ML20078N918
| ML20078N918 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/31/1982 |
| From: | Mardis D FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 3F-0882-19, 3F-882-19, NUDOCS 8311030073 | |
| Download: ML20078N918 (39) | |
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1/1/82
.6/30/82 s
s FLORIDA POWER CORPORATION CRYSTAL RIVER - UNIT 3 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET N0. 50-302 AUGUST, 1982 4
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i TABLE'0F CONTENTS r
PAGE I
Introduction 1
s' II Releases of ~ and Doses from Gaseous Effluents 4
III Releases of and Doses from Liquid Effluents 17 IV Solid Waste Shipments 26 V
Meteorological Data 28 FIGURES III-1 Methods of Meeting 10 CFR 20, Appendix B, 21 Table II, Column 2 MPC Limits
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LIST OF TABLES PAGE I-1A Summation of Doses to Individuals from Gaseous and 2
Liquid Effluent Releases - First and Second Quarters 1-1B Summation of Doses to Population from Gaseous and 3
Liquid Effluent Releases - First and Second Quarters 11-1 Summation of Gaseous Effluent Releases 11 11-2 Summation of Nuclides in Gaseous Effluent Ground 12 Level Releases II-3 Doses to Individuals from Continuous Gaseous 13 Effluent Releases - First and Second Quarters i
II-4 Doses to Individuals from Batch Gaseous Effluent 14
'/
Releases - First and Second quarters
't 11-5 Doses to the Population from Continuous Gas;ous 15 Effluent Releases - First and Second Quarters II-6 Doses to the Population from Batch Gaseous Effluent 16 Releases - First and Second Quarters III-1 Summation of Liquid Effluent Releases 22 III-2 Summation of Nuclides in Liquid Effluent Releases 23 III-3 Doses to Individuals from Liquid Effluent Releases -
24 First and Second Quarters III-4 Doses to the Population from Liquid Effluent 25 Releases - First and Second Quarters IV-1 Summation of Solid Waste and Irradiated Fuel 27
/ ' Shipments f
V-1 Summation of Meteorological Conditions at 33' (10 29 meters) - First Quarter V-2 Summation of Meteorological Conditions at 33' (10 29 meters) - Second Quarter V-3 Summation of Meteorological Conditions at 33' (10 29 meters) Concurrent with Datch Gaseous Effluent Releases - First Quarter V-4 Summation of Meteorological Conditions at 33' (10 29 meters) Concurrent with Bach Gaseous Effluent Releases - Second Quarter
7 O
Y I
INTRODUCTION
' This Effluent and Waste Disposal Report is submitted as required by Techni-
- cal Specification 5.6.1.B of Appendix B to the Crystal River Unit 3 Facil-l ity Operating License No. OPR-72.
The data in this report covers the
, period from January 1 to June 30, 1982.
I j
There have been no changes to the Technical Specification Requirements for effluents and waste disposal in Appendix B of the Facility Operating License during the period of this report.
Crystal River Unit 3 has' had no significant measurable radiological impact on the surrounding environment during the reporting period.
This is based on the Radiological Environmental Monitoring Program data and the doses
}
calculated for individuals and the population due to effluent releases i
being significantly below the levels required by 10 CFR 50, Appendix 1.
l The summations of gaseous and liquid effluents, solid waste shipments and meteorological data are in accordance with the tables in Regulatory Guide 1.21 (Rev. 1, 6/74) Appendix B.
The~ gaseous individual and population doses are not available for this report due to failure of the meteorological tower ' historical data retrieval system. A Supplemental Report of the doses to the public will be generated as soon as the historical meteorologicel data is available.
The individual and population doses were calculated using the LADTAP (for liquid effluents) computer code obtained from the Nuclear Regulatory Conmission anc revised to include site specific data wherever possible.
These doses are sumnarized in Tables I-1A and B.
The values reported for the activity of.nuclides released are the actual measured activities.
If no activity for a nuclide was detected for a quarter, the total of the lower -limits of detection for all samples is reported as "<X.XXE-X".
The totals of activity released is a total of only the nuclides that had measured activity.
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' i TABLE I-1A SUMMATION OF DOSES TO INDIVIDUALS FROM
--- - ~~ -
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GASEGUS AND LIQUID EFFLUENT RELEASES First Quarter
-I Whole Body Dose Distance (Mi.) and Design Effluent Release Direction Age Group Organ Dose Objectives (rarem/yr)
(mrem /yr)
Not available Continuous Gaseous Not available Batch Gaseous Continuous Liquid N/A Adult N/A 4.30E-04 5.00E+00 Batch Liquid fi/A Teen N/A 1.24E-03 Organ Dose
+
Not available Continuous Gaseous Not available Batch Gaseous Continuous Liquid
~~
N/A Adult Thyroid 2.79E-03 5.00E+00 Batch Liquid N/A-Adult GI-LLI 7.22E-03 n,
Second Quarter Whole Body Dose Not available Continuous Gaseous f
~
~ Batch Gaseous Not availaM e.
...5.00E+00... _ _
Continuous Liquid N/A Teen N '4 8.05E-05 Batch Liquid N/A Teen N,..
1.07E-03 Organ Dose Not available Continuous Gaseous Not available Batch Gaseous Continuous Liquid N/A Teen Li ver-1.38E-04 5.UUE+00 Batch Liquid '
N/A' Adult GI-LLI 7.14E-03 l
l
4 TABLE I-1B SUMMATION OF DOSES TO THE POPULATION FROM GASE0US AND LIQUID EFFLUENT RELEASES First Quarter Whole Body Dose Organ Dose Effluent Release Dose Design Objectives Organ Dose
' Design Objectives (MAN-REM /YR)
(MAN-REM /YR)
(MAN-REM /YR)
~~l 'AN-REM /YR)
Continuous Gases Not available B,tch Gaseous Not available Continuous Liquid 4.67E-02 N/A Thyroid 1.73E-01 H/A Batch Liquid 1.03E-01 N/A GI-LLI 6.5UE-01
._N/A u,
Second Quarter Continuous Gaseous Not available Batch Gaseous Not available Continuous Liquid 9.12E-03 N/A Thyroid 1.56E-02 N/A Batch Liquid 1.05E-01 N/A GI-LLI 2.80E-01 N/A
7 f
II RELEASES OF AND DOSES FROM GASE0US EFFLUENTS There are three normal methods of releasing gaseous. effluents to the atmos-phere:
- 1) continuous release via the Auxiliary Building Exhaust; 2) batch release from the Waste Gas Decay Tanks; and 3) batch and continuous releases from the Reactor Building purge. All three, methods release to the atmosphere from one po4nt, the Plant Vent.
l 1.
Regulatory Limits The Technical Specification limits' for gaseous effluent releases are as follows:
i Specification 2.4.2 The terms used in these Specifications are as follows:
subscripts v, refers to vent releases 1, refers to individual noble gas nuclide (Refer to Table 2.4-5 for the noble gas nuclides considered) i QT the total noble gas release rate (Cf/sec)
=
IjQj sum of the individual noble gas radionuclides
=
determined to be present by isotopic analysis E
the average total body dose factor due to gama emission
=
(rem /yr per Ci/sec)
E the average skin dose factor due to beta emissions (rem /yr
=
per C1/sec)
R the average air dose factor due to beta emissions (rad /yr
=
per C1/sec)
R the averge air dose factor due to beta emissions (rad /yr
=
perC1/sec)
The values of K, L, M and N are to be determined each time isotopic l
analysis is required as delineated in Specification 2.4.2.J.
Deter-
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mine the following using the results of the noble gas radionuclide analysis:
E (1/Qt)IjQjKj
=
[
(1/QT)E 0 liii
=
-R (1/QT)E9Mi1i
=
R (1/4T)IjQ Nii
=
4
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where the values of Kj, Lj, Mj and Nj are provided in Table 2.4-5 and are site dependent ganna and beta dose factors.
Table 2.4-5 GAMMA AND BETA DOSE FACTORS FOR CRYSTAL RIVER UNIT 3 x/Q = 1.46 x 106 sec/m3 at 1450 meters, ENE I
Dose Factors for Vent l
, Kjy Ljy-Hjy Hjy Total Body Skin Beta Air Gamma Air Noble Gas rem /yr rem /yr radlyr rad /_yr Radionuclide Ci/sec Ci/sec C1/sec Ci/sec Kr-83m 7.0 x 10-5 0
0.92 0.035 Kr-85m 0.80 2.1 2.9 0.84 Kr-85 0.0096 2.0 2.8 0.010 Kr-87 2.5 14 15 2.6 Kr-88 6.1 3.5 4.3 6.4 Kr-89 2.79 15 15 0.83 Xe-131m 2.28 0.69 1.6 0.35 Xe-133m 0.22 1.5 2.2 0.29 Xe-133 0.26 0.55 1.5 0.31 Xe-135m 1.2 1.0 1.1 1.1 Xe-135 1.2 2.7 3.6 1.3 l
Xe-137 0.12 18 19 0.12 Xe-136 2.4 6.0 6.9 2.5 5
Q = The measured releasc. rate of! the radioiodines and radioactive materials in particulate forms with half-lives greater than eight days.
(Ci/sec)
A.
(1) The release rate limit of noble gases from the site shall be such that 2.0 (QyyE ) 11 y
and O.33 (QTv ('L'y+ 1.1Ii )) fl y
(2) The release rate limit of all radioniodines and radioactive materials in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site shall be such that 3.5 x 104 Qy 11 B.
(1) The average release rate of noble gases from the site during any calei dar quarter shall be such that 13 (QTyR ) 11 y
and 6.3 (QTvN ) 11 v
(2) The average release rate of noble gases fron the site during any 12 consecutive months shall be Ii 25 (QTV v) Il 5
13-(QTv v) 11 (3) The average release rate per si t>e of all radiciodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter shall be such that 13 (3.5 x 104 Qv)11 (4) The average release rate per site of all radiciodines and i
radioactive materials in particulate form with half-lives greater than eight days during any period of 12 consecutive months shall be that 25 (3.5 x 104 Qy)11 6
7-e (5) The amount of iodine-131 raleased during any calendar quarter shall not exceed 2 Ci/ reactor.
(6) The amount of iodine-131 released during any period of 12 consec-utive months shall not exceed 4 Ci/ reactor.
C.
Should any of the conditions of 2.4.2.C(1), (2) or (3) listed below exist, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to re-duce the release rates to design objective levels listed in Sec-tion 2.4, and report these actions to the NRC within 30 days from the end of the quarter during which the releases occurred.
(1)
If the average release rate of noble gases from the site during any calendar quarter is such that 50 (QyyW ) >l y
or N
25 (QTv v) >l (2) if the average release rate per site of all radioiodines and ra-dioactive materials in particulate form with half-lives greater than eight days during any calendar quarter is such that 4
50 (3.5 x 10 Qv) >l (3)
If the amount of iadine-131 released during any calendar quarter is greater than 0.5 Ci/ reactor.
D.
During the release of gaseous wastes from the primary system waste gas holdup system the effluent monitor for the Waste Gas Storage Tanks shall be operatet' and set to alarm and to initiate the automatic clos-ure of the waste gas discharge valve prior to exceeding the limits specified in 2.4.2. A above.
The operability of each automatic isola-tion valve listed in Table 2.4-4 shall be demonstrated quarterly.
E.
The maximum activity to be contained in one waste gas storage tank shall not exceed 47,000 Curies (considered as Xe-133). An administra-tive control has been established on Waste Gas Decay Tanks at a value lower than 47,000 curies due to conflicts in safety analyses.
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7 2.
Maximum Permissible Concentrations The maximum permissible concentrations of nuclides in gaseous releases is based on the resultant doses at the site boundary as determined from the concentrations of nuclides at the release point.
The Technical Specifica-tions provide the equations and dose factors that relate the gaseous activ-ity to be released to doses at the site boundary and restrictions are placed on instantaneous, quarterly and yearly release rates.
The gaseous releases do not exceed the concentration limits specified in 10 CFR 20 and are as lav as reasonable achievable in accordance with the requirements of 10 CFR 50.
3.
Measurements and Approximations of Total Radioactivity The gaseous effluent release via the Auxiliary Building Exhaust is treated as a continuous release subdivided into discrete periods of filter changes and the radioactivity measured as follows:
A.
Fission and Activation Gases - The total activity released is deter-mined from the net count rate of the gaseous monitor (RMA-2G), its calibration factor, and the total exhaust flow.
The activity of radiogas is determined by the isotopic distribution of radiogas in the analysis of the Auxiliary Building vent for that period.
B.
Iodines - The activity released as Iodine-131,133, and 135 is based on the charcoal cartridge activities (RMA-21), the particulate filters activities (RMA-2P) and the total vent ficw.
C.
Particulates - The activity released via particulates with half-lives greater than eight days is determined by isotopic analysis of particu-late filters (RMA-2P) and the total vent flow.
I D.
Tritium - The activity released as tritium is based on monthly grab sample analysis and total vent flow.
The radioactivity released by batch releases of the llaste Gas Decay Tanks via the Auxiliary Building Exhaust is measured as follows:
A.
Fission and Activation Gases - The activity released is based on the l
volume released and the activity of the individual nuclides cbtained j
from an isotopic analysis of a grab sample taken prior to the release.
B.
lodines - The iodines from batch releases are included in the iodine determination from the continuous Auxiliary Building releases.
C.
Particulates - The particulates from batch releases are included in the particulate determination from the continuous Auxiliary Building release.
D.
Tritium - The ~ activity released as tritium is based on a grab sample analysis of each batch and the batch volume.
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7 The radioactivity released by purge releases of the Reactor Building through the Reactor Building vent is measured as follows:
A.
Fission and Activation Gases - The activity released is determined from the net count rate of the ~ gaseous monitor (RMA-1G), the monitor calibration factor and the total vent flow.
The release of each radi-ogas is a product of the total curies released times the fraction of that radiogas in the isotopic analysis for that purge.
B.
Iodines - The total curies released as iodine-131,133 and 135 was de-termined from the charcoal cartridge activities (RMA-11) and the par-ticulate filter activities (RMA-1P).
C.
Particulate - The total curies released via particulates with half-i lives greater than eight days is determined by isotopic analysis of each purge particulate filter (RMA-1P).
l D.
Tritium The total curies released as tritium is based on grab samples taken for each purge (or the average if more than one grab sample was taken).
Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, nonsteady re-lease rates, chemical yield factors and sample losses for such items as charcoal cartridges.
A.
Fission and Activation Gas Total Release as calculated from process monitor readings and grab sample isotopics.
Monitor Statistical Error 30%
Monitor Error in Calibration 50%
Vent Flmv Rate 10%
Non-Steady Release Rate 20%
110%
B.
1-131 Total Release as calculated from charcoal and particulate filter activity.
Statistical Error 60%
Counting Equipment Calibration 10%
Vent Flow Rate 10%
l Vent Sample Flow Rate 10%
Non-Steady Release Rate 10%
l Losses from Charcoal Cartridge 10%
110%
9
C.
Particulates with half-lives greater than eight days release as calcu-lated from particulate filter activities.
Statistical Error 60%
Counting Equipment Calibration 10%
Vent Flow Rate 10%
Vent Sample Flow Rate 10%
Non-Steady Release Rate
'10%
100%
0.-
Total Tritiun release as calculated from periodic grab sample analy-ses.
Water Vapor in Sample Stream Determination 20%
Vent Flow Rate 10%
Counting Calibration and Statistics 10%
Non-Steady Release Rate 50%
90%
4.
Batch and Unplanned Releases The batch gaseous effluent releases may be summarized as follows:
First Second Quarter Quarter Number of Batch Releases 1.30E+01 1.00E+01 Total time for all releases (minutes) 2.48E+03 2.28E+03 Maximum time for any one release (minutes) 5.27E+02 5.23E+02 Average time for all releases (minutes) 1.91E+02 2.28E+02 Mininum time for any one release (minutes) 5.00E+00 5.00E+00 Number of Unplanned Releases 6.00E+00 4.00E+00 Total Unplanned Activity Released (Curies) 2.69E-01 3.52E-05 The summation of gaseous effluent releases is in Table 11-1 and the sunnia-tion of nuclides in gaseous effluent ground level releases is in Table 11-2.
The summation of doses to individuals and populations is not included in this Report due to the failure of the historical meteorological data retrieval unit.
A Supplemental Report will be issued to incorporate gas-eous dose data as soon as the data is available.
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7 The unplanned releases for the first and second quarters of 1982 are list-ed below giving the date, the Nonconforming Operations Report Number, and the cause of each release.
1-10-82 82-007 Possible unmonitored release from the steam re-lief valves during a plant trip.
1-29-82 82-028 Possible unmonitored release from the steam re-lief valves during a plant trip.
3-2-82 82-062 Possible unmonitored release from the steam re-lief valves during a plant trip.
3-16-82 82-081 RM-A2 tripped due to improper valve line-up allowing gas release.
3-30-82 82-101 Possible unmanitored release from the steam re-lief valves during a plant trip.
3-31-82 82-103 RM-A2 tripped due to unidentified release of gas.
5-19-82 82-141 Possible unmonitored release from the steam re-lief valves during a plant trip.
5-30-82 81-154 Possible unmonitored release from the steam re-lief valves during a plant trip.
6-17-82 82-163 Possible unmonitored release from the steam re-lief valves during a plant trip.
6-20-82 82-166 Possible unmonitored release fran the steam re-lief valves during a plant trip.
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7 TABLE 11-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL. REPORT - 1/1/82 - 6/30/82 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES r
Unit Quarter Quarter Est. Total 1
2 Error %
.A.
Fission and Activation Gases l
1.
Total Release C1 1.61E+03 1.74E+03 1.10E+02 l
2.
Average Release Rate for Period Ci/sec 1.03E+02 1.10E-04 l
3.
Percent of Technical Specification Limit 1.04E+00 8.83E-01 B.
Iodines 1.
. Total Iodine - 131 Ci 3.96E-04 1.73E-04 1.01E+02 2.
Average Release Rate for Period Ci/sec 2.52E-11 1.09E-11 3.
Percent of Technical Specification Limit 7.92E-02 8.63E-03 C.
Particulates i
1.
Particulates with half-lives > 8 days Ci 2.02E-03 2.36E-04 1.00E+02 2.
Average Release Rate for Period Ci/sec 1.28E-10 1.49E-11 3.
Percent of Technical Specification Limit 7.33E-03 6.79E-04 4.
Gross Alpha Radioactivity C1 1.29E-07 1.60E-08 D.
Tritium f
1.
Total Release Ci 7.39E+00 7.59E+00 9.00E+01 2.
Average R'elease Rate for Period C1/sec 4.70E-01 4.81E-01 3.
Percent of Technical Specification Limit 4.76E+00 4.88E+00 n
11 e
v TABLE 11-2 EFFLUENT AND BAS'TE DISPOSAL SEMIANNUAL REPORT - 1/1/82 - 6/30/82 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES CONTINU0US MODE BATCH MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 1.
Fission gases krypton-85 Ci 6.31E+02 8.15E+01 1.92E+00 8.52E-01 krypton-85m Ci 8.12E-01 5.13E-01 3.70E-02 3.~531-02 krypton-87 krypton-88
~~
Ci
<l.55E+01 7.20E-02 7.03E-03
<4.78E-03 Ci 2.54E+00 6.09E-02 2.48E-02 1.46E-02 krypton-89 Ci
<2.03E+04
<1.54E+04
<l.82E+01
<4.43E+00 xenon-133 Ci 8.15E+02 1.48E+03 4.14E 01 3.12E+01 xenon-135 Ci 5.44E+01 6.82E+01 2.80E-01 4.42E-01 xenon-135m Ci
<2.74E+01 3.59E+00
<3.35E-02
<8.35E-Q3 xenon-137 Ci
<3.30E+03
<2.46E+03
<3.42E+00
<7.98E-01 xenon-138 Ci
<l.18E+02
<9.94E+01
<7.49E-02
<3.31E-02 argon-41 Ci 5.86E+01 6.11E+01 1.49E-01 1.89E-01 xenon-133m Ci 3.95E+00 1.64E+01 1.56E-01 2.09E-01 xenon-131m Ci
<2.83E+02
<2.63E+02 1.82E+00 1.65E-01 unidentified Ci E
E E
E Total for Period Ci 1.57E+03 1.?lE+03 4.58E+01 3.31E+01 lodines iodine-131 Ci 2.37E-04 1.41E-04 2.39E-04 5.13E-05 iodine-f33 Ci 3.59E-04 4.25E-02
<1.14E-04
<5.96E-05 iodine-135 Ci
<2.77E-01
<2.46E-01 (2.58E-02
<3.32E-02 Total for Period Ci 5.95E-04 4.27E-02 2.39E-04 5.13E-05 3.
Particulates strontium-89 Ci 5.50E-06 2.27E-05
<1.60E-03
<2.16E-10 strontium-90 Ci
<2.46E-01 8.27E-05
<1.19E-03
<2.06E-10 cesium-fl4 Ci
<1.18E-06
<l.24E-06 7.75E-04 5.01E-05 cesium-137 Ci 9.88E-08 3.50E-07 1.06E-03 1.010-04 barium-lathanum 140 Ci
<7.72E-06
<8.39E-06 2.09E-05 l~.' 12 E-05 cobalt-57 Ci
<5.96E-07
<6.53E-07
<1.06E-05
<1.35E-06 cobalt-58 C1 2.19E-07 1.40E-07 2.80E-05
<1.90E 06 cobalt-60 Ci 3.14E-07 7.33E-07 2.51E-05 1.66E-06 chromium-51 Ci
<8.53E-06
<9.19E-06
<l.83E-04
<2.19E-05 manganese-54 Ci
<l.2TE-06
<1.22E-06 4.14E-05
<1.93E-06 iron-59 Ci
<3.48E-06
<3.48E-06
<3.51E-05
<4.61E-06 zinc-65 Ci
<2.59E-06
<2.72E-06
<2.35E-05
<5.44E-06 niobium-95 Ci
<1.3dl-06
<l.19E-06
<1.29E-05
<2.52E-06 zirconium-95 Ci
<2.05E-06
<2.07E-06
<2.30E-05
<3.20E-06 silver-110m Ci
<1.51E-06
<1.70E-06
<1.91E-05
<2.11E-06 antimony-126 Ci
<1.23E-06
<1.26E-06
<1.04E-05 1
<1.62E-06 cerium-141 Ci
<l.36E-06 2.35E-07
<1.88E-05
<3.00E-06 gross alpha Ci E
E Total excluding C1 6.13E-06 3.34E-05 1.95E-03 1.84E-04 gross alpha 12
.k TABLE II-3 Doses to Individuals from Continuous Gaseous Effluent Releases FIRST QUARTER Whole Body Dose Organ Dose Distance Distance (Mi.) and Dose (Mt.) and Dose Pathway _
Direction
. Age Group (mrem /yr)
Direction Age Grcup Organ (mrem /yr)
Plume Immersion Not available*
Ground Contamination Not available*
Inhalation Not available*
Vegetable Consumption Not available*
Cow Milk Consumption Not available*
Goat Milk Consumption Not available*
Meat Consumption Not available*
Total t;
SECOND QUARTER 1
Whole Body Dose Organ Dose Distance Distance (Mi. ) and Dose (Mi.)and Dose Pathway Di rection Age Group (mrem /yr)
Direction Age Group Organ (mrem /yr)
Plume Immersion Not available*
Ground Contamination Not available*
Inhalation Not available*
Vegetable Consumption Not available*
Cow Milk Consumption Not available*
Goat Milk Consumption Not available*
Meat Coasumption Not available*
Total Not available*
- Meteorological data retrieval system failure precluded inclusion of gaseous doses in the Report. A Supplemental Report will be issued when the meteorological data has been translated from recorder charts to magnetic tapes and processed accordingly.
\\
f TABLE 11-4 Doses to Individuals from Batch Gaseous Effluent Releases FIRST QUARTER Whole Body Dose Organ Dore Distance Distance (Mi.)and Dose (Mi.) and Dose Pathway Direction Age Group (mrem /yr)
Direction Age Group _
Organ (mrem /yr)
Plume Immersion Not available*
Ground Contamination Not available*
Inhalation Not available*
Vegetable Consumption Not available*
Cow Milk Consumption Not available*
Goat Milk Consumption Not available*
Meat Consumption Not available*
Total Not available*
g; SECOND QUARTER Whole Body Dose Organ Dose Distance Distance (Mi.) and Dose (Mi.) and Dese Pathway Direction Age Group (mrem /yr)
Direction Age Group Organ (mrem /yr)
Plume Immersion Not available*
Ground Contamination Not available*
Inhalation Not available*
v getable Consumption Not available*
e
' ow Milk Consumption Not available*
Goat Milk Consumption Not available*
Meat Consumption Not available*
Total Not available*
- Meteorological data retrieval systen failure precluded inclusion of gaseous doses in the Report. A Supplemental Report will be issued when the meteorological data has been translated from recorder charts to magnetic tapes and processed accordingly.
TABLE II-5 Doses to the Population from Continuous Gaseous Effluent Releases FIRST QUARTER i
Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Plume Immersion
~
Not available*
Ground Contamination Not available*
Inhalation Not available*
Vegetable Consumption Not available*
Milk Consumption Not available*
Meat Consumption Not available*
Total Not available*
l SECOND QUARTER i
Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Plume Immersion iiut availabie" Ground Contamination Not available*
Inhalation Not available*
Vegetable Consumption Not available*
hilk Consumption Not available*
Meat Consumption Not available*
l Total Not available*
- Meteorological data retrieval system failure precluded inclusion of gaseous doses in the Report. A Supplemental Report will be issued when the meteorological data has been translated from recorder charts to magnetic tapes and processed accordingly.
15 w
~
T TABLE II-6' Doses to the Population from Batch Gaseous Effluent Releases FIRST QUARTER Whole Body Dose Organ Dose Pathway _
(Man-Rem)
Organ Dose (Man-Rem)
Plume Immersion Not available*
Ground Contamination Not available*
Inhalation Not available*
l Vegetable Consumption Not available*
I Milk Consumption Not available*
Meat Consumption Not available*
]
Total Not available" SECOND QUARTER Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Plume Immersion Not available*
Ground Contamination Not available*
Inhalation Not available*
Vegetable Consumption Not available*
Milk Consumption Not available*
Meat Consumption Not available*
Total Not available*
- Meteorological data retrieval system failure precluded inclusion of gaseous doses in the Report. A Supplemental Report will be issued when the meteorological data has been translated from recorder charts to magnetic tapes and processed accordingly.
I r
16
O O
111 RELEASES OF AND DOSES FROM LIQUID EFFLUENTS There are three sources of liquid effluents released to the discharge canal:
- 1) the Laundry and Hot Shower Sump, 2) the Evaporator Condensate Storage Tanks and 3) the Regeneration Waste Neutralization Tank.
The Laundry and Evaporator Condensate are batch type releases made through the plant liquid release monitor RML-2. The Regeneration Waste Tank discharges are continuous type releases made through the plant liquid release monitor RML-7.-
1.
Regulatory Limits l
The Technical Specification limits for liquid effluent releases are as follows:
Specification 2.4.1 A.
The instantaneous concentration of radioactive materials released in liquid waste effluents from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B,
Table II, Column 2, for unrestricted areas.
B.
The cumulative release of radioactive materials in liquid waste effluents excluding tritium and dissolved gases, shall not exceed 10 C1/ reactor / calendar quarter.
C.
The cumulative release of radioactive materials in liquid waste effluents excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months.
D.
During release of radioactive wastes, the effluent control moni-tor shall be set to alarm and to initiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in 2.4.1.A above.
E.
The operability of each automatic isolation valve in the liquia radwaste discs,arge lines shall be demonstrated quarterly.
F.
The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected cumula-tive release could exceed 1.25 Ci/ reactor / calendar quarter, exclud'ng tritium and dissolved gases.
G.
The maximum ridioactivity to be contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved gases.
H.
If the cumulative release of radioacti ve materials in liquid effluents, excluding tritium and dissolved gases, exceeds 2.5 Ci/
reactor / calendar quarter, the licensee shall make an investiga-tion to identi fy the causes for such releases, define and 17 s
m
7 initiate a program of action to reduce such releases to the design objective levels listed in Section 2.4, and a report of these actions shall be made to the USNRC in accordance with Sec-tion 5.6.2.C(1).
2.
Maximum Permissible Concentrations The maximum permissible concentration values used in determining allowable liquid radwaste release concentrations are taken from 10 CFR Part 20, Ap-pendix B, Table II, Column 2.
Release rate and dilution ratio for each batch are determined by a mixed nuclide MPC calculation performed beforo the release of the batch. To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission reactor have been grouped according to MPC value and type of radiation as shown in Figure III-1.
The concentration of each of the 23 gamma emitting nuclides specifically noted in Figure 111-1 is measured individually because of interest in that nuclide.
For any of the 23 nuclides not detected in the gama scan, the l
MDA Limit is computed from the measured data for that sample.
Only twp pure beta emitters, Sr-89 and Sr-90, have MPC values less than 9 x 10-0 pCi/ml.
Individual measurements are made on proportional compos-ite liquid radwaste samples to determ'ne the Sr-89 and Sr-90 concentration or MDA value to be applied to individual batch release calculations.
Although the MPC limit for tritium is greater than 9 x 10-6 pCi/ml, a sepa-rate measurement is made for tritium. A distillation and liquid scintilla-tion counting technique is used to measure tritium concentration.
The measured and calculated concentration valuas for each batch are used to calculate the dilution ratio, release rate, and dilution rate prior to release of each batch.
Both the concentration and release data are stored on a computer disc file.
The disc file data is used to assure that quar-terly and annual release limits are not exceeded.
Bases used for the data of Table 111-1 are as follows:
A.
Fission and activation products - The total release values (not including tritium, gases, alpha) are comprised of the sum of the indi-vidual radionuclide activities in each batch released to the discharge canal for the respective quarter. These values represent the activity known to be present in the liquid radwaste effluent.
Percent of applicable limit is determined from a mixed nuclide MPC calculation.
The average concentration for each nuclide summed over all batches is divided.by the corresponding individual MPC value.
The sum over all nuclides of the C/MPC raties times 100 is the percent of applicable limit for effluent releases during the quarter.
B.
Tritium - The measured tritium concentration in a composite sample is used to calculate the total release and average diluted concentration during each period.
Average diluted concentration divided by the MPC 18 r
L
_r n
.s v
limit, 3 x 10-3 uCi/ml, is converted to percent to give the percent of applicable limit.
C.
Dissolved and entrained gases Concentrations of dissolved and entrained gases in liquid effluents are measured renthly by Ge(Li) spectroscopy on a sainple from a representative liquid radwaste batch.
Dissolved and entrained gases for which measured or MDA concentrations are determined include noble gases with half lives greater than 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s: Xe-135, Xe-133m, Xe-133, and Kr-85.
lodine radionuclides in any form are determined during the isotopic analysis for each batch, therefore a separate analysis for possible gaseous forms is not per-formed because it would not provide additional information.
l A consprvative release limit, the maximum sensitivity limit of 4 x 10-3 pCi/ml of each dissolved and entrained radionuclide as speci-fied in Table Note 5, Table 2.4-1, Environmental Technical Specifica-tions, has been applied in determining the percent of applicable limit.
3.
Measurements and Approximations of Total Radioactivity Details of the analytical procedures for liquid radwaste analysis are as follows:
Measurement Frequency Method 1.
Gamma Isotopic Each Batch Ge(Li) spectrometry with on-line computer 2.
Gross Beta Each Batch Liquid scintillation 3.
Sr-89 Monthly Composite Chemical separation and gas flow proportional counting 4.
Sr-90 Monthly Composite Chemical separation and gas flow proportional counting 5.
Tritium Monthly Composite Distillation and liquid scintillation counting 6..
Alpha Monthly Composite Gas flow proportional counting.
7.
Dissolved Gases One Batch / Month Ge(Li) spectrometry with on-line computer Estinated errors are based on errors in counting equipment calibration, counting statistics, nonsteady release flow rate, chemical yield factors, sampling and mixing losses, and volume determinations.
(
A.
Fission and Activation Products Total Release as calculated for each
(
batch.
Statistical Error at MDA 60%
Waste Volume 10%
~
Counting Equipment Calibration 10%
Sampling and Mixing 20%
100%
19
,. +
B.
Total Tritium Release as calculated from a monthly composite.
Waste Volume 10%
Counting Equipment Calibration 10%
Sampling and Mixing 20%
40%
C.
Dissolved and Entrained Gases Total Release as calculated fran one batch per month.
Statistical Error at )DA 60%
Waste Volume 10%
Counting Equipment Calibration 10%
Sampling and Mixing 20%
100%
D.
Total Gross Alpha Radioactivity Release as calculated from a monthly composite.
Statistical Error at MDA 60%
Waste Volume 10%
Counting Equipment Calibration 10%
Sampling and Mixing 20%
100%
4.
Batch and Unplanned Releases The batch liquid effluent releases may be summarized as follows:
First Second Quarter Quarter Number of Batch Releases 1.17E+02 1.26E+02 Total Time for all Releases (minutes) 5.95E+03 6.00E+03 Maximum Time for any one Release (minutes) 2.43E+02 6.20E+02 Average Time for all Releases (minutes) 5.10E+01 4.80E+01 Minimum time for any one Release (minutes) 9.00E+00 1.00E+01 Average dilution flow of Units 1, 2, and 3 during all Releases (liters / minutes) 5.39E+06 4.49E+06 Number of Unplanned Releases 0.00E+00 0.00E+00 Total Unplanned Activity Releases (Curie) 0.00E+00 0.00E+00 The summation of liquid effluent releases is in Table III-1 and the summa-tion of nuclides in liquid effluent releases is in Table III-2.
These re-leases are based on the dilution of the radioactive liquid effluent by the condenser cooling and nuclear services water of Unit 3.
The d6ses to individuals from liquid effluent releases are in Table III-3 and the ' doses to the population from liquid effluent releases are in Table III-4.
These doses are based on the dilution of the radioactive liquid effluents by the condenser cooling water of Units 1, 2, and 3.
There were no unplanned releases for the first and second quarters of 1982.
20
Figure III-1 METHODS OF MEETING 10 CFR 20, APPENDIX B, TABLE II, COLUMN 2 MPC LIMITS MPC RANGE GAMMA-RAY BETA ALPHA 19C1/ml)
EMITTERS EMITTERS EMITTERS 1-131, I-132, I-133 Sr-89, Sr-90 l
I-135, Cs-134 (Separation and Gas (9 x 10-6 Flow Counting)
(Ge(L1) Gamma-Ray Spectroscopy)
All (Gas Flow Counting 10gitivity Sen pCi/ml as Pu-239)
Ba-La-140, Na-24, Cu-64 Tritium Co-60, Fe-59, 2n-65 (Distallation and LiquidScintjllation
>9 x 10-6 Ag-110m, Mn-54, Co-58 Counting 10- pC1/ml)
Zr-Nb-95, Cs-Ba-137 As-76. F-18, Cr-51 All others Np-239, Ce-141 (Liquid Scin Counting 10 gillation pCi/ml as Cs-137)
Mo-Tc-99, Ce-Pr-144 (Ge(L1) Gama-Ray Spectroscopy) 21 3_
n
TABLE 111-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1/1/82 - 6/30/82 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1
2 Error %
A.
Fission and Activation Products 1.
Total Release (not including tritium, gases, alpha)
Ci 2.49E-02 9.36E-03 1.00E+02 2.
Average diluted concentration during period Ci/ml 4.05E-14 1.91E-14 3.
Percent of applicable limit 1.88E+00 1.65E-01 B.
Tritium 1.
Total Release, Batch Mode Ci 1.95E+01 3.81E+01 4.00E+01 2.
Average diluted concentration during period Ci/ml 3.18E-11 7.79E-11 3.
Percent of applicable limit 1.06E+00 2.60E+00 4.
Total release, Continuous Mode Ci 3.19E-01 1.33E-01 4.00E+01 C.
Dissolved and entrained gases 1.
Total release Ci 5.97E-01 4.42E-01 l 1.00E+02 2.
Average diluted concentration during period, Batch Mode Ci/ml 9.72E-13 9.03E-13 3.
Percent of applicable limit, Batch Mode 2.43E+00 2.26E+00 D.
Gross alpha radioactivity 1.
Total release Ci 9.86E-05 9.91E-06 1.00E+02 l
E.
Volume of Waste released (prior to dilution) l l
I 1.
Batch and Continuous Modes liters 2.33E+07 1.59E+07 1.00E+01 l
F.
Volume of dilution water used during period 1.
Batch and Continuous Modes liters 6.32E+11 5.88E+11 1.00E+01 22 m
I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1/1/82 - 6/30/82 LIQUID EFFLUENTS CONTINUGUS MODE BATCH MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 strontium-89 Ci 8.47E-06
<2.92E-05 2.08E-04 5.04E-05 strontium-VO Ci 1.13E-05
< f!b4E-05 4.50E-05 2.97 E-05
~
cesium-134 Ci 8.35E-04 1.12E-04 1.20E-03 1.22E-03 cesium-13'7~
Ci 1.77E-03 3.84E-04 1.60E-03 1.96L-03 iodine-131 Ci 2.09E-03
<2.62E-04 9.34E-04 7.06E-05 cobalt-58 Ci 2.02E-04 4.75E-06 8.72E-03 1.73E-03 cobal t-60 Ci 1.06E-04 3.91E-05 2.35E-03
_1.83E-03 iron-59 Ci 3.36E-05
<6.16E-04 1.40E-04 8.82E-06 zinc-65 Ci
<7.78E-04
<5.11E-04 1.08E-J6
<9.08E-05 manganese-54 Ci
<3.84E-04
<2.24E-04 1.55E-04 1.00E-04 chromium-51 Ci
<3.63E-03
<2.02E-03 6.83E-05 (4.96E-04 zirconium-niobium-95 Ci
<1.00E-03
<6.16E-04 1.20E-04 1.03E-04 molybdenum-79 Ci
<2.49E-03
<1.55E-03 4.23E-05
<3.10E-04
~
tecnnetium-99m Ci
<3.65E-04
<2.06E-04 7.60E-05 5.13E-06 EaFium-lantnanum-140 Ci 1.44E-05
<1.19E-03 1.91E-03 1.50E-04 cerium-141 Ci
<6.97f!04
<4.01E-04
- 2. T2 E-06
<1.29t-04 sodium-24 Ci 6.90E-05
<2.91E-04
<4.63E-05
<2.95E-05 cop _per Ci
<7.70E-02
<5.28E-02
<7.f3E-03
<4.46E-03 todine-135 Ci
<1.18E-03
<7.77E-04
<1.10E-04 2.42E-06 silver-110m Ci
<4. 73E-04
<3.07E-04 8.06E-05 2.94E-04 iodine-132 Ci
<4.75E-04
<2.85E-04 3.58E-04
<3.74E-05 arsenic-76 Ci
<8.78E-04 1.69E-05
<2.24E-04
<1.24E-04 iodine-133 Ci 4.57E-04
<2.40E-04 3.64E-06 3.36E!'06 neptunium.-239 Ci
<2.98E-03
<1.77E-03 (6.67E-04
<3.92E-04 cerium-144 Ci
<2.90E-03
<1.70E-03 7.14E-05 6.74E-04 zirconium-niobium-97 Ci 0.00E+00 0.00E+00 0.00E+00 1.23E-05 cesium-136
~~Ci 1.09E-04 0.00E+00 0.00E+00 9.89E-06 cobalt-57 Ci 0.00E+00 2.08E-06 1.19E-06 5.02E-07 rubidium
~
Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ruthenium-l03 Ci 0.00E+00 0.00E+00 1.02E-05 0.00E+00 antimony-125 Ci O.00E+00 1.33E-05 9.19E-04 4.17E-04 antimony-124 Ci 0.00E+00 0.00E+00 7.10E-05 4.50E-05 unidentified Ci E
E E
E xenon-133 Ci 2.18E-02 3.61E-04 5.60E-01 4.27E-01 xenon-135 Ci 1.59E-03 1.10E-05 4.01E-03 7.55E-03 23 k
ib tsh
- bbM!NbNbbh
~~T' TABLE 111-2 (Continued)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1/1/82 - 6/30/82 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 krypton 85 Ci
<1.38E-01 1.41E-03 2.72E-03
<1.90E-02 xenon 133M Ci 1.70E-03
<2.16E-03 5.41E-03 5.37E-03 xenon 131M Ci
<2.0SE-02
<l.19E-02 (6.00E-03
<4.20E-03 k_rypton 8bM Ci
<4.44E-04
<2.61E-04 9.57E-06 1.84E-05 C1 B-187 Ci 0.00E+00 3.57E-05 1.11E-05 1.36E-05 Nb-95m Ci 0.00E+00 0.00E+00 0.00E+00 2.53E-05 Mn 56 Ci 0.00E+00 0.00E+00 2.79E-07 0.00E+00
~
Sb-136 Ci 0.00E+00 0.00E+00 2.lbE-06 0.00E+00 Zn-69m Ci 5.12E-05 0700E+00 0.00E+00 0.00E+00 I Total for period (above)
Ci 5.75E-03 6.07E-04 1.91E-02 8.75E-03 9&
23a
a TABLE III-3 Doses to Individuals from Liquid Effluent Releases FIRST QUARTER - CONTINUOUS RELEASES Whole Body Dose Organ Dose Dose Dose Pathway Age Group (mrem /yr)
Age Group Organ (mrem /yr)
Fish Adult 3.21E-04 Adult Thyroid 1.26E-03 Invertebrates Adult 7.79E-05 Adult Thyroid 1.50E-03 Shoreline Use Teen 1.77E-04 Teen GI-LLI 1.77E-04 Total Adult 4.30E-04 Adult Thyroid 2.79E-03 SECOND QUARTER - CONTINUOUS RELEASES Whole Body Dose Organ Dose Dose Dose Pathway Age Group (mrem /yr)
Age Group Organ Imrem/yr)
Fish Adult 5.96E-05 Teen Li ver 8.42E-05 Invertebrates Adult 1.05E-05 Adult GI-LLI 1.45E-05 Shoreline Use Teen 4.09E-05 Teen Skin 4.77E-05 Total Teen 8.05E-05 Teen Li ver 1.38E-04 r
FIRST QUARTER - BATCH RELEASES 1
Whole Body Dose Organ Dose Dose Dose Pathway Age Group (mrem /yr)
Age Group Organ
_(mrem /yr)
Fish Adult 5.62E-04 Adult GI-LLI 4.03E-03 Invertebrates Adult 3.70E-04 Adult GI-LLI 3.09E-03 Shoreline Use Teen 5.45E-04 Teen GI-LLI 5.45E-04 Total Teen 1.24E-03 Adult GI-LLI 7.22E-03 SECOND QUARTER - BATCH RELEASES t
Whole Body Dose Organ Dose Dose Dose Patnway Age Group (mrem /yr)
Age Group Organ (crem/yr)
Fish Adult 6.25E-04 Adult GI-LLI 5.00E-03 Invertebrates Adult 2.15E-04 Adult GI-LLI 2.05E-03 Shoreline Use Teen 5.16E-04 Teen Skin 6.05E-04 Total Teen 1.07E-03 Adult GI-LLI 7.14E-03 24
\\
_.w r
TABLE III-4 Doses to the Population from Liquid Effluent R21 eases FIRST QUAfklEN '- CONTINUOUS RELEASES Whol Body Dose Organ Dose Pathway (1an-Rem)
Organ Dose (Mah-Rem)
Sport fish x
4.55E-02 Inyroid 1.29E-01 Commercial Fish
- 4.67E-05 Thyroid 1.02E-04 Sport Invertebrate ~
'3.14E-04 Thyroid 4.30E-02 Commercial Invertebrate 2.22E-05 Thyroid 2.39E-04 Shoreline Use 7.93E-04 Skin 9.26E-04 Swinning 3.87E-06 Thyroid 3.87E-06 Boating 3.87E-06 Thyroid 3.87E-06
+
Total
[
4.67E-02 Thyroid 1.73E-011 g
SECOND QUARTER - CONTINUOUS RELEASES Whole Body Dose Organ Dose Pathway (Han-Rem)
Organ Dose (Man-Rem)_
Sport Fish
> 8.49E-03 Liver 1.49E-02 Comoercial Fish
' 2 8.75E-06 Liver 4.54E-05 Sport Invertebrate
'4.35E-04 Liver 6.59E-04 Connercial Invertebrate 3.14E-06 Liver 4.75E-06 Shoreline Use 1.83E-04 Skin 2.14E-04 Swintaing 4.77E-07 Thyroid g.77E-07 4
., Boating 4.77E-07 Thyroid 4.77E-07 Total 9.12E-03 Liver
. "1.56E-02 QRST QUARTER - BATCH RELEASES T
Whole Body Dos 9 Organ Dose Pathway (Man-Rem).
Organ' Dose (Man-Rem)
' Sport Fish c
8.37E-02 GI-LLI s C41E-01 Commercial Fish 8.57E-05
' GI-LLI 5.36E-04 Sport Invertebrate 1.69E-02 GI-LLI x LO8E-01 Coanercial Invertebrate 1.20E-04 GI-LLI '.
7.56E-04 Shoreline Use 2.44E -03 Skin 2.86E-03 Swimming 1.85E-05 Thyroid
-1.85E-05 Boating 1.85E-05 Thyroid
,1,. 8 S E -05 Total 1.032-01 GI-LLI 6.50E-01 SECOND QUARTER
'6ATCH RELEASES Whole Body Dase Organ Dose Pathway (Man-ifem)
Organ Dose (Man-Rem)
Sport fish 9.24E-02 GI-LLI 6.96E-01 Commercial Fish 9.52E-05 GI-LLI 6.68E-04 Sport Invertebrate 9.87E-03 GI-LLI 8.25E-02 Comaercial Invertebrate 7.08E-05 GI-LLI 5.89E-04 Shoreline Use 2.31E-03 Skin'
'l?/1E-03 s
Swimming 1.01E-05 Tnyroid-1.01E-05 Boatin9 1.01E-05; Thyroie 1.01E-05
\\
Total 1.05E-01 GI-LLI 2.80E-01 25
\\
J
U IV. SOLID WASTE SHIPMENTS Solid waste shipments from the plant may include irradiated fuel, solidi-fied liquid waste and compressed solid waste.
1.
Regulatory Limits The Technical Specifications for solid waste shipment are as follows:
Specification 2.4.3 A.
The total curie quantity and principle radionuclide composition shall be determined by measurement or estimates for all radioac-l tive solid waste shipped offsite.
l B.
Reports of the radioactive solid waste shipments, volumes, prin-I l
ciple radionuclides, and total curie quantity, shall be submitted in accordance with Section 5.6.1.
l The summation of solid waste and irradiated fuel shipments is in l
Table IV-1.
I
)
r 26
^'
1
7 TABLE IV-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1/1/82 - 6/30/82 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
50'.1D WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Non irradiated fuel)
First 1.
Type of waste Unit 6-month Est. Total period Error, %
a.
Spent resins, filter sludges, evaporator m3 1.60E+02 bottoms, etc.
Ci 2.22E+02 3.70E+01 b.
Dry compressible waste, contaminated m 3 2.48E+02 equip, etc.
Ci 5.72E+00 6.50E+01 c,
Irradiated components, control m
E+
3 rods, etc.
Ci E+
E+
c.
Other (describe) 3 E+
m Ci E+
E+
2.
Estimate of major nuclide composition (by type of waste) a.
Cs-137 5.46E+01 Cs-134 3.42E+01 Co-58 5.71E+00 Co-60 4.10E+00 Mn-54 8.12E-02 E+
E+
E+
b.
Cs-137 3.82E+01 Cs-134 2.63E+01 Co-58 1.68E+01 Co-60 4.04E+00 I-131 6.28E+00 c.
E+
E+
E+
E+
E+
E+
E+
E+
3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination 27 Transport Truck Chem-Nuclear Systems, Inc.
Exclusive Use Vehicle Barnwell, SC
~
6 Transport Truck U.S. Ecology Exclusive Use Vehicle Richland, Washington 27 m
T TABLE IV-1 (Cont'd)
B'., IRRADIATED FUEL SHIPMENTS (01sposition)
Number of Shipments Mode of Transportation Destination None tiR NR
)
ed i
27a r
I
~ M* mwm m
~ ^ ~ ~
m e
(
V METEOROLOGICAL DATA The meteorological data at 33 feet (10 meters) is summarized in Tables V-1 (for the First Quarter), V-2 (for the Second Quarter), V-3 (concurrent with batch gaseous effluent releases - First Quarter), and V-4 (concurrent with batch gaseous effluent releases - Second Quarter).
The classification of atmosphere stability is as follows:
Stability Pasq'uill Temperature change Classification Categories with height ( C/100m)
Extremely unstable A
<-1.9 Moderately unstable B
>-1. 9 to <-1. 7 Slightly unstable C
1-1. 7 to <-1. 5 Neutral D
>-1. 5 t o <-0. 5 Slightly stable E
l-0. 5 to < 1.5 Moderately stable F
2,1. 5 to < 4.0 Extremely stable G
2, 4.0 28
m c
(
TABLES V-1, V-2, V-3 & V-4 The meterological data summaries for the first and second quarters 1982, are not available for this report due to the failure of the meteorological data system magnetic tape unit. This data is being transcribed from avail-able strip charts onto magnetic tape for inclusion into the GASPAR program.
A Supplemental Report including the meteorological data and i
resulting dose values will be submitted as soon as the data retrieval and l
analysis is completed.
l 29
m g
~
~W
' b F,OC1. EAR-
. [5p,q
-c _. CSAFETY ;
cv t;/ A AN#LYSISo T' ENTER -
j
.;p.,ted (a.
(fp~aW i theelectrac s
'utdttV inIntry
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- Elecsc Rmer.
a 7
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- $ h May)7, 1982.-
g
/
Sg g uu y d"""'
-T0i B&W Owner's Group Executive Comittee Members {
SUBJECT:
EPRI/NSAC Efforts Useful for B&W Owner's Group
-ResponsiveLto the. requests in _ the. last executive comittee meeting, I am mailing you the following information:
Egg F (1)
"Using RETRAN-02 and DYN0DE-P to Analyze Steam Generator Tube Breaks",
p S1
~ NSAC-47 draft ' report by J. Chao,. B. Chexal, W. Layman, D. Rautmann, C. Peterson and L. Cress, May 1982.
(2)<
Y "EPRI Publications Pertinent to Pressurized Thermal Shock", October 1981 - May 1982.
g3.(3)-
" Fluid <and Thermal Mixing in a.Model Cold Leg and Downcomer With
^
Vent Valve Flow", EPRI NP-2227, March 1982.
ghs4 (4)-
" Revised List of NSAC Reports", May:1982.
In addition,--I am mailing ~you a copy.of the letter from Public Service Company
- of Oklahoma to Mr.~ liarold Denton 'regarding cancellation of Black Fox Station
' Units 1 and 2.
There. was interest expressed in receiving this by some
- members in ~the last meeting, gg 4,
_o If you have any questions or comments please contact me at (415) 855-2997.
-Sincerely, n
Bi i Chexal
- NSAC Project Manager-
. Generic' Issues. Program BC/dde Enclosuresi cc: -D.'Rossin-1Ri Breen W. Layman-J3412 HJherAwnue Ibst OfhceIka X1412 11%AluCA94303 -
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NSAC REPORTS l
TITLE Date Contact Phone # (415) 1 Analysis of Three Mlle Island Unit 2 Accident 2
Mitigation of Small-Break LOCAs in Pressurized Water Reactor Systems 3/80 B. Layman 855-2013 3
Analysis and Evaluation of Crystal River - Unit 3 Incident 3/80 G. Thomas 855-2057 4
Application of Aerospace Failure Reporting Systems to Power Plants 3/80
- 8. Chexal 855-2997 5
Computer S stems Interface Guidelines for Nuclear Plants 6/80 B. Lava 11ee 855-2038
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6 Workshop on Nuclear Plant Safety Data Acquisition And Display 9/80 D. Cafn 855-2112 7
Oconee Probabilistic Risk Assessment Project Plan 11/80 D. Cain 855-2112 8
Nuclear Plant Safety Parameter Evaluation by Event Tree Analysis 11/80 B. Sugnet 855-2996 9
Screening and evaluation cf 1979 Licensee Event Reports 10/80 D. Cain 855-2112 10 A Parameter Set for a Nuclear Plant Safety Console 12/80
- 8. Lava 11ee 855-2038 11 A Code for Predicting the Temperature and Oxidation of Undercooled Cores 11/80 D. Cain 855-2112 12 A Prediction of THI-2 Core Temperatures from the Ff ssion Product Release History 1/81 G. Thomas 855-2057 13 Instrument and Control Bus Power loss at Rancho Seco on March 11/80 G. Tho:::as 855-2057 20, 1970 11/80
- 8. Chexal 855-2997 14 Workshop on todine Releases in Reactor Accidents 15 Thercohydraulic Analysis of Crystal River - Unit 3 Incident 11/80 D. Cain 855-2112 16 Analysis and Evaluation of St. Lu:le Unit 1 Natural Circulation Cooldown 6/S1
- 0. Chexal 855-2997 17 Designing for Post Accident Radiological Conditions 12/80 W. Layman 855-2013 18 Workshop on Post-Accident Sampling 12/00 R. Catlin 855-2919 19 Power Plant Infomation Systems Data Entry - Reducing Labor and Costs 3/81 R. Catifn 855-2919 20 Analysis of Delayed Control Rod Insertf on at Browns Ferry-3 11/E0 W. Lavallee 855-2038 21 Fundamental Safety Parameter Set for Boiling Water Reactors 12/80 M. Leverett 855-2936 22 Response of a TMI-2 Type Containment Structure to a 100% Hydrogen Bart 12/80 D. Cain 855-2112 23 Nuclear Station Post Accident Lfquid Samp1fng System 12/81 J. Haugh 855-2763 24 TMI-2 Accident Core Heatup Analysis 1/81 J. Haugh 855-2763 25 TMI-2 Accident Core Heatup Analysis -- A Sepplement 1/81 D. Cain 855-2112 26 A Review of the Population Radiation Exposure at TM!-2 6/81 D. Cafn 855-2112 27 Analysis of a Heatup and Pressurizstfon during Dresden-3 Shutdown 8/81 R. Catifn 855-2919 29 The Retarding Ef fect of Hydrogen on Zircaloy Oxidatf an 9/81 R. Brugge 855-2921 30 lodine-131 Behavior During the TMI-2 Accident 7/81 G. Thomas 855-2057 31 U.S. Space and Missfie Safety and Relf ability Program 9/81 R. Catlin 855-2919
'2 Proceedings of Hydrogen Workshop 2/01 R. Kubik 855-8905 33 Reactor Neutronics Analysts of Browns Ferry-3 Partial Control Rod Insertion 7/81 J. Haugh 855-2768
's 34 Design and Pardware Alternatives For a safety Parameter Display System 6/81 B. Chexal 855-2997 35 Screening and Evaluation of First Half 1980 Licensee Event Reports 5/81 D. Cain 855-2112 37 Screening and Evaluation of Second Half 1980 Licensee Event Reports 5/81 W. Lavallee 855-2038 39 Verification and Validation of Safety Panel Display Sytems 9/81 W. Lavallee 855-2038 l
40 Accident Sequences for Desf gn, Validation and Training - Safety Parameter Display System 12/81 R. Kubik 855-8905
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41 Lightning Problems and Protection for Nuclear Power Plants 4/82 R. Kubik 855-8905 42 Reactor Water Level Measurement Using Ex-Vessel Neutron Detectors 12/81 W. Reuland 855-2977 43 LOCA by inadvertent Contaireent Spray - Sequoyah-1 12/81 D. Cain 855-2112 44 Investigation of Failures in I&C Power Supply Hardware 12/81 W. Reuland 855-2977 45 On-Line Doron Analysis Equipment Performance Evaluation 12/81
- 8. Chexal 855-2997 High Pressure Core Cooling System Milfunction at Hatch-1 4/82 R. Kubik 855-8905 4/81, W. Layman 855-2013 3
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Mr. 3. P. O'Reilly, Regional Administrator
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U.S. Nuclear Regulatory Commission, Region 11 101 Marietta Street N.W., Suite 3100
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e Atlanta, Georgia 30303
SUBJECT:
Crystal River Unit 3. f~)f Docket No. 50-302 / /
Operating License No. DPR-72
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Effluer.t and Waste Disposal Semiannual Report
Dear Mr. O'Reilly:
Pursuant to Title 10, Code of Federal Regulations, Part 50.36a(a)(2) and Crystal River Unit 3 Technical Specifications, Appendix B, 5.6.1.B; Florida Power Corporation's Crystal River Unit 3 Effluent and Waste Disposal Semiannual Report for the period January 1, 1982, through June 30,1982, is hereby submitted.
The Report does not include doses to individuals or the population from radioactive gaseous effluents due to the malfunction of the meteorological tower magnetic tape unit.
This tape unit supplies meteorological data to be used in the "GASPAR" computer code to calculate the above referenced doses. Without the tape data, manual transcription from recorder strip charts is necessary, thus requiring additional analysis tirne. A supplemental report of doses to individuals and population from radioactive gaseous effluents for the period of the Report will be prepared and issued oy December 1,19S2. Efforts to repair and procure replacement parts for the magnetic tape unit are continuing.
Osw<Y $
David G. Mardis Acting Manager 62N-Nuclear Licensing lV jI
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Attachments cc:
Document Control Desk U.S. Nuclear Regulatory Commission 7.q.,
Washington, DC 20555 CD Y,j O n i-General Ofhce 3201 inirty-voorth street sou:n. P O Dx 14042. St Petersburg. Florida 33733 813 - 806 5151 a