ML20235U277

Semiannual Radioactive Effluents Release Rept,Jul-Dec 1988

ML20235U277
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1988
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20235U279	List: B13139, Forwards Haddam Neck Plant Semiannual Radioactive Effluents Release Rept Jul-Dec 1988. Annual Radioactive Effluents Dose Rept to Be Submitted in Mar 1989 to Include Assessment of Radiation Doses Due to Stated Effluents During CY88 ML20235U277
References
NUDOCS 8903090124
Download: ML20235U277 (12)

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a s SEMIANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT JULY-DECEMBER 1988

. DOCKET NO. 50-213 i

LICENSE DPR-61 l

1

NORTHEAST UTILITIES c,,n.,,i Omc.. . s,io n si,,,,, e.,iin, Conn.ciicui

" ' " " ' ' P.O. BOX 270

,,',"*"" - HARTFORD, CONNECTICUT 06141-0270

' J N. mar C'((,,$,,,,c.

.sv.uca a s.naavco. , (203) 665-0000 February 28, 1989 Docket No. 50-213 B13139 Re: 10CFR50.36a U.S. Nuc. lear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Haddam Neck Plant Semiannual Radioactive Effluents Release Report In accordance with the requirements of 10CFR50.36a, the Technical Specifica-tions and the Radiological Effluents Monitoring Manual, a copy of the Semi-annual Radioactive Effluents Release Report is herewith submitted.

This report includes a summe.ry of the quantities of solid radioactive waste and liquid and gaseous effluents for the period of July through December 1988.

An Annual Radioactive Effluents Dose Report (to be submitted in March 1989) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents during the calendar year (January through December 1988).

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 Y . .) , O rct A E. J. Mroczka Senior Vice President h

b?ubth-By: C. F. Sears

• Vice President cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant

TABLE OF CONTENTS e-Table of Con ten ts .. .. . .. . . . . . ... . . .... .... ... . .. .. ... .. .. . . .. . . . ... ... . . ... . .... ... . ... .. ... . . ....... ..... 1 I n trod u'c ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . 2 . . . . . .. . . . . . . . . . . . . . .. . . . . . .

Radiological Effluents Information ........................................................ 3-4 Gaseous Effluents - Summation of all Releases ................................ 5 Gaseous Effluents - Mixed Mode Release ............................................ 6 Liquid Effluents. - Summation of all Releases ................................... 7 Liquid Effluents - B atch and Continuous ............................................. 8 SolidWaste....................................................................................................... 9-10 Iof10 i

i

Introduction 4

This report is submitted for the Connecticut Yankee Atomic Power Company's Haddam Neck Plantin accordance with the requirements of10CFR50.36a, and the Radiological Effluent Technical Specifications and in the format outlined by the U.S.NRC Regulatory Guide 1.21.

During the period July-December 1988 the Haddam Neck Plant operated with a 97.5% capacity factor of the Design Electrical Rating (DER).

This report , resents data on radioactive materials in airborne and liquid effluents as well as solid radioactive waste shipped offsite during that period.

Based on comparisons with data from previous years, the amount of radioactive materials released during this period will result in doses well within regulatory limits. A detailed calculation of the dose consequences will be provided in the Annual Radioactive Effluents Dose Report to be submitted on March 30,1989.

2cf]0

1 Radiological Effluents Information Third Quarter Fourth Quarter

. I. Average Energy (E)(in Mev/ dis) E Beta E Gamma E Beta E Gamma For Fission and Activation Gases 2.21E-01 1.08E-01 1.99E-01 5.73E-02 11 Measurements and Approximation ofTotal Radioactivity j

a. Fission and Activation Gases: Stack effluents are monitored for gross activity by a scintillation detector in aarallel with an in-line G. M. Detector. Gas samples are collected on the stack anc are analyzed for low level fission and activation gases on a GeLi system for nuclide identification.

b. Iodines: Continuous in-line charcoal sample filter on main stack effluent.

Charcoal filters are then analyzed for iodines on a GeLi detector.

c. Particulate: Continuous in-line particulate sample filter on main stack effluent.

Particulate samples are then counted for gamma activity on a GeLi detector.

A monthly composite is made from weekly samples and is analyzed for gross alpha and 89Sr/90Sr.

d. Liquid Effluents: In-line scintillation detectors monitor 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 batch and weekly samples. Gross alpha,89Sr,90Sr, and 55Fe are determined on the monthly composite.

III. Radioactive Effluents McnitorInoperability ( > 30 days)

None 1

IV. REMM/ODCM/PCP Chances None S of l0

i 9

V- Batch Releases

a. Liquid I Number of batch releases: 63 1) 2)- Total time period for batch release: 325 Hours

3) Maximum time period for a batch Irlease: 16.6 Hours

4) Average time period for batch release: 5.16 Hours l

5) Minimum time period for a batch release: 2.75 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: 6

2) Total time period for batch releases: 776 Hours

3) Maximum time period for a batch release: 316 Hours

4) Average time period for batch releases: 129 Hours

5) Minimum time period for a batch release: 2.25 Hours VI Abnont.al Releases

• None

• Releases that exceed Technical Specification Limits 4 of 10

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT - 1988

. GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES 3rd 4th EST. TOTAL l UNIT QUARTER QUARTER ERROR % l A. FISSION & ACTIVATION GASES I

i

1. Tota 1 release Ci 2.20E+02 7.18E+02 1.40E+01

2. Average release rate for period Ci/sec 2.77+01 9.03E+01  !

B. IODINES

1. Total Iodine - 131 Ci 6.93E-06 1.57E-05 1.30E+01

2. Average release rate for period pCi/sec 8.74E-07 1.98E-06 C. PARTICULATE i

1. Particulate with half-lives

> 8 days Ci 4.32E-05 2.03E-05 1.40E+01

2. Average release rate for period pCi/sec 5.43E-06 2.55E-06

3. Gross alpha radioactivity Ci 1.41E-06 <MDA D. TRITIUM

1. Total release Ci 7.94E+00 6.08E+01 8.00E+00

2. Average release rate for period pCi/sec 9.99E-01 7.65E+00 5 of 10

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT - 1988 GASEOUS EFFLUENTS - MIXED MODE RELE ASES l i

CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER FISSION GASES Argon-41 Ci d1DA d1DA 4.18E-01 2.87E-01 Krypton-85 Ci diDA d1DA 6.76E+00 2.76E+00 Krypton-85m Ci diDA diDA 2.35E+00 9.39E-01 Krypton-87 Ci diDA diDA 2.18E+00 8.71 E-01 Krypton-88 Ci diDA d1DA 3.26E+00 1.26E+00 Xenon-131m Ci diDA diDA 7.78E-01 6.45E-04 Xenon-133 Ci 1.04E+02 6.38E+02 7.90E+01 5.30E+01 Xenon-133m Ci diDA diDA 1.31E+00 8.81E-01 Xenon-135 0 3.13E+00 1.25E+01 1.56E+01 5.90E+00 Xenon-135m Ci diDA diDA 2.44 E-01 2.92E-01 Xenon-137 Ci etDA diDA 1.71 E-02 3.27E-01 Xenon-138 Ci d1DA d1DA 5.57E-01 7.85E-01 TOTAL FOR PERIOD Ci 1.07E+02 6.51 E+02 1.12E+02 6.73E+01 H-3 Ci 7.94E+00 6.08E+01 diDA diDA Halogens Ci lodine-131 Q 6.93E-06 1.57E-05 ** **

Iodine-133 Ci etDA diDA ** **

lodine-135 Ci d1DA d1DA ** **

TOTAL FOR PERIOD Ci 6.93E-06 1.57E-05 diDA diDA PARTICULATE Alpha Q l.41 E-06 d1DA ** **

Chromium-51 Q diDA d1DA ** **

Manganese-54 O d1DA diDA "

d1DA diDA ** **

Cobalt-58 Ci Cobalt-60 Q l .55E-05 1.09E-05 diDA ** **

Strontium-89 Ci diDA 4.49E-06 1.10E-06 ** **

Strontium-90 Ci O d1DA d1DA ** **

Zirconium / Niobium-95 _

Ruthenium-103 Q d4DA d4DA **

Ruthenium-106 Q d1DA d1DA Cesium-134 Q diDA d1DA ** **

Cesiurn-137 0 2.18E-05 8.31E-06 diDA ** **

Barium-Lanthanum-140 Ci diDA d1DA ** **

Cerium-141 Ci diDA d1DA d1DA ** **

Cerium-144 C1 TOTAL FOR PERIOD Ci 4.32E-05 2.03E-05 Reported under continuous mode.

l 6 of 10 1

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT - 1988 LIOUID EFFLUENTS SUMMATION OF ALL RELEASES l

3rd 4th EST. TOTAL UNIT QUARTER QUARTER ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. Total release (not including tritium, noble gases, alpha) 0 1.98 E-01 2.97E-02 1.10E+01

2. Average diluted concentration during period pCi/ml 1.06E-09 1.57E-10 B. TRITIUM

1. Total release O 2.53E+02 5.08E+02 3.50E+00

2. Average diluted concentration during period pCi/ml 1.36E-06 2.68E-06 C. DISSOLVED & ENTRAINED GASES

1. Totalrelease O 5.75E-03 2.10E-02 1.90E+01

2. Averagedilutedconcentration during period pCi/ml 3.09E-11 1.11E-10 D. GROSS ALPIIA RADIOACTIVITY

1. Totalrelease O 2.26E-04 1.83E-04 8.00E+00 E. Volume of waste released (prior to dilution) Liters 3.43E+07 2.99E+07 3.00E+00 F. Volume of dilution water used during period Liters 1.86E+11 1.89E+11 2.50E+00 4

7 of 10

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT 1988 LIOUID EFFLUENTS CONTINUOUS MODE BATCll MODE 3rd 4th 3rd 4th NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Alpha Ci diDA 5.23E-06 2.26E-04 1.78E-04 Chromium-51 O diDA diDA ofDA diDA Manganese-54 Ci diDA diDA 4.76E-04 1.11 E-05 Iron-55 Ci diDA diDA 1.01E-03 1.48E-02 Cobalt-57 O diDA d1DA diDA d1DA Cobalt-58 O diDA d1DA 8.47E-03 5.16E-04

~

Iron-59 Q diDA diDA diDA d1DA Cobalt-60 Ci diDA diDA 2.17E-02 1.38 E-02 Strontium-89 Ci d1DA d1DA 1.09E-05 1.03E-05 Strontium-90 Ci diDA diDA 9.48E-04 2.11 E-05 Zirconium-Niobium-95 Ci diDA diDA d1DA diDA Ruthenium-103 Ci efDA diDA diDA diDA Ruthenium-106 Ci diDA diDA <MDA diDA Silver-110m Ci diDA d1DA diDA d1DA Antimony-124 C1 diDA diDA diDA diDA Antimony-125 Ci <MDA diDA 41DA diDA lodine-131 Ci 1.09E-02 diDA d1DA d1DA lodine-132 Ci 2.90E-02 diDA diDA diDA lodine-133 Ci 3.59E-02 diDA diDA d1DA lodine-134 0 4 ^ 4E-02 (MDA diDA d1DA Cesium-134 Cl 4DA <MDA 2.54E-04 d1DA lodine-135 Ci 4.36E-02 diDA diDA 41DA Cesium-137 Ci 4.21E-04 d1DA 1.llE-03 3.10E-04 Barium-Lanthanum-140 Ci diDA diDA diDA diDA Cerium-144 Ci d1DA d1DA d1DA <MDA Total for Period (above) Ci 1.63E-01 5.23E-06 3.42E-02 2.96E-02 Tntium C1 2.22E+00 1.34E+00 2.50E+02 5.07E+02 Krypton-85 Ci diDA diDA d1DA d1DA Xenon 131M Cl diDA d1DA diDA diDA Xenon-133 Ci 1.16E-03 3.55E-03 4.57E-03 1.70E-02 Xenon-133M Ci diDA d1DA diDA diDA Xenon-135 Ci diDA 2.61E-04 3.12E-05 1.09E-04 8 of 10

.+.

SOLID WASTE AND IRR ADIATED FitEL SHIPMENTS

' A. SOLID WASTE SHIPPED OFFSITE FOR BUPIAL OR DISPOSAL NOT IRRADIATED FUEL) 6-Month EST. TOTAL

, 1. TYPE OF WASTE UNIT E< nod ERROR %

a. Spent resins, filter m3 6.18E+00 sludges, evaporator Ci 2.19E+02 1.0E+01 bottom, etc.

b. Dry compressible m3 4.94E+01 Waste, Contaminated Ci - 7.21E+00 1.0E+01 equip., etc.

c. Irradiated components m3 -

Ci 1.0E+01

2. ESTIMATE OF M AJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)in %

a. Co60 16.38 b. Co60 19.8 Cs137 40.03 Cs137 3.5 Cs134 3.92 Co58 5.47 CoS7 .01 Cs134 2.00 CoS8 ' 2.65 Mn54 1.58 Mn54 0.40 H3 .385 Fe59 .01 Cl4 .377 Cr51 1.50 Tc99 1.329E-03 H3 .01 1129 1.54E-03 Cl4 .06 Ni63 4.16 Tc99 6.02E-04 Fe55 61.5 1129 1.57E-04 Sr90 5.94E-03 Ni63 4.85 Pu241 1.11 Fe55 29.45 Cm242 1.93E-02 Sr90 .28 Pu238 4.12E-02 Pu241 .32 Pu239 6.18E-03 Cm242 .02 Pu240 6.18E-02 Pu238 .01 Am241 2.37E-02 Pu239 2.518E-03 Cm243 1.34E-02 Pu240 2.518E-03 Cm244 1.34E-02 Am241 7.95E-03 i Cm243 5.712E-03 Cm244 5.712E-03 9 of 10

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3. SOLID WASTE DISPOSITION

• ~

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION

, 4 -Truck Barnwell, SC Richland,WA B. IRRADI ATED FUEL SHIPMENTS (DISPOSITION)

None C. ADDITIONALINFORMATION

1. Solidification Agents Utilized: N/A

2. ContainerInformat' ion:

- High Integrity Containers 119 ft3 High Integrity Containers 193 ft3 Steel Liners 182 ft3 Steel Boxes 96 ft3 l

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