ML20237G628

Semiannual Radioactive Effluents Release Rept,Jan-June 1987

ML20237G628
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1987
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20237G619	List: B12655, Forwards Semiannual Radioactive Effluents Release Rept, Jan-June 1987. Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents.Annual Radioactive Effluents Dose Rept Will Be Submitted in Mar 1988 ML20237G628
References
NUDOCS 8709020339
Download: ML20237G628 (17)

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TABLE OF CONTENTS 1

i Radiological Effluents Information.

1g Gaseous Effluents - Summation of all Releases g

10 Gaseous Effluents - Mixed Mode Release. - Liquid Effluents - Summation of all Releases. 12 Liquid Effluents - Batch and Continuous 13-14 Solid Waste 6 i l l l l 4 1 i l

i i Radiological Ef fluents Information 2. Regulatory Limits Specifications for Caseous Waste Efiluents ,, l A. The dose rate, at any time, offsite due to radioactive i materials released in gaseous effluents from the s te 1. shall be limited to the f ollowing values: I The dose rate limit for noble gases shall be less d than or equal to 500 mree/yr to the total body 1) for iodine-131, The dose rate limit due to inhalatic.: iodine-133, tritium and for all radioactive materials ii) in particulate form with half lives greater than 8 days shall be less than or equal to 1500 mrem /yr to any organ. The air dose of fsite due to noble gases released in gas-eous effluents shall be limited to the following: 2. During any calendar quarter, to less than or equal al to S mrad for ga=ma radiation and less than or equ i) to 10 mrad for beta radiation; During any calendar year, to less than or eq i ii) to 20 mrad for beta radiation; Fygorting Requirements in gaseous j With the calculated air dose from radioactive noble gases s d submit to the l ef fluents exceeding any of the above limits, prepare an 3 Special Commission within 30 days, pursuant to Specification 6.9., a i ( ) and Report which identifies the cause(s) for exceeding l ses of h emainder of radioactive noble gases in gaseous ef fluents during t e rinder of the calenda 1 the current calendar quarter and during the rema ar is within 10 d year so that the cumulative dose during the calen ar ye diation. mrad for gamma radiation and 20 mrad for beta ra m e

Specifications for Radioactive Effluents in Particulate Form B. The dose to any MEMBER OF THE PUBLIC f rom iodine-131, C 1. dodine-133, tritium and radioactive materials in partic-ulate form with half lives greater than 8 days in gas-eous ef fluents released offsite shall be limited to the following:

1) During any calendar quarter to less than or equal L

to 7.5 mrem to any organ; ii) During any calendar year to less than or equal to 15 arem to any organ. Reporting Requirements 1 k'ith the calculated dose from the release of radionuclides, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous ef fluents exceeding any of the above limits, prepare and to the Commission within 30 days, pursuant to Specification submit 6.9.3, a Special Report which identifies the cause(s) for exceeding the and defines the corrective actions to be taken to reduce the 1 limit releases during the remainder of the current calendar quarter and the cumulative dose during the tc. ainder of the calendar year so that to any MEMBER OF THE PUBLIC from such releases or dose commitment during the calendar year is within 15 mrem to any organ. l l l l 1 " ~ - -

_ Specifications for Liquid Waste Effluents C. The concentration of radioactive material released from the site shall not exceed the concentrations specified in 10 CFR 1. cg 20, Appendix B. Table 11, Column 2 for radionuclides For dissolved Part other than dissolved or entrained noble gases. The concentration shall not ex-or entrained noble gases, ceed 2 x 10-4 uCi/ml total activity. The dose or dose commitment to any MIM3ER OF THE PUBLIC from radioactive materials in liquid effluents released from the 2. D site shall be limited: During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal 1) to 5 mrem to any organ, and During the calendar year to less than or equal to 3 mrem to the total body and to less than or equal 11) i to 10 mrem to any organ. l Reporting Requirements ~ l With the calculated dose from the release of radioactive materials i l liquid ef fluents exceeding any of the above limits, prepare and submit l to Specification 6.9.3, a to the Commission within 30 days, pursuant Special Report which identifies the cause(s) for exceeding the limit (s) 4 I and defines the corrective actions to be taken to reduce the releas h l of radioactive materials in liquid effluents during the remainder of t e current calendar quarter and during the remainder of the calendar i year so that the cumulative dose or dose commitment t l l 3 mrem to the total body and 10 mrem to any organ. i. l - pe r We'

Specification for Cumulated Dose Commitment D. The dose or dose commitment to a HEMBER OF THE PUBLIC from the site is limited to less than or equal to 25 1. arem 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. m' Reporting Requirements With the calculated dose from the release of radioactive materia I liquid or gaseous effluents exceeding twice the limits of Specification 7.1.1.2., 7.1.2.2., or 7.3.2.3., prepare and submit a Special Report to to Specification 6.9.3 and limit the sub-R OF THE PUBLIC from the site is lietted to less than o the Commission pursuant limited-mrem to the total body or any organ (except thyroid, which is h This to less than or equal to 75 mrem) over 12 consecutive mont s. Special Report shall include an analysis which demonstrates that radiation exposures to any MEMBER OF THE PUBLI If the esticated doses exceed the above 40 CFR Part 190 Standard. shall include a request for a variance in limits, the special report Submittal of the report. accordance with the provisions of 40 CTR 190.is considered a l ) action on the request is complete. l 4 j i l 0 mk- )

Cur 10s/al) II. Maximum Parialssib10 Concentrations (Micra Tission and Activation Cases a. 3.0 E-07 Kr - 85 1.0 E-07 Kr - 85m 2.0 E-06 Kr - 87 2.0 E-08 Kr - 88 3.0 E-07 Ke - 133 1.0 E-07 h Xe - 135 3.0 E-08 Xe - 135m 3.0 E-08 f Xe - 138 1.0 E-04 l Ar - 37 b. Iodines 1.0 E-10 I - 131 4.0 E-10 j I,'133 1.0 E-09 1 - 135 Particulate. Half-lives > 8 Days i c. I 3.0 E-10 Sr - 89 3.0 E-11 f Sr - 90 4.0 E-10 f Cs - 134 5.0 E-10 Cs - 137 1.0 E-09 Ba - 140 4.0 E-09 La - 140 d. Liquid Effluents _ 3.0 E-06 Sr - 89 i 3.0 E-07 Sr - 90 4.0 E-05 Cs - 134 2.0 E-05 Cs - 137 3.0 E-07 I - 131,-, a

Liquid Effluents (Cont.) e 9.0 E-05 Co - 58 3.0 E-05 Co - 60 5.0 E-05 Fe - 59 1.0 E-04 In - 65 su 1.0 E-04 J Mn - 54 2.0 E-03 Cr - 51 6.0 E-05 Zr - 95 1.0 E-04 Nb - 95 I 4.0 E-05 I Mo - 99 ) 3.0 E-03 \\ Tc - 99: 2.0 E-05 B4 - 140 2.0 E-05 La - 140 9.0 E-05 Ce - 141 2.0 E-05 Eu - 154 2.0 E-03 Be-7 I 1.0 E-05 \\ Ru - 106 3.0 E-05 Ag - 110m 2.0 E-05 Sb '124 1.0 E-04 Sb - 125 4.0 E-04 Co - 57 3.0 E-06 Ke - 133 i 3.0 E-06 Ke - 135 3.0 E-06 Ar - 37 3.0 E-06 Kr - 85 1 l I l I e e

.I First QTR Secona QTR 3. Averagc Energy (f) E Beta E Ganna E Beta E Gamma For lissicn and 2.08601 E81E-02 ~E09U01 3.79E-02 Activation (,ases Bl Measurements and Approximation of Total Radioactivity 4 a. Fission and Activation Cases: 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 fodines, c. Particulate: Continuous in-line particulate filter on main stack effluent. Particulate samples are then counted for Gross lf. 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 vaste 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, and 905r are de te rmined. I l.. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _

J { l

1. 5)

Batch Releases a. Liquid

1) Number of batch releases:

1.25E402

2) Total time period for batch release:

6.16E+02 Hours 9.75E+00 Hours y

3) Maximum time period for a batch release:

4) Average time period for batch releases:

4.12E+00 Hours

5) Minimum time period for a batch release:

3.73E+00 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:

2.60E+01 3.51E+02 Hours

2) Total time period for batch releases:

3) Maximum time period for a batch release:

3.65E+01 Hours

4) Average time period for batch releases:

1.35E+01 Hours

5) Mimicum time period for a batch release:

7.60E-01 Hours (/6 Abnormal Releases I None l

1. 7 Chances to REftM/0DCM/PCP None
2. 8 Effluent Monitors Inoperable >30_ days None,

8 9

ETFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1987 GASEOUS EFTLUENTS-SUMMATION OF ALL RELEASES o FIRST .SECOND EST TOTAL UNIT QUARTER QUARTER ERROR % i A. FISSION & ACTIVATION GASES U 1. Total release Ci 6.31E+01 8.52E+02 1.40E+01 l 2. Average release rate for period pCi/sec 8.11E400 1.08E+02 B. 10 DINES 1. Total iodine - 131 Ci < MDL 3.71E-05 1.30E+01 2. Average release rate for period uCi/sec < MDL 4.77E-06 C. PARTICULATE l 1. Particulate with half-lives Ci > 8 days 3.20E-05 6.02E-05 1.40E+01 2. Average release rate for period pCi/sec 4.11E-06 7.74E-06 I 3 Gross alpha radioactivity C1 1.57E-07 9.64E-08 D. TRITIUM 1. Total release Ci 4.10E+00 7.53F+00 8.00E+00 2. Average release rate for period pCi/sec 5.27E-01 9.68E-01 t l.

EFFLUENT AND MASTE DISPOSAL SEMI-ANNUAL REPORT 19 87 l l GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE l FIRST SECOND FIRST SECOND NUCLIDES RELEASED UNIT OUARTER OUARTER OUARTER OPAR*ER TISSION CASES Kry pton-85 Ci 8.44E+00 9.44E+01 Krypton-85m Ci 1.62E-01 1.33E+00 Krypton-87 Ci 1.18E-01 1.39E+00 Krypton-86 C1 1.66E-01 2.21E+00_ Xenon-133 Ci 4.99E+01 7.12E+02 Xenon-135 Ci 2.10E+00 2.14E+01 i Xenon-135m Ci 7.36E-02 6.54F-01 l Xenon-138 Ci 1.53E-01 2.71E+00 Ci 3H C1 1.71E+00 3.42E+00 2.39E+00 4.11E+00 Ci \\ Irgon 41 C1 6.42E-02 6.52E-01 1 Xenon 131M Ci 5.29E-01 1.91E-01 Xenon 133M Ci 1.44E+00 1.32E+01 Xenon 137 Ci 2.72E-02 1.49E+00 TOTAL FOR PERIOD Ci 0.00E+00

0. 00E+00 6.31E+01 0.52E+02 Iodine-131 Ci 3.71E-05 Iodine-133 C1 5.36E-04 Iodine-135 Ci Y6TAL FOR PERIOD Ci 5.73E-04 PARTICULATE Alpha C1 1.57E-07 9.64t-ud Strontium-89 Ci 1.46E-07 2.50E-07 Strontium-90 C1 6.56E-07 1.84E-06 j

Cesium-134 Ci l Cesium-137 Ci 2.15E-05 1 Barium-lanthanum-140 Ci Cerium-144 Ci Cobalt-60 C1 3.llE-05 3.66E-05 Manganese-54 Ci Cobalt-58 Ci Cerium-141 Ci Ruthenium-103 Ci

== Zirconium / Niobium-95 C1 Ruthenium-106 Ci yhromium-51 ~'Ci ~ TOTAL FOR PERIOD Ci 3.20E-05 6.02E-05 < MDL

• • Reported under continuous mode _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ -

- 19 87_ EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL PIPORT f LIQUID EFFLUESTS-SUMMATION OF ALL RELEASES _ I EST. TOIAL FIRST SECOND UNIT QUARTER QUARTER ERROR % FISSION AND ACTIVATION PRODUCTS E Total release (not including 5.67E-02 9.65E-02 1.10E+01 1. C1 tritium, gases, alpha) f Average diluted concentration pCi/mi 1.84E-10 2.97E-10 2. during period \\ 3 IRITIUM i l Ci 5.90E+02 1.96E+03 3.50E400 l 1. Total release l pci/mi 1.88E-06 6.02E-06 2. Average diluted concentration duript period I l DISSOLVED AND ENTRAINED GASES i 'C, I Ci 4.53E-02 1.24E-01 1.90E401 1. Total release 4 Average diluted concentration pCi/mi 1.44E-10 3.81E-10 2 l l during period I l CROSS ALP 11A RADIOACTIVITY D. C1 1.06E-03 3.15E-04 8.00E+00 1. Total release 9 Volume of vaste released (prior 2.23E+06_ l 3.76E+06 3.00E+00 Liters E. to dilution) Volume of dilution water used 1.61. E411 1.84E+11 2.50E+00 Liters F. during period Liters 2.24E+10 3.13E+10 , 2.50E+00 of dilution water used Volume G. during releases (batch)

M-g g _A%SUAL gt?0 g ASD "" gytutsT COSTistous M U R ED r E o-EE a=j UA c. y1RST o," r TARTER (J - rA W1 o .q 2 ~ r 2.60E 02 ~ r Ci t. 2.67E-04 + 2.3(3E04g, 9E 02 g Ci + 1.96E-04 Ci Ci 03 + Ci t L-Ci

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FOLID WASTE /';D lERADI ATED FUEL SMIPMENTS l d A. FOL3P V.*.F E EF:PTE? OTTS]7F T07. EURI AL Oh DISPOSAL (NOT IRRAD] ATED TrE1.) { l 1 6-MONTH EST. TOTAL j 1. TYPE ^T WAS7I L' NIT -PERIOD ' ERROR ' ) 1.959 E+ a. Spent resins, fd3ter n

1 0 E+01 sludges, evaporator C1 3.115 E+2 botter, etc.

7.068 E+ 2 1.0 E-01 b. Dry compressible n Waste, Contaednated C1 2.665 E+ ecudp., etc. c. Irradiated components a N/A t 1.0 E+01 Ci 2. ESTIMATE OT MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) a. Co60 54.26 Pu24 .571 b.' Co60 19.8 Cs137 3.22 Cm242 1.04 E-2 Cs137 3.5' j Co38 2.46 Pu238 2.26 E-2 CoS8 5.47 Co57 1.89 E-2 Pu239 3.46 E-3 Cs134 2.00 Mn54 3.87 Pu240 3.46 E-3 Mn54 -1.58 Cs134 5.77 Am241 2.04 E-2 H3 .385 Fe59 2.58 Ca243 1.18 E-2 C 14 .377 Cr51 .849 Cm244 1.18 E-2 Tc99 1.329 E-3 H3 .0115 1129 1.154 E-3 l C14 .0175 N163 4.16 Tc99 4.90 E-4 Fe5S 61.5 1129 1.04 E-4 Sr90 5.945 E-3 i N163 2.40 .Pu241 1.11 .Fe55 23.97 Cm242 1.963 E-2 Sr90 .665 Pu238. 4.124 E-2 Pu239 6.185 E-3 i Pu240 6.185 E-3 Am241 2.371 E-2 l Ca243 1.340 E-2 i Ca244 1.340 E-2 )

l 1 l l 3. SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 10 Truck Barnwell, S.C. B. IRRADI ATED FUEL SHIPMENTS (DISPOSITION) - None NONE l C. ADDITIONAL INFORMATION Solidification Agents utilized: Cement (For evaporator bottoms and Steam Generator Decontamination Resins) Types of containers / volume of containers: Compacted Trash - 96 ft Steel Box Resin - 119 ft High Integrity Container 3 Solidified Liquids / Resins - 182 ft Steel Liner 108 ft Steel Liner 1. m

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