B12433, Semiannual Radioactive Effluents Release Rept,Jul-Dec 1986

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Semiannual Radioactive Effluents Release Rept,Jul-Dec 1986
ML20212E128
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/31/1986
From: Mroczka E, Sears C
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B12433, NUDOCS 8703040275
Download: ML20212E128 (18)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENTS RELEASE REPORT JULY-DECEMBER 1986 DOCKET N0. 50-213 LICENSE DPR-61 4 9[

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TABLE OF CONTENTS Radiological Effluents Information . . . . . . . . . . . 7,g Gaseous Effluents - Summation of all Releases . . . . . 9 Gaseous Effluents - Mixed Mode Release . . . . . . . . . 10 Liquid Effluents - Summation of all Releases . . . . . . 17 Liquid Effluents - Batch and Continuous . . . . . . . , 12 Solid Waste . . . . . . . . . . . . . . * * * * * * *

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Radiologic':1 Efflurnts informatien

1. Reguistory Limits A. Specifications for Gaseous Waste Effluents
1. The dose rate, at any time, offsite due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

i) The dose rate limit for noble gases shall be less than or equal to 500 arem/yr to the total body and less than or equal to 3000 arem/yr to the skin, and ii) The dose rate limit due to inhalation for iodine-131, iodine-133, tritium and for all radioactive materials in particulate form with nalf lives greater than 8 days shall be less than or equal to 1500 mrem /yr to any organ.

2. The air dose offsite due to noble gases released in gas- *

. cous effluents shall be limited to the following:

1) During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation; ii) During any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation; Reporting Requirements With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report which identifies the cause(s) for exceeding the limit (s) and l definss the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

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B. Specifications for Radioactive Effluents in Particulate Form .

1. The dose to any MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium.and radioactive materials in partic-ulate form with half lives greater than 8 days in gas-eous effluents released offsite shall be limited to the following:-
1) During any calendar quarter to less than-or equal to 7.5 arem to any organ; ii) During any calendar year to less than or equal to 15 arem to any organ.

Reporting Requirements With the calculated dose from the release of radionuclides, radioactive materials in particulate form, or rrdionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such releases during the calendar year is within 15 mrem to any organ.

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C. Specifications for Liquid Waste Effluents .

1. The concentration of radioactive material released from the site shall not exceed the concentrations specified in 10 CFR -

Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases. The concentration shall not ex-ceed 2 x 10-4 uCi/ml total activity.

2. The dose or dose commitment to any MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the site shall be limited:

i) During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

11) During the calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

Reporting Requirements With the calculated dose from the release of radioac'tive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents durin.g the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMEER OF THE PUBLIC from such release during the calendar year is within 3 mrem to the total body and 10 mrem to any organ.

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r-D. Specification for Cumulated Dose Commitment

1. The dose or dose commitment to a MEMBER OF.THE PUBLIC from the site is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 arem) over a period of 12 consecutive months.

Reporting Requirements With the calculated dose from the release of radioactive materials in -

liquid or gaseous effluents exceeding twice the limits of Specification 7.1.1.2., 7.1.2.2., or 7.1.2.3., prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 and limit the sub-sequent releases such that the drese or dose commitment to any MEMBER OF THE PUBLIC from the site is limited to less than or equal to 25 mrem to the total body or any or'gan (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to any MEMBER OF THE PUBLIC from the site (in-cluding all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. If the estimated doses exceed the above limits, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

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21. Maximus Psrmissibio Concentr tions (Micro curie:/ml)
a. Fission and Activation Casas 3.0 E-07 Kr - 85 Kr - 85m 1.0 E-07 Kr - 87 2.0 E-08 Kr - 88 2.0 E-08 Xe - 133 3.0 E-07 Xe - 135 1.0 E-07 Xe - 135m 3.0 E-08 Xe - 138 3.0 E-08 Ar - 37 1.0 E-04
b. Iodines 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 l
d. Liquid Effluents Sr - 89 3.0 E-06 Sr - 90 3.0 E-07 1

Cs - 134 4.0 E-05 Cs - 137 2.0 E-05 I - 131 3.0 E-07

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Lieuid Effluents (Cont.)

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 No - 99 4.0 E-05 Tc - 99 3.0 E-03 34 - 140 2.0 E-05 La - 140 ,

2.0 E-05 Ce - 141 9.0 E-05

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Eu - 154 2.0 E-05 Se - 7 2.0 E-03 Ru - 106 1.0 E-05 As - 110m 3.0 E-05 Sb '124 2.0 E-05 Sb - 125 1.0 E-04 Co - 57 4.0 E-04 Ke - 133 3.0 E-06 Ke - 135 3.0 E-06 Ar - 37 3.0 E-06 Kr - 85 3.0 E-06 mi i ie is i ii

3. Average Energy (E) (MeV) Third Quarter Fourth Quarter For Fission and E Beta E Gamma E Beta E Gama Activation Gases 2.02E-01 5.17E-02 2.12E-01 5.85E-02 Measurements and Approximation 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: Continuous in-line particulate filter on main stack effluent. Particulate samples are then counted for gamma activity.

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, 90Sr, and 55 Fe are determined.
65) Batch Releases

. 'a. Liquid

1) Number of batch releases: 1.13E+02
2) Total time period for batch release: 6.24E+02 Hours
3) Maximum time period for a batch release: 2.05E+01 Hours
4) Average time period for batch releases: 5.52E+00 Hours
5) Minimum time period for a batch release: 1.67E-01 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: 1.90E+01
2) Total time period for batch releases: 3.01E+02 Hours
3) Maximum time period for a batch release: 3.09E+01 Hours
4) Average time period for batch releases: 1.58E+01 Hours
5) Minimum time period for a batch release: 7.50E-01 Hours
  1. 6) Abnormal Releases None.
  1. 7) Chances to the REMM/0DCM/PCP None.
  1. 8) Ef fluent Monitors inoperable for > 30 days None 4

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  • -- EFFLUENT AND W5STE DISPOSAL SEMI-ANNUAL REPORT 19 86

. 4 CASE 0dS EFFLUENTS-SUMMATION OF ALL RELEASES / .-

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A. FISSION & ACTIVATION GASES 1,  %

1. Total release C1 3.93E+02 1.50E+02 1.40E+01
2. Average release rate for period pCi/sec 4.94E+01 1.89E+01 ,

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1. Total iodine - 131 Ci - 8.09E-04 4 l'DL 1.30E+01
2. Average release rate for period pCi/sec 1.02E 04 p3L s

C. PARTICULATES 4

1. Particulates with half-lives

> 8 days Ci 1.49E-04 8.'PAE-04 1.40E+01

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2. Average release rate for period pCi/sec 1.87E-05 1.11E-04

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3. Gross alpha radioactivity Ci 1.59E-08 OtDL D. TRITIUM
1. Total release ci 8.05E+00 6.79E+00 8.00E+00
2. Average release rate for period pCi/see 1.01E+00 8.54E-01 i

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Data for Sr-89, Sr-90, gross A is incomplete '

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EFFLUENT AND 'WA$TE DISPOSAL SEMI- ANNUAL REPORT -1986 GASEOUS EFFLUENTS- MIXED RELEASE CONTINUOUS MODE BATCH MODE A ,

i Fourth Third Fourth FJCLIDESiRELEASED UNIT R OUARTER OUARTER OUARTER t

FISSION G'ISES-Krypt'n-85 ' Ci 1.41E+00

  • 3 ORF+01 9.7AF+01 Kryptin-8)m Ci *
  • 1 Rar+nn 1.4?F-01 sKrypt~n-S7. Ci *
  • 4.89E-02 2.36E-02 sgrypton-88 C1 .,

2.31E-01 1.25E-01 kenon-133 C1 1.92E+02

  • 1 EnF+n? 1 nor+n9 Xenon-135 Ci 'l.66E-01
  • 9.R6E+00 4.25E+00 Xenon-135m *
  • Ci 1.65E-02 1.05E-02 Xenon-138 Ci *
  • 8.80E-01 1.73F+00 Ci '

3H _ Ci 6.70E+00 4.6AF+00 1.1RF+00 2.11F+0D Arg'n 37 L * *

  • Ci 4.00E-02 Argon 41 C1 2.70E-04
  • 1.20E-01
  • X non 131M s C1 4.63E-03
  • 2.52E-01 2.92E-01 X n:n 133M \ r ,

, C1 4.31E-01

  • 5.40E+00 6.66E+00 Xenon 137 ' *
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  • 1.70E-02 3.70E-02 TOTAL FOR PERIOD * '

l' C1 1.94E+02 1.99E+02 1.50E+02 Iodinc-131 Ci 8.09E-04 * ** **

Iedin1-133 Ci * * ** **

Iodini-135 * * ** **

Ci TOTAL FOR PERIOD Ci 8.09E-04 * ** ~

PARTICULATES Ci * * ** **

Alpha C1 1.59E-08 * ** **

Str ntium-89 Ci * * ** **

Str:ntium-90 Ci * * ** **

Cr:1um-134 Ci * * ** **

C cier-137 C1 1.04E-05 4.04E-05 ** **

B rium-lanthanum-140 Ci * * ** **

C riun-144 Ci * * ** **

Cabnit-60 Ci 1.39E-04 8.44E-04 ** **

Mang:nese-54 Ci * * ** **

CtbSit-58 Ci * * ** **

Cariux-141 Ci * * ** **

Ruth niun-103 Ci * * ** **

Zirc niua/ Niobium-95 Ci * * ** **

Ruth:nium-106 Ci * * ** **

Chromium-51 Ci * * ** **

TOTAL FOR PERIOD Ci 1.49E-04 8.84E-04 ** **

  • Isotope Values ( MDL C* Reported under continuous Mode

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 19 86 ~

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES EST. TOTAL UNIT h ER bR* ERROR %

, A. FISSION AND ACTIVATION PRODUCTS

1. Total release (not including tritium, gases, alpha) C1 1.01E-01 a aqr.n? 1 inr+ni

.2. Average diluted concentration during period VCi/ml 5.49 E-10 2.43E-10 i

B. TRITIUM

1. Total release Ci 5.09E+02 1.07E+03 3.50E+00
2. Average diluted concentration during period pCi/ml 2.77E-06 5.86E-06

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C. DISSOLVED AND ENTRAINED CASES

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-1. Total release . C1 8.81E-02 3.05E-02 1.90E+01

2. Average diluted n 'eentration during period pCi al 4.79E-10 1.67E-10 n

D. GROSS ALPHA RADIOACTIVITY

1. Total release C1 1.31E-04 1.97E-05 8.00E+00  !

E. Volume of waste released (prior to dilution) Liters 4.20E+07 4.57E407 3.00E+00 F. Volume of dilution water used during period Liters 1.839E+11 1.825E+11 2.50E+00 i G.

Volume of dilution water used 2.94E+10 during releases (batch) Liters 2.21E+10 2.50E+00

  • Data for Sr-89,Sr-90, gross et is incomplete

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 19 86 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Third Fourth Third Fourth NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Strontium-89 Ci 2.74E-04 2.27E-04 4.10E-05 3.79E-05 Str ntium-90 C1 2.83E-04 3.52E-05 3.00E-05 1.29E-04 Cesium-134 C1 4.25E-03 4.98E-04 2,89E-03 7.85E-03 Ce,3um-137 C1 7.78E-03 2.49E-03 5.18E-03 2.11E-02 Iodine-131 Ci 3.65E-02 3.26E-04 4.85E-03 1.50E-04 c b-It-58 Ci *

  • 3.04E-03 2.58E-04 Cob ^1t-60 Ci 4.55E-03 4.45E-03 8.66E-03 3.41E-03 Iren-59 Ci 3.61E-04 Antimony-124 Ci *
  • 4.50E-04 3.94E-04 Manaanese-54 Ci 1.02E-03
  • 8.47E-04 7.74E-05 Chromium-51 Ci *
  • 9.43E-04 1.58E-04 Zirconium-Niobium-95 Ci Molybdenum-99 Ci *
  • 1.05E-04 *
  • 5.06E-05
  • Technetium-99m Ci lanthannm lan Ci 1.47F-04
  • 1.81E-04 7.73E-06 Corium-141 Ci * * *
  • Ci *
  • 3.61E-05
  • Barium-140
  • Cerium-144 Ci * *
  • Alphn C1 1.29E-04 1.69E-05 2.03E-06 2.75E-06 Ruth nium-106 Ci * *
  • Ci * * *
  • Silvnr-110m Ruthenium-103 Ci
  • 1.17E-05 Antimenv-125 Ci *
  • 5.45E-04 1.68E-03 Iron-55 Ci
  • 6.32E-04 Iedine-133 C1 2.62E-02 * *
  • Cesium-136 Ci 1.61E-04 .

Tetal for Period (above) Ci 8.11E-02 8.0SE-03 2.90E-02 l3.62E-02 X'nnn-133 Ci 9.87E-03

  • 4.94E-02 2.94E-02 X'n n-135 Ci 7.75E-03
  • 3.28E-04 1.07E-03 ,

Xp.133M Ci * *

  • 4.19E-05 Kryptnn-85 Ci
  • 2.07E-02 Tritium Ci 9.60E+00 3.71E+00 5.02E+02 1.07E+03 Argon-41 Ci
  • 2.29E-04
  • Is6 tope Values are U1DL.

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SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) r MONTH EST. TOTAL

1. TYPE OF WASTE UNIT PERIOD ' ERROR %

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a. Spent resins, filter m 1.348E+1 1.0 E+01 sludges, evaporator Ci bottom, etc. 4.866E+2
b. Dry compressibic m --

1 1.0 E+01 Waste, Contaminated Ci __

equip., etc.

c. Irradiated components m [~_ t 1.0 E+01 Ci
2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) in %
a. CoS7 1.03E-3 Sr90 4.11 CoS8 15.76 Pu241 0.648 Co60 10.99 cm242 0.012 Cs134 20.39 Np237 2.56E-6 Cs137 19.61 Pu238 0.012 Mn54 3.01 Pu239 1.72E-3 Cr51 3.48E-3 Pu240 1.72E-3 H3 2.26 Pu242 1.52E-5 C14 0.054 Am241 5.04E-3 Tc99 0.044 Cm243 5.17E-3 1129 5.43E-3 Cm244 5.17E-3 Ni63 2.19 Fe55 20.85 4

3.- SOI,ID WASTE DISPOSITION MODE OF TRANSPORTATION DESTINATION NUMBER OF SHIPMENTS Truck Barnwell, S.C.

4 B. IRRADIATED FUEL SHIPMENTS'(DISPOSITION)

NONE C. ADDITIONAL INFORMATION

1. Solidification Agents utilized : Cement
2. Container Information:

(A.1.a) High Integrity Containers 119 ft 3 193 ft3 Steel Liners 182 ft 3 (A.I.b) Steel Boxes 96 ft3 i

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CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N, CON N ECTICU T P o. box 270 + HARTFORD, CONNECTICUT 06141-0270 h] February 27,1987 Docket No. 50-213 B12433 Re: 10 CFR 50.36a U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Haddam Neck Plant Semiannual Radioactive Effluents Release Report In accordance with the requirements of 10 CFR 50.36a and the Radiological Effluent Technical Specifications, a copy of the Semiannual Radioactive Effluents Release Report is herewith subrnitted.

This report includes a summary of the quantities of solid-radioactive waste, and liquid & gaseous effluents for the period of July - December,1986. An Annual Radioactive Effluents Dose Report (to be submitted in March,1987) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released during the previous calendar year (January - December,1986).

Due to unavoidable delays in sample analysis, results for Sr-89, Sr-90, and gross alpha for the last quarter of 1986 are incomplete. These results will be forwarded as soon as they become available.

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 10 CFR 50.4(b)(2)(viii).

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY U.d.U '

E. 3. Mroczka Senior Vice President b

By: C. F. Sears Vice President i

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4 l ~cc: . Dr. T. E. Murley, Region I Administrator P. D.'Swetland, Resident NRC Inspector, Haddam Neck Plant '

J F. M.' Akstulewicz, NRC Project Manager, Haddam Neck Plant 3

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