ML20147B257
| ML20147B257 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1987 |
| From: | Burski R LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20147B261 | List: |
| References | |
| NUDOCS 8803020032 | |
| Download: ML20147B257 (45) | |
Text
.
Semiannual Radioactive Effluent Release Report July 1, 1987 - December 31, 1987 Waterford 3 SES Louisiana Power & Light
]'
I
(
W310Labnr
$22 b 8803020032 PDR 0ls000382 ADOCK O R DCD }
TABLE OF CONTENTS 1.0 SCOPE 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Unplanned Abnormal Releases 3.0 GASE0US EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA 7.0 ASSESSMENT OF DOSES 7.1 Doses due to Gaseous Effluents 7.2 Doses due to Liquid Effluents 7.3 40 CFR Part 190 Dose Evaluation 7.4 Doses to Public Inside the Site Bounlary 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program 8.2 Changes to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability i 8.5 Missed Effluent Samples 8.6 Corrections to Previous Semiannual Radioactive Effluent Release Reports 9.0 TABLES !
t 10.0 ATTACHMENTS i W310526HP 1
1.0 SCOPE This Semiannual Radioactive Effluent Release Report.is submitted as required by Louisiana Power and Light's Waterford 3 Technical Specification 6.9.1.8. It covers the period from July 1, 1987 through December 31, 1987. Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21.
The information contained in this report includes:
(1) A summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period; (2) A summary of the meteorological data collected during 1987; '
(3) Assessment of radiation doses due to liquid and gaseous radioactive effluents released during the 1987; (4) Explanation of why certain instrumentation was not restored to -
operable status within the time specified in the ACTION Statement, as per Waterford 3 bEu Technical Specification 3/4.3.3.11; I
d (5) A summary of misred samples required by Waterford 3 SES Technical i Specification 4.11.2.1.2; b
(6) A description of changes made to the Offsite Dose Calculation Manual; and (
(7) A summary and correction of errors identified in previous Semiannual Radioactive Release Reports.
i W3105261D 2
2.0 SUPPLEMENTAL INFORMATION 2.1 Ri gulatory Limits The Technical Specification Limits applicab'e to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
The air dose due to noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar year: Less than or equal tr.10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
2.1.2 Iodines; Particulates, Half Lives > 8 Days; and Tritium The dose rate due to Iodine-131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be i
limited to less than or equal to 1500 mrem /yr to any organ.
W310526HP 3
The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days in gaseous effluents released to areas at and beyond the. site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pC1/ml total Lctivity.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.
l l
I I
i W310526HP 4 l
\_
')
2.1.4 Uranium Fuel Cycle Sources l l
r The dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel f cycle sources shall be limited to less than or equal to 25 mrem to the total body.or any organ (except the. thyroid, which shall be limited to less than or equal to 75 mrem) over li consecutive months.
2.2 Maximum Permissible Concentrations i
2.2.1 Fission and Activation Gases; Iodines; and Particulates, Half Lives > 8 Day.s For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicabic limits are expressed in terms of dose rate at the site boundary.
2.2.2 Liquid Effluents The maximum permissible concentration (MPC) values specified in 10 CFR Part 20, Appendix B, Table II, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in ,
liquid effluents.
t 2.3 Average Energy This is not applicable to Waterford 3 SES's radiological effluent technical specifications.
r 2.4 Measurements and Approximations of Total Radinactivity J j i
The quantification of radioactivity in liquid and gaseous effluents a
was accomplished by performing the sampling and radiological analysis {
of effluents in accordance with the requirements of Tables 4.11-1 and i 4.11-2 of the Waterford 3 SES Plant Technical Specifications.
V310526HP 5
2.4.1' Fission and Activation Gases (Noble Gases)
For c ntinuous releases, a gas grab sample was analyzed monthly for noble gases. Each week a Gas Ratio (GR) was calculated according to the following equation:
GR = Average _ Weekly Noble Gas Monitor Reading Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the previous week. For gas decay tank and containment purge batch releases, a gas grab rample was analyzed prior to release to determine noble gas concentrations in the batch.
In all cases the total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged.
2.4.2 Iodines and Particulates Iodines and particulates discharged were sampled using a continuous sampler which contained a charcoal cartridge and a particulate filter. Each week the charcoal cartridge and particulate filter were analyzed for gamma emitters using gamma spectroscopy. The deternined raoionuclide concentrations and effluent volume disebarged were used to calculate the previous week's activity released.
The particulate samples were composited and analyzed quarterly for Sr-89 and St-90 by a contract laboratory (Teledyne Isotopes). Particulate gross alpha activity was measured weekly using alpha scintillation counting techniques. The determined activities were used to estimate effluent concentrations in subsequent releases until the next scheduled '
analysis was performed.
W310526HP 6 m
r, Grab samples of continuous and batch releases were analyzed monthly for tritium. The determired concentrations were used to estimate tritium activity in subsequent releases until the next scheduled analysis was performed.
2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentra-tions were used to determine radionuclido concentrations in i the previous week's releases. For batch releases, gamma analysis was performed on the sample prior to release.
i i
For both continuous and batch releases, composite samples were analyzed quarterly by a contract laboratory (Teledyne Isotopes) for Sr-89, Sr-90, and Fe-55. Samples were composited and analyzed monthly for tritium and gross alpha using liquid !
scintillation and gas flow proportional counting techniques, respectively. For radionuclides ceasured in the composite j samples, the measured concentrations in the composite samples from the previous conth or quarter vare uaed to estimate released quantities of these isotopes in liquid effluents i during the current month or quarter.
l The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of ,
each radionuclide present and the total volume of the effluent discharged.
2.5 Batch Releases t t l
The summarization of information for gaseous and liquid batch releases
! is included in Table 1.
W310526HP 7 u __.________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ __ _
2.6 Unplanned Abnormal Releases No unplanned abnormal releases occurred during the reporting period.
3.0 GASE0US EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A, IB, and IC. Note that there were no elevated releases, since all Waterford 3 SES releases are considered to be at ground level.
4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B, 5.0 SOLID WASTES The summary of radioactive solid vastes shipped offsite for disposal is listed Table 3.
6.0 METEOROLOGICAL DATA In Table 4 the hourly meteorological data from January 1, 1987 through December 31, 1987, is presented in the form of joint frequet.cy distributions of wind speed, vind direction, and atnospheric stability. The Waterford-3 data recovery results by parameter are as follows:
Parameter January - June July - December Entire Year Delta T 98% 98% 98%
WS/WD 69% 99% 84%
Delta T, WS/WD 69% 99% 84%
overall 69% 98% 84%
W310526HP 8
The data losses were largely due to equipment failures. Recorder malfunctions at both towers resulted in the loss of wind speed and direction data during the first half of 1987. The wind speed and direction recorder at the primary tower frequently failed throughout January, February and March. Recorder failure was characterized by a lack of traces, flat traces, improper traces and often a lack of chart paper advance with smeared markings on the chart. Therefore, much of the primary tower wind speed and direction data were unavailable or
-unusable. Unfortunately, the wind speed and direction recorder at the [
backup tower was simultaneously experiencing malfunctions. The servo motor on the backup tower recorder failed often during the first half of 1987 and much of this data was also unusable. Repair of the recorders l was delayed due to an inadequate supply of spare servo motors onsite.
These simultaneous recorder malfunctions of both primary and backup wind speed / direction recorders resulted in the poor data recovery level during the first half of the year. However, due to the implementation of corrective actions, data recovery significantly improved during the second half of 1987.
LP&L has endeavored to correct the equipment problems and minimize data loss as demonstrated by the following actions: ,
The spare parts inventory onsite has improved, especially with respect to the strip chart recorders.
A weekly walkdown of the meteorological towers is performed by Health Physics personnel.
I Strip chart data are interpreted on a monthly basis rather l than quarterly to allow for early detection of potential problems with the system. {
l 7.0 ASSESSMENT OF DOSES !
l l
7.1 Dose Due to Caseous Effluents !
l i
6310526HP 9 l
r 7.1.1 Air Doses.at the Site. Boundary An assessment of air doses from gaseous effluents was performed for a location at the site boundary in the sector having the most restrictive atmospheric dispersion parameter (X/Q).
Based on actual meteorological conditions existing during the reporting period and excluding any sectors over water, this location was determined to be the ESE sector at 966 meters.
Doses were assessed at this location in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only beta and gamma exposures to air due to noble gas. The results of these assessments for the year 1987 are summarized as follows:
Beta air dose: 2.76 mrad Gamma air dose: 1.02 mrad The beta and gamma air doses are 14% and 10% of the Annual Technical Specification Dose Limits, respectively. The results of the dose calculations by quarter are summarized in Table 5.
7.1.2 Maximum Organ Dose to the Critical Receptor The maximum organ dose to a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary was determined for 1987.
An assessment of the maximum organ dose was performed for the critical receptor. The critical receptor was assumed to be located at the nearest residence to the plant having the highest atmospheric dispersion and deposition parameters (X/Q) and (D/Q). Using 1987 land use census and meteorological data for 1987, the location of the critical receptor was determined to be in the N sector at a distance of 1287 meters.
The dose calculation was performed in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering the inhalation, ground plane exposure, and cow's milk ingestion pathways.
W310526HP 10
The maximum organ dose to the critical receptor was determined to be 1.4 mrem to the infant thyroid. This represents 9% of j the Annual Technical Specification Dose Limit. Dose
- calculation results are summarized by quarters in Table 5, 7.2 Doses Due to Liquid Effluents The annual doses to the maximum exposed individual resulting from i exposure to liquid effluents released during 1987 from Waterford 3 SES were 4.9E-2 mrem total body and 3.2E-1 mrem to the maximum exposed organ (GI-LLI). These values are 1% and 3% respectively, of the Annual Technical Specification Dese Limits. Dose calculation results are summarized by quarters in Table 5. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.
7.3 40 CRF Part 190 Dose Evaluation In accordance with Waterford 3 Offsite Dose Calculation Manual.
Section 8.15, dose evaluations to demonstrate compliance with Surveillance Requirements 4.11.4.1 and 4.11.4.2 of the Waterford Technical Specifications, dealing with dose from the uranium fuel l cycle, need to be performed only if quarterly dossa exceed 3 mrem to ]
! the total body (liquid releases),10 mrem to any organ (liquid j releases), 10 mrad gamma air dose, 20 mrad beta air dose, or 15 mrem to any organ from radiciodines and particulates. l At no time during 1987 were any of these limits exceeded; therefore, j no evaluations were reouired. !
4 7
t i
I i
1 W310526HP 11
7.4 Doses to Public Inside the Site Boundary The Member of the Public inside the site boundary expected to have the maximum exposure due to gaseous effluents would be an employee at Waterford 1 and 2 fossil fuel plants located in the NW sector, 1
! approximately 670 meters from the plant. Based on an assumed occupancy of 25% (40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week) and the fact all employees are r
adults, the maximum organ dose would be less than 0.01 mrem to the thyroid. This dose was calculated according to the methodology described in the Waterford 3 Offsite Dose Calculation Manual "
! considering only the inhalation pathway.
1 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program There were no changes to the Process Control Program for the period covered by this report.
i 8.2 Changes to the Of fsite Dose Calculatien Manual On July 7, 1987, Revision 6 of the Waterford 3 SES Offsite Dose Calculation Manual was approved for issue by the Plant j l Manager-Nuclear.
Revision 6 incorporated all of the changes made to Revision 5 which !
vere discussed in previous Semiannual Radioactive Effluent Release j Reports. The changes included in Revision 6 that were not l previously discussed were made to correct typographical errorst to incorporate changes to the liquid waste management system; and to
- incorporate current meterological data. These changes are summarized in the following sections.
1 l
8.2.1 Equation (11) was corrected by deleting the constant K'.
This constant was already incorporated into the value of P it' l W310526HP 12 i
1
+
8.2.2 -Tcble 1 (Attachment 10.1), "Annual Avarage Dispersion cad Deposition Parameters for Areas at and Beyond the Unrestricted Area Boundary" was revised to incorporate meteorological data collected during 1986.
8.2.3 The figure in Attachment 10.8 (page 1) was revised to reflect the addition of Waste Tank C to the Liquid Waste Management System.
8.2.4 The bioaccumulation factor for Niobium in Table 6, page 2 (Attachment 10.12) was corrected to agree with that listed in Regulatory Guide 1.109. The incorrect value had a negative exponent.
8.2.5 Table 11 (Attachment 10.18), "Annual Average Dispersion Parameter at or Beyond the Unrestricted Area Boundary" was revised to incorporate 1986 meteorological data.
8.2.6 Table 12 (Attachment 10.19), "Annual Average Deposition Parameter at or Beyond the Unrestricted Area Boundary" was revised to incorporate 1986 meteorological data.
8.3 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with Technical Specification Table 3.12-1. Milk is collected, when available, from the control location and three identified sampling locations as indicated in Waterford 3 Offsite Dose Calculation Manual, Table 2 and Table 3.
8.4 Report of Technical Specification Required Instrument Inoperability Technical Specification, Limiting Condition for Operation (LCO),
3.3.3.11 requires the reporting in the Semiannual Radioactive Effluent Release Report of why designated inoperable instrumentation was not restored to operability within the time specified in the ACTION Statement. During the reporting period, there were four separate cases when instrt: mentation was not restored to operability within the time specified. These cases are described in the following sections.
W310526HP 13 I_
8.4.1 Monitor
Waste Gas Holdup System Hydrogen and Oxygen Monitors Period of Inoperability: 3/21/85 - 12/31/87 (At end of reporting period monitors were still inoperable)
Time Required by Technical Specifications to Restore Operability: 30 days Cause of Inoperability:
Due to initial design problems excess amounts of moisture were allowed to leak into both the Beckman 02 and Delphi H2and 0 2 analyzer systems. Replacement of the analyzers and ,
modification of the sample system was implemented during this period. While this was being done the system remained out of ,
service.
Reason operability Not Restored Within Allotted Time: I Fxtensive hours were spent attempting to restore these analyzers to operable status. Several analyzer cells were replaced, the solenoid and regulator were repaired, and the sample pump was both repaired and replaced. After these efforts failed tc return the monitor to service, a station modification was initiated to replace the analyzer cells with less moisture sensitive models and to completely redesign the sample line condensate drain system.
This modification entailed work in several areas of the plant '
and on four different systems. All existing piping and electronics associated with the Waste Gas Holdup System l Hydrogen and Oxygen Monitors was essentially scrapped and redasigned.
1 W310526HP 14
E l
i Work included re-routing all sample lines in the Laundry Room, modifying the existing drain header, and fabrication of a new drain header to tie into the Vent Gas Collection Header.
Re-routing of the Gas Surge Header Sample line and fabrication l
of its drain was performed in Safeguards Room B. On Gas Decay Tank A a new separator and drain line on the Waste Gas Collec-tion Discharge Header was added to the second low point.
Actual work on the Gas Analyzer Panel consisted of (1) adding 12 new solenoid valves in the sample inlets; (2) modifying the l panel to accommodate the new exo-sensor units; (3) installing a new pump and its issociated tubing; and (4) wiring of all new and relocated components.
While testing the system, the Gas Decay Tank "C" sample line was found to be crossed with the Gas Surge Tank sample line.
l Due to greater pressure in the Gas Decay Tank than that of t
the Gas Surge Tank the sampling pump diaphragm was blown.
This event also identif ted other problems with the system which required correction.
Design changes have been made to uncross the lines and install a pressure switch to prevent any subsequent over-pressurization. The pump was replaced and new wiring was installed. Additional moisture traps, preseure regulators, valves and pressure indicators have been installed.
A detailed test procedure was prepared and approved. Testing of the system was completed in early December of 1986 and the system was placed "in-service". Operational checks were performed on the system after the plant returned to the operating mode following a refueling outage. The operational l checks demonstrated that while the piping and sample tubing 1
changes proved beneficial, the analyzers themselves proved unreliable due to inherent design problems. Therefore, the Waste Gas Hydrogen and Oxygen Monitoring System could not be returned to operable status.
W310526HP 15
Based on the problems encountered with the present analyzers and sample / analyzer system, a new sample / analyzer system has been designed and is being installed. The system is based around sample conditioning, proven analyzers for the applica-tion and simple design. Testing vill commence immediately following the completion of construction. The analyzer system will be returned to service immediately following successful completion of testing. The scheduled completion date is June 30, 1988.
8.4.2 Monitor
Vaste Gas Holdup System Noble Gas Activity Monitor Period of lnoperability: 8/6/87 to 10/30/87
_ Time Required by Technical Specifications to Restore Operability: 30 days Cause of Inoperability:
The beta scintillation detector in the radiation e.onitor failed.
R,eason Operability Not Restored Within Allotted Time:
On August 6, 1987, a condition identification was written for the Gaseous Waste Management (GWM) system effluent monitor
- due to an invalid spiked reading. Troubleshooting the monitor indicated that its beta scintillation detector had failed. A new detector was installed in the monitor and a calibration was attempted. Part of the calibration procedure for the new detector involved measuring the response of a solid calibration source used during the primary calibration of the old detector. This was done in order to relate the response of the new detector to the response of the old detector to radioactive gases which was measured during the
, original primary calthration.
W310526HP 16
a: ;
L However..upon attempting the calibration it was discovered that the procedure used to perform the primary calibration
]
did not include an adequate description'of how the_ solid j source was physically positioned with' respect to the detector. f
- Without this description, the detector-to-source geometry used l
- j. during'the primary calibration of the old detector could not !
-be reproduced. Subsequently, traceability to the primary
]
!- calibration performed on the old detector was lost, _
.Not being able'to reliably correlate _the new detector's-
[.
! response to.the original primary calibration performed on the old detector, necessitated redoing the primary calibration on '
the new detector using gaseous sources. In order to perform i t
- -this calibration, solid and gaseous calibration sources had to ,
be manufactured by an outside vendor. Delivery time for.the gaseous and solid calibration sources was approximately six to l t
eight weeks. In order to prevent recurrence, the primary -l j calibration procedure was revised to correct the source ;
j alignment description deficiency. The revised procedure also included additional checks to evaluate detector energy ,
- - response and linearity. !;
The primary calibration and functional testing of the monitor i
j was completed on 10/30/87 at which time the monitor was !
t
! declared operable and placed back in service.
l
! l 1 t h
)' i i
i !
,d l 1 !
l .i 1 l I
l l
l
, \
4 l
j a ,
1 l
i I
, W310526HP 17 l
l
8.4.3 Monitor
Gaseous Waste Management System Effluent Flow Rate Measuring Device l Period of Inoperability: 8/6/87 to 10/30/87 ,
L 1
Time Required by Technical Specifi:ations to Restored Operability: 30 days i
Cause of Inoperability: The instrument required a ;
precalibrated constant pressure to be maintained at the ,
instrument location in order to obtain an accurate reading.
However, due to design deficiency, a constant pressure was not maintained re ulting in inaccurate readings.
Reason Operability Not Restored Within Allotted Time:
Station Modification Number 80 proposed increaring the maximum discharge flow rate of the Gas Decay Tanks from 5 scfm to 50 scfm. As a result, the flow rate measuring instrument was replaced with one having an increased scale !
range. The instrument requires a precalibrated constant i
pressure to be maintained at the instrument location in order to obtain accurate readings. However, while conducting a review of the Gaseous Waste Management System design to determine why the maximum flow rate of 50 sefa was not being attained, a design deficiency was discovered that affected j the accuracy of the flow rate measuring device. A constant ,
pressure was not maintained at the flow rate measuring device by means of an installed throttle valve and resulted i in readings which did not reflect actual dir' charge rates.
l i
i l
V310526HP 18 r
. =
r
Operations normally releases Gas Decay Tanks at a discharge pressure of 150 psig. At this pressure, an installed pressure egulating valve (CVM-3094) is supposed to maintain the flow instrument (GWM-IFT-0648) at 15 psig for accurate output and concurrently maintain a high flow rate via a constant pressure drop. However, the installed regulator valve could not perform its function because the trim across an upstream valve (GWM-306) was too small and resulted in a large pressure drop before the regulator valve. Consequently, the pressure of the flow rate measuring instrument was not maintained at 15 psig. In order for the regulator valve to perform its <
designed function, a backpressure in the system must be created. This could be accomplished by adjusting a downstream l throttling valve, GWM-311. I The discovered inaccuracy brought shout a concern over having violated Gaseous Release Permits. A review of all Gaseous Batch Waste Release Permits pertaining to the Gas Decay Tank ,
release point was performed going back to January of 1986 (approximate date of initial operation of the system following !
implementation of SM #80) to the present. The perr.its revealed '
that discharge rates during the period were to be limited to '
50 scfm. However, a review of the system installed under i SM #S0 uncovered a design deficiency which limited flov to a maximum of 35 scfm as a result of choked flow at valve GWM-308.
Therefore, since all Gaseous Release Permits issued since January of 1986 did not require restricted flow rates below 35 scfm. violation of these release permits could not have ;
occurred.
t l
i W311526HP 19
t Operability of the flow rate measuring instrument was delayed until the review of the Gaseous Waste Management System design could be completed. This was done to assure no other problems existed which would affect the instrument's accuracy. Changes to the Gaseous Waste Management System will be made during the next refueling outage to install an automatic throttling valve that will maintain a constant 15 psig' pressure at the flow measuring device. However, in the interim, Operations has revised the procedure governing operation of the G3seous Waste Management System (0P-007-003) to manually throttle valve WM-311 in order to create a backpressure in the system so that the regulator will maintain a constant pressure of 15 psig at the flow measuring' device.
Operability of the flow measuring device was restored and verified on October 30, 1987 at which time the monitor was l placed back in service.
8.4.4 Monitor
Main Condenser Evacuation and Turbine Gland Sealing System Noble Gas Activity Monitor Period of Inoperability: 8/24/87 to 10/30/87 Time Required by Technical Specifications to Restore Operability: 30 days Cause of Inoperability:
Excessively high sample inlet temperatures to the radiation monitor's sample drying system rendered it ineffective resulting in a sample with a high moisture content.
Subsequently, the moisture within the sample condensed in the sample lines as well as in the radiation monitor and resulted in erroneous readings.
W310526HP 20
Reason Operability Not Restored Within Allotted Time:
A review of the design of the drying system indicated that it was inadequate for high sample temperatures. An extensive amount of time was spent on redesigning the sample drying system. The redesign involved monitoring sample inlet temperatures and designing a drying system that would operate effectively at these temperatures. The redesigned system involved the purchase and installation of heat exchangers, sample conditioners, moisture traps, and additional sample pumps. The redesign also involved revising functional test procedures for the monitor.
System installation and functional testing of the monitor were completed on 10/30/87 at which time the monitor was declared operable and placed back in service.
8.5 Missed Effluent Samples On October 9, 1987, the 7 day Fuel Handling Building tritium sample required by Waterford 3 SES Technical Specification 4.11.2.1.2 Table 4.11-2 footnote "e" was not collected. The tickler card reminding the Chemistry Technician to collect and analyze the sample was misfiled. The root cause of the event was that there were no administrative controls or second checks to detect and correct a missed sample in a timely manner. As a result, the Health Physics and Chemistry Departments have implemented formalized watchstation turnover sheets and Technical Specification surveillance logsheets to enable lead technicians to monitor sample requirements independently of the method used for scheduling the analyses.
A complete description of this event and the subsequent corrective i actions was reported to the NRC in LER 87-025-00.
l i
I W310526HP 21
8.6 Corrcctions to Previous Semiannual Radioactive Effluent Release Reports While reviewing the effluent release data for inclusion in this report, an error was found in the computer program used to summarize the data included in Table 1A. The program incorrectly calculated average release rates for the quarter by dividing the curies released during the quarter by the duration of both quarters rather than that specific quarter. It is'important to note that only the release rates were calculated incorrectly, all curie totals were correct.
The software error was rectified and the correct information for the second half of 1987 was included in this report. However, upon review of previous reports the software errer resulted in incorrect release rates being reported in all previous reports. Attachments 2 through 6 contain the corrected tables for these reports.
In addition to the software error, reviewing the information included in the previous reports uncovered another error. The curies of tritium released during the first half of 1986 from~ airborne releases was incorrectly reported as 2.21E3 and 4.73E3 curies during the first and second quarters, respectively. The correct values should have been 5.18 and 1.71 curies for the first and second quarters, respec-tively. 'The corrected tables (Table 1A and Table IB) for this report are included in Attachment 4. The error resulted from using incorrect composite results to compute the total curies released from airborne effluents. All dose calculations for airborne releases during 1986 were based on the correct information and do not require revision.
To prevent a recurrence, computer programs have been written to perform quality control reviews on all effluent software data files.
In addition, all composite data entered into the data files are now routinely reviewed for accuracy.
I l
W310526HP 22
r 9.0 TABLES 1 Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All Airborne Effluents IB Semiannual Airborne Continuous Elevated and Ground Level Releases 1C Semiannual Airborne Batch Elevated and Ground Level Releases 2A Semiannual Summation of All Releases by Quarter - All Liquid Effluents 2B Semiannual Liquid Continuous and Batch Releases 3 Solid Waste Shipped Offsite for Disposal 4 Joint Frequency Distribution of Meteorological Data 5 Dose Calculatioe Results for 1987 10.0 ATTACHMENTS T
- 1. Offsite Dose Calculation Manual, HP-1-230, Revision 6
- 2. Corrections to the Semiannual Radioactive Effluent Release Report for the period of January 1 to June 30, 1987
- 3. Corrections to the Semiannual Radioactive Effluent Release Report for the period of July 1 to December 31, 1986
- 4. Corrections to the Semiannual Radioactive Effluent Release Report for the period of January 1 to June 30, 1986 ,
t
- 5. Corrections to the Semiannual Radioactive Effluent Release Report for the period of July 1 to December 31, 1985
- 6. Corrections to the Semiannual Radioactive Effluent Release Report for the period of March 4 to June 30, 1985 l
)
l 1 W310526HP 23 I l
r
TABLE 1 (1 of 1)
MkWR" ; W """ "
TM 7 ELEASE MT01 LlaJ!D Ale OASE0US PERIOD START TIE 4344 0014tS = 12:00M JLLY 1 1987 PERl(2 De TIE I 8759859 MS = lil59PM DEGMER 31 1987 LlajlD ElfAES KfWt 0F IELD6ES 178 TOT 4. TIE FWt 4.L IELDGES 45669.0 MI m!!!UI T!E FWt 4 1 353.0 MI MOME T!4 FWt A 256.6 M1
.!!N!!UI TIE FWt A fELIASE I 8.0 M!stlTES AiKMOE STEM FLOW I 908918.1 (PM GAGE 0VS fELEASES Rfeut OF R EASES I 11 TOT 4. TIE FOR 4.L ELD 6ES I 5119.0 MI MI!!UI TIE FWt 4 IELIAIE t 887.0 M!
MOA(E T!E FWt A fELIAGE I 465.4 Mll8JTES MIM!!U! TIE FWt A lELEAIE I 247.0 Milt /TES
]
I l
24
l TABLE 1A (1 of 1) i EPGti CATUGtY SEMI Sut9T!GI & EL El.EAES BY ElutTER l T19E F ACTIVITY I EL A! EFFLlefTS EPGlT!W PERICS : MTE 6 3 M MTR 8 4 l 1
)
l A. FIS$!0N M ACT!WTim PRODUCTS l
- 1. TOT 4. M11AE cut!ES 2.46E 03 9.24E 02 1.50E 01: 1
- 2. AMGE M11 AGE MTE FGt PER100 IUCI/SEC t 0.09E 02 t 1.16E 02 ;
- 3. PDGNT F #9LICAEE LIMIT % WA WA i
- 1. M0!O!(BIES
- 1. TUT 4. !(E!E-131 ICut!ES 7.6M-05 t 4.0 M 4 1.50E Ott
- 2. #4M(E fELEASE MTE FWt PERIOD IUCl/SEC I 9.66E-06 5.12E 46 8
- 3. PER2 NT OF APPLICA E E LIMIT I 1 WA WA C. PMTIC1LATES
- 1. PMTIC1LATESHLF4.!WS)0 DAYS) ICUt!ES 2.56E-05 1.00E-05 1.50E 01
- 2. AYEM0E M11AE MTE FGt PERICS IUCl/SEC 3.21-06 1.26E-06
- 3. P D E NT F # 9LICAE E LIMIT 1 : WA : WA
- 4. OMSS ALM M010 ACTIVITY ICUt!ES 1.79E-05 t 9.63E-05 D. TRIT!tM
- 1. T9T4. IELIAGE : Cut!ES 5.21E 02 8.43E 01 1.50E Ott l
- 2. #4NE lELEASE MTE FWt PGICS IUC1/SEC 6.56E Cl : 1.06E 01 l I
- 3. PER3XT OF #9LICAILE LIMIT I N/A : W4 :
j l
j 1
l l
25 l
1 l
4 TABLE IB (1 of 1) !
TWE (F ACTIVITY
! LidlN.N4N.S fNt EACH I FIS$1(BI M6ES.1211ES. AIS PtRTIQA.ATES IEPGl TING PER12 MTER t 3 40 MTER t 4 ELEV4TED lE11AES W10 lie IE11AES I L811T tmTER 3 INTER 4 80uttTER 3 imTER 4 8
- IMuts imS tielftS i MJQ.lE I IMuls 4345-6552 655347601434H552162347M i FISSIGIOASES 10Hel QRIES 0.00E-01 10.00E41 12.2E-013 0.12E 00 2-6B t QRIES : 0.00E-01 1 0.00E-01 8 4.10E41 1 0.00E-01 E-131M i cut!ES I 0.00E-01 0.00E-01 1 1.7M 01 10.00E 01 1 XE-133Pt IE-133 QAIES I 0.00E-Cl 0.00E-018 4.36E 00 t 0.0541 :
QA!ES 0.00E-01 10.00E-01 1.20E 03 6.6E 02 IE-135 I QRIES 0.00E-0110.00E41 4.30E 018 9.91E 01 TOT 4. FWt PERICS t QRIES : 0.00E41 : C.00E-01 1.24E 0317.72 02 8 100!IES i
1-131 I QRIES : 0.00E-01 0.00E-01 7.67E46 6 4.0K-05 t 1-133 I QRIES I 0.00E-0110.00E4181.7M-46 f 0.00E41 TOT 4. FWt PERl(S I cwt!ES 0.00E-01 0.00E-018 7.8E-0514.0M-05 I l
PNtT!QA.ATES H-3 I QRIES 0.00E-01 10.00E-018 5.21E 02 8 8.4X 01 CD-SS I QRIES 0.00E-01 1 0.00E-01 8 1.3E-05 5.0E-00 CS-134 I QRIES 0.00E41 0.00E-0113.10E46 8 0.00t41 :
1 CS-137 : cwt!ES 0 3.M 0.0E-018 0.00E418 8.77E 0612.44E-08 8 QRIES 0.0E-Cl 8 0.00E-011 1.79E-06 8 9.61-05 :
TOT 4. FOR PERIOD QRIES 0.00E-018 0.00E41 I 5.21E 02 8.4101 I
l l
1 26
TAPLE IC (1 of 1)
EPGli CATEGORY SUIIN00lt. A!RIGeel 94T04 ELEVATD M GIOlae
- LEWL ELEA6ES. TOTALS FOR EA0414A2!K ELEAEB.
TWE & ACTIVITY l FIS$191 OASES.100!ES. M P#tTICtLATES MPCRTING PERIOD t QUMTER I 3 M GUM 19t i 4 ELEVATED ELEASES I GVUG M1IAGES I I latIT taWtTER 3 IQUMTUt 4 taWtTUt 3 talARTER 4 8 I islfts IH0t#tS IMRftS IM15tS :
MXLIDE : :4345-6552 65534760 84345-6552 8655H760 t l
FIS$!0N GASES pt-05M CtRIES 0.00E-018 0.00E-01 I 8.36E-01 10.00E-01 :
Ut-85 : CtRIES 0.00E4110.00E418 6.90E 00 t 3.32 00 t Ut-08 : ClJt!ES 8 0.00E-01 1 0.00E41 8 8.17E41 1 0.00E-01 IE-131M i M !ES I 0.00E41 0.00E-01 1.20E 01 1 3.0E 00 I XE-133M I CLRIES I 0.00E-01 1 0.00E41 1 1.04E 01 2.30E41 IE-133 I QRIES I 0.00E4110.00E-011 1.12 03 81.42E 02 IE-135 MIES 0.00E-01 1 0.00E41 8 1.19E 01 8 0.00E-01 :
M-41 : CtRIES I 0.00E-018 0.00E4119.07E4210.00E-01 I TOT 4. FOR PERIOD QJt!ES 0.00E-0110.00E411 1.19E 03 1.49E 02 8 100!ES N0E PMTICtLATES 14 - 3 MIES 0.00E4110.00E418 4.09E4210.00E-01 CO-58 QJt!ES I 0.0E-01 0.00E-01 0.00E-018 9.9546 :
TOT 4.FWtPERI(2 : CLRIES I 0.00E41 0.00E-0114.09E-02 9.95-06 8 1
27
TABLE 2A (1 of 1) gCAg i gig SWg 0F E1. MLEASES W MTR MPORTING PUt!@ t MTR I 3 M WTR S 4
- LNii IWla 3 IMTR 4 IEST.TCT4.s MS IWL8t3 Iagat 1 I TYPE F EFFLIBit t t4345-4552 1655 H 760 t t i
A. FIS$10N N ACT!WTIGi MINUCTS
% MAK DILUTD CGEDITMTIGI I I I ,
M 1 2 PDtl(B tlE!/It. I 2.3E4 5.75-09 l
- 3. POEDIT F MPLICAKE LIMIT I I I WA WA I I
- 3. TRITitM
!. TOT 4. M1. DIE MID t 1.90E 02 : 2.50E 02 1 1.50E 01
- 2. AME DILUTD CGEDITMil0N I I I I Mle PUt!GI IUCInt. I 3.04E 4 1 2.73E-06
- 3. PDCDif 7 #PLICAKI LIMIT 1 WA I WA C. O!SSCLVED M DNIED 048ES
- 1. TOT 4. MLIAE I M IES 4.4E 0014.4M 00 1.50E 01:
- 2. WAE DILUTD CGEDfTMTIGI I : l Mle PDt!GI IUCI/It. t 6.74E-40 4.82E-00 t l
- 3. PDE DIT F MPLICAILE LIMIT I 1 WA I WA I D. 'ORDSS ALPM MD10 ACTIVITY
- 1. TOT 4. IELDGE I M IES 9.29E 4 8 1.19E 4 1.50E 01:
, E. MSTE VOL fELIASED(PE-D!lllTION) 10AL I 8.02E 05 t 1.29E 06 1.50E 01:
) F. VOLIAE F DILUTI(N WTR USED 104. I 1.72E 10 1 2.42E 10 8 1.50E 01:
J l
, 28
1 TABLE 2B )
(1 of 2)
MPGli CATEORY I SEMIA10GIL LIEJID MillAIB ADO MTOI fll. DIES TOT 4.S FWt EACN IEEll!E M1fAEB.
TYPE OF ACTIVITY t E RA0!GElu.10ES MPGtille PERIOD QLWiTER 8 3 Ale MTB 8 4 C0(TiltJOUS MLEASES I MTDI MLEASES I LMIT IMTG 3 IEWtim 4 IMTER 3 IEWITH 4 a
~
ticUts licWts IHautS tietsts I IEICLIDE :4345-655216TM76014345-6552 I655H760 t I 1
E BEEllE3 j cut!ES I 0.00E-01 0.00E-01 1.90E 02 2.50E 02 : I H-3 W24 : M IES I 0.00E-41 0.00E-01 8 5.10E-05 8 1.00E-03 i !
Ot-51 I Cut!ES 0.00E-01 0.00E41 2.40E 03 I 4.6E-021 !
m-54 : cut!ES t 0.00E-01 0.00E-01 2.82E-04 1 5.92E 03 FE-55 : CutlES I 0.00E-0110.00E41 9.54E-03 8 2.2E 02 i FE-59 : Cut!ES t 0.0E-0110.00E-01 t 5.79E-05 t 1.19E42 CD-58 : cut!ES I 0.00E41 0.00E41 1 1.06E-01 2.34E-01 i
!!di l: OA!ES Hili lI 0.00E41 8:511l 8:511l1:23l':W3!
1 0.00E41 1 4.3K-04 I 9.1X-04 RH8 St-69 : cut!ES I 0.00E-01 0.00E-01 1 1.95-031 3.19E 04 5 92 CutlES I 0.00E-01 0.0E41 0.00E4112.92E-04 ZR-95 I CutlES I 0.00E-01 1 0.00E-01 1 0.00E 01 8 8.54E-03 I ZR-97 : MIES I 0.00E-01 10.00E41 10.00E418 6.21-05 8 5 95 cut!ES I 0.00E-01 I 0.00E41 I 6.4tE-05 t 1.44E42 :
70-99 : Cul!ES I 0.0E-01 10.00E-01 1 1.89E44 8 3.9E44 :
TC-99M I Cut!ES I 0.00E-01 0.00E-01 I 3.34E-04 8 6.87E44 :
FU 103 cut!ES 0. 411 0. -01 1 0, 41 1 8.52E-04 :
Er110M i 0AIES 0. -01 0. -01 0. -ci 4.3E-03 :
TE-132 : cut!ES I 0. 4110. 41 1.71 -04 8 8.67E-05 1 1-131 : cut!ES I 0.00E-0110.00E4181.22E-02 8 5.76E421 1-133 cut!ES I 0.00E-01 1 0.00E-01 1 2.74E-04 8 4.82E 03 1-135 I QAIES I 0.00E41 1 0.00E 01 0.00E-01 1 1.39E-04 CS-134 I QA!ES 0.00E4110.00E41 2.96E-0310.00E-01 i CS-136 I QA!ES I 0.00E41 0.00E41 1.79E-05 8 0.00E41 CS-137 I QAIES 0.00E41 0.00E-018 6.31E 03 8 1.52E-04 I CS-138 : cut!ES 0.00E-01 1 0.00E-01 8 0.00E41 1 2.37E-04 :
M-139 CAlES I 0.00E 0110.00E-018 4.58E 05 81.96E-05 l
i 29 l
TABLE 2B (2 of 2)
T M OF ACTIVITY
!t ALL ER@!(MRIES M $ k n$ id N #
REPWITi m PERIOD t GUNITD 9 3 A 2 9 3 TER 8 4 CONTIMJtUS RELIAIES : MTOI IELEAES I l811f aSMRTG 3 MRTER 4 :GullRTH 3 :EMRfD 4 1 12tJts alcJts IHotsis II(Uts :
Male 4345-6552655 H 760 t4345-6552 655 H 760 alt.MRIES C0(TIMED LA-140 Cut!ES 0.0E41 0.00E41 1 1.51E-0314.01-03 i LA-142 : DJt!ES I 0.00E-01 0.00E-01 : 0.0004113.8544 i E-141 QJt!ES I 0.00E-01 10.00E-018 0.00E41 1.3E-04 :
E-144 OJt!ES I 0.00E-01 1 0.00E-01 0.00E-01 1 4.32E-04 :
14-187 i OJt!ES I 0.00E-01 1 0.00E41 1 0.00E 01 1 2.9E-04 F-239 : Cut!ES I 0.00E41 0.00E-01 8.64E4410.00E 011 KR-95M OJt!ES 0.00E-01 10.00E-018 3.4M-0413.00E 04 UI-95 : OJt!ES I 0.00E-01 10.00E-01 2.04E-02 2.2E42 8 Ut-88 OJt!ES I 0.00E4110.00E-01 2.2N 04 a 6.39E-05 :
E-131M Oft!ES I 0.00E 01 10.00E-01 4.42E-021 9.91E-02 IE-133M i QJt!ES I 0.00E 01 0.00E-01 1 2.79E-02 1 1.4 N-02 E-133 Cut!ES 0.00E41 10.00E-0114.2E 00 4.2E 00 XE-135 cut!ES I 0.00E-01 1 0.00E-01 1.80E-02 1 2.91E-02 St-90 t cut!ES . t 0.00E 01 8 0.00E-01 1 3.42E-051 0.00E-01 I O ALPld i OJt!ES I 0.00E-01 0.00E-01 19.29E 06 t 1.19E-06 OM7 : OJt!ES 0.00E-01 1 0.00E 01 1 1.3M-04 1 2.3E 04 i SD124 OJt!ES I 0.00E-01 1 0.0E-01 1 2.99E 031 3.62E-02 i SM-ll3 I CutlES I 0.00E41 10.00E-01 2.50E4513.91-03
+ 97 : OJtlES 0.00E-018 0.00E-018 2.6E-04 8 9.0E-04 58-122 OJt!ES t 0.00E-0110.00E-011 1.314312.3103 8 58-125 QJt!ES 0.00E-01 1 0.00E-01 1 1.11-03 I 3.2E-02 E-139 OJt!ES I 0.00E-01 1 0.00E-01 0.00E-01 1 3.42E-06 i TOTAL FGt PERIOD t QJt!ES 0.00E-01 0.00E4112.03E 02 2.5E 02 i f
30
TABLE 3
-(1 of 7)
REGULATORY GUIDE 1.21 REPORT i SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL i
, DURING PERIOD FROM 7/1/87 TO 12/31/87 CONTAINER CUBIC WASTE TYPE VOLUME FT3 METERS CURIES- % ERROR (CI)
Compacted Dry Active Waste 95 61.8 1.05E+00 225 Non-Compacted Dry Active 95 2.7 1.61E-02 125 Waste Evaporator Bottoms 182 5.2 7.51E-01 125 Solidified with Cement Dewatered Cartridge Filters 120 6.8 7.75E+01 225 Packaged in a High Integrity Container i
Liquid Waste Management 182 -67.0 4.27E+01 125 i
System Spent Resin Solidified with Cement Dewatered Liquid Waste 182 36.1 1.34E-03 125 j Management System Spent Resin i j Resin Waste Management 182 5.2 5.11E+01 125 System Spent Resin Solidified with Cement I
t i Waste Oil / Water Solidified 7.5 25 1.26E-01 125 j with Aquaset and Petroset .
, Dry Charcoal Packaged in a 95 10.8 9.21E-04 125 in a B-25 Box Dry Charcoal Packaged in 170 9.6 8.11E-04 i25 '
i a HN-100 Liner Non-compacted Dry Active 133 11.3 5.94E-02 125
, Waste in a B-25 Overpack 1 Container 4
l J
i l
31
t TABLE 3 (2 of 7)
ESTIMATES OF MAJOR KUCLIDES BY WASTE TYPE h
Compacted Dry NUCLIDE PERCENT Active Waste NAME ABUNDANCE CURIES Cs-137 58.229 6.13E-01 Cs-134 19.653 2.07E-01 .
Co-58 7.948 8.36E-02 '
Fe-55 5.205 5.48E-02 Co-60 3.901 4.10E-02
- Ni-63 2.072 2.18E-02 l 4
Mn-54 1.474 1.55E-02 '
I-131 1.334 1.40E-02 C-14 .186 1.95E-03 Ni-59 .000 0.00E+00 Nb-94 .000 0.00E+00 H-3 .000 0.00E+00 ;
, Sr-90 .000 0.00E+00 Tc-99 .000 0.00E+00 ,
I-129 .000 0.00E+00 ,
Pu-241 .000 0.00E+00 cm-242 .000 0.00E+00 4 ;
Non-Compacted Dry NUCLIDE PERCENT I Active Waste NAME ABUNDANCE CURIES a
Cs-137 59.101 9.53E-03 Cs-134 22.574 3.64E-03 ;
, Fe-55 10.605 1.71E-03 i
Co-60 2.636 4.25E-04 Ni-63 1.712 2.76E-04 ,
j Co-58 1.247 2.01E-04
.1 Mn-54 1.160 1.87E-04 ;
) C-14 .967 1.56E-04 Ni-59 .000 0.00E+00 Nb-94 .000 0.00E+00 H-3 .000 0. 00'2+ 00 Sr-90 .000 0.00E+00 i Tc-99 .000 0.00E+00 I-129 .000 0.00E+00 Pu-241 .000 0.00E+00 Cm-242 .000 0.00E+00 i
i l
i
)
i 32 l l
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ __l
TABLE 3
, (3 of 7)
ESTIMATES OF MAJOR NUCLIDES BY WASTE TYPE Evaporator Bottom NUCLIDE PERCENT Solidified with Cement NAME ABUNDANCE CURIES '
H-3 79.597 5.98E-01 ;
Fe-55 14.775 1.11E-01 ;
C-14 3.128 2.35E-02 Ni-63 1.085 8.15E-03 Co-60 1.005 7.55E-03 Cs-137 .007 5.49E-05 Ni-59 .000 0.00E+00 Nb-94 .000 0.00E+00 L Sr-90 .000 0.00E+00 i Tc-99 .000 0.00E+00
- I-129 .000 0.00E+00 Pu-241 .000 0.00E+00 Cm-242 .000 0.00E+00 ,
Dewatered Cartridge NUCLIDE PERCENT ,
r Filters Packaged NAME ABUNDANCE CURIES In a High Integrity Container Fe-55 53.444 4.14E+01 Co-60 19.480 1.51E+01
- Ni-63 11.037 8.55E+00 Co-58 9.713 7.53E+00
- Mn-54 2.526 1.96E+00 Zn-65 1.061 8.22E-01 ,
j Cs-137 .063 4.86E-02 i C-14 .044 3.41E-02 '
j Pu-241 .014 1.09E-02 Ni-59 .009 7.32E-03 I-129 .001 1.04E-03 Cm-242 .000 1.87E-06 Nb-94 .000 0.00E+00 i j H-3 .000 0.00E+00 j Sr-90 .000 0.00E+00
[ Tc-99 .000 0.00E+00 i Liquid Waste Management NUCLIDE PERCENT System Spent Resin NAME ABUNDANCE CURIES Solidified with Cement I Co-58 81.695 3.49E+01 3 Cs-137 6.080 2.59E+00 Fe-55 4.693 2.00E+00 i Cs-134 2.828 1.21E+00 !
l Co-60 1.975 8.43E-01 i Ni-63 1.110 4.74E-01 C-14 .137 5.83E-02 .
H-3 .112 4.79E-02 l j Ni-59 .000 0.00E+00 i
, Nb-94 .000 0.00E+00 i
} Sr-90 .000 0.00E+00 )
i Tc-99 .000 0.00E+00 l l I-129 .000 0.00E+00 ,
- Pu-241 .000 0.00E+00 !
4 Cm-242 .000 0.00E+00 i i
33 i
TABLE 3 (4 of 7) '
ESTIMATES OF MAJOR NUCLIDES BY WASTE TYPE ,
Dewatered Liquid Waste NUCLIDE PERCENT F
Management System Spent NAME ABUNDANCE CURIES Resin l Cs-137 57.424' 7.72E-04 !
Fe-55 23.528' 3.16E-04 ,
~
Co-60 8.944 1.20E-04 :
Ni-63 5.406 7.27E-05 Mn-54 2.002 2.69E-05 4
H-3 1.130 1.52E-05 Cs-134 1.042 1.40E-05 C-14 .405 5.45E-06 q
Ni-59 .000 0.00E+00 h
) Nb-94 .000 0.00E+00 Sr-90 .000 0.00E+00 Tc-99 .000 0.00E+00 I-129 .000 0.00E+00 Pu-241 .000 0.00E+00 Cm-242 .000 0.00E+00 3
Resin Waste Management NUCLIDE PERCENT
, System Spent Resin NAME ABUNDANCE CURIES j Solidified with Cement i Cs-137 43.665 2.23E+01 i
Cs-134 20.364 1.04E+01 a Ni-63 9.418 4.81E+00 i
- Co-60 8.988 4.59E+00 j Co-58 7.793 3.98E+00 j j Mn-54 5.306 2.71E+00 t 1
.380 1.94E-01 l
! Sr-90 .032 1.62E-02 H-3 .021 1.07E-02 5 I
Ni-59 .000 0.00E+00 i Kb-94 .000 0.00E+00 ;
1 Tc-99 .000 0.00E+00 i I-129 .000 0.00E+00 l 4
Pu-241 .000 0.00E+00 j Cm-242 .000 0.00E+00 !
i 1
1 ,
r i
t 1 I
)
i 34 !
I
TABLE 3 (5 of 7) '
E3TIMATES OF MAJOR NUCLIDE BY WASTE TYPE t
i Waste Oil / Water NUCLIDE PERCENT Solidified with Aquaset NAME ABUNDANCE CURIES i and Petroset Cs-137 39.190 4.95E-02 Fe-55 18.079 2.29E-02
, Cs-134 12.689 1.60E-02 Co-58 7. P 65' 9.94E-03
- Co-60 6.823 8.63E-03 Mn-54 5.469 6.91E-03 '
i I-131 4.711 5.96E-03 Ni-63 4.039 5.11E-03 I H-3 .772 9.76E-04 !
C-14 .322 4.07E-04 Ni-59 .000 0.00E+00 Nb-94 .000 0.00E+00 Sr-90 .000 0.00E+00 Tc-99 .000 0.00E+00 I-129 .000 0.00E+00 4
Pu-241 .000 0.00E+00 Cm-242 .000 0.00E+00 Dry Charcoal Packaged NUCLIDE PERCENT in a B-25 Box NAME ABUNDANCE CURIES C-14 95.958 8.84E-04 t Cs-137 3.652 3.36E-05 Co-60 .317 2.92E-06 Ni-59 '000
. 0.00E+00 t i
Ni-63 .000 0.00E+00 Nb-94 .000 0.00E+00 .
- H-3 .000 0.00E+00 !
) I-129 .000 0.00E+00 Pu-241 .000 0.00E+00 Cm-242 .000 0.00E+00 Dry Charcoal Package NUCLIDE PERCENT in a HN-100 Liner NAME ABUNDANCE CURIES C-14 95.957 7.78E-04 Cs-137 3.651 2.96E-05 Co-60 .318 2.58E-06
) Ni-59 .000 0.00E+00 3 Ni-63 .000 0.00E+00 '
i Nb-94 .000 0.00E+00 i j H-3 .000 0.00E+00
Pu-241 .000 0.00E+00 :
Cm-242 .000 0.00E+00 -
35
TABLE 3 (6 of 7)
ESTIMATES OF FAJOR NUCLIDE BY WASTE TYPE Non-compacted Dry Active NUCLIDE PERCENT Waste in a B-25 Overpack NAME ABUNDANCE CL%IES Container Cs-137 51.443 3.06E-02 Cs-134 23.501 1.40E-02 Fe-55 10.657 6.34E-03 Co-58 8.053 4.79E-03 Co-60 2.439 1.45E-03 Ma-54 1.602 9.52E-04 Ni-63 1.475 8.77E-04 C-14 .830 4.94E-04 Ni-59 .000 0.00E+00 Nb-94 .000 0.00E+00 H-3 .000 0.00E+00 Sr-90 .000 0.00E+00 Tc-99 .000 0.00E+00 I-129 .000 0.00E+00 Pu-241 .000 0.00E+00 Cm-242 .000 0.00E+00
- THE ONLY NUCLIDES LISTED ARE THOSE HAVING GREATER THAN 1 %
ABUNDANCE AND/OR SPECIFIED IN 10 CFR PART 61 i
i l
l l
36
i TABLE 3 ~'
I (7 of 7)
. i SOLID WASTE DISPOSITION
SUMMARY
j
' i NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION j 2 Truck Barnwell I
s 19 Truck Beatty b
1 .
't I
WASTE NUMBER OF TYPE OF TYPE OF MODE OF r
CLASS SHIPMENTS SHIPMENTS CONTAINER TRANSPORT DESTINATION '
A 7 LSA Type A Truck Beatty A 11 LSA Strong Tight Truck Beatty I B Type A 1 LSA Truck Beatty i C 2 Type B Type B Truck Barnwell f l ;
i i
)
Y i
1 4
i 1
1 e
j i
37 e____---___-__--___
4 e
's e se e to 4 en e ob ed og - e e N me e e se @ e S e e e e == . ed e N e d me e O e N e me @ em se e q eme t U M P W G N M se N N se N N d se @ e e e U k q se e e es se N N se N as as se se Ne r o en se h O m e4 > .4 W
.4 e4 me se a D
@ O CP O en e to e 4 e 990000 OOOOOOO9000 4 e 900OOOOOOOO000OO O as as se *=
A A O O e e e e
~ ~
OOOOOOOOOOOOOOOO O
~ 00099990000990004 .
. e e e se -
4 I
b e m Q a 0000000000000000 0 I 0000000000000000 0 J -
O O 4
U = *
- e . . .
e O O O O en so O O O A O N se O O N O O O M ee O @ *e - OOseOOOONOOOOOOOO m O , i , i a e . e .
O O
- e "
M a as a
as C u O v O W I E mOneNNoe-dee-acO c E e-emONew-eNo---Ne p i N- - - - - E. ,
y i J ma
- - 9 J -
e as e 2* De > e > > e as as e e
. 4 se 4 ed see D m C a e O. m e O.
A 4 e e N em e h m e en e e N m se e me h N == 4 4 e NNePeedNhheMsed6he 4 4 9 O 4 M-ee- == --N Mmg e 9 O e -- -- -
g - - M - - )
W % C e e e .
O > e O > c d O W to 4 to 4 m g , m e A 4-Q e.
e e
e et o.
p v m 9 m i
-e-meheNmee.%,me N-aN - N e
a.t O
u i e emee.N 0%.eO..Ne N Del S w == 3 w ==
g ==. =.=
m a N 3 4 N 4 h me hl se ha L
Q e R$
M a as O a se O O e
- O at e C se N O N e N ft @ M O O N O N M e O O N e e se N == e e e se O O O O N N N e N @ h N t
- e e I se em W S d U M See et me e as == e.
y a 3 - e 3 -
se se 4 Z e a y e wh a e a .
Q 3 == N4MMmOOOOOOOONMO O 3 - se M M @ O en O O sesese O O N N M N cy 4 e N O 4 e n 0 W e e a e g as en te as 38 W as ed an en O se O h a -000000000000o00 - a
~O--00000000000- <
Z = i
> a i =
% == e > - es e 3 se 3 as C m. .J h. .s q to se b ==
0 e O e em 4 e 4
' a to a m M O m. O900000OOOO00000 0 et O e OOOOOOOOO90000OC O se me ee 4 M == N -
a e n e e 4 e e. e me es e as to O De O J et ed at em
- e. O90000O000O0009O O O se o OOO000000OO90000 0 el O
a t en a e to a% em to M e De M e U
- E u e E S e4 5 =J gp 4 as 4 9 U 1 W O w as a to es a b e O 90 tf ht af 3 3 3 3 0 m O hi tf 93 48 3 3 3 3 9 to e me a te a en es e en 3 en S3S to e == S hl S et td e e 3 en 33S E De E E S 30 kB 88 45 44 e e WB 3 3 3 5 S e R> E S E tieledtese e etat 3 3 3 m S as be se u e* es be == u .J as B 3 as 4 e B 3 ed 4 e se a M 3 == a k 3 9 se O O O se O a
- t S k E et G > S
.S8
I 9
u a e #
e en 4 .J 4 .4 J g to e m M N N em e es en e e se a me A g N e e e e h me g a e p e g N pen !
u > ee = e e ce en se ce ee me se se me en == mo >
e.ene ase e e e n.e m e m m m o e m V
O a O m se . m e eJ k =e
.ed a =J i se me p 8
& O & 9 e e e e 1
4 o ......... 09 09. . 4 e 99.....O 0999 9.
m = m
! A A O
=
e*
.e. e en i 8 OOO0890999999999 9 e 9969999990000000 0 l C E
<: e a b eeeeOOOOOeOOaOOO O
~
O O O O O O g o ee O O O O e O O
<: T.
. O.
c O e e
= O.
>3 m
! < e e h
o .
I O e e e O pe == == 09O==0OeeOOOOOOOM N == en seO.eee me.eOOOOOOe N O N a a == ==
- i
== W se Q me e h e og a m e
A x C W g u O u O O$ ma e as e C, e a mam*name*=NMOOme e a >
eJ **
e e s O e h n se eee == e
==-Neormmee m -s e se m se ee.c N
$ $ .J as N b >
u o M e W W to am > > c E e4 e es t
4 4 ed e O m O A S
- 3 3 e b 4 e e emee9haeseNe@MSO N 4 9 e meh==e=M*McMh=de m O % O "" " = % e a *
- m e * * * " M e* = = a e*
}
$ p% es m'e "m e .O e .e. d 4 5 e '
8 e Z O k 4
M
( O H e W g h m 4 e.: C >e et a o se a ,
E b a e
e
% e o e en o.
e m et e e N O e e e h e e e m me 3 % a M e e G O P e a e h e e m es ce see eC N
D e E I NN e O E t M m e e M =a == ee m se ** re M M ee N N p a w = = g w = e v >g =I a a N e
3 a N e
g M M ma w W se b a mO a 6 m o a e O m O. .
es e
ee 6 re O N N ce se O m en O e e N O e a se ee h Mem e e N h e e e m se 3 m p h e H t == == * > a e se == re ce se as es .= == o c u es .ae e e
u as .ae e e
ce a
e 3 == m 3 .-
)* me a
on y e a Z e
- e m o W B ==
- m a e O O O 9 0 .e o n O .e e., e m a .=
. 4 e re O 4 h.eem o == seO e e eese e esees> == e e .m. se y
.I.
Q A e a e ,
as == es se L
- b. es gg a.s a e.
g a o* e e*
e OnaooooooooOOOOn e e emen=Ognmaneenee e g a . , > a i m .
= e se se e p Z 3 m me 3 % oo e e .J e ed
. en t.
O O e O em m
M e 4 e 4 s
a a e a a >
O
==
e O==0 0==0 e O O O O O O O O = m a O e O O re me se o o e o se se == re == N O N m 6 se I =
k == H =
D e B e I e
We e U e se o e a e
> 0 to o se e W e e e i
- e e OOOOOOOOO909OOOO O O == = O == == O O en O == 0 == =a == == 0 == O
- e !
e i es a i no !
e e
> M e4 > a e U *- E U e 3 m e4 S ed as 4 es 4 e u a w or &
1 e* O to us a to e O S se es as es as 3 3 an es e e3m 3
83 4 m to O es y as es 3 3 y e I to 3 he S G o. 3 es 3 e es e a3m W3 ]
3> 3 3 3 as as to e en et en et 3 3 3 S W S> 3 3 A es as es e et e e G S 3 $ S 5 to se G .A q > em Q =J q 5 3e 4 e B 3 as 4 e en a g e >
O Ie to me O = G e 9 = j M e to S 9 e to E i l
l l
39
e et en et a e se 4 e4 4 eJ ed as ce e e N e e as e e e e e e h e e4 e 4 W me ** * . e e h es e O e g e N pg g e e
> e en o n e am e *e N e o c eoe e o s ee me e se se se == se = es a es uo U k O
d e e e H M e e e p e s en c e ce el & M e4 >
== en o ed en se se
==
m 9
@ O 1P O m o en e 4
A
...............O . 4 e .................
A O
e ee e e e.s .............O.. . s.e .......e3......O .
e o e e se ==
4 m e b I oo0oo000o0o.0000 0 ... 00 0e0 00oos e: . .I 0 O .
O O.
. em d h h eC e e e o U e O e O
= ee omOoogeMONeee.OOO O se M e se
=
a 0000000000ee.0000 y a en a en ts e u C e h a h e
a a a w
C v as v o cc w O. w e C a h m e .m e e fve d e e eme N O O O O 4 h OOOOOOOOOOOOOOOO O W $ ed i
se e i
% m2 es y te e as e
=
> > e W e m to a
> e me g 4 m
4 4 J O e o S S
- a 4 0 e
$se O
0 em h e e e se e e a h 9 e e M N e O M es 4 e e e O M O e M es se O O O O O se *
- O *t em e
en e en e M N e e N em se M e *t O I N g e se -
g e e e
4 e.
a6-O > ** O > e e
to 4 at W W C to g a a O w sc g,b e e
et e e
a en o
a=. m e m ee - c = e e e e m m e e e e e o % e e
meehmeceecheceme
< p O g
a g,,
e emeencemennem==m e O a a ==n= -n ====
h e
b *(geg E se. e g w me me w a a n a e ee e
me M 82 me se to p a 9 w O
sm a e e h oe M w N MOpmemmeehNememe m O
w M
a pas M G t en M N m N esse N m pg m M N esM en e S hhedeeceSeeheNeme U S e m De , se se se e se M se se mo le gm-as se e U S e, se en on e 3 se e
p as 3 en se a a O e e g a e a e W
5 4
es emmONeeNeeeeseoee em se e se e, 3 se OseOdemeehOheehah e e~ em 6 enseem M N M e M se = e 4 i N ** se e m M N N ** me N e e N me me N e C" u .e e lu M . .o h M E w O to Ele
- m O a v m m e N e v e nus e e e. s a a e n cepee e w a =, vehnheecheeeh0h-o n u n ev ev ee e
b en d m
e me H en e N
to g 3 e
em 3 h as W en se b e
ma C e e o om e
e e D E h De 5 e
h 4
O e mMCOeOMMeeOeeeMm e et O he en e en e ne e
e e e N O e en m me e a e e De e P N st 6e me 6 en me en en O De se o e a e me a e W e e me en se e ts
> O De O ut e GI en e se e me es es se se e et O M N en e se se me h me O en e e
& N m M N M M e se e en e M e en eg et M O e
4 si en e i e Gb en De m a > **
48 e m S E U e R
as ed a me as he D W D aE O O W e 3 to ts a e O te el t$ 3 3 3 3 . e en Gn a e. e as a kl et as en a3m a3m O
a en as te to W 3 3 3 a y )a O Gm a me a en to a en 3 e to .a euto E S & W B0af a e a e m 3 3 3 a a e m> a a a me es to a e e a em 3 3 3 m a a S
J e k se W J ma
==
3 as e e 5 3 as 4 e a to B ** e e == & De E 9 O se O S et e > S *t A De S 40
. ~
G .
e s e
4 .A sa 4 M e e m h e M h me M e es e e e e e U > m es a == se e m e e e e e e e i O e J >
ea se 5
e
.e 4 e soseeoOooooosees e 6 =
A 3
e e
7, ee eessesseossee s
- 5
< a b
I-sooooooooseeesoe e ,
C o
.e m
4 e e o
e
= -
e oooooo.oooooooooo o e ~
o I
- a S ,
?
C $ e M
o w
X
( se..o..ooooo.... e c
p >
t-
> e A. e as E 4 .a e o*
I S S b 4 4 e DeseOOooeme.oeoO =
C ' * '
, e = =
- T 4 e e 1
2
- 4 1 y o a om o e o e se e A b e % e *Mone=MaeoooMoMee .
< g S e M H[mmC a e
M M m
- b g 6 .*
M "
j - M es e ee e - se N m . . M n e - @ M M ke > e a so se e 1 g U S e
, e =
- e 3 se i
p me O
- e e
I 2 e o eM i
y S ** eeMeMM@ e e e N N e e e se e se e I 4 6 M N N M M M se M =e e hM r l e e so e
M @ se O as se W es 6
4 8 .
M e eo oe b em e ao M M es M es e se e e e o e se o e se em ao se i
S 4 M M M M N es se4 > kk
.I"* ** e 9 as > en se !
m M JJ J
E 3 e sa se N h as 44 C o e >>
I e 4 em i 9 8 m >
}
o oe e emo.co-MMmeceeemee ao ao es e e JJ et e8 e
44 $
> a e e es I
e
- U
- OO
, a ha
> 0 e
- e e e 1 em o M M M M M esse M M M M @ es e e h so O e 1 e 4 es se se es b e e m
> P e OS d U e E e 1 8 =J G l e 4 es j 1 g U e ed i
, y se 4 m 8 . l e 8 m a e e . 9 B
e Jt e
> es j h e se SeS e af e e3e S> a a S e asas e e at e e 3 3 S e
> ee U J q J en
,I S Be 4 e de se a kk e - I ee M e >
l 41
/ -
TABLF 5 (1 of 2)
DOSF CALCULATION RESULTS FOR 1987 (DOSES DUF TO CASFOUS RADIOACTIVF FFFLUFNTS) 17 1997 WTD 2 0F 1997 DOE F1DI W!O!3 PittT!QLATTS. M TRIT!lM DDEE FIUt M101@!ES. Pf$7!0!ATES. Age TRITILM AT COGOLLIW LOCAT!WI AT CafTROLLIG LOCAT!Gdt TOTAL 006E OVEM) FGt f(BE 4.4641E-03 TOTAL DJSr OfEM) FOR 3GC t 2,9991 44 '
TOTAL DOE OfEM) FGt LIG t 1.1846E42 TOTAL 005E 0900 Fm LIG 5.3304E-03 '
TOTAL 006E (19EM) FGt TOTAL BWY I 8.182VE-03 TOTAL DOSE OfEM) F01 TOTAL BODY I 5.0871E 03 l
- TOTAL DOSE DIEM) FGt T)MIO!D t 5.9652E-01
- TOTAL 006E (NEM) Fal l)M0!D 4.367E42 TOTAt. (DGE OfEM) FQt KlGEY I 1 TOTAL COSE UfEM) FGt K!DEY t 5.2097E43 TOTAL DOSE OVEM) FGt Lt8dC I 7 515X-03 0051E-02 TOTAL DOIE OfEM) FM LLE3 8 5.0474E-03 TOTAL 006E OfEM) FW O! tt! t 7.2635E43 TOTAL DOE OfEM) FGt O!-tL! ! 5.0240E-03 NCEE GA6 DOSE AT $ITE 801.80lRY NDEE GAS DOE AT SITE 80.80*Y:
TOTAI. BODY 00SE TOTAL UTEM) 4.0854E-02 TOTAL ICBY DOSE TOTAL OfEM) I 2,7102E-01
$1N DOSE TOTAI. OfEM) I 1.1784E41 $ !N DOSE TOTAL Uf HI) t 6.4492E-01 ME GAS A!RDOSE AT SITE 80. DORY: NDEE GAS AIRDOSE AT SITE BOLN)ARY:
TOTR CM 4!RDOSE Usmo) 5.8140E42 TOTAI. GM AIRDOSE (IfM0) : 3.2159E-01 TOTAL ATA Al b27 OfMC) i 1.6735E41 TOTAL ETA AIRDOSE OfMD) 9.1175 -01 W TER 3 0F 1987 ..
EllRTER 4 7 1997 DOSE FROM fuo!0!00!ES. PARTIO.LATES. M TRIT!lft DOE FIDI IMDIO!0D!IES. PART!QAATES. M TRIT!tM AT CDITM(LLING LOCAT!Wt AT CD(TM3J.!W LOCATION:
TOTAL DOSE OfEM) FM B0E I 7.3714E44 TOTAL DOE 09EM) FOR BGE I 9.6561E-05 l TOTAL 00!E 09EM) FGt LIVER t 5.5799E-01 TOTAL DOE OfEM) FGt LIG 1 9.0169E42 TOTAL DDE 09EM) Fm TOTAL BODY 5.5731E-01 TOTAL DOIE OfEM) FGt TOTAL IGrf I 9.010E-02
- TOTAL 00!E OfEM) FOR T)MIO!D t 6.241 5 4 1
- TOTAL DOE OfEM) FR TWWt!D 1 1.255X41 TOTAL DOSE 0001) FOR Klt8EY 5.5758E 01 TOTAL 00!E 0900 F5t K I 9.0186E-02 TOTAL DOSE UWEM) FGt LLM0 1 5.5725E41 TOTAL DOE USEM) FR I 9.0061 42 TOTAL DOE 0000 FGt 01 tL1 1 5.5719E 01 TOTAL 006E 0990 R5t 6 41! t 9.0064E42 NOBLE GAS DOSE AT $1TE 80ucRYI NDEI 046 DOE AT $1TE I(BASIRY TOTAL BODY DOSE TOTAL OfEM) 3.6219E41 TOTAL SCBY 00E TOTAL OfEM) I 1.8966E41 SKIM DOSE TOTAL 0900 t 8.5017E41 $!M DOE TOT 4. OfEM) t 4.395N41 N0EE GAS AIRDOSE AT SITE 80llefRY NOILE 046 A! RODE AT $1TE BOLIORY:
TOTAL Gaff % A!RDOSE DfWC) 4.2900E01 TOTAL 04HPM A!RD06E 09140) I 2.1602E41 TOTAL ETA A!RDolE Of%D) I 1.1867E 00 TOTAL KTA A!RDOE UfMD) t 4.9729E 01 :
TOTALS FGt 1967 DDE FWM FWD 1010 DIES. PARTICLATES 40 TRIT!(M AT C3(TMLLIE LOCATimt TOTAL 00EE OfEM) FM IDE t 5.6177E-03 TOTAL DOE (IfEM) FGt LIG I 6.6534E-01 TOTAL DOE OfEM) FGt TOTAL BODY I 6.6069E-01
- TOTAI. DOSE UfEM) FGt TWi110!D 1,3e99E 00 TOTAI. 00EE OVEM) FGt K!IBEY I 6.6303-01 TOTAL DOSE OfEM) FGt LtM0 1 6.5997E-01 TOTAL 00K 0900 FGt 01 LLI 6.5954E-01 NDEI 0A6 00K AT SITE BORDORY:
TOTAL SCCY 00EE TOTAt. OfEM) 8.717X-01 EIN DOE TOTAL 0900 1 2.0605E(C NIRI GAS AlfW0tE AT $!TE 80L9tARY TOTAR. GAfft A!RDOE Ofte) 1 TOT 4. ETA AIRD0E OfflD) I 2.7631E 023E 00 00
- Critical Organ for the period.
42
TABLE 5 (2 of 2)
DOSF CALCULATION RESULTS FOR 1987 (DOSFS DUE TO LIOUTD RADI0 ACTIVE EFFLUENTS)
- e MTB 7 iM7 TOTE DOE ( ) FW R I 5.446 2 -03 7074. DOE ( ) FM L I 7.9574E-03 TOTAL DOSE ( ) Fm TUT 4. 300Y t 5.2370E43 TOT 4. DOE 00EM) Fm T)M0!D t 6.529E43 TOTAL 00E DIEM) Fm K!MY 2.6396E-03 TOT 4. 006E DIEM) FM LLee i 1.052W-03
- TOTAL 001E (W) Fm 01-tLI i 1.62tX-01 ,
WTG 2 0F 1987 TOTAL 006E OGER) FM M t 2.1300E42
- TOTAL DOSE DIEM) Fm LIG t 3.5070E42 TOT 4. D06E (lGEM) Fm TOT 4. BODY I 2.5190E42 TOTAL DOSE UWEM) FM T)M0!D t 1.010E-03 TOTAL DOIE (NEM) Fm KIMY t 1.181E-02 TOTAL D0!E OfEM) FOR Li4G 3.9490E-03 TOT 4. 00E OfEM) Fm 01 t!.! t 2.60 EKE 42 MTG 3 0F 1987 TOTP., DOSE (NEM) FM DK t 1.4617E-02
- TOTAL DOSE DIEM) Fm LIG t 2.3777E42 TOTAL DOSE (NEM) Fm TOT 4. 800Y I 1.7222E42 TOTAL DOSE UWEM) FOR T)M0!D 4.001 2 03 TOTAL DOSE (MEM) Fm KlDIEY t 8.0910E 03 ,
TOTAL DOE (NEM) FOR LLNG t 2.843E 03 TOTAL DOE (NEM) FOR 0141 1 2.1226E43 MTG 4 0F 1997 TOTAL DOEE (NEM) Fm SOff 8 6.6149E-04 TOTAL DOSE (MO() FM LIM i 1.6264E 03 7074. DOE (NEM) FOR TOT 4. 33)Y t 1.2602E-03 TOTAL 006E (NEM) FM T)M0!D I ?.4248E42 TOT 4. 006E (NEM) Fm KIMY t 8.52iAE44 T074. DOSE OfEM) FM Ltse t 5.0992E-04
- T0hlt. DOE (NEM) F2 01 tt! I 1.2957E-01 TOTALS F m 1967 TOTAL DOE OfEM) Fm IM 4.210E 42 TOTAL 006E DIEM) FM LIM t 6.8430E-02 TOT 4. DOSE (MEM) FOR TOTAL BODY t 4.9909E-02 TOT 4. 00EE 00EM) F3 ThMt0!D I 3.5799E-02 .
TOTAL 00E 00EM) FOR K!MY t 2.3393E-02 TOT 4. DOE UWEM) FM Lule
l l
l l
- Critical Organ for the period.
43 x
. 6 i ;
a >
I 5
P i
j 4
1 i
l I
l t
ATTACHMENT 1 l OFFSITE DOSE CALCULATION MANUAL HP-1-230, REVISION 6 l f
i 1
k 1
2 4
l 1
1 J
9 I
1 i
i I
4
- ---_._ - ,__ - , - - - - . - . , - . . -- .,