ML20137M622

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1996 Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters Including Annual Radiological Impact on Man
ML20137M622
Person / Time
Site: Yankee Rowe
Issue date: 12/31/1996
From: Kay J
YANKEE ATOMIC ELECTRIC CO.
To: Fairtile M
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-97-016, BYR-97-16, NUDOCS 9704080141
Download: ML20137M622 (48)
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YANKEEATOMICELECTRIC COMPANY "*fsr"N!3eO.

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W. 580 Main Street, Bolton, Massachusetts 01740-1398

.YANKEl:: .

1 March 28,1997 l BYR 97-016 l

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U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attention: Mr. Morton B. Fairtile Senior Project Manager Non-Power Reactors and Decommissioning Project i Directorate Division of Operating Reactors Ref:rences: (a) License No. DPR-3 (Docket No. 50-29)

Subject:

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

Dear Mr. Fairtile:

Enclosed are the tables that summarize the quantities of radioactive liquid and gaseous effluents and solid waste released from the Yankee Nuclear Power Station (YNPS) at Rowe, Massachusetts for the third and fourth quarters of 1996. The report also summarizes the estimated dose commitments from all radioactive liquids and gaseous efDuents released during ,

1996. The report is submitted in accordance with YNPS Defueled Technical Specification 6.8.2.b.

Ifyou have any questions, or require additional information, please' contact us.

Sincerely, YANKEE ATOMIC ELECTRIC COMPANY r

a' f J. A. Kay

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Principal Licensing Engineer y c: J. White, NRC Region I

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9704080141 961231  ! fn DR ADOCK 0500 9 gggggg T ,

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EFFLUENTAND WASTE DISPOSAL  :

SEMIANNUAL REPORT  ;

FOR THIRD AND FOURTH QUARTERS 1996 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN FOR 1996 i

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4 Yankee Atomic Electric Company Rowe, Massachusetts JMYINiFPtNT Sec 3r3147 i

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ERRATA -

= The second quarter liquid releases reported in Tables 2A and 2B of the Semiannual Report covering the first and second quarters of 1996 have been revised. The revised tables are provided in the following pages.

. The number of curies associated with the evaporator bottom solid waste shipments reported in Table 3 (Item A.1.c) of the Semiannual Report covering the third and fourth quarters of 1996 have been revised. The revised table is provided in the following pages.

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'i TABLE 2A (Errata)  !

t Yankee Atomic Elecinc Company. Rowe. Massachusetts l Efnuent and Waste Disposal Semiannual Report First and Second Quarters 1996 Llauid Efnuents - Summation of All Releases k

E Unit Quarter 1 . Quarter 2 E

A. Fission and Activation Products

1. Total Release (not including tritium, cases, alpha) Cl 9.74E-05 3.72E-04 t2.00E+01
2. Average D8uted Concentradon During Period pCi/ml 9.98E-11 3.95E-10  !
3. Percent of Appucable UmW  % 9.73E-05 1.09E-03 f

i B. Tritium l

1. TotalRelease Ci 6.73E-02 7.63E 02 *1.00E+01
2. Average DIuted Concentrabon During Period pCl/ml 6.90E-08 8.10E-08
3. Pqrcego' Applicable UmW -  % 2.30E-03 2.70E-03 i

C. Dissolved and Entrained Gases i

1. TotalReloose Ci <3.73E-04 <1.33E-03 t2.00E+01  !
2. Average D5uted Concentration During Period pCi/mi <3.82E-10 <1.41E-09 l
3. Percent of Appbcable Umit*3  % <1.91 E-04 <7.06E-04 ,

i D. Gross Alpha Radioactivity f

1. Total Release Ci 1.32E-05 <2.38E-07 23.60E+01 E. Volume of Waste Release (prior to dilution) liters 1.70E+05 5.79E+05 i3.00E+01 F. Volume of Dilution Water Used During Period liters 9.76E+08 9.42E+08 ti.50E+01 j l

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i (a) Cencontration imits speedied in 10CFR20, Appendix B, Table 11, Column 2 (ODCM Control 2.1). The percent i of applicable limit reported is bened on the overage diluted concentrabon during the period At no time did  !

!- any release exceed the concentrabon Bmit. l (b) Concentrabon limits for desolved and entrained noble gases is 2.00E-04 pCi/ml(ODCM Control 2.1). The ,

percent of applicable imit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentrabon limit. ,

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, 1 TABLE 2B (Errata) j Yankee Atomic Electne Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report i First and Second Quarters 1996 l Liould Effluents - Routina Releases l i f Continuous Mode Batch Mode

. Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 .

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l Strontium-89 Ci <9.63E-07 <5.99E-07 <5.98E-06 <1.40E-05 l Strontium-90 Cl <6.19E-07 2.15E-06 <2.72E-06 2.57E-07 Cesium-134 Ci 2.33E-07 4.42E-07 <1.27E-06 9.33E-08 1.01E-05 Cesium-137 - Cl 4.44E-06 5.95E-06 6.66E-06 i Cobalt-58 Ci <1.59E-07 <7.75E-08 <1.25F-06 -

<5.00-E06  !

t Cobalt-60 Cl 8.99E-08 7.93E-08 8.03E-06 2.95E-05

j. Iron-59 Ci <3.41 E-07 <1.72E-07 <2.40E-06 <9.97E-06 l

Zine-65 Ci <3.73E-07 <1.77E-07 <2.80E-0C <1.14E-05 ,

! i Manganese-54 Ci <1.75E-07 <8.31 E-08 <1.36E-06 <5.12E-06 l 2

Zirconium-Niobium-95 Ci <2.87E-07 <1.38E-07 <1.98E-06 <8.27E-06 Molybdenum-99 Ci <1.23E-06 <5.92E-07 <8.31E-06 <3.44E-05

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Cerium-144 Cl <1.13E-06 <7.42E-07 <6.42E-06 <2.48E-05 i i

Sher 110m Ci <1.98E-07 <1.06E-07 <1.24E-06 <4.48E-06  ;

i Antimony-124 Ci <1.91E-07 <1.09E-07 <1.18E-06 <4.32E-06 l

Carbon-14 Ci - - 7.79E-05 <5.56E-05 l

. Iron-55 Ci <8.26E-06 <1.01E-05 <2.45E-05 3.24E-04 Antimony-125 Ci <5.47E-07 <3.71 E-07 <3.14E-06 <1.19E-05 Unidentified Cl - - - -

Total for Period (above) Ci 4.76E-06 8.62E-06 9.26E-05 3.63E-04  !

Krypton-85 Ci <5.38E-05 <3.10E-05 <3.20E-04 <1.30E-03 i

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TABLE 3 (Errata)

(Sheet 1 of 2) 4 i

Yankee Atomic Electnc Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report  !

Third and Fourth Quarters 1996  !

Solid Waste and Irradiated Fuel Shloments  !

t. sOUD WASTE SHIPPED OFF8ITE FOR BURIAL OR DISPOSAL (not Irradiated fuel)  ;

i Unit

&mont ER W j

1. Type of Waste - Period Error, %  ;
s. Dry Active Weste: Class A Containers: steel box (101 m' 3.93e+01 2.50e01 -

ft'), steel Ener (177.5 ft') CI(Est.) 1.08e+00

b. Dry Aceve Waste: Class A Containers: (a) m' 5.37e+01 2 50e+01 i Ci(Est.) 2.55e-04 i
c. Evap. Bottoms: Class A Containers: steel drum (7.5 m' 5.95e+00 2 50e+01  !

ft') (b) C1(Est.) 5.27e-01 l

d. Filtem: Class C Containers: steel Ener (126 ft') (b) 2.5W01 l Ci st.) 4e l

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2. Estimate of Maior Nuclide Composition (by type of waste) >1%
a. Iron-55  % 6.44e+01 <

Cobalt 40  % 2.24e+01 Nickel 43  % 1.05e+01 l

b. Iron-55  % 0.50e+01 Cobalt 40  % 2.26e+01 1 Nickel 43  % 1.06e+01
c. Cobalt 40  % 3.82e+01 Nickel 43  % 3.13e+01 fron-55  % 1.61e+01 Cesium-137  % 1.20e+01 Cerium-144  % 1.60e+00
d. Iron-55  % 7.26e+01 Cobalt 40  % 1.69e+01 ,

N W=L83  % 9 50e+00 Jamemsm.wr see -V- sms7 I l

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NOTES  :

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1. Yankee Nuclear Power Station's last day at any power levelwas October 1,1991. The  !

facility is permanently shut down for future decommissioning. Due to ceased operations, short-lived nuclides have been deleted from the gaseous and liquid effluent tables. Their activity concentrations in the fuel inventory have decayed to zero values.

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TABLE OF CONTENTS  ;

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- 1. 0 I NTRO DUCTIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ,

2.0 METEORO LOGICAL DATA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3  ;

3.0 DOSE ASSESSMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4  ;

3.1 Doses From uquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4:  ;

3.2 . . Doses From Noble Gases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.3 Doses From lodine-131, Tritium, and Radionuclides in Particulate Form With Half-Uves Greater Than 8 Days . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1 4.0 R EFER E NCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 ,

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APPENDlX A Radioactive Uquid Effluent Monitoring i

instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 APPENDIX B Radioactive Gaseous Effluent Monitoring instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1 APPENDIX C Liquid Holdup Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-1 i

APPENDIX D Radiological Environmental Monitoring Program . . . . . . ..... D-1 l l

APPENDIX E Land Use Census . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-1 j i

APPENDIX F Process Control Progim (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . F-1 )

l APPENDIX G  !

Off-Site Dose Calculation Manual (ODCM) . . . . . . . . . . . . . . . . . G-1 APPENDlX H Radioactive Uquid, Gaseous, and Solid Waste Treatment i Syste m s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H- 1  ;

i APPENDIX l . Supplementallnformation .............................l-1 1 1

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LIST OF TABLES r

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1A Gaseous Effluents - Summation of All Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 i

1B Gaseous Effluents - Elevated Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 1C Gaseous Effluents - Ground Level Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 i 2A Liquid Effluents - Summation of All Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 i

2B . Liquid Effluents - Routine Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 l 3 Solid Waste and Irradiated Fuel Shipments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4 Maximum Off-Site Doses and Dose Commitments to Members of the P u blic . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 5 5 1995 Meteorological Data Joint Frequency Distribution . . . . . . . . . . . . . . . . . . . . . 16 i

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YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MASSACHUSETTS  !

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT THIRD AND FOURTH QUARTERS 1996. ]

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1.0 INTRODUCTION

Tables 1 through 3 list the recorded radioactive gaseous s,ad liquid effluents and solid waste,

, < respectively, with data summarized on a quarterly basis for the second six months of the year.

Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and -

gaseous effluents released during the year 1996. Table 5 provides the cumulative joint j frequency distributions of wind speed, wind direction, and atmospheric stability for 1996. ,

Radioactive effluents reported in the Emuent and Waste Disposal Semiannual Report covering

' the first six months of the year were used to determine the off-site doses for the first half of 1996.

4 As required by Control 7.2.b, dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the Yankee Nuclear Power i Station Off-Site Dose Calculation Manual (ODCM). These dose estimates were made using a  ;

Method il analysis as described in the ODCM. A Method ll analysis incorporates the

methodology of Regulatory Guide 1.109 (Reference 1) and actual measured meteorological data recorded during the reporting period. For gaseous releases, the meteorological conditions 4 concurrent with the time of release of radioactive materials (quarterly average) were used for determining the gaseous pathway doses. As required by Control 7.2.b, this report also shall ,

include an assessment of the radiation doses from radioactive effluents to member (s) of the i

public due to allowed recreational activities inside the site boundary during the year. However, a for this reporting period, no recreational activities inside the site boundary were permitted. As a l result, recreational activities are not addressed. The limited use of the Information Center on-site l l Is associated with educational activities as they pertain to the production of electricity and as l l such, are not included under Control 7.2.b. Assessment of radiation doses (including direct j

radiation) to the likely most exposed real member (s) of the public for the calendar year for the i purposes of demonstrating conformance with 40CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operations," also are required to be included in this report, if conditions indicated in Control 3.2 have been exceeded during the year. Since the ,

! . conditions indicated in the action statement under Control 3.2.s were not entered into during the year, no additional radiation dose assessments are required.

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All calculated dose estimates for this reporting period are well below the dose criteria of 10CFR Part 50, Appendix 1.- -

l Appendices A through H indicate the status of reportable items per the requirements of -

Controls 5.1, 5.2, Technical Specification 3.11.1.4, Controls 4.1,4.2, 2.0 (PCP), 7.2, and 7.3, respectively. Appendix l of this report provides supplementalinformation on effluent releases for i I

this reporting period.

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2.0 METEOROLOGICAL DATA Meteorological data was collected during the reporting period from the site's 200-foot meteorological tower, located approximately 180 meters north of the vapor container. The tower instrumentation is designed to meet the requirements of Regulatory Guide 1.23 (Reference 2) for meteorological monitoring. A summary of meteorological data recorded during 1996 is provided in Table 5 of this report.

The main release point for gases discharged from the plant is via the 150-foot primary vent stack, located between the vapor container and the primary auxiliary building. The primary vent stack is treated as a mixed mode elevated release point dependent upon windspeed, as described in Regulatory Guide 1.111 (Reference 3).

CHl/Q and D/O values were derived for all receptor points from the site meteorological record using a straight line airflow model. All dispersion and deposition factors have been calculated employing appropriate source configuration considerations and removal mechanism (e.g., dry deposition) described in Regulatory Guide 1.111 (Reference 3). Terrain elevations, including downwind valley flow corrections for the surrounding area, were factored into the calculation of CHl/Q and D/Q values at each receptor location.

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4 3.0 DOSE ASSESSMENT ,

3.1 Doses From Liquid Effluents  !

Control 3.1 limits total body (1.5 mrom per quarter and 3 mrom per year) and organ (5 mrom per quarter and 10 mrom per year) doses from liquid effluents to a member of the public to those specified in 10CFR Part 50,' Appendix 1. By implementing the requirements of 10CFR Part 50, l

Appendix 1, Control 3.1 assures that the release of radioactive material in liquid effluents will be {

- kept "as low as is reasonably achievable."

Exposure pathways that could exist as a result of liquid effluents are fish, direct exposure f from river shoreline sedimentation, milk and meat via animal ingestion of the Deerfield River  !

. water, and meat, milk, and vegetable pathways via crop irrigation with water withdrawn from the j Deerfield River. Drinking water and aquatic invertebrate pathways do not exist downriver of the  !

I Yankee plant at Rowe. The dose analysis for the liquid pathways assumes a dilution based on - t the monthly average flow at the Sherman Dam.

l The whole body and organ doses due to liquid effluents were determined by summing the l

contributions from all pathways. The whole body and organ doses to a member of the public j from liquid effluents are given in Table 4. The estimated quarterly and annual doses due to liquid effluents are well below the 10CFR Part 50, Appendix I dose criteria of Control 3.1.

3.2 Doses From Nobie Gases i

i Control 3.4 limits the gamma air (5 mrad per quarter and 10 mrad per year) and beta air (10 mrad per quarter and 20 mrad per year) doses from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10CFR Part 50, Appendix 1. By implementing the requirements of 10CFR Part 50, Appendix 1, Control 3.4 assures that the release of radioactive noble gases in gaseous emuents will be kept "as low as is j h reasonably achievable."

t if noble gases are determined to be present in effluent discharge, the dose estimates are l

! . calculated at the site boundary, nearest resident, nearest vegetable garden, and nearest milk j l animal in each of the sixteen principle compass directions, as well as the point of highest off-site

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ground level air concentrations of radioactive materials. Gamma and beta air doses, as well as l nomsmm e <sier y - sy-w -r

.. j whole body and skin doses, are calculated at each of the above locations. l f

To determine the beta contribution to the skin dose, a semi-infinite cloud model is utilized.

The whole body gamma dose is calculated using a finite cloud sector average model with a 3 Gaussian distribution of activity in the vertical plane. The gamma radiation received from the cloud at a point of interest is determined by integrating the contribution from a differential volume  ;

over the entire cloud, taking into account the geometry of the cloud, variation in concentration, I attonuation by the interaction of photons with matter in the path between the source and receptor l point, and scattering of radiation from material outside the direct path to the point of interest. No additional credit is taken for decay of radionuclides in transit to the receptor point. f i

The estimated quarteriy and annual gamma and beta air doses, as listed in Table 4, are zero  !

because there were no noble gas releases during 1996.

3.3 Doses From lodine-131. Tritium. and Radionuclides in Particulate Form With Half-Lives l Greater Than 8 Days Control 3.5 limits the organ doses to a member of the public from lodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called iodines and l particulates) in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10CFR Part 50, Appendix I (7.5 mrem per quarter and 15 mrem per year).

By implementing the requirements of 10CFR Part 50, Appendix 1, Control 3.5 assures that the releases of tritium, lodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable." It should be noted that due to the permanent shutdown of the plant (last power operation was in October 1991), the lodine-131 source term has decayed away and no longer has the potential to affect dose assessment.

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Exposure pathv/sys that could exist as a result of the release of particulates and tritium to the atmosphere include extemal irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat, and milk. Dose estimates were made at the site

. boundary, nearest resident, nearest vegetable garden, and nearest milk animalin each of the sixteen principle compass directions. The nearest resident, vegetable garden, and milk animal in each sector were identified by the most recent Land Use Census, as required by Control 4.2.

Doses were calculated for pathways which were determined by the field survey to actually exist.

i Conservatively, a vegetable garden was assumed to exist at each milk animal location.

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Furthermore, the meat pathway was assumed to exist at each milk animal location. Meat and milk animals were assumed to receive their entire intake from pasture during the second and third quarters. This assumption is conservative since most dairy operations utilize supplemental i

- feeding of animals when on pasture or actually restrict animals to full time silage feeding throughout the entire year. l The organ doses were determined after adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI tract, bones, liver, kidneys, thyroid,  :

lungs, and skin for adults, teenagers, children, and infants. The maximum estimated quarterly and annual organ doses due to tritium and particulates at any of the off-site receptor locations j are reported in Table 4. The doses to all other organs at all other locations for all other age groups are less than the doses reported in Table 4. The estimated organ doses from tritium and 4 particulates in gaseous effluents are well below the 10CFR Part 50, Appendix I dose criteria of Control 3.5.

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4.0 REFERENCES

1. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance With 10CFR Past 50,  ;

Appendix 1," U.S. Nuclear Regulatory Commission, Office of Standards Deve!opment, Revision 1, October 1977, i

2. Regulatory Guide 1.23, "On-Site Meteorological Programs (Safety Guide 23)," U.S.

Nuclear Regulatory Commission, Office of Standards Development, February 1972.  !

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3. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion i

of Gaseous Effluents in Routine Releases from Light - Water- Cooled Reactors," U.S.

Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October .

1977.

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l TABLE 1A Yankee Atomic Electnc Company. Rowe. Massachusetts  ;

Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1996 Gaseous Effluents - Summation of All Releases  ;

E Unit Quarter 3 Quarter 4 Eo, A. Fission and Activation Gases 1.= TotalRelease Ci 0.00e+00 0.00e+00 t2.50e+01

2. Average Release Rate for Period pCi/sec 0.00e+00 0.00e+00 3 Percent of Control Limit *  % 0.00e+00 0.00e+00
8. lodines

C. Particulates ,

1. Particulates with half 4ves > 8 days Ci <1.11e-05 <9.01e 06 i3.00e+01
2. Average release rate for period pCi/sec <1.41 e-06 <1.15e-06
3. Percent of Control UmW4  % 9.30e-02 8.00e-02
4. Gross Alpna Radioactivity Cl <3.24e.08 <3.73e-08 D. Tritium
1. Total Release Ci 9.34e-02 7.38e-02 i3.00e+01
2. Average Release Rate for Period pCi/sec 1.18e-02 9.39e-03
3. Percent of ControlUmW*  % NA NA (a) ODCM Control 3.4.a for gamme-air dose. Percent values for ODCM Control 3.4.5 for beta-air dose would be l approximately the same.

(b) lodine data have been deleted. These nuclides are no longer available for discharge.

(c) Per ODCM Control 3.5, the percentage of the limit is based on the combined dose contribubon from lodines, tritium, and parbculates with half tves greater than 8 days. Percentage of limits are calculated using ODCM ,

Method I dose equations.

(d) Per ODCM Control 3.5, percentage dose contribution from tritium is included in Part C.3.

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TABLE 18 1

Yankee Atomic Electric Comoany. Rowe. Massachusetts l Effluent and Waste Disposal Semiannual Rooort ]

. Third and Fourth Quarters 1996 i l Gaseous Effluents - Elevated Releases Con 6nuous Mode Batch Mode")

l l Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Krypton-85 Cl 0.00e+00 0.00e+00 - -

Total for Period Cl 0.00e+00 0.00e+00 -- -

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2. lodines*)
3. Particulates ,

, Strontum-89 Ci <2.65e-06 <7.16e-07 - -  !

Strondum-90 Ci <8.65e-07 <4.70e-07 - -

f Coelum-134 Ci <4.52e-07 <4.92e-07 - -

Cesium-137 Ci <5.96e-07 <6.15e-07 - -

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Zine-65 Ci <1.28e-06 <1.21 e-06 - -

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i Cobalt-58 Cl <4.98e-07 <5.09e47 - -

Cobalt 40 Ci <6.92e-07 <6.98e-07 - - I Zirconium-Niobium-95 Ci <8.65e-07 <9.07e-07 - -

Cerium-144 Ci <1.76e-06 <1.86e-06 - -

i l j An6 mony-124 Ci <4.48e-07 <4.86e-07 - -

l

, Manganese-54 Ci <5.30e-07 <5.46e-07 - -

Sliver-110m Ci <4.550 07 <5.02e-07 - -

Total for Period _

Ci <1.11e-05 <9.01 e-06 - -

(a) There are no longer any batch mode gaseous releases (b) lodine 131, lodine-133, and lodine 135 actMbes have been deleted. These nuclides are no longer available for discharge.

.. avumunun eec ms>er

i TABLE 1C Yankee Atomic Electric Cpmoanv. Rowe. Massachusetts ,

i Effluent and Waste Disposal Semiannual Report 4 Third and Fourth Quarters 1996 Gaseous Effluents - Ground Level Releases.

There were no routine measured ground level continuous or batch mode gaseous releases l i

during the third or fourth quarters of 1996.

4 6

2 1

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I 1

I a

TABLE 2A Yankee Atomic Elecinc Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1996 Liauid Effluents - Summation of All Releases i

E Unit Quarter 3"3 Quarter 4 E  %

A. Fission and Activation Products

1. Total Release (not including tritium, cases, alpha) Ci 0.00e+00 2.63e 06 22.00e+01
2. Average Duuted Concentration During Period pCi/mi 0.00e+00 2.21e-11
3. Percent of Applicable Umit'd  % 0.00e+00 7.59e 05 B. Tritium
1. Total Release Ci 0.00e+00 2.76e-03 ti.00e+01
2. Average Dauted Concentration During Period pCi/mi 0.00e+00 2.32e-08 f
3. Percent of Appbcable Umitid  % 0.00e+00 7.73e-04 C. Dissolved and Entrained Gases I 1. Total Release Ci . 0.00e+00 <4.78e-04 *2.00e+01
2. Average Diluted Concentration During Period pCi/ml 0.00e+00 <4.02e-09
3. Percent of Appilcable Umit*3  % 0.00e+00 <2.01 e-03 D. Gross Alpha Radioactivity
1. Total Release Ci 0.00e+00 <1.43e-07 t3.50e+01 L E. Volume of Waste Release (prior to dilution) liters 0.00e+00 3.49e+05 i3.00e+01 I

F. Volume of Dilution Water Used During Period liters 7.99e+07 1.19e+08 11.00e+01 4

2 (a) Concentration Emits speeded in 10CFR20, Appendoc B. Table 11, Column 2 (ODCM Control 2.1). The percent ,

of applicable hmit reported is based on the average diluted concentration during the period. At no time did j any release exceed the concentration Smit. I (b) Concentration bmits for dissolved and entrained noble gases is 2.00E-04 pCi/ml(ODCM Control 2.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration En1 (c) There were no liquid discharges during the Third Quarter of 1996.

evemnerrun we wne

1 TABLE 2B 5 Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1996 .

Liauld Effluents - Routine Releases  !

)

Continuous Mode Batch Mode ]

)

Nucides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 4

Strontium-89 Cl 0.00e+00 <6.00e-06 0.00e+00 <8.14e-06 Strontium-90 Cl 0.00e+00 <3.10e-06 0.00e+00 <3.19e-06 Coelum-134 Ci 0.00e+00 <7.51e-07 0.00e+00 <7.64e47 Cesium-137 Cl 0.00e+00 9.40e-09 0.00e+00 1.39e-07 4

t Cobalt-58 Cl 0.00e+00 <8.33e-07 0.00e+00 <7.83e-07 Cobalt-60 Cl 0.00e+00 2.32e-06 0.00e+00 1.65e-07 fron-59 Ci 0.00e+00 <1.72e-06 0.00e+00 <1.62e-06 l Zine-65 Cl 0.00e+00 <1.87e-06 0.00e+00 <1.86e-06 ManDanese-54 . Ci 0.00e+00 <9.55e-07 0.00e+00 <8.50e-07 Zirconium-Niobium-95 Cl 0.00e+00 <1.41e46 0.00e+00 <1.46e-06 i

Molybdenum-99 Ci 0.00e+00 <6.07e-06 0.00e+00 <5.48e-06 '

Cerium-144 Cl 0.00e+00 <4.82e-06 0.00e+00 <4.66e-06 S8ver-110m Cl 0.00e+00 <7.68e-07 0.00e+00 <8.25e-07 I

i Antimony-124 Ci 0.00e+00 <7.33e-07 0.00e+00 <7.77e 07  :

l Carbon-14 Cl 0.00e+00 - 0.00e+00 <4.54e-06 Iron-55 Cl 0.00e+00 <4.64e-05 0.00e+00 <7.26e-05 1

Antimony-125 Ci 0.00e+00 <2.07e-06 0.00e+00 <2.20e46 Unidentrhed Cl 0.00e+00 - 0.00e+00 -

Total for Period (above) Ci 0.00e+00 2.33e-06 0.00e+00 3.04e 07 Krypton-85 Cl 0.00e+00 <2.38e-04 0.00e+00 <2.39e-04 ameammm esc smm

  • i TABLE 3 (Sheet 1 of 2)

Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1996 Solid Waste and Irradiated Fuel Shipments A. 80U0 WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

I 6-month Est. Total  ;

1. Type of Waste Unit Error, %

. Period .

a. Dry Active Waste: Class A Containers: steel box (101 m' 3.93e+01 2 50e+01 1 ft'), steelliner (177.5 ft') Ci(Est.) 1.08e+00 j 8
b. Dry Active Waste: Class A Containers: (a) m 5.37e+01 2'50e+01 i Ci(Est) 2.55e.04
c. Evap. Bottoms: Class A Containers: steel drum (7.5 m' 5.95e+00 2'50e+01 ft')(b) Cl(Est) 5.27+01 i d.
  • 2.50e+01 Filters: Class C Containers: steelliner (126 ft')(b) c;gE )  :
2. Estimate of Major Nuclide Composition (by type of waste) >1%
a. Iron-55  % 6.44e+01 Cobalt 40  % 2.24e+01  !

Nickel-63  % 1.05e+01

-b. Iron-55  % 6.50e+01 Cobalt 40  % 2.26e+01 Nickel 43  % 1.06e+01 f

c. Cobalt-60  % 3.82e+01 Nickel-63  % 3.13e+01 Iron-55  % 1.61e+01 Cesium-137  % 1.20e+01 Cerium-144  % 1.60e+00 l

r

d. Iron-55  % 7.26e+01  ;

Cobalt 40  % 1.69e+01 Nickel 43  % 9.50e+00 JWtsMYmENLNT Sec mm

r TABLE 3  :

(Sheet 2 of 2)

Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1996 Sohd Waste and irradiated Fuel Shloments

3. Solid Weste Disposition Number of Shloments Mode of Transoortabon Deshnation  :

4 truck Barnwel, SC 17 (c) truck Oak Ridge, TN 51 (a) truck Barnwet, SC B. IRRADIATED FUEL SHIPMENTS (Disposition): None (a) Partial shipments by the processor to disposal.

(b) Solidification agent is cement.

(c) Waste shipments to processors.

9 s me m s m ursee mis 7-2

TABLE 4 Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Disposal Semlannual Reoort 1EEf2 Maximum (*) Off-Site Doses and Dose Commitments to Members of the PublicN Source Unit ist Quarter 2nd Quarter 3rd Quarter 4th Quarter Year (*

1. Liquid Effluents Whole Body mrem 6.81 e-05(* 1.60e-04(* 0.00e+00'* 1.34e-0649 2.29e-04 Critical Organ mrem 1.45e-049 5.15e-04* 0.00e+00id 2.30e-065 6.62e-04
2. Airborne Effluents

' 1.50e-04* 9.49e-04 mrem 2.65e-04" 2.62e-04* 2.72e-04*

Pa e

" mrad 0.00e+00s 0.00e+00* 0.00e+00e 0.00e+00s o,00,+0g B Al

  • o,00,+0g mrad 0.00e+00* 0.00e+00e 0.00e+00* 0.00e+00s Gamma (a) " Maximum" means the largest fraction of corresponding 10 CFR Part 50, Appendix 1, dose design objective.

(b) The numbered footnotes indicate the location of the dose receptor, age group, and organ, where appropriate.

(c) " Maximum" dose for the year is the sum of tho maximum doses for each quarter. This results in a conservative yearly dose estimate, but sts within the imits of 10 CFR Part 50. .

(d) Adult (e) There were no liquid discharges during the third quarter.

(f) Bone of Chud (g) Uver of Chad (h) SW, WSW,1300 meters; #ver, lung, GI-LLI, and whole body of chid.

(1) SW, WSW,1300 meters; nyer, lddney, lung, GI-LU, thyroid, and whole body of chRd.

0) There were no noble gases released during the four quarters of 1996.

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TABLE 5 (Sheet 3 of 8)

Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report c- 1.991 Meteoroloaical Data Joint Freauency Distribution

c. 1se.e FT WIND DATA STABERY Ct. ASS C CUuBS FREQUENCY (PERCENT) = 1.22 WIND DIRECTION FROM SPEED (MPH) N. NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBI, TOTAL CAIM .0 0 0 0 0 0 0 0 0 0 0 0 0 o o 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0G (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 c-3 1 1 1 1 0 0 o o 0 0 0 0 0 0 1 0 0 5 (1) 1.04 1.04 1.04 1.04 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.04 .00 .00 5.21 (2) .o1 .01 .01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .o6 4-7 0 1 0 0 0 0 0 3 4 4 2 2 1 0 0 0 0 17 (1) .00 1.o4 .00 .00 .00 .00 .00 3.13 4.17 4.17 2.08 2.08 1.04 .00 .00 .00 .00 17.71 (2) .00 .01 .00 .00 .00 .00 .00 .04 .05 .05 .03 .o3 .01 .00 .00 .00 .00 .22 8-12 1 2 0 0 o o 0 2 0 10 22 25 2 0 o 1 0 65 (1) 1.04 2.08 .00 .00 .00 .00 .00 2.08 .00 10.42 22.92 26.04 2.08 .00 .00 1.04 .00 67.71 (2)- .01 .03 .00 .00 .00 .00 .00 .03 .00 .13 .28 .32 .03 .00 .00 .cl .00 .83 13-18 0 0 0 o o 0 0 o 1 0 1 6 1 0 0 0 0 9 (1) .00 .00 .00 .00 .00 .00 .00 .00 1.04 .00 1.04 6.25 1.04 .00 .00 .00 .00 9.38 (2) .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .o1 .o8 .o1 .00 .00 .00 .00 .11 15-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 .0C .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 o o 0 0 0 0 0 0 o o 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALI. SPEEDS 2 4 1 1 o o 0 5 5 14 25 33 4 0 1 1 0 96 (1) 2.08 4.17 1.04 1.04 .00 .00 .00 5.21 5.21 14.58 26.04 34.38 4.17 .00 1.04 1.04 .00 100.00

, (2) .03 .05 .01 .01 .00 .00 .00 .06 .06 .18 .32 .42 .05 .00 .01 .01 .00 1.22 (1).esRcszrr OF ALL GOOD OBSERVATIONS FOR TET* PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR TM.' PERIOD c =cAIm (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) svownevu.Tsee -l 8- war

TABLE 5 (Sheet 4 of 8)

Yankee Atomic Electric Comoany. Rowe. Massachusetts Effluent and Waste Disoosal Semiannual Reoort IEEE Meteoroloaical Data Joint Frecuency Distribution D. 1se.e FT WIND DATA STA81UTY class D CLASS FREQUENCY (PERCENT)= 47.78 WIND DIRECTION FRCM SPEED (MFH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW ,VRBL TOTAL CAIM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 57 135 60 25 17 20 15 18 19 20 31 30 23 22 20 28 0 540 (1) 1.52 3.59 1.60 .67 .45 .53 .40 .48 .51 .53 .83 .80 .61 .59 .53 .75 .00 14.38 (2) .73 1.72 .76 .32 .22 .25 .19 .23 .24 .25 .39 .38 .29 .28 .25 .36 .00 6.87 4-7 126 300 89 40 62 45 55 72 78 123 198 184 93 63 70 77 0 1675 (1) 3.35 7.99 2.37 1.06 1.65 1.20 1.46 1.92 2.08 3.27 5.27 4.90 2.48 1.68 1.86 2.05 .00 44.60 (2) 1.60 3.82 1.13 .51 .79 .57 .70 .92 .99 1.56 2.52 2.34 1.18 .80 .89 .98 .00 21.31 8-12 137 252 32 20 30 22 20 25 46 90 133 177 112 55 38 96 0 1285 (1) 3.65 6.71 .85 .53 .80 .59 .53 .67 1.22 2.40 3.54 4.71 2.98 1.46 1.01 2.56 .00 34.21 (2) 1.74 3.21 .41 .25 .38 .28 .25 .32 .59 1.14 1.69 2.25 1.42 .70 .48 1.22 .00 16.35 13-18 36 88 3 2 o 2 1 1 7 12 17 46 14 3 3 12 0 247 (1) .96 2.34 .08 .05 .00 .05 .03 .03 .19 .32 .45 1.22 .37 .08 .08 .32 .00 6.58 (2) .46 1.12 .04 .03 .00 .03 .01 .01 .09 .15 .22 .59 .18 .04 .04 .25 .00 3.14 19-24 0 7 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 9 (1) .Ci .19 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .00 .00 .00 .00 .24 (2) .00 .09 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 00 .00 .00 .00 .00 11 cT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 356 782 174 87 109 89 91 116 150 245 379 439 242 143 131 213 0 3756 (1) 9.48 20.82 4.90 2.32 2.90 2.37 2.42 3.09 3.99 6.52 10.09 11.69 6.44 3.81 3.49 5.67 .00 100.00 (2) 4.53 9.95 2.34 1.11 1.39 1.13 1.16 1.48 1.91 3.12 4.82 5.58 3.08 1.82 1.67 2.71 .00 47.78 (1)= PERCENT OF ALL OOOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT CF ALL GOOD OBSERVATIONS FOR THIS PERIOD C =CAIM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) m mmunenc 3rw,7

TABLE 5 (Sheet 5 of 8)

Yankee Atomic Electric Comoanv. Rcwe. Massachusetts Effluent and Waste Disposal Samiannual Report 129.E Meteoroloaical Data Joint Freauency Distribution E. 199.8 FT WBdD DATA STABIUTY class E CLASS FREQUENCY (PERCENT) = 39.36 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW - NW NNW VRBL TOTAL CAIM o o o o o o o 0 o o o o o o o o o o (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 185 596 298 95 58 57 56 49 49 42 83 69 40 31 54 69 o 1831 (1) 5.98 19.26 9.63 3.07 1.87 1.84 1.81 1,58 1.58 1.36 2.68 2.23 1.29 1.00 1.75 2.23 .00 59.18 (2) 2.35 7.58 3.79 1.21 .74 .73 .71 .62 .62 .53 1.06 .88 .51 .29 .69 .88 .00 23.29 4-7 55 409 85 16 17 13 10 26 29 93 121 80 29 12 26 22 0 1o43 (1) 1.78 13.22 2.75 .52 .55 .42 .32 .84 .94 3.01 3.91 2.59 .94 .39 .84 .71 .00 33.71 (2) .70 5.20 1.08 .20 .22 .17 .13 .33 .37 1.18 1.54 1.02 .37 .15 .33 .28 .00 13.27 8-12 10 37 4 0 1 4 1 6 0 42 37 14 7 2 3 9 o 177 (1) .32 1.20 .13 .00 .o3 .13 .o3 .19 .00 1.36 1.20 .45 .23 .06 .10 .29 .00 5.72 (2) .13 .47 .05 .00 .01 .o5 .01 .08 .00 .53 .47 .18 .09 .o3 .04 .11 .00 2.25 13-18 4 5 1 2 o o o o 3 23 2 1 0 0 0 2 0 43 (1) .13 .16 .03 .o6 .00 .00 .00 .00 .10 .74 .06 .03 .00 .00 .00 .06 .00 1.39 (2) .o5 .os .o1 .03 .00 .00 .00 .00 .04 .29 .o3 .01 .00 .00 .00 .o3 .00 .55 19-24 o o o o o o o o o o o o o o o o o o (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .co crr 24 o o o o o o o o o o o o o o o o o o (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .co .oo .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00. .00 .00 ALL SPEEDS 254 1047 388 113 76 74 67 81 81 200 243 164 76 45 83 102 o 3094 (1) 8.21 33.84 12.54 3.65 2.46 2.39 2.17 2.62 2.62 6.46 7.15 5.3o 2.46 1.45 2.68 3.30 .00 100.00 (2) 3.23 13.32 4.94 1.44 .97 .94 .85 1.03 1.03 2.54 3.09 2.09 .97 .57 1.06 1.30 .00 39.36 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE '

(2)= PERCENT OF ALL 000D OBSERVATIONS FOR THIS PERIOD c =cAIM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) avtsuvuvrutr.sec O sems7

w. - . - - . _-- - . . . .- .- ... -

r TABLE 5 (Sheet 6 of 5)

Yankee Atomic Electnc Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report 1221 Meteorolooical Data Joint Freauency Distribution F. 199.0 FT WM) DATA STABOUTY CLASS F Ct. ASS FREQUENCY ', PERCENT) = 8.89 WIND DIRECTIOtt FROM SPEED (MPH) N NtfE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL 'lUTAL CAIM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 39 98 86 36 31 22 16 12 21 21 24 15 20 8 15 19 0 483 (1) 5.58 14.02 12.30 5.15 4.43 3.15 2.29 1.72 3.00 3.00 3.43 2.15 2.86 1.14 2.15 2.72 .00 69.10 (2) .50 1.25 1.09 .46 .39 .28 .20 .15 .27 .27 .31 .19 .25 .10 .19 .24 .00 6.14 4-7 19 46 18 4 3 0 3 11 12 14 37 14 7 4 6 7 0 205 (1) 2.72 6.58 2.58 .57 .43 .40 .43 1.57 1.72 2.00 5.29 2.00 1.00 .57 .86 1.00 .00 29.33 (2) .24 .59 .23 .05 .04 .00 .04 .14 .15 .18 .47 .18 .09 .05 .08 .09 .00 2.61 8-12 0 0 0 0 0 0 0 0 2 1 5 3 0 0 0 0 0 11 (1) .00 .00 .00 .00 .00 00 .00 .00 .29 .14 .72 .43 .00 .00 .00 .00 .00 1.57 ,

(2) .00 .00 .00 .00 .00 .00 .00 .00 .03 .01 .06 .04 .00 .00 .00 .00 .00 .14 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 '

.00 .00 .00 .00 .00 .00 ar 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 *

(2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .( D .00 .00 .00 .00 .00 alt SPEEDS 58 144 104 40 34 22 19 23 35 36 66 32 27 12 21 26 0 699 (1) 8.30 20.60 14.88 5.72 4.86 3.15 2.72 3.29 5.01 5.15 9.44 4.58 3.86 1.72 3.00 3.72 .00 100.00 (2) .74 1.83 1.32 .51 .43 .28 .24 .29 .45 .46 .84 .41 .34 .15 .27 .33 .00 8.89 1

(1)=PERCElfr OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCIINT OF ALL GOOD OBSERVATIONS FOR 11119 PERIOD c =ckim (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) i l

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.+

TABLE 5 (Sheet 7 of 8)

Yarkee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Disposal Gemuunnual Report  ;

1991

  • /,;.;earuloaical Data Joint Frecuency Distribution G. 190.0 FT WWdD DATA STABIUTY CLASS G CLASS FREQUENCY (PERCENT) = 2.36 WIND DIREC* TION F1tCM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBI, 'EvrAL .

CAIM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 3 +> 14 10 10 7 8 6 7 3 8 5 1 1 3 1 0 100 (1) 1.62 7.t 3 7.57 5.41 5.41 3.78 4.32 3.24 3.78 1.62 4.32 2.70 .54 .54 1.62 .54 .00 54.05 (2) .04 .17 .18 .13 .13 .09 .10 .08 .09 .04 .10 .06 .01 .01 .04 .01 .00 1.27 4-7 4 6 1 3 5 5 0 6 5 13 26 3 1 0 2 0 0 80 (1) 2.16 3.24 .54 1.62 2.70 2.70 .00 3.24 2.70 7.03 14.05 1.62 .54 .00 1.08 .00 .00 43.24 (2) .05 .08 .01 .04 .06 .06 .00 .08 .06 .17 .33 .04 .01 .00 .03 .00 00 1.02 8-12 0 0 0 0 0 0 0 0 0 1 3 1 0 0 0 0 0 5 i (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .54 1.62 .54 30 .00 .00 .00 .00 2.70 i (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .04 .01 .00 .00 .00 .00 .00 .06 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,

(2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 7 19 15 13 15 12 8 12 12 17 37 9 2 1 5 1 0 185 (1) 3.78 10.27 8.11 7.03 8.11 6.49 4.32 6.49 6.49 9.19 20.00 4.86 1.08 .54 2.70 .54 .00 100.00 (2) .05 .24 .19 .17 .19 .15 .10 .15 .15 .22 .47 .11 .03 .01 .06 .01 .00 2.35  !

(3)= PERCENT OF atz. GOOD OBSERVATIONS FVR THIS PAGE (2)=PERCE2rr OF ALL GOOD OBSERVATIONS FOR THIS PERIOD l C =CAIM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) n o s m a n w eec 3,wn

_1 TABLE 5 (Sheet 8 of 8)

Yankee Atomic Electnc Company. Rowe. Massachusetts Effluent and Waste Disoosal Semiannuel Report 1995 Meteoroloaical Data Joint Freauency Distribution it. 1so.e FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (f ERCENT) = 100.00 WIND DIREt TION FROPt SPEED (MPH) N NNE NE ENE E ESE SE SSE 3 SSW 'S5 WSW W WNW NW NNW VRBL TCYTAL CALM O O O O O o 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,00 .00 .o0 i (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .90 .00 .00 .00 .

C-3 285 843 459 167 116 los 95 85 96 86 146 119 84 62 93 118 0 2960 t (1) 3.63 10.72 5.84 2.12 1.48 1.35 1.21 1.08 1.22 1.09 1.86 1.51 1.07 .79 1.18 1.50 .00 37.65  !

(2) 3.63 10.72 5.84 2.12 1.48 1.35 1.21 1.08 1.22 1.09 1.86 1.51 1.07 ."' 1.18 1.50 .00 37.65 ,

4-7 205 762 193 63 87 63 68 118 129 249 386 284 132 79 104 106 0 3028  !

(1) 2.61 9.69 2.46 .80 1.11 .80 .87 1.50 1.64 3.17 4.91 3.61 1.68 1.00 1.32 1.35 .00 38.52 j (2) 2.61 9.69 2.46 .80 1.11 .80 .87 1.50 1.64 3.17 4.91 3.51 1.68 1.00 1632 1.35 .00 38.52 8-12 148 292 36 20 31 26 21 34 49 145 210 227 122 57 41 106 0 1565 (1) 1.83 3.71 .46 .25 .39 .33 .27 .43 .62 1.84 2.67 2.89 1.55 .73 .52 1.35 .00 19.91 (2) 1.88 3.71 .46 .25 .39 .33 .27 .43 .62 1.84 2.67 2.89 1.55 .73 .52 1.35 .00 19.91 13-18 40 53 4 4 0 2 1 1 11 35 20 53 15 3 3 14 0 299 (1) .51 1.18 .05 .05 .00 .03 .01 .01 .14 .45 .25 .67 .19 .04 .04 .18 .00 3.80 1 (2) .51 1.18 .05 .05 .00 .03 .01 .01 .14 .45 .25 .57 .19 .04 .04 .18 .00 3.80 i t

19-24 0 7 0 0 0 0 0 0 0 0 0 2 0 0 0 0 G 9 (1) .00 .09 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .00 .00 .00 .00 .11 (2) .00 .09 .00 .00 .00 .00 .00 .00 .00 .00 .co .03 .00 .00 .00 .00 .00 .11 i er 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .0L .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ' .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l ALL SPtrm 678 1997 692 254 234 197 185 238 285 515 762 685 353 201 241 3 14 0 7861 (1) 8.62 25.40' 8.80 3.23 2.98 2.51 2.35 3.03 3.63 6.55 9.69 8.71 4.49 2.56 3.07 4.38 .00 100.00

(

l (2) 8.62 25.40 8.80 3.23 2.98 2.51 2.35 3.03 3.63 6.35 9.69 2.71 4.49 2.56 3.07 4.38 .00 100.00 I I (1)=PERCE3rr OF ALL GOOD OBSERVATIONS FDR THIS PAGE j

(2)=PERCEtrF OF ALL GOOD OBSERVATIONS FUR THIS PERIOD I

C =CAIM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

~

MtEHYmEFFLNT_90C 3r31/97 i

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i APPENDIX A Radioactive Liould Effluent Monitorina Instrumentation Reauirement: Radioactive liquid effluent mor.itoring instrumentation channels are required to be operable in accordance with ODCM Control 5.1. With less than the

. minimum number of channels operable and reasonable efforts to retum the instrument (s) to operable status within 30 days being unsuccessful, ODCM Control 5.1 requires an explanation for the delay in correcting the inoperability in the next Effluent and Waste Disposal Semiannual Report.

Resoonse: As part of plant decommissioning, systems reconfiguration to support the l permanent shutdown has included the installation of a new Auxiliary Service Water (ASW) System which was installed in 1995 to support Spent Fuel Pool (SFP) cooling. This engineering design change also added a new ASW ,

composite sampler on the down stream side of the SFP heat exchanger to I provide an additional method of determining if any contamination was leaking into this normally clean system. This same ASW effluent line is also equipped I with an on-line radiation monitor which monitors the cooling water for any 4

potential contamination ingress.

Soon afterinstallation, the ASW composite sampler had to be declared inoperable (August 18,1995) due to blockage in the sample kne. At that time, a program of daily grab samples was implemented with laboratory  !

analysis as a remedial action to the out of service sampler. The original 1 design of the sample system contained a series of valves with a microtubing sample outlet. This was to reduce the sample volume collected over a period of time to a volume that matched laboratory analysis requirements. The low sample volume flow rate contributed to plugging from suspended sediments I

. typically found in the pond and cooling water. Higher flow rates could not be l used because of the lack of a local drain for excess sample volume where the l equipment was located. The on-line monitor remained in operation during the entire grab sampling period.

1 Due to the above conditions, a change to the original EDCR was prepared. l This change incorporated both a new sample system arrangement and '

location. The new sampling system methodology is similar to the Turbine t Building sump composite sampling system that has proven to have a high degree of reliability witn cooling water that has suspended sediment. The new location for the sample system is in the Screenwell House which has an adequate drain system to accommodate higher flow rates thereby eliminating the microtubing.

On October 31,1996, Revision 11 to the ODOM was approved. This revision formally included the requirement for a composite sampler on the ASW, but the design change and installation had not been completed. As a result, Action Statement 5 of Table 5.1 of the ODCM required that the commitment to take at least daily grab samples from the auxiliary service water be continued until the new system could be put into service.

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Installation of the new ASW composite sample system was completed on {

February 26,1997, and declared operational on February 27,1997, i completing the design change and allowing the plant to exit Action Statement 5.

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APPENDIX B Radioactive Gaseous Effluent Monstpnna Instrumentatson Reauirement* Radioactive gaseous effluent monitoring instrumentation channels are .

required to be operable in accordance with ODCM Control 5.2. With less than the minimum number of channels operable and reasonable efforts to retum the instrument (s) to operable status within 30 days being unsuccessful, ODCM Control 5.2 requires an explanation for the delay in correcting the inoperability in the next Effluent and Waste Disposal Semiannual Report. i Response The requirements of ODCM Control 5.2 goveming the of arability of l radioactive gaseous effluent monitoring instrumentation . vere met for this j reporting period.

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APPENDIX C Liould Holduo Tanks Reauirement- Defueled Technical Specification 3.4 limits the quantity of radioactive mate..H contained in any outside temporary tank. With the quantity of radioactive materialin any outside temporary tank exceeding the limits of Technical Specification 3.4, a description of the events leading to this condition is '

required in the next Effluent and Waste Disposal Semiannual Report.

Response: The limits of Technical Specification 3.4 were not exceeded during this resporting period.

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APPENDlX D 1

Radiological Environmental Mondoring Proaram i 1

Requirement The Radiological Environmental Monitoring Program is conducted in i accordance with ODCM Control 4.1. With milk or fresh leafy vegetation  !

samples no longer available from one or more of the required sample locations, ODCM Control 4.1 requires the identification of the new location (s) i for obtaining replacement sample (s) in the next Effluent and Waste Disposal Semiannual Report and inclusion of revised Off-site Dose Calculation Manual figure (s) and table (s) reflecting the novilocation(s).

Response: Milk sampling locatien TM-14 was dropped from the REMP program due to unavailability of milk samples. This location has shown to be unreliable in its supply of milk due to the limited number of cows (1 to 2) which are not always i producing milk. This farm is not considered to be a dairy farm, but periodically has milk animals for home use only. The last several land use censuses have .

shown that the site vicinity is not a significant milk producing area. Only a few I locations have milk animals, and these tend to be of the single animal for '  ;

home use type. Since the significance of the milk pathway as an indicator of f the buildup of iodine released from the plant has been eliminated due to the ,

removal of the lodine source term in the plant, and the lack of a reliable i replacement supply of milk from the site area, the number of indicator milk ,

i stations has been reduced from 2 to 1 in the ODCM.

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APPENDIX E l l

Land Use Census f

Reauirement- A land use census is conducted in accordance with ODCM Control 4.2. Wdh -

a land use census identifying a location (s) which yields at least a 20 percent i greater dose or dose commitment than the values currently being calculated in i ODCM Control 3.5, ODCM Control 4.2 requires the identification of the new location (s) in the next Effluent and Waste Disposal Semianneal Report.  !

Response- The land use census for this reporting period did not identify any locations  !

yielding at least 20 percent greater dose or dose commitment than the values  !

currently being calculated in ODCM Centrol 3.5. ,

Reauirement- With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent ,

greater than at a location from which samples are currently being obtained in accordance with ODCM Control 4.1, ODCM Control 4.2 requires that the new location (s) be added to the Radiological Environmental Monitoring Program if permission from the owner to collect samples can be obtained and sufficient sample volume is available. The identification of the new location (s)is required in the next Effluent and Waste Disposal Semiannual Report. j Response No new locations were added to the Radiological Environmental Monitoring  !

Program as a result of the 1996 land use census.

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c APPENDIX F Process Control Prooram (PCP)

Reauirement- PCP Control 2.0 requires that licensee-initiated changes to the PCP be submitted to the Commission in the Effluent and Waste Disposal Semiannual Report for the period in which the change (s) was made. .

Haagsnan There were no licensee-initiated changes to the PCP during the reporting period.

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l APPENDIX G l Off-Site Dose Calculation Manual (ODCM)

Reauirement- ODCM Control 7.2 requires that licensee-initiated changes to the ODCM be submitted to the Commission in the Effluent and Waste Disposal Semiannual  ;

Report for the period in which the change (s) was made effective. l i Response: Due to the permanent shutdown and decommissioning of the Yankee plant, the Off Site Dose Calculation Manual (ODCM) had become outdated in reference to descriptions of plant systems and surveillance requirements that l related to the old operating power plant configuration. A revised ODCM that l reflected the current status of the plant, including its reduced source terms, modified effluent and dose pathways, elimination of plant components and systems, as well as the addition of temporary systems installed to support the -  !

decommissioning effort was needed. Revision 11 of the Yankee ODCM was )

approved by PORC in meeting No. 96-63, October 31,1996, and was attached to the previous 1996 Semiannual Radioactive Effluent Report submitted on February 28,1997 (Letter Number BYR 97-0010).

A summary of changes made to the ODCM follows:

. The removal of Fe-59 (half life = 44.5 days) and Mo-99 (half life = 2.7 days) from dose assessment and lower limit of detection (LLD) analysis requirements on effluent samples, and the removal of Fe-59 and Ba/La-140 (half life = 12.8 days) from the LLD requirements for REMP sample analyses.

. inclusion of the new temporary liquid waste evaporator and discharge pathway in place of the originally installed waste evaporator system.

This includes updates on monitoring and surveillance requirements for evaporator effluents and the auxiliary service water system.

. The inclusion of gross alpha determination of weekly continuous particulate plant vent samples in place of only doing monthly composite analysis on weekly particulate samples.

. Extension of PVS system and sampler flow rate determination from 8 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the required equipment channels are inoperable.

. Establishment of ACTION requirements for the detection limits and analysis frequency for the ASW grab samples if the composite sampler is down.

= Removal of the SW radioactivity monitor and flow rate measuring instrumentation and surveillance requirements as a result of the elimination of possible contamination of this flow path (shutdown of old waste evaporator).

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. Updste of the liquid and gaseous effluent flow pathways on Figures 6-1 s
and 6-2 to reflect changes in plant configurations. -;

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. Deletion of reference to nearest resident within the site propedy due to its vacancy and planned removal (Figure 1-1).

j = Additional editorial changes to improve the ' consistency of terms used as l well as the removal of outdated references and operational data, and the correction of typographical errors. l 4

l 1 = Administrative corrections to various references made in the ODCM to the i Defueled Tech Specs. ,

4

  • Inclusion of a new Appendix B that lists the MPC limits of the original  :

10CFR20.1-20.602, Appendix B which is no longer in publication, but required by Tech Specs.  :

+ Editorial changes in bases to Control Requirements to substitute fundamental dose requirements in place of references to old 10CFR20 ,

sections that were replaced when Part 20 was revised.

- Elimination of the service water composite sampler requirement that provided sample collection of water used to cool the old waste evaporator condenser.

- Elimination of dissolved gas sample and analysis requirements in secondary liquids (service water).  ;

  • The reduction from 2 to 1 of indicator milk sampling locations required in the REMP.

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- Eliminating the time restriction (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) to complete a radiological l analysis of grab samples taken from the turbine building sump if the l composite sample were inoperable.

- Elimination of lodine sampling and analysis for plant vent releases, i

+ Removal of reference to sampling and analysis requirements forwaste gas system and containment purges.

  • Elimination of reference to Steam Generators and secondary coolant leakage, including surveillance requirements.

- Elimination of LLD requirements for radionuclides no longer present due to short half lives.

- Referencing all noble gas dose calculations and setpoint determinations to Kr-85 as the only remaining potential source.

Elimination of requirement for use of concurrent meteorology with releases in assessing dose (use historical data only).

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- Elimination of iodine sampling and analysis for REMP air monitors.

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Extending air particulate change out frequency from weekly to once every  :

two weeks (REMP).

i Elimination of iodine analysis in milk samples (REMP).

+ Reduction of milk sample collection during grazing season from every 2  ;

weeks to monthly (REMP).  !

  • Elimination of broad leaf vegetation sampling (REMP).
  • Elimination of upstream river water automatic composite sampler (REMP).

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- Reduction in the number of outer ring incident response TLD locations (REMP).

The changes to the RETS and REMP programs as contained in Revision 11 to i the ODCM reflect the shutdown status of the plant and the ongoing ,

decommissioning of the facility. None of the changes reduce the affective level of radioactive effluent control and monitoring of release pathways that still represent a potential effluent source term. Decommissioning activities .

have removed various potential sources, along with the natural radioactive i decay of relatively short lived radionuclides due to the cessation of the fission process in October,1991, (5 years ago). It is therefore concluded that these changes to the ODCM will continue to maintain the level of radioactive effluent control required by 10CFR 20.106 (new 20.1301),40 CFR 190,10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of affluent measurements, or dose and setpoint calculations.

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..- s APPENDIX H -

1 p Radioactsve Liauid. Gaseous. and Sohd Waste Treatment Syste'ns Renuirement ODCM Control 7.3 requires that licensee-initiated major changes to the

, radioactive waste systems (liquid, gaseous, and solid) be reported to the .!

, Commission in the Effluent and Waste Disposal Semiannual Report for the .

1 period in which the evaluation was reviewed by the Plant Operation Review  !

Committee. ,

i Response' The original plant design included a liquid radwaste evaporator as an installed

! treatment system to volume reduce and process radioactive liquid waste. As 4

part of th' plant decommissioning process, this installed system has been taken out of service and replaced with a temporary, skid mounted, liquid radwaste evaporator (i.e. Temporary Waste Water Process!ng Island) that

, operates on the same principle as the original equipment. The same t functional design requirements to produce liquid waste acceptable for release  :

i to the environment has been included to ensure that the same or better i process capability still exists until final termination of the license. ODCM Revision 11 (attached to the previous 1996 Semiannual Rad;oactive Effluent

Report Submittal) reflects this change in waste processing equipment .

configuration. l l

The summary of the safety evaluation for the Temporary Waste Water l Processing Island (TWWPI) system demonstrated the following:

a) All TWWPI systems, structures and components are classified NNS with j the only exception being the existing radiation monitor which is classified

as ROA.

b) The probability of occurrence and consequences of an accident previously evaluated in the SAR is not increased.

c) The probability of occurrence and consequences of a malfunction of

, equipment important to safety previously evaluated in the SAR is not increased.

d) The possibility of an accident of a different type than previously evaluated 4

in the SAR is not created.

1 e) The possibility of a different type of malfunction of equipment important to safety than any previously evaluated in th,e SAR is not created.  ;

f)' The margin of safety as defined in the basis for any technical specification is not reduced.

Therefore, the design change does not constitute an unreviewed safety

question as defined in 10CFR 50.59 (a)(2). Furthermore, ,

g) The plant modifications implemented by this EDCR do not significantly increase the cost of decommissioning.

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i h) The plant modifications implemented by this EDCR do not foreclose -

release of the site for unrestricted use. ,

1) The plant modifications implemented by this EDCR do not cause any significant environmental impact not previously evaluated.

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j) The activity does not violate the terms of the existing facility license.

The design change presents a consolidated TWWPl system capable of processing all the expected plant waste water at YNPS until the completion of spent fuel pool decommissioning activities. Operation of the TWWPl system ,

allowed for the removal of the permanent plant waste water evaporator system and the eventual dismantlement of the Waste Disposal Building (WDB).

Waste water, generated as a result of decommissioning activities, is routed to a new 20,000 gallon waste water storage tank. The tank is constructed with a  !

seconday berm so that in the event a leak was to develop, the contents are contained, thereby prevanting a spill of contaminated water. The tank accepts ,

i water from the Radioactive Lab Service Sump. However, the piping is installed in a way to accommodate future connections from the plant as needed. The tank is instrumented to provide level and temperature indication.

Additionally, the tank is serviced by a hot water heating system to prevent freezing in the winter, i

The contents of the waste water storage tank are processed through an evaporator consisting of a propano-fired bumer, a condensate cooler, and the necessary equipment to route the liquids. Steam generated as a result of the j boiling process is routed over a cool 6r resultirig in collected distillate. Due to their higher density, the contaminants are concentrated and settle out on the bottom of the evaporator.

The resultant two liquids from the evaporative process consist of distillate and bottoms. The distillate is transferred and stored in two 5,000 gallon storage tanks. Prior to transferring the distillate to the tanks, the clean water is further

' purified by a filter and two ion exchange polishers. Similar to the 20,000 l

, gallon storage tank, both tanks have heating capability and instrumentation for l temperature. At a predetermined level, the tank (s) are recirculated, sampled, j and then discharged to Sherman Pond via the Auxiliary Service Water system.

l The resultant bottoms is pumped into a locally staged waste container (HIC) ,

i for eventual transfer to an offsite disposal facility.

4 The cargo enclosure is ventilated with 1,000 cfm of fresh outside air. The ,

l exhaust is routed to the plant vent stack. j i

The TWWPl system was selected to duplicate the original treatment process 4

and match, or improve upon, the cleanup capability that was associated with

, the old installed radwaste evaporator system that it replaced. Therefore, the amount of radioactive materials expected to be released in liquid effluents after processing in the new system is anticipated to be equivalent, or lower, than that which would have been predicted for the original evaporator

<. operations. As a result, the maximum exposures to members of the public at  ;

the site boundary and to the genersi population will not differ significantly from V ,

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I those that would have occurred during the decommissioning process if the j

. original evaporator system was assumed to be used. . A comparison of liquid l 3

effluent water quality from the new evaporator system to the water quality from l the old evaporator system prior to the change shoves that the total particulate .  !

radioactivity during the first few months of operatum of the new system ranged j on the order of E-8 to E-9 uCi/ml compared to typical values for the original  !

system that were on the order of E-8 uCi/ml.

i Occupational exposure is minimized, monitored, and controlled in strict compliance with existing plant procedures. The AL. ARA program continues to be implemented. The program ensures that ALARA is considered in all aspects of plant operation, maintenance, inspection, and modifications.  !

l Additionally, the HIC which contains the concentrated bottoms liquid is shielded from the rest of the equipment in the cargo enclosure. Also, the '

estimated dose to personnel is minimal because the radioactive content of the '

- waste water currently is significantly less than during when the plant was operating. Finally, the TWWPl system operates more efficiently than the old liquid radwaste system. A net benefit is realized in dose savings from no longer having to perform maintenance on the old system.

The design change, TWWPl system, was reviewed and found acceptable by PORC on July 11,1996 as documented in PORC meeting number 96-41.

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APPENDIX l i l

SupplementalInformation Third and Fourth Quarters 1996 4

1. Control Limits'- Dose and Dose Rate Contml and Cateoorv klmit
a. Noble Gases Control 3.3, Total body dose rate 500 mrem / year Control 3.3, Skin dose rate 3000 mrem / year Control 3.4, Gamma air dose 5 mrad / quarter Control 3.4, Gamma air dose 10 mrad / year Control 3.4, Beta air dose 10 mrad / quarter Control 3.4, Beta air dose 20 mrad / year
b. lodine-131. Tritium. and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Davs I Control 3.3, Organ dose rate 1500 mrem / year  !

Control 3.5, Organ dose 7.5 mrem / quarter Control 3.5, Organ dose 15 mrem / year  ;

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c. Llaulds Control 3.1, Total body dose 1.5 mrem / quarter Control 3.1, Total body dose 3 mrem / year i Control 3.1, Organ dose 5 mrem / quarter Control 3.1, Organ dose 10 mrem / year i

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2. Control limits - Concentration Control and Cateoorv M i
s. Llaulds Control 2.1, Total sum of the fraction of MPC (10CFR20, 1.0 Appendix B, Table ll, Column 2), excluding ncble gases b less than:

Control 2.1, Total noble gas concentration 2.00E-04 pCi/cc 4

3. Measurements and Anoroximations of Total Radioactivity l l
a. Noble Gases. Krvoton-85,

. Continuous discharges are determined by direct measurements. A primary vent stack gas sample is taken monthly and analyzed for Krypton-85. A review of the

weekly primary vent stack noble gas integrator readings for any increase in values above the background level also is used as a reference. There are no longer any batch discharges. Errors associated with the above measurements are estimated l, to be 125 percent.
b. lodines. Particulates There are no longer any iodine isotopes available for discharge. The sampling

. system design requires the use of a charcoal cartridge as a support for the particulate filter during particulate collection. The sampling system continuously t draws a sample from the primary vent stack through a filter and charcoal cartridge. Both the filter and charcoal cartridge are removed and analyzed weekly. The errors associated with the determination of particulate effluents are estimated to be i30 percent.

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c. Llauld Effluents A gamma isotopic analysis is performed on a representative sample using a

. Marinelli Beaker geometry for both a batch or continuous discharpe. Composite samples for batch and continuous discharges are analyzed for strontium-89, strontium-90, iron-55, gross alpha activity, and carbon-14.

Tritium analysis is performed on composite samples for continuous discharges and on each batch discharge. The errors associated with these measurements

are as follows: fission and activation products, *20 percent; tritium,110 percent; dissolved fission gases,120 percent; and alpha activity, *35 percent.

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4. Batch Releases P
a. Llauids i The batch release data is presented in two categories to provide accurate average discharge rate values.

Outdoor Routine Tank Third Quarter Batches Moats Number of batch releases: 0 0 Total time period for batch releases (minutes): - -

Maximum time period for a batch release (minutes): - -

Average time period for batch releases (minutes): - -

Minimum time period for a batch release (minutes): - -

' Average stream flow (Sherman Dam) during period (cfs): 125 125 Average discharge rate (gpm): - -

l Outdoor  :

Routine Tank  ;

Fourth Quarter Batches Monts Number of batch releases: 4 5 Total time period for batch releases (minutes): 3,425 13,299 i Maximum time period for a batch release (minutes): 1,420 7,644 Average time period for batch releases (minutes): 856 2,660 Minimum time period for a batch release (minutes): 135 330 Average stream flow (Sherman Dam) during period (cfs): 728 728 Average discharge rate (gpm): 5.7 2.0

b. Gases There are no longer any gaseous batch discharges.
5. Abnormal Releases ODCM Control 7.2 requires the reporting of any unplanned releases from the site to the l site boundary of radioactive materialin gaseous and liquid effluents made during the  !

reporting period. l

a. Llauid There were no nonroutine liquid releases during the repordr.g period. j l
b. Gases 4

There were no nonroutine gaseous releases during the reporting period.

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