ML20217J653
| ML20217J653 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/31/1997 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20217J643 | List: |
| References | |
| NUDOCS 9804060348 | |
| Download: ML20217J653 (45) | |
Text
EFFLUENTAND WASTE DISPOSAL SEMIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS 1997 INCLUDlHG ANNUAL RADIOLOGICAL IMPACT ON MAN FOR 1997 l
1 Yankee Atomic Electric Company i
Rowe, Massachusetts
- 88"2888"3888882, R
PDR J-EfMAYREFFLNT,97C 3"J7/98
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r l-l ERRATA l
The first quarter gaseous releases reported in Tables.1 A and 1B and Appendix ! of the l
Semiannual Report covering the first and second quarters of 1992 have been revised to F
include a gaseous batch discharge of 50 pCi of Krypton-85 which was inadvertently omitted from the original report. The revised tables and Appendix are provided in j
Appendix K to this report.
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NOTES-
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Yankee Nuclear Power Station's last day at any power level was October 1,1991. The facility is permanently shut down for future decommissioning. Due to ceased operations,
~ hort-lived nuclides have been deleted from the gaseous and liquid effluent tables. Their s
activity concentrations in the fuel inventory have decayed to zero values.
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TABLE OF CONTENTS l
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l 1.0 I NTR O D U CTIO N........................................................
1 2.0 M ETEOROLOGIC AL D ATA.............................................. - 3 l
3.0 DOSE ASS ESSM ENT....................................................
4 3.1 Doses From Liquid Effluents.......................................
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3.2 Doses From Noble Gases......................................... - 4 3.3 Dosas From lodine-131, Tritium, and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days................................
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4.0 R E F E R E N C E S..........................................................
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APPENDIX A Radioactive Liquid Effluent Monitoring Instrumentation....... A-1 i
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l APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation.... B-1 APPENDIX C Liquid Holdup Tanks.................................. C-1 l
APPENDIX D Radiological Environmental Monitoring Program........... D-1 APPENDIX E Land Use Census................................... E-1 l
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APPENDIX F Process Control Program (PCP)....................... F-1 APPENDIX G Off-Site Dose Calculation Manual (ODCM).............. G-1 APPENDIX H Radioactive Liquid, Gaseous, and Solid Waste Treatment Syste m s............................................ H - 1 APPENDIX 1
- Supplemental Information............................
1-1 APPENDIX J Sewage Sludge Disposal...'.......................... J-1 APPENDIX K Errata Pages for the 1992 First and Second Quarter Effluent l
And Waste Disposal Report............................. K-1 f
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LIST OF TABLES Table Tit!2 EaQA 1A Gaseous Effluents - Summation of All Releases............................
8 1B Gaseous Effluents - Elevated Releases....................................
9 1C Gaseous Effluents - Ground level Releases...............................
10 2A Liquid Effluents - Summation of All Releases..............................
11 2B Liquid Effluents - Routine Releases......................................
12 3
Solid Waste and irradiated Fuel Shipments................................
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Maximum Off-Site Doses and Dose Commitments to Members of the Public.....
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1992-1996 Meteorological Data Joint Frequency Distribution..................
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YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MASSACHUSETTS EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT THIRD AND FOURTH QUARTERS 1997
1.0 INTRODUCTION
Tables 1 through 3 list the recorded radioactive gaseous and liquid effluents and solid waste, respectively, with data summarized on a quarterly basis for the second six months of the l
year. Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 1997. Radioactive effluents reported in the Effluent 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 1997.
As required by Control 7.2.b, dose commitments resulting from the release of radioactive i
materials in liquids and gases were estima;ed in accordance with the Yankee Nuclear Power Station Off-Site Dose Calculation Manual (ODCM). These dose estimates were made using a Method 11 analysis as described in the ODCM. A Method ll analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 1) using historic meteorological data. For gaseous releases, five years of historic (1992-1996) quarterly meteorological data were used for determining the gaseous pathway doses. As required by Control 7.2.b, this report also shall include an assessms d Qf the rntation doses from radioactive effluents to member (s) of the public due to allowed recreational activities inside the site boundary during the year. However, for this reporting period, no recreational activities inside the site boundary were permitted. As a result, recreational activities are not addressed. The limited use of the Information Center
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on-site is associated with educational activities as they pertain to the operation / decommissioning of the plant and as such, are not included under Control 7.2.b. Assessment of radiation doses (including direct radiation) to the likely most exposed real member (s) of the public for the calendar year for the purposes of demonstrating conformance with 40CFR Part 190, i
" 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.a were not entered into during the year, no additional radiation dose assessments are required.
I All calculated dose estimates for this reporting period are well below the dose criteria of 10CFR Part 50, Appendix 1.
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Appendices A through H indicate the status of reportable items per the requirements of Controls 5.1, 5.2, Technical Specification 3.4, Controls 4.1,'4.2, 2.0 (PCP),7.2, and 7.3, respectively. Appendix l of this report provides supplementalinforrnation on effluent releases for.
this reporting period and Appendix J provides information concerning the disposal of sewage sludge which occurred during this reporting period.
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2.0' METEOROLOGICAL DATA
- Five years of historic meteorological data (1992-1996) collected from the site's 200-foot '
meteorological tower, located approximately 180 meters north of the vapor container, were used -
to model the atmospheric dispersion of airborne effluents. The tower instrumentation was h
designed to meet the requirements of Regulatory Guide 1.23 (Reference 2) for meteorological monitoring.- A summary of the 1992-1996 meteorological data is provided in Table 5 of this
. report.
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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 1
g vent stack is treated as a mixed mode elevated release point dependent upon wind speed, as L
described in Regulatory _ Guide 1.111 (Reference 3).
l Atmospheric diffusion was calculated using quarterly historical data along with the recorded quarterly effluent information. CHl/O and D/O values wors derived for all receptor
-q points using a straight line airflow model. All dispersion and deposition factors have been I
calculated employing appropriate source configuration considerations and removal mechanism (e.g., dry deposition) described in Regulatory Guide 1.111 (Reference 3).' Terrain elevations, h
. including downwind valley flow corrections for the surrounding area, were factored into the calculation of CHl/O an' D/O values at each receptor location.
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3.0 '
DOSE ASSESSMENT 3.1 Doses From Liauld Effluents I
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g Control 3.1 limits total body (1.5 mrem per quarter and 3 mrem per year) and organ (5
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" mrem per quarter and 10 mrem per year) doses from liquid effluents to a member of the public to 1
those specified in 10CFR Part 50, Appendix 1. By implementing the requirements of 10CFR Part 50,' Appendix 1, Control 3.1 assures that the release of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."
p f7 Exposure pathways that could exist as a resuit of liquid effluents are fish, direct exposure j
from river shoreline sedimentation, milk and meat via animalingestion of the Deerfield River b
' water, and meat, milk, and vegetable pathways via crop irrigation with water withdrawn from the Deerfield River. Drinking water and aquatic invertebrate pathways do not exist downriver of the
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Yankee plant at Rowe. The dose analysis for the liquid pathways assumes a dilution based on
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the monthly average flow at the Sherman Dam.
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The whole body and organ doses due to liquid effluents were determined by summing the contributions from all pathways. The whole body and organ doses to a member of the public 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 l dose criteria of Control 3.1. -
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' 3.2 Doses From Noble Gases 1
I Control 3.4 limits the gamma air (5 mrad per quarter and 10 mrad per year) and beta air-j
.(10 mrad per quarter and 20 mrad per year) doses from noble gases released in gaseous -
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effluents from the site to areas at and beyond the site boundary to those specified in 10CFR Part
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50, Appendix 1. By implementing the requirements of 10CFR Part 50, Appendix 1, Control 3.4 L assures that the release of radioactive noble gases in gaseous effluents will be kept "as low as 1
is reasonably achievable."
h if noble gases are determined to be present in effluent discharge, the dose estimates are t. calculated at the site boundary, nearest resident, nearest vegetable garden, and nearest milk h
'animalin'each of the sixteen principle compass directions, as well as the point of highest off-site
' gro'und level air concentrations of radioactive materials. Gamma and beta air doses, as well as
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whole body and skin doses, are calculated at each of the above locations.
l 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 Gaussian distribution of activity in the vertical plane. The gamma radiation received from
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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, attenuation by the interaction of photons with matter in the path between the j
source and receptor 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 i
point.
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i The estimated quarterly and annual gamma and beta air doses, as listed in Table 4, are
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zero because there were no noble gas releases during 1997.
3.3 Doses From lodine-131. Tritium. and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Davs 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 lodines and 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 reasonablyachievable." 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.
Exposure pathways that could exist as a result of the release of particulates and tritium to the atmosphere include external 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.
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1 Conservatively, a vegetable garden was assumed to exist at each milk animal location.
Furthermore, the meat pathway was assumed to exist at each milk animallocation. 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 feeding of animals when on pasture or actually restrict animals to full time silage feeding throughout the entire year.
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 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 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
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- Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance With l~
10CFR Part 50, Appendix l," U.S. Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October 1977.
- 2.
Regulatory Guide 1.23, "On-Site Meteorological Programs (Safety Guide 23),"
U.S. Nuclear Regulatory Commission, Office of Standards Development, February 1972.
3.
Regulatory Guide 1.111, " Methods for Estimating ' Atmospheric Transport and Dispersion 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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TA,BLE 1 A Yankee Atomic Electric Comoany. Rowe. Massachusetts Effluent and Waste Disposal Semlannual Report Third and Fourth Quarters 1997 Gaseous Effluents - Summation of All Releases Est. ol Unit Quarter 3 Quarter 4 p,9 I
A. Fission and Activation Gases
- 1. Total Release Ci 0.00e+00 0.00e+00
- 2.50e+01 j
- 2. Average Release Rate for Pedod pCi/sec 0.00e+00 0.00e+00 j
- 3. Percent of Control LimitW 0.00e+00 0.00e+00 B. lodines*
C. Particulates
- 1. Particulates with half-lives > 8 days Ci 9.82e-08 2.50e-08 3.00e+01
- 2. Average release rate for period pCi/sec 1.24e-08 3.18e-09
- 3. Percent of Control Limit" 8.00e-03 5.33e-03
- 4. Gross Aioha Radioactivity Ci
<3.18e-08
<3.57e-08 D. Tritium
- 1. Total Release Ci 7.699-02 6.06e-02
- 3.00e+01
- 2. Average Release Rate for Period pCi/sec 9.78e-03 7.71 e-03
- 3. Percent of Control Limit
- NA NA
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(a) ODCM Control 3.4.a for gamma-air dose. Percent values for ODCM Control 3.4.b for beta-air dose would be approximately the same.
l (b) lodine data have been deleted. These nuclides are no longer available for discharge, j
(c) Per ODCM Control 3.5, the percentage of the limit is based on the combined dose contribution from j
iodines, tritium, and particulates with half lives greater than 8 days. Percentage of limits are calculated using ODCM Method I dose equations.
i (d) Per ODCM Control 3.5, percentage dose contribution from tritium is included in Part C.3.
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TABLE 1B Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Discosal Semiannual Reoort Third and Fourth Quarters 1997 Gaseous Effluents - Elevated Releases I
Continuous Mode Batch Mode'*)
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Krypton ~85 Ci 0.00e+00 0.00e+00 I
Total for Period Ci 0.00e+00 0.00e+00 1
- 2. lodines*
- 3. Particulates i
Strontium-89 Ci
<8.40e-07
<4.74e-07 Strontium 90 Ci
<5.30e-07
<2.22e-07 Cesium-134 Ci
<2.67e-07
<2.55e-07 Cesium-137 Ci 1.61 e-08
<2.72e-07 Zinc-65 Ci
<7.44e-07
<6.40e-07 Cobalt-58 Ci
<2.81 e-07
<2.22e-07 Cobalt 60 Ci 8.21 e-08
<4.78e-07 Zirconium-Niobium-95 Ci
<4.79e-07
<3.75e-07 Cerium-144 Ci
<1.01 e-06
<8.06e-07 Antimony-124 Ci
<8.67e-07
<6.66e-07 Manganese-54 Ci
<2.82e-07
<2.25e-07 Sliver-110m Ci
<4.26e-07
<3.41 e-07 Total for Period Ci 9.82e-08
<4.98e-06 (a) There are no longer any batch mode gaseous releases.
1 (b) lodine-131, lodine-133, and lodine-135 activities have been deleted. These nuclides are no longer available for discharge.
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Yankee Atomic Electric Comoanv. Rowe. Massachusetts
- Effluent and Waste Disoosal Semiannual Reoort Third and Fourth Quarters 1997 Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode" Nuclides Released -
Unit Quarter 3 -
Quarter 4" Quarter 3 -
- Quarter 4
- 1. Fission Gases Krypton-85 '
Ci 0.00e+00 0.00e+00 j
h Total for Period Ci 0.00e+00 0.00e+00
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' 2. lodines" i
- 3. Particulates Strontium-89 Ci 0.00e+00
<1.23e-07 1
Strontium-90 Ci 0.00e+00
<4.52e-08 Cesium-134 Ci 0.00e+00
<1.25e-08 Cesium-137 Cl 0.00e+00 4.59e-09 Zinc-65 Ci 0.00e+00
<2.76e-08
- Cobalt-58 Cl 0.00e+00
<1.23e-08'
- Cobalt-60 Ci 0.00e+00 2.04e-08
' Zirconium-Niobium-95 Ci 0.00e+00
<2.26e-08 Cerium-144 Ci 0.00e+00
<4.37e-08 Antimony-124 Ci 0.00e+00
<3.42e-08 Mancanese-54 '
' Ci 0.00e+00
<1.35e@
i Sliver-110m Ci 0.00e+00
<2.15e-08
- I Total for Period Ci 0,00e+00 2.50e-08 f
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. (a) There are no longer any batch mode gaseous releases.
(b) The ground level release of activity for the fourth quarter occurred during scabbling of outbuildings and moat wall and floors. The HEPA filter units used for these work sites met all the specifications and mon ltoring requirements stated in the Final Safety Analysis Report. The small dose contribution from this source had an insignificant impact on the total dose value associated with gaseous elevated releases.
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- (c) lodine-131, lodine-133, and lodine-135 activities have been deleted. These nuclides are no longer avellable for discharge.
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TABLE 2A 1
Yankee Atomic Electric Comoany. Rowe. Massachusetts Effluent and Waste Discosa! Semiannual Reoort Third and Fourth Quarters 1992 Liauid Effluents - Summation of All Releases
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Est. o Unit Quarter 3 Quarter 4 p,,g A. Fission and Activation Producta
- 1. Total Release (not including tritium, cases, alpha)
Ci 1.30e-06
<8.11 e-05 2.00e+01
- 2. Average Diluted Concentration During Period pCi/ml 1.67e-11
<1.13e-09 i
- 3. Percent of Applicable Limit'*
6.93e-05 0.00e+00 B. Tritium
- 1. Total Release Ci 7.27e-03 3.85e-03 e1.00e+01
- 2. Average Diluted Concentration Durina Period pCi/ml 9.33e-08 5.35e-08
- 3. Percent of Applicable Limit
- 3.11e-03 1.78e-03 C. Dissolved and Entrained Gases
- 1. Total Release Ci
<9.99e-05
<1.73e-04
- 2.00e+01 1
- 2. Averaae Diluted Concentration Durina Period pCi/ml
<1.28e-09
<2.41 e-09
- 3. Percent of Applicable Limit
- 0.00e+00 0.00e+00 D. Gross Alpha Radioactivity
- 1. Total Release Ci
<4.26e-02
<6.41 e-02 e3.50e+01 i
E. Volume of Waste Release (prior to dilution) liters 9.26e+04 1.15e+05 A2.50e+01
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F. Volume of Dilution Water Used During Period liters 7.79e+07 7.19e+07 1.50e+01 1
(a) Concentration limits specified in 10CFR20, Appendix B, Table 11, Column 2 (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 limit.
(b) Concentration limits 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 limit.
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TABLE 2B i
Yankee Atomic Electric Company. Rowe. Massachusetts Effuent and Waste Disoosal Semiannual Report Third and Fourth Quarters 1997 Liould Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Oue.rter 4 Strontium-89 Ci 0.00e+00 0.00e+00
<3.83e-06
<4.72e-06 Strontium-90 Ci 0.00e+00 0.00e+00
<2.34e-06
<2.89e-06 Cesium-134 Ci 0.00e+00 0.00e+00
<3.590-07
<7.12e-07 Cesium-137 Ci 0.00e+00 0.00e+00 6.41e-07
<7.99e-07 Cobalt-58 Ci 0.00e+00 0 00e+00
<3.830-07
<6.18e-07 Cobalt-60 Ci 0.00e+00 0.00e+00 6.60e-07
<1.08e-06 fron-59 Ci 0.00e+00 0.00e+00
<8.91 e-07
<1.41 e-06 Zine-65 Ci 0.00e+00 0.00e+00
<1.17e-06
<1.96e-06 Manganese-54 Ci 0.00e+00 0.00e+00
<3.55e-07
<6.12e-07 Zirconium-Niobium-95 Ci 0.00e+00 0.00e+00
<6.230-07
<1.06e-06 Cerium-144 Ci 0.00e+00 0.00e+00
<2.06e-06
<3 42e-06 Silver-110m Ci 0.00e+00 0.00e+00
<5.90e-07
<9.78e-07 I
i Antimony-124 Ci 0.00e+00 0.00e+00
<1.23e-06
<7.21 e-07 Carbon-14 Ci 0.00e+00 0.00e+00
<6.43e-06
<5.58e-06 Iron-55 Cl 0.00e+00 0.00e+00
<2.10e-05
<5.31 e-05 Antimony-125 Ci 0.00e+00 0.00e+00
<9.44e-07
<1.40e-06 Unidentified Ci 0.000+00 0.00e+00 0.00e+00 0.00e+00
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Total for Period (above)
Cl 0.00e+00 0.00e+00 1.30e-06
<8.11 e-05 l
Krypton-85 Ci 0.00e+00 0.00e+00
<9.99e-05
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TABLE 3 (Sheet 1 of 2)
Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Discosal Semiannual Reoort Third and Fourth Quarters 1997 Solid Waste and Irradiated Fuel Shloments A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel) 6-month Est. Total
- 1. Type of Waste Unit Penod Error, %
a.
Dry Active Waste: Class A Containers m'
1.n7e+01 a
d.50e+01 steet liner (201 ft',177.5 ft,7.5 ft')
Ci (Est.)
7.94e-01 i
8 b.
Resins, Filters, Evap Bottoms: Class A Containers m
2.50e+00 d.50e+01 steel drum (7.5 ft')
Ci (Est.)
5.24e-02 8
c.
Dry Active Waste: Class A Containers m
4.38e+02 d.50e+01 steel box (101 ft )
Ci (Est.)
3.70e-01 d.
Dry Active Waste: Class A Containers (b) d.50e+01 Ci st.)
9.95e 02
- 2. Estimate of Major Nuclide Composition (by type of waste) >1%
a.
Iron-55 6.50e+01 Cobalt-60 2.26e+01 Nickel-63 1.06e+01 b.
Cesium -137 3.19e+01 Cobalt-60 2.80e+01 Nickel-63 2.65e+01 fron-55 1.17e+01 c.
Iron-55 4.47e+01 Cobalt-60 2.71e+01 Nickel-63 2.47e, +01 Cesium-137 3.49e+00 d.
Iron-55 6.34e+01 Cobalt-60 1.99e+01 Nickel-63 1.50e+01 l
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TABLE 3 (Sheet 2 of 2)
Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Discosal Semiannual Reoort Third and Fourth Quarters 1997 Solid Waste and Irradiated Fuel Shioments -
- 3. Solid Weste Disposition Number of Shioments Mode of Transoortation Destination 3
truck Bamwell, SC l
17(b) truck Barnwell, SC 38 truck So. Clive, UT 9(a) truck Oak Ridge, TN 3(a) truck Memphis, TN 1(a) truck Bamwell, SC l
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I B. IRRADIATED FUEL SHIPMENTS (Disposition): None l
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TABLE 4 Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Disoosal Semiannual Reoort j
192Z t
Ma;cimum') Off-Site Doses and Dose Commitments to Members of the Public" Source Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter YearM i
- 1. Liquid Effluents 4
Whole Body mrem 1.03e-06*
1.84e-05*
1.39e-05*
1.39e-06*
3.47e-05 1
Critical Organ mrem 1.22e-06*
1.94e-055 2.51e-055 1.39e-06*
4.71e-05
- 2. Airborne Effluents
, Tn ium and mrem 1.34e-045 1.60e-045 2.02e-04*
1.28e-04N 6.24e-04 P cut mrad 0.00e+005 0.00e+00*
0.00e+005 0.00e+00m 0.00e+00 Be a A 0
mrad 0.00e+00*
0.00e+00*
0.00e+005 0.00e+005 0.00e+00 G ma (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 the maximum doses for each quarter. This results in a
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conservative yearly dose estimate, but still within the limits of 10 CFR Part 50.
(d) Child l
(e) Adult (f) GI-Lil of Teen and Child i
(g) Liver of Child (h) Liver, Kidney, Lung, GI-Lil, and Thyroid of Child (i) SW, WSW,1300 Meters; Lung of Child (j) SW, WSW,1300 Meters; Liver of Child (k) SW, WSW,1300 Meters; Liver, Kidney, Lung, GI-LLl, Thyroid, and Whole Body of Child (I) There were no noble gases released during the four quarters of 1997.
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8
e APPENDIX A Radioactive Liauld Effluent Monitorina instrumentation Reauirement.
Radioactive liquid effluent monitoring 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 return 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 1
in the next Effluent and Waste Disposal Semiannual Report.
u
Response
As part of the plant's dismantlement and decommissioning process, the Turbine Building Sump composite sampler, located on_ the 002 discharge pathway, was permanently removed from service on June 2,1997. On that date, the service water pumps were permanently secured from service, resulting in the cessation of water flow via the 002 pathway. Chemistry -
confirmed by inspection that flow via the 002 outflow pipe had been i
terminated. Additionally, auxiliary boiler and air conditioning equipment that also had drains associated with the 002 discharge have been similar'y -
removed from service. All remaining drains in the Turbine Building have been plugged to assure that no inadvertent releases occur via the 002 pathway.
ODCM Tables 2.1 and 5.1 state the analysis and compositing sample requirements for plant effluent surveillances. These requirements are
)
necessary only when releases are occurring via the appropriate effluent release points. Therefore, with the securing of the 002 pathway, no continued operation of the Turbine Building Sump composite sampler is required.
Reference to the Turbine Building Sump composite sampler will be deleted -
from ODCM Control 5.1.
i-l!
I mumrrowc A-1 l.
L
i APPENDIX B Radioactive Gaseous Effluent Monitorina instrumentation i-l Reauirement Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Control 5.2. With less l
than the minimum number of channels operable and reasonable efforts to retum the instrument (s) to operable status within 30 days being unsuccessful, l
ODCM Control 5.2 requires an explanation for the delay in correcting the.
l Inoperability in the next Effluent and Waste Disposal Semiannual Report.
{
Response-The requirements of ODCM Control 5.2 governing the operability of radioactive gaseous effluent _ monitoring instrumentation were met for this j
reporting period.
l l
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r tmtVREFFLNT.WC O*l l
APPENDIX C 1
Liauid Holduo Tanks i
)
Reauirement:
Defueled Technical Specification 3.4 limits the quantity of radioactive material l
contained in any outside temporary tank. With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical I
Specification 3.4, a description of the events leading to this condition is I
required in the next Effluent and Waste Disposal Semiannual Report.
Resoonse:
The limits of Technical Specification 3.4 were not exceeded during this reporting period.
i I
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s m a rrtuterc C-1 i
APPENDIX D Radioloalcal Environmental Monitorina Proararu Reauirement:
The Radiological Environmental Monitoring Program is conducted in 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) for obtaining replacement sample (s) in the next Effluent and Waste Dis;.osal Semiannual Report and inclusion of revised Off-Site Dose Calculation Manual figure (s) and table (s) reflecting the new location (s).
Resoonse:
All required milk or fresh leafy vegetation samples were available during this reporting period.
l I
i l
inumemma D-1
i APPENDlX E Land Use Census 4
)
Reauirement:
A land use census is conducted in accordance with ODCM Control 4.2. With.
a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in ODCM Control 3.5, ODCM Control 4.2 requires the identification of the new
{
- location (s) in the'next Effluent and Waste Disposal Semiannual Report.
Response.
~ The land use census for this reporting period did not identify any locations '
yleiding at least 20 percent greater dose or dose commitment than the values currently being calculated in ODCM Control 3.5.
3 1
)
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 -
q 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.
=1 Response-No new locations were added to the Radiological Environmental Monitoring Program as a result of the 1997 land use census..
l l
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marrun.we E-1
APPENDIX F t
Process Control Procram (PCP) l l
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.
l'
Response
There were no licensee-initiated changes to the PCP during this reporting -
l period.
1
+
l I
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nonmemm.we F-1 o
f i
i.
i APPENDIX G
)
Off-Site Dose Calculation Manual (ODCM)
Bequirerng;)1:
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.
' B9FAnse:
There were no licensee-initiated changes to the ODCM during this reporting period.-
l l^
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i
~
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i i-4 J.VGAYlhEFFLNT.9m G-1 1
APPENDIX H Radioactive Llauld. Gaseous. and Solid Waste Treatment Systems Reauirement-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 period in which the evaluation was reviewed by the Plant Operation Review
' Committee.
Response
There were no major changes to the radwaste treatment systems during this reporting period.
I J. !
neemtrrunwc H-1
.t
i APPENDlX l Sucolemental Information Third and Fourth Quarters 1997 1.
Control Limits - Dose and Dose Rate Control and Cateaorv ymji 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 1
Form With Half-Lives Greater Than 8 Davs
-)
Control 3.3, Organ dose rate 1500 mrem / year Control 3.5, Organ doso 7.5 mrem / quarter Control 3.5 Organ dose 15 mrem / year c.
Llaulds Control 3.1, Total body dose :
1.5 mrem / quarter Control 3.1, Total body dose 3 mrem / year Control 3.1, Organ dose 5 mrem / quarter Control 3.1, Organ dose -
10 mrem / year I
f
( '.
l m m mnm.ec l-1 Y
l
I l
]
2.
. Control limits - Concentration Control and Cateaorv 1JI pjt I
a.
Lioutds Control 2.1, Total sum of the fraction of MPC (10CFR20, 1.0 i
Appendix B, Table ll, Column 2), excluding noble gases.
less than:
Control 2.1, Total noble gas concentration 2.00E-04 pCi/cc i
3.
Measurements and Acoroximations of Total Radioactivity
'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 i
longer any batch discharges. Errors associated with the above measurements are estimated to be t25 percent.
1 1
b.
lodines. Particulates There are no longer any lodine isotopes available for discharge. The sampling
)
system design requires the use of a charcoal cartridge as a support for the 1
particulate filter during particulate collection. The sampling system continuously j
draws a sample from the primary vent stack through a filter and charcoal j
cartridge. The particulate filter is removed and analyzed weekly. The errors associated with the determination of particulate effluents are estimated to be $30 percent.
^
' c.
Liould Effluents.
A gamma isotopic analysis is performed on a representative sample using a Marinelli Beaker geometry for both a batch or continuous discharge. Composite samples for batch and continuous discharges are analyzed for strontium-89, strontium-90, iron-55, gross alpha activity, and carbon-14.
.j 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,120 percent; tritium, t10 percent; l
dissolved fission gases, *20 percent; and alpha activity, i35 percent.
1 i
J 74BHWmEFFLNT.970 l*2 L
4.
Batch Releases a.
Liaulds The batch release data is presented in two categories to provide accurate average discharge rate values.
Batch Releases Outdoor :
1 Tank Third Quarter Routine
.MQallL
~ Number of batch releases:
1 5
Total time period for batch releases (minutes):
1320 4305-Maximum time period for a batch release (minutes):
1320 1815' Average time period for batch releases (minutes):
1320 861 Minimum time period for a batch release (minutes):-
1320 400
' Average stream flow (Sherman Dam) during period (cfs):
255 255
. Average discharge rate (gpm):
6.1 3.8 Fourth Quarter Number of batch releases:
2 7
Total time period for batch releases (minutes): _
2,160 6,402 Maximum time period for a batch release (minutes):
1,255--
1,480 Average time period for batch releases (minutes):
1,080 914 Minimum time period for a batch release (minutes): _
905
_320 Average stream flow (Sherman Dam) during period (cfs):'
462 -
462' Average discharge rate (gpm):
6.2 2.9
- 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
- site boundary of radioactive material in gaseous and liquid effluents made during the reporting period, a.
Llauld There were no nonroutine liquid releases during the reporting period.
b.
Gases There were no nonroutine gaseous releases during the reporting period.
L
-}veema m m sc
-l-3
l l
APPENDIX J
'~
Sewaoe Sludoe Disoosal Reauirement-For periods in which disposal of septage occurs, the licensee shall report in the Effluent and Waste Disposal Semiannual Report, the volume discharged, liquid and solid fractions, and total activity discharged.
Resoonse:
The following information is provided for the disposal of sewage sludge during the reporting period:
Volume Discharged (gallons):
9.50e+03 l'
Liquid Fraction (by weight) of Waste:
7.91e-01 Solid Fraction (by weight) of Waste:
2.09e-01 Nuclide Content in Liquid Fraction (pCi/g): ND(*)
Nuclide Content in Solid Fraction (pCi/g wet):
= 1.61e-07 Cobalt-60
= 6.70e-07 Total Activity Discharged (pCl):.
= 1.21e+00 Cobalt-60
= 5.03e+00 TOTAL 6.-24e+00 l
l l-
)
l
(
l (a)
ND = Not Detectable
-1 l
L hmmmme J-1 l
APPENDIX K i
Errata Paoes for the 1992 First and Second Quarter j
l Effluent and Waste Disoosal Reoort j
- Attached are revisions to the following pages to the Semiannual Report covering the first and
,1 1
.second quarters of 1992:
Page 1 (Table 1 A)
Page 2 (Table 18)
L Page 1-2 (page 2 of Appendix l}
Page 1-4 (page 4 of Appendix l}
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I 1
1 TABLE 1A ERRATA
_ Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste DisDosal Semiannual Report First and Second Ouarters 1992
)
Gaseous Effluents - Summation of All Releases
)
Est. Total I
Unit Quarter 1 Quarter 2 Error, %
A.
Fission and Activation Gases 1.
Total Release Ci 5 00E-05 0.00E+00 12.50E+01 2.
Average Release Rate for Period uC1/sec 6.36E-06 0.00E+00 3.
Percent of Technical Specification 7.41E-07 0.00E+00 1
f Limit 03 i
8.
lodines 1.
Total lodine-131 Ci
<8.70E-07
<7.62E-07 12.50E+01 2.
Average Release Rate for Period uCi/sec
<1.11E-07
<9.69E-08 3.
Percent of Technical Specification 1.11E-01 8.27E-02 Limit (2)
C.
Particulates 1.
Par'
'lates with T-1/2 > 8 days C1 4.29E-06 1.86E-06 i3.00E+01 2.
Average Release Rate for Period uCi/sec 5.46E-07 2.34E-07 3.
Percent of Technical Specification (33 (33 Limit 4.
Gross Alpha Radioactivity Ci
<5.37E-08
<4.69E-08 0.
Tritium 1.
Total Release Ci 1.16E+00' 8.59E-01 13.00E+01 2.
Average Release Rate for Period uti/sec 1.48E-01 1.09E-01 Perc'nt of Technical Specification 3.
e (3)
(33 Limit I
"I 8ased on beta-air dose which was the most limiting of either the gamma-air or beta-air dose requirements.
l (EI Technical Specification 3.11.2.3.a for dose from I-131. tritium, and radionuclides in particulate form.
(3I Per Technical Specification 3.11.2.3. dose contribution from tritium and particulates are included with I-131 above in Part 8.
R12\\35 1-
l i
TABLE 18 ERRATA Yankee Atomic Electric Compenv. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Ouarters 1992 Gaseous Eff'uents - Elevated Releases Continuous Mode Batch Mode
- Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 1.
1,f.gston Gases Krypton-85 Ci 0.00E+00 0.00E+00 5.00E-05 l
r,enon 1?3 Ci 0.00E+00 0.00E+00 0.00E+00 Xenor 131m Ci 0.00E+00 0.00E+00 0.00E+00 Tot;l for Period Ci 0.00E+00 0.00E+00 5.00E-05 l
2.
<8.70E-07
<7.62E-07 0.00E+00 Total for Period Ci
<8.70E-07
<7.62E-07 0.00E+00 3.
Particulates Strontium 89 C1
<1.25E-06
<6.85E-06 0.00E+00 i
Strontium 90 Ci
<3.19E-07
<2.33E-07 0.00E+00 Cesium-134 C1
<3.92E-07
<3.21E-07 0.00E+00 Cesium-137 C1 3.18E-08 1.04E-07 0.00E+00 Barium-Lanthanum-140 Ci
<1.27E-06
<1.05E-06 0.00E+00 Zinc 65 Ci
<9.61E-07
<7.67E-07 0.00E+00 Cobalt-58 Ci
<4.26E-07
<3.55E-07 0.00E+00 Cobalt *60 Ci 4.26E 06 1.76E-06 0.00E+00 tron-59 Ci
<9.09E-07
<7.36E-07 0.00E+00 Chromium-51 C 1'
<2.63E-06
<2.11E-06 0.00E+00 Zirconium-Niobium 95 Ci
<7.3GE-07 (6.15E-07 0.00E+00 Cerium-141 Ci
<3.33E-07
<2.68E-07 0.00E+00 Cerium-144 Ci
<1.41E-06
<1.13E 06 0.00E+00 Antimony-124 Ci
<3.81E-07
<3.21E 07 0.00E+00 Manganese-54 Ci
<4.48E-07
<3.68E-07 0.00E+00 Silver-110m Ci
<3.91C-07
<3.08E-07 0.00E+00 l
There were no batch mode gaseous releases during the second quarter.
R12\\35 2-
q p
L i
ERRATA YAEC ist/2nd Otr. 1992 Report a
Technical Snecification and Catecory liqLQ i
p c.
Liouids' L
3.11.1.1 Total sum of the fraction of i
Table II, Column 2), excluding noble gases'less than:
1.0 l
3.11.1.1 Total noble gas concentration 2.00E-04 pCi/cc I
L
'3.
' Measurements and Anoroximations of Total Radioactivity 1
J a.
Noble Gases Continuous discharges are determined by taking a grab sample from the primary vent' stack using a Marinelli gas sample container.
Errors associated with this measurement are estimated to be 125 percent.
t L,
Routine plant batch discharges do not' occur because all the
.l gaseous systems are vented, and the production of fission gases has ceased with the permanent shutdown of the facility. The only source for noble gases' is within the cladding of the spent fuel stored in the Spent Fuel Pool. There was one batch gaseous discharge associated with testing area monitors located in the Spent Fuel Pit and the Primary Auxiliary Building.
8 b.
Iodines lodines are continuously monitored by drawing'a sample from the primary vent stack through a particulate filter and charcoal cartridge. The' filter and charcoal cartridge are removed and analyzed weekly.- The errors associated with these measurements are estimated to be i25 percent.
I c.
Particulates The particulate filter. described in (b) above is analyzed weekly.
The errors associated with the determination of particulate.
j effluents are estimated to be 130 percent.
R12\\35 I-2 I
4 74
1 ERRATA YAEC 1st/2nd Otr. 1992 Report-Outdoor Routine Tank Second Quarter Batches Moats Number of batch releases:
34 4
i
-Total time period for batch releases (minutes):
9957 8460 l
Maximum time period for a batch release (minutes):
780 2820 Average time period for batch releases (minutes):
293 2115 q
l Minimum time period for a batch release (minutes):
210 1835 l-Average stream flow (Sherman Dam) during period (cfs):
468 468
, Average discharge rate (gpm):
25 4.4
)
b.
G# ses.
L
[
First Quarter Number'of batch releases:
1 Total time period for batch releases: 25 minutes Maximum time period for batch releases:
25' minutes
- Average time period for batch release:
25 minutes Minimum time period-for batch release:
25 minutes Second Quarter There were no batch releases during this period.
L
-5..
Abnormal Releases-Technical Specification 6.9.5.b requires the reporting of any unplanned releases from the site to the site boundary of radioactive material in 4
gaseous and ifquid effluents made during the reporting period.
'a.
Liauid There were no nonroutine liquid' releases during the reporting y
period.
b.
fditi.
There were no nonroutine caseous releases during the reporting period.
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