ML20138H042

Annual Radioactive Effluent Rept for 1996

ML20138H042
Person / Time
Site:	Millstone
Issue date:	12/31/1996
From:	Thayer J NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20138H049	List: B16424, Forwards 1996 Annual Radioactive Effluent Rept, Which Consolidates Radioactive Effluents Release Rept & Radioactive Effluents Dose Rept.Rept Includes Summary of Quantities of Solid Radwaste & Liquid Gaseous Effluents ML20138H042
References
NUDOCS 9705070050
Download: ML20138H042 (58)

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l Annual Radioactive Effluent Report i

1996 1

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Northeast Nuclear Energy Company Millstone Nuclear Power Station

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Unit License Docket 1 DPR-21 50-245

2 DPR-65 50-336 1

3 NPF-49 50-423

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9705070050 970502 PDR ADOCK 05000245 R PDR

Table of Contents introduction 1.0 Doses 1.1 Dose Calculations 1.2 Dose Results 2.0 Radioactivity 2.1 Airborne Effluents 2.2 Liquid Effluents 2.3 Solid Waste 3.0 REMODCM Changes 4.0 Inoperable Effluent Monitors 5.0 Errata

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Introduction This report is being submitted for Northeast Nuclear Energy Company's Millstone Power Station's Units 1,

2, and 3, in accordance with 10CFR50.36a and the Radiological Effluent Technical Specifications and in the US NRC Regulatory Guide 1.21 format. A ccmbined report is being submitted for all three units because they share some common effluent facilities.

l The report provides radioactivity information for airborne and liquid effluents and solid waste. Doses and regulatory limits are provided for airborne and liquid effluents. If applicable, any changes to the

REMODCM, description of any effluent monitors inoperable for more than 30 days, and any corrections j to previous reports are included.  ;

The annual capacity factor for: Unit 1 was 0.0%, Unit 2 was 13.7%, and Unit 3 was 24.8%. Listed

- below are the major shutdowns for each unit during 1996 l

Period Reason Unit 1 01/01 - 12/31 The Unit was taken off-line for Refueling outage 15.

] Unit 2 02/20 - 12/31 The unit was taken off-line for re-engineering of the Containment ornergency Sump Screen.

Unit 3 03/30 - 12/31 The unit was taken off-line to correct design deficiencies of a i number of Containment Isolation Valves.

All three of the Millstone units are currently designated as Category til on the NRC Watch List and will require NRC permission for restart.

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,. . 1.0 Doses This report provides a summary of the estimated off-site radiation doses from routine releases of )

radioactive materials in airborne and liquid effluents for each unit, included are the annual population dose commitments (person-rem) for the area within 50 miles of the site, the annual average dose

, commitment (mrem) to the population, and the annual maximum dose commitment (mrem) to any real

! member of the public. Also provided are the maximum gamma and beta air doses.

The doses are compared with the regulatory limits and with the annual average population dose commitments from natural background and other sources to provide perspective.

. 1.1 Dose Calculations

! l The off-site dose to humans from radioactive airborne and liquid effluents have been calculated using measured radioactive effluent data, measured meteorological data, and dose computer models developed by the US Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA). These doses generally tend to be conservative because of the i- conservative assumptions used in these models. More realistic estimates of the off-site dose can be obtained by analysis of environmental monitoring data. A comparison of doses

! estimated by each of the above methods will be presented in the Annual Radiological

Environmental Monitoring Report.

1 1.1.1 Population and Maximum Individual Dose Commitment Population dose commitment is defined as the total radiation dose received by the specified population in a specified time period from an ident:fied radiation source. For this report, the specifiec' , Spulation is defined as the population within 50 miles of the i Millstone nuclear site. The doses are based upon continuous exposure to the airborne and liquid effluents for a one year period and an associated dose commitment over a 50-year period from initial exposure, taking into account radioactive decay and biological

elimination of the radioactive materials contributing to the dose. The population dose commitment (person-rem) is the sum of the individual doses.

1 The dose calculations are based upon these three types of input: radioactive source term, site specific data, and generic factors. The radioactive source term (Curies) is 2 characterized in the Effluent Activity section of this report. The site specific data includes: meteorological data (e.g. Wind speed, direction, stability, etc.) to calculate the transport and dispersion of airborne effluents, dilution factors for liquid effluents, the population distribution and demographic profile surroundmg the site by compass sector.

Other site specific data include the average annual production of milk, meat, vegetation, fish, and shellfish. The generic data includes the average annual consumption rates (for inhalation of air and ingestion of fruits, vegetables, leafy vegetables, grains, milk, poultry, meat, fish, and shellfish) and occupancy factors (for air submersion and ground irradiation, shoreline activity, sv/imming, boating, etc.) for determining the dose to the individual who would receive the maximum dose (maximum individual). All these inputs are used in the appropriate dose models to calculate the population and individual dose commitments from radioactive site airborne and liquid effluents.

1.1.1.1 Airborne Effluents Maximum individual doses and population doses due to the release of noble gases, radioiodines, and particulates were calculated using the computer code GASPAR (Ref 1), with the exception of Unit i noble gas doses. The maximum individual dose due to direct exposure from the Unit 1 noble gas 4 l

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, - o plume was calculated using the computer code AIREM (Ref 2). l The GASPAR code is an NRC code which uses a semi-infinite cloud model to implement the NRC Regulatory Guide 1.109 (Ref 3) dose models. The AIREM code is an EPA code which uses a sector averaged Gaussian diffusion model that includes ground and inversion lid reflections, radionuclide decay, first daughter in-growth, ground deposition, cloud depletion, and dose contributions from radionuclides in clouds at all azimuths. The finite cloud model used in AIREM is a modified version of R.E. Cooper's code EGAD (Ref 4).

The values of average relative effluent concentration (yf0) and average  !

relative deposition (D/Q) used in the GASPAR code were generated using a '

meteorological computer code which implements the assumptions cited in NRC Regulatory Guide 1.111 (Ref 5), Section C. The annual summary of hourly meteorological data (in 15-minute increments), which includes wind speed, direction, atmospheric stability, and joint frequency distribution, is not provided in the report but can be retrieved from computer storage.

Unit 1 (375 ft) stack releases are always considered elevated releases; and, Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 447 ft meteorological tower levels. Because GASPAR's semi-infinite cloud modelwould underestimate the direct exposure [

dose from the plume within 2 miles of the stacir, AIREM was used to  !

determine the maximum individual exposure from an overhead finite gamma cloud.

Unit 2 (159 ft) vent releases are considered mixed mode (partially elevated i and partially ground) releases; and, Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 142 ft meteorological tower levels. GASPAR was used to calculate doses for Unit 2 continuous releases throcgh the Unit 2 vent (building ventilation) and steam generator blowdown tank flashed gases; and, doses for Unit 2 batch releases through the Unit 1 stack (containment vents and wasts gas tanks) and Unit 1 2 vent (containment purges). These doses were analyzed to determine the total Unit 2 airborne effluent dose.

Unit 3 (142.5 ft) vent releases are considered mixed mode (partially elevated and partially ground) releases; and, Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 142 ft meteorological tower levels. GASPAR was used to calculate doses for Unit 3 continuous releases through the Unit 3 vent (building ventilation) and for Unit 3 batch releases from containment purges and drawdowns. These doses were analyzed to determine the total Unit 3 airborne effluent dose.

1.1.1.2 Liquid Effluents Maximum individual and > "datu doses from the release of radioactive liquid effluents were ca'cula% 'm t 7 LADTAP (Ref 6) code, which uses the dose models and parameters ua m NRC Regulatory Guide 1.109. i I

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' l 1.1.2 Gamma and Beta Air Doses  !

i Maximum gamma and beta air doses from the release of noble gases were calculated I using the GASPAR code, with the exception of the Unit 1 gamma air dose which used the greater dose from either GAGPAR or AIREM. l 1.2 Dose Results 1.2.1 Airbome Effluents For population doses, the GASPAR code calculates the dose to the whole body, GI-tract, bone, liver, kidney, thyroid, lung, and skin from each of the following pathways: j direct exposure from the plume and from ground deposition, inhalation, vegetation, I cow's milk, and meat. The values presented are a total from all pathways; however, I only the whole body, skin, and maximum organ dose are presented.

For the dose to the maximum individual, the GASPAR code calculates the dose to the same organs listed above for the following pathways: direct exposure to the plume (except for Unit i finite cloud doses), exposure from ground deposition, inhalation, and ingestion of vegetation, meat, cow's milk, and goat's milk. The doses are calculated for adults, teenagers, children, and infants separately.

For the plume and inhalation pathways, the maximum individual dose is calculated at the off-site location of highest decayed x/O where a potential for oose exists.

For ground deposition, the maximum individual dose is calculated at the off-site maximum land location of highest x/O and highest D/O where a potential for dose exists.

For the vegetation pathway, the maximum individual dose is calculated at the vegetable garden of highest D/Q. For the meat, cow's milk, and goat's milk pathways, the calculated dose is included for the maximum individual's dose only at locations and times where these pathways actually exist. Doses were calculated at the cow farm and goat farm of maximum deposition.

The AIREM code calculates the individual whole body and skin dose for each sector-segment. The maximum individual dose is obtained by taking the maximum AIREM result at the off-site location where a potential for dose exists and multiplying by a factor of 0.7 to compensate for building shielding and occupancy.

To determine compliance with 10CFR50, Appendix I (Ref 7), the maximum individual whole body dose only includes the extemal pathways (i.e. plume and ground exposure) while the maximum individual organ dose only includes the internal pathways.

Population doses include all applicable pathways.

l The air dose includes only the dose from noble gases in the plume. Hence, if the I

ground shine contribution was significant, there may be cases where the maximum whole body or skin dose is greater than the maximum gamma or beta air dose respectively. To determine the gamma air dose from the overhead finite cloud, the AIREM results were divided by 0.7 to convert mrem whole body to mrad gamma air dose.

3 The off-site dose commitments from airbome effluents are presented in Table 1-1.

These doses are the maximum doses observed.

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1,2.2 Liquid Effluents l The LADTAP code performs calculations for the following ra thways: fish, shellfish,  !

algae, drinking water, irrigated food, shoreline cctivity, swirraing, and boating. At Millstone, the algae, drinking water, and irrigated food pathways 03 not exist; and, thus, only the other pathways are included in the totals. Doses are cale slated for the whole body, skin, thyroid, GI-LLI, bone, liver, kidney, and lung. Calculations Sre performed separately for adults, teenagers, and children.

The off-site dose commitments from liquid effluents are presented in Table 1-2. These doses are the maximum doses observed. ,

1.2.3 Analysis of Results The doses are well below the permissible levels and smallin comparison to the dose from natural background radiation. The statistical expectation of adverse health effects from the calculated radiation dose due to nuclear plant operations is essentially zero. I Refer to Table 1-3 for the annual effluent whole body airborne and liquid doses for the maximum and average individuals and a quantitative comparison between the doses from nuclear plant operations and those doses from other sources such as naturally occurring background radiation. Also provided are the allowed 40CFR190 (Ref 8) levels .

to a real member of the public. Note that the maximum individualin Tables 1-1,1-2, I and 1-3 is conservatively assumed to be a real member of the public. 1 For compliance with 40CFR190, any direct dose from the site must be added to the I

effluent dose to a "real member of the public " At Millstone, the only potential direct dose of significance would be from Unit 1 turbine shine and radwaste storage.

However, all radwaste storage during this year was well within storage criteria that ensure the public dose would be less than 1 mrem. Hence, the direct dose would be less than 1 mrem and inconsequential for 40CFR190 compliance. The Unit 1 turbine shine dose is typically 2.0 mrem to the maximum individual, who is assumed to be a lobsterman that frequents the water immediately outside the Unit 1 turbine building.

However, since Unit 1 was shutdown for the entire year, this dose was zero (0); and, hence, inconsequential for 40CFR190 compliance.

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References l 1. NUREG-0597 User Guide to GASPAR Code. KF Eckerman, FJ Congel, AK Roecklien, WJ Pasciak, Division of Site Safety and Environmental Analysis, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission, Washington, DC 20555, manuscript completed January 1980, published June 1980.

l 2. EPA-520/1-74-004, AIREM Proaram Manual- A Computer Code for Calculatina Doses.

Population Doses. and Ground Depositions Due to Atmospheric Emissions of l

Radionuclides, JA Martin Jr, CB Nelson, PA Cuny, Field Operations Division, Office of Radiation Programs, US Environmental Protection Agency, Washington, DC 20460, May 1974.

3. NRC Regulatory Guide 1.109 Calculation of Annual Doses to Man from Routine I Releases of Reactor Effluents for the Purpose of Evaluatina Comoliance with 10 CFR Part 50. Appendix 1. Revision 1, October 1977.

4. DF-1304 EGAD - A Computer Proarem to Compute Dose Intearals from Extemal Gamma Emitters. RE Cooper, Mathematics and Computers (TID-4500, VC32), ,

Savannah River Laboratory, Aiken, SC, September 1972. ,

5. NRC Regulatory Guide 1.111 Methods for Estimatino Atmospheric Transport and i Dispersion of Gaseous Effluents in Routine Releases from Liaht-Water-Cooled i l Reactors. Revision 1, July 1977. ,

i l 6. NUREG/CR 1276 ORNidNUREG/TDMC-1 User's Manual for LADTAP ll- A Computer  !

Proaram for Calculatina Radiation Exoosure to Man from Routine Release of Nuclear

Reactor Liouid Effluents, DB Simpson, BL McGill, prepared by Oak Ridge National Laboratory, Oak Ridge, TN 37830, for Office of Administration, US Nuclear Regulatory Commission, manuscript completed 17 March 1980.

7. 10 CFR Enerav. Part 50 Domestic Licensina of Production and Utilization Facilities.

Appendix 1 Numerical Guides for Desian Objectives and Limitim Conditions for Operation to Meet the Criterion *As low As Reasonably Achievable" for Radioactive Material in Liaht-Water-Cooled Nuclear Power Reactor Effluents.1 January 1994 Edition.

8. 40 CFR Environmental Protection Aaenev, Part 190 Environmental Radiation Protection Standard for Nuclear Power Operation. Revision 0,13 January 1977.

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Table 1-1 1996 ON-Site Dose Commitnients from Airborne Emuents Millstone Unit- 1 2, 3 '

Unni 1st Ouener 2nd Quener 3n10uaner 4th Quener Max Air (mred) (mred) (mrad) (mrad)

Bete 0 00E+00 0 00E+00 0. 00E+ 00 0 00E+00 [

Gamma 0 00E+00 0 00E+00 0 00E+00 0 00E+00 '

Max indMdual (mrem) (mrem) (mrem) (m em)

Mole Body 2 08E-04 c 102 = EsE 4.42E-05 c 110 = r 7.10E-05 0 0 9 m NNw 2.15E-04 c 10 n ESE Thyroid 0.00E+ 00 0.00E+00 0.00E+00 0 00E+00 Skin 2 45E 04 o 102 m ESE 519E-05 e 110 m E 8 34E-05 o O e ma.NW 2 52E-04 e 10 mi ESE Population (person rem) (person 4em) (pe son-rem) (person rem)

Mole Body 6 65E-04 3 03E-04 7.66E-04 1.19E-03  ;

Thyroid 6.65 ')4 2.56E-04 7.08E-04 1.12E-03  ;

SAin 7.77E-04 3 01E-04 8.32E-04 1.32E-03 Avg individual (mrem) (mesm) (mrem) (mrem) ,

Mole Body 2 28E-07 1.04 E-07 2.62E-07 4.08E-07 Thyroid 2.27E-07 8.77E-08 2 42E-07 3. 84 E-07 I SAin 2.66E-07 1.03E-07 2 85E-07 4.52E-07 Unit 2 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Air (mrad) (mrad) (mred) (mrad)

Beta 1.77E-04 o 0 3 n NE 4 53E-06 e16 m ESE 3 89E-07 o 3 5 mi NNE 0.00E+00 Gamma 5 93E-05 o 0 3 miNE 4.15E-08 e 18 mi ESE 3 43E-09 o 3 5 mi NNE 0.00E+00 Max Individual (mrom) (mrem) (mrem) (mrem)

Mole Body 3 47E-05 o 0 3 mi NE 2.70E-08 e 16 m ESE 2.25E-09 o3$n NNE 0.00E+00 Thyroid 127E-05 o 0 3 m NE (t) 7.31 E-09 o 13 mi ESE (c) 3.13E-10 o 6 0 = N (c) 0.00E+00 Skin 9 96E-05 o 0 3 miNE 315E-06 e 16 m ESE 2.70E-07 o 3 5 mi NNE O00E+00 Population (person-rom) toerson-tem) (person rem) (person rem)

Mole Body 1.80E 04 7.78E-07 1.36E-09 0.00E+00 Thyroid 180E-04 7.78E-07 1.36E-09 0 00E+00 Skin 4 74E-04 1.10E-04 3 61E-08 0 00E+00 Avg Individual (mrom) (wem) (mrem) (mrem)

Mole Body 6.16E-08 2.66E-10 4 66E-13 0.00E+00 Thyroid 6.16E-08 2.66E-10 4.66E-13 0.00E+00 ,

l SAin 1.62E 07 3.77E-08 1.24E-11 0 00E+00 '

Untt3 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Air (mrad) (mrad) (mred) (mrad)

Beta 1.10E-03 o 0 3 mi NE 2.38E-06 o O e = www 0.00E+00 0 00E+00 Gamma 3 70E-04 o 0 3 m NE 9.56E-07 o O s = WNw 0.00E+00 0.00E+00 l Max Individual (mrem) (mrem) (mrem) (mrem) l Mole Body 2.20E-04 o 0 3 mi NE 2.43E-06 o O e = wNw 6.74E-06 o 0 3 mi NE 0.00E+00 l Thyroid 4.25E-03 o 0 3 mi NE (t) 8.10E-05 o 7 0 = www (i) 0.00E+00 0.00E+00 l Skin 612E-04 o 0 $ m NE 3 77E-06 o08m WNw 7.89E-06 o 0 3 m NE O00E+00  ;

j Population (person rem) (person 4em) (person tem) (person-rem) l Mole Body 2.74E-02 5 95E-05 4.19E-06 0 00E+00 Thyroid 2.81 E-02 5.10E-04 3 39E-06 0.00E+00 Skin 2 97E-02 6 46E-05 3 97E-06 0 00E+00 ~

l Avg individual (mrem) (mrom) (mrom) (mrom)

! Mole Body 9.38E-06 2.04E-08 1.43E-09 0 00E+00

Thyroid 9 62E-06 1.75E-07 1.16E-09 0 00E+00 Skin 1.02E-05 2.21 E-08 1.36E-09 0 00E+00

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(1)= Adult. (c)=Cnild, (i)= Intent, (t)= Teen

Table 1-2 1996 Off-Site Dose Commitments from Liquid Effluents

! Millstone Units 1,2,3 Unit 1 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max individual (mrem) (mrem) (mrem) (mrem) i Mtola Body 1.20E-02 (c) 5.89E-02 (c) 1.99E-01 (c) 1.50E-01 tc)

! Thyroid 1.08E-05 m 9.60E-05 N 1.42E-04 m 1.92E-04 m j Maxorgan 2.40E-02 mm 1.17E-01 m oo 3.96E-01 mm 3.00E-01 mm Population (pemon-rom) (poman-rem) (pomon-rom) (pomon4em) l nhole Body 1.17E-02 5 83E-02 1.89E-01 1.49E-01 Thyroid 1.16E-04 9 99E-04 1.62E-03 1.86E-03 Max Ogan 2.41 E-02 m 1.19E-01 m 3.91 E-01 00 3 09E-01 m l Avg Individual (mrem) (mrom) (mrem) (mrem) l nhole Body 4.01 E-06 2.00E-05 6.47E-05 5.10E-05 l Thyroid 3.97E-08 3 42E-07 5.55E-07 6.37E-07 Max Organ 8 25E-06 m 4 08E-05 m 1.34E-04 00 1.06E-04 m Unlt 2 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Man individual (mrem) (mrem) (mrem) (mrom)

Whole Body 2.09E-03 c) 7.62E-03 (c) 4.94E-04 m 1.16E-03 N Thyroid 9.68E-04 W 1.35E-03 m 2.04 E-04 m 5 24E-04 m Max Organ 1.75E-02 m(oo 2.76E-02 (e)(oo 1.33E-03 m (p) 7.65E-03 m <no Population (pemon rem) (pemon4em) (Mrson4em) (person 4em)

Khole Body 3 94E-02 6.40E-02 1.14E-02 2.39E-02 Thyroid 1.07E-02 1.41 E-02 1.94E-03 5.84E-03 Max organ 2 61E-01 (a) 3.35E-01 (so 2.30E-02 (so 1.15E-01 (o Avg individual (mrem) (mrom) (mrom) (mrom) nhole Body 1.35E-05 2.10E-05 3.90E-06 8.18E-06 l Thyroid 3 66E-06 4.83E-06 6.64E-07 2 00E-06 l Mas Organ B.94E-05 to 1.15E-04 (o 7.8BE-06 (so 3 94E-05 (so j l  !

Unht3 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter l Max Individual (mrem) (mrem) (mrem) (mrem >

nhole Body 1.83E-03 (c) 2.91E-03 (e) 2.99E-03 m 5 32E-04 m Thyroid 3 33E-04 m 8.11 E-04 m 1.05E-03 m 2.56E-04 W Max Organ 1.62E-02 w(oo 1.03E-02 m too 8 4BE-03 m(so 9 40E-03 m(oo Population (pemon4em) (pemon. rem) (pemon-rom) (pemonsem)

Whole Body 4.07E-02 9.06E-02 8.96E-02 1.30E-02 Thyroid 3.95E-03 1.21 E-02 1.20E-02 4.07E-03 Max Organ 3.52E-01 (m 1.90E-01 to 1.82E-01 (m 3 57E-01 te l Avg individual (mrem) (mrem) (mrom) (mrem) nhole Body 1.39E-05 3.10E-05 3.07E-05 4.45E-06 Thyroid 1.35E-06 4.14E-06 4.11E-06 139E-06 Max organ 1.21 E-04 too 6 51E-05 (ao 6.23E-05 (ao 1.22E-04 (ao

(a)= Adult,(c)= Child,(i)=lntant (t)= Teen (bo)= Bone; (gi)=Gi-LLI, (ki)= Kidney, (ii)= Liver, (lu)= Lung. (th)= Thyroid

l Table 1-3 1996 Off-Site Dose Summary l Millstone Units 1,2,3 Population Dose Committments (person-rem)

Airborne Liquid Whole Body l Thyroid l Skin Whole Body l Thyroid l Max Organ Unit 1 0.0029 0 0027 0.0032 0 4080 0.0046 0.8431 Unit 2 0 0002 0 0002 0.0006 0 1387 0.0326 0.7340 Unit 3 0 0275 0.0286 0 0298 0.2339 0 0321 1.0810 station 0 0306 CD315 0.0336 0.7806 0 0693 2 6581 Max individual Doses vs Limits Whole Body Thyroid Max Organ Skin Air Airborne l Liquid Airborne l Liquid Liquid Airborne Beta l Gamma (mrom) (mrom) (mrem) (mrom) (mrad)

Unit LknH * $ 3 15 10 10 15 20 10 Un6t1 Actual 00005 0 4199 0 0000 0 0004 0 8370 0 0006 0 0000 0.0000 Unit 2 Actual 00000 0.0114 0 0000 0 0030 0 0541 0 0001 0 0002 00001 Unit 3 Actual 0 0002 0 0083 0 0043 0 0025 0 0444 0 0006 0 0011 0 0004 Station Umit" 25 75 25 Station Actual 04403 0 0103 0 9355 Connecticut Resident Average Whole Body Doses (mrem)

Cosmic 27

Cosmogenic 1 Terrestial (Atlantic and Gulf Coastal Plain) 16 inhaled 200 in the Body 40 Average CT Resident Whole Body Dose from Background "* l 284 Average CT Resident (within 50 miles) Whole Body Dose from Millstone Station Radioactwo Emuents 0.0003

• 10CFR50 Appenex 1

" 43CFR190

" NCRP94 e

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2.0 Radioactivity 2.1 Airborne Effluents 2.1.1 Measurer ent of Radioactivity i l

2.1.1.1 Unit 1 Stack 2.1.1.1.1 Fission and Activation Gases Stack monitors continuously record the effluent activity and flow rate. Weekly grab samples are taken from the stack and ,

analyzed for isotopic content. When the recombiner is not '

operable sampling frequency is increased. The isotopic concentrations at the relcase point are multiplied by the total stack flow to obtain the total activity released for each isotope.

Tritium collection is accomplished t.y the gas washing bottle method. The sample is counted on a Jguid scintillation detector. j Concentration is computed using the warst possible case,100% '

humidity. Concentration is multiplied by volume to give the total activity released.

2.1.1.1.2 lodines and Particulates Charcoal cartridges and particulate filters are used to collect l iodines and particulates, respectively. These filters are then analyzed for isotopic content using a gamma spectrometer.

Particulate filters are also analyzed for Sr-89, Sr-90 and gross alpha. Isotopic cor.centrations are multiplied by the release flow rate and sampling time to determine the total amount of activity released.

2.1.1.2 Unit 2 Vent Total effluent volume from the Unit 2 vent per month is multiplied by the isotopic concentrations as measured by gamma spectrometer HPGe analysis for gases and liquid scintillation detector for tritium to obtain the total activity released from the vent.

Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively. These filters are then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for St-89, Sr-90 and gross alpha. Isotopic concentrations are multiplied by the release flow rate and sampling time to determine the total amount of activity released.

Tritium collection is accomplished by the gas washing bottle method. The sample is counted on a liquid scintillation detector. Concentration is

computed using the worst possible case.100% humidity. Concentration is multiplied by volume to give the total activity released.

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• i 2.1.1.3 Unit 2 Containment Purges Grab samples are taken for gaseous, particulates, and iodine. These are analyzed on a HPGe gamma spectrometer and liquid scintillation detector for tritium. Computed concentrations are then multiplied by the purge volume for the total activity released.

Tritium collection is accomplished by the gas washing bottle method. The f l sample is counted on a liquid scintillation detector. Concentration is computed using the worst possible case,100% humidity. Concentration is multiplied by volume purged to give the total activity released.

2.1.1.4 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, HPGe, analysis of steam generator blowdown water and grab samples of condensed steam exiting the blowdown tank vent. This DF was then applied to the total iodine releases via the steam generator blowdown water to determine the iodine releases out of the b!owdown tank vent. An additional factor of 0.33 was utilized to account for the fraction of blowdown volume actually flashing to steam in the blowdown tank.

2.1.1.5 Unit 3 Vent and ESF Building Vent The Unit 3 ventilation vent collects gas streams from the auxiliary, fuel, waste disposal, and service building exhausts, containment purge, and gaseous waste process vent. The Unit 3 Engineered Safety Features (ESF) building vent collects gas streams from the ESF building ventilation system. This vent ,

is located on the south wall and discharges 23 feet above grade. Total i effluent volume per month is multiplied by isotopic concentrations from the analysis of grab samples and composites to obtain the total activity released.

These samples are obtained monthly for fission gas, weekly composites of filters for iodines and particulates, monthly composites of particulate filters for  !

gross alpha and strontium.

I 2.1.1.6 Unit 3 Containment Drawdown and Purge i

Unit 3 containment is drawn down and purged intermittently. The initial 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 subatmospheric pressure following 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 and are therefore considered batch releases. Calculated volume discharged is multiplied by isotopic concentrations from the analysis of grab samples to

, obtain total activity released.

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2.1.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the i following guidehnes:

J l Samphng/ Data Collection 10% Variation in data collection l Calibration 10% Calibration to NBS standards l Sample Counting 10% Maximum error for counting statistics l Flow & Level Measurements 10% Maximum error for release volumes  !

2.1.3 Batch Releases Unit 2 Purge WGDT Summary Number of Batches 1 6 7 Total Time (min) 1,846 1,908 3,754 Maximum Time (min) 1.846 735 1,846

, Average Time (min) 1,846 318 536 Minimum Time (min) 1,846 120 120 Unit 3 Purge Drawdown Summary l

Number of Batches 1 0 1 Total Time (min) 1,354 0 1,354 Maximum Time (min) 1,354 0 1,354 1

Average Time (min) 1,354 0 1,354

! Minimum Time (min) 1,354 0 1,354 1 l '

! 2.1.4 Abnormal Releases None.

2.2 Liquid Effluents 2.2.1 Measurement of Radioactivity 2.2.1.1 Liquid Tanks There are numerous tanks which are used to discharge liquids containing radioactivity to the environs; they are:

Unit i Decontamination Solution Tank Floor Drain Sample Tanks (2)

Waste Sample Tanks (2)

Unit 2 Clean Waste Monitor Tanks (2)

Aerated Waste Monitor Tank Unit 3 High Level Waste Test Tanks (2) l Low Level Waste Tanks (2)

, Prior to release, a tank is recirculated for two equivalent tank volumes. a j sample is drawn and analyzed on the HPGe gamma spectrometer and liquid scintillation detector for individual radionuclide composition. Isotopic l

., _. _ - - - . _ - _ - - _ - . = .

[ ,

concentrations are multiphed by the volume released to obtain the total activity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55 and gross alpha.

2.2.1.2 Unit 2 and Unit 3 Steam Generator Blowdown l

Steam generator blowdown water grab samples are taken and analyzed on the HPGe gamma spectrometer and hquid scintillation detector. Total volume of blowdown is multiplied by the isotopic concentrations to determine the total activity released via blowdown. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55 and gross alpha.

Tritium is determined through liquid scintillation counting; and, strontiums are analyzed by radiochemical separations and appropriate counting techniques.  !

Unit 3 steam generator blowdown is typically recycled and therefore no radioactivity is discharged.

2.2.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:

Sampling / Data Collection 10% Variation in data collection Cahbration 10% Calibration to NBS standards Sample Counting 10% Maximum error for counting statistics Flow & Level Measurements 10% Maximum error for release volumes 2.2.3 Batch Releases Unit 1 Unit 2 Unit 3 i l

Number of Batches 154 81 189 I Total Time (min) 12,S54 6,075 17,888 Maximum Time (min) 189 220 1,560 Average Time (min) 82 75 95 Minimum Time (min) 12 1 10 Average Stream Flow Not Applicable - Ocean Site 2.2A Abnormal Releases None.

l I

f

+

Effluent Release Tables Table 2.1-1 Unit 1 Airborne Effluents, Release Summary Table 2.1-2 Unit 1 Airborne Effluents, Elevated Continuous Table 2.1-3 Unit 1 Liquid Effluents, Release Summary Table 2.1-4 Unit 1 Liquid Effluents, Batch Table 2.2-1 Unit 2 Airborne Effluents, Release Summary Table 2.2-2 Unit 2 Airborne Effluents, Mixed Continuous-Vent & SGBD Tank Vent Table 2.2-3 Unit 2 Airborne Effluents, Mixed Batch-Containment Purges Table 2.2-4 Unit 2 Airborne Effluents, Elevated Batch-WGDT Table 22-5 Unit 2 Liquid Effluents, Release Summary Table 2.2-6 Unit 2 Liquid Effluents, Continuous-SGBD Table 2.2-7 Unit 2 Liquid Effluents, Batch Table 2.3-1 Unit 3 Airborne Effluents, Release Summary Table 2.3-2 Unit 3 Airborne Effluents, Mixed Continuous-Normal Ventitation Table 2.3-3 Unit 3 Airbome Effluents, Mixed Continuous-ESF Building Ventilation Table 2.3-4 Unit 3 Airborne Effluents, Mixed Batch-Containment Drawdown Table 2.3-5 Unit 3 Airborne Effluents, Mixed Batch-Containment Purges Table 2.3-6 Unit 3 Liquid Effluents, Release Summary Table 2.3-7 Unit 3 Liquid Effluents, Continuous-SGBD Table 2.3-8 Unit 3 Liquid Effluents, Batch-LWS Table 2.3-9 Unit 3 Liquid Effluents, Batch-CPF WN Sumps l

l 4

Table 2.1-1 l Millstone Unit No.1 Airborne Effluents - Release Summary l

l l

l 1996 Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total L

A. Fission & Activation Gases

1. Total ActNdy Cl N/D l N/D l N/D l N/D l N/D Released No Activity Detected

2. Average Penod uCVsec - - - - -

Release Rate B. lodine-131

1. Total ActNdy Ci N/D l N/D l N/D l N/D l N/D Released No Activity Detected l

2. Average Period UCvsec - - - - -

Release Rate C. Particulates

1. Total Activdy C6 2.17E-04 1.12E-04 1.35E-04 9.79E-05 5.61 E-04 Reitased

2. Average Penod uCvsec 2.76E-05 1.42E-05 1.69E-05 1.23E-05 1.78E-05 l Release Rate l D. Gross Alpha

1. Total ActNdy Cl 1.44E-06 6.04E-07 1.02E-06 1.12E-06 4.18E-06 Released

E. Tritium

1. Total ActNay Cl N/D l N/D l N/D l N/D l N/D Released No Activity Detected l 2. Average Period uCt/sec - - - - -

Release Rate N/D = Not Detected i

a f

Table 2.1-2 Millstone Unit No.1 Airborne Effluents - Elevated Continuous l

l l Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l

A. Fission & Activation Gases l Ci I - I - I -

I -

l -

Total Activity l Cl 1 -

1 -

1 - 1 -

l N/D

~

l B. lodines 1-131 Cl - - - - -

Ci - - - - -

Total Activity 1 Ci I -

I - 1 -

I -

I N/D C. Particulates 1131 Cl - - - - -

i Co-60 Ci 6.40E-05 4.26E-05 8.65E-05 6.61E-05 2.59E-04 Cs-137 Cl 1.34E-05 2.44E-05 3.58E-05 2.26E-05 9.62E-05 l Mn-54 Ci 6.34E-06 7.70E-07 - - 7.11E 06 Sr-89 Ci - -

6.80E-07 7.71 E-06 8.39E-06 Sr-90 Cl 1.88E-06 2.32E-07 1.10E-06 1.45E-06 4.66E-06 l Zn-65 Cl 1.31 E-04 4.39E 05 1.06E-05 - 1.86E-04 Total Activity l Ci l 2.17E-04 1 1.12E-04 i 1.35E 04 l 9.79E-05 1 5.61E-04 l

D. Gross Alpha l Gross Alpha l Ci i 1.44E-06 I 6.04E-07 l 1.02E-06 l 1.12E-06 I 4.18E-06 l l

l E. Tritium l lH-3 I Ci 1 -

l -

I -

1 -

l N/D l N/D = Not Detected i

I t

i i

l l

~

l Table 2.1-3 Millstone Unit No.1 l Liquid Effluents - Release Summary i

l 1996 Units 1 st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission and Activation Products

1. Total Activdy Ci 4.47E-03 7.65E-03 6.91 E-03 9.69E-03 2.87E-02 Released

2. Average Penod uCi/mi 7.45E-10 1.28E-09 1.15E-09 1.61E 09 1.20E-09 j Diluted Activay B. Tritium

1. Total Activny C1 1.25E+00 2.49E+00 2.80E+00 7.81 E-01 7.32E+00 Released

2. Average Penod uCi/mi 2.08E 07 4.18E-07 4.66E-07 1.30E-07 3.05E-07 Diluted Activny C. Dissolved and Entrained Gases

1. Total Activay Ci N/D l N/D l N/D l N/D l N/D Released No Activity Detected

2. Average Penod uCi/mi - - - - -

l Diluted Activity D. Gross Alpha l

l 1. Total Activity Ci N/D l N/D l N/D l N/D l N/D l Released No Activity Detected 1 i l E. Volume

1. Released Waste Liters 8.83E+05 2.30E+06 1.79E+06 1.18E+06 6.15E+06 Volume

2. D61ution volume Liters 9.07E+07 2.01E+08 4.48E+09 1.31 E+08 4.90E+09 l

( Dunng Releases

3. Ditution volume Liters 6.00E+09 5.95E+09 6.01E+09 6.01 E+09 2.40E+10 During Penod I

N/D = Not Detected '

l l

i

l Table 2.1-4 Millstone Unit No.1  :

Liquid Effluents - Batch l

Nuclides 1996 l Released Units 1st Otr l 2nd Qtr l 3rd Otr l 4th Otr l Total A. Fission & Activation Products l Ag-110m Ci - - -

2.91 E-04 2.91 E-04 Co-58 Ci 2.56E-04 5.42E-06 - -

2.62E-04 Co-60 Ci 9.97E 04 3.01 E-03 1.67E-03 2.64E-03 8.32E-03 Cs-137 Ci 6.62E-04 9.98E-04 5.31 E-04 1.07E-03 3.26E-03 Fe-55 Ci - - -

5.34E-04 5.34E-04 Mn-54 Ci 1.16E-04 2.09E-04 7.31 E-05 1.13E-03 1.53E-03 Sb-122 Ci 2.73E-06 - - -

2.73E-06 Sb-125 Ci - - -

1.14E-05 1.14E 05 Sr-90 Ci -

1.20E-05 - -

1.20E-05 Zn-65 Ci 2.44E-03 3.41 E-03 4.63E-03 4.01 E-03 1.45E-02 Total Activdy i Cl I 4.47E-03 1 7.65E-03 1 6.91E-03 i 9.69E-03 l 2.87E-02 B. Tritium lH-3 I Ci l 1.25E+00 l 2.49E+00 1 2.80E+00 l 7.81 E-01 1 7.32E+00 l C. Dissolved & Entrained Gases l Ci 1 -

1 - I - 1 -

I -

Total Activity i Ci I - i -

I - I - I N/D D. Gross Alpha l Gross Alpha l Ci I -

I -

1 -

I -

I N/D l N/D = Not Detected l

l

i Table 2.2-1 4 -

Millstone Unit No. 2 Airborne Effluents - Release Summary 1

1 4

1996 4

Units 1st Qtr l 2nd Otr l 3rd Qtr l 4th Qtr l Total 3 A. Fission & Activation Gases ,

1. Total Activity Cl 1.65E+00 4.45E-01 3.42E-02 N/D 2.12E+00 Released

2. Average Period uCi/sec 2.09E-01 5.66E-02 4.30E-03 -

6.72E 02 Release Rate B. lodine-131

1. Total Actwity Ci N/D l N/D l N/D l N/D l N/D Released No Activity Detected

2. Average Period uCl/sec - - - - -

Release Rate C. Particulates

1. Total Activity C6 N/D j N/D l N/D l N/D l N/D Released No Activity Detected

2. Average Penod uCi/sec - - - - -

Release Rate D. Gross Alpha

1. Total Activity Cl 2.26E-08 N/D N/D N/D 2.26E-08 Released E. Tritium

1. Total Activity Ci 9.20E-02 3.28E-04 2.53E-05 N/D 9.23E-02 Released

2. Average Penod uCi/swc 1.17E-02 4.17E-05 3.19E-06 -

2.92E-03 Release Rate N/D = Not Detected

l l

Table 2.2-2 Millstone Unit No. 2 Airborne Effluents - Mixed Continuous - Vent & SGBD Tank Vent Nuclides 1996 Released Units 1st Otr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Xe-133 I Cl i 1.29E+00 1 -

I -

I -

l 1.20E+00 Total Activity I Ci i 1.29E+00 l - I -

I -

l 1.29E+00 B. lodines 1-131 l Ci - -

I -

I - -

l Ci - -

I -

I - -

Total Activity l Ci I - I -

1 -

I -

I N/D C. Particulates 1-131 Ci - - - - -

Ci - - - - -

Total Activity i Ci 1 -

I -

I -

I -

l N/D D. Gross Alpha l Gross Alpha I Ci l 2.26E 08 I -

I -

I -

l 2.26E-08 l E. Tritium

[H-3 i Ci I - I -

I -

I -  ! N/D l N/D = Not Detected i

Table 2.2-3 Millstone Unit No. 2 Airbome Effluents - Mixed Batch - Containment Puiges l

Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total t

l A. Fission & Activation Gases Xe-133 l Cl 3.22E-01 - - -

3.22E-01 Xe-133m Cl 9.45E-03 - - -

9.45E-03 Xe 135 Ci 6.88E-03 - - -

6.88E-03 Total Activity l Cl I 3.38E 01 1 -

I -

1 - .I 3.38E-01 B. lodines 1131 Cl - - - - -

Ci - - - - -

Total Activity i Ci 1 -

I -

I -

1 -

I N/D C. Particulates 1131 Ci ! - - - - -

Ci 1 - - - - -

Total Activity l Ci i -

I - 1 -

I -

l N/D D. Gross Alpha l Gross Alpha i Ci 1 - I -

I -

I - l N/D l E. Tritium lH-3 I Ci I 8.66E-02 l - I -

I -

l 8.66E-02 l l N/D = Not Detected l

l

! i i

i

! , 4 l

Table 2.2-4 Millstone Unit No. 2 Airbome Effluents - Elevated Batch - WGDT Nuclides 1996 Released Units 1st Otr l 2nd Qtr l 3rd Otr l 4th Otr l Total A. Fission & Activation Gases Kr 85 Ci 9.94E 03 4.44E 01 3.42E-02 .

4.88E-01 Xe-131m Ci 1.54E-04 5.67E-04 - - 7.21E-04 Xe 133 Ci 3.90E-03 5.69E-04 - .

4.47E-03 Xe 133m Cl 1.17E-05 - - -

1.17E-05 Total Activity l Ci l 1.40E-02 1 4.45E 01 1 3.42E 02 1 -

l 4.93E-01 B. lodines 1-131 Ci - - . . .

Ci . - - - .

Total Activity l Cl 1 - I -

I -

I .

I N/D C. Particulates 1131 l Ci . . . . .

I ci - . . - -

Total Activity l Ci I -

I -

I -

I -

l N/D D. Gross Alpha .

l Gross Alpha I Ci 1 - I -

I .

1 .

I N/D l E. Tritium lH-3 i Ci I 5.35E-03 1 3.28E-04 1 2.53E-05 1 -

l 5.70E-03 l N/D = Not Detected l

1 i

l

. . .- . . - - _ _ - . - _ . _ . - _ ~ _ . . - _ _ , . . . _ .

I i

l Table 2.2-5 l Millstone Unit No. 2 Liquid Effluents - Release Summary 1996 Units 1st Otr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission and Activation Products

1. Total Actuny C1 2.14E-01 9.03E-02 6.80E-03 1.41 E-02 3.25E-01 Released

2. Average Penod uCi/mi 9.67E-10 1.46E-09 2.95E-10 7.87E-10 1.00E-09 Diluted Activity B. Tritium

1. Total ActNity Ci 1.38E+02 3.58E+01 3.87E-01 1.05E+01 1.85E+02 Released i 1

2. Average Pened uCi/ml 6.24E-07 5.78E-07 1.68E-08 5.87E-07 5.70E-07 Diluted Actuity C. Dissolved and Entrained Gases

1. Total ActNity C6 7.94E 03 6.10E-05 N/D N/D 8.00E-03 Released

2. Average Period uC6/mi 3.59E 11 9.84E-13 - -

2.47E-11 Diluted Actwity D. Gross Alpha

1. Total Activity Ci N/D l N/D l N/D l N/D l N/D Released No Activity Detected E. Volume

1. Released Waste Liters 6.00E+05 3.22E+05 1.34E+06 1.75E+05 2.44E+06 volume

2. Dilution volume Laers 2.34E+09 1.31 E+09 5.08E+09 6.72E+08 9.40E+09 Dunng Releases

3. Dilution volume uters 2.21 E+11 6.20E+10 2.30E+10 1.79E+10 3.24E+11 Dunng Period N/D = Not Detected i

r l

I l

l

i .

l l

Table 2.2-6 Millstone Unit No. 2 Liquid Effluents - Continuous - SGBD u No Activity Detected >>

Nucides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l A. Fission & Activation Products l l Ci 1 - I -

I -

I - l -

l Total Activity i Cl 1 -

I - I -

I -

l N/D B. Tritium lH-3 I Cl 1 -

I -

I - I - I N/D l C. Dissolved & Entrained Gases l l Ci 1 -

1 -

I -

I - I -

l Total Activity l Cl 1 -

I -

I -

I -

I N/D l

D. Gross Alpha  ;

l Gross Alpha I Ci ! - I - 1 -

I - I N/D l l

N/D = Not Detected l l

l l

l l

l I

i h

i i

l l

l

Table 2.2-7 Millstone Unit No. 2 Liquid Effluents - Batch l

l Nuclides 1996 i Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total l

! A. Fission & Activation Products Ag-110m Cl 3.39E-03 1.07E-03 -

1.83E-04 4.64E-03 Co 57 Ci 3.03E-04 1.81E 04 3.69E 05 8.99E-06 5.30E-04 Co-58 Ci 2.13E-02 1.05E-02 2.35E 03 7.51 E-04 3.50E-02

'Co-60 Ci 1.23E-01 4.93E-02 2.47E-03 8.19E-03 1.83E-01 Cr 51 Ci 1.96E-04 - - - 1.96E-04 Cs 134 Ci -

1.57E-04 1.69E-04 1.31E 04 4.57E-04 Cs-137 Ci 2.22E 03 1.83E-03 1.27E-03 1.28E-03 6.61 E-03 Fe-55 Ci 5.34E-02 2.47E-02 3.30E-04 2.80E-03 8.12E-02 Fe 59 Cl 4.14E-05 - - -

4.14E-05

( La-140 Cl 1.73E-04 7.86E-05 - -

2.52E-04 Mn-54 Ci 4.01 E-03 1.45E 03 -

3.20E-04 5.79E-03 Nb 95 Ci 4.05E-05 - - - 4.05E-05 l Ru-105 Ci 3.40E 05 - - - 3.40E-05 Sb-124 Cs 8.71 E-04 - - - 8.71 E-04 l Sb-125 Ci 4.31 E-03 5.67E-04 8.97E-05 1.87E-04 5.15E-03

Sr89 Ci 6.21 E-05 - - - 6.21 E-05 Sr90 Cl 3.41 E-05 1.03E-04 8.00E-05 2.15E-04 4.32E-04 Zn-65 Cl - 2.78E-04 - -

2.78E-04 Total Activity 1 Cl i 2.14E-01 1 9.03E-02 1 6.80E-03 1 1.41E-02 1 3.25E-01 l B. Tritium l lH-3 l Cl i 1.3BE+02 1 3.58E+01 1 3.87E-01 I 1.05E+01 i 1.85E+02 l C. Dissolved & Entrained Gases Xe-133 Cl 7.93E-03 6.10E-05 - I - 7.99E-03 Xe-135 Ci 8.26E-06 - -

l -

8.26E-06 Total Activity l Cl I 7.94E-03 1 6.10E-05 l -

I -

I 8.00E-03 D. Gross Alpha l Gross Alpha l Ci 1 - I - I -

1 -

l N/D l N/D = Not Detected l

Table 2.31 Millstone Unit No. 3 Airbome Effluents - Release Summary 1996 Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total A. Fission & Activation Gases

1. Total Activty Cl 1.59E+01 1.616-02 N/D N/D 1.59E+01 l Released '

2. Average Penod uCusec 2.02E+ 00 2.05E-03 - - 5.04E-01 Release Rate B. lodine-131

1. Total Actwty Ci 9.38E-05 4.06E-06 N/D N/D 9.79E-05 Released

2. Avmpo Period uC4/see 1.19E-05 5.17E-07 - - 3.10E-06 Release Rate C. Particulates

1. Total Activity Ci N/D 8.77E-07 6.79E 06 N/D 7.66E 06 Released

2. Average Penod uCusec -

1.12E 07 8.54E-07 - 2.42E-07 Release Rate D. Gross Alpha

1. Total Activity Ci 2.89E-07 1.13E-08 1.29E-07 9.67E-08 5.25E 07 Released E. Tritium

1. Total ActMty Ci 4.87E+01 4.71 E-02 N/D N/D 4.87E+01 Released

2. Average Period uCi/sec 6.19E+00 5.99E-03 - - 1.54E+00 Release Rate N/D = Not Detected l

l I

I

. .~ .. --. ---- -- -. _ - . . - - - . . - - - . ,

Table 2.3-2 Millstone Unit No. 3 Airbome Effluents - Mixed Continuous - Normal Ventilation

', l Nuchdes 1996 1

Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Xe-133 i Ci , 1.59E+01 i - I - 1 -

1 1.59E+01 Total Activity i Ci i 1.59E+01 i - I - I - l 1.59E+01 B. lodines 1-131 Ci 9.36E-05 3.43E-06 - -

9.70E-05 l133 Ci 3.67E-04 - - - 3.67E-04 Total Activity i Cl I 4.60E-04 3.43E-06 l -

1 - l 4.64E-04 C. Particulates 1-131 Ci - - - - -

Ce 144 Ci - -

6.73E 06 - 6.73E-06 Co-60 Ci - - 5.55E-08 - 5.55E-08 Total Activity i Cl i - I -

l 6.79E-06 l -

1 6.79E-06 D. Gross Alpha l Gross Alpha l Cl i 2.34E-07 l -

1 1.13E 07 I 5.82E-08 I 4.05E 07 l E. Tritium lH-3 i Cl l 4.87E+01 1 - I - I -

1 4.87E+01 l N/D = Not Detected

. l

I Table 2.3-3 Millstone Unit No. 3 Airbome Effluents - Mixed Continuous - ESF Building Ventilation >

Nuclides 1996 Released Units 1st Otr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases I Ci I -

I -

I -

I - I -

Total Activity i Ci 1 - I -

I -

l -

l N/D B. lodines 1-131 l Ci 2.18E-07 6.33E-07 - -

8.51E 07 l-133 i Ci 8.92E-07__ 3.51 E-07 - - 1.24E-06 Total Activity l Ci l 1.11E 06 I 9.84E 07 I -

I -

l 2.09E-06

. C. Particulates 1-131 Cl - - - - -

Co-58 Cl -

8.77E-07 - - 8.77E-07 Total Activity I Cl i -

l 8.77E-07 l -

1 -

l 8.77E-07 i D. Gross Alpha l Gross Alpha l Cl I 5.49E-08 l 1.13E-08 l 1.57E-08 1 3.85E-08 l 1.20E 07 l f

E. Tritium lH-3 I Cl 1 - I - I - I - I N/D l N/D = Not Detected

.l

- )

l )

Table 2.3-4  !

Millstone Unit No. 3 Airborne Effluents - Mixed Batch - Containment Drawdown l

<< No Activity Detected >> l Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. RJsion & Activation Gases

, i Cl 1 - j - I -

l - j -

Total Activity l Ci ! -

1 -

I -

I -

I N/D B. lodines 1131 Ci - - -

l i Ci - - -

l - -

I Total Activity l Ci 1 -

I -

I - I -

I N/D C. Particulates 1131 Ci - - -

l

Ci - - -

l - -

l Total Activity I Ci 1 -

I - I -

I -

l N/D D. Gross Alpha l Gross Alpha i Ci 1 - I - I -

I -

I N/D l 9

l E. Tritium I lH-3 I Cl 1 -

I -

1 -

I -

I N/D l I

N/D = Not Detected 1 i t

i

. l Table 2.3 5 Millstone Unit No. 3 Airbome Effluents - Mixed Batch - Containment Purges Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total j A. Fission & Activation Gases Xe-133 Ci -

1.50E-02 - -

1.50E-02 Xe-135 Ci -

1.09E-03 - -

1.09E-03 Total Activity i Ci i -

l 1.61E-02 l -

I -

1 1.61 E-02 B. lodines 1-131 Cl 1 - - -

I - -

Ci j - - -

I - -

l Total Activity i Ci 1 -

I -

I -

I -

I N/D l l

C. Particulates 1-131 Ci - - - - -

Ci - - - - -

Total Activity l Cl 1 -

I -

I -

I -

t N/D D. Gross Alpha l Gross Alpha I Cl l - I -

i -

I -

I N/D l E. Tritium lH-3 Ci 1 -

l 4.71E-02 l - I -

1 4.71E-02 l N/D = Not Detected

Table 2.3-6 Millstone Unit No. 3 Liquid Effluents - Release Summary I

1996 i i Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission and Activation Products

1. Total Actwity c6 1.99E-01 1.37E-01 4.41E-02 1.12E-02 3.91 E-01 Released

2. Average Period uCVml 4.48E-10 1.11 E-09 9.01 E-10 1.71E 10 5.74E-10 Diluted Activity B. Tritium

1. Total Actwny Ci 6.93E+01 1.07E+02 2.13E+01 1.81 E+01 2.16E+02 Released

2. Average Period uCum! 1.56E-07 8.66E-07 4.34E-07 2.77E-07 3.17E-07  !

Diluted Actwity C. Dissolved and Entrained Gases

1. Tot .: etivey Ci N/D N/D N/D 2.06E-05 2.06E-05 l R a '.>. 5 +d

2. Aveiage Period uCum! 4.65E-14 - - -

3.03E-14 Diluted Actwity D. Gross Alpha

1. Total Actwity Ci N/D l N/D l N/D l N/D j N/D Released No Activity Detected E. Volume

1. Released Waste uters 2.42E+06 1.41 E+06 1.03E+06 9.43E+05 5.81E+06 Volume

2. Dilution volume uters 1.11 E+10 5.49E+09 3.66E+09 7.45E+09 2.77E+10 Dunng Releases

3. Dilution volume uters 4.43E+11 1.23E+11 4.90E+10 6.54E+10 6.81E+11 Dunng Penod I l

N/D = Not Detected

Table 2.3-7 Millstone Unit No. 3 Liquid Effluents Continuous - SGBD

<< No Activity Detected >>

Nuclides 1996 Released Units 1st Otr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Products i Ci l -

1 - I -

I -

I -

Total Activity l Ci l -

I -

I -

1 -

l N/D l

i B. Tritium l lH-3 i Cl 1 -

I -

I -

1 -

i N/D l l l l C. Dissolved & Entrained Gases l l Ci I -

I - I -

I -

1 -

! Total Activity l Ci I -

l - I - I -

I N/D l

D. Gross Alpha l Gross Alpha l Ci I -

1 -

I -

l -

l N/D l l

N/D = Not Detected l

l t

l l

i I i

f i

d Table 2.3-8 Millstone Unit No. 3 Liquid Effluents - Batch - LWS 1

Nuchdes 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Products Ag-110m Ci 2.80E-03 2.97E-04 7.01 E-05 6.88E-05 3.23E-03 Ba-139 Cl 2.34E-05 - - -

2.34E-05 Co-57 Cl 1.14E-04 4.25E-05 2.66E-05 2.64E-06 1.85E-04 Co-58 Ci 2.56E-02 6.65E-02 8.20E-03 7.16E-04 1.01 E-01 Co-60 Ci 3.70E-02 1.01 E-02 8.04E-03 2.96E-03 5.81 E-02 Cr-51 Ci -

3.06E-04 - -

3.06E-04 Cs-134 Ci 9.06E-04 6.50E-03 2.93E-03 1.65E-04 1.05E-02

'Cs-137 Ci 4.89E-03 2.56E-02 1.13E-02 7.61 E-04 4.26E-02 Fe-55 Ci 1.05E-01 1.36E-02 2.87E-03 1.30E-03 1.23E-01 La-140 Ci -

3.94E-05 - -

3.94E-05 l La-142 Ci 4.03E-05 - - - 4.03E-05 Mn-54 Ci 9.06E-03 7.54E-03 5.50E-03 8.10E-04 2.29E-02 Nb-95 Cl 1.83E-03 7.79E-06 1.64E-05 4.96E-04 2.35E-03 Nb 97 Ci 3.50E-04 l 9.68E-05 -

1.08E-04 5.55E 04 Ru-105 Ci 2.79E-04 - - -

2.79E-04 Sb-124 Ci -

3.61 E-05 8.36E-05 -

1.20E-04 Sb 125 Cl 1.03E-02 6.12E-03 5.06E-03 3.35E-03 2.48E-02 Sn-113 Ci 4.48E-05 - -

3.38E-05 7.86E-05 Sr-89 Cl 2.26E-05 1.09E-04 - -

1.32E-04 Tc-101 Ci - - -

1.40E-04 1.40E-04 Zr-95 Ci - - -

2.43E-04 2.43E-04 Zr-97 Ci - -

2.24E-06 -

2.24E-06 Total Activity i Cl I 1.99E-01 1 1.37E-01 1 4.41E-02 l 1.12E-02 1 3.91 E-01 B. Tritium lH-3 i Ci i 6.93E+01 l 1.07E+02 l 2.13E+01 l 1.81E+01 l 2.16E+02 l C. Dissolved & Entrained Gases Xe-135 i Ci i 2.06E-05 l -

I -

I -

1 2.06E-05 Total Activity l Ci l 2.06E-05 l - I -

I -

l 2.06E-05 D. Gross Alpha l Gross Alpha l Ci 1 -

l -

I -

I -

I N/D l N/D = Not Detected

Table 2.3-9 .

Millstone Unit No. 3 Liquid Effluents - Batch - CPF WN Sumps

<< No Activity Detected >>

Nuclides 1996 Released Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total j A. Fission & Activation Products l l Cl 1 -

l - I - I -

I -

l Total Activity i Ci 1 - 1 - l - I -

I N/D l

B. Tritium lH-3 I Ci I - I -

I -

I - I N/D l C. Dissolved & Entrained Gases l Ci l -

I - I I -

Total Activity l Cl 1 -

1 - 1 -

1 -

l N/D l

D. Gross Alpha l Gross Alpha l Cl 1 -

I -

I -

I -

I N/D l N/D = Not Detected i

1 I

t i

I

l l

l- 2.3 Solid Waste l

Solid waste shipment radioactivity summaries for each unit are given in the following tables:

Table 2.1-5 Unit 1 Solid Waste and Irradiated Component Shipments Table 2.2-8 Unit 2 Solid Waste and irradiated Component Shipments Table 2.3-10 Unit 3 Solid Waste and irradiated Component Shipments l The principal radionuclides in these tables were fror" shipping manifests.

Solidification Agent (s):

No solidification on site for 1996 1

l Containers routinely used for radioactive waste shipment include:

l 55-gal Steel Drum DOT 17-H container 7.5 ft' Steel Boxes 45 ft' 87 ft 91 ft' 95 ft' 122 ft' Steel Container 202.1 ft' Steel" Sea Van" 1280 ft' Polyethylene High Integrity Containers 120.3 ft' 132.4 ft' 173.4 ft' 202.1 ft' l

1 l

j l

l l

\

l i

i l

Table 2.1-5 Solid Waste and Irradiated Component Shipments i

l Millstone Unit i I

l January 1,1996 through December 31,1996

1. Type of Waste i

I a Spent resins, filter sludges, evaporator bottoms, etc.

Disposition Units Annual Totals Est. Total Error %

From Wistone Nuclear Pour Station To Chem-Nuclear Services. Inc - m 8.23E+01 a.mweii. SC Ci 1.08E+03 25 %

b Dry compressible waste, contaminated equipment, etc.

Disposition Units Annual Totals Est. Total Error %

From Millstone Nuclear Power Station To Chem-Nuclear Services,Inc. - m3 3.38E+00 sammii. SC Ci 2.88E+00 25 %

From Melistone Nuclear Power Station To Scientire Ecology Group Oak m3 4.49E+02 Ridge. TN Ci 1.85E+00 25%

From Wistone Nuclear Power Station To F.W. Hake Associates m 5.43E+01 Memphis. TN Ci 2.16E-01 25%

l From Wistone Nuclear Power Station To Manufactunng Scences Corp. m 6.79E+00 Oak Ridge, TN Cl 1.58E-02 25%

i From SEG to Chem-Nuclear Services. Inc Samwell. SC m 3.10E+01 Ci 1.93E+00 25%

From Manufactunng Sciences Corporation to Chem-Nuclear Services. Inc.- m 5.55E+00 aarnweri. SC Cl 1.58E-02 25%

c Miscellaneous - Oil, Oily Sludge 1 Disposition Units Annual Totals Est. Total  !

Error %

From Wistone Nuclear Power Station To Scenterc Ecology Group Oak m3 2.55E+00 Ridge. TN Ci 1.11 E-02 25 %

From SEG to Chem-Nuclear Services,Inc.. Barnwell, SC m 2.14E+00 Ci 1.58E+01 25%

d Mixed Waste Disposition Units Annual Totals Est. Total Error %

m3 1.31 E+00 l.From Wistone Nuclear Power Station To Diversified ine. Oak Ridge.TN Ci 1.46E-03 Scentifc 25%Sennces i

I l

Millstone Unit i l Page 1 of 6 i

l *

2. Estimata of major nuclida composition (by type of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

t

. From Millstone Nuclear Powe,r Station To Chem-Nuclear Services. Inc. - Bamwell. Sc for Bunal i

Radionuclide '4 of Total (Estimate) Curies H-3 <0.01 % 6.94E-02 c-14 0.015 % 1.61 E-01 Mn-54 7.011 % 7.54E+01 Fe-55 14.326 % 1.54E+02  !

co-60 7.622 % 8.20E+01 Ni63 l

1.296'4 1.39E+01 '

zn-65 64.377 % 6.93E+02 St-89 < 0.01 '4 7.97E-03 Sr-90 0.016 % 1.73E-01 Ag-110m 0.363 % 3.91 E+00 cs-134 0.140% 1.50E+00 cs137 4.763 % 5.12E+01 Pu-238 <0.01 % 1.57E-02 Pu-239 < 0.01'4 8.21 E-03 Am-241 < 0.01'4 3.31 E-02 Pu-241 0.056 % 5.99E-01 cm-242 <0.01 % 6.75E-04 cm-244 <0.01 % 3.06E-02 ,

Total 1.08E+03  !

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc. I From fAllstone Nuclear Power Station To Chem-Nuclear Services. Inc. - Barnwell, SC for Bural Radionuclide  % of Total (Estimate) Curies H-3 0.039 % 1.13E-03 c-14 <0.01 % 1.08E-04 cr-51 0.078 % 2.26E-03 Mn-54 3.618% 1.04E-01 Fe-55 69.682% 2.01 E+00 Co-57 0.027 % 7.87E-04 co-58 <0.01 % 1.73E-04 cm 15.726 % 4.53E-01 Ni 63 7.235 % 2.09E-01 Zn-65 2.487 % 7.17E-02 Sr-90 <0.01 % 2.68E-04 Ag-110m 0.135% 3.90E-03 Sb-125 0.322 % 9.29E-03 cs-134 0.311 % 8.98E-03 Cs-137 0.241 % 6.95E-03 Pu-238 <0.01 % 2.95E-05 Pu-239 <0.01 % 1.74E-05 Am-241 <0.01 % 2.38E-05 j Pu-241 0.071 % 2.04E-03

cm-244 <0.01 % 5.04E-05 l Total 2.88E+00 l

Millstone Unit 1 Page 2 of 6

- _ _ _ _ __ __ _ . - ____.____m__ _ _ _ _ __ _ .m..

t

2. Estimite of major nuclids composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc.

1 . From hMistone Nuclear Power Stanon To Scientific Ecology Group . Ook Rulge. TN for Super-Cornpoetion, incineration, etc.

Radionuclide  % of Total (Estimate) Curies l H-3 0.212 % 3.93E-03 c-14 0.123 % 2.27E-03 cr-51 0.158 % 2.93E-03 Mn-54 4.105% 7.60E-02 Fe-55 79.000% 1.46E+00 l Co-57 <0.01 % 5.78E-05 co-58 0.025 % 4.59E-04 1 co.60 8.940 % 1.66E-01 Ni S3 1.447 % 2.68E-02 ,

zn-65 5.256 % 9.73E-02 I Nb-95 <0.01 % 1.31 E-05 I Ag-110m 0.015 % 2.84E-04 sb-125 <0.01 % 7.85E-05 cs-134 <0.01 % 6.26E-05 Cs-137 0.622 % 1.15E-02 Pu-238 <0.01 % 1.28E-06 Pu-239 <0.01 % 6.76E-07 Am-241 <0.01 % 8.33E-07 Pu-241 <0.01 % 9.42E-05 cm-242 <0.01 % 3.40E-07 cm-244 <0.01 % 5.42E-06 Total 1.85E+00

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc.

From Millstone Nuclear Power Station To FW Hake & Associates- Memphis, TN Radionuclide  % of Total (Estimate) Curies H-3 0.052 % 1.12E-04 1 c-14 0.205 % 4.42E-04 Mn 54 3.404 % 7.35E-03 Fe-55 50.641 % 1.09E-01 co-58 8.481 % 1.83E-02 co.60 10.153% 2.19E-02 l Ni 63 6.146 % 1.33E-02 Zn-65 10.391 % 2.24E-02 cs-134 1.945 % 4.20E-03 Cs-137 8.583 % 1.85E-02 Total 2.16E-01 l

l Millstone Unit 1 Page 3 of 6 l

. _ _ _ . - . _ _ - - . - . . . . -- , . - - - - . - . - _ . - . _ - - .- . - _ _ = - - - - _

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc.

From IMistone Nuclear Power Station To Manufactunno Sciences Corporation - Oak Ru$ge. TN for Placement Packagmg

( Radionuclide  % of Total (Estimate) Curies H3 0.500 % 7.91 E-05 l Fe-55 80.864 % 1.28E-02 l co-60 8.781 % 1.39E-03 l Ni 63 1.074 % 1.70E-04 I cs-137 8.781 % 1.39E-03 ,

Total 1.58E-02

2. Estimate of major nuclide composition (by type of waste) l j b. Dry compressible waste, contaminated equipment, etc.

From Scientific Ecology Group To Chem-Nuclear Services. Inc. - Barnwell, SC for Burial Radionuclide  % of Total (Estimate) Curies H-3 0.587 % 1.13E-02 Be-7 0.066 % 1.27E-03 c-14 0.194 % 3.75E-03 cr-51 0.161 % 3.10E-03 Mn-54 3.817 % 7.36E-02 Fe-55 71.623% 1.38E+00 Co-57 <0.01 % 1.70E-04 co-58 0.279 % 5.39E-03 co-60 10.915 % 2.11E-01 Ni 63 2.581 % 4.98E-02 Zn-65 4.650 % 8.97E-02 l

l Sr-90 <0.01 % 1.38E-05 Zr-95 <0.01 % 1.18E-05 Ag-110m 0.046 % 8.78E-04 -

sb-125 0.018 % 3.50E-04 cs-134 4.865 % 9.39E-02 Cs-137 0.177 % 3.41E-03 Pu-238 <0.01 % 2.76E-06  ;

Pu-239 <0.01 % 1.33E-06 Am-241 <0.01 % 1.735-06 Pu-241 0.011 % 2.06E-04 cm-242 <0.01 % 5.42E-07 crn-244 <0.01 % 3.20E-06 Total 1.93E+00

2. Estimate of major nuclide composition (by type of waste) __

b. Dry compressible waste, contaminated equipment, etc.

From Manufacturing Sciences Corporation To Chem-Nuclear Services. Inc. Barnwell, S', for Burial Radionuclide  % of Total (Estimate) Curies l H-3 0.500 % 7.91 E. 05

! Fe-55 80.864 % 1.28E 02 co60 8.781 % 1.39E-03 Ni 63 1.074 % 1.70E-04

[

Cs-137 8.781 % 1.39E-03 Total 1.58E-02 Millstone Unit 1 Page 4 of 6

. _ _ _ - _ - . . - . _ . . _ . . _ _ . _ _ . . . . . _ _ _ _ _ . _ _ . . ~ . _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ . .

j i

l

2. Estimata of mrjor nuclida composition (by type of wiste) '

c. Miscellaneous Oil, Oily Sludge. I From Epstone Nucteer Power Station To Scientdic Ecology Group Ook Ridge. TN for Super-Compaction. Incinersten. etc. l Radionuclide  % of Total (Estimate) Curies H-3 1.137% 1.26E-04  !

c-14 7.008 % 7.77E-04 l l Mn-54 0.011 % 1.18E-06

' j co-57 <0.01 % 2.82E-07 i

! co-58 0.006 % 6.29E-07 '

4 co-60 7.623% 8.45E-04 .

Ni 63 83.209 % 9.23E-03 l zn-65 <0.01 % 1.46E-07 Nb-95 <0.01 % 7.36E-11 l

. A9-110m 0.013 % 1.42E-06 '

sb-125 0.079 % 8.71 E-06

cs134 0.055 % 6.13E-06 Cs-137 0.819 % 9.08E-05  !

Ra-226 <0.01 % 1.81 E-07

Th-228 0.034 % 3.80E-06 l l Th-234 <0.01 % 5.60E-08 '

i Total 1.11 E-02  :

l

] 2. Estimate of major nuclide composition (by type of waste)

c. Miscellaneous Oil, Oily Sludge.

From Scientific Ecology Group To Chem-Nuclear Services, Inc. Bernwell. SC for Burial f

1 Radionuclide  % of Total (Estimate) Curies H-3 7.179 % 1.13E+00 3

c-14 <0.01 % 1.36E-04

) Mn-54 2.154 % 3.40E-01 1 Fe-55 74.937 % 1.18E+01 l co-60 13.854 % 2.19E+00 1 Ni63 1.184 % 1.87E-01

! Zn-65 0.516 % 8.16E-02 sr-90 <0.01 % 8.86E-04

, cs-137 0.045 % 7.07E-03

Pu-238 <0.01 % 5.20E-04 i Pu-239 <0.01 % 2.35E-04 l Am-241 <0.01 % 8.32E-04

} Pu 241 0.110 % 1.74E-02 1 cm-242 <0.01 % 6.90E-06 Pu-242 <0.01 % 1.80E-06 l cm-244 <0.01 % 8.28E-04 Total 1.58E+01 l

Millstone Unit 1 Page 5 of 6

_ - _ _ _ _ _ _ . ._________...._m .. _ _ . _ _ . - . _ . _ . . _- . _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ . _ . _ .

1

2. Estimita of maior nuclida composition (by type of waste) i d. Mixed Waste l

, - From Mustone Nucieer Power Station To Divers (ed Scient(c Servces Inc. Ook Rusge. TN incineration. l l

Radionuclide  % of Total (Estimate) Curies  !

! H-3 99.489 % 1.45E-03 l l Fe-55 <0.01% 6.77E-08 i i co40 <0.01 % 2.17E-08 3 Ni 63 <0.01 % 8.79E-09 j 3 Zn-65 <0.01 % 2.79E-08  ;

j cs-134 0.098 % 1.43E-06 l j cs137 0.404 % 5.90E-06 l 1

Total 1.46E 03 l

i i

j 1 l

l I

i l I i .

i j

I a

l 1

i s

a i

i 1

Millstone Unit 1 Page 6 of 6

Tcbla 2.1-5 S: lid W20ts and irrsdictsd C:mpensnt Shipm:nta l Millstone Unit 2 l January 1,1996 through December 31,1996

1. Type of Waste )

a Spent resins, filter sludges, evaporator bottoms, etc.

Disposition Units Annual Totals Est. Total Error % i From Mllstone Nuclear Power Station To Chem Nuclear Sennces, Inc. - m 6.81 E+00 l earnwell. Sc Cl 6.69E+01 25%

From Mllstone Nuclear Power Staten To Scientarc Ecology Group - Ook 3 m 2.21 E+01 Rdge. TN Ci 6.7 tie-03 25%

From SEG to Chem-Nuclear Services. Inc.- Barnwell, Sc 3 m 1.80E+01 Ci 6.76E-03 25%

b Dry compressible waste, contaminated equipment, etc.

Disposition Units Annual Totals Est. Total Error %

From Mllstone Nuclear Power Station To Chem-Nuclear Services, Inc. - 3 m 4.23E+00 sarnwell. Sc Ci 5.30E+00 25%

From Milstone Nuclear Power Station To Scientife Ecology Group Oak m 093E+01 Rdge. TN Ci 1.36E-01 25%

From Millstone Nuclear Power Staten To F.W. Hake Associates m 5.43E+01 Memphis. TN Cl 1.93E-01 25 %

From Mdistone Nuclear Power Staten To Manufactunng Sciences Corp. 3 m 1.27E+01 Oak Ridge. TN Ci 4.87E-03 25%

From SEG to Chem-Nuclear Servces, Inc.- Barnwell, Sc m3 9.48E+00 Ci 1.96E-01 25%

c Miscellaneous - Oil, Oily Sludge Disposition Units Annual Totals Est. Total Error %

From Milstone Nuclear Power Staten To Scientire Ecology Group Oak m3 8.41 E+00 Ridge. TN Ci

• 3.52E+00 , 25%

From SEG to chem-Nuclear Servces, Inc Barnwell, Sc m3 6.76E-01 Ci 8.51 E-01 25%

d Mixed Waste Disposition Units Annual Totals Est. Total Error %

From Mailstone Nuclear Power Staten To Diverstred Scientife Sennees m 1.08E+00 lac Oak Rdge. TN Ci 3.01 E-03 25%

Millstone Unit 2 Page 1 of 6

2. Estimat3 of major nuclid3 composition (by type of wasts)

a. Spent rIsins, filttr sludg:s, cvaporator bottoms, etc.

Frorn Menstone Nuclear Power Staten To Chem-Nuclear Services. Inc. . Barnwell, Sc for Burial Radionuclide  % of Total (Esimate) Curies H-3 <0.01 % 1.95E-03 c-14 0.381 % 2.55E-01 Mn-54 0.022 % 1.46E-02 Fe-55 22.933 % 1.53E+01 Co 57 <0.01 % 5.84E-03 co-60 18.892 % 1.26E+0i NiS3 44.240 % 2.96E+01 Sr-89 <0.01 % 1.34E-03 Sr-90 0.168% 1.13E-01 cs-134 0.325'4 2.17E-01 Cs-137 13.009 % 8.70E+00 Pu-238 <0.01 % 1.87E-04 Pu-239 <0.01 % 9.45E-05 Am-241 < 0.01'4 1.69E-04 Pu-241 0.014'4 9.54E-03 cm-242 < 0.01 '4 7.26E-05 cm-244 <0.01'4 4.34E-04 Total 6.69E+01

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, filter sluoges, evaporator bottoms, etc.

From Millstone Nuclear Power Staten To ScentMc Ecology Group Oak Radge. TN for Sur.sr Cramoseton, incineration. etc.

Radionuclide  % of Total (Esimate) Curies c-14 85.910% 5.81 E-03 Mn-s4 0.460% 3.11 E-05 cm 3.357 % 2.27E-04 Sr-90 8.487 % 5.74E-04 cs-134 0.158 % 1.07E-05 Cs-137 1.628 % 1.10E-04 Total 6.76E-03

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

From ScientMc Ecology Group To Chem-Nuclear Services, Inc. - Bamwell, sC for Bonal Radionuclide  % of Total (Esimate) Curies c-14 85.914 % 5.81 E-03 Mn-54 0.457 % 3.09E-05 co.60 3.356 % 2.27E-04 Sr-90 8.490 % 5.74E-04 cs-134 0.155'4 1.05E-05 Cs-137 1.627 % 1.10E-04 Total 6.76E-03 i l

1 Millstone Unit 2 Page 2 of 6 1

m . _ . . _ _ . _ . . . . _ _ _ _ _ _ _ . . . _ - __ _ _ . _ . _ _ _ . .

2". Estimat1 of major nuclida composition (by type of waste)

b. Dry compr:ssibl3 wasta, contaminated equipmsnt, etc.

From Mlistone Nuclear Power Staten To Chem-Nuclear Services. Inc.- Barnwell, Sc for Bur 6al

[

i* Radionuclide Curies

% of Total (Esimate)

H-3 0.047 % 2.50E-03 4

c-14 0.282 % 1.49E-02 Mn-54 2.692 % 1.43E-01 Fe-55 51.623 % 2.74E+00 co-57 0.033 % 1.77E-03 co-58 0.860 % 4.56E-02

,, coso 20.415% 108E+00 l NiS3 12.038% 6.38E-01 sr 90 0.011 % 6.02E-04 Ag-110m 0.166 % 8.78E-03 sn-113 0.003 % 1.49E-04 sb-125 0.394 % 2.09E-02

, cs-134 1.954 % 1.04E-01 Cs-137 9.389 % 4.98E-01 Hf 181 <0.01 % 3.40E 11 Pu-238 <0.01 % 6.64E-05 j Pu-239 <0.01 % 3.92E-05

^

Am-241 <0.01 % 5.35E-05 Pu-241 0.087 % 4.59E-03 j cm-242 <0.01 % 6.10E-06 l Pu-242 <0.01 % 2.97E-07 1 cm-244 <0.01 % 1.13E-04 Total 5.30E+00 d

2. Estim_ ate of major nuclide composition (by type of waste)

b. Dry compressible waste, contamiriated equipment, etc.

From Mdistone Nuclear Power Station To Scientific Ecology Group - Oak Radge. TN for Super-Compaction, incinerat.on, etc.

Radionuclide  % of Total (Esimate) Curies H-3 2.125% 2.88E-03 c-14 1.941 % 2.63E-03 Mn-54 2.055 % 2.79E-03 Fe-55 49.381 % 6.69E-02 co-57 0.041 % 5.61 E-05 co-58 1.375 % 1.86E-03 cm 16.000 % 2.17E-02 Ni 63 12.717 % 1.72E 02 St-90 <0.01 % 7.52E-06 Nb-95 <0.01 % 3.96E-06 Ag-110m 0.202 % 2.74E-04 sb-125 0.056 % 7.62E-05 cs-134 2.404 % 3.26E-03 Cs-137 11.622 % 1.58E-02 Pu-238 <0.01 % 1.24E-06 Am-241 <0.01 % 8.09E-07 Pu-241 0.067 % 9.14E05 cm-242 <0.01 % 3.30E-07 cm-244 <0.01 % 1.50E-06 Total 1.36E-01 Millstone Unit 2 Page 3 of 6

. 2. Estimtte of major nuclids composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc.

, From Wisione Nuclear Power Station To PW Hake & Accociates. Mornphis, TN Radionuclide  % of Total (Esimate) Curies H-3 0.058 % 1.12E-04 c-14 0.228 % 4.41E-04 Mn-54 3.798 % 7.34E-03 Fe-55 56.510 % 1.09E-01 co-58 9.463 % 1.83E-02 cm 11.337 % 2.19E-02 Ni 63 6.858 % 1.32E-02 cs-134 2.170 % 4.19E-03 Cs-137 9.577 % 1.85E-02 Total 1.93E-01

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc.

Frorn Millstone Nuclear Power Station To Manufactunng Sciences Corporation - Ook Radge, TN for Placement Packaging Radionuclide  % of Total (Esimate) Curies H-3 6.714 % 3.27E 04 c-14 3.921 % 1.91 E-04 Fe-55 43.936 % 2.14E-03 co-60 36.956 % 1.80E-03 Ni 63 6.611 % 3.22E-04 Cs 137 , 1.862 % 9.07E-05 Total 4.87E-03 Millstone Unit 2 Page 4 of 6

2. Estimits of major nuclide composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc.

From Scentdic Ecology Group To Chem-Nuclear Sennees. Inc. - Barnwell. Sc for Burial Radionuclide '4 of Total (Esimate) Curies H-3 1.792 % 3.51 E-03 Be-7 0.050 % 9.74E-05 c-14 0.710 % 1.39E-03 cr 51 0.050 % 9.76E-05 Mn-54 3.001'4 5.88E-03 I Fe-55 61.679 % 1.21 E-01 l Co-57 0.024 % 4.80E-05 co-58 1.433 % 2.81 E-03 co40 12.726 % 2.50E-02 Ni 63 6.966 % 1.37E-02 zn-65 2.621 % 5.14E-03 Sr-90 <0.01 % 3.89E-06 l zr-95 < 0.01 '4 3.35E-06 i Ag-110m 0.127 % 2.4BE-04 l sb-125 0.087 % 1.71 E-04 cs-134 1.521 % 2.98E-03 Cs-137 7.178 % 1.41 E-02 Pu-238 < 0.01'4 7.81 E-07 Pu-239 < 0.01 '4 3.77E-07 Am-241 <0.01 % 4.88E-07 Pu-241 0.030 % 5.83E-05 cm-242 <0.01 % 1.53E-07 cm-244 <0.01 % 9.06E-07 Total 1.96E-01

2. Estimate of major nuclide composition (by type of waste)

c. Miscellaneous Oil, Oily Sludge.

From Millstone Nuclear Power Station To Scientific Ecology Group - Oak Radge. TN for Super-Compaction. Incineraten, etc.

Radionuclide  % cf Total (Esimate) Curies H-3 <0.01 % 2.65E-04 c-14 3.427 % 1.21 E-01 Fe-55 8.541'4 3.01 E-01 co-60 22.043% 7.77E-01 Ni 63 60.133% 2.12E+00 Sr-90 0.024 % 8.59E-04 Nb-95 <0.01 % 7.36E-11 Ag-110m <0.01 % 1.42E-06 sb-125 0.295 % 1.04E-02 cs-134 0.641 % 2.26E-02 CS-137 4.571'4 1.61 E-01 Ta-182 <0.01 % 1.50E-09 Ra-226 <0.01 % 1.78E-07 Th-228 <0.01 % 3.80E-06 Th-234 <0.01 % 5.58E-08 Pu-238 < 0.01'4 1.15E-04 Pu-239 <0.01 % 1.88E-04 Am-241 0.011 % 3.86E-04 Pu-241 0.292 % 1.03E-02 cm-242 < 0.01'4 1.91 E-06 cm-244 < 0.01 '4 1.80E-04 Total 3.52E+00 Millstone Unit 2

2. Estimate of major nuclide composition (by type of waste)

"rge 5 of 6

c. Miscellaneous Oil, Oily Sludge.

_ . _ _ . . ..___._..____m_ _ _ _ _ _ _ . _ _ _ . . . _ . _ _ . = - _ _ _ _ _ , _ _ . . . . _ _ . _ _ _ . _ _ _ _ , _ . _ - _ _ _ _ . _ _ _ . .

From Scientire Ecology Group To Chern. Nuclear Serwces. Inc. - Barnwell. SC for Buriti Radionuclide  % of Total (Esimate) Curies H-3 4.394 % 3.74E-02

~

c-14 4.131 % 3.52E-02 cr 51 21.573 % 1.84E-01 Fe-55 0.648 % 5.51 E-03 Co-57 8.368 % 7.12E-02 co-58 0.042 % 3.57E-04 Fe-59 0.286 % 2.44E-03 Ni 63 58.439 % 4.97E-01 Sr-90 <0.01 % 5.39E-05 zr-95 0.100 % 8.48E-04 Ag-110m 0.270 % 2.30E-03 sb-124 0.043 % 3.63E-04 sb-125 0.389 % 3.31 E-03 cs-134 0.125% 1.06E-03 Cs-137 1.185% 1.01 E-02 Pu-241 <0.01 % 2.50E-06 Total 8.51 E-01

2. Estimate of major nuclide composition (by type of waste)

d. Mixed Waste From IMistone Nuclear Power Station To Deverstres Scientdic Serwces Inc. - Ook Radge. TN incineraten.

Radionuclide  % of Total (Esimate) Curies H-3 99.978 % , 3.01 E-03 Fe-55 0.014 % 4.06E-07 co-60 <0.01 % 7.38E-08 Ni 63 <0.01 % 3.31 E-08 Cs-137 <0.01 % 1.41E 07 Hf-181 <0.01 % 6.29E-09 Total 3.01E-03 i

\

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Millstone Unit 2 Page 6 of 6

Tcbla 2.1-5 Solid Waste and Irradiated Component Shipments Millstone Unit 3 I January 1,1996 through December 31,19%

1

1. Type of Waste 4

~

l a Spent resins, filter sludges, evaporator bottoms, etc. l Disposition Units Annual Totals Est. Total Error %

1 3

From Millstone Nuclear Power Staten To Chem-Nuclear Sorvces. Inc. - m 1.89E+01 samweii Sc Ci 4.59E+02 25% i From Millstone Nuclear Power Staten To Scientife Ecology Group Oak m 6.08E+00 Ridge. TN Cl 1.36E-04 25%

j i

From SEG to Chem-Nuclear Servces. Inc - Bamwell. Sc m3 1.16E+01 Ci 1.52E+01 25%

i i b Dry compressible waste, contaminated equipment, etc.

I Disposition Units Annual Totals Est. Total

Error %  ;

m3 l, From Millstone Nuclear Power Staten To Chem-Nuclear Servces. Inc

• 9.21 E+00

sarnweii. Sc Ci 3.98E+01 25%

j From Millstone Nuclear Power Staten To Scientirc Ecology Group- Oak m3 4.39E+01 Rdge. TN Ci 2.88E-01 25%

From Mellstone Nuclear Power Staten To F W. Haka Associates m 3.62E+01 Memphis. TN Ci 1.93E-01  %

{

From SEG lo Chem-Nuclear Servces. inc Barnwell. Sc m3 4.97E+00 Ci 3.11 E-01 25%

c Miscellarieous - Oil, Oily Sludge l

Disposition Units Annual Totals Est. Total Error %

From Millstone Nuclear Power Staten To Scientife Ecology Group - Oak m3 2.56E+00 Rdge. TN Ci 1.14E-02 25%

From SEG to Chem-Nuclear Servces, Inc Bamwell. Sc m3 3.25E+00 Ci 4.68E+r'0 25%

d Mixed Waste Disposition Units Annual Totals Est. Total Error %

From Millstone Nuclear Power Staten To Diversified Scienhfc Servces m 9.85E-01 ine Oak Ridge. TN Ci 1.32E-03 25%

Millstone Unit 3 Page 1 of 7

_ - . . - - _ . _ _ - _. ._-. .._._ - --- . . . . . . - . _ . _ - _ ~.

d

2. Estimat3 of major nuclids composition (by type of wasts)

a. Spent resins, filter sludges, evaporator bottoms, etc.

. From ullstone Nuclear Power Station To Chem-Nuclear Serwoes. Inc. - Samwell, SC for Buriel

Radiortuclide  % of Total (Esimate) Curies H-3 <0.01% 2.38E-02 c-14 0.018 % 8.11 E-02 Mn-54 13.958 % 6.41 E+01 Fe-55 11.409% 5.24E+01

, Co-57 0.260 % 1.19E+00 co-58 10.340% 4.75E+01 co40 16.812 % 7.72E+01

Ni 63 34.505 % 1.58E+02 zn-65 0.107 % 4.92E-01 sr-89 <0.01 % 3.76E-02 sr-90 0.049 % 2.26E-01 Nb-95 <0.01 % 2.94E-03 Ag-110m <0.01 % 3.50E 02 sn-113 <0.01 % 3.42E-02 sb 125 0.386 % 1.77E+00 cs-134 5.867 % 2.69E+01 Cs-137 6.250 % 2.87E+01 Total 4.59E+02

2. Estimate of major nuclide composition (by type of wast 3) l a. Spent resins, filter sludges, evaporator bottoms, etc.

From Milstone Nuclear Power Station To Scientific Ecology Group - Ook Radge. TN for Super-Compaction. Incineration. etc.

Radionuclide  % of Total (Esimate) Curies c-14 85.756 % 1.17E-04 Mn-54 0.459 % 6.26E-07 '

j co-so 3.391 % 4.63E-06 sr 90 8.502 % 1.16E-05 cs-134 0.158 % 2.15E 07 d

Cs-137 1.735 % 2.37E 06

Total 1.36E-04 i

I 4

l l

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Millstone Unit 3 Page 2 of 7 4

e ,

2. Estimats of mijor nuclide composition (by type of waste)

. a. Spent resins, filter sludges, evaporator bottoms, etc.

, From Scentific Ecology Group To Chem-Nuclear Services, Inc. Barnwell. SC for Burial Radionuclide  % of Total (Esimate) Curies c-14 0.132 % 2.00E-02 cr-51 31.811 % 4.83E+00 Fe-55 3.474 % 5.27E-01 co-57 11.791 % 1.79E+00 co-sa 0.143 % 2.17E-02 Fe-59 0.293 % 4.45E-02 Ni S3 51.514 % 7.82E+00 zn-65 0.431 % 6.54E-02 sr-90 0.025 % 3.84E-03 Nb-95 <0.01 % 6.48E-04 zr-95 <0.01 % 4.56E-05 sn-113 0.013 % 2.00E-03 sb-125 0.358 % 5.44E-02 cs-134 <0.01 % 2.11 E-07 Cs-137 <0.01 % 2.22E-06 Pu-238 <0.01 % 2.99E-05 Pu-239 <0.01 % 1.25E-05 Am-241 <0.01 % 8.90E-06 Pu-241 <0.01 % 1.38E-03 cm-242 <0.01 % 8.10E-06 Pu-242 <0.01 % 1.00E-07 cm-244 <0.01 % 4.60E-05 Total 1.52E+01 i

Millstone Unit 3 Page 3 of 7

i l

2. Estimata of major nuclide composition (by type of waste)

- b. Dry compressible waste, contaminated equipment, etc.

. From MDstone Nuclear Power Staten To Chem-Nuclear Servees,Inc. Bernwell. SC for Burial Radionuclide  % of Total (Esimate) Curies l H-3 0.025 % 1.01 E-02 c-14 0.099 % 3.95E-02 l cr-51 <0.01 % 2.07E-03 Mn-54 2.248 % 8.95E-01 1 Fe-55 68.982 % 2.75E+01 Co-57 0.031 % 1.23E-02 co-58 0.209 %

)

8.31 E-02 Fe-59 <0.01 % 1.46E-07 cuo 13.163% 5.24E+00 Ni 63 11.606'4 4.62E+00  ;

zn-65 0.174 % 6.92E-02 i sr-89 <0.01 % 8.32E-09 Sr-90 <0.01 % 1.81 E-03

)

Nt>-95 <0.01 % 2.84E-08 l Zr-95 <0.01 % 7.58E-05 I Ru-103 <0.01 % 5.09E-10 l Ag-110m 0.105% 4.17E-02 sn-113 <0.01 % 1.17E-03 sb-125 0.455'4 1.81 E-01 cs-134 0.464 % 1.85E-01 Cs 137 2.375 % 9.45E-01 co-144 <0.01 % 1.73E-05 Hf-181 < 0.01'4 9.83E-09 Pu-238 < 0.01 '4 2.73E-04 Pu-239 <0.01'4 1.48E-04 Am-241 < 0.01'4 1.65E-04 Pu-241 <0.01 % 1.96E-02 cm-242 <0.01 % 4.63E-05 Pu-242 < 0.01'4 8.27E-07 cm 244 <0.01 % 5.02E-04 Total 3.98E+01 i

Millstone Unit 3 Page 4 of 7

2. Estimate of major nuclids composition (by type of waste)

b. Dry compressible waste, contaminated equipment, etc.

From Wistone Nuclear Power Staten To Scent (c Ecology Group Ook Radge, TN ke Super-Compacten. Incmeraten, etc.

Radionuclide  % of Total (Esimate) Curies H-3 5.569 % 1.60E-02 c-14 0.913 % 2.63E-03 Mn-54 3.357 % 9.68E-03 Fe-55 62.288% 1.80E-01 Co-57 0.080 % 2.30E-04 co-58 2.007 % 5.79E-03 coe 12.335 % 3.55E-02 Ni 63 12.222 % 3.52E-02 sr-90 <0.01 % 1.26E-05 Nb-95 <0.01 % 1.59E-05 Ag-110m 0.424 % 1.22E-03 sb 125 0.061 % 1.77E-04 cs-134 0.125% 3.61 E-04 Cs-137 0.524'4 1.51 E-03 Pu-238 < 0.01'4 3.15E-06 Pu-239 <0.01 % 1.44E-06 Am-241 <0.01'4 1.91 E-06 l Pu-241 0.081 % 2.32E-04 l cm-242 <0.01 % 5.73E-07 I Pu-242 <0.01 % 0.00E+00 l cm-244 <0.01 % 3.56E-06 lotal 2.88E-01

2. Estimate of major nuclide composition (by type of waste) l

b. Dry compressible waste, contaminated equipment, etc.

From Wistone Nuclear Power Staten To FW Hake & Accociates. Memphis. TN Radionuclide  % of Total (Esimate) Curies H-3 0.043 % 8.38E-05 c-14 0.228 % 4.40E-04 Mn-54 3.792 % 7.32E-03 Fe-55 56.580 % 1.09E-01 co-58 9.448% 1.82E-02 co.so 11.318 % 2.19E-02 Ni 63 6.866 % 1.33E-02 cs-134 2.164 % 4.18E-03 Cs-137 9.560 % 1.85E-02 Total 1.93E-01 I

l

)

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Millstone Unit 3 Page 5 of 7 l

. e

2. Estimate of mijor nuclida composition (by type of wasta) 1

, : b. Dry compressible waste, contaminated equipment, etc.

8 From Scientire Ecology Group To Chem-Nuclear Services,Inc. Samwen, Se for Bunal Radionuclide  % of Total (Esimate) Curies H-3 2.644 % 8.21 E-03 Be-7 <0.01 % 2.78E-05 C-14 0.920 % 2.86E-03

Cr 51 0.020 % 6.13E-05 i Mn-54 3.376 % 1.05E-02 Fe-55 65.037 % 2.02E-01 Co-57 0.041 % 1.26E-04 Co-58 1.175 % 3.65E-03 Co-60 12.042 % 3.74E-02 Ni-63 8.355 % 2.60E-02 Zn-65 1.928 % 5.99E-03 Sr-90 <0.01% 1.03E-05 Nb-95 <0.01 % 8.82E-06 Ag-110m 0.210 % 6.54E-04 Sb-125 0.069 % 2.14E-04 Cs-134 0.738 % 2.29E-03 Cs-137 3.379 % 1.05E-02 Pu-238 <0.01% 2.0BE-06 Pu-239 <0.01 % 9.92E-07 Am-241 <0.01 % 1.29E-06 Pu-241 0.049 % 1.54E-04 Cm-242 <0.01 % 4.04E-07 Cm-244 <0.01 % 2.39E-06 Total 3.11 E-01

2. Estimate of major nuclide composition (by type of waste)

c. Miscellaneous Oil, Oily Sludge.

From Mustone Nuclear Power Station To Scientire Ecology Group Ook Radge, TN for Super-Compacton, incineration. etc.

Radionuclide  % of Total (Estimate) Curies I H-3 1.105 % 1.26E-04 c-14 7.013 % 8.01 E-04 Mn-54 0.011 % 1.22E-06 2.90E-07 Co-57 <0.01 %

co-58 <0.01 % 6.48E-07 cm 7.620 % 8.70E-04 '

Ni S3 83.242 % 9.51 E-03 Nb-95 <0.01 % 7.58E-11 Ag-110m 0.013 % 1.47E-06 sb.125 0.079 % 8.97E-06 cs 134 0.055 % 6.27E 06 Cs-137 0.819 % 9.35E-05 Ta-182 <0.01 % 1.53E-09 Ra-226 <0.01 % 1.78E-07 Th-228 0.034 % 3.91 E-06 Th-234 <0.01 % 5.74E-08 Total 1.14E-02 Millstone Unit 3 Page 6 of 7

o , '

2. Estimate of major nuclide composition (by type of waste)

c. Miscellaneous Oil, Oily Sludge.

O From Scent (c Ecology Group To Chem-Nuclear Services,Inc. Barnwell, SC for Bunal Radionuclide  % of Total (Estimate) Curies H-3 0.129% 6.05E-03 c-14 0.117 % 5.46E-03 Mn-54 1.772 % 8.29E-02 Fe-55 48.949% 2.29E+00 co-58 0.453 % 2.12E-02 co.60 19.858 % 9.29E-01 Ni 63 18.661 % 8.73E-01 St-90 0.050 % 2.34E-03 Zr-95 0.053% 2.46E-03 sb-125 1.436 % 6.72E-02 cs-134 1.238 % 5.79E-02 cs-137 7.182 % 3.36E-01 Pu-238 0.002 % 8.22E-05 Pu-239 0.000 % 4.00E-06 Pu-241 0.099 % 4.65E-03 Pu-242 0.000 % 7.70E-06 cm-244 0.001 % 6.69E-05 Total 4.68E+00

2. Estimate of major nuclide composition (by type o'iwaste)

d. Mixed Waste Frorn IMstone Nuclear Power Station To oivers(ed Scent (c Serices Inc. - Oak Redge, TN Incineraten.

Radionuclide  % of Total (Estimate) Curies H-3 99.303% 1.31 E-03 Fe-55 0.057 % 7.47E-07 co-so 0.018 % 2.32E-07 Ni 63 <0.01 % 9.22E-08 Cs-137 0.115 % 1.52E-06 Total 1.32E-03 Millstone Unit 3 Page 7 of 7

~__ _ _ _ _ . . _ _ _ _ _ _ . _ -

I 3.0 REMODCM Changes e e in 1996, there were no changes to the REMODCM.

4.0 Inoperable Effluent Monitors During the period January 1 through December 31, 1996, the following effluent monitors were inoperable for more than 30 consecutive days:  ;

t 4.1 Unit 1 Service Water Monitor Due to the shutdown mode cross tie of Reactor Building and Turbine Building Service Water, this monitor has been out of service since November 26,1996.

4.2 Unit 1 Liquid Radwaste Effluent Monitor Due to system design changes and instrument response time method determination, this monitor was inoperable June 7,1996 to April 1,1997. >

4.3 Unit 2 Steam Generator Blowdown Radiation Monitor (RM4262)

The Steam Generator Blowdown (SG BD) Radiation Monitor (RM) was inoperable from February 22 through December 31,1996 due to lack of flow while the plant was in Modes 5 (2/22/96- t 12/18/96) and 6 (12/18/96-12/31/96) even though there were no discharges du ing this period.

The current Technical Specification 3.3.3.9 (Amendment 186,3/27/95) requires the SGBD RM to be operable in " Modes 1-5 and Mode 6 when pathway is being used.. " Due to SGBD RM system configuration, SG flow through RM4262 is not feasible while in Mode 5. Currently there is a proposed change to this technical specification before the NRC to require the SGBD RM to be operable in " Modes 1-4 and Modes 5-6 when pathway is being used.. " If accepted, this change would eliminate inoperability declarations associated with the lack of flow for the SGBD RM in Mode 5. RM4262 is not excepted to be declared operable until Mode 4 is reached again during start-up.

4.4 Unit 3 Liquid Waste Effluent Monitor (3LWS-RE70)

Licensee Event Report 96-043-00 (11/27/96) discusses a technicalinoperability of the Unit 3 Liquid Waste Effluent Monitor due to a historical misinterpretation of Technical Specification requirements.

5.0 Errata Enclosed is an errata for Section 1.2.3 of the 1995 Annual Radioactive Effluent Report. The Unit 1 turbine shine dose should have read 2.6 instead of 2.0. The total dose should have read 2.7 instead of 2.1. The corrected total dose is no longer less that ten percent of the 25 mrem limit.

i* i I* 1.2.2 Liquid Effluents

, The LADTAP code performs calculations for the following pathways: fish, shellfish, algae, drinking water, irrigated food, shoreline activity, swimming, and boating. At Millstone, the algae, drinking water, and irrigated food pathways do not exist; and, thus, only the other pathways are included in the totals. Doses are calculated for the whole -

i body, skin, thyroid, GI-LLI, bone, liver, kidney, and lung. Calculations are performed

separately for adults, teenagers, and children.

, The off-site dose commitments from liquid effluents are presented in Table 1-2. These doses are the maximum doses observed.

1.2.3 Analysis of Results

$ The doses are well below the permissible levels and small in comparison to the dose

from natural background radiation. The statistical expectation of adverse health effects from the calculated radiation dose due to nuclear plant operations is essentially zero.

Refer to Table 1-3 for the annual effluent whole body airborne and liquid doses for the 4 maximum and average individuals and a quarititative comparison between the doses from nuclear plant operations and those doses from other sources such as naturally 1

occurring background radiation. Also provided are legally allowed 40CFR190 (Ref 8) levels to a real member of the public. Note that the maximum individual in Tables 1-1, i 1-2, and 1-3 is conservatively assumed to be a real member of the public.

Prior to its refuel outage, Unit 3 was operating with a degraded fuel rod. During refueling, this caused higher than normal primary side activity to be vented. This, in turn, resulted in a relatively higher second-quarter airborne thyroid dose for Millstone.

]

j For compliance with 40CFR190, any direct dose from the site must be added to the effluent dose to a real member of the public." At Millstone, the only potential direct l dose of significance would be from Unit i turbine shine and radwaste storage.

However, all radwaste storage during this year was well within storage critena that ensure the public dose would be less than 1 mrem. Hence, the direct dose would be

less than 1 mrem and inconsequential for 40CFR190 compliance. The Unit 1 turbine shine dose is 2.6 mrem to the maximum individual, who is assumed to be a lobsterman  ;

that frequents the water immediately outside the Unit 1 turbine building. Adding this }

dose to the 0.1 maximum whole body dose from effluents yields a total of 2.7 mrem, 3 which is less than the 25 mrom limit.

Errata l l