B12830, Semiannual Radioactive Effluents Release Rept for Jul-Dec 1987

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Semiannual Radioactive Effluents Release Rept for Jul-Dec 1987
ML20147C384
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/31/1987
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20147C373 List:
References
B12830, NUDOCS 8803030063
Download: ML20147C384 (17)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT -

SEMIANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT JUL Y-DECEMBER 1987 DOCKET NO. 50-213 LICENSE DPR-61 Tii 'i R

9 888 888PDR  % 9(A

CONNECTICUT Y AN KEE AT O MIC POWER COMPANY e B E R L I N. C O NN E CT IC U T i

P O BOX 270 e HARTFORD. CONNECTirVT 061414270 February 24, 1988 T Et t*MONE

'""* Docket No. 50-213 B12830 Re: 10CFR50.36a U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Haddam Neck Plant Semiannual Radioactive Effluents Release Recort in accordance with the requirements of 10CFR50.36a, the Safety Technical Specifications and the Radiological Effluents Monitoring Manual, a copy of the Semiannual Radioactive Effluents Pelease Report is herewith submitted.

This report includes a summary of the quantities of solid radioactive waste and liquid and gaseous effluents for the period of July - December,1987. An Annual Radioactive Effluents Dose Report (to be submitted in March, 1988) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents during the calendar year (January - December,1987).

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 10CFR50.4(b)(1).

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY E . h . D rMg E. J. Mroczka "

Senior Vice President Mb.U1 By: C. F. Sears Vice President cc: W. T. Russell, Region 1 Administrator A. B. Vang, NRC Project Manager, Haddam Neck Plant J. T. Shodiosky. Senior Resident inspector, Haddam Neck Plant

TABLE OF CONTENTS Radiological Ef fluents Inf orm' tion . . . . . . . . . .

  • l-2 Gaseous Effluents - Summation of all Releases . . . . . 9 Gaseous Effluents - Mixed Mode Release . . . . . . . . 10 Liquid Effluents - Sum: nation of all Releases . . . . . . 11 Liquid Effluents - Batch and Continuous . . . . . . . .

12 Solid Waste . . . . . . . . . . . . . . . . . . . . . . 13-14 l

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' Radialogical Efflu;nts informaticn is ,

I. Regulatory Limits A. Specifications for Caseous 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 f ollowing values:
1) The dose rate limit for noble gases shall be less than or equal to 500 ares /yr to the tots 1 body and less than or equal to 3000 aree/yr to the skin, and 11)

The dose rate limit due to inhalation for fodine-131, iodine-133, tritiu: and for all radioactive materials in particulate fore with half lives greater than 8 days shall be less than or equal to 1500 are=/yr to any organ.

2. The air dose of f site due to noble gases released in gas-

. eous ef fluents shall be li=ited to the f ollowing:

1) During any calendar quarter, to less than er equal to 5 mrad f or gn==a radiation and less than er equal to 10 trad for beta radiation;
11) 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 geses in gaseous k'ith the calculated air dose from radicactive no'in ef fluents exceeding any of the above limits, prepate anc sekeit to the Co==ission 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 noble gases in gasecos ef fluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cu=ulative dese during the calendar year is within 1C erad f or gn==a radiation and 20 erad for beta radiation.

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3. Specifications for Radioactive Effluents in Particulate Form .
1. The dose to any MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritius. and radioactive materials in partie-ulate form with half lives greater than 8 days in gas-eous effluents released offaite shall be limited to the following:

i) 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 aree to any organ.

Reporting Require ents With the calculated dose fro: the release of radionuclides, radioactive mater.als jn particulate fore, or radionuclides other than noble gases in gaseous efiNents exceeding any of the above licits, prepare and sub it to the Co==ission 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 retainder of the current calendar quarter and during the remainder of the calendar year so that the cut-alative dose or dose co=.iteent to any MEMBER OF THE PUBLIC f rom such releases during the calendar year is within 15 aren to any organ.

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C. Specifications for Liquid Vaste Effluents .

1. The concentration of radioactive material released from the site shall not exceed the cricentrations specified in 10 Crk Part 20, Append!x 5. Table 11. Column 2 for radionuclides other than disso1'ad or entrained noble gases. For dissolved or entrained noble s: ses. The concentration shall not ex-caed 2 x 10-4 uCi/ml total activity.
2. The dose or dose con =itment to any MIF3ER OT THE PUBLIC fro:

radioactive materials in liquid effluents released from the site shall be limited:

1) During any calendar quarter to less than er equal to 1.5 aren to the total body and to less than or. equal to 5 cre: to any organ, and
11) During the calendar year to less than or equal to 3 mre to the total body ani to less than or equal to 10 cre: to any organ.

_Reperting T;equireeents With the calculated dose from the release of radioac'tive materials in liquid ef fluents exceeding any of the above limits, prepare and sub=1t to the Com=ission within 30 osys, pursuant to Specification 6.9.3, a Special Report which identifies the cause(s) for exceeding the the licit (s) releases and' defines the corrective actions to be taken to redu.

of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the recainder of the calendar year so that the cumulative dose or dose ce=:iteent to any MIM3ER OT TdE PUBLIC fro: such rele.'se during the calendar year is within 3 nree to the total body and 10 nree to any organ.

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D. Specification for Cumulated Dose Commitment

1. The dose or dose coumitment to a MIKBER OF THE FUBLIC free the site is lisited to less than or equal to 25 arem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 ares) over a period of 12 consecutive months.

Reporting Requirements With the calculated dose free the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 7.1.1.2. , 7. 3.2.2. , or 7.1.2.3. , prepare and sub=1t a Special Report to the Co==ission pursuant to Specification 6.9.3 and limit the sub-sequent releases such that the dose or dose co= itment to any MIM3ER OT THE PUBLIC from the site is limited to less than or equal to 25 tre= te the total bod / or any organ (except thyroid, which is limitedThis to less than or equal to 75 rree) over 12 consecutive months.

Special Aeport shall include an analysis which demonstrates that radiation exposures to any MIN 3ER OT THE PUBLIC f rom the site (in-cluding all effluent pathways and direct radiation) are less than the 40 CTR Part 190 Standard. If the estimated doses exceed the above limits, the special report shall include a request for a variance in Subeittal of the report accordance with the provisions of 40 CTR 190.

is considered a timely request, and a variance is granted until staf f action on the request is co:plete.

2 3, Maxime Formissible Concentreticas (Micra C+; ries /al)

a. , Fission and Activation Cases Kr - 85 3.0 E-07 .

Yz - 85m 1.0 E-07 Kr - 87 2.0 1-08 Kr - 88 2.0 E-08 Ia - 133 3.0 E-07 Ia - 135 1.0 E-07 Xe - 135m 3.0 E-08 Is - 138 3.0 E-08 Ar - 37 1.0 E-D4

b. Iodices I - 131 1.0 E-10 1 ,'133 4.0 E-10 1 - 135 1.0 E-09 I
c. Particulatas ,141f-Lives > 8 Davs 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 l La - 140 4.0 E-09
d. Liquid Effluents Sr - 89 3.0 E-96 Sr - 90 3.0 E-07 Cs - 134 4.0 E-05 Cs - 137 2.0 E-05 I - 131 3.0 E-07 l

Liquid Effluente (Cont.)

Co - 58 9.0 E-05 Co - 60 3.0 E-05 Te - 59 5.0 E-05 En - 65 1.0 E-04 Mn - 54 1.0 E-04 Cr - 51 2.0 E-03 Ir - 95 6.0 E-05 Nb - 95 1.0 E-04 No *9 4.0 E-05 j

Tc - 99: 3.0 E-03 u - 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 As - 110m 3.0 E-05 Sb '124 2.0 E-05 1.0 E-04 Sb - 125 C4 - 57 4.0 E-04 Xe - 133 3.0 E-06 Ie - 135 3.0 E-06 Ar - 37 3.0 T-06 Kr - 85 3.0 E-06

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I 3 - Average Energy (E) (MeV) Third Ouarter Fourth Ouarter For Fission and E.Bela E Gamma E Beta E. Gamma Activation Gases 1.98E 01 4.75E 02 2.43E-01 7.75E 03 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 sam?l es are then counted for gamma activity. A monthly composite is made from wee dy 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.

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  1. 5 Batch Releases
a. Liquid
1) Number of batch releases: 87
2) Total time period for batch release: 591.87 Hours
3) Maximum time period for a batch release: 41.4 Hours
4) Average time period for batch release: 6.80 Hours
5) Minimum time period for a batch release: 0.67 Hours
6) Average stream Dow during periods of 15,800 cubic feet release of ef0uent into a Dowing per second stream:
b. Gaseous
1) Number of batch releases: 12
2) Total time period for batch releases: 156.85 Hours
3) Maximum time period for a batch release: 22.55 Hours
4) Average time pericd for batch releases: 13.07 Hours
5) Minimum time period for a batch release: 6.75 Hours 06 Abnormal Releaes None e

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EFFLUENT & WASTE DISPOSAL SEMI ANNUAL REPORT 1987 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Third Founh E.ST.T OT A L UNIT QUARTER QUARTER ERRORG A. FISSION & ACTIVATION G ASES

1. Totalrelease C1 2.666E+03 1.901 E-01 1.40E+01
2. Average release rate for period pCi/sec 3.354E+02 2.392E-02 B. IODINES
1. Total Idne - 131 0 5.212E 04 < MDL 1.30E+01
2. Average release rate for penod pCusec C. PARTICULATES
1. Particulates with halt-hves

> Sdays Ci 4.527E 04 2.454E-04 1.40E+01

2. Average release rate for penod pCusec 5.695E 05 3.087E 05
3. Gross alpha radioactivity Ci 6.921E-06 7.033E-07 D. TRITIUM
1. Totalrelease Ci 2.8451E+01 2.077E+01 8.00E+00
2. Average release rate for penod pCVsec Page 9

EFFLUENT & WASTE DISPOSAL SEhfI. ANNUAL REPORT - 1987

- G ASEOUS EFFLUENTS HlXED MODE RELEASE CONTINUOUS hiODE BATCH hiODE nird Fouth Third Fouth NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER FISSION GASES Krypton 85 Ci 2.762E+01 <htDL 8.79E+01 1.657E 01 Krypton 85m Ci <hiDL 1.02bE+00 <h1DL Krypton 87 C1 9.947E-Ol

_ Krypton 88 Ci 1.374E+00 Xenon 131m Ci 4.475E-01 Xenon 133 Ci 2.036E+03 4.717E+02 2.444E-02 Xenon 133m Ci 9.258E+00 4.406E+00 <51DL Xenon 135 Ci 1.247E+01 9.798E+00 Xe.w. .35m Ci <h1DL 4.475E 01 Xenon 137 Ci 1.410E+00 Xenon 138 Ci 1.535E+00 Argon 41 Ci 1.649E-01 TOTAL FOR PERIOD Ci 2.085E+03 <h1DL 5.813E+02 1.901E 01 E:, Ci 2.645E+01 2.077E+01 2.041 E+00 5.904E 05 lodine 131 Ci 5.212E-04 <h1DL lodine l.T3 Ci <h1DL lodine-13:. Ci TOTAL FOR PERIOD Ci 5.212E-04 <h1DL <h1DL <hiDL PARTICULA'."ES ~

Ci Alpha Ci 6.921E-06 7.033E-07 Chromium-51 Ci <hiDL <hiDL

  • hianganese-54 Ci

! Cobalt 58 Ci 1.540E-05 4.203E-05 Cobalt-60 Ci 3.626E-04 1.334E-04 ._

Strontium-b9 Ci 9.676 E-07 2.992E-07 Strontium-90 Ci 6.159E-06 4.739E-06 Zirconium / Niobium-95 Ci <htDL <h1DL Ruthenium-103 Ci Ruthenium-106 Ci -

Cesium 134 Ci Cesium-137 Ci 4.066E-05 6.418E-05 Barium Lanthanum-140 Ci <hiDL <hiDL

  • Cenum 141 Ci Cerium 144 Ci TOTAL FOR PERIOD Ci 4.527E-04 2.454E-04

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. ' EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT 1987 L10UID EFFLUENTS SUMMATION OF ALL RELEASES Third Founh . 'EST.T OT A L UNIT QUARTER QUARTER' ERRORG A. FISSION & ACTIVATION PRODUCTS

1. Total release (not including tritium, gases, alpha) Ci 1.94E 01 7.90E-02 1.10E+01
2. Average diluted concentration during period pCi/ml 2.55E-09 2.76E-09 B. TRITIUM
1. Total release Ci 6.13E+02 1.19E+01 3.50E+00
2. Average diluted concentration during period Ci/mi 8.06E-06 4.16E-07 C. DISSOLVED & ENTR AINED G ASE S
1. Total release Ci 1.23E-01 dtDL 1.90E+01
2. Average diluted concentration during period pCi/ml 1.62E-09 dlDL D. GROSS ALPIIA R A DIO ACTIVITY
1. Total release Ci 6.70E 06 6.51E 06 8.00E+00 E. Volume of waste released (pnor to dilution) Liters 1.19E+07 1.45E+06 F. Volume of dilution water used during period Liters 7.61E+10 2.86E+10 Page 11

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EFFLUENT & WASTE DISPOSAL SEN11 ANNUAL REPORT 1987 LIOUID EFFLUENTS CONTINUOUS h10DE BATCHN10DE Third Founh nird Fourth NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Alpha Ci (MDL NOTE 1 6.70E-06 6.51 E-06 Chromium-51 Ci 1.02E-02 1.12E 03 hiancanese-54 Ci 4.96E-03 1.94E-03 fron-55 Ci 8.60E-03 6.39E 03 Cobalt-57 Ci 6.43E-05 d1DL Cobalt 58 Ci 2.95E-02 1.47E-02 1ron-59 Ci 2.03E-03 1.I1E-03 Cobalt-60 Ci 8.02E 04 1.19E-01 4.64 E-02 Strontium 69 Ci 2.59E-05 2.91E-05 6.24 E-Ob Strontium 90 Ci 2.22E-05 5.72E-05 9.46E-06 Ztrconium-Niobium 95 Ci diDL 2.77E 04 61DL hiolybdenum 99 Ci 9.64E-05 Technetium-99m Ci 3.54E-03 Ruthenium-103 Ci 6.45E 04 Ruthenium loo Ci 1.30E-03 Silver-110m Ci <hiDL Andmany 124 Ci 3.60E 04 Andmony 125 Ci 1.92E-04 lodine-131 Ci 7.I1E 04 lodine 133 Ci d1DL Cesium 134 Ci 2.60E-03 1.blE 03 Cesium-137 Ci 4.97E 04 7.25E-03 5.51 E-03 Banum-Lanthanum-140 Ci d1DL l.11E-04 diDL Cenum 141 Ci 4.66E-05 Cerium-143 Ci 5.71E-05 Cenum 144 Ci 8.09E 05 Total for Period tabove) C1 1.35E-03 1.91 E-01 7.90E 02 Trinum Ci 1.3bE 01 6.13E+02 1.19E+01 Krypton-85 Ci d1DL otDL diDL Xenon 133 Ci l .19 E-01 Xenon 135 Ci 3.71 E-03 l

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1) No continuous discharges in founh quaner I

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,, g* . SOLID WASTE AND IRRADIATED FUEL SHIPME*'TS A. SOLID WASTE SHIPPED OFTSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-NONTH EST. TOTAL

1. TYPE OF WASTE UNIT PERIOD ERFOk %
a. Spent resins, filter. m 2.3846E+1 2 1.0 E+01 sludges, evaporator C1 2.2275E+2 bottom, etc.
b. Dry coepressible m 2.0561E+2 1 1.0 E+01 Waste, Contaminated Ci 7.473E+0 equip., etc.

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c. Irradiated components m N/A t 1.0 E+01 Ci l
2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (EY TYPE OF WASTE) In %
a. Co60 16.23 b. Co60 19.80 Csl37 16.99 Csl37 3.50 ,

Csl34 10.77 CoSB 5.47

! CoS8 5.31 Cs134 2.00

  • l Mn54 1.464 Mn54 1.58 4

Fe59 .0245 H3 .385 l Cr51 2.843 Cl4 .377 '

H3 .0246 Tc99 1.329E-3 i CI4 .0972 1129 1.154E-3 i Tc99 7.96E-4 N163 4.16 i

1129 1.204E-4 Fe55 61.5 Ni63 4.052 Sr90 5.945E-3  :

Fe55 41.77 Pu241 1.11 l

Sr90 .1446 cm242 1.963E-2 Pu241 .1742 Pu238 4.124E-2 Cm242 .0311 Pu239
  • 6.185E-3 Pu238 .028 Pu240 6.185E-3 i Pu239 4.19E-3 Am241 2.371E-2  !

l Pu-240 4.19E-3 Cm243 1.340E-2  ;

l Am241 .0146 Cm244 1.340E-2 l l

Cm243 .013 -

Cm244 .013

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3. SOLID WASTE DISPOSITION NDiBER OF SHIPMESTS MODE OF TRASSPORTATION DESTINATION Truck Barnwell, SC. and

, 14 Richland, WA.

B. IRRADIATED TUEL SHIPMENTS (DISPOSITION)

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