _ _ . . . . . _ _ . _ _ . _ , . _ , _ _ _ . - . _ . , _ . _ _ _
3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 19 85 LIQUID EFFLUENTS
- - CONTINUOUS MODE BATCH MODE .
l THIRD FOURTH THIRD FOURTH j NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER f.
I Strontium-89 Ci 1.47E-04 6.80E-05 2.42E-05 1.20E-05 Strentium-90 C1 1.79E-04 7.02E-05 5.66E-05 1.21E-05 Cmium-134 Ci 4MDL 4 MDL 4.28E-03 2.IlE-03 C eium-137 C1 4MDL 4 MDL 6.63E-03 2.74E-03 Iodine-131 Ci (MDL 8.10E-04 1.53E-04 3.19E-04 Cabelt-58 Ci 4 MDL ( MDL 6.47E-05 1.26E-03 Cobalt-60 Ci 7.65E-04 4MDL 1.90E-03 2.69E-02 Iron-59 Ci 4 MDL 4MDL 4. MDL 4. MDL Antimony-124 C1 4MDL 4 MDL 4MDL 4MDL Mannanese-54 C1 2.30E-05 4 MDL 4 MDL 1.12E-03 Chromium-51 Ci 4MDL 4MDL 4 MDL 3.70E-04 Zirconium-Niobium-95 Ci 4MDL 4 MDL 4 MDL <.MD L Molybdenum-99 Ci (MDL 4 MDL 4MDL 4 MDL Technetium-99m C1 cMDL 4MDL 4MDL 4.MDL Borium-Lanthanum-140 C1 4 MDL 4 MDL < MDL 3.24E-04 Carium-141 C1 4MDL 4 MDL 4MDL 4MDL Cerium-143 C1 4MDL 4 MDL 4MDL 1.55E-05 Ctrium-144 C1 4 MDL 4 MDL 4 MDL 6.00E-04 Alphe C1 4 MDL 4 MDL 1.24E-06 2.51E-05 Ruth'nium-106 Ci 4MDL 4MDL 4 MDL 2.93E-04 Silvsr-110m C1 4 MDL 4 MDL 4MDL 4 MDL Ruthenium-103 Ci 4 MDL c MDL 4MDL 4 MDL Antimony-125 C1 4.MDL cMDL 9.34E-04 4 MDL Cebalt-57 Ci . 4 MDL 4MDL 4MDL 1.39E-04 I? dine-133 Ci 4.02E-04 3.67E-04 4MDL 2.52E-05 Sodium-22 Ci 4MDL 4MDL 4MDL 3.02E-05 Total for Period (above) C1 1.49E-03 1.31E-03 1.41E-02 3.63E-02 Xn131M C1 1.35E-02 Xenon-133 Ci 4MDL 4 MDL 4.14E-01 1.48E+00 Xcnon-135 C1 cMDL 4 MDL 5.89E-03 4.81E-02 Xe133M _ C1 4MDL 4 MDL 2.38E-02 4.04E-02 Krypten-85 Ci (MDL 4 MDL 2.40E-03 3.20E-02 Tritium C1 4.09E+00 1.26E+00 1.85E+03 l 1.33E+03
" 4.MDL" = /.5.0E-07 uC1/ml
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SOLID k'ASTE AFD IRRADIATED FUEL SHIPMENTS A. SOLID
- 1. 6-MONTF. EST. TCTAL TYPE OF WASTE ts;T PERIOD ERROR *
- a. Spent resins, filter m3 4.07 E+1 sludges, evaporator bottom, etc. 1.96 E ,1 -+ 1,0 g,o1 C1
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, b. Dry cc=pressible
- m3 8.98 E+1 Waste. Centaminated equip., etc. + 1.0 E+01 C1, 8.88 E+0
- c. Irradiated components N/A N/A N/A 2.
EE!!PATE OF MAJOR NUCLIDE COMPOSITION (ST TYPE OF '.'ASTE) a) CoS8 8.21% b) Cs134 1.55h Co60 83.70% Cs137 4.12*
Cs134 1.07% Mn54 4.73%
Cs137 2.16% CoS8 8.72*
Mn54 3.45% Co60 80.90%
Cel44 1.41" dE '
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5 A 3. SOLID WASTE DISPOSITION NDGER OF SEI?MECS MODE OF TRANSPORTATION DESTINATidN 14 Truck Barnwell. S.C.
, _ B. IRRADIATED FUEI. SHIP $.'TS (DISPOSITION) - None o .
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OFFSITE DOSE ESTIMATES
.In accordance with the requirements of Section 5.6.1.b of the Environmental Technical Specifications and Regulatory Guide 1.21, the offsite dose to humans from the gaseous and liquid' radioactive effluents of Connecticut Yankee have been estimated.
These estimations are performed using measured effluent data, measured meteorological data, and calculational models developed by the U.S. Nuclear-Regulatory Commission.
The dose estimates generally tend to be conservative due to the use of conservative assumptions in the calculational models. More realistic estimates of the offsite dose are obtained by analysis of the environmental monitoring data. A comparison of the doses estimated by each of the above methods will be present'ed in the Annual Radiological Environmental Monitoring Report due to be published during the first half of 1986.
- 1. Dose Models
- a. Airborne Effluents Maximum individual and population doses due to the release of noble gases, radiolodines and particulates were calculated using the computer code GASPAR(1).
n The codes uses the semi-infinite cloud model to implement the dose models of U.S.N.R.C. Regulatory Guide 1.109 (October,1977). The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in the GASPAR code were generated using a meteorological computer code which implements the assumptions given in Section C of NRC Regulatory Guide 1.111,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors".
Releases from the CY 175 foot stack were considered as a mixed mode release (partially elevated and partially ground). The Pasquill stability classes were determined using the temperature gradient between the 33 foot and 196 foot levels of the meteorological tower.
The GASPAR code was run separately for continuous releases (building ventilation)
- and batch releases (waste gas tanks). The resulting doses were then summed to determine the total dose.*
- b. Liould Effluents Maximum individual and population doses due to the release of radioactive liquid effluents were calculated using the computer code LADTAP(2),
i The code implements the dose models and parameters given in Regulatory Guide 1.109 (October 1977). -
_ . 4.m Third and Fourth quarter GASPAR based upon continuous met data with continuous and batch releases totalled as one continuous release.
- 2. Results
- a. Airborne Effluents The calculated doses are presented in Table 5.1.
For population doses, the GASPAR code calculates the dose to the whole body, GI-tract, bone, liver, kidney, thyroid, lung and skin from cach of the following pathways: direct exposure from the plume, direct exposure from ground deposition, inhalation, vegetation, cow's milk and meat.
The values presented in the attached table are a total from all pathways, but only the whole body, skin and thyroid dose are presented.
For the maximum individual, the GASPAR program calculates the dose to the same organs listed above for the following pathways:
direct exposure from the plume, direct exposure from ground
! deposition, inhalation, vegetation, meat, cow's milk and goat's ,
! milk. The doses are calculated for adults, teenagers, children and i
infants separately. Unless otherwise noted in the table the doses given are for adults.
i For the plume, ground deposition and inhalation pathways, the maximum individual dose is calculated at the offsite location of maximum decayed X/Q where a potential for dose exists.
i i
_19 i
4
J :0 ,
For the vegetation pathway the maximum individual dose is ,
calculated at the vegetable garden of highest D/Q.
For the meat, cow's milk and goat's milk pathways, the calculated a
. dose is included as the maximum individuals dose only at locations -
and times where these pathways actually exist. Doses were calculated at the cow farm and goat farm of maximum deposition.
The doses presented in Table 5.1 are the maximum doses" j observed.
I
- b. Llauld Effluents The calculated doses are presented in Table 5.1.
s The LADTAP code performs calculations for the following pathways: fish, shellfish, algae, drinking water, irrigated food, shoreline activity, swimming and boating. - At Connecticut Yankee, the algae, shellfish, drinking water and irrigated food pathways do not exist, and thus only the other pathways are .
included in the totals given in Table 5.1. ;
e j >
Doses are calculated for the whole body, skin, thyrold, Gl-LLI, y .
bone, liver, kidney, and lungs. -t j
Table 5.1 presents the doses to the whole body, thyroid, and the maximum organ, which in all cases was the liver. The dose to all j other organs was less than that given for the liver.
f
^; .
k y..
t l i,., '
- 7 . Calculadons are performed for adults, teenagers, children and infants s . ,
. separately. Unl.ess otherwise noted in the table the doses given are adult doses.
- 3. Analysis of Results
/" . . .
The' doses are well below permissable levels end are of no significance as far as effects on the general population. For perspective, the average whole body doses to an individual from natural background radiation in the vicinity of Connecticut Yankee is about 40 millirem (3) for a six month period as opposed to the average individual whole body dose within 50 miles of the site of .0003 millirem from gaseous effluents and .00013 millirem from liquid effluents during the report period. The maximum individual whole body dose of .67 millirem from gases and .09 millirem from liquids are approximately 2 percent of the
+ background dose'.
'I I
)
t I
a-
$' \
?
t ,
en
., , cm-v, ygw-y g , - -,n+w--
) ,
\
f REFERENCES e i
(1) GASPAR Dose Code, K. F. Eckerman, Radiological Assessment Branch, U.S. Nuclear Regulatory Commission, Wash. D.C. - Revised 2/20/76.
(2) LADTAP - U.S. Nuclear Regulatory Commission; Washington, D.C.
(3) Does not include an average additional dose of approximately 30 mrem due to internal radiation, f allout, etc.
c.
}
o 1
.i t
(
rI t
U s TABLE 5.1 OFF-SITE ESTIMATES _
Connecticut Yankee s,
I i t
- 1985 A. Airborne E*fluents Units Juiv-sept oct-Dec -
- 1. Maximum Individual Dose Millirem
- a. Whole Body 4.5 (-l ) a, b 2l2 (-1) b
- b. Skin 1.2 ( 0 )b 5.0 (-l ) b
- c. Thyroid 8.0 (-2,) e 8.4 (-2) b
- 2. Population Dose D-50 Miles Person-Ren
- a. Whole Body 5.5 (-l ) 6.7 (-1)
- b. Skin 1.7 (0) 1.7 (0 )
- c. Thyroid 7,3 (-2) 3.3 (- 1 )
- 3. Average Dose 0-50 Miles Millirem
- a. Whole Body 1.3 (-4 ) 1.5 (-4)
- b. Skin 3.9 (-4 ) 3.9 ' (- 4 ) -
- c. Thyroid 1.7 (-5. ) 7.6 '(-5)
B. Liouid Effluents
- 1. Maximum Individual Dose Millirem
- a. .2
.g.3
(-2) c 2.9 (-2)e
- b. Whole Body (LIVER)
Max Organ (-2 ) d 3.9 (-2) d
- c. Thyroid 5.2 (-3 ) c 4.5 (-3)e
- 2. Population Dose 0 50 Miles Person-Ren
- a. Whole Body 3.7 (-1) 1.8 (-1)
- b. Max Organ (LIVER) 6.1 (-1) 2.8 (-1)'
- c. Thyroid 35 (-2) 2.8 (-2)
- 3. Average Dose 0-50 Miles Millires
- a. Whole Body 8.6 'F5 ) 4.2 (-5)
- b. Max Organ (LIVER) 1.4 E4 ) 6.5 (-5)
- c. Thyroid 1.2 (-6 ) 6.5 (-6)
- a. 4.5 (-1 ) = 4.5 x.10-3 -
- b. Dose to the teenager at the critcal location - 515 meters, NNW
- c. Dese to th= adult
- d. Dose to the teenager
- c. Dose to.the child at the critical location - 630 meters, NNW
l f
4 CONNECTICUT YANKEE METEOROLOGICAL JOINT FREQUNCY DATA FOR CONTINUOUS RELEASES s
a .
.,,-...n. _ _ , ___, _ _
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G A
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CONNECTICUT YANKEE ATOMIC POWER COMPANY BERLIN. CONNECTICUT P o Box 270 HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-665-5000 February 28, 1986 Docket No. 50-213 B12012 Dr. Thomas E. Murley, Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19t+06
Dear Dr. Murley:
Haddam Neck Plant Semiannual Radioactive Effluents Release Report In accordance with the requirements of 10CFR50.36a and the Technical r
Specifications,2 copies of the Semiannual Radioactive Effluents Release Report are herewith submitted.
The report has been prepared in accordance with the format of Regulatory Guide 1.21 and copies of the report are being forwarded in accordance with the provisions of Regulatory Guide 10,1.
The Radiological Effluent Technical Specification became effective for the Haddam Neck Plant on January 1,1986. This report covers the last 6 month period in which the Environmental Technical Specifications were in effect. As such, this report is written to the schedular and format requirements of the Environmental Technical Specification in effect during the July to December 1985 time period. Any reference to Technical Specification limits in the attached report is in reference to such Environmental Technical Specifications.
Subsequent reports will follow the requirements specified in the Radiological Effluent Technical Specifications.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY
-F. (kJL U
- 3. F. Opekh Senior Vice President t
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