B12974, Semiannual Radioactive Effluents Release Rept,Jan-June 1988

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Semiannual Radioactive Effluents Release Rept,Jan-June 1988
ML20153D843
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 06/30/1988
From: Mroczka E
CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
B12974, NUDOCS 8809060053
Download: ML20153D843 (15)
v • d • e


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NORTHEAST UTILITIES o.n.r.i ove.c.. . s.io.n sir..i. e.ri n. conn.ci.cui e  ; i[

August 30, 1980 Docket No. 50 213 B12974 Re: 10CFR50.36a 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 10CFR50.36a, the Safety Technical Specifications and the Radiological Effluents Monitoring Manual, a copy of the Semiannual 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 - June,1988. An Annual Radioactive Effluents Dose Report (to be submitted in March,1989) will include an assessment nf the radiation doses due to the radioactive liquid and gaseous effluents during the calendar year (January - 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 k FCd;

. .fr'ocika y Senior 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

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+ i TABLE OF CONTENTS e

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Radiological Effluents information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17  :

i Gaseous Effluents Summation of all Releases . . . . . . . . . . . . . . . . . . . . . . . . 8 l l

i Gaseous Effluents Mixed Mode Release . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 L

Liq uid Ef fluents - Summation of all Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . 10  !

l Liquid Effluents - Batch and Continuous . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11  ;

i S o l i d Wa s t e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 12-13 I 1

Ch a n g es to R E M M/O DCM/PCP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N/A ,

Effluent Monitors Out of Service .................................... N/A i

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Radiolonical Effluents Information i f

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1. Regulatory Limits t A. Soccifications for Gaseous Waste Effluents ,

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1. The dose rate, at any time, offsite due to radioactive materials released l in gaseous effluents from the site shall be limited to the following values:

l i) *Ihe dose rate limit for noble gases shall be less than or equal to 500 mrenVyr to the total body and less than or equal to 3000 mrenVyr to the skin, and

11) The dose rate limit due to inhalation for lodine 131, iodine-133, tritium and for all radioactive materials in particulate form with half lives greater  !

than 8 days shall be less than or equal to 1500 mrem /yr to any organ.  ;

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2. The air dose offsite due to noble gases released in gaseous effluents shall be i' limited to the following:

i) 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; l

11) During any calendar year, to less than or equal to 10 mrad for gamma l radiation and less than or equal to 20 mrad for beta radiation; Rennrtine Heautrements t 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 j 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective a actions to be taken to reduce the releases of radioactive noble gases in gaseous effit.ents during the  !

remainder of the current calendar quarter and during the remainder of the calendar year so that the l cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta i radiation.

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I B. Speci6 cations for Radioactive EfDuents in Particulate Form

1. The dose to any MEMBER OF Tile PUBLIC from lodine-131, iodine 133, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous ef0uents released offsite shall be limited to the following:

i) During any calendar quarter to less than or equal to 7.5 mrem to any organ; li) During any calendar year to less than or equal to 15 mrem to any organ.

Renorting Reautrements With the calculated dose from the release of radionuclides, radioactive materials in particulate fomt, or radionuclides other than noble gases in gaseous ef0uents exceeding any of the above limits, premare and submit to the Commission with 30 days, pursuant to SpeciGeation 6.9.2, a Special Report whic't 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 TiiE PUBLIC from st.ch releases during the calendar year is within 15 mrem to any organ.

Page 2 of 13

C. Speci0 cations for Liquid Waste Efnuents

1. The concentration of radioactive material released from the site shall not exceed the concentrations specified in 10 CRF Part 20, A 3pendix B, Table 11, Column 2 for radionuclides other than dissolved or entrainet noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0E-04 pCi/ml total specific activity.
2. 'Ile dose or dose commitment to any h1EN1BER OF THE PUBLIC from radioactive materials in liquid efnuents 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 nuem to any organ, and ii) 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.

Reoortine Reaulrements With the calculated dose from the release of radioactive materials in liquid efnuents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) anc. defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid efnuents 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 h1EN1BER OF Tile 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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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 a less tnan or equal to 75 mrem) over a period of 12 consecutive months.

1 Reportino Requirements f

t With the calculated dose from the release of radioactive materials in liquid or gaseous I effluents twice the limits of Specification 7.1.1.2,7.1.2.2, or 7.1.2.3., prepare and submit a l Special Report to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose 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 organ (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 i to any MEMBER OF THE PU3LIC from the site (including all ef fluent pathways and direct  ;

radiation) are It:ss 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 2

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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'il. Maximum Permissible Concentrations (Micro cunes/cc)

a. Fission and Activation Gases Kr 85 3.0E-07 Kr - 85m 1.0E-07 Kr 87 2.0E-08 Kr 88 2.0E-08 Xe 133 3.0E-07 Xe-135 1.0E-07 Xe 135m 3.0E-08 Xe-138 3.0E-08
b. Imlines

! 131 1.0E 10 1 133 4.0E 10 1- 135 1.DE-09

c. Paniculates. Half Lives > 8 days Sr 89 3.0E 10 Sr 90 3.0E.ll Cs 134 4.0E 10 Cs 137 5.0E 10 Da 140 1.0E-09 La 140 4.0E-09 Co-58 2.0E-09 Co-60 3.0E 10 d, liquid Efnuents (uC/ml)

Sr 89 3.0E-M Sr 90 3.0E-07 Cs 134 4.0E-05 Cs 137 2.0E-05 I 131 3.0E 07 Co 58 9.0E 05 Co 60 3.0E-05 Fe 59 5.0E 05 Zn 65 1.0E44 Mn 54 1.0E-N Cr 51 2.0E-03 Zr 95 6.0E-05 Nb 95 1.0E44 Mo 99 4.0E-05 Tc 99m 3.0E-03 Da 140 2.0E-05 La 140 2.0E-05 Ce 141 9.0E-05 Ru 106 1.0E 05 Ag Il0m 3.0E 05 Sb 124 2.0E-05 Sb 125 1.0E44 Co 57 4.0E-N Page 5 of 13

4 111 Average Energy (E) (in hieV) FIRST QUARTER ~ SECOND QU ARTER For Fission and EBeta E Gamma E Beta E Gamma Activation Gases 2.59E 01 1.26E 01 2.01E 01 4.26E 02 i

IV hicasurements and Approximation of Total Radioactivity

a. Fission and Activation Gases: An in line G. bl. Detector monitors stack efnuents. Gas samples are collected on the stack and are analyzed for low level fission and activation gases,
b. Iodines: Continuous in line charcoal sample 61ter on main stack efnuent. Charcoal
Dlters are then analyzed for lodines.

! c. Paniculates: Continuous in line particulate sample filter on main stack efnuent. 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. Liauid Efnuents: In line scintillation detectors monitor waste liquid bein;; released.

Prior to discharge a sample is taken. Principal gamma emitters, entrainec gases and tritium analyses are performed. A monthly composite is made from the samples. Gross Alpha,89Sr,90Sr, and 55 Fe are determined.

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V Batch Releases

a. Liquid
1) Number of batch releases: 82
2) Total time period for batch release: 882 Ilours
3) hiaximum time period for a batch release: 28.7 Ilours
4) Average time period for batch release: 10.76 Ilours
5) hiinimum time period for a batch release: .15 Hours
6) Average stream now during periods of 15.800 cubic feet release of ef0uent into a flowmg per second stream:
b. Gaseous
1) Number of batch releases: 21
2) Total time period for batch releases: 152 liours
3) h!aximum time period for a batch release: 20.7 Ilours
4) Average time period for batch releases: 7.24 Ilours
5) hiinimum time period for a batch release: .083 Ilours VI Abnormal Releases
  • None
  • Releases that exceed Technical Specineation Limits Page 7 of 13

' EFFLUENT & WASTE DISPOSAL SENil ANNUAL REPORT - 1988

. G ASEOUS EFFLUENTS SU3151 ATION OF ALL RELE ASES ist 2nd EST.'l O TA L UNIT QUARTER QUARTER ERRORCc A. FISSION & ACTIVATION GASES

1. Total release Ci 3.35E 01 1.61 E+03 1.40E+01
2. Averace release rate for period pCi/sec 4.21E 02 2.03E+02
11. IODINES
1. Total lodine - 131 Ci d1DA 3.64E 02 1.30E+01
2. Averace release rate for period pCi/sec d1DA 4.58E 03 C. PARTICULATES
1. Particulates with half lives f

> 8 days Ci 1.93E-04 2.61E 04 1.40E+01

2. Averace release rate for period pCi/sec 2.43E-05 3.28E 05
3. Gross alpha radioactivity Ci 4.51E-07 d!DA D. TRITIU51
1. Total release Ci 1.12E+01 1.21E+01 8.00E+00
2. Averace release rate for period pCi/sec 1.41E+00 1.52 E+00 Page 8 of 13

FFFLUENT & WASTE DISPOSAL SEN11 ANNUAL REPORT - 1988 G ASEOUS EFFLUENTS El EVATED RELEASES CONTINUOUS 510DE IIATCll SIODE lst 2nd 1st 2nd NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER FISSION GASES Arcon 41 Q dlDA d1DA 1.055E 03 7.549E 03 Krypton 85 Ci d1DA 1.82+02 5.00E-02 2.710E+(x)

Krypton-85m Ci d1DA d1DA 2.354E-03 8.563E 02 Krypton h? Ci 41DA diDA 1.722E 03 1.832E 02 Krypton 88 O d1DA d1DA 2.241E 03 2.692E 02 Xenon 131m Ci d1DA d!DA 2.853E 03 3.266 E+00 Xenon-133 O d1DA 1.16E403 1.72hE 01 2.374E+02 Xenon 133m Ci diDA 3.21 +00 9.650E 03 2.284 E+00 Xenon 135 O d1DA 1.01E+01 ~ 8.429E 02 6.884 E+00 Xenon-135m Q d1DA d1DA 9.045 E414 7.663E 03 Xenon 137 Ci d1DA d1DA 3.404E 03 1.7blE 02 Xenon 138 Q d1DA diDA 3.119E 03 1.930E 02 TOTAL FOR PEltlOD Ci d1DA 1.36E+03 3.350E 01 2.510E+02 H3 O 1.116E+01 1.063E+01 1.745E 03 1.429E+00 lodine-131 Ci d1DA 3.64E 02 " "

lodine 133 ,

Ci d1DA 2.55E 03 " "

lodine 135 O d1DA 3.89E 02 " "

TOTAI, FOR PERIOD Ci EGITIC UI.AT ES

Alpha O 4.512E-07 d!DA Chromium 51 Q d1DA d1DA " "

Alancanese-54 Ci d1DA d1DA " "

! Malt-58 Ci dtDA d1DA " "

Cobalt 40 Ci 1.52 E4M 1.754E 04 Strontium h9 Q 61DA dtDA " **

Strontium-90 0 2.533E 06 5.7 h9E-07 ZirconiunVNiobium-95 Ci d1DA dtDA " "

Ruthenium-103 O d1DA dtDA " "

Ruthenium-106 Ci d!DA d1DA Cesium 134 O dtDA 6.109E 06 "

l Cesium 137 Ci 3.799E 05 8.157E 05 liarium.Lanth.'num-140 Q d1DA dtDA "

Cerium 141 Ci 61DA diDA Cenum-144 O d1DA d1DA " "

TOTAL FOR PERIOD G 1.93 E-04 2.61E 04 " "

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" Reported under continuous mode.

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. EFFLUENT & WASTE DISPOSAL SE5fl. ANNUAL REPORT .1988 LIOUID EFFLUENTS. SUN 131 ATION OF ALL REI E ASES Ist 2nd EST. TOTA L UNIT QUARTER QUARTER ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. Total release (not including tritium, noble gases, alpha) Ci 8.32E 02 3.76E 01 1.10E+01
2. Average diluted concentration during period pCi/ml 1.02E 09 2.34E 09
11. TRITIUM
1. Total release Ci 6.85E+01 3.53E+02 3.50E+00
2. Average diluted concentration during period pCi/ml 8.43E-07 2.19E-06 C. DISSOI.YED & ENTRAINED G ASES
1. Total release Ci d1DA 2.02E-01 1.90E+01
2. Average diluted concentration during period pCi/ml dtDA 1.2 SE-0 9 D. GROSS Al.I'll A R ADIOACTIVITY
1. Total release Ci 2.37E 04 3.40E 04 8.00E+00 E. Volume of waste released (prior to dilution) 1.iters 4.20E+06 4.35E+06 2.50E+00 F. Volume of dilution water used during period Liters 8.13E+ 10 1.61E+11 2.50E+00 Page 10 of 13

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' EFFIATE$T & WASTE DISPOSAL SEMI ANNUAL REPORT1988 ,

LIOUID EFFLUENTS CONTINUOUS MODE IIATCll MOl)E ist 2nd 1st 2nd NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Alpha O 2.091i414 1.13E 04 2.81 E-05 2.2hE 04 Chromium 51 Ci 61DA dtDA d1DA c1DA hiancanese 54 Ci d1DA d1DA 2.14E 03 2.67E 04 Iron 55 Ci d1DA 1.56E 02 1.27E 03 2.14E 02 Cobalt 57 Ci 41DA d1DA 1.29E 04 8.06E 06 Cobalt 58 Ci d1DA d1DA 9.thE 03 6.20E 04 Iron-59 Q d1DA d1DA d1DA d1DA Cobalt 60 Ci 1.07E 03 7.25E 03 4.65E 02 1.26E 02 Strontium h9 Ci dtDA d1DA 3.40E 05 3.47E 05 Strontium 90 Ci d1DA dtDA 9.h9E 05 4.36E 05

, Zirconium-Niobium-95 Ci otDA d!DA 5.79E-05 d1DA Ruthenium-103 Ci dtDA d1DA d1DA d1DA Ruthenium lob C dtDA d1DA d1DA d1DA Silver llom Q 61DA d1DA d1DA 1.81 E-05 Antimony 124 Ci d1DA d1DA 3.54E 04 4.40E-05 Antimony 125 O 61DA dtDA 7.55E 04 1.17E 04 lotline 131 Ci dtDA 2.37E 02 dtDA 2.97E 03 lodine 132 Ci d1DA 4.71E 02 61DA c1DA ladine 133 O d1DA 6.36E 02 d1DA 1.56E 04 Imitne 134 Ci 61DA X.96E 02 d1DA 41DA '

1 Cesium 134 Cl 1.29E-03 1.74E 03 3.30E-03 9.4nE 04 l Imiine-135 Ci etDA 8.22E 02 d1DA d1DA '

Cesium 137 Ci 6.62 E-03 3.02E 03 9.h5 E-03 2.93E 03 1 liarium 1.antharium 140 Q d1DA d1DA d1DA X.16E Un Cerium 144 O 41DA d1DA dtDA d1DA Total for Period (ahme) O 9.19E 03 3.34E 01 7.40E 02 4.23E 02

'I ritium Cl 8.32 E-02 9.00E 01 6.841i+01 3.52 E+ 02 Krypton h5 O 61DA d1DA d1DA 61DA Xenon 131M Cl d1DA d1DA dtDA 4.25E 03 '

Xenon 133 Ci otDA 61DA d1DA 1.92E 01 Xenon 133M Q dtDA d1DA 61DA 3.40E 03 Xenon 135 O 61DA 2.43E 04 dtDA 1.h3E 03 i

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, , Enf ih WARTE AND IDR Anl ATED FUEL ElllPMI'N*fE '

A. SOLID WASTE SillPPED OFFSITE FOR BURIAL OR DISPOSAL (NO r IRRADIATED FUED i 6-Month EST. TOTAL

1. TYPE OF WASTE UNIT kigd ERROR % ,

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a. Sp:nt resins, filter m3 2.385E+1 1.0 E+01 Ci 1.094E+2 l guggs,e porator
b. Dry compressible m3 4.07 '3+ 1 ,t,1.0E+01 l Waste, Contaminated Ci 1.0 P E+0 -

equip., etc.  ;

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c. Irradiated components m3 N/A 11.0E+01 i Ci f l
2. ES.TIMATE OF MAJOR NUCl.lDE COMPOSITION (BY TYPE OF WASTE)in % [

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a. Co60 17.83 b. Co60 19.80  !

Csl37 18.02 Csl37 3.50 Csl34 10.59 CoS8 5.47 CoS7 1.641E 2 Csl34 2.00 CoS8 6.66 Mn54 1,58 Mn54 .936 113 .385 Fe59 1.938E-2 Cl4 .377 ,

Cr51 2.25 Tc99 1.329E 3 I 113 .054 112 9 1.154E 3  !

Cl4 .085 Ni63 4.16 [

Tc99 6.492E 4 Fe55 61.5  :

1129 1.219E 4 560 5.945E 3 i Ni63 4.82 Pu241 1.11 (

Fe55 38.23 Cm242 1.963E ' '

Sr90 ,136 Pa238 4.124E 2  !

Pu241 .274 Pu239 6.185E 3  !

Cm242 .022 Pu240 6.185E 3  !

Pu238 .018 Am241 2.371E 3 [

Pu239 3.251E 3 Cm243 1.340E 2 i Pu240 3.251E 3 Cm244 1.340E 2 i Am241 8.642E 3 I Cm243 6.369E 3  !

Cm244 6.369E-3 i l

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3. SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF TR ANSPORTATION DESTINATION 9 Truck Barnwell, SC Richland,WA B. IRR ADIATED FUEL SHIPMENTS 90lSoOSITION NONE C. ADDITIONAL INFORMATION
1. Solidification Agents Utilized: Cement
2. Container Information:

(A.1.a) High Integrity Containers 119 ft3 193 ft3 Steel Liners 182 ft3 (A.1.b) Steel Boxes 96 ft3 Page 13 of 13

NORTHEN5Y (fTILITIES o.n.,.i Orr,ce. . s w.n sire.t. Bernn, conneci cut 9 '.sN.1)N,,$eNN.5 P.O. BOX 270

' * ' ' * * * * * " * " H ARTFORD. CONN ECTICUT 061414270 L L J U,U,"'5,U2 "cc.,,[ (203) 665-5000 August 30, 1988 Docket No. 50-213 B12974 Re: 10CFR50.36a U S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Haddam Neck Plant Semiannual Radioactive Ef fluents Release Reoort 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 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 - June,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 - 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)'l).

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY

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. .ffir~ocika g/

Senior Vice President cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Pro.'Mt Manager, Haddam Neck Plant l

J. ~. Shedlosky, Sei.ior Resident Inspector, Haddam Neck Plant f

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