ML20206F511
| ML20206F511 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 04/07/1987 |
| From: | Rodgers R NORTHEAST UTILITIES |
| To: | Bottomley R NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NE-87-RA-331, NUDOCS 8704140271 | |
| Download: ML20206F511 (1) | |
Text
_
EEE General Offices e Selden Street, Berlin, Connecticut stII.N Its5YE$w="
P.O. BOX 270 em am"wa **
HARTFORD, CONNECTICUT 06141-0270 k
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((, "d',1*',",~[,
(203) 665-5000 April 07,1987 NE-87-RA-331 Mr. R. Bottomley Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission c/o Distribution Services Branch DDC, ADM Washington, D.C. 20555
Dear Mr. Bottomley:
Attached are your copies of the Semiannual Radioactive Effluents Release Report for Millstone Units #1, # 2 and #3 and Connecticut Yankee. These reports have been submitted to the Nuclear Regulatory Commission as per the Stations' Technical Specifications and the requirements of 10CFR50.36a.
Very truly yours, f*
Reginald C. Rodgers, Ph.D., Manager Radiological Assessment Branch RCR/jha Attachments l
//
ty 8704140271 870407 DR ADOCK 05000213 PDR
CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N.
CONNECTICUT P o Box 270 e HARTFORD. CONNECTICUT 06141-0270
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February 27,1987
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Docket No. 50-213 B12433 Re: 10 CFR 50.36a 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 10 CFR 50.36a and the Radiological Effluent Technical Specifications, a copy of the Semiannual Radioactive Effluents Release Report is herewith subniitted.
This report includes a summary of the quantities of solid-radioactive waste, and liquid & gaseous effluents for the period of July - December,1986. An Annual Radioactive Effluents Dose Report (to be submitted in March,1987) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released during the previous calendar year (January - December,1986).
Due to unavoidable delays in sample analysis, results for Sr-89, Sr-90, and gross alpha for the last quarter of 1986 are incomplete.
These results will be forwarded as soon as they become available.
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 10 CFR 50.4(b)(2)(viii).
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY E3n 4 E. J. Mroczka Senior Vice President o
By: C. F. Sears Vice President
TABLE OF CONTENTS 1.g Radiological Ef fluents Information.
Gaseous Effluents - Summation of all Releases 9
10 Gaseous Effluents - Mixed Mode Release.
11 Liquid Effluents - Summation of all Releases.
12 Liquid Effluents - Batch and Continuous 13-14 Solid Waste 4
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Radiological Effluints Information 1.
Regulatory Limits A.
Specifications for Gaseous 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 following values:
i) The dose rate limit for noble gases shall be less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and ii) The dose rate limit due to inhalation for iodine-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 arem/yr to any organ.
2.
The air dose offsite due to noble gases released in gas-
,eous effluents shall be 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; ii) 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 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 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 gaseous effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumu'1stive dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.
B.
Specifications for Radioactive Effluents in Particulate Form 1.
The dose to any HIMBER OF THE PUBLIC from iodine-131, t
iodine-133, tritium.and radioactive materials in partic-ulate form with half lives greater than 8 days in gas-eous effluents released offsite shall be limited to the following:
- 1) During any calendar quarter to less than or equal to 7.5 mrem to any organ; ii) During any calendar year to less than or equal to 15 stem to any organ.
Reporting Requirements With the calculated dose from the release of radionuclides, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission 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 a
releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose j
or dose commitment to any MEMBER OF THE PUBLIC from such releases during the calendar year is within 15 arem to any organ.
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C.
Specifications for Liquid Waste Effluents The concentration of radioactive material released from the 3.
site shall not exceed the concentrations specified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides For dissolved other than dissolved or entrained noble gases.
or entrained noble gases, The concentration shall not ex-caed 2 x 10-4 uCi/a1 total activity.
- 2..The dose or dose commitment to any MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the site shall be limited:
During any calendar quarter to less than or equal to i) 1.5 mrem to the-total body and to less than or equal to 5 mrem to any organ, and During the calendar year to less than or equal to ii) 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Reporting Requirements With the calculated dose from the release of radioac'tive materials in liquid ef fluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report which identifies the cause(s) for exceeding the limit (s) i and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents durin,g 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 0F THE PUBLIC from such release during the calendar year is within i
3 arem to the total body and 10 stem to sny organ.
3
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D.
Specification for Cumulated Dose Commitment The dose or dose commitment to a MEMBER OF THE PUBLIC 1.
from the site is limited to less than or equal to 25 arem to the total body or any organ (eycept the thyroid, which is limited to less than or equal to 75 arem) over a period of 12 consecutive months.
Reporting Requirements With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 7.1.1.2., 7.1.2.2., or 7.1.2.3., prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 and limit the sub-sequent 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 This to less than or equal to 75 mrem) over 12 consecutive months.
Special Report shall include an analysis which demonstrates that radiation exposures to any MEMBER OF THE PUBLIC from the site (in-cluding all effluent pathways and direct radiation) are less 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 Submittal of the report accordance with the provisions of 40 CFR 190.
is considered a timely request, and a variance is granted until staff action on the request is complete.
4 II, Maximum Paraissiblo Conccntreti:ns (Micra C ries /al)
I Fission and Activation Casas a.
Kr - 85 3.0 1-07 Kr - 85m 1.0 E-07 Kr - 87 2.0 E-08 Kr - 88 2.0 E-08 Ia - 133 3.0 E-07 Is - 135 1.0 E-07 Xe - 135m 3.0 E-08 Ia - 138 3.0 E-08 Ar - 37 1.0 E-04 b.
Iodines I - 131 1.0 E-10 I.' 133 4.0 E-10 I - 135 1.0 E-09 Particulates, Ralf-Lives > 8 Days c.
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 La - 140 4.0 E-09 d.
Liquid Effluents Sr - 89 3.0 E-06 Sr - 90 3.0 E-07 Cs - 134 4.0 E-05 Cs - 137 2.0 E-05 I - 131 3.0 E-07
Liquid Ef fluents (Cont.)
Co - 58 9.0 E-05 Co - 60 3.0 E-05 Fe - 59 5.0 E-05 Zn - 65 1.0 E-04 Mn - 54 1.0 E-04 Cr - 51 2.0 E-03 Zr - 95 6.0 E-05 Nb - 95 1.0 E-04 Mo - 99 4.0 E-05 Tc - 99a 3.0 E-03 54 - 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 Sb - 125 1.0 E-04 Co - 57 4.0 E-04 Xe - 133 3.0 E-06 Xe - 135 3.0 E-06 Ar - 37 3.0 E-06 Kr - 85 3.0 E-06 9.
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3.
Average Energy (E) (MeV)
Third Quarter Fourth Quarter For Fission and E Beta E Gamma E Beta E Gamma Activation Gases 2.02E-01 5.17E-02 2.12E-01 5.85E-02 4
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 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.
Liquid Effluents:
In-line scintillation detector monitors waste liquid being raleased.
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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e h5) Batch Releases a.
Liquid
- 1) Number of batch releases:
1.13E+02
- 2) Total time period for batch release:
6.24E+02 Hours
- 3) Maximum time period for a batch release: 2.05E+01 Hours
- 4) Average time period for batch releases:
5.52E+00 Hours
- 5) Minimum time period for a batch release: 1.67E-01 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:
1.90E+01 Hours
- 2) Total time period for batch releases:
3.01E+02
- 3) Maximum time period for a batch release: 3.09E+01 Hours
- 4) Average time period for batch releases:
1.58E+01 Hours
- 5) Minimum time period for a batch release: 7.50E-01 Hours
- 6) Abnormal Releases None.
- 7) Changes to the REMM/0DCM/PCP l
None.
- 8) Ef fluent Monitors inoperable for > 30 days None 9
I i
v EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 19 86 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES i
UNIT hbbER bb
- ERROR A.
FISSION & ACTIVATION GASES 1.
Total release Ci 3.93E+02 1.50E+02 1.40E+01 i
2.
Average release rate for period pCi/sec 4.94E+01 1.89E+01 B.
10 DINES 1.
Total iodine - 131 Ci 8.09E-04 4 MDL 1.30E+01 2.
Average release rate for period pCi/sec
.02E M
< MOL C.
PARTICULATES 1.
Particulates with half-lives
> 8 days C1 1.49E-04 8.84E-04 1.40E+01 2.
Average release rate for period uCi/sec 1.87E-05 1.11E-04 3.
Cross alpha radioactivity C1 1.59F-OR (MDL
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TRITIUM 1.
Total release Ci 8.05E+00 6.79E+00 8.00E+00 2.
Average release rate for period VCi/see 1.01E+00 8.54E-01
. g.
Data for Sr-89, Sr-90, gross dis incomplete
EFFLUENT AN.D WASTE ' DISPOSAL SEMI-ANNUAL REPORT - 1986
~
GASEOUS EFFLUENTS-MIXED RELEASE CONTINUOUS MODE BATCH MODE i
Fourth Third Fourth NUCLIDES RELEASED UNIT R
OUARTER OUARTER OUARTER EISSIONCASES Kryptan-85 C1 1.41E+00 3.0RF+01
? 7AF+n1 Krypten-85m Ci 1 RaF+nn 1.Q?F-01 4.89E-02 2.36F-0?
Krypten-87.
Ci 2.31E-01 1.25E-01 Krypten-88 C1 Xcn:n-133 ci 1.92E+02 1 RnF+n?
1 nor+n?
X'.non-135 C1 1.66E-01 4.R6E+00 4.25E+00 1.65E-02 1.05E-02 X:ntn-135m Ci 8.80E-01 1.73F+00 X nsn-138 Ci Ci 3H Ci 6.70E+00 4.6RF+00 1 1RF+00 2 11F+nn Argen 37 Ci 4.00E-02 1.20E-01 Argon 41 C1 2.70E-04 2.52E-01 2.92E-01 X n n 131M Ci 4.63E-03 5.40E+00 6.66E+00 Xsn n 133M Ci 4.31E-01 1.70E-02 3.70E-02 Xcnsn 137 Ci 1.99E+02 1.50E+02 TOTAL FOR PERIOD C1 1.94E+02 Iodine-131 Ci 8.09E-04 lodine-133 Ci Iodine-135 Ci TOTAL FOR PERIOD C1 8.09E-04 PARTICULATES Ci Alpha C1 1.59E-08 Strontium-89 C1 Strontium-90 Ci Csaium-134 Ci l
Cazium-137 C1 1.04E-05 4.04E-05 Barium-lanthanum-140 Ci Csrium-144 Ci
' Cobalt-60 Ci 1.39E-04 8.44E-04 Mxnginese-54 Ci Cobnit-58 Ci Carium-141 Ci Ruthinium-103 Ci Zirconium / Niobium-95 Ci Ruthinium-106 Ci Chro21um-51 Ci
. TOTAL FOR PERIOD Ci 1.49E-04 8.84E-04
- Isotope Values ( MDL
?* Reported under continuous Mode,
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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT
- 19 86 i
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES EST. TOTAL h
ER UNIT R*
ERROR %
A.
FISSION AND ACTIVATION PRODUCTS 1.
Total release (not including tritium, Eases, alpha)
Ci 1.01E-01 a atr.n?
1 Inr+nt 2.
Average diluted concentration durina period pCi/ml 5.49 E-10 2.43E-10 i
e B.
TRITIUM 1.
Total release Ci 5.09E+02 1.07E+03 3.50E+00 2.
Average diluted concentration during period pCi/ml 2.77E-06 5.86E-06 C.
DISSOLVED AND ENTRAINED GASES 1.
Total release Ci 8.81E-02 3.05E-02 1.90E+01 2.
Average diluted concentration during period pCi/mi 4.79E-10 1.67E-10 D.
GROSS ALPHA RADIOACTIVITY l
1.
Total relt.ase C1 1.31E-04 1.97E-05 8.00E+00 E.
Volume of waste released (prior to dilution)
Liters 4.20E+07 4.57E+07 3.00E+00 t
F.
Volsme of dilution water used 1.839E+11 1.825E+11 2.50E+00 durina period Liters G.
Volume of dilution water used 2.94E+10 2.21E+10 2.50E+00 during releases (batch)
Liters
- Data for Sr-89,Sr-90, gross et is incomplete _
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1986 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Third Fourth Third Fourth NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Strontium-89 Ci 2.74E-04 2.27E-04 4.10E-05 3.79E-05 Strontium-90 Ci 2.83E-04 3.52E-05 3.00E-05 1.29E-04 cm ium-134-Ci 4.25E-03 4.98E-04 2.89E-03 7.85E-03 Croium-137 Ci 7.78E-03 2.49E-03 5.18E-03 2.11E-02 Iodine-131 Ci 3.65E-02 3.26E-04 4.85E-03 1.50E-04 3.04E-03 2.58E-04
)
Ccb+lt-58 Ci 4
Cobelt-60 Ci 4.55E-03 4.45E-03 8.66E-03 3.41E-03 3.61E-04
.'. Iran-59 Ci 4.50E-04 3.94E-04 l Antimony-124 Ci 8.47E-04 7.74E-05 Manaanese-54 Ci 1.02E-03 Chronium-51 Ci 9.48E-04 1.58E-04 l Zirconium-Niobium-95 Ci Molybdenum-99 Ci 1.05E-04 Tnchnstium-99m Ci 5.06E-05 1.81E-04 7.73E-06 Ianthannm 1an Ci 1.47F-04 Carium-141 Ci Ci 3.61E-05 Barium-140 Ctrium-144 Ci
! Alpha C1 1.29E-04 1.69E-05 2.03E-06 2.75E-06 3
Ruthinium-106 Ci Silvar-110m Ci Ruthenium-103 Ci 1.17E-05 5.45E-04 1.68E-03 Antimony-125-Ci Iron-55 Ci 6.32E-04 l
Iodint-133 C1 2.62E-02 l
Cxium-136 Ci 1.61E-04 j
Total for Period (above)
Ci 8.11E-02 8.08E-03 2.90E-02 3.62E-02 i-4.94E-02 2.94E-02 Xsnon-133 Ci 9.87E-03 3.28E-04 1.07E-03 finon-135 Ci 7.75E-03 Ci 4.19E-05 Xes.l.33M Krypton-85 Ci 2.07E-02
-Tritium Ci 9.60E+00 3.71E+00 5.02E+02 1.07E+03 2.29E-04 Argon-41
, Ci Isotope Values are C1DL.
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SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRA3IATED FUEL) 6-MONTH EST. TOTAL 1.
TYPE OF WASTE UNIT PERIOD ERROR %
a.
Spent resins, filter m
1.348E+1 1 1.0 E+01 sludges, evaporator Ci 4.866E+2 bottom, etc.
1 1.0 E+01 b.
Dry compressible m
Waste, Contaminated Ci equip., etc.
[",
t 1.0 E+01 c.
Irradiated components m
Ci 2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) in %
a.
CoS7 1.03E-3 Sr90 4.11 CoS8 15.76 Pu241 0.648 Co60 10.99 Cm242 0.012 Cs134 20.39 Np237 2.56E-6 Cs117 19.61 Pu238 0.012 Mn54 3.01 Pu239 1.72E-3 Cr51 3.48E-3 Pu240 1.72E-3 H3 2.26 Pu242 1.52E-5 C14 0.054 Am241 5.04E-3 Tc99 0.044 Cm243 5.17E-3 I129 5.43E-3 Cm244 5.17E-3 Ni63 2.19 Fe55 20.85 l
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SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION Truck Barnwell, S.C.
4 IRRADIATED FUEL SHIPMENTS (DISPOSITION)
B.
NONE C.
ADDITIONAL INFORMATION 1.
Solidification Agents utilized : Cement 2.
Container Information:
3 119 ft (A.I.a)
High Integrity Containers 193 ft3 3
182 ft Steel Liners 96 ft3 (A.1.b)
Steel Boxes o
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4
NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATI0li UNITS NO 1, 2, 8 3 i
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SEMIANNUAL RADI0 ACTIVE EFFLUENTS RELEASE REPORT l
JULY-DECEMBER 1986 OPERATING LICEllSE N0's. DPR-21, DPR-65, 8 NPF-49 DOCKET N0's 50-245, 50-336, 8 50-423 Q 3YY@d57
I General Offices o Selden Street. Berl[n. Connecticut
).,,7.'on weasowacow =.7a7c om, ~
P.O. BOX 270 q
HARTFORD. CONNECTICUT Ci141-o270 L
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(2on ess-sooo February 27,1987 Docket Nos. 50-245 30-336 30-423 B12432 Re: 10 CFR 50.36a U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C. 20535 Gentlemen:
Millstone Nuclear Power Station, Unit Nos.1,2 and 3 Semiannual Radioactive Effluents Release Report in accordance with the requirements of 10 CFR 50.36a and the Radiological Effluent Technical Specifications, 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 & gaseous effluents for the period of July - December,1986. An Annual Radioactive Effluents Dose Report (to be submitted in March,1987) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released during the previous calendar year (January - December,1986).
Due to unavoidable delays in sample analysis, results for Sr-89, Sr-90, Fe-55, and gross alpha for the last quarter of 1986 are incomplete. These results will be forwarded as soon as they become available.
The reoort 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 10 CFR 50.4(b)(2)(viii).
2 Sample analyses delays from our contracted lab facilities due to the excess sample load from the Chernobyl incident had caused the results for Fe-55, SR-89, Sr-90, and gross alpha to be incomplete for the January - June,1986 report.
These updated tables are included with this report as Appendix A.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY h.bs E. J. Mroczka Senior Vice President L
By: C. F. Sears Vice President cc:
Dr. Thomas E. Murley, Region ! Administrator
- 3. Shedlosky, Resident inspector Unit 3 T. Rebelowski, Resident Inspector, Millstone Units 1 and 2
- 3. 3. Shea, NRC Project Manager, Millstone Unit No. I D. H. Jaffe, NRC Project Manager, Millstone Unit No. 2 E. L. Doolittle, NRC Project Manager, Millstone Unit No. 3
TABLE OF CONTENTS 1.0 Introduction 2.0 Radioactive Effluent Releases 3.0 Radioactive Solid Waste 4.0 Supplemental Information 5.0 Changes to the REMM/0DCM/PCP 6.0 Effluent Monitor Inoperability Appendix A - Updated Tables i
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INTRODUCTION 1.0 This report is being submitted for Northeast Nuclear Energy Company's Millstone Nuclear Power Station, Units 1, 2 and 3 in accordance with the requirements of 10CFR50.36a, and the Technical Specifications and in the format outlined by U.S.
During the period covered by this report, Unit No. 1 operated with a unit capacity factor of 88.5%, Unit No. 2 operated with a unit capacity factor of 42.2%, and Unit No. 3 operated with a unit capacity factor of 81.8%.
(Percent of design electrical rating.)
Unit No.
2 was shutdown September 1986 through December 1986 for refueling.
A single report is being submitted for all three units as they i
share a number of items related to this report.
- However, release data are presented separately for each unit.
l 0
4
RADIOACTIVE EFFLUENT RELEASES 2.0 The plants were operated in accordance with the Technical Specifications.
The liquid and airborne radioactive effluents are given in the attached tables as follows:
Table 2.1-1 Unit 1 Liquid Effluents-Summation Table 2.1-2 Unit 1 Liquid Effluents-Batch Mode Table 2.1-3 Unit 1 Gaseous Effluents-Summation Table 2.1-4 Unit 1 Gaseous Effluents-Elevated Continuous Table 2.1-5 Unit 1 Gaseous Effluents-Batch Mode Table 2.2-1 Unit 2 Liquid Effluents-Summation Table 2.2-2 Unit 2' Liquid Effluents-Continuous Mode (SGBD)
Table 2.2-3 Unit 2 Liquid Effluents-Batch Mode Table 2.2-4 Unit 2 Gaseous Effluents Summation Table 2.2-5 Unit 2 Gaseous Effluents-Mixed Continuous Mode -
Unit 2 Ventilation and S.G. Blowdown Tank Vent Table 2.2-6 Unit 2 Gaseous Effluents-Mixed Batch Unit 2 Containment Vents Table 2.2-7 Unit 2 Gaseous Effluents-Elevated Batch Unit 2 Waste Gas Tanks Table 2.3-1 Unit 3 Liquid Effluents-Summation Table 2.3-2 Unit 3 Liquid Effluents-Continuous Mode (SGBD)
Table 2.3-3 Unit 3 Liquid Effluents-Batch Mode (LWS)
Table 2.3-4 Unit 3 Liquid Effluents-Batch Mode (WNS)
Table 2.3-5 Unit 3 Gaseous Effluents-Summation Table 2.3-6 Unit 3 Gaseous Effluents-Mixed Continuous (Unit 3 Venti 11ation Vent)
Table 2.3-7 Unit 3 Gaseous Effluents-Mixed Continuous (ESF Building Vent)
Table 2.3-8 Unit 3 Gaseous Effluents-Mixed Batch (Containment Drawdown)
Table 2.3-9 Unit 3 Gaseous Effluents-Mixed Batch (Containment Purge)
Table 2.3-10 Unit 3 Gaseous Effluents-Mixed Continuous (Turbine Gland Sealing System Exhaust)
Table 2.3-11 Unit 3 Gaseous Effluents-Mixed Batch (Main Condenser Mechanical Vacuum Pump Exhaust)
Table 2.1-1 MILLSTONE NUCLEAR POWER STATION UNIT #1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES S
UNITS JULY AUGUST SEPTEMBER TOTALS TEAR 1986 A. Fission and Activation Products
- 1. TOTAL ACTIVITY Ci RELEASED 9.75E-04 8.48E-02 1.49E-01 2.39E-01
- 2. AVERAGE DILUT D yCi/mi 1.31E-11 1.1lE-09 2.01E-09 1.06E-09 ACTIVITY DURING PERIOD B. Tritium
- 1. TOTAL ACTIVITY RELEASED 1.95E-03 6.81E-01 3.30E-01 1.01E+00 2 =;=,ng;=,,,
uCu.1
- 2. 62 E-n 8.9 u-09 u.u6E-09 u.
-09 C. Dissolved and Entrained Cases
- 1. TOTAL ACTIVITY 4.64E-04 2.78E-04 7.42E-04 RELEASED 9 -1 37
-1 3 30E-12 ACT UR PERIOD D. Cross Alpha
- 1. TOTAL ACTIVITY RELEASED
<4.56E-06 14.13E-05 13.92E-05 E. Volume
- 1. VOLUME OF WASTE L
RELEASED
- 7. 60E+04 5.16E+05 3.92E+05 9.84E+05
- 2. VOLUME OF DILUTION DURING RELEASES 2.03E+09
- 3. 60E+09 4.22E+09 9.85E+09
- 3. VOLUME OF DILUTION LITERS 7.44E+10 7.62E+10 7.40E+10 2.25E+11 i
DURING TIME PERIOD
l Table 2.1-1 MILLSTONE NUCLEAR FOWER STATION UNIT #1 LIQUD RFFLUENTS - $129(ATION OF ALL RELEASES
' QUARTERLY UNITI October November December TOTALS YEAR 1986 A. Fission and Activation Products Ci 5.74E-04 2.18E-04 3 29E-03 4.08E-03
- 1. T A
- 2. AVERACE DILUTED U 1/*1 7.82E-12 3.05E-12 6.69E-Il 2.10E-ll ACTIVITY DURING PERIOD
- i i
i
- 3. Tritium Ci 2.45E-03 1.27E-02 7.92E-01 8.07E-01 hAD U
3.3
-11 7
-O l.61E-08 4.16E-09
- 2. AVERACE DILUTED ACTIVITY DURING PERIOD C. Dissolved and Entrained Gesas
- 1. TOTAL ACTIVITY C1 1.10E-04 1.10E-04 RELEASD
- 2. AVERAGE DILUTED UCi/M 2.24E-12 5.67E-13 ACTIVITY DURING PERIOD D. Cross Alpha
- 1. TOTAL ACTIVITY I
RELEAID
<J.46E-05 fJ.58E-05 63.01E-05 E. Volume
- 1. VOLINE OF WASTE L
RELEASD 1.62EM 5 1.58 EMS 5.01EM5 8.21EM5
- 2. VOLUME OF DILUTION L
DURING RELEASES 3.45E+09 3 84E+09 3.25EM9 1.05E+10
- 3. VOLUME OF DILUTION L TERS 7.34E+10 7.14E+10 4.92E+10 1.94E+11 DURING TIME P D100
i l
Tcblo 2.1-2 MILL. STONE NUCLEAR POWER STATION - UNIT #1 LIQUID EFTLUENTS - BATCH MODE Tear 1986 Nuclides Released Unit JULY AUGUST SEPTEMBER rtejIy Ci Ci 4.08E-05 5.79E-04 3.68E-03 4.30E-03 m-54 C1 2.27E-03 2.27E-03 Ci Co-58 Ci 5.82E-04 3.16E-03 1.49E-02 1.86E-02 Co-60 5.79E-03 3.45E-03 9.24E-03 C1 1-131 4.51E-04 4.51E-04 Ci 1-133 Ci 4.32E-03 6.52E-03 1.08E-02 C1 Co-134 C1 1.82E-04 6.86E-02 1.15E-01 1.84E-01 Co-137 ci ci ci ci ci 4.52E-04 1.34E-03 1.79E-03 ci^
f Na-24 C1 C1 C1 Ci Fe-55 ci 1.67E-04 1.29E-03 9.14E-04 2.37E-03 Sr-89 C1 13.04E-06 1.70E-04 1.14E-03 1.31E-03 2.81E-06 2.22E-05 1.80E-04 2.05E-04 Ci Er-90 9.75E-04 8.48E-02 1.49E-01 2.39E-01 ci T*tal Activity 3.98E-04 2.78E-04 6.76E-04 Ee-133 ci 6.60E-05 6.60E-05 ci In-135 C1 Ci Ci C1
,r.---
Table 2.1-2 MILLSTONE NUCLEAR POWER STATION - IMIT #1 LIQUID EFFLUENTS - BATCH N00E Year 1986 Qu'arterly Nuclidae Released Unit October November December Ci 2.04E-05 2.04E-05 h-54 C1 Ci 3.01E-06 9.01E-05 9.31E-05 Co-58 C1 Co-40 C1 1.40E-04 1.36E-04 1.04E-03 1.32E-03 Ci C1 C1 1.04E-05 Cs-134 Ci 1,04g.05 Co-137 C1 2.11E-04 6.38E-05 6.01E-04 8.76E-04 ci c1 ci ci ci 4.12E-05 4.12E-05
~
Na-24 ci ci ci ci ci Fe-55 ci 2.03E-04 11.58E-04 I.50E-03 1.70E-03 1.00E-05 2.21E-05 Sr-89 ci 6.80E-06 1.53E-05 1
ar-90 ci 2.43E-06 11.58E-06 63.76E-06 2.43E-06
.1
-04 3.29E-03 4.08E03 Total Activity ci Ci 1.10E-04 1.10E-04 Ita-1M ci ci c1 C1 I
Ci 1
Tcble 2.1-3 MILLSTONE NUCLEAR F0WER STATION UNIT f1 CASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QUARTERLY gggyg TOTALS JULY AUGUST SEPTEMBER TEAR 1986 A. Ficsion and Activation Cases Ci 1.50E+02 7.90E+02 6.18E+02 1.56E+03 ED
- 2. AVERAGE RELEASE RATE UCi/sec 4.99E+01 3.25E+02 2.59E+02 1.99E+02 FOR THE PERIOD
- 3. Iodines
- 1. TOTAL I-131 ACTIVITY Ci 9.91E-04 1.48E-03 1.46E-03 3.93E-03 RELEASED
- 2. AVERAGE RELEASE RATE 3.30E-04 6.09E-04 6.11E-04 5.03E-04 FOR THE PERIOD C. ? articulates
- 1. TOTAL PARTICULATE Ci 2.28E-02 3.05E-03 1.85E-03 2.77E-02 ACTIVITY PriFASED
- 2. AVERAGE RELEASE RATE 1/**C 7.60E-03 1.26E-03 7.74E-04 3.54E-03 FOR THE PERIOD
- 3. TOTAL GROSS ALPHA Ci 5.96E-06 8.52E-07 5.72E-07 7.38E-06 ACTIVITY RELEASED D. Tritium
- 1. TOTAL ACTIVITY Ci 7.64E+00 6.51E+00 5.40E+00 1.96E+01 RELEASED
- 2. AVERAGE RELEASE RATE UOI!***
3.14E+00 2.68E+00 2.26E+00 2.50E+00 FOR THE PERIOD
Table 2.1-3 MILL 8 TONE WCLEAR POWER STATION UNIT fl CASROUS EFFLUENTS - $1DWATION OF ALL RELIASES QUARTERLY UNITS October November December yggggg TEAR 1986
~
A. Fission and Activation Cases
- 1. TOTAL ACTIVITY Ci 4.03E+02 4.38EM 2 1.86E+02 1.03E+03 g
RELEASED 1
- 2. AVERAGE RELEASE RATE UCi/see 1.34E+02 1.82E+02 7.72E+01 1.31E+02 POR TEE PERIOD l
- 3. Icdineo
- 1. TOTAL I-131 ACTIVITY Ci 1.34E-03 2.09E-03 7.58E-04 4.19E-03 RELEASED 2.
RA E M E RAM UCi/sec 4.44E-04 8.67E-04 3.15E-04 5.34E-04 g gg C. Particulates
- 1. TOTAL PARTICUMTE ci 1.55E-03 2.07E-04 6.03E-04 2.36E-03 ACTIVITY M2 2.
E EASE RAM UCi/sec 5.13E-04 8.59E-05 2 50E-04 3 01E-04 gg 3.
Cno Ci 6.38E-07 3.59E-07 5 74E-07 1 57E-06 gg l
l l
D. Tritium
- 1. TOTAL ACTIVETT Ci 5.15E+00 5 06E+00
' 11E+00 1.43E+01 RELEASD
- 2. AVESAGE RELEASE RATE 1.71E+00 2.10E+00 1.66E+00 1.83E+00 FOR THE PERICO Data for Sr-89,Sr-90, gross (A is incomplete
Tcble 2.1-4 MILLSTONE NUCLEAR POWER STATION - UNIT #1 CASEOUS EFFLUENTS - ELEVATED RELEASE - CONTINUOUS MOD SEPTEMBER u
f hc11 des Released l Unit JULY AUGUST f 2. 65E+02 6.40E+02 l
- 1. Fission gases 3.75E+01 Ei C1 2.59E+01 7.99E+01 7.21E401 1.78E402 3*-lM C1 1.57E+01 4.97E+01 3.09E+01
- 9. 63 E401 Er-87 EP-88 Ei 1.17F+01 7 ?or+n1 7 n?r n1 s 11r+nt C1 8.86E+01 -
1.57E+02 1.41E+02 3.87E+02
~
I#*Ib CI 5.93E+00 1.42E+01 1.1st+01 3.36F401 3.-135 b133 C1 C1 9.17t+oi 7,697+oi i_gyy n, Ci Xe-135m C1 C1 ti t1 C1 7.90E+02 16.18E+02_
l.56F+n1 i
tt 1.snr+no
. Tota For hviod l
I h 1_46v-n1 T otr n1
- t. Sodines Ci k oir n4 1.cgr-n1
,.08E-03
,1.10E-02 1.16E-02
,2.97E-02
_ l
~
todine-131 7
Ci todine.133 i
- 3. Particulates l 7.16E-03 1.84E-03 9.91E-04 9.99E-03 Ci Ci s nar-n1 7.nter-04 4.s?r-ns 5.33r-01 Cr-51 8.53E-04 Mn-54 C1 8.16r-04 1.67E-05 Co-58 Ci 9.47E-04 1.60E-04 7.23E-05 1.18E-03 Fe-59 Co-60 Ci 8.46E-03 5.54E-04 3.99E-04 9.41E-03 _
5.99E-05 5.99E-05
,3.84E-06 _
rM 2n-65 3.84E-06 I-131 C1 6.I1E i Ci 6.I1E-06 Co-57 6.77E-05 6.18E-05 _
l.72E-04 __
C1 4.28E-05 Cs-137 6.44E-05 4.06E-05 1.05E-04 C1 5.06E-05 3a-140 Ci 5.06E-05 3.47E-05__
Ce-141 3.47E-05 C1 6.46E-05 Zr-95 ci 6.46E-05 3.04E-04 C1 2.94E-05 1.42E-04 1.33E-04 Nb-95 2.24[-_05_
La-140 Ci 2.74E-05 9.76r n% --
Ru-103 5.4.75F-07 5.1RF 05 C1 4 sAr ns C1 1.88E-06 1.44E-06*
8.64E-07 4.18E-06_
Sr-89 3.27r ns _
St-90 C1 1.77r 05
.1.R5F 03_ 12.77E n' o
Sb-124 Ci
,7
?ar n?
i 1 0;r 01 t
TOTAL
- - - - - ^ - - - - - _ _ _ _
Table 2.1-4 MILLSTONE NUCLEAR POWER STATION - IntIT #1 CASEOUS ETFLUENTS - ELEVATED RELEASE - CONTINUOUS MODE
[ Eec11 des Asleased lOnft 0*ctober l November December 1.
Ffssion gases E 353
.C1 1.18E+02 1.52E+02 6 62E+01 3.36E+02 te.s?
_C1 5.63E+01 6.52E+01 2.75E+01 1.49E+02 C1
- 4. 08E+01-2.27E+01 3.57E+00 6.71E+01 ty-88 Er-89m C1 1.88E+01 _ 2.09E+01 9.79E+00-4.95E+01
', ~ ~
~
' C1 1.28E+02, 1.26E+02 5.92E+01 3 13E+02 E 13 Es.i n Cl 8.92E+00 5.62E+00 4.23E+00 1.88E+01 C1 C1
[. Ie.ine C1 3.25E+01 4 55E+01 1.52E+01 9.32E+01 C1 ti
~
C1 tt Ar-11 tt Toki For Derite C1 4.03E+02 -
4.3BE+02 1.86E+02 1.03E+03
- 3. Iedtnes_
7.58E-04 4.19E-03 todine.131 C1 1_. 34E-03 2.09E-03 (ed(ne.133 Ci 8.14E-03 l'.35E-02 1.64E-03 2.33E-02
- 3. Partism1stes Cl 9.71E-04 4.13E-05 1.43E-04 1.16E-03 Cr-51
&_sa Cl 4 35E-05 1.92E-05 3.24E-05 9.51E-05 tt Co-58 Cl 6.32E-05 3.96E-05 1.03E-04 __
Co-60 C1 2.26E-04 7.58E-05 2:37E-04 5.39E
- es CI C1 Cs-137 C1 4.31E'-05 1.28E-05
'3.44E-05 _ 9.03E-05 Ba-140 C1 2.24E-05 3.25E-05 5.49E-05 41 Ci ct La-140 Cl 1.37E-04
_3.23E-05 4.67E-05 2.16E-04 C1 Sr-49 Cl 4.60E-05 2.52E-05 3.57E-05 1.07E-04 Ci 6_. 5 5 E-07 15.81Er07 1.64E-06 2.10F.
tr-10_
tt TOTAL C4 1.55E-03 2.07E-04
,6.03E-04 2.36E-03
Tchio 2.1-5 MILLSTONE MICLEAR POWER STATION - UNIT #1 GASEOUS EFTLUENTS - 31.IVATED RELEASE - RATCH MODE - C0h7AI II l Ase11 des Released l Unit July l August September No discharges this quarter f
- 8. fission gases
)
l
_C1 go.13g C1 Er.37 C1 gr.as C1 gr.sg C1 3e-1)$
Ci 3e-133 C1 Er.eg Ci 1. 1 77 Ci
- Re-119e CI EF-Sb C1 Ie-13D C1 s
3e.131s Ci gr-SS Ci Ar-77 "Cf
.T4tal Fer k riod I
- 1. todines I
Cl I
todtne-131 l
ti l
I todine 133
- 3. Particulates Cl Cr-51 Ci m-se Cf Te-59 Co-58 C1
-~
C1 Co-60 rM Zn-65 1-131 C1 C1 Cs 134 Cl Cs-137 C1 f
sa-140 Cl
~
Ce-141 C1 Ce-144 ci La-1EO C1 C1 C1 St-89 C1 Sr-90 C1 1
l I
II L
l TOTAL
Tcble 2.1-5 MILLSTONE NUCLEAR POWER STATION - IINIT #1 CASEQUS ETTLUENTS - ELEVATID RELEASE - RATCE MODE - CONTAINMENT PURGE
[ Aiclides teleased Unit l0ctober l November December (e
~
No discharges this quarter 9, yggggg,,,,,
b 13g
_C1 ar.y7
.C1 C1 gr gg b eta Ci b 135 C1 5e-133 Ci gr.39 C1 te-177 C1 b1h Ci b8%
Ci te-33)e Ci Ci 3,-131m 5
^
Er-85 Ci Ar.yr ti Tatal For period Ci
- 2. lodines todine-131 Ci todine-133 Ci
- 3. Particulates C1 cr-51
&-s4 Ci Te-$9 C1 Co-58 C1 Co-60 C%
Zn-65 cf I-131 C1 Cs-134 C1 Co-137 Ci sa-140 C1 Ce-141 Ci Ce-144 C1 cf 14-1CO C1 C1 Sr-89 C1 II Sr-90 Ci gq L.
Tcble 2.2-1 MILLSTONE NUCLEAR POWER STATION UNIT #2 11@lD EFFLUENT - SUN (ATION OF AL1, nytviagg ARTERLT WIT 8 July August September @ TOTALS 1986 gggg L. Fission and Activation Products I. TOTAL ACTIVITY Ci 1.73g.01 1.15EMO 2.29E-01 1.55E%0 RELEAstD ffY UC1/m1 1.79E-09 1.20E-08 1 97E-08 7 59E-09 UR PERIOD B. Tritium Ci 2.01EM1 4.79E+01 1.3BEM I 8.18EM1
- 1. T A IM gg
- 2. AVERAGE DILUT 2 UC1/mi 2.08E-07 5 00E-07 1.19E-06 4.01E-07 ACTIVITY DURING PERIOD l
C. Dissolved and Intrained Cases
- 1. YOTAL ACTIVITY Ci RELEASD 5 28E-01 3 43E-01 2.86E-01 1.16E+00 VCi/mi 5.45E-9 3 5BE-09 2.47E-08 5.68E-09 AC V FERIOD D. Oroaa Alpha
- 1. TOTAL ACTIVITY RELEASED 11.061-03 12.54E-03 11.41E43 12.54E-03
- s. values
- 1. VOLUME OF MASTE I*I RELEASED 1.51M07 2.54FA07 1.41FA07 5,46E+07 LITERB 1.10E+10 1.58E+10 8.30I+10 1.11E+11
[,,fah
- 3. VOLUME OF DILUTION LITERS 9.68E+10 9.58E+10 1.16E+10 2.042E+11 DURING TIME TER12
- includes Unit i dilution for periods of releases while shutdown (for MPC calculations)
Table 2.2-1 MILL 5 TONE NUCLEAR POW S STATION WIT #2 LI@ID ETFLUENT - SUIMATION OF ALL RELEASES I
' @ARTERLY UNIT 5 October November December TgAL3 TEAR 1986 A. Fission and Activation Products
- 1. TOTAL ACT191TY C1 8.01E-01 ggg
- 2. AVERACE DILITIED VCi/al 2.85E-07 ACTIVITY DURING PERIOD i
l I
- 5. Tritium i
A Ci 4.38E+00 3.10E+00 5.38E+00 1.29E+01 D
2.
D UCi/mi 1.56E-06 1.32E-06 1.09E-07 2.37E-07
- pgggg, i
i C. Dissolved and Entrained Cases 1.15E-04 3.11E-03 I* T A"U3U C1 2.99E-03 g
2.33E-12 5.71E-Il UI "
UC1/al 1.06E-09 gIY D PERIOD l
l h
- 3. Orces A1P a
- 1. TMAL Af,TIVITY EA 17.981-05 RE1.tASD
[
E. timme I
LITERS 1.33E+C6 9.391+05 2.79E+07 3.02E+07 LITsRs 1.13E+10 7 02u09 1.185+10 3.01E+10 ggghggty I
LITERS 2.81E+09 2.35E+09 4.93E+10 5.45E+10 IhERIOD I'
Data for Sr-89.Sr-90. gross gis incomplete includes Unit 1 dilution for periods of releases while shutdown (for MPC calculation'
Tcble 2.2-2 WILL8 TONE NUCLEAR POWEA SIAT10N UNIT #2 LIQUID EFFLUENTS - CONTINUccS. 3/g Ye:r 1986 Qu' art ly' puc11 des Released Unit July Au8ust September Ci C1 C1 7.85E-04 Co-58 Ci 7.85E-04 Co-60 C1 2.72E-03 2.64E-03_
5.36E-03 2.03E-02 1.691-02 3.721-02 1-131 Ci 3.43E-02 1.97E-02_
3.40E-02_
1-133 C1 I-135 Ci
_3.82E-02 8_.20E-03 4.64E-02 Co-134 Ci 4.22E-03 4.22E-03 1.07E-02 2.ist-03 1.29E-02 C1 Cs-137 i
ci ci ci ci ci 2.66E-02 1.0$E-02 3.71E-02 I_132 ci 1.06E-02 1._06E-02 I-134 c1 Ci Ci ci Fe-35 cg 11.38E-02 12.29E-02 11.20E-02 d.29E-02_
5r-89 et 14.83E-04 16.87E-04 13.60E-04 16.87E-04 ar-co cf 11.04E-04 43.89E-04 12.04E-04 43.89E-04_
~
Total _ Activity Ci Ci 3 59E-01 2.79E-01 7.13E-02 7.09E-01 M3 7.34E-03 7.34E-03 Xe-133 et
_6.82E-03 2.69E-03 9.51E-03 Ye-1M ci 6 85r-02 6 85E-02 No-135M ci 5.80E-01_.
Kr-83 ci 5.13E-01 6 72E-02
^
S
Table 2.2-2 i
MILLSTONE NUCLEAR POWER STATION UNIT #2 Taar _
1986 LIQUID IFFLUENTS - CONTINUQUS - 3/0
'"*'I7 Wuclides Released Unit October November December Ci
~
C1 Co-58 C1 6.65Z-03 6.65E-03 1.79E-02 1.79E-02 Co-60 C1 C1
[_
1-133 Ci 3 04E-03 3.04E-03 7.46E-03 7.46E-03_
Co-134 Ci Ci ci__
c1
_ci ci ci ei C1 Ci
_ C1 cg Fe-55 et 87-89 ci ar-to cf Total Acti_vity ci
-z_
8.27342 4.27E42
~
~
g_3 Ee-133 ci En-1M Cl Ea-135h ct Crema 11aha di Ci Ci
WILIATONE NUCLEAR POWER STATION UNIT #2 TTr 1986 1.11UID ETT UENTS - 1AT "M - AWMT/E NT /TK Nuclides Released Unit July August September Qu rta ly Cs-136 2.11E-05 2.11t-05 Co-144 3.48 M 5 3 4'e Ci Cr-51 C1 1/13E-04 3.86E-03 1.89E-03 5.861-03 h-54 Ci 1.19E-03 5.27E-03 3.51E-04 6.81E-03 Ci 5.14E-05 5.02E-05 8.011-05 1.821-04 Nb-95 Co-38 Ci 2.92E-03 1.04E-01 3.72E-02 1.44E-01 Co-60 Ci 5.94E-02 7._83E-01 7.59E-02 9.18E-01 1-131 Ci 6.02E-04
- 2. 7 7 E-03_.
9.45E-03 1.28E-02 I-133 Ci 4.72E-04 4.94E-03 6.90E-03 1.23E-02 1-135 C1 3.22E-04 2.91E-04 6.13E-04 Co-134 C1 2.09E-02 8.18E-03 2.80E-03 3.19E-02 Co-137 Ci 7.0$E-03
- 2. 54E-02__
__1.07E-02 4.32E-02 Co37 et
__1.31E-04 3.99E-05 1.71E-04 2.95E-04 1.20E-03 1.50E-03 Sb-124 eq 5.29E-05 5.24E-04 5.77E-04 La-140_
ci_
4.84E-04 4.84E-04 Tc-99m ei 8.63E-05
_8.632-05 W-187 ci Nb-97 ci 1.90E-03 1.67E-03 6.54E-04 4.22E-03 Gr-92 Ci _
4.42E-04 1_.93E-04 1.01E-04 7.36E-04 S5-125 C1 1.37E-03 1.41E-03 3.27E-C3 6 05E-03
_1.26E-04 4.26E-04 Na-24 Ci_
3.00E-04 1.50E-04 1.31E-03 As-110M ci 9.64E-04 1.99E-04 re-55 ct 7.24E-02 6.15E-02 1.73E-02 1.51E-01 fr-89 Ci' 55.36E-05 1.43E-04 3.62E-04 5.05E-04_
tr no ci 19.38E-06 12.46E-05 2.56E-05 2. 56E-0."
1.70E-01 1.00E400 1.71E-01 1.34E400 kt tv ci T s 5.16E-04 4.27E-03 4.79E-03 Ko-133M 3.90E-01 5 20E-03 1.49E-01 2.361-01_
~
Ko-133 c1 5.51E-03 4.28E 02
- 4. 21E-0_2_
9.04E-02_
re-135 c1 8.03E-04 5.02E-04 1.31E-03 Xt-135M eg 8.63E-05 4.50E-03 4.41E-03 Kr-85 ci 11 - 3 Ci 1.97E401 4.76E4a1 1.17E+0f R 10F+0i
--- -~----. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Table 2.2-3 MILL 5 TONE NUCLEAR P0hT.R STATION WIT #2 Y ar 1986 LIQUID b1 miss - n'rs - m/cm /TK Wucitdes Released Unit October November December 1.24E-04 1.32E-04 Cel144 Ci 7.943-06 Cr-51 Ci 4.48E-02 1.36E-02 3.62E-02 9.46E-02 Mn-54 Ci 4.64E-03 1.17E-02 5.22E-03 2.16E-02 Ci 2.411-03 1.42E-03 5.80E-04 4.41E-03 La-140 Co-58 C1 3.58E-01 2.38E-01 2.89E-01 8.85E-01_
Cc-60 C1 1.79E-01 1.25E-01 2.64E-01 5.68E-01 9.12E-05 1-131 Ci 9.12E-05 1.19E-04 1.74E-02 1-133 C1 1.73E-02 C1 2.70E-03 2.87E-04 1.97E-03 4.96E-03 Zr-95 Co-134 Ci 6.30E-05 1.97E-03 2.80E-03 4.33E-03 Cs-137 Ci 4.65E-03 1.20E-02 2.05E-02 3.72E-02 3.23E-04 2.94E-04 2.63E-04 8.80E-04 Ru-303 c1 1.04E-03
_6.69E-04 8.37E-04 2.55E-03 cf Co-57 5.04E-03 4.74E-03_
3.95E-03 1.37E-02_
Ag-110m ci 1.93E-03 1.70E-03 1.40I-03 5.0_3E-03 ci sr-92 1.25E 3.65E-05 3.28E-04 1.61E-03 Fe-59 ci Nb-95 et 6.34F-03 3.19E-03 6.87E-03 1.64E-02__
7.76E-03_
8.59E-03 6.48E-03 2,28E-02 5b-97 ci 1.67E-02 2.38E-02 1.57E-02 5.62E-02 sb-124
.C1 Sb-125 ci 2.34E-02 7.24E-02 3.11E-02 1.27E-01 Ka-24 c1 3.40E-04 5.38E-04 1.85E-04 1.06E-03 1.20E-01 Fe-55 ci Sr. 89 ci 2.13E-04 c1 2.26E-05 ar en subrotal subtotal 8 *01E41 (5.20E-01) (6.8BE+00)
Total Activity ci H-3 C1 4.38E+00 3.10E+00 5 38E+00 1.29E+0!
2.96E-05 3.02E-03_.
I4-133 c1 2.99E-03 4.59E-05 4.591-05 h-1M C1 3.95E-05 3.95E-05 Ar-41 ci Cross Aloha ci 17.98E45 0
-6 i
Table 2.2-3 M11,LSTONE m) CLEAR POWER STATION UNIT #2 LIQUID EFTLUENTS - SATCH - TK 10/11 ar 1986_
~
Qdarterly Nuclides Released Unit July August September emi Not Applicabis cr-51 C1 Mn-54 C1 Te-99M C1 Co-58 C1 Co-60 Ci
~
1-131 Ci I-133 Ci 1-135 Ci Co-134 Ci g
Cs-137 Ci 1
Mo-99 ci Co-141 et en-144 Ci En-65 et 7e-59 ci ci ci
_Ci ci Ci fe-55 c1
-^
Er-89 Ci
__te-eg Ci Total Activity Ci r
Xa-133 ci Ya-115 Ci Xa-135M ci ci ci Ci
Table 2.2-3 MILLBTONE NUCLEAR POWA STATION WIT #2 y.,
1986 L1 QUID EFFLUENTS - RATC3L - TK 10/11 terly puclides Released Unit October November December Wo Discharges this Quartar Cr-31 C1 h-34 Ci Te-9FM C1 Co-50 Ci Co-60 Ci
~
1-131 C1 1-133 C1 1-135 C1 Cs-134 Ci Cs-137 Ci No-99
'ei Ce-141 c,
ca.1AL Ci --
[
En-65 I
ci Fe-39 ci c1 ci Ci Ci ci F3-55 gg Sr-89 ci han ci Total Activity 21
_1 T
.i
~
.-133 ma 115 ci Es-13SM a
ti 21 fi
Tcble 2.2-4 MILLSTONE NUCLEAR POWER STATION UNIT #2 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NUAEIIAkY UNITS July August September TOTALS TEAR 1986 A. Fission and Activation Gases
- 1. T T AWm C1 1.82E+00 1.93E+01 4.77E+01 6.89E+01 g
2.
E A
UCi/sec 7.24E-01 6.39E+00 1.90E+01 8.58E+00 R
~
- 3. Tcdines
- 1. TOTAL T-131 ACTTVITY ci 2.351-04 3 67E-04 3.83E-03 4.43E-03 RELEAS D
- 2. AVERACE RELEASE R/.71
/888 9.36E-05 1.22E-04 1.53E-03 5.51E-04 FOR THE FERIOD C. Partic_ulates
- 1. TOTAL FARTICULATi.
I 9.26E-06 6.87E-06 1.41E-06 1.75E-05 ACTIVITY RELEAS E
- 2. AVERAGE RELEASE RATE i ***
FOR THE PERIOD 3.69E-06 2.27E-06 5.62E-07 2.18E-06
- 3. TOTAL GROSS ALPH4 ACTIVITY RELEASD 11.73E-07 12.79E-07 12.81E-07 12.44E-07 3._ Tritium
- 1. TOTAL ACTIVITY Ci 6.20E+01 1.12E+01 5.59E+00 7.88E+01 RELLAS D
- 2. AVERAGE RELEASE RATE if***
2.47E+01 3.71E+00 2.23E+00 9.80E+00 FOR THE PERIOD
(
Tcbla 2.2-4 MILLSTONE IlUCLEAR 70WER STATION MIT 02 GAstops EFFLUENTS - 8120nTION OF ALL RELRASIS l
QUARTERLY October November December TOTALS TEAR 1986 A. Fission 'nd Activation Games a
- 1. TOTAL ACTIVITY Ci 2.20E-01 2.05E-02 2.41E-01 RE1.EASD
- 2. AVERACE RELEASE RATE UCi/sec 8.21E-02 7.65E-03 3.03E-02 FOR THE PERIOD
}.Tedinaa
3.70E-06
- 2. AVERACE RELEASE RATE U 1/sec 9 32E-05 1.53E-06 2.99E-05 FOR THE PERIOD C. Particulates
- 1. TOTAL PARTICULATE C1 5.21E-06 1.12E-05 7.941-06 2.44E-05 ACTIVITT RELEASEE
=
- 2. AVERACE RELEASE RATE UCi/sec 2.08E-06 4.63E-06 2.63E-06 3.07E-06 FOR THE PERIOD
- 3. TOTAL GROSS ALFMA CA ACT1VITY RELEAS D
<2.14E-07
. 1-
. I D. Tritimi _
- 1. TOTAL ACTIVITT Ci 3.24 emu 2.84E+00 3.46E+00 9 54E+00 RELEASED
- 2. AVERACE RELEASE RATE FOR THE PERIOD 1.29E400 1.17E+00 1.15E+00 1.20E+00
- Data for Sr-89, Sr-90, gross x is incomplete
l Table 2.2-5 MILI. STONE NUCLEAR POWER STATION - UNIT #2 GA510US ETF1. VENTS -MIXED RELEASE - C01:TIhT005 MODE Iccr 1986
[ Ac1fdes Aetessed
_ Unit July August September, 4Ql1
- 1. Ffssion estes Re.338
_Cl n_.rf _
C1 _
_ _t1 p-se h-ese C1
~
C1 24 135 M 6! -
7.12E4 0 8,37E-01__ 8.68E+00 ie.13)
Cl.
tr.99 Ci 9.93E+03 4.394+01 5138E+01 16-177 Cl Re-133r __
C1 D-sb
_ C1
_!e.133s
_Cl _
I
. tt I --
fe.i b _
5 h-85 ti AP-77
, ft Tott) For Petted C1 7.26E-01 *--
1.705EM) 4.47E+01 4.25F+01
- 3. IofInes (inclu(ing s/c vent) 3 (edine 13)
Ct
- 2. 3 5E-_04 3.67E-04
'l.43E-03 i,03F-03 (hitN.533 Ct 6DCh-04 I.46E-03 8.33E-03 1.07E-02
- 3. Particulates C1 Cr-51
\\.
__C1 Hn-S t.
Te -_59 -
__Cl Co-58 gg 3.54t.06 3.54E-06__
Co__60
_ _C1 7.80E-06 2.48E-06 1.417-06 1.17E-05__
Zn-65 ef l_
_ _C1
__l C
Cs-Q4 2.31E-06
_ __ __ _ C s _1_3 7
_,Ji
_1, t.6 NOA -
9.50E-07 Ba-140
_ Ci Ce-141 Cl_
Cs-144 Ci Tritium _
J
- 6. 20EM1_
1.09 tgi g _ g y rmn _ 7_. 8 5 E+01 Cl Ci sr-89 C1
".1.08E-07_
5.2. 5 4E-07 S.16E-07.
13.24E-08 15.08E-E,K6. l. S E-0 6__
sr-to Cl _
Gross Alpha
_ C I__ _11.73E-01_ _17:7dr.n?
19_att h
i
_ - _ _ _ _ _ = _ _ - -
Tcblo 2.2-5 NILLSTONE NUCLEAR POWEA STATION UNIT #2 GASIOUS EFFLUENTS - MIXED RELEASE = CONTINUOUS MBE Tear 1986
[ h tlidet heleased l Unit lDetober l November December aW
- 1. Fisefen genes a ies i
et a rp _
tt
_$1 __
85 4 thats ti 3e-135 81 Es 121 81
~~
Rr.se ti mm.irr et et
.um E>-th tf Xe-112m 24
~
Re.1 h s
it tt E>09 ff
&>FF
~
gg g y,, p,ygeg gg
~S. bdfass
~
2.36E-04 tof tne-Ill C1 2.34E-04 3.70E-06 _
2.58E_-0 5 l
tt 1.99E-05 3.90E-06 l
tedine.133
+
- 8. Stettslates Ru-103 ft 1.49E-06
_1._49 E-06 g
h-1A C1
_7e-59 E4 -
3.60E-06 6.31E-06 Co-58
_ gg _
2.71E-06 T
_ Co-60 tt I
4_.871-06 4.34E-06 9.211-06 Es-6l c1 1-131 i
et
=
Cs-134,
21 7._35E-06 Co-131 81 1.0_1f-06 6.34E-06 Sa-1_49 ~
tt C.
4i
_ s, _
Ce=144 C1 C,
.52.14E-07 Gross Alphs -
t,
.si.43E 07 si...
sr-se
_ _St 42 14E-08 i
Es tt _
- 3. 24 M Q-2 84E400 3 46E+00 9 54r40 a
at
Tcblo 2.2-6 M11.LSTONE NUCitAR POWER STAT!0It - 11 NIT #2 CASEOUS EFTLUENT8 -
MIXED BATCH MODE - ConrIAIIDENT Punct J
Year _ _1_9_86 f Ibelfdes talossed
_l Unit l.N1y l August j septemberg4 Is
- 1. Ffssten gases i
Is.113 C1
=
g _
gg
-Er 88 Ct _ _.
~
re-ssa st I
~
I*-1M C1 ___
1.01E+00 1.01E%0-A 13)
_Cf 5.24E-02 5.24E.
Er-99 C1 I iw C1
_ _ Ie-lh C1 IP-SD CI Se*133m CL fe.111a t
_tt _
Er-89 f(
_ 5 Ar-21 t1 1.66E+00 1.06L+00 tott) For perted 21 l
S. Iodines LI_
(odine 131
_Cl 3.97E 3.97r-nA q,gtne.in gt 1.24E-04 1.24E-04
_3
- ** N '"'* W 41 cr-51
~
1 m._s t
_C_t
_ re -s e _
_ti l
Co-S8 g;
l co-60 Ci te-65 et i
l I-in
_ct l
Co-134
._ C1
__ _ Co-137
_tt _
sa-149 C1
~
Co-141
. $1 co-144 C1
~ - ~ - _
1.52E-02E
~
=
__]
l.52r-n2 _
u-3 en i
41 St u -_ =
gr-89
_C1 z_
_1r-90 C1
--a Ct_
et
Tcblo 2.2-6 MILL 87WE NUCLEAR PWER STATIN - WIT #2 GAssotts ETTLUENTS -
MIXED BATCM NODE - CONTA!WtENT PURC3 Txt 1986 j
l Unit l October l November l December I
[InttijdesAsleased_
g b Finsten gases No Discharges this Quarter I
so-lh1 81 i
w st
_C1 go.gs sm 41 1
Redst 83 sesss 41 I
FM
._ C1 In.ift._ _
Cf
. to.ite.
_ _ =
tt Ci i
gr.g3m _ _
In-H 3m C1 l
Ee-ina s
et Er-Af et l
Ar-17 t1 i
L te W. For h rted et j
- s. secos tedine.131
_C1 C1 l
todine-133 _
- 8. Portfalates C1 Cr-51 m.u C1. -
Fe-39
_tt C'*SO tt Co-60 et T
sn-as n
I_-231 et
=
l ca-1M _
84 co-131
_tt 3a-140 ff Co-141 Cf i
co-144 C1 (1
$1 Sr-89 Cf i
sr-to
--89 g{
i I
Il
.L a__-__
t l
t
Tabla 2.2-7 MILLSTONE NUCLEAR POWER STAT 1011 - 1DlIT (2 i
CASEQUE EFFLUENTS =
ELEVATED BATCE MODE - WGDT 1
i Yase 1986 l
ILtc11 des Celeased l Unit l duly
} August l Septembei 4 ly 1._ Ffssion gases 4
~
~
En-1M Ci 1.25E-04 5.98E-04 Er.37 C1 4.70E-04
= - 2.31E-DJ 8.00E-03 Er=88 Ci S.49E-03 Er=89s 2.75E-03 7.12E-03
~
C1 4.37E-03 l
Ee-139 Ci 8 48E-02 1.66E-04 1.04E-01 1.89E-01 l
3e.133 C1
~ 9.00E-01 1.89E+00 I.66E+00 4.45E+00
~
l L =pe Ci t 139 _ _
Ci i
- xe-i m Ci C1 l
Er.93e__
_ 7.05E-03
~4.6BE-03 3.563-03 1.42E-02 Re-133e
__ t t 1.70E-02
.1.53E-02 3. 9_4_E-02
_tt 5.95E-03 Ie-111m_
l Er-83 tt
_8 00E-02 3.40E-01 1.84E-01 s.04E-01 5.17E-04 1.43E-03 l
Ar-41 tt_
).31E+00 fatal For period ti
- 1. 09 E+00-2.25E+00 1.97E+00
_3. Iodines _
l Sodine-131 Cf iodine.133 C1_ _
' 3. Particulates Cr-51 Ci h 3a C1 Te-59 tt Co-i4 gg Co-60
__gt
__ zn-65 cf
~
1-131 Ci
=
Co-134 _
__ C f Co-137
_Cf Ba-140 C1 Ce-141
. Cf Ce-144 C1-Tritids-gg
. 2.24E-02 3.11E-01 _
7._8_6g 03 3.41E-01 Ct Sr-89 Cf
=
_sr-90 Ci
~~
Ct Ci 4
Table 2.2-7 HILLSTONE NUCLEAR POWER STATION - UNIT #2 GASEOUS EFFLUENTS -
ELEVATED BATCE MODE - WGDT Tear l$ovemberl December l%
11 Ast11 des Reletted l Unit October
- 1. Ffstion genes l
I
_ Es-1M _ __
81 h rt St 81 gp.gg g,,gg gg-
.~
se-13s 81 in-133 C1 2.05I-01~
1.42E-05 2.05E-01 m _n Ct him C1 l
= 2a-l h C1 Cf g>.43.
2.83E-04 Ia.113n C1 2.83E-04
_ _4.83E-03
~
~
4.83I-03 21 2.05E-_02 3.05E-02 go.i_m i
Er-49 tt 9.95E-03 Ar-M tt 2.41E-01
- 2.05r-02
. Total For Period 21 2.2_0E-01*
l
_9. ledinet i
l l
_Nine.131 _
_C4 J
l l
'l Wine-133 41
- 8. Partissistas
_st cr-51 m na C1 Fe-59 et Co-54 Cf Co-60 et En-45 et
~
I-131 C1 Cs-134 C1 Co-137 Jf -
Ba-140 Cf tt Co-141 Co-144 c1 El 3.5AE-o3 6.38E-03
~
hs C1 2.82E-03__
r St-49 Cl St nr.go A
L I
Table 2.3-1 MILLSTONE UNIT No. 3 SUMATION OF LIQUID EFFLUENT RELEASES 1
UNITS TOTALS July Aug Sepg YEAR 1986 L. Fission and Activation Products
- 1. TOTAL ACTIVITY Ci RELEASED 1.177F+nn 3.456F-n1 3.89E-01 1.9616r+00 l
- 2. AVERAGE DILUTED UCi/mi g.17E.09 3.41E-09 2 59E-09 4.78E-09 ACTIVITY DURING PERIOD
- 5. Tritium
- 1. TOTAL ACTIVITY Ci RELEASED 120.7 114.4 32.94 268.04 2.. AVERAGE DILUTED UCi/81 8.38E-07 9.86E-07 2.20E-07 6.54E-07 ACTIVITY DURING PERIOD C. Disssived and Entrained Cases
- 1. TOTAL ACTIVITY i
5.601E-02 2.28E-02 1.74E-02 9.62E-02 RELEASED l 2. AVERAGE DILUTED VCi/mi 3.89E-10 1 97E-10 1.16E-10 2.35E-10 ACTIVITY DURING PERIOD lD. Grcss Alpha
- 1. TOTAL ACTIVITY RELEASED 11.75E-04 13.087E-04 11.19E-04 16.03E-04 E. v21use
- 1. VOLUME OF WASTE LITERS RELEASED
- 2. VOLUME OF DILUTION I'
DURING RELEASES 2.315E+10 1.613E+10 1.354E+10 5.282E+10
- 3. VOLUME OF DILUTION LITERS 1.44E+11 L.16E+11 1.50E+11 4.10E+11 DURING TIME PERIOD
i Table 2.3-1 NILLSTOR 1RIT No. 3 StDMATION OF LIQUID EFFLUENT REUASES
'QUARTDLT UNITS October November December 70745 gggg 1986
-l A. Fission and Activatten Products 3.70AAMIW Ci 3.984E-02 3.71E-02 gg
- 2. AVERAGE DILUT D 1.266E-09 5.54E-09
- ygg g ACTIVITY DURINC FERIOD S. Tritsum I
h#
C1 85.0 47.13 37.22 169 35 D
2.. AVERAGE DILUT D C1/m1 6.1 E-06 7.03E-06 5.48E-06 6.2 E-06 ACTIVITY DURING F nIOD l
C. Dissolved and Entrained Cases
- 1. TOTAL ACTIVITY C1 2.63E-02 2.61E-03 2.89E-03 3.18E-02 RELEAS D
- 2. AVERAGE DILUTED U 1/81 1.89E-09 3.89E-10 4.25E-10 9.10E-10 ACTIVITY DURIN0 FDIOD D. Cross Alpha
- 1. TOTAL ACTIVITY I.36E-04 Ci
<1.57E-04 I
RELEASD E. Volume
- 1. V F WASM LITERS 3.146E+06 1.51E+06 1.53E+06 6.19E+06 2.
F Im LITERS 1.393E+10 6.WE+09 6.79E+09 2.74E+10 LITERS 1.479E+11 1.528E+11 1.59E+11 4.597E+11 DUR PER 0 ' Data for Sr-89,Sr-90, gross M is incomplete
Tcble 2.3-2 NILLSTONE UNIT No. 3 LIQUID EFFLUENTS - CONTINUOUS 1986 Year STEAM CENERATOR BLOWDOWN
.I*j l
Nuclides Released Unit Aug Sept 7,,3y No activity discharged this quarter Ci Cr-51 h-54 Ci Tc-99M Ci Ci co-58 Co-60 Ci 1-131 Ci 1-133 Ci C1 I-135 Cs-134 C1 Cs-137 Ci Mo-99 ci 1
Ce-141 ci Ci' '
Ce-1&L Zn-65 ci Fe-59 ci ci ci Ci Ci cf Fe-55 eg Sr-89 eg ci tr-co Ci Total Activity Xe-133 eg t
In-115 Ci Xe-135M eg Ci ci H-3 Ci
Table 2.3-2 W1LLST WE UN11 No. 3 EI 8~
8 Tear 1986 STIAM 93r5AATOR BLOWDOWN Wualides Baleased Umst October November December
.EN I No Activity Discharged this Quarter Or-51 C1 Ib-54 C1 Ta-99M C1 Co-53 C1 Co-60 Ci I-131 Ci 1-133 C1
~
1-135 C1 Co-134 Ci Ca-137 C1 MD-99 er Co-141 ci ca.1LL ti En-65 c1 Fe-59 et et 21 C1 ci Ci Fe-55 et Sr-89 et a,-an ei Total Aettwit?
Ei L*
Be-133 et n.nts ei Ee-135N et ei 21 F3 m
l Tsble 2.3-3 MILLSTONE UNIT No. 3 LIQUID RAD WASTE EFFLUENTS - BATCH - LWS Year 1986 Nuclides Released Unit July Aug Sept 3.559E-02 1.864E n2
%. Anr n?
C1 h-51 C1 1.024E-02 1.381E-02 6.011r n1 10081E-02 Mn-54 4.4775E-03 Ci 3.475E-03 4.925E-04
- s. tnt na Tc-99M C1 4.075E-02 2.412E-01 2.86E-01 5.6795E-01 Co-58 C1 3.38E-04 3.973E-03 7.22E-03 1.1531E-02 Co-60 Ci 1.071E-02 1.167E-03 2.784E-03 1.4661E-02 1-131 Ci 6.391E-02 3.856E-03 1.15E-02 7.9266E-02 1-133 C1 4.495E-02 4.83E-04 4.96E-03 5.0393E-02 I-135 3.92E-03 5.4E-05 3.974E-03 C1 Sb-124 C1 2'.19E-05
- 1. 65E-04 1.869E-04 CoS7 5.26E-05 1.844E-04_
W-187 ci 1.118E-04 7.375E-05 7.375E-05 Sb-125 pg 9.89E-04 Ba-140 ci o.nor-nt 1.56E-05 2.162E-03 6.83E-03 9.0076E-03 6.73E-05 1.524E-03 1.85E-03 3.4413E-03 Nb-95 '
ci Fe-59 cf 9.339E-01 5.813E-02 2.0E-02 1.01203E00 1.275E-04 3.1925E-03 Na-24 ci 3.065E-03 I-132 cs 5.23E-03 5.231E-03 Pr-144 Ci 1.11E-04 9.675E-04 8.565E-04 1-134 Ci 3.299E-04 3.299E-04 Mn-56 ci
$.98E-03 57.05E-03 1
11.98E-03
.13.09E-03 Fe-55 cs 1.46E-03 6.48E-04 2.96E-04 2.40E-03 Sr-89 eg i 1.98E-05 $2.16E-05 11.58E-05 15.72E-05 sr-90 1.74E-03 4.94E-03 6.68E-03 cf Zr-95 1.1204E+00 3.688E-01 3.72E-01 1.86E+00 cf 1
Total Activity
- ~I33 C1 1.847E-02 2.095E-02 7.96E-03 4.738E-02 1.129E-02 1.329E-03 2.62E-03 1.5239E-02 2.625E-02 4.864E-04 6.84E-03 3.3576E-02; ci re-135 5.601E-02 2.276E-02 1.742E-02 9.6195E-02' Xe-135M gg 11.75E-04 13 09E-04 11.19E-04 16.03E-04 Total cg Gross Alpha C1 120.7
- 114.4 32.94 2.68E+02 H-3 Ci l
Tcble 2.3-3 MILLSTONE UNIT No. 3 Tsar 1986 LIQtTID RAD MASTE EFFLUENTS - SATCR - LWS snely Nuclides Released Unit October November December Cr-51 Ci 4.46E-03 2.22E-03 9.59E-04 7.64E-03 981-54 Ci 2.57E-03 2.96E-03 2.83E-03 8.36E-03 Tc-99M Ci 2.903E-05 2.99E-05 5.893E 05 00-38 C1 1.85E-02 1.36E-02 1.25E-02 4.46E-02 Co-60 Ci 1.17E-03 1.31E-03 1.25E-03 3.73E-03 1-131 C1 4.68E-04 5.62E-04 6.12E-04 1.642E-03, I-133 C1 9.65E-04 5.82E-OL 7.77E-04 2.324E-03 1-135 C1 3.05E-04 3.05E-04 Cs-134 Ci
~
ca-1LL ci En-65 eg Ee-59 c1 5.5 E-04 4.121-04 L 97E-04 1.159E-03.
8.54E-03 2.706E-02I Ka-24 ci 7.52E-03 1_.1 E-02_
l Zr-95 ci 1.25E-03 1.63E-03
- 1. 0_2E-03 3.90E-03 Nb-95 ci 1.93E-03 2.64E-03 1.74E-03 _
6.51E-03 Co-57 ci 1.15E-05 1.49E-05 2.64E-05 3.713I-02 3.047E-02.
1.073E-Ol Total ci 3.972E-02 To-51 c1 13.146E-03 51 sir-01
$r-89 gg 1,195E-04 fr..ntr-ns I.01E-05 3
ar-se ci
.52,52E-05
- ' ' ~
Total Activity ci 3.71F-02 4.82E-05_
Ka-133M 4.82E-05 Xe-133 ci 2.47E-02
_1.38E-03 1.67E-03 2.775E-02 mm 115 ci 1.5 E-03 1.23E-03 1.22E-03 3.95E-03 7.44E-05 Ie-135M c1 7.44E-05 l
Toem1 ci 2.A1E-02 2.61E-03
- 2. ROE-os
- 3. tar-02 c,.n.. Atow.
ci it.s7r nt II.36E-04 E-3
~
85.0 47.13 37.22 169.35 c1
Tcblo 2.3-4 MILLSTONE UNIT No. 3 Year 1986 LIQUID RAD WASTE EFF1.UENTS - BATCH CPF WASTE NEUTRA1,121NG SUMPS Quarterly Nuclides Balsased Unit July Aug Sept Tntal No activity Discharged this quarter Cr-51 Ci kn-54 Ci Tc-99H C1 Co-58 Ci Co-60 C1 1-131 Ci 1-133 Ci I-135 Ci Cs-134 C1 Cs-137 Ci Ho-99 ci Ce-141 ci co-14L cs 2n-65 ci Te-59 cf
~
I ci-ci C1 Ci l
Ci Fe-55 Ci Sr-89 C1 fr-90 Cf Total Activity Ci Xe-133 Ci le-135 Ci Xe-135M Ci ci CL B-3 C1
=
l l
t
l Table 2.3-4 N!!18 TONE UNIT No. 3 LIQUID EAD WASTE EFFLUENTS - SATCH CFF WASTE MEUTRALIETWC SUMP 5 heterly Wuclides seleased Unit October November Decer.ber e=* a No Activity Discharged this Quarter cr-51 C1 th-54 Ci _ _t Tc-99N Ci Co-38 Ci Co-60 C1 I-131 C1 I-133 Ci 1-135 C1 Cs-134 C1 Cs-137 C1 No-99 et Ce-141 c,
co-1LL Ci In-65 ci Te-59 et ci ci n
ci -
ci Fe-55 eg Sr-&9 et a, en ci Total Activity ci Xe-133 et sr.-iss ci za-13SM et et ci F3 m
Tchle 2.3-5 MILLSTONE UNIT No. 3 SUMMATION OF GASEOUS EFFLUENT RELEASES QUARTERLY TOIALS WITS July Aug Sept TEAR 1986 A. Fission and Activation Cases
- 1. TOTAL ACTIVITY Ci 4.27E-02 1.66E+01 6.47E-03 1.67E+01 RELEASED 1.59E-02 6.21E+00 2.49E-03 2.098E+00
- 2. AVERACE RELEASE RATE UCi/sec FOR THE PERIOD B. I dines
- 2. AVERAGE RELEASE RATE if***
5.41E- 05 1.42E- 05 2.26E- 06 7.07E-05 FOR THE PERIOD C. Perticulates
- 1. TOTAL PARTICULATE Ci r
ACTIVITY RELEASED 8.88E-05 2.07E-05 19.76E-07 1.09E-04
_2. AVERAGE RELEASE RATEUC'i/sec 3.31E- 05 5.55E-05 13.77E-07 8.86E-05 FOR THE PERIOD 8.23E-09 8.23E-09
- 3. TOTAL GROSS ALPHA CA 17.93E-07
$6.4E-07 ACTIVITY RELEASED
% Tritium
- 1. TOTAL ACTIVITY Ci RE1.EAS E 2.81 45.89 38.31 87.01
- 2. AVERAGE RELEASE RATE UCi/sec ' 1.05E+00 1.71E+01 1.48E+01 1.09E+01 _.
FOR THE PERIOD
i Tcble 2.3-5 MILLSTONE UNIT No. 3 SUMMATION OF CASEOUS EFFLUENT RELEASES QUARTERLY UNITS October November December TOTALS TEAR 1986 A. Fission and Activation Gases
- 1. TOTAL ACTIVITT Ci RELEASED 6.0BE+00 7.34E-02 1.34E-02 6.17E+00
- 2. AVERAGE RELEASE RATE 1/ set FOR TEE PERIOD 2.27E+00 2.83E-02 5.74E-03
.8118
- 3. Tadines
- 1. T 131 A M IU Ci 8.95E-06 5.21E-06 6.03E-06 2.019E-05
- 2. AVERAGE RELEASE RATE UCi/see 3.34E-06 2.012E-06 2.59E-06 2.65E-06 FOR THE PERIOD
(
C. Particulates l
- 1. TOTAL PARTICULATE Ci
<l.46E-06 15.63E-07 ACTIVITY RELEASED
- 2. AVERALI RELEASE RATE UCif,ec
<5.45E-07
$.17E-07 2
FOR THE PERIOD
~
- 3. TOTAL CROSS ALPMA Ci 9.25E-09 58.98E-09 l
ACTIVITY RELEASED D. Tritium _
- 1. TOTAL ACTIVITY C1 16.86 2.55 60.7 80.11 RELEASED 2.AVERACEAELEASERATE VCi/see 6.29
.984 26.05 11.1 FOR THE PERIOD Data for Sr-89,Sr-90, gross x is incomplete
Tcble 2.3-6 MILLSTONE UNIT No. 3 - CASEOUS EFFLUENT - CONTINUOUS NORMAL VENTILATION Yccr 1986 f helldes Released titt J0lv Aug Sept I
- 1. Fissten gases Et En-150 C1 ge-37 C1 M
C1 ge.sgs C1 Sc-13$
16.58 16.58 C1 Ie-133 C1 Er-09 C1 me-irr CI
. Ie-11Ss C1 1
Er-C >
Ci Es-133e Ci Ie-131s r
Cf Er-85 C1 Ar-17 16.58 I
ic yo C1 Tatal For kriod Cl 1.44E-04 3.niE-05 5.863E-06 1.879E-04 l
- 2. ladines todine-13)
C1 2.119r_nc i.o9or_ns R.nar nA
?.3Rsv-oc iI.
tedine-133
- 3. Particulates Ci 1.44E-05 Cr-51 C1 1.444E-05 h-54 Fe-59 C1 9.00E-05 Co-58 C1 7.287E-05 1.717F-ns Co-60 Cf Zn-65 cf I-131 C1 Cs-134 Ct Cs-137 Ci Ba-140
' C1 Ce-141 Cf Ce-144 C1 Ci SR-8#
C1 1 1.572E-0(
q q,_ng g 1.61E-Of 1.s?r nA Ct 17.86E-07 5 2.88E-07 5 3.22E-07 14.65F n7 Total C1 8.73E-05 2.07E-05
<9.66E-07 1.08E-04 SR-90 16.89E-07 Gross Alpha C1 57.86E-07 16.40E-07 16.40E-07 C1 2.66E+00 45.48 37.77 85.91 Tritium Ct 4
Table 2.3-6 M1118701tE UNIT alo. 3 - GASEOUS EFFLUENT - CONTINUOU$
NORMAL VENTI 1ATION Year 1986 l November l December
[F
[ Ibclfdes Released l Wait October
- 1. Finsten gases C1 Es.1M C1 eM C1 Er=80 41 Er-ess Ci 20-135 6.ogr ac C1 6.0EE400
_ Ee-133 C1 E: M C1 b1D C4
- wnen C1 E-JD
.Is.112m C4 Is.itim
.i
_ti Er t$
ti tt Ar~T1 6.08E+00
[
6.08E+00 -
f Total For period eq R. lediars f
todine-13)
Ci 8.95E-06 5.21E-06 6.03E-06 2.02E-os l
Cl 1.212E-05 1.nov ns A.cir na 2.cor n;
~
tedine.133
- 3. Particulates 1
Cf Cr-51 C1 E ta Fe-59 21 Co-58 C1 Co-60 C1
~
2n-65 e4
~
I-13:
et
~
Cs-134 C4 Co-137 C1 Sa-1_40 Ci Co-141 St Co-144 Ci Sr-89 et 11.2 E-os k at x n7 Sr-9L gt 12.4 E-07 5s.05 E-0A Total C1 11.AAK on
$5.63 E-07
~
Ci H-3 C1 16.78 2.43.'
60.3a 79 79 i
~ Cf Sa. ole-07 SA.0L r n7
~~
Cross Alpha L
Cf l
_ ~ _ _
Table 2.3-7 MILLSTONE UNIT No. 3 - GASEOUS EFFLUENT - CONTINUOUS EST BUILDING VENTILATION 1986 Yact r
ty
[ ess11 des Messed l Mt l 3ulv Aug
- Sept,
- 1. Fission gases Ci Es-113 C1 h s7 C1 Ep.88 C1 gr.33m Ci Es-235 6.47E-03 1.437E-02 7.qv_n, C1 Ie-133 Ci L-a Ci hirr Ci b1h Cf E7 33 C1 Xe-233m ti h 131m tt I
Ir-SS 21 1.437E-02 l
Ar-37 7.9E-03 6.47E-03 ti Total For Period
- 2. ledines 1 4.91E-08' 4.69E-08 1 3.36E-08
'.69E-nR C{
C1 1 6.25E-08,4.81E-08
< 1.7E-07 4.81E-08 l
todine-131 l
tedine-133
- 3. Particatates Ci Cr-51 C1 h-54 C1 Fe-59 Co-58 gg Co-60 Ci ei l
En-65 I-131 Ci Cf Cs-134 Cs -137 Cf Ba-140 Cf 4.35E-08 4.35E-08 C1 Ce-141 Ce-144 Ci ct H-3
- C1 1.18E-01 4.06E-01 6_17F-n1 1.nAr+no Cf Sr-89 C1 1 1.82E-08 11.4RE-ng 41.49E-08 il.59F-nR Cf 5 3.64E-09
- 54. 44E--09 54.48E-09 14.19E-nQ 4.35F-nA Sr-90 Cf
- 12. S I E-df 4.1sE-nR
_9.AQF no Totn1 17.28E-05 17.4F-no
,8.23E-09 R.71E-04 Cg Grnas Alpha i
l
Teble 2.3-7 MILLSfollE 1FNIT No. 3 - GA5EOUS EFF1 RENT - 0057INDOUS Tear 1986 l
l
(_ helfdes teleased jWatt
_0ctober }
November December, $[F l
- 1. Ffssten gases i
an.iu C1 me.87 Ct 81 D=88 Ct E> ess Ee.139 C1 is-133 CI 7.34E-02 1.34E-02
_8.68E-02 E>-Se Ct n in C1
- In th C1 D Sh C1 In-isk et In i h i
et SD-SS f(
l
- Ar*77 et-7.34r-02 1.16r-02 a.sar-02 l
fetal For parted ti
- 3. ledines ledine-13)
Ci 5.2.09E-07_'
11.53I-0?
11.74E-07 15.361 07 C1 13.55E-07 52.48E-07 12.37E-07
37 4.13E-02 ti Titti For period
- 3. Iodines Ci Wine-131 Cl tedine-133
- 3. Particu1stes C1 l
Cr-51 C1 m-s4 ti Fe-59 Co-58 C1 Co-60 Ci cf En-65 I-131 C1 C1 Cs-134 l
Cs-137_
Ci f
Ba-140 C1
~
C1 Ce-141 Ce-144 Ci ct I
C1 C1 TOTAL Ci Ci 1 or m -
2.9E-03 C1 H-3 Ci l
Table 2.3-8 MII1STOWE IINIT No. 3 - BATCH Year 1986 k I' M M 88 W Whit October l November December l%,1T1
- 1. Fissten gases No Contairnmens Drawdowns this Quarter
_st i
- t!
5_7 St St R>es R>0sm St as-13s Ci Be-123 C1 a,.se et n.-in et I
. so na-C1 l
t>s3a tt l
Es-132n a(
En-1Ma i
et I
b-85 et Ar M 21 Total For Berted 24
- 3. ledines l
tedine-131 et I
todine.133 Ci
(
- 3. Partissistes cr-51 Ci h t1 et Fa-39 et Co-58 gg Co-60 31 En-63 c4 1-131 et Co-234 C1 l
c.-In 84 l
Se-160 Ci Ce-141 ti co-144 C1 et St TOTA 1 et tt et
_W-3 C1 -
Et
l I
Tcble 2.3-9 MII.LSTONE UNIT No. 3 - BATCH CONTAINMENT PURGES i
Yxt 1986 th
[ esslides teleased l Unit y*ulv lAug Sept I- ~
No containment Purges for Aug and Sept
- 1. Fission gases
_C1 Es-113 Ci ze.s?
C1 Ep.38 C1 m
1.13E-02 Cf 1.13E-02.
3e-13S 3.14t.-uz 3.14t.-u4 C1 1
Ee-133 Ci LM C1 h1Tr Ci h 139s i
C1 Er s>
i ti i
Re-13h ti Ie-131s l
ti Er-85 ef 4.27E-02 Ar-37 4.27E-02
- C1 Trtal For Period l 8.86E-07
- 2. Iodines I
Ci 8.86v_n, 3.25E-06 i
tedine-13)
Ci 3.25E-06 tedine-133
- 3. Particatstes l
C1 1.49E-06 Cr-51 C1 1.49E-06 m.st c1 Fe-59 Co-58 C1
~
Co-60 C1 cf 2n-65 I-131 C1 C1 Cs-134
~
Cs-137 Ci Cf Ba-140
~
C1 Ce-1*1 Co-144 Ci 1
ct Ci 1.49ELO6 Cf 1 Aar,
TOTAL C1 I
, C1 8.13E-03 l
8.13E-03 Cg g-3 C1
Table 2.3-9 MILL 8TNG UNIT No. 3 - BATCH CONTA130GNT FURCES Year 1986
[ h 1fdes telected l Waft lOEtober l
November December aW
~
No Containaant Purges this Quarter 9, pg,,,,,,,,,,
I Sm
_Cf m es.
C1 C1 sp.es se ti 1
as.4ps C_t i
is.111 C1 l
LM Ci Ea.117 C1
. him St i
N3s Ci bish 24 him i
et tr-SS et Ar-21 et f
Total For period 24
- f. Iedtnes todtat-131 Cl l
tedine-133 C1 l
- 3. portfestates Cl Cr-51 E-sa
_C1 Fe-59 24 Co-5:
gg Co.60 Ci In-65 es I-131 Ct Co-134 C4 Co-137 C(
Ba-140 C1 Co-141 Cf Co-144 C1 M
Cf 1
TOTAL C4 C1 1
C_
a J
l 5-3 Cf Ce m
-,__.--_,,...-,.----,,-,,,,n--
i Tchle 2.3-10 MILLSTONE UNIT No. 3 - CONTINUOUS TURBINE GIAND SEALING SYSTEM EXHAUST Yccr _1986
[ helides teleased l Unit fulv Aug Sept i
ta No Activity Discharged
- 1. Fission gases C1 Io.1r C1 te-37 J
C1 Ep.48 Ci gr.33.
C1 Ee-135 C1 3 133 C1 L-E ti I. In C1
. Ie-139s Ci Er-82 ti Ze-133e 5
C1 Ie-131m Cf Er-SS Cf Ar*31 Cf
,Ttt.a1 For k riod
- 2. ledines Ci (edine-131 Cl todine-133
- 3. Particulates i
Cf Cr-51 C1 h.s4 C'i Fe-59 Co-58 gt Co-60 Ci
)
c4 2n-65
~
I-131 Ci C1 Cs-134 Cs-137 Ci C1 Ba-140 C1 Ce-141 C1 Ce-144 ct C1 C1 TOTAL C1 Ci C1 C1
Table 2.3-10 MILI.8 TONE UNIT No. 3 - CollTINUOU$
TURBINE GLAND SCALING SYSTEM IIMAUST Year 1986
[ helfdes teleased l Unit Ohtober l November _
Decer.ber
[#
No Activity Discharged this Quarter
~
- 1. Ffssim gases ze-is;
_C1 41 E _v
=
gt w==
U Ci so-135 Ci Be-133 Ci E-M C1 m in C1
. Xe-l h Ci EP-83s Cf In ins 21 Ia-131s 6
tt Er-t$
Cf Ar-37 21 Tot,a3 For 7.r'.ed C1 l
- t. ledines 1edino.131 C1 tedine 133 Ci
Co-134 C1 Cs-137 Cf Sa-140 Cf Co-141 C1 Co-164 Ci cf Ct
~
C1
- -,C1 b
C1 21
. t.
t
1 Tcble 2.3-11 MILLSTONE UNIT No. 3 - BATCH MAIN CONDENSER MECHANICAI. VACUUM PUMP EXHAUST Y ar 1986
[ Asc11 des Released Unit l July Aug Sept k r krly Total
- 1. Fission gases No Acitvity Discharged Ie-in C1 Er.37 Ci Ci Ep-es Er.sse C1 3.-135 Ci Ee-133 C1 Ira Cf Ie-1M C1
. Ie-itse Ci 1
37-33 Ci Ze-1Me C1 Ci Ie-132m 5
Er-85 tt Ar-37 tt Tttal For period C1
- 2. ledines l
4edine-131 C1
% dine-133 C1
1 i
~
Tcble 2.3-11 MII.LSIONE UNIT No. 3 - BATCR IN CONDINSH MECEANICAL VACUUM FUMP EIMAUST Year 1986
[ Asetides Released l Onit l 0ctober l November l December N No Activity Discharged this Quarter 3 12
.Cf w _
Ci E> as C1 Ep 99m Ci so-135 C1 ie.in Ci Er=89 Ci hin C1
. so-im Ci Er-Sas ci binn et
.i et se-ima i
S$
et An 37 24 Tott3 Per R ed et
- 9. Iodines tedine-131 C1 tedine.133 Cl
- 3. Partissistes Ci Cr-51 un.s4 Ci Fe-59 et Co-SP gg Co_-60 Ci l-Ea-65
__ e4 I-131 c1 C1 Ca-134 Co-137 Cf Sa-140 C1 Co-141 Ci Co-144 C1 ci C1 TOTA 1 81 C1 C4 C1 l
C1 l
i
3.0 Radioactive Solid Waste Sumaries of solid waste shipments for each unit are given in the attached tables.
Solidification Agent (s) - When solidification was required, cement was used.
Types and typical volumes of containers -
55 gallon steel drum, DOT 17-H 83 gallon steel overpack, 00T 17-H 87 ft3 LSA steel box 202 ft3 polyethylene High Integrity Container I
Page 1 of 6 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT -
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS MILLSTONE UNIT 1 JULY 1, 1986 - DECEMBER 31, 1986 6-Month Est. Total Type of Waste Unit Period Error, %.
6.85Ef 3
Spent Resins, Filter Sludges, M
I Evaporator Bottoms Etc.
Ci 2.57E 2.5 E 3 3
2 Dry Compressable Waste, M
2.90E
)
Contaminated Equipment, Etc.
Ci 1.22E 2.5E 3 3
Irradiated Components, M
)
Control Rods, Etc.
Ci NONE N/A 3
M Other(Describe)
Ci NONE N/A 1
Estimate of Major Nuclide Composition (By Type of Waste)
(%)
o
)
3 1.66E-2 H
l4 2.33E-1 I
C 0
2.78E 51 Cr l
54 1.78E l
Mn 0
55 2.61E i
Fe l
58 1.01E Co l
60 5.43E l
Co 63 4.05E~l I
Ni 0
65 1.05E Zn 90 2.02E~l I
Sr l
Tc" 7 02E'"
Page 2 of 6 l
I3I 4.22E-2 I
I l34 7.17E-1 l
Cs 0
l37 9.45E Cs l40 8.50E-2 Ba l40 9E-2 La l4l 1.23E-2 l
Ce 0
54 1.9 E p)
Mn l
55 3.37E l
Fe 0
S8 3.43E I
Co l
60 1.85E I
Co 0
63 9.50E I
Ni 90 3.13E-2 l
Sr 99 2.34E-4 l
Tc 0
l34 7.05E I
Cs l
l37 2.59E Cs 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination 26 Truck (Sole Use Vehicle)
Barnwell, S.C.
).
Irradiated Component Shipments None t
/
s e
e r
.._-__._-y
-,.-m,
-y w
Page 3 of 6 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT -
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS MILLSTONE UNIT 2 JULY 1, 1986 - DECEMBER 31, 1986 6-Month Est. Total Type of Waste Unit Period Error, %
2.82Ef 3
Spent Resins, Filter Sludges, M
D Evaporator Bottoms, Etc.
Ci 5.67E 2.5E,1 3
Dry Compressable Waste, M
Unit #2 Type (B) Waste is D
Contaminated Equipment, Etc.
Ci included in Unit #1 Report 3
Irradiated Components, M
,)
Control Rods. Etc.
Ci NONE N/A i
f M
- )
Other(Describe)
Ci NONE N/A i.
Estimate of Major Nuclide Composition (By Type of Waste)
(%)
- )
3 3.41E-2 9
I4 3.87E'I C
0 51 1.17E Cr 0
54 1.88E Mn I
55 1.93E Fe I
b8 1.52E Co I
60 4.84E Co 0
63 2.64E Nf 90 2.53E'E Sr Nb'l 1.01E-2 II 8.11E-2 Tc 0
l03 2.13E Ru i
-m-
Page 4 of 6 1
0 110M 4.30E Ag 0
l34 1.02E Cs 0
l37 3.36E Cs 238 2.06E-5 Pu 239 1.53E-5 Pu 241 2.03E-2 Pu 241 4.07E-3 Am 244 1.96E-5 Cm Solid Waste Disposition Number of Shipments Mode of Transportation Destination 6
Truck (Sole Use Vehicle)
Barnwell, S.C.
1 Truck (Sole Use Vehicle)
Richland, Washington b
Irradiated Component Shipments None
- 6
Page 5 of 6 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT -
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS MILLSTONE UNIT 3 JULY 1, 1986 - DECEMBER 31, 1986 6-Month Est. Total Type of Waste Unit Period Error, %.
3 0
Spent Resins, Filter Sludges, M
5.47E }
i)
Evaporator Bottoms, Etc.
Ci 5.17E' 2.5 E.
3 Dry Compressable Waste M
>)
Contaminated Equipment, Etc.
Ci NONE N/A 3
frradiated Components, M
- )
Control Rods, Etc.
Ci NONE N/A 3
M d)
Other (Describe)
Ci NONE N/A 2.
Estimate of Major Nuclide Composition (By Type of Waste)
(%)
- )
3 9.00E-I H
-3 l4 C
2.30E 0
51 4.85E Cr 0
54 5.53E Mn l
55 Fe 1.59E 0
59 Fe 2.46E l
58 5.91E C0 0
60 7.56F Co 0
63 3.53E Ni 99 6.54E-2 Tc
-2 129 5.83E 1
Page 6 of 6 Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1
Truck (Sole Use Vehicle)
Barnwell, S.C.
Irradiated Component Shipments None l
l I
/
l l
4.0 SUPPLEMENTAL INFORMATION A.
MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 4.1 Gaseous Releases a.
Unit 1 Stack - Gaseous Releases (1) Fission and Activiation Gases Stack monitors continuously record the effluent activity i
and flow rate.
During periods when the augmented off-gas system is not operable, the radiation monitor reading is related to uCi by off-gas sampling at the steam jet aif ejectors and subsequent isotopic analysis.
The isotopic activity at the SJAE is mathematically decayed to ektablish the activity in the stack using the known holdup time.
During periods of augmented off-gas system operation, samples are taken directly from the stack with a subsequent isotopic analysis.
In both cases, the calculated activity in the stack is then correlated to the
~
monitor reading.
The isotopic concentrations at the f
release point are multiplied by the total stack flow to l
l obtain total uCi release for each isotope.
1 I
l (2)
Iodines and Particulates Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively.
The filters are then analyzed for isotopic content using a gama spectrometer; particulate filters are also analyzed for strontium.
Isotopic concentrations are multiplied by the release flow rate to determine the total amount of
~
J activity released.
l l'
b.
Unit 2 Vent Total effluent volume from the Unit 2 Vent per month is multiplied by the isotopic concentrations as measured by gama spectrometer Ge(L1) analysis of grab samples of gases, iodine and particulates to obtain total uCi released from the Vent.
c.
Unit 2 Containment Purges Grab samples are taken for gaseous, particulate, and iodine.
These are analyzed on Ge(Li) gama spectrometer and concentrations computed.
Computed concentrations are then multiplied by the purge volume for total uCi released.
Tritium collection is accomplished by the gas washing bottle method.
The sample is counted on a liquid scintillation counter.
Concentration is computed using worst possible case, 100% humidity.
Concentration is multiplied by volume purged to give total uCi released.
l d.
Unit 2 Steam Generator Blowdown Tank Vent A decontamination factor (DF) across the steam generator blowdown tank vent has been determined for iodines by comparison of the results of gamma spectrometry, Ge(Li),
analysis of steam generator blowdown water and grab samples of condensed steam exiting the blowdown tank vent.
This DF wa,s then applied to the total iodine releases via the steam generator blowdown water to determine the iodine releases out of the blowdown tank vent.
An additional factor of 0.33 was I
utilized to account for the fraction of blowdown volume 69rm in the blowdown 9aIk.
s e.
Unit 3 Vent and ESF Building Vent The Unit 3 Venti 11ation Vent collects gas streams from the Auxiliary, Fuel, Waste Disposal, and Service Building exhausts, containment purge and gaseous waste process vent.
The Unit 3 Vent is located on the roof of the turbine building and
. discharges 133 feet above grade.
The Unit 3 ESF Building Vent collects gas streams from the Engineered Safety Features Building Venti 11ation System.
This vent is located on tne south wall and discharges 23 feet above grade.
Total Effluent Volume per month is multiplied by isotopic concentrations from the analysis of grab samples to obtain the total activity released.
These grab samples are obtained monthly for fission gas and tritium, weekly filters for iodines and particulates, monthly composites of particulate filters for gross alpha and Strontium.
f.
Unit 3 Containment D awdown and Purge Unit 3 Containment is drawn down and purged intermittently.
The drawdown is accomplished by using the containment vacuum steam jet ejector and releases through an unmonitored vent on the roof of the Auxiliary Building.
The containment vacuum pump discharge, which maintains sub-atmospheric pressure following the initial drawdown, is released through the Unit 1 Stack.
The purge is the process of discharging air from containment to maintain temperature,
- humidity, pressure, concentration, etc.,
where air is replaced.
Purges are filtered and normally released through the Unit 3 Vent but may use the Unit 1 Stack.
Purges and Drawdowns are intermittent
I-and are therefore considered batch releases.
Calculated volume discharged is multiplied by isotopic concentrations from the analysis of grab samples to obtain activity released.
Unit 3 Turbine Gland Sealing System Exhaust g.
The turbine gland sealing system prevents air leakage into the 4
A mixtare turbine and valve stems and collects steam leakage.
of air and steam drawn from the turbine shaft packing is condensed and the noncondensable gases _ are vented to the atmosphere at a point above the condensate polishing building.
Noble Gas' This vent is at an elevation of 48 feet above grade.
Activity released is calculated using the air ejector monitor activity concentration and the percentage of steam to the gland sealing condenser.
Iodine and particulate activity is calculated using the steam generator blowdown activity fraction.
(See concentration and appropriate-carry.over Appendix H, 00CM).
Unit 3 Main Condensor Mechanical Vacuum Pump Exhaust h.
The Main Condensor Evacuation System draws the initial vacuum i
in the condensor during startup and maintains vacuum during The Main Condensor mechanical vacuum pumps exhaust startup:
the condensate polishir.g building roof.
through the vent on Steam Jet Air Ejectors maintains condensor vacuum during normal operation.
Air and noncondensable gases removed from the condensor by the steam jet air ejectors are discharged to the, Unit 1 Stack.
i ew= = - -... en
-, =
-4
.,.v.-e,.<-
n-
,-r-my-w-
--y
. - --- - - -, ~, -
7
_e,-y e
---,r
i l
c I
Noble Gas Activity released during startup by the Main Condensor Vacuum Pumps is obtained by multiplying the condensor volume by a grab sample of the air ejector decay corrected for time of shutdown.
Iodine and particulate activity is obtained and from a grab sample of the mechanical vacuum pump exhaust volume discharged.
(See Appendix H. 00CM).
4.2 Liquid Effluents a.
Liquid Tanks There are numerous tanks which are used to discharge liquids conta[ningradioactivitytotheenvirons;theyare:
Unit 1 - Decontamination Solution Tank Unit 1 - Floor Drain Sample Tanks (2)
Unit 1 - Waste Sample Tanks (2)
Unit 2 - Clean Waste Monitor Tanks (2)
Unit 2 - Aerated Waste Monitor Tank Unit 3 - High Level Waste Test Tanks (2)
Unit 3 - Low Level Waste Tanks (2)
Prior to release, a tank is recirculated for two equivalent i
tank volumes, a sample is drawn and analyzed on the Ge(L1)
An gama spectrometer for indivdual radionuclide composition.
aliquot of the sample is analyzed for tritium.
Isotopic concentrations are multiplied by the volume released to obtain the total activity released.
--v-,
.w.
,e
A proportional aliquot of each discharge is retained for composite analysis for strontium and gross alpha.
b.
Unit 2 and Unit 3 Steam Generator Blowdown Grab samples are taken of steam generator blowdown water, and are analyzed by gansna spectrometry, Ge(Li).
Total volume of blowdown is multiplied by the isotopic concentrations to determine the total activity released via blowdown.
The calculated activity released out of the blowdown tank vent is accounted for pending the point of blowdown sampling.
Tritium-is determined through liquid scintillation counting and strontiums are analyzed by radiochemical separations and appropriate counting techniques.
l l
4.3 Estimates of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:
(1) Sampling and Data Collection - 10% accounts for variation in personnel obtaining required data.
(2) Calibration - 5% instrument calibration to NBS standards.
10% maximum error due to counting l
(3) Counting of Samples statistics.
(4) Flow and Level Measurements - 105 maximum errors on volumes released.
j 4.4 BATCH RELEASES l
Liould i
Unit 1 Unit 2 Unit 3 i
a.
Number of Batches:
92 276 602 b.
Total Time: (Min) 14,508 51,880 44,582 c.
Maximum Time: (Min) 235 1,549 230 d.
Average Time: (Min) 158 188 74 e.
Minimum Time: (Min) 8 1
1 Average Stream Flow - Not Applicable - Ocean Site Gaseous
. Unit 1 Unit 2 Unit 2 Unit 3 Unit 3
' Purge Purge WGDT Purge Drawdown l
a.
Number of Batches:
0 1
12 1
1 b.
Total Time: (Min) 240 4,824 270 259 c.
Maximum Time: (Min) 240 508 270 259 d.
Average Time: (Min) 240 402 270 259 o.
Minimum Time: (Min) 240 217 270 259 4.5 ABNORMAL RELEASES l
None
5.0 CHANGES TO THE REMM/00CM/PCP There were no changes to the REMM/0DCM/PCP during the period July-December 1986.
4
!6.0 EFFLUENT MONITOR INOPERABILITY l
l During the period covered by this report, the following monitors were inoperable for greater then 30 days:
1.
Unit 3 Steam Generator Blowdown Monitor This monitor has not been placed in initial service yet.
Until this monitor is in service, Steam Generator Slowdown is being recovered without discharge to the environment.
2.
Unit 2 Ventilation Stack Flow Recorder This recorder was out of service from 3/17/86 to 6/11/86, due to a failed diaphragm.
Replacement parts were not received in a timely During the period of inoperability, required action statements manner.
f were fulfilled.
This inoperability was not reported in the Jan.
f June report due to an administrative oversight.
Procedural changes have been made to ensure such reports are made in the future.
l
{
APENDIX A UPDATED TABLES FOR THE SEMIANNUAL EFFLUENT RELEASE REPORT - JANUARY-JUNE 1986 Saaple analyses delays from our contracted lab facilities due to the excess sa ple load from the Chernobyl incident caused the results of Fe-55, Sr-89, Sr-90, and gross f to be incomplete for the second quarter 1986.
Attached are the tables with the required data to update your copy of the Semiannual Effluent Release Report - January-June 1986.
I e
b e -- - - -
,,-,e
.,-,,..-m-
,+-,-----,w,
-,-vn--,----,mvrn, s-,.,
7-g-,-..,,.----~~
---w--w
Table 2.1-1 MILLSTONE NUCLEAR POWER STATION UNIT #1 LIQUID EFFLUENTS - SUMATION OF ALL RELEASES
' QUARTERLY UNITS APRIL MAY JUNE TOTALS
-TEAR 1986 A. Fission and Activation Products
- 1. TOTAL ACTIVITT 3.49E-04 9.89E-04 5.10E-01 5.11E-01 RELEASED UC1/al 4.94E-12 1.56E-Il 7 13E-09 2.48E-09 i
ACT UR NG PERIOD lB. Tritium
- 1. TOTAL ACTIVITT C1 1.50E-01 6.45E-01 9.80E-01 1.78E+00 RELEASED
- ^
UCi/a1 2.12E-09 1.02E-08 1.37E-08 8.64E-09 AC UR N PERIOD C. Dissolved and Entrained dases
- 1. TOTAL ACTIVITY Ci 2.39F-04 1.01E-03 1.77E-04 1.43E-03 RELEASED l
- 2. AVERAGE DILUTED UCi/mi 3.38E-12 1.60E-11 2.48E-12 6.94E-12 ACTIVITY DURING PERIOD D. Grcss Alpha
- 1. TOTAL ACTIVITT i
RELEASED 11.00E-05 12.97E-05 13.82E-05 E. Volume OF WASTE LITERS 2.00E+05 3.96E+05 4.78E+05 1.07EM6 LITERS 3.20E+09 2.95E+09 2.58E+09 8.73E+09 D
E
- 3. VOLUME OF DILUTION LITERS 7.07E+10 6.33E+10 7.15E+10 2.06E+11 DURING TIME PERIOD
Table 2.1-2 MILLSTONE NUCLEAR POWER STATION - UNIT #1 LIQUID EFFLUENTS - BATCH NODE
. Year iens Nuclides Released Unit APRIL MAY JUNE Cr-51 Ci 6.40E-05 1.45E-05 7.85E-05 Ma-54 Ci 5.08E-06 1.38E-02 1.38E-02 Te-99M C1 Co-58 Ci 2.40E-06 1.11E-03 1.11E-03 Co-60 Ci 2.05E-04 2.02E-04 2.05E-02 2.09E-02 I-131 C1 1-133 Ci i
1-135 Ci Cs-134 C1 2.69E-02 2.69E-02 f
Cs-137 C1 1.38E-04 1.74E-04 4.45E-01 4.45E-01 f
Mo-99 ci l
Co-101 ci ca.1&&
ci Zn-65 ci Fe-59 ci 2.09E-05 2.09E-05 Ru-106 c1 1.23E-03 1.23E-03 Na-24 Ci Ci Ci CL '
Fe-55 ci 12.00E-04 11.60E-04 1.20E-03 1.20E-03 Sr-89 ci 19.00E-06 5.15E-04 4.34E-04 9.49E-04 Er-en ci 5.50E-06 5.94E-06 1.82E-04 1.93E-04 3.49E-04 9.89E-04 5.10E-01 5.11E-01 Total Activity ci Ia-133 ci 7.89E-04 1.77E-04 9.66T-04 Re-1M ci 2.39E-04 2.24E-04 4.(3i.-04 Xe-135M eg C1 C1 Ci 1
.._ ~ _. m _ _.. _..,,, -,.,,
.._._~_,.,,,...m_
l Table 2.1-3 MILLSTONE NUCLEAR FOWER STATION UNIT #1 i
l GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l
QUARTERLT UNITS APRIL MAY JUNE TOTALS YEAR 10A6 l
A. Ficsion and Activation Gases
- 1. m ACTIV1W C1 1.44E+00 1.14E+02 5.44E+02 6.59E+02 j
I l
- 3. Indines
- 1. TOTAL I-131 ACTIVITY Ci RELEASE 5.12E-05 6.06E-04 1.44E-03 2.03E-03 A
A8 UCi/sec 2.13E-05 2.01E-04 5.95E-04 2.59E-04 g p i
C. Particulates
- 1. TOTAI. M TIC M TL Ci 4.99E-04 1.23E-03 3.91E-04 2.12E-03 ACTIVITY RELEASD 2.
RA E RAM UCi/sec 2.08E-04 4.09E-04 1.62E-04 2.71E-04
- 3. 701AL GROSS ALFRA C1 4.35E-07 7.71E-06 4.72E-07 8.62E-06 ACTIVITY RELEASD D. Tritium
- 1. TOTAL ACTIVITY Ci 5.06E+00 4.79E+00 3.88E+00 1.37E+01 l
RELEASD
- 2. AVERACE RELEASE RA M UC1/sec 2.11E+00 1.59E+00 1.60E+00 1.75E+00 FOR THE PERIOD r-,-.-----.-%
,%..,-,-e,--
-m - ---
eeo+w
-w gw-
Table 2.1-4 MILLSTollE NUCLEAR 70WER STATION - UNIT fl GASEOUS EFFLUENTS - ELEVATED RELEASE - CONTINDOUS MODE l [ = *smi-sw I wt Iam Im l
,U,E Igr j l
L Finsten gases
.C1 5.68E+01 3.13E+02 3.70E+02 Be-1M l
C1 9.77E+00 4.84E+01 5.82E+01 i
E "7 CI 7.58E+00 6.22E+00 1.38E+01 M
C1 2.25E+00 1.63E+01 1.86E+01 f
Er S$a C1 1.44E+00-1.93E+01 8.10E+01 1.02E+02 j
38-139 Cf 2.51E+00 3.98E+00 6.49E+00 4
Ee-133 C1 Er M CI Re-1TF C1 1.4 Aran 1 7 A trAn t n 07ran1 j
f
- In-l h C1
)
gr-8h C4 Ee-133m ti s -
Ee-Isla
~
tt Er-SS 1.Idr+00 1 i nemn Ar-41 ff 1.44E+00 - 1.14E+02 5.44.E+02 6.59E+02 l
tt Total For Period
- 1. ledines l 5.37E-04 1.44E-03 2.03E-03 Cl 5.12E-05 1.07E-02 f
4edine-131 C1 3.56E-04 2.00E-03 8.32E-03 j
tedine-133 f
S. Particulates
<C1 2.26E-04 4.56E-04 1.52E-04 8.34E-04 I
Cr-51 4.00E-05 C1 4.n0E,9) h s4 6.04E-06 l
tt A.nar-06 Fe-59 5.88E-05 Co-58 C1 2.12E-06 5.67E-05 i
I Co-60 C1 1.37E-04 4.61E-04 7.53E-05 6.73E-04.
2n-65 cf 6.92E-05
,6.92E-05 _
I-131 C1 Cs-134 C1 i.64E-05 1.51E-04 Co-137 C1 u or ns
- 7. A*tr ns 2
i i
Be-140 C1 I
Ce-141 C1 Ce-144 C1 i
La-140 gg
.4.27E-05 3.21E-05 8.65E-05 1.61E-04 ci i
1 Ci 1.26E-04 _
l C4 4.62E-05 3.87E-05 4.07E-05_
f Cl 7.69E-07 1.21E-06
- 7.37E-08 2.05E-06 SF-89 i
Er-to 2.12E-031 C1 Ci 4...t 04 t 23E-03 2.9iE-04 m At 1
j L. _-
i Tabla 2.2-1 MILLSTONE NUCLEAR POWER STATION UNIT #2 LIQUID EFFLUENT - SU M ATION OF ALL RELEASES y,37,
' QUARTERLY APRIL MAY JUNE TOTALS YEAR 1986 A. Fission and Activation Products l1. TOTAL ACTIVITY Ci RELEASED 1.37E-01 1.47E-01 7.51E-02 3.59E-01 UC1/a1 1.47E-09 I.60E-09 8.IIE-10 I.29E-09 A
UR NG PERIOD o
B. Tritius
- 1. TOTAL ACTIVITY Am 1.24E+OL 4.11E+01 8.04E+01 1.34E+02
- 2. AVERAGE DILUTED 1
UCi/al I.33E-07 4.49E-07 8.68E-07 4.82E-07 ACTIVITY DURING PERIOD C. Dissolved and Entrained Cases
- 1. TOTAL ACTIVITY Ci RELEASED 8.62E-03 1.63E-02 8.30E-01 8.55E-01 ia 9.2 E-11 1.78E-10 8.96E-09 3.08E-09 PERIOD D. Crc 0s Alpha
- 1. TOTAL ACTIVITY C1 RELEASED 18.25E-04 12.15E-03 11.25E-03 12.15E-03 E. Valune
- 1. VOLUME OF WASTE 1.84E+07 3.74E+07 2.24E+07 7.82E+07
- 2. VOLUME OF DILUTION DURING RELEASES TERS 1.85E+10 1.22E+10 1.36E+10 4.43E+10 3 Y LITERS 9.33E+10 9.16E+10 9.26E+10 2.78E+11 DR C 10D l
Table 2.2-2 MILLSTONE NUCLEAR POWER STATION UNIT #2 LIQUID EFFLUENTS - CONTINUOUS - S/G Tsar 1986
- *jl7 f
Nuclides Released Unit APRIL MAY JUNE l
Cr-51 Ci l
Mn-54 Ci i
Tc-99M Ci 1.49E-03 I
co-58 Ci 1.49E-03 1.33E-02 1.74E-02 Co-60 Ci 4.12E-03 1.68E-02 T 131 Ci 1.68E-02 1.30E-02 1-133 Ci 1.30E-02 1-135 C1 6.33E-03 Co-134 Ci 6.33E-03 Co-137 Ci 3.17E-04 2.15E-02 2.32E-03 2.41E-02 No-99 c1 Ce-141 ci ci ce-144 Zn-65 c1 Te-59 eg 7.64E-04 7.64E-04 Na-24 ci i
Ci Ci Ci Ci Te-55 Ci
<1.65E-02 1 3.58-02 <2.OBE-02 1 1.5R n9 15.78E-04 1 1.61E-021 6.24E-04 1 1.61E-03 Sr-89 Ci 1 64E-04 1 3.5BE-041 1.66E-04 1 3.58E-04 l
2 C1 Sr-90 4.44E-03 5.99E-02 1.56E-02 8.00E-02 C1 Total Activity Xe-133 cg 2.40E-04 2.40E-04 re-115 Ci 7.01E-01 7.01E-01 I
Kr-85 C1 Ci R-3 Ci 8.77E-01 1.31E+00 2.73E-01 2.46E+00 Cross Alpha Cf S.25E-04 I? 1w n1 11.25E-03 1 2.15E-03 i
.______.__._-..___,_____._,__.___._,___._______9..___
Table 2.2-3 MILLSTONE NUCLEAR POWER STATION UNIT #2 Yra-1986 LIOUID ETT.UENTS - BAT N - AWT/ CWT /Tr.11 Nuclides Released Unit APRIL MAY JUNE
($I Cr-51 C1 1.23E-04 1.23E-04 Mn-54 C1 1.18E-03 1.03E-03 8.61E-04 3.07E-03 5.95E-05 Tc-99M Ci 5.95E-05 Co-58 Ci 4.60E-03 5.54E-03 3.53E-03 6.49E-02 Co-60 Ci 2.86E-02 3.16E-02 2.87E-02 8.89E-02 1-131 C1 1.45E-03 2.44E-03 5.12E-05 3.94E-03 1-133 Ci 2.44E-03 8.60E-04 5.04E-05 3.35E-03 5.30E-05 I-135 Ci 5.30E-05 Cs-134 C1 1.89E-02 2.40E-02 7.64E-03 5.05E-02 Cs-137 Ci 5.35E-02 6.75E-02 2.28E-02 1.44E-01 2.71E-05 2.71E-05 Sb-124 ci Ce-141 c,
Ce-144 Ci 2n-65 eg Fe-59 ci 5.53E-05 1.20E-04 1.75E-04 Ag-110m ei l
Nb-97 Ci 9.33E-05 2.34E-04 4.75E-04 8.02E-04 Na-24 C1 1.98E-04 1.98E-04 8.50E-05 4.81E-04 Sb-125 C1 1.08E-03 1.19E-03 3.21E-04 2.59E-03 i.
l Sr-92 C1 1.24E-05 8.60E-05 1.21E-04 2.19E-04 1.93E-02 1.22E-02 1.02E-02 4.17E-02 Fe-55 eg 1.27E-04 1 6.52E-05 14.86E-05 1.27E-04 St-89 C1 Sr-90 Ci n 11 nt
- 3.42E-05l19.72E-06 1.15E-04 1.37E-01 1.47E-01 7.51E-02
- 3. f Y-0 l Total Activity Ci Gross A C1 11.16E-04 1 1.47E-04 11.46E-04 11.47-04 Xe-133 Ci 7.24E-03 6.88E-03 2.26E-02 3.67E-02 l
Ie-135 Cf 1.14E-03 1.66E-03 8.14E-04 3.61E-03 7.71E-03 7.71E-03 f
Kr-85 C1 H-3 C1 1.15E+01 3.98E+01 8.01E+01 1.31E+02 Ci Cf
Table 2.2-4 MILLSTONE NUCLEAR POWER STATION UNIT #2 GASEOUS EFFLUENTS - 1;UMMATION OF ALL RELEASES QUARTERLY UNITS 70TA'.S April May June TEAR 1986 A. Pission and Activation Cases
- 1. TOTAL ACTIVITY Ci RELEASD 8.33E+00 2.94E+00 1.01E+00 12.3E+00
- 2. AVERAGE RELEASE RATE UCi/sec POR THE PERIOD, 3.32E+00 1.21E+00 0.33E+00
- 1. 5 5E +00
- 3. Iodines
- 2. AVERAGE RELEASE RATE UCi/sec FOR THE PERIOD 3.86E-05 7.52E-05 6.42E-05 5.95E-05 C. Particulates
- 1. TOTAL PARTICULATE Ci ACTIVITY RELEASE 9.39E +00 3.65E +00
- 0. 91E +00 14.0E +00
=-
- 2. AVERACE RELEASE RATE UCi/sec TOR THE PERIOD 3.74E-06 1.51E-06 3.01E-07 1.76E-06
- 3. TOTAL GROSS ALPHA C1
~
ACTIVITY RELEASE
$ 1.33E-07 1 4.05E-08 1 5.50E-07 s
i D. Tritium
- 1. TOTAL ACTIVITY Ci RELEASD 2.67E +00 3.05E +00 9.89E +00
- 15. 6E +00
- 2. AVERACE RELEASE RATE UC1/sec FOR THE PERIOD 1.06E+00 1.26E+00 3.27E400 1.96E+00
Table 2.2-5 MILLSTONE NUCLEAR POWER STATION - ITNIT #2 l
CASEOUS EFFLUENTS mixed
- CONTINUOUS MODE Taar i e. A n
( 8belfdes Released l Unit l
- April l
May l
June fta
~
- 1. Fission gases Ie-13 C1 Er-37 C1 C1 te-se 1
Er 33m C1 3*-135 C1 j,ogg.co.
0.60E+00 1.01F+no x.Anr+nn Ie-133 Ci 6.xar+nn 9 urm, e ang nn gr-39 C1 Ie-177 C1 Ee-139:
Ci Er-Sh Ci Ie-133m C1 Re-131m C1 Er-85 ti Ar-37 c1 Total For Period C1 8.33E+00
- 2.94E+00 1.01E+00 1.23E+01
- 2. todines todine-131 Ci 9.70E-05 1.82E-04
' I.94E-04
' d 73E-04 todine-133 C1 4.07E-04 1.02E-03 1.09E-03 2.52E-03
- 3. Particulates Cl Cr-51 Mn-s t.
C1 Fe-59 ti 1.33E-06 1.33E-06 Co-58 C1 l
Co-60 C1 8.80E-06 8.90E-07 9.10E-07 1.06E j i
Zn-65 ci I-131 C1
=
cs-134 Ci Cs-137 C1 5.90E-07 1.43E-06 2.02E-06 Ba-140 C1
~
Ce-141 C1 Ce-144 C1 1.JJE-D/
1 4.05E-08 1 5.5E-07 1
Gross Aloha ci C1
~
H-3 C1 2.67E+00 3.05E+00 9.89E+00 1.56E+01 Sr-89 C1
<1.44E-07 11.44E-07
<2.00E-07 Sr-v>
Cl 13.61E-08 11.45E-08
<3.00E-08 C1 i
TOTAL Cl O TQF-06 3.69E-06
.9.10E-07 1.40E 0K
Tabic'2.3-1 l
l MILLSTONE UNIT No. 3 SUltiATION OF LIQUID EFFLUENT RELEASES i
' QUARTERLY UIIU APRIL MAY JUNE TOTALS I
YDA 1986 O. Firsion and Activation Products
- 1. TOTAL ACTIVITY Ci 3.96E-01 1.48E-01 3.35E-01 8.79E-01 RELEASED
- 2. AVERAGE DILUTED UCi/al ACTIVITY DURING PERIOD 3.66E-09 1.37E-09 3.09E-09 2.70E-09 B. Tritium
- 1. T AMM Ci 3.18E+01 4.29E+01 2.49E+01 9.96E+01 g
i UCi/al 2.94E-07 3 96E-07 2.30E-07 3 06E-0.7 2..A D
G PERIOD C. Dissolved and Entrained Cases i
- 1. TOTAL ACTIVITY Ci 5.76E-03 5.77E-03 6.55E-03 1.81E-02 i
RELEASED
- D. Cross Alpha
^
Ci g1.18E-04 3.1.84E-04 61.93E-04 gg
,E. Valune 1.
F WASTE LITERS 2.36EM6 3.06E+06 3.22E+06 8.64E406 LITERS 2.59E+10 2.36E+10 2.43E+10 7.38E+10 D
E l
- 3. VOLUME OF DILUTION,
LITERS 3.25E+11 l
DURING TIME PERIOD l
- estimated
Table 2.3-3 l
NILLSTONE UNIT No. 3 LIQUID RAD WASTE EFFLUENTS - BATCH - LUS Tear 1986 i
- 17 Nuclides Released Unit APRIL MAY JUNE 7.84E-03 Cr-51 Ci 5.77E-03 2.07E-03 th-54 C1 2.12E-03 5.85E-04 4.42E-04 3.15E-03 Tc-99M C1 1.04E-03 1.44E-04 2.31E-04 1.42E-03 Co-58 Ci 5.64E-02 2.33E-02 8.54E-03 8.82E-02 Co-60 Ci 8.06E-04 2.67E-04 1.38E-04 1.21E-03 1-131 Ci 3.7aE-03 7.43E-04 2.77E-03 7.24E-03 I-133 Ci 1.03E-02 4.16E-03 1.59E-02 3.04E-02 1-135 C1 3.50E-03 4.61E-04 7.13E-04 4.67E-03 Cs-134 Ci Ci 3.11E-04 2.92E-04 3.76E-05 6.41E-04 Nb-95 4.15E-04 4.15E-04 l
Np-239 eg 2.57E-04 2.57E-04 I
La-140 ct c.-144 ci 9.1RE-03 R.04E-04 2.1er 04 1_04E-n2 Zn-65 c1 6.71E-04 5.02E-04 1.69E-04 Te-59 ci Na-24 ci 2.88E-01 1.14E-01 3.05E-01 7.07E-01 1.14E-02 7.03E-04 1.93E-04 1.23E-02 W-187 c1 9.30E-04 Nb-97 ci 9.30E-04 2.47E-04 2.47E-04 I
I-132 ci 9.90E-04 Zr-95 Ci 6.75E-04 3.15E-04 Fe-55 Ci 62.36E-03 4 3.06E-03 13.22E-03 3.30E-04 21.22E-05 3.54E-06 6.84E-04 Sr-89 C1 ci 11.42E-05 12.30E-05 4.3. 22 E-05 Er-co Total Activity ci 3.96E-01 1.48E-01 3.35E-01 8.79E-01 1.91E-03 3.55E-03 7.34E-04 6.19E-03 Xe-133 c1 re-iss ci 2.79E-03 1.85E-03 2.99E-03 7.63E-03 1.06E-03 3.66E-04 2.83E-03 4.26E-03 Xe-135M ci 5.76E-03 5.77E-03 6.55E-03 1.81E-02 TOTAL ci l
Cross Alpha Ci f1.18E-04 51.84E-04 d.1.93E-04 3.18E+01 4.29E+01 2.49E+01 9.96E+01 f
H-3 C1
l l
Table 2.3-5 MILLSTONE UNIT No. 3 SUM ATION OF GASEOUS EFFLUENT RELEASES QUARTERLY UNITS APRIL HAY JUNE TOTALS YEAR 1986 A. Fission and Activation Gases
- 1. TOTAL ACTIVITY Ci 7.16 E-01 7.16E-01 RELEASD
- 2. AVERAGE RELEASE RATE 3 gf***
9.11E-02 FOR TEE PERIOD 2.76E-01
- 5. Iidines
- 1. TOTAL I-131 ACTIVITY C1 1.80E-05 1.94E-05 41.28E-06 3.74E-05 RELEASD
- 2. AVERAGE RELEASE RATE UCi/sec
- 6. 94E-06 7.24E-06 4.75E-06 FOR TEE PERIOD C. P:treiculates 3.50E-06
- 1. TOTAL PARTICULATE C1 3.50E-06 ACTIVITY RELEASD 4.45E-07
- 2. AVERAGE RELEASE RATE UCi/sec 1.31E-06 FOR THE ?ERIOD 1.40E-07
- 3. TOTAL GROSS N C1 1.38E-07 2.07E-09 ACTIVITY RELEASE D. Tritium I* MALACINIU C1 1.05E+02 4.50E+02 4.48EM1 5.99EM2 RELEAS D 2.
RAGE E RAM g
4.05E M 1, 1.68EM2 1.73 E+01 7.62E+01 UC1/sec
/
Table 2.3-6 MILLSTONE UNIT No. 3 - GASEOUS ETFLUENT - CONTINUOUS NORMAL VENTILATION Year 1986 f
klides blessed hit l APRIL N,'[
MAY JUNE p
l
- 1. Fission gases l
Es-1E C1 n-rr Ci i
D48 Ci tr4ss C1 3e-135 Ci Ie-133 Ci Er-M C1 n.-177 Ci
. In-11Ss Ci Er-85 Ci Ee.133m Ci Ie-131m Ci Er-SS tt Ar-T!
tt i
total For period et j
- 3. ledines l
1edine.131 C1 1.15E-05 1.94E-05 3 2.51E-06 3.09E-05 iodine.133 Ci 1.25E-05 7.82E-05 5 2.71E-06 4.07E-05
$1.38E-05 3.50E-06 41.35E-06 3.50E-06__
Cs-136 Ci l
Cs-137 C1 l
Ba-140 Ci f 5.98E-06 16.94E-06 17.14E-06 Ce-141 C1 Ce-14l C1 Sr-89 ci 11.93E-06 48.03E-07 46.44E-07 Sr-90 Ci 6 3.21E-07 6 1. 21E-07 d1.29E-07 3.50E-06 3.50[-nA TOTAL C1 C1 Cross Alpha C1 1.35E-07 06.15E-07 f4.03E-07 1.35E-07 C1 Tritium C1 1.01E+02 4.41E+02 3.69E+01 5.79E+02 m.
i Table 2.3-7 MILLSTONE UNIT No. 3 - GASEOUS EFFLUENT - CONTINU0US EST BUILDING VENTILATION Yxt 1986 l
Sf hec 1fdes Refessed l Unit l APRIL l
MAY l
JUNE u
- 1. Fission gases S 11 81 i
n.s7 Cf C1 l
E>40 ar-ase C1 So-139 Cl i
Ie-133 Cf l
x: -n C1 Ite-in C1
. In 1ttem C1
+
tr.83s C1 i
te-133m et Ie-1sta i
et I
Er-8s 24 l
Ar=37 tt l
tttal For perted et
- 2. ledines l
todtno-131 C1 1.01E-07 61.04E-07 34.20E-08 1.01E-07
'l '
tedine-133 C1 1.12E-07 11.54E-07 1 6.22E-08 1.12E-07 i
l
- 3. Particulates 1
i C1 Cr-51 h-u C1 Fe-59 et Co-58 C1 Co-60 Ci En-65 et l
I-131 gg
$3.15E-08 64.02E 08 42.87E-08,- - - - -__
Co-134 C1 Cs-137 C1 Ba-140 Ci fl.61E-07
$1.57E-07 61.61E-07 Ce-141 C1 Co-144 C1 c1 Sr-89 C1 63.68E-08 bl.85E-06 a 2.22E-08 Sr-90 Ct
$7.37E-09 13.70E-07 i 3.70E-09 C1 C1 Gross Alpha Ct 3.23E-09 2.07E-09
- 17. 40E-09 5.30E-09 _
l l
l i
Tritium ct 3.81E+00 9.11E+00 7.94E+00 2.09E+0!
t mem------r-,
,~ r e wo,.
-e-
MILLSTUIE INIT Wo. 3 - BATCE l
Tear 1986 l
[ =sims mi==*
I saa i unt I
my l,,,
l*g* p i
- 1. Fission gases l
s eu
_C1 h e?
Cf C1 M
+
i g,.gg, C1 2.19E-03 2.19E-03 I
Be-135 C1 5.08E-02 5.08E-02 i
3.-122 C1 6.63E-01 A str.n1 n==
C1 j.
h1TP C1 l
. him C1 j
tr-83s C1 Re.112m tt l
b111e 5
ti
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l Arm 11 tt g,gg y,, = g tg 7.16E 7 1Kr_nt
(
C. Sodines
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. 6.38E-06 f
todtne.131 Cf 6.38E-06 1.01E-05 gegtne.133 Ct 1.01 E-05
- 3. Partismistes C1 cr-51 m-na C4 Fe-59 24 Co-58 C1 Co-60 ft En-65 et 1-131 et "s-134 24 Co-137 Cf Ba-140 Cf Ce-141 Cf Co-144 C1 ci C1
'e ttrrAL C1 C1 Ct 5.13E-02 _
g.3 Ct 5.13E-02
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Ct m
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