B13347, Semiannual Effluents Release Rept, Jan-June 1989
| ML20246F227 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/30/1989 |
| From: | Mroczka E, Sears C CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B13347, NUDOCS 8908300213 | |
| Download: ML20246F227 (12) | |
Text
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- NORTHEAST UTILITIES con ,, Omc.. . somen si,,,i se,nn, Conn cuco, !
'; 1 . .S n$a =w P.O. BOX 270 g '
I N .n U . c1 . HARTFORD. CONNECTICUT 06141-0270 '
nomme mim ewaw w= (203) 665-5000 j J
August 23, 1989 Docket No. 50-213 B13347 q l
Re: 10CFR50.36a i I
U.S. Nuclear Regulatory Commission 2 Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Haddam Neck Plant Semiannual Radioactive Effluents Release ReDort i In accordance with the requirements of 10CFR50.36a, the Technical Specifica- j tions ' and the Radiological Effluents Monitoring Manual, a copy of the Semi- ?
annual Radioactive Effluents Release 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 January through June 1989.
An Annual Radioactive Effluents Dose Report (to be submitted in March 1990) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents during the calendar year (January through December 1989).
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 t .h.N w "
E. J. Mroczka Senior Vice President
- t. ,,. LSO By: C. F. Sears j Vice President W. T. Russell, Region I Administrator cc:
A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant ,
8908300213 890630 i PDR ADOCK 05000223L R PNU-
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1 TABLE OF CONTENTS p ..
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, Table of Contents ..... .................... ... ........... ....... .... ..... .. .. . ... . ..... ... .... . . ...... .. 1; ...
! f
~ l n trod u c ti o n ~ . . . . .. . . . . . .. . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . .. ... .. . ... . ... .. .... . .. . .. ... .... ... ... .- . . 2-
' Radiological Effluents Information ........................................................ ~ 3 - 4.
Gaseous Effluents - Summation of all Rel. eases ................................ 5 Gaseous. Effluents - Mixed Mode Release ............................................ 6'
' Liquid Effluents - Summation of all Releases ............. ..................... 7
.i' .
E Liquid Effluents -- Batch and Continuous ...................... ...................... 8.
SolidWaste......'................................................................................................. 9-10
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- Introduction 1
[
p This report is submitted for the Connecticut Yankee Atomic Power Company's Haddam Neck Plant in accordance with the requirements of 10CFR50.36a, and the Radiological Effluent Technical Specifications, and in the format outlined by the U.S.NRC Regulatory Guide 1.21 During the period January - June 1989, the Haddam Neck Plant operated with an 84.9%
capacity factor of the Design Electrical Rating (DER).
This report presents data on radioactive materials in airborne and liquid effluents as well as solid radioactive materials shipped offsite during that period.
Based on previously reported dh.3, the amount of radioactive materials released in effluents would result in doses well within regulatory limits. These dose consequences will be provided in the Annual Radioactive Effluent Dose Report to be submitted on March 30,1990.
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RADIOLOGICAL EFFLUENTS INFORMATION First Ounrter Second Ouarter 1 ' Average Energy (E) (in MeV) E Beta 5 Gamma E Beta 5 Gamma j For Fission and Activation Gases 1.98E-01 5.37E-02 1.08E-01 4.88E-02 II Measurements and Approximation of Total Radioactivity I
- a. Fission and Activation Gases: Stack effluents are monitored by a scintillation detector in parallel with an in-line G. M. Detector. Gas samples are collected on the stack and are analysed for low level fission and activation gases. '
- b. Iodines: Continuous in-line charcoal sample filter on main stack effluent. Charcoal filters are then analysed for iodines.
- c. Particulate: Continuous in-line particulate sample 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. Liould 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 55 Fe are determined.
III Radioactive Effluents Monitor Inoperability (> 30 days)
On June 16,1989, test tank monitor R-22 was declared out of service due to inability of the check source to be read.
The cause was due to intemal background around the detector from plateout. Efforts are underway to correct the platcout problem and restore the monitor to service. The trip set point function is backed up by monitor R.18, thereby providing automatic termination of release should the trip set point be exceeded.
IV REMM/ODCM/PCP Changes None 3 of 10
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'I V Batch Releases
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- a. Liquid j
- 1) Number of batch releases: 112
' 2) Total time period for batch release: j 528.05 Hours ,
- 3) Maximum time period for a batch release: 8.50 Hours
- 4) Average time period for batch release: 4.72 Hours
- 5) Minimum time period for a batch nicase: 2.08 Hours l
- 6) Average stream flow during periods of . 15,800 cubic feet f mlease ofeffluent into a flowing per second satam:
- b. Gaseous l 1) Number of batch releases: 2 i
- 2) Total time period for batch releases: 60.52 Hours
- 3) Maximum time period for a batch release: 54.50 Hours
- 4) A verage time period for batch releases
- 30.26 Hours
- 5) Minimum time period for a batch release: 6.02 Hours VI Abnormal Releases
- None 1
0 Releases that exceed Technical Specification Limits l
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EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT - 1989
.y -' . GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES e
1st 2nd EST. TOTAL UNIT QUARTER QUARTER ERROR %
A. FISSION '& ACTIVATION GASES
- 1. Totalrelease Ci 1.31 E+03 2.28E+03 1.40E+01
- 2. Average release rate for period pCi/sec 1.68E+02 2.93E+02 B. IODINES
- 1. Total Iodine - 131 Ci dfDA 9.54E-06 1.30E+01
- 2. Average release rate for period pCi/sec N/A 1.22E-06 C. PARTICULATE
- 1. Particulate with half-lives
> 8 days Ci 3.15E-05 8.50E-06 1.40E+01 -
- 2. Average rrlease rate for period pCi/sec 4.05E-06 1.08E-06
- 3. Gross alpha radioactivity Ci diDA d1DA D. TRITIUM
- 1. Toul release Ci 1.27E+01 1.12E+01 8.00E+00
- 2. Average release rate for reriod pCi/see 1.63E+00 1.42E+00 5 of 10 E
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, EFFLUENT & WASTE DISPOSAL SEMI ANNUAL REPORT - 1989
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GASEOUS EFFLUENTS - MIXED MODE RELEASES l
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CONTINUOUS MODE BATCH MODE )
Ist 2nd 1st 2nd NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER FISSION GASES l Argon-41 O diDA diDA 2.01 E-01 9.98E-02 Krypton-85 Ci diDA 7.72E-01 4.59E+00 4.90E+01 Krypton-85m Ci 8.04E-01 1.78E+00 6.68E-01 3.29E-01 Krypton-87 O diDA diDA 6.85E-01 3.42E-01 Krypton-88 Ci diDA diDA 8.97E-01 4.23E-01 Xenon-131m Q diDA 8.91E-02 5.99E-01 1.47E+01 Xenon-133 O 1.22E+03 1.84E+03 4.24E+01 3.35E+02 Xenon-133m Ci d1DA 2.90E-02 5.68E-01 6.58E-01 "
Xenon-135 Ci 3.61E+01 3.95E+01 3.02E+00 1.79E+00 Xenon-135m Q diDA diDA 2.31 E-02 9.75E-02 Xenon-137 Ci diDA diDA 2.78E-01 ' l.8 IE-01 Xenon-138 Ci diDA diDA 1.23E 01 2.82E-01 TOTAL FOR PERIOD Ci 1.26E+03 - 1.8SE+03 5.43E+01 4.03 E+02
'I RITIUM H-3 Ci 1.16E+01 1.10E+01 1.12E+00 2.23E-01 IIALOGENS lodine-131 O d1DA 9.54E-06 ** **
lodine-133 Ci d1DA d1DA ** **
iodine-135 Ci d1DA diDA " "
TOTAL FOR PERIOD [ Ci diDA 9.54E-06 " "
PARTICULATE Alpha Ci diDA d1DA ** "
Chromium-51 O d1DA d1DA " "
Manganese-54 O d1DA d1DA " **
Cobalt-58 O d1DA diDA ** "
Cobalt-60 Ci 2.46E-06 1.98E-06 ** "
Strontium-89 ' Ci diDA diDA ** "
Strontium-90 Q l.43 E-06 2.82E-06 " **
Zirconium / Niobium-95 Ci diDA diDA " "
Ruthenium-103 O diDA d1DA ** "
Ruthenium-106 Q diDA d1DA ** "
Cesium-134 Ci 3.80E-06 diDA ** "
Cesium-137 O 2.39E-05 3.70E-06 ** "
Barium /Lan hanum-140 O diDA diDA ** **
Cerium-141 Ci diDA diDA ** **
Cenum-144 Q d1DA diDA " **
TOTAL FOR PERIOD Ci 3.15E-05 8.$0E-06 " **
- Reported under continuous mode.
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j EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT - 1989 LIOUID EFFLUENTS-SUMM ATION OF ALL RELE4,$ES I 3
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Ist 2nd EST. TOTAL
, UNIT QUARTER QUARTER ERROR %
A. FISSION & ACTIVATION PRODUCTS
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- 1. Total release (not including ~
tritium, noble gases, alpha) 0 1.42E-02 1.80E-01 1.10E+01
- 2. Average diluted concentration during period uCi/ml - 7.55E-11 9.47E-10 B. TRITIUM
- 1. Totalmiease 0- 9.14E+02 2.67E+03 3.50E+00
- 2. ' Average diluted concentration during period pCi/mi 4.86E-06 1.41E-05 C. DISSOLVED & ENTRAINED GASES
- 1. Totalrelease G 1.29E-01 2.27E+00 1.90E+01
- 2. Average diluted concentration during period pCi/ml 6.86E-10 1.19E-08 -4 m D. GROSS ALPilA RADIOACTIVITY
- 1. Totalmlease Q 7.10E-04 1.22E-03 8.00E+00 E. Volume of waste released (prior to dilution) Liters 3.56E+07 3.66E+07 3.00E+00 F. Volume of dilution water used during period Liters 1.88E+11 1.90E+11 2.50E+00 7 of 10
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EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT 1989 O LIOUID EFFLUENTS T
j' .- CONTINUOUS MODE BATCH MODE i Ist 2nd 1st 2nd IL NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER -QUARTER Alpha Ci 5.11 E-04 1.04E-03 1.99E-04 1.82E-04
- Chromium-51 O diDA diDA diDA diDA
- p. Manganese-54 O diDA diDA 4.59E-06 1.86E-03 j 1ron 55 Ci diDA 1.03E-02 6.41E-03 2.27E-02
[' Cobalt-57 O diDA diDA 8.86E-07 'diDA Cobalt-58 O diDA diDA diDA diDA d Jron-59 O diDA diDA diDA diDA U Cobalt-60 Ci diDA- dtDA 2.87E-03 1.40E-01 Strontium-89 Ci 9.02E-05 2.57E-04 6.06E-05 2.42E-05 Strontium-90 0 4.09E-05
)
4.18E-04 2.~67E-05 1.82E-04 Zirconium-Niobium-95 O diDA d1DA diDA diDA Ruthenium-103 O ciDA diDA diDA diDA Ruthenium-106 O diDA diDA diDA 2.91 E-04 Silver-110m Ci <MDA diDA diDA diDA )
Antimony-124 Ci d1DA diDA diDA diDA Antimony-125 O diDA diDA diDA 9.64E-05 )
lodine-131 Q diDA diDA 9.32E-06 1.83E-05 I lodine 132 O diDA diDA diDA diDA j lodine-133 O diDA diDA diDA dtDA lodine-134 O diDA diDA diDA d1DA Cesium-134 -
Ci etDA diDA 7.58E-04 5.82E lodine-135 O d1DA <MDA diDA diDA Cesium-137 5.17E-04 diDA 3.36E-03 2.58E-03 Barium-Lanthanum-140 5 d1DA diDA diDA diDA Cerium-144 Ci diDA diDA diDA diDA
'I'otal for Period (above) Ci 1.16E-03 1.20E-02 1.37E-02 1.69E-01 Tritium Q l.08E+00 7.48 E-01 9.13E+02 2.67E+03 Krypton-85 Ci diDA d1DA d1DA 7.94E-02 Xenon 131M Q diDA diDA 4.12E-02 3.77 E-02 I Xenon-133 0 1.57 E-02 2.17E-02 7.12E-02 2.12E+00 l Xenon-133M Ci diDA d1DA 9.53E-05 1.19E-02 1
Xenon-135 Q diDA 2.99E-03 3.81E-04 5.llE-04 E
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. SOI ID WASTI' AND IRR ADI ATED FUEL ' SHIPMFNTS
-I A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-Month . EST. TOTAL
- 1. TYPE OF WASTE - UNIT Period ERROR %
1; I
s a. ' Si cit resins, filter m3 1.022E+01 sludges, eva bottom, etc.porator O 3.9626E+01 1.0E+01 lL b. Dry compressible m3 2.5915E+01 Waste, Contaminated O 2.9997E+00 1.0E+01 -
eq'"n., etc.
i c. . Irradiated components . m3 -
O -
1.0E+01 L.
- 2. ESTIMATE OF M AJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)in %
l a. Co60 21.12 b. Co60 10.3 E Cs137 13.00 Cs137 -7.54
-Cs134 4.00 CoS8 2.98 CoS7 .10 Cs134 1.41 CoS8 3.60 H3 .457 Mn54 1.50 Cl4 .247 l
-Ce144 1.00 Tc99 2.864E-02 H3 . 20 1129 .151 Cl4 .241 Ni63 5.87 Tc99 1.102E-04 Fe55 61.8 112 9 2.048E-04 Sr90 9.044E-02 Ni63 7.22 Pu241 8.85 Fe55 47.40 Cm242 1.647E-02 Sr90 - 2.05E-03 Pu238 .188
'Pu241 .50 Pu239 2.234E-02 Cm242 9.75E-05 Pu240 2.234E-02 Pu238 .022 Am241 1.915E-02 Pu239 3.292E-03 Cm243 1.117E-02 Pu240 3.292E-03 Cm244 1.117E-02 Am241 .0129 Np237 3.191E-03
. Cm243 6.846E-03 Cm244 6.846E-03
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- 3. EQllD WASTE DISPOSITION
) NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 4 Truck Barnwell, SC.
O Truck Richland, WA.
B. IRR ADI ATED FUFL SHIPMENTS DISPOSITION)
NONE C. ADDmONALINFORMATION
- 1. Solidification agents utilized: N/A
- 2. Container information: ft 3
- a. High Integrity Container. 119
- b. High Integrity Container 193
- c. Steellint:s 182
- d. Steel boxes 96 f
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