W3P89-0044, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1988
| ML20235W079 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1988 |
| From: | Burski R LOUISIANA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3P89-0044, W3P89-44, NUDOCS 8903100486 | |
| Download: ML20235W079 (52) | |
Text
.
g g
V y
Semiannual Radioactive Effluent Release Report July 1, 1988 - December 31, 1988 Waterford 3 SES Louisiana Power & Light 8903100486 881231 PDR ADDCK 05000382 R PNU W310526HP
\fN .
TABLE OF CONTENTS 1.0 SCOPE i
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 GASEOUS 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 Boundary 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 8.5 Missed Effluent Samples 8.6 Corrections to Previous Semiannual Radioactive Effluent Release Reports 9.0 TABLES 10.0 ATTACHMENTS W310526HP 1
J ., e m; "5 1.0 SCOPE
.s This Semiannual Radioactive Effluent Release Report is submitted as-required by Louisiana Power and Light's Waterford 3 Steam Electric Station =
(SES) Technical Specification 6.9.1.8. It covers the period fr m July 1, 1988 through December 31, 1988. Information in this report is presented 1 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 sunnary of the meteorological data collected during 1988; (3)' Assessment of radiation doses due to liquid and gaseous radioactive effluents released during 1988; (4) Explanation of why certain instrumentation was not restored to operable status within the time specified in the ACTION Statement,
,4 as per Waterford 3 SES Technical Specification 3/4.3.3.11; (5.) A summary of missed samples required by Waterford 3 SES Technical Specification 4.11.2.1.2; (6) A description of changes made to the Offsite Dose Calculation Manual; (7) A report on unplanned releases which occurred during the reporting period; and (8) A summary and correction of errors identified in previous Semiannual Radioactive Effluent Release Reports. l W310526HP 2
1 4
w -
h
, 2.0 SUPPLEMENTAL'INFORMATION 2.1 Regulatory Limits The Technical Specification Limits applicable 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 2nd 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 to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
2.1.2 Iodines; Particulate, Half Lives > 8 Days; and Tritium i
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 limited to less than or equal to 1500 mrem /yr to any organ.
W310526HP 3
, ; x; m ,%l 3, -
' _" y -
i f;;g, y y 49 Tis' , ,
yc + , :
l u 5 .,J,g' 1 "p . a'< . ,
- 7. (
pg < , '
' ( J .. . . , 4
-V
( ', . (; _ q , ,,
1 i
~
1, ', /Thedoseioam< ember.offthelpublicfromIodine"1311andl133h
~
tMitium? an'd all radionuclides 11n parti $ulate/ form with half .j n , ,
' lives great.nr than'eight; (8) days;in gaseous:. effluents.
~
v ,
.- 4 n
{
^'
@w ,
released to arsas at and beyond.the' sit'e bo'undaryLsha11'be.
1 H
' limited (to'the following: '
. ,. s m e.g h r b :a. During any calendar quarter: ~Less;thanor'equalitof7.5i mrem tocany.. organ'and, i
1
-)
'b. During 'any calendar ' year: LLess than or equal toL15, mrem l ,
to any organ.
- 2.1.3 , Liquid Effluents .q o
. -j l . .. !
The concentration of radioactive material released'in liquid 1 i" 1 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 l entrained. noble. gases. -For dissolved or entrained noble ,
-1 gases,.theconcentrationshallbelimitedto2.0E-4'pci/m1L i total activity.
^
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:
1
- 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.
W310526HP 4
. .. . i
2.1.4 Uranium Fuel-Cycle Sources The, dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel-
. 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 12 consecutive months.
2.2 Maximum Permissible Concentrations 2.2.1 Fission and. Activation Gases; Iodines; and Particulate, Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable 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. !
2.3 Average Energy I
This is not applicable to Waterford 3 SES's radiological effluent technical specifications.
I l
2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liqaid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 4.11-1 and 4.11-2 of the Waterford 3 SES Technical Specifications.
W310526HP 5
pg +
s.. u yt.
A:, t, . ;
.+., i ' , '
l i p[ % . 23,1;: Fission' and Activation Gases (Noble Gases) .l
~For continuous releases, aigas; grab sample was. analyzed- !
O> monthly for noble-gases. .Each week a Gas Ratio (GR) was I calculated according to the following equation:
p .
' N GR = Averag'e Weekly Noble Gas Monitor Reading-
.i ; - Monitor Reading During Noble Gas Sampling-
)
j 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 a'nd-containment purge batch releases, a gas grab sample was analyzed prior-t'o-release to_ determine noble gas concentrations'in.the batch.
I In all cases the total radioactivity in gaseous effluents was determined from measured concentrations of.each radionuclides
- present and the total volume' discharged.
2.4.2' Iodines and Particulate
-Iodines-and particulate 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 determined radionuclides concentrations-and effluent volume discharged were used to calculate-the previous week's activity released.
The particulate samples were composited and analyzed quarterly for Sr-89 and Sr-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.
W31052611P- 6 1
1 1
.;J Grab samples of continuous and batch releases were analyzedL monthly for_ tritium. The determined 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 radionuclides concentrations in' the previous week's releases. For batch releases, gamma analysis was performed on the sample prior to release.
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 measured in the composite =
samples, the measured concentrations in the composite samples from the previous' month or quarter were used to estimate released quantities of these isotopes in liquid effluents during the current month or quarter.
The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclides present and the total volume of the effluent discharged.
2.5 Batch Releases The summarization of information for gaseous and liquid batch releases is included in Table 1.
l 1
W310526HP 7
. 2.6f Unplanned Abnormal Releases _
i Unplanned Release on November 30, 1988' Description of Event:
On November 30, 1988 at 1620, an unplanned release was made via the Plant Stack,-which did not result in any related Technical Specification limit being exceeded. Based on the Plant Stack Monitor reading and grab sample results the maximum total body instantaneous dose rate was calculated to be 216 mrem /yr or 43.3% of the 500 mrem /yr limit. 'The gamma and beta doses in air for the entire duration of the' release were both less than 0.009 mrad or 0.09% and 0.05% of the respective annual limits.
Cause of the Event The normal vent pathway for the Volume Control Tank (VCT) is to the Gas Decay Tanks (GDT) from the Gas Surge Header (GSH) and Waste Gas Compressors (WGC). Station Modification (SM) 461, implemented in March of 1986, allows venting the Boric Acid Concentrator (BAC) to the Vent Gas Collection Header (VGCH). Before SM 461, the BAC was vented to the GSH. This provided a second vent path in' addition to the existing vent to the GSH. The VGCH is vented directly to the Plant Stack.
There are valves on the vent pathways to prevent a dischage directly from the GSH to the Plant Stack; BM-252A on the VGCH and GWM-121A on the GSH side. With both BM-252A and GWM-121A open, a path is established from the GSH through the VGCH to the Plant Stack. On November 30, 1988 the VCT was being vented and the two valves were open.
The root cause of this event is cognitive, personnel error.
Operations personnel operated valves not specified by procedure during the startup of BAC A. The operator had trouble esta-blishing feed flow through BAC A and opened GWM-121A. The operator did not realize he was cross-connecting the GSH to the VGCH.
W310526HP 8
. Actions Taken to Prevent' Recurrence A Problem Evaluation Information Request has.been sent to engineering to evaluate'the BAC design and the possibility of installing a spool piece in the vent path from the BAC to the GSH. Valves GWM-121A&B are being added to the locked
. valve list in Operating Procedure OP-100-009.
Radiological Consequences of the Release:
At no time during this abnormal release were any of the Technical Specifications exceeded. The dose calculations and related Technical Specification information are given in Table 6. All calculations were performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual.
3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A, IB, and 1C. 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 wastes shipped offsite for disposal is listed in Table 3. For certain waste forms Waterford 3 is now using volume reduction services provided by Scientific Ecology Group, Inc.
These waste forms are identified in Table 3 and volumes reported reflect the volume of waste shipped offsite, not final disposal volumes.
W310526HP 9
9
\6 -
'V u
l", 6.0 METEOROLOGICAL DATA
'In Table 4 the hourly meteorological data from January 1, 1988 through December 31, 1988, is presented in the form of joint frequency distribu-l tions of wind speed, wind direction, and atmospheric stability. The Waterford-3 data recovery results by parameter are as follows:
Parameter. January - June July - December Entire Year Delta T 99.4 99.8 99.6 Wind Speed 82.8 99.0 90.9 Wind Direction 82.8 99.8 91.3 Overall* 82.6 99.8 90.7
- Simultaneous occurrence of valid data for all three parameters.
7.0 ASSESSMENT OF DOSES 7.1 Dose Due to Gaseous Effluents 7.1.1 Air Doses at the Site Boundary Air doses from gaseous effluents were evaluated at the closest offsite location that could be occupied continuously during the term of plant operation and that would result in the highest dose. This location was determined by examining the atmospheric dispersion parameters (X/Q's) at the closest offsite locations that could be continuously occupied during plant operation in each of the meteorological sectors surround-ing the plant. The location that would have the highest dose l would be that location having the most restrictive (largest)
X/Q value. Based on actual meteorological data collected during 1988, this location was determined to be in the NNE sector at a distance of 1207 meters from the plant. Since the W310526HP 10
h,k ',} , jy !: .jf S x s 1.. . s- ,
,j ,' .
i ~ ' l
' ~
L;7 <
lsiteboundaryiintheNNEsectoroccursdirectlyoverwater,
- the' location selected correspon'ds to.the closest 1and beyond <
~
.thel site boundary in the NNE. sector. Doses were assessed'at
- this location in accordance with .the methodology described in the Waterford 3.0ffsite Dose Calcula' tion Manual considering o
hi 'onlyfbeta and gamma: exposures"in air due to noble gas. The g
results of these assessments- for the year.1988 are. summarized 6 as follows:
h-g Beta air dose: 2.04 mrad Gamma air dose: '0.7$L mrad The beta and . gamma air su'es are 10.2% and 7.6% 'of the Annual:
Technical SpeclJication Osse Limits, respectively._. The.
results of the dose' calculations by quarter are. summarized in-Table 5.
-i 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 1988.
W310526HP 11
.; -~ ,-
n . -
n 3
5 57 '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 to1the' plant havingEths
-most restrictive atmospheric dispersion parameter (X/Q).
1Furthermore, it was assumed that the. receptor living at this residence consumed food products 1that were either raised or produced at-the nearest residence having the most restrictive.
(largest) atmospheric deposition parameter (D/Q). .Using~1988 land use census and meteorological data for 1988, the residence with.the highest X/Q value wasfdetermined to be in the NNE sector'at a distance of 1287 meters. The residence with the
. largest D/Q value 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.
The maximum organ dose to the critical receptor was determined-to be 1.12 mrem to the infant thyroid. This represents 7.5%-
of'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-exposure to liquid effluents released during 1988 from Waterford 3 SES were 0.44 mrem total body and 0.60 mrem to the maximum exposed organ (liver). These values are 14.7% and 6.0% respectively, of the Annual Technical Specification Dose 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.
i i
W310526HP 12
}' l b , ,
l
- ; , , * +
1g,g y.y--
,01- .t 7.3 40 CFR' Par't 190 Dose Evaluation l
L <
11L 'a:cordtace with W'aterford 3 Offsite Dose Calculation Manual, I. Section 8~15,-dose' evaluations to demonstrate compliance with Surveil-lance Requirements 4.11.4.1.and 4.11.412 of the'Waterford Technical.
Specifications, dealing with' dose from the uranium' fuel cycle,'need-to be performed only if quarterly doses exceed 3 mrem to.the total body (liquid. releases), 10 mrem to any organ (liquid releases),J10 mrad gamma air dose, 20 mra~d beta air dose, or 15 mrem to any organ from radioiodines and particulate.
At no time during 1988 were any.of these limits exceeded;1therefore,.
no evaluations.were required.
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,.
approximately 670 meters-from the plant. Based on an-assumed occup-ancy 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 that all employees are-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 con-sidering only the inhalation pathway.
V310526HP 13
- 1 -j I
8.0 EELATED INFORMATION !
j I
8 .1 - Changes to the Process Control Program 3
There were no changes to the Process Control Program for the period.
I covered by this report.
8.2 Changes to the Offsite Dose Calculation Manual On August 28, 1988, several changes to Revision 6 of the Waterford 3 SES Offsite Dose Calculation Manual were approved by the Plant Manager-Nuclear.
The changes were made to correct a typographical error in the equation for monitor setpoint calculations, include 1987 meteorological data, change the location description for two Thermoluminescent Dosimeter's (TLD) that were moved and to correct typographical errors regarding the sector directions for two water sample locations. Copies of the affected pages are included in Attachment 1 of this report. These changes are summarized in the following sections.
8.2.1 Equation (26) was corrected by changing KKr-88 ' O Kr-88, which is the maximum release rate for Kr-88.
8.2.2 Table 1 (Attachment 10.1), " Annual Average Dispersion and Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary" was changed to incorporate meteorological data collected during 1987.
8.2.3 Table 3 (Attachment 10.3), " Sample Location Table" was changed by correcting the location description for TLD D-2, which was moved from a survey marker to a fence at the entrance to the spillway; correcting the location description for TLD H-6, which was moved from a construction sign to a road sign at the same location; correcting the sector direction for GWJ-1; and correcting the sector direction for DWP-7.
W310526HP 14
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),
3.3.3.10 and 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 three separate cases when instrumentation was not restored to operability within the time specified. These cases are described in the following sections.
8.4.1 Monitor
Waste Gas Holdup System Hydrogen and Oxygen Monitors Period of Inoperability: 3/21/85 - 08/05/88 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 0 and Delphi H and 0 2 2 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.
W310526HP 15
e:p, .,. .. O '
f %f if <MN 1
[
j '
-' Reason Operability Not' Restored.Within Allotted Time:
u .
Extensive hours were spent attempting'to restore these
,', analyzers'to op'erable status. LSeveral analyzer cells were
- replaced, the solenoid and regulator were repaired, Land the:
,. sample pump was.both-repaired and replaced. After these.
, efforts failed to 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 e~xisting piping and electronics associated with the Waste Gas Holdup System
. Hydrogen and Oxygen Monitors was essentially scrapped and
- redesigned.
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-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.
panel to accommodate the new exo-sensor units; (3) installing a new pump and its associated 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 the Gas Surge Tank the sampling pump diaphragm was blown.
This event also identified other problemn with the system which required correction.
o
=W310526HP 16 u___ _____ ___ -__
Design changes have been made to uncross the lines and install a pressure switch to prevent any subsequent overpressurization.
The pump was replaced and new wiring was installed. Additional moisture traps, pressure 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 perfonned on the system after the plant returned to the operating mode following a refueling outage. The operational checks demonstrated that while the piping and sample tubing 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.
Based on the problems encountered with the analyzers and sample / analyzer system, a new sample / analyzer system has been designed and installed. The improved system was designed with emphasis on sample conditioning, use of proven analyzers for the application and simple design. Initial testing has been completed. Initial operation began on June 29, 1988.
Final testing is complete and operating procedures are in place. The analyzer system was returned to service on August 5, 1988.
8.4.2 Monitor
Waste Gas Holdup System Noble Gas Activity Monitor Period of Inoperability: 10/19/88 to 12/31/88 Time Required by Technical Specifications To Restore Operability: 30 days Cause of Inoperability:
l The monitor was full of water.
W310526HP 17 I'
e
,- Reason Operability Not Restored Within Allotted Time:
The Gaseous Waste Management (GWM) System effluent monitor was taken out of service on October 19, 1988 due to severe-moisture problems. Design Change (DC) 3117 Revision 0 was initiated to correct the problem by relocating a check. valve from the upstream side of.the moisture trap to the downstream side which is at atmospheric pressure. Prior to the change, with the valve on the upstream side of the moisture trap, a vapor lock was formed. When the check valve opened 15 pounds of pressure would become trapped between the moisture trap and the valve forcing the check valve to remain closed thus not allowing moisture to pass out of the sample line.
-After the DC was completed, a functional test was performed which demonstrated that the calibration was off. During monitor calibration it was determined that it was necessary to rebuild the detector. The failure of the detector was-attributed to the excess moisture collected in the sample chamber. Once the detector was rebuilt, the monitor was recalibrates. Following recalibration another functional test was run. As part of the functional test it was necessary to cause the monitor to isolate on a " loss of counts" signal.
When this test was performed the monitor did not initiate isolation of the discharge isolation valve. Extensive testing was done on the I/O Board which controls the isolation signal and no problems were revealed. With further investigation it was discovered that a relay created a noise spike which cleared the " loss of counts" condition before the valve could close. This problem was remedied by installing Electrocute Noise Suppressors across the relay under Temporary Alteration Request (TAR) 89-01. After this was done the monitor passed the functional test. A Station Modification is being done to make the TAR permanent.
The GWM monitor was still inoperable at the end of the reporting period, but had been placed back in service on January 6, 1989 prior to the issuance of this report.
W310526HP 18
k i o 1 8:4.? Monitor: Gaseous Waste Management System Effluent Flow Rate Mesouring Device Period of'Inoperability: 6/29/88 to 8/26/88 Time Required by Technical Specifications to Restored Operability: 30 days Cause of Inoperability: The in place flow meter was not suitable for measuring an increased flow rate and a malfunc-tioning back pressure regulator would cause inaccurate readings.
Reason Operability Not Restored Within Allotted Time:
Part of Station Modification 1328 involved making changes to increase the discharge flow rate from the gas decay tanks.
As part of Station Modification 1328, engineering calculations showed that the scale on the in place flow meter would not be suitable for the increased flow. A new scale for the flow meter had to be ordered from the manufacturer. In addition, the back pressure regulator for the flow meter did not function properly, and as a result a constant pressure could not be maintained at the flow meter. This condition would render any flow measurements questionable. Following repair to the flow meter, the flow rate measuring device remained out of service until engineering was able to successfully resolve the problem with the back pressure regulator. The system was returned to service on August 26, 1988.
W310526HP 19
L n
-Q * "
,; '8.5 Missed Effluent Samples On November 10, 1988, it was discovered that the weekly.
particulate and iodine analyses of the "A" train Fuel Handling-Building (FHB) normal ventilation exhaust were not performed within the required 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Technical Specification (TS)
Surveillance 4.11.2.1.2 Table 4.11-2 Section D.1 requires these samples to be analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from the time of collection. Both semples were collected at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> on November 7, 1988. The Health Physics Technician who collected the samples did not have enough time on shift to analyze them, but failed to place them on the turnover checklist. As a result, sometime during the following shift, the particulate filter was stored for later compositing and the iodine cartridge was discarded. By the time the mistake had been discovered, the iodine cartridge could not be located. Therefore,- aly the particulate filter could be counted. The root cause of this event was personnel error. As corrective action, the Radiation Protection Superintendent counseled the responsible individual and discussed the event with other Count Room Technicians.
A complete description of this event was reported to the NRC in I.ER-88-029. Although the particulate sample was later analyzed, effluent discharges of radioiodines were estimated using iodine results from the FHB "B" train which was in service for a portion of the week.
8.6 Corrections to Previous Semiannual Radioactive Effluent Release Reports I
While reviewing the effluent release data covering the period from January 1, 1988 through June 30, 1988, a typographical error was found on page 33 of that report. The curies of C-14 (Carbon-14) in spent resin solidified with cement was incorrectly report ed as 5.08E+02. The correct value should have been 5.08E-02 curies. The corrected data is included in Attachment 2 of this report.
W310526HP 20
V Ltfl}
9.0 TABLES-1 Batch' Release Summary; l 1A Semiannual Summation of'all Releases by Quarter - All Airborne 1
!' Effluents
'IB Semiannual-Airborne Continuous Elevated and' Ground Level Releases
-IC 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 Calculation Results for 1988
- 6. Dose Calculations and Activity Calculations for the Unplanned Release.on November 30, 1988.
10.0 ATTACHMENTS
- 1. Affected Pages for Changes to the 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, 1988.
W310526HP 21
4 i
TABLE 1 (1 of 1)
EPORT CATEGORY : BATCH RELEASE Su MARY ELEASE POINT : ALL TYPE OF RELEASE : RATCH LIQUID AND GASEOUS PERIOD START TIE : 4368:00 M S = 12:00AM JULY I, 1988 PERIOD END TIE : 8783 59 R S = II:59PM DECEMBER 31,1988 LIQUID RELEASES NUMBER OF RELEASES : 67 TOTAL TIE FOR ALL RELEASES : 18502.0 MI M ES MAXIMUM TIE FOR A RELEASE : 353.0 MI WTES AVERAGE TIE FOR A RELEASE : 276.1 MIWTES MINIMUM TIE FOR A RELEASE 153.0 MINUTES A'ERAGE STREAM FLOW 843932.3 GPM GASEOUS RELEASES NUMBER OF RELEASES : 10 TOTAL TIE FOR ALL RELEASES : 3265.0 MINUTES MAXIMIN TIE FOR A RELEASE : 600.0 MIWTES l AVERAGE TIE FOR A RELEASE : 326.5 MINUTES MINIMUM TIE FOR A RELEASE 18.0 MINifTES I
V310526HP 22
7 i I ih TABLE-1A 1
(1 of 1) i REPORT CATEGORY : SEMIANAL SMTION OF AU. RELEASES BY MTER TYPE OF ACTIVITY : ALL AIRBORE EFFLLENTS REPORTINGFERIOD QUARTER S 3 A2 QUARTER 8 4
- lNIT 0UARTER 3 0UARTER 4 *EST. TOTAL:
- HOURS IHOURS ERROR % :
TYPE OF EFFLLENT 84345-65"286553-8760:
A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE ICLRIES 2.14E 02 8 6.87E 02 1.50E 01:
~
- 2. AVERA0E RELEASE RATE FOR PERIOD :UCI/SEC 2.70E 01 8.65E 01 8
- 3. PERCENT OF APPLICABLE LIMIT 1 I N/A N/A B. RAD 1010 DIES
- 1. TOTAL 10 DIE-131 ICtRIES : 5.47E-06 8 4.46E-05 1.50E 01:
~'
- 2. AVERAGE RELEASE RATE FOR PERIOD IUCI/SEC 6.99E-07 8 5.63E46 8
% N/A N/A
- 3. PERCENT OF APPLICABLE LIMIT C. PARTICULATE _
!. PARTIClLATES(H4lf-LIVES)0 DAYS) IClRIES : 5.15E-05 1.75E-05 1.'d 01:
~~'5VERAGE
- 2. RELEASE RATE FOR PERIOD 6.49E-06 8 2.21E-06 UCI/SEC
% N/A N/A
- 3. PERCENT OF APPLICABLE LIMIT
- 4. GROSS ALPHA RADIOACTIVITY IClRIES 2.45E-05 6.60E-05 D. TRITIlM CURIES : 1.33E 02 5.21E 01 1.50E 01:
- 1. TOTAL RELEAT ___
~
- 2. AVERADE RELEASE RATE FOR PERIOD IUCI/SEC 1.68E 01 8 6.56E 00 8
- % N/A N/A
- 3. PERCENT OF APf ICABLE LIMIT W310526HP 23
- n. - -- -. _- __
4
- TABLE IB (1 of 1)
REPORT CATEGORY SEMIA101UAL AIRBORE CONTINUQUS ELEVATED A@ OR0lW LEVEL RELIASES. TOTALS F0G EACH 14JCLIDE RELEASED.
- FIS$10N GASES 10 DIES, AND PARTICULATE TYPE OF ACTIVITY REPORTINOPERIOD : QUARTER 8 3 AND QUARTER 8 4
- ELEVATED RELEASES : GROU@ RE1 EASES :
- UNIT IQlARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 :
- HOURS HOURS- IH0lRS . HOURS :
PUCLIDE : 84345-655286553-876024345-655286553-8760:
FISSION GASES XE-133 : ClRIES 0.00E-01 0.00E-01 1.42E 02 6.24E 02 :
XE-135 : CURIES : 0.00E-01 0.00E-01 : 2.62E 01 2.78E 01 :
CURIES 0.00E-01 0.00E-01 1.68E 02 : 6.52E 02 TOTAL FOR PERIOD 10 DIES I-131 : CURIES : 0.00E-01 0.00E-01 5.47E-06 4.48E-05 1-133 : CURIES 0.00E-01 : 0.00E-01 0.00E-01 2.82E-06 :
TOTAL FOR PERIOD . CtRIES 0.00E-01 0.00E-01 5.47E-06 4.76E-05 PARTICULATE H-3 : CLRIES : 0.00E-01 0.00E-01 : 1.33E 02 5.13E 01 :
CR-51 : CURIES : 0.00E-01 : 0.00E-01 9.14E-07 0.00E-01 :
W 54 : CURIES : 0.00E-01 : 0.00E-01 : 1.56E-06 4.23E-07 :
00-58 : CURIES : 0.00E-01 0.00E-01 3.29E-05 : 1.14E-05:
@-60 : CURIES : 0.00E-01 : 0.00E-01 6.99E-06 3.39E-06 ZR-95 : CtRIES 0.00E-01 0.00E-01 : 1.42E-07 0.00E-01 g 95 : CURIES : 0.00E-01 : 0.0 Z-01 8 8.20E-06 2.14E-06 :
- CURIES : 0.00E-01 0.00E-01 6.71E-07 1.94E-07 :
CS-137 G ALPHA CURIES : 0.00E-01 : 0.00E-01 1 2.45E-05 a 6.60E-05 :
- CLRIES : 0.00E-01 0.00E-01 1.11E-07 : 0.00E-01 :
00-57 10D : CURIES : 0.00E-01 0.00E-01 1.33E 02 5.13E 01 :
TOTAL FOR W310526HP 24
r:
L.,4'- ,
i-TABLE.1C
(:1 of 1)-
l PEPORT CATEGORY : SEMIAMUAL AIRBORE BATCH ELEVATED A2 GROLM)
- LEVEL RELEASES. TOTALS FOR EACH WCLIDE RELEASED.
TYPE OF ACTIVITY FISSION GASES 10 DIES A@ PARTIClLATES' REPORTINGPERIOD s QUARTER 8 3 AND QUARTER 8 4 l
8 ELEVATED RELEASES ^ OROU2 RELEASES :'
LMIT QUARTER 3 IGUARTER 4 IGUARTER 3 8004RTER 4 :
- IHOURS IH0tRS IH0tRS H0lRS NUCLIDE : 84345-655286553-876084345-655286553-6760 FISSIONGASES KR-85N CURIES : 0.00E-01 0.00E-01 9.32E-02 3.24E-02 :
KR-85 : CURIES : 0.00E-01 0.00E-01 14.21E-02 7.52E-01 :
XE-131M CURIES : 0.00E-01 0.00E-01 1.52E-02 : 1.1?E 00 CLRIES : 0.00E-01 : 0.00E-01 4.78E-01 1.43E-01 :
XE-133M IE-133 : CLRIES : 0.00E-01 : 0.00E-01 4.37E 01 8 3.20E 01 :
XE-135 : CURIES 0.00E-01 0.00E41 1 1.63E 00 6.07E-01 :
AR-41 : CLRIES : 0.00E-01 0.00E-01 0.00E-01 : 1.41E-01 :
TOTAL FOR PERIOD CURIES : 0.00E-01 0.00E-01 4.59E 01 a 3.48E 01 10 DIES PARTICULATE H-3 : CLRIES : 0.00E-01 : 0.00E-01 2.42E-018 8.51E-01 :
W310526HP 25 ,
r, _ - _ _ _ _ _ . _ _ _ _ __-------___ __ _ ____
J i.
L
(.
. TABLE 2A (1 of 1)
REPORT CATEGORY' s SEMIAl#0AL SUPfl4 TION OF ALL RELEASES BY MTER TYPE OF ACTIVITY : ALL LIQUID EFFLLENTS REPORTING PERIOD MTER I 3 AND MTER I 4 UNIT I N TER 3 I M TER 4 *EST. TOTAL:
- HOURS IH0lRS ERROR % .*
TYPE OF EFFLlDfi '84345-655286553-8760 a A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING : : : : :
TRIT M , GASES. ALPHA) IQRIES : 2.22E-01 8 3.71E-01 1.50E 018
- 2. AVERAGE DILUTED CONCENTRATION : :
DURING PERIOD - IUCI/PL 6.71E-09 : 1.42E-00 8
- 3. PERCENT OF APPLICABLE LIMIT % : N/A : N/A B. TRITIUM
- 1. TOTAL RELIAM CURIES : 6.54E 01 : 2.92E 02 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION : : :
DURING PERIOD IUCI/PL 1.98E-06 8 1.12E-05
- 3. PERCENT OF APPLICABLE LIMi! % N/A N/A :
C. DISSOLVED AND ENTRAIED GASES
- 1. TOTAL RELEASE ClRIES : 3.44E-01 : 1.16E 00 1.50E 01 2.AVERAGEDILh3 CONCENTRATION : : : :
DlRING PERIOD IUCI/PL 1.04E-00 4.45E-00
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A D. GROSS ALPHA RADI0 ACTIVITY
- l. TOTAL RELEASE :CLRIES : 2.3E-06 : P.51E-07 1.50E 01 E. MSTE VOL RELEASED (PRE-DILUTION) 80AL : 4.03E 05 4.35E 05 : 1.50E 01:
F. VOLLE OF DILUTION ETER USED 10AL 8.73E 09 6.80E 09 1.50E01:
W31052611P 26 L- - . - - - - - ---____________________ _____ _ _ _ _ _J
. TABLE 2B (1 of 2)
REPORT CATEGORY : SEMIA N AL LIQUID CONTINUOUS A10 BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY : ALL PADIONUCL!tES REPORTING PERIOD : QUARTER # 3 AND GUARTER # 4
- CONTIMJOUS RELEASES : BATCH RELEASES
- LNIT' QUARTER'3 QUARTER 4 QUARTER 3 : QUARTER HOURS : HOURS HOURS H0lRS :
NUCLIDE 14345-6552 86553-8760 14345-6552 16553-8760 :
ALL NUCLIDES H-3 : CtRIES : 0.00E-01 0.00E-01 6.54E 01 : 2.92E 02 :
NA-24 : CURIES : 0.00E-01 0.00E-01 1.71E-04 3.37E-04 :
CR-51 : CURIES : 0.00E-01 0.00E-01 8 4.49E-03 2.39E-02 :
l91- 54 : CURIES : 0.00E-01 : 0.00E-01 2.80E-03 1.80E-03 :
FE-55 : CURIES 0.00E-01 0.00E-01 : 1.10E-02 3.74E-02 :
FE-59 : CURIES ' 0.00E-01 : 0.00E-01 1.70E-03 3.63E-03 :
C0-58 : CLRIES : 0.00E-01 0.00E-01 : 5.45E-02 : 1.77E-01 :
C0-60 : CURIES : 0.00E-01 0.00E-01 1.51E-02 : 9.43E-03 ZN-65 : CtRIES : 0.00E-01 0.00E-01 1.68E-04 0.00E-01 :
SR-92 : CURIES : 0.00E-01 0.00E-01 1 6.25E-05 : 1.16E-04 ZR-95 : CURIES : 0.00E-01 : 0.00E-01 4.70E-03 4.95E-03 ZR-97 .
- CURIES : 0.00E-01 : 0.00E-01 2.73E-04 0.00E-01 :
NB-95 : CURIES : 0.00E-01 0.00E-01 9.80E-03 7.29E-03 :
RU-103 : CURIES : 0.00E-01 0.00E-01 4.23E-04 6.40E-04 :
RlH06 : CURIES 0.00E-01 : 0.00E-01 : 1.93E-03 0.00E-01 :
AG-110M CURIES : 0.00E-01 0.00E-01 6.83E-03 1.22E-03 :
TE-132 : CURIES : 0.00E-01 1 0.00E-01 0.00E-01 1 4.89E-05 :
1-131 : CURIES s 0.00E-01 0.00E-01 1 1.73E-03 2.26E-03 1-133 : CURIES : 0.00E-01 : 0.00E-01 1 2.19E-04 : 7.47E-05 :
CS-134 : CURIES 0.00E-01 0.00E-01 2.67E-02 7.79E-03 :
CS-136 : CLRIES : 0.00E-01 0.00E-018 3.50E-05 : 0.00E-01 :
CS-137- CURIES : 0.00E-01 : 0.00E-01 4.40E-02 1.36E-02 :
BA-139 : CURIES : 0.00E-01 : 0.00E-01 0.0/4-01 1.16E-04 :
LA-140 : CURIES : 0.00E-01 : 0.00E-01 : 1.05E-03 1.39E-03 :
CE-141 : CURIES : 0.00E-01 0.00E-01 : 0:00E-01 8 4.50E-05 :
CE-144 : CURIES : 0.00E-01 0.00E-01 7.07E-04 2.02E-04 :
W-187 : CURIES : 0.00E-01 0.00E-01 5.80E-04 0.00E-01 :
KR-85M : CLRIES : 0.00E-01 0.00E-01 : 2.62E-05 : 1.10E-04 :
W310526HP 27
i
. TABLE 2B (2 of 2) l l
1 REPORT CATEGORY SEMIA W UAL LIQUID CONTINUOUS A @ BATCH PELEASES TOTALS FOR EACH WCLIDE RELEASED.
TYPE OF ACTIVITY : ALL RADIONUCLIDES REPORTING PERIOD : QUARTER f 3 AND QUARTER f 4 l
1 CONT!WOUS RELEASES : BATCH RELEASES I UNIT : QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4
- : HOURS HOURS : HOURS HOURS NJCLIDE 84345-6552 86553-8760 84345-6552 86553-8760 :
All NUCLIDES CONTINUED KR-85 : CURIES 0.00E-01 1 0.00E-01 : 8.55E-04 3.38E-03 :
KR-88 : CURIES 0.00E-01 : 0.00E-01 1 0.00E-01 3.87E-05 :
XE-131M CURIES 0.0CE-01 0.00E-01 4.97E-03 8 3.21E-02 XE-133M : ClRIES : 0.00E-01 0.00E-01 1.88E-03 8 4.36E-03 :
XE-133 : CURIES : 0.00E-01 0.00E-018 3.29E411 1.11E 00 :
XE-135 : CLRIES : 0.00E-01 10.00E-01 7.30E43 8 1.28E-02 :
G ALPM : CURIES 0.00E-01 : 0.00E-01 2.30E-06 8 9.51E-07 :
C0-57 : CURIES : 0.00E-01 1 0.00E-01 1.19E-04 8 2.32E-04 :
SB-124- 1 CURIES : 0.00E-01 : 0.00E-01 : 8.10E-03 1.09E-02:
SN-113 : CURIES 0.00E-01 : 0.00E-01 8 5.25E-03 1.04E-03:
NB-97 : CURIES 0.00E-01 : 0.00E-01 3.85E-04 8 2.44E-04 :
SB-122 : CURIES 0.00E-01 : 0.00E-01 1.31E-04 1.71E-04 SB-125 : CURIES : 0.00E-01 0.00E-01 1.85E-02 6.52E-02 :
TOTAL FOR PERIOD CUP.IES 0.00E-01 1 0.00E-01 : 6.60E 01 2.93E 02 :
W310526HP 28
._____-__-__-________-__a
s t
TABLE 3-(1 of 5)-
t ;
f SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL l l
DURING PERIOD 7-1-88 THRU 12-31'-88 CONTAINER WASTE . TOTAL % 1 VOLUME VOLUME ACTIVITY ERROR WASTE TYPE (Ft3) (M3) (Ci) .(Ci)
I'
- Compacted Dry Active 95 14.62 .121 125% ;
Waste Shipped to Scientific Ecology Group, Inc. for Volume 1 Reduction ,
- Mon Compacted Dry Active 2,560 72.49 .206 .f25% '{
Waste Shipped to l l
Scientific Ecology Group, Inc. for Volume Reduct-ion Resin Waste Management 181.7 5.145 333.68 125%
and Liquid Waste Manage-ment Resin Solidified with Cement .
)
Dewatered Filters Pack- 120.3 3.406 -38.5 125%
aged in a Polyethylene j High Integrity Container Irradiated Components 26.2 .736 3850 -125%
- Waste Volumes Shipped for Volume Reduction Do Not ,
Reflect Final Burial Waste Volumes ]
j W310526KP 29 1 1
)
L: . .o _ __ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ -
h TABLE 3 I'
(2 of 5) -
p-
]
NUCLIDE PERCENT WASTE TYPE NAME ABUNDANCES- CURIES i
Compacted Dry. Os-137 38.69% 4'.'699E-2' Active Waste Co-58 _ 21 44% ~ 2.604E-2 Sentito Scientific .Cs-134- 17.71% 2.151E-2
, Ecology Group for Fe 9.21% 1.119E-2 Volume Reduction I-131 5.22% 6.34E-3 ,.
Co-60 13.47% 4.22E Ni-63 2.05% 2.5E-3 Mn-54 2.01% 2.45E-3
'C-14 .16% 1.99E-4 NUCLIDE PERCENT NAME ABUNDANCE CURIES Non-Compacted Dry Co-58 .55.25% 1.14E-1 Active Waste Cs-137 15'.71% 3.23E-2 Sent To Scientific CS-134 11.1% 2.28E-2 Ecology Group for Fe-55 8.8% 1.813E-2 Volume Reduction Ni-63 4.3% 8.86E-3 Co-60 3.2% 6.59E-3 Mn-54 1.6% 3.29E-3 W310526HP 30
.A. w . .- .
_______________________________________a_______________________-______a
.TABI2 3
~
(3 of 5) 1.
I NUCLIDE- PERCENT
' WASTE TYPE ~ NAME ABUNDANCE- CURIES Resin' Waste Manange- Cs-137 47.346% '1.58E+2 ment-and Liquid Waste Cs-134 -29.366% 9.80E+1' !
~ Management Spent Resin Co-58 8.75% . 2.92E41 2 Solidified With Cement Ni-63 6.443% 2.15E+1 Fe-55 2.985% 9.96E+0 Co-60 2.865%. 9.56E+0' ;
Mn-54 1.966% 6.56E+01 C-14 .172% 5.73E-1 Sr-90 .077% 2.57E-1 H-3 .018%' 6;17E-2 .
< PU-241 .003% 1.11E-2 l Cm-242 .000% 1.85E-4 NUCLIDE PERCENT NAME ABUNDANCE CURIES ,
i Dewatered Filters Fe-55 73.718. 2.84E+1 Packaged in A Co-60 13.835 5.33E+0 ;
l Polyethylene High Ni-63 8.618 3.32E+0
. Integrity Container Mn-54 1.799 6.93E-1 l Co-58 1.607 6.19E-1 Cs-137 .337 1.30E-1 C-14 .046 1.78E-2 PU-241 .021 8.22E-3 i I-129 .019 7.27E-3 j
l l
1 I
W310526HP 31 ;
%w ' .
-TABLE 3 (4 of 5)
NUCLIDE PERCENTAGE:
. WASTE TYPE NAME' ABUNDANCE ' CURIES-Irradiated Co-60 72.483% 2.81E+3
. Components Fe-55 15.012%. . 5.78E+2 Ni-63 5.506% 2.12E+2 Co-58 4.545% 1.75E+2 Mn-54 -1.906% 7.34E+1 Ni-59 .044% 1.69E+0 C-14 . 003% 1.05E-1 l
W320526HP 32 .
I t-____-_--_ _ _ _ _ _ _ _ _ - - . _ _ - - - - - _ _ - - - - .- - - - - - - - _ - - _
- ,w ___,
TABLE 3 o _
'(5 OF 5)
SOLID WASTE DISPOSITION
SUMMARY
l NUMBER OF' MODE OF SHIPMENTS TRANSPORTATION' DESTINATION' 5 -Truck Barnwell, S.C. ,
Oak Ridge.TN. ;
NUMBER TYPE TYPE
~ WASTE OF OF- OF ;
CLASS SHIPMENTS SHIPMENT- CONTAINER MODE DESTINATION A 2 LSA Strong Truck Oak Ridge, Tight TN.
B 1 'LSA Type A Truck Barnwell, S.C.
C 1 LSA Type A Truck Barnwell, I,
S.C.
C. 1 Type B Type B Truck Barnwell, i S.C. ,
l
.i l
l I
i 1
I l
W310526HP- 33 1 J
_-______-___--________-_____________-__-_____________________________,____n_--______________--____--____--._
i ::
e O
N N - -
< o < o d 4 ocooooooCooooooC o d 4 oooooooooooooooo o
^
d
~ d ^
~
a o g b g k eoeooooooeoooooo o k ooeOOooooOoeoOoo o C c p m m
< 7 oooooooooooooooo o 7 coooooooooCococc o c:a .
a S S U g g y -. - - N o m o o N *= *e o Ci o - o N 4 N - - o ** O o o 4 - *= O O O o - o O o -. - - -
0
=e o e o N8 ,
a ?
a ameannemeneo-oeo " ' g E
. a ?
a m*Omoom<num-mn-e
- m s b5
.E b5 m
4 g a 9 = 9 O
- 4m , 6 ? ;62MN"S$3620E"*""2 %
,5 6 *
- SR*"**** #*"S"3 ;- m 4z 5
n -
9 o - m 5
- m h O ? E $ *.
% v- - aa E 2 o
7- "#G """"**""***2 A
- E k
? "
2SNM-ede@NmNmd g
.h a ;
a ss ~ samooomm-m-mo-mo g .s w
se ~ 4.,*u oc om -u-o- oo .g u 9 e u 9 e o W s4 W 5. :
Z Q O m* m*
l ocococooOooooooo O - o--ooooooNooooo- e
, l ,
yes o e
s o g g : ococcomeCoCocoo- -
, g ococoooooooooooo o ,
o s 2 0 s
5 2 :
9 a 8 g B E a 8 ooooooooooo Com om a 6 oooooooooooooooo o s
- a
- : a a < B
- m E E
- o >- o OOOOoooooooOoooC o 5 OooOooOoOooooooo o ,b W n sa e n sa
=
y 5 g 5 W s . , a W s s 9e =IW"w,W,.nR$2lM$ w . =
Sc =IW5w . .
W,wwR$2lE!
w a =
=
~
se* W m se" s
% o 5
- 5, o B 1
N to o
e N
3
g . .
r p-1 l
I*
l l
o f
- EERN*"SEADACENNA% o - %%CR$2EE$$8MEEf ~R o < o b d oooooooooooooooo o d i acoooooooooooooo o d
d R 9
" R 9 aooooooooooooooo o n. oooooooooooooooo o n -
<- " ~
.H a C. oooooooooooooooo o C. ~~ooooooeooooooo m
.A &
e e
sI c -
s ---~oo~~~oooo-o. g I s
~g.omo-~g.--o-.g ~
a m - - - -
o a e d o -
y* . . s ~ o - m e- g n - o - ~ m e g E j ggggg ;gg.omm.gg h'
W wa - wa m e n =
o a 9 = 9 A
- ^4z , 6 ? 022:*"*SONC**WWC C ,5 6 ? $-- 23 S RM 23 C S G RiE R R 2 E y E E
< b. - . . - o bexH =I gg
~.g.~o--mm.mm,-.s e g gg gegg-oggggggungga
~ = o ~
m - 8 - w h a .
H u 9 e
~ - m-oom--~~m.~ 4 g -
u 9 e
~ egg ~~a.ecogge~.~g -
a g 5 ; g g ;
z
@ m e 6 g m~~-oooooo-~-o~- e, g g ...~--,~ .,-....s e,
@3 e a,
e
- g 7 oooooooooooo-oo-~ , g ; m-moooo-oom--c.- e, o
9 5 2 0 5 2 :
g g B m B e 5 c. oooooooooooooooo o .
5 5 C. oooooo-~-ooooooo ,, .
5 B
~
u E a
=
G S. G S.
o oooooooooooooooo o 5 o
o ooooooooooo~oo m 5 4 4 U U _$,
5
w a . . . .
9~ =EW5. WN a .RS23 , ,R$ s= =
5 9: =EW..
.g . .
WN..a RS2 = lE! i s
=
2 5S" i 58" 5
, o 5
- 5, o B
b
- 'c c
N LA O
O 3
w- - _ _ - _ _ _ _ _ _ _ _ _ _ . - _ _ _ - _- ._ - _ _ _ - _ _ _ _ - - _ _ _ .__ _ - _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ - - _ _ _ - - _ - _ _ - _ _ _ - _ _ _ _ _ - _ _ _
.3 ,
u.>
1.
s, l.
'l _
$$- ---~
z# E E8bD---EI 858E- j ,
8 y 'ENIIEEE888DIEEE8 , -----
E o 5 e d g ^ooooooooooooooooo d g oooooooo.sooooo;oo o.
- i. A -
A
-j a -
8 aooooooooooooooo l'e at 5
e o ooooooooooooooooo.
d d
'Q. a _.;
C ooooooooooooooooo O
- oooooanooooooooo o j' .d $
v g .
g .
0 weeooooomNoeooewe' ? oooooooooooooooo 8e .: -
e o
8o a:
-u o
o a
O e .
.y 5 . a.
'G '~menkmme.eoooo~.g n
., a -
y' oooeeoooooeooooo
~
k.I
-@ _ ga
. > gW
[L k . o o .
4^ *** ""*"*"***""* $-
42.
- -e
$$$$$$$$ES@S**
- -- REC. -3 NWk E $
1 t; o ao -
ae ses N l ;r. . e essRmmessessmemog l ae *~==~~exe**e-a 2s-8" 5 S ~
O'5 A E E*? 5 I*
e gmms**ms3RSMR22c cu N*:"*aNR*RAmea** S-u m u
.!. -* N-r !. ?9 .
~
- ' E E
$ 9 9 o
8:
- sas*~~;stzzzzsa~em
~ ,
I :
~~~~~~~mma$Re=** z- ~-
w s= w e=
E o E o gj g e ~ . - - ~ ~ m m t e s . ~ ., ~ o s ,. g 9 .~~m.,-,~Cntge.o. g a=8 9 a =
8 9 s i i B' o-o.:mo-~.--~mo~- g 3 5 m e m o o ~ ~ m ., m o g ., - ~ , g3
, o s. n w 3 E 2 R. 3 S. g g ,
~--oooo-~--~-o~o g ! g ,
-oo--o--,m~ .,~-- g ,
N > ?
W Q a W E s
g 5 g 5
E s
8 o .IwL Ew!adat lal a !Ia_ s- s' Iw! Ew!alal=lal v !
sm - m '.g -
%_ E S R E E E:
G N
LA C.
O 3
n.. ]
$ N " * * " * $ Di R G R E S E A Rg o a N
- 6 e oooooooooooooooo o d i
~
o
$ e t 7 oooooooooooooooo o C
H m
". oooooooooooooooo o f
a .g v S5 .
M o e - - oooooooooooooooo o 3
0 N
crl O vo *. .
Ca.1 o N ocoooooooooooooo o. t b .- .a L
A hEo 4,0 ,3 j d oooeonoeoooooooo n 4 las dw o 5 A I SQ O u o o
$4mv-E E
y6
-o--oomoeooomooo g W
a 5 Ke~ e---oomggoogs-m. e a
8
=
- s -
Z o d
o 8 i =~a~=-aczmaca *~ "* S ~ Ems
@ o -
m p .,
$ g i m--~~oes~gsgosm= g "
, ==
o 5 2* 33 9 - d SS g 2 33 5, mu -m-*mmeggsom g 3 g a n . ,,
y --
f m mumoomouu-ooemon g 5
.l g"
3 J o 8
- i!
E s
s8" ,jir! Ew!.!abial v vs 5, B B
- .B.
L C
N Ln O
i O"'
3 L.- _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _
- TABLE 5 (1 of 2) ,
DOSE CALCULATION RESULTS FOR 1988 (DOSES DUE TO GASEOUS RADIOACTIVE EFFLUENTS)
- QUARTER 1 0F 1980 ** H QUARTER 2 0F 1980 M DOSE FROM RADIOI0 DIES. PARTICULATE. Am TRITILM DOSE FROM RAD 1010 DIES. PARTICULATE, AND TRITIUM
- AT CONTROLLING LOCATION
- AT CONTROLLING LOCATION:
TOTAL DOSE (MEM) FOR B0E : 2.5282E-04 TOTAL DOSE (MEM) FOR BOE 2.8441E-03 TOTAL DOSE (MEM) FOR LIVER : 3.1440E-02 TOTAL DOSE (MEM) FOR LIVER : 1.5907EH)2 TOTAL DDSE (MEM) FOR TOTAL BODY : 3.1269E-02 TOTAL DOSE (MEM) FOR TOTAL BODY : 1.4367E-02 TOTAL DOSE ( MEM) FOR THYROID : 1.2073E-01 TOTAL DOSE OftiM) FOR THYROID 8.1486E-01 TOTAL DOSE ( MEM) FOR KIDNEY : 3.1471E-02 TOTAL DOSE (MEM) FOR XIDEY : 1.6170E-02 TOTAL DOSE ( M EM) FOR LlNG : 3.1150E-02 TOTAL DOSE ( MEM) FOR LlMG : 1.3356E-02 TOTAL DOSE (MEM) FOR GI-LLI : 3.fl50E-02 TOTAL DOSE (MEM) FOR 01-LLI 1.3377E-02 NOBLE GAS DOSE AT SITE BOUNDARY: N0BLE GAS DOSE AT SITE BOU M ARY: 1 TOTAL BODY DOSE TOTAL ( MEM) : 3.0393E-01 TOTAL BODY DOSE TOTAL (MEM) : 2.1653E41 !
SKIN DOSE TOTAL (MEM) : 7.1230E41 SKIN DOSE TOTAL ( MEM) 5.1631E-01 !
NOBLE GAS AIRDOSE AT SITE BOUNDARY: N0BLE GAS AIRDOSE AT SITE B0lMDARY:
TOTAL GAN AIRDOSE (MAD) : 3.5687E-01 TOTAL GA N AIRDOSE ( EAD) : 2.5636E-01 TOTAL IfTA AIRDOSE ( S AD) : 9.5016E-01 TOTAL BETA AIRDOSE (MAD) : 7.2319E-01 i
1 ** GUARTER 3 0F 1988 w ** QUARTER 4 0F 1900 *< f DOSE FROM RAD 1010 DIES, PARTICULATE, AND TRITIUM DOSE FROM RADIOI0 DIES, PARTICtLATES. Am TRITILM AT CONTROLLING LOCATION:
AT CONTROLLING LOCATION:
- 2.1890E-04 TOTAL DOSE ( M EM) FOR B0NE : 2.0946E-04 TOTAL DOSE (MREM) FOR B0E
- 9.6073E-02 TOTAL DOSE ( MEM) FOR LIVER 3.7724E42 TOTAL DOSE (MEM) FOR LIVER
- 9.6020E-02 TOTAL DOSE (MEM) FOR TOTAL BODY 3.7635E-02 TOTAL DOSE (MEM) FOR TOTAL BODY 1.0169E41 TOTAL 00SE ( MEM) FOR THYROID : 8.4037E-02' TOTAL DOSE (MEM) FOR THYROID
- 9.6046E-02 TOTAL DOSE (MEM) FOR KIDEY : 3.7739E-02 TOTAL DOSE (MEM) FOR KIDEY
- 9.6034E-02 TOTAL DOSE (MEM) FOR LUNG 3.7578E42 TOTAL DOSE (MEM) FOR LUNG
- 9.6021E-02 TOTAL DOSE (MEM) FOR GI-LLI 3.7577E42 TOTAL DOSE ( MEM) FOR GI-LLI NOBLE GAS DOSE AT SITE BOLMDARY: NOBLE GAS DOSE AT SITE BOLN)ARY:
TOTAL BODY DOSE TOTAL (MEM) 3.6609E42 TOTAL BODY DOSE TOTAL (MEM) : 8.5737E42 SKIN DOSE TOTAL ( M EM) : 8.4276E-02 SKIN DOSE TOTAL (MEM) : 2.0064F-01 N0BLE GAS AIRDOSE AT SITE BOUNDARY: NOBLE GAS AIRDOSE AT SITE BOLN)ARY:
- 9.2243E-02 TOTAL BETA AIRDOSE ( SAD) 2.6509E-01 TOTAL BETA AIRDOSE ( M AD)
. H TOTALS FOR 1990 H i DOSE FROM RAD 1010 DIES. PARTICULATE, AND TRITIUM 1
AT CONTROLLING LOCATION:
TOTAL DOSE (MEM) FOR BOE
- 3.5253E-03 1.8114E-01 ;
TOTAL DOSE ( M EM) FOR LIVER '
TOTAL DOSE ( M EM) FOR TOTAL BODY
- 1.7930E-01 TOTAL DOSE (MEM) FOR THYROID
- 1.1213E 00 TOTAL DDSE (MEM) FOR KIDEY
- 1.8143E-01 TOTAL DOSE (MEM) FOR LUNG
- 1.7812E-01 TOTAL DOSE (MREM) FOR 01-LLI
- 1.7813E-01 NOBLE GAS DOSE AT SITE BOU N RY:
TOTAL BODY DOSE TOTAL (MEM)
- 6.4200E-01 SKIN DOSE TOTAL (MEM)
- 1.5135E 00 N0BLE GAS AIRDOSE AT SITE BOUNDARY:
TOTAL GA N AIRDOSE ( M D)
- 7.5521E-01 TOTAL BETA AIRDOSE (MAD)
- 2.0395E 00 W310526HP 38 j
, TABLE 5 (2 of 2)-
DOSE CALCULATION RESULTS FOR 1988 k (DOSES DUE TO LIQUID RADI0 ACTIVE EFFLUENTS)
. ** QUARTER 1 0F 1988 **' !
TOTAL DOSE USEM) FOR B0E 6.1787E-02 i TOTE DOSE OREM) FOR LIVER 1.0790E-01 TOTAL DOSE OREM) FOR TOTAL BODY 7.9570E-02
, TOTE DOSE OREM) FOR THYROID 3.9581E-03 TOTAL DOSE OREM) FOR KIDEY : 3.5843E-02 TOTAL DOSE OREM) FOR LUND - I'l.2055E-02 TOTAL DOSE OREM) FOR GI-LLI : 4.5368E-03
- QUARTER '2 0F 1988 **
TOTAL DOSE OREM) FOR BOE- 1 1.3579E-01 TOTAL DOSE OREM) FOR LIVER 2.3146E-01 TOTAL DOSE DREM) FOR TOTAL BODY 8 1.6922E-01 TOTAL DOSE umEM) FOR THYROID 5.3455E-02 TOTAL DOSE DEEM) FOR KIDEY 7.7155E-02 ,
TOTAL DOSE OREM) FOR L(MG 2.5611E-02
(
TOTAL DOSE DEEM) FOR G H LI 1.3807E-01
{
- QUARTER 3 0F 1998 **
TOTAL DOSE OREM) FOR BOE 1.0732E-01 TOTAL DOSE OREM) FOR LIVER 1.8184E-01 TOTAL DOSE OREM) FOR TOTAL BODY 1.3249E-01 TOTAL DOSE OREM) FOR THYROID 6.1763E-04 TOTAL DOSE OREM) FOR KIDEY 6.0483E-02 TOTAL DOSE OREM) FOR L(MG 2.0137E-02 TOTAL DOSE OREM) FOR GI-LLI 4 6.9247E-02
- QUARTER 4 0F 1988 **
TOTAL DOSE USEM) FOR BOE : 4.4862E-02 i TOTAL DOSE OREM) FOR LIVER 7.6057E-02 TOTAL DOSE OREM) FOR TOTAL BODY 5.5506E-02 TOTAL DOSE OREM) FOR THYROID 1.6974E-03 TOTAL DOSE OREM) FOR KIDEY 2.5520E-02 TOTAL DOSE OREM) FOR LUNO 8.8767E-03
. TOTAL DOSE OREM) FOR O!-LLI : 8.3963E42
- TOTALS FOR 1988 ** !
TOTAL DOSE OREM) FOR B0E 8 3.4976E-01 TOTAL DOSE umEM) FOR LIVER 5.9726E-01 TOTAL DOSE OREM) FOR TOTAL BODY 4.3678E-01 TOTAL DOSE OREM) FOR THYROID 5.9720E-02 TOTAL DOSE OREM) FOR KIDEY I 1.9901E-01 TOTAL DOSE (MREM) FOR LUNG 6.6679E-02 TOTAL DOSE OmEM) FOR GI-LLI : 2.9582E-01 W31052611P 39 t
i TABLE 6 (1 of 1)
DOSE CALCULATIONS AND ACTIVITY CALCULATIONS FOR THE UNPLANNED RELEASE ON NOVEMBER 30, 1988 CALCULATED DOSES % OF '
-TS REFERENCE TS LIMIT AND DOSE RATES TS LIMIT 3.11.2.1(a)* 500 mrem /yr 216 mrem /yr 43. 3*A (Total Body) 3.'11.2.1 (a)* 3000 mrem /yr 384' mrem /yr 12.8%
(Skin) 3.11.2.2(a)** 5 mrad gamma /qtr 8.4E-3 mrad 0.17%
3.11.2.2(a)** 10 mrad beta /qtr 8.8E-3 mrad 0.088%
3.11.2.2(b)** 10 mrad gamma /yr 8.4E-3 mrad 0.085%
3.11.2.2(b)** 20 mrad beta /yr 8.8E-3 mrad 0.044%-
- Maximum instantaneous dose rates
- Air dose limits The total activity released was calculated using grab sample and radiation monitoring data collected during the event and is summarized below.
TOTAL ACTIVITY ISOTOPE RELEASED (Ci)
Ar 41 0.50 Kr-85M 0.27 Kr-88 0.52 Xe-133 12.0 Xe-135 3.68 TOTAL 17.00 W310526HP 40
_. -_-________-_____-________E
( -:
ATTACHMENT 1 i
AFFECTED PAGES FOR CHANGES 1
TO THE OFFSITE !
1 DOSE CALCULATION MANUAL, HP-1-230, I REVISION 6 l
I I
i l
.I I
i I
i l
l l
i iI i
l W310526HP i
l
_._____ _ ___________________ __ _ _ ____ ___j
p, e ..
Jurv:111anca Prac dura .
HP-1-230
,'. . Offsite Dose Calculation Manual j Revision 6
/
10.18 Annual Average Dispersion Parameters at or Beyond the Unrestricted A:aa Bount' ry (Table 11) (2 pages) 10.19 Annual Average Deposition Parameters for Ared.s at or Beyond the Unrestricted Area Boundary (Table 12) (2 pages) .
10.20 ODCM Technical Specifications Cross-Reference (Table 13)
(1 page)
LIST OF EFFECTIVE PAGES Title Revision 6 1-103 Revision 6 .
8)NI &j$,62;W SS i j $ l ct.
e 3
! "L + ..SurvSillcaca Prec ura HP-1-230 "
Offsito Dosa Calculctica Manual Revision 6 q , (500 ares /yr.)(RF)(SF) (24a) ,
- ~
(X/Q),(le6pci/pci)(h-88)
Then, based on maximum flow rate, the monitor setpoint SN in pCi/cc can be calculated:
e r- (26)
SN =
,Bax me where:
F ,,.= maximum effluent flow rate (cc/sec) ,
NOTE To determine whether total body or skin dose is more
~
limiting for Er-88, equations (24) and (25) are solved _
for..Q[,.88'-~8I"C'
-
- l' b -88 is required to reach the total body limit of 500 area /yr, the total body dose is more limiting.
8.14- PROJECTING DOSE FOR RADIOACTIVE GASEOUS EFFLUENTS Technical Specification 3.11.2.4 requires that appropriate subsystems of the Gaseous Radwaste Treatment System be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond'the SITE BOUNDARY would exceed, in a 31-day period, either:
~,W 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 . area to any organ of a MEMBER OF THE PUBLIC.
41
~-
ANNUAL AVERAGE DISPERSION AND DEPOSITIO PARAMETERS FOR AREAS AT OR BETOND THE UNRESTRICTED BOUNDARY (TABLE 1)
LPSL (CTHFORD $1 tee WINS JAN - EC 1986 ET 84T6 - IW 1/29/87 Roue LEVEL RELEA$te 0 M COMECTD UBING STAGARD GPD TERRAIN FACTORS WECIFIC POINTS OF INTEREST ELEASE TYM OF MRECTION DI5fANCE I/ ' I '0 1/8 3/8 2 LOCATim FROM SITE (NILES) ( ETER$) (SEC/CU . ETB ) (S 8.E TER) ( E C/CUS. E TER) (P D N.ET B )
g' Ag 2 gag f 8. g f 8 IILK CONS lef 1.10 1770. 1 4 -M 1. E-06 1 4E-06 6.7E-09 8 IILK COWS W 4.40 7081. 10 47 9.E-08 7.M-00 2.M-10 8 il 8047 E 3.30 5311. 4.4 -07 4. -07 3 4E-07 5.N-10
$ tl AILE GARBD N 1.10 1770. 5446 5. 4 4.7E-06 1.E48 s t AILE 8AREN 10E 1.30 2092. 314 3. -
3.E46 6.9E-09 8 LIE TAILE SAR9 0 E 1.00 1609. 37 5. E-te 5.0E-06 1 4E-08 8 (IETAR.E GAREN EIE 0.90 1448. 74 7. E-06 6.M-06 1.N-08 *
~~ o .
8 8
LIETAILE GARBD LIETABLE GAREN ESE E 3.20 2.30 5149.
3701.
4.6 7 7.1 7
- 4. I-07 7.E47 3.E47 6.1E47 6.E-10 1.0E-09 y
8 LIETAILE GARIEN SE 2.30 3701. 6. 47 6. E47 5.E47 . 9.E-10 -
L GARBD $ 0.90 1448. 5 46 5. F06 4.E-06 2.E-08 I L 8ARDEN SIW 0.M 1448. .9 -96 4. E-06 4.54 20E-08 8 LIE TAILE GARDEN SW 0.90 1448. .7 -06 4. 4. -96 2.1 -08 y l 4 g- gj t
IBAf"i h.:'I' 1448. i#l:
8 i:t3 1 7 -06 i:
- 1.
1:
- 1. -06
- 1:-0,
- 6. -09 i H E if 2l E A 1:# 12: M3 1: 2 BR3 did I
I lifEEli fIIIEEES
.i IE I:18 0.90 IE 1:lla 7.3 -06 1:la
- 7. 4 0:52 6.4E-06 bila 1 1.8E48 E 319ENCES EIE 6.90 1 . 74 4 7. -06 6.M-46 1.M-08 E . . . . 4.
I a tenevn E 3.90 6276. 2.5 -07 2. -07 19E47 2.M-10 '
. E ' 13 TEES W 1.30 2092. 9.A 47 9. -07 8. 5 -07 3. 5 -09 8 A IENCES IBAf . 0 90 1448. 1.74 1. -06 1 5-06 6.4E49 --
8 A:IENCES Inf 0.90 1448. 2 6 -06 2. -W 2.5-06 1 1E-08 8 R: IERETE ISAf 2. 3219. 7.8 47 7. 47 6.4E-07 2 5 -09 8 8 TE NU GARY ll 0. 1287. 1 1 -45 1. -45 1 0E-05 3.1E-08 8 8 TE IIMIDARY let 60 9M. 1.0 -05 1. -05 1. 45 4.1E-08 8 8TElous4RY lE .60 W. 1 6 -05 1. -05 1. 4.E-08 8 0.60 9M. . 7 -05 EIE -05 8g10lBSARY . 1. -05 3.9E-48 i !TE Ed, E
hN 64.
W.
h 8 8 0 60 1 1 -05 1. 45 h 2 2E-08 8 8 Y SIE 4.80 . 4446 6. 46 5. 2148 I8 [L El SW l.:"N
. }:'$
. 07 }.: 473 }.:3 7 i: *
- 8. -10 8 TE 80L8SARY 1.50 2414. 1.3 46 1 46 1 1E-06 5.9E-09 8 $ TE 80lBSARY 1.00 1609. 1.E46 1. -06 1. 5 -06 6.7E49 ,
4 5 TE Y 0.80 1287. 2.2 -06 2. 46 2.E-06 8.9E49 8 8TE Y W 0.80 1287. 3.4 -06 3. 46 3.0E-06 1.5-08 8 8 TE BRISSY G81 0 90 1448. 4.4 -06 4. 46 3.9E46 1.M-08 EN Am WIL9115 !~~
ELEAIE lEIBIT ( )_._4.00 EP. BDS E!sti (lETER5) 10.0 SIAIETH ( ) 0.00 W IL N W IEl eff (lETBS) 61.0 EKIT RLaCITT ( ) .-0.00 SLIBellIN.tal.EC.AEA (N.lETDS) 2M8.0
~
i ALL Wolail LEVEL ,
HP-1-230 Revision 6 Attachment 10.1 (1 of 1) 46
l
~
AT o m FOR (TABLE 1) i 1
, l
!1 3 CATE27Eco s1TE. Usr3c JameA27 - Sectusta 1937 us7 3AEA - ass 2/13/88 l
% mi*
sta LEVEL att. EASE. ON .
25.TED celes stassate Orts TEstAss rk d, 33 rte retcTs Sr 2WTEREST ,
"a Es3 TYPE or 91stcTios 9tsTAscs I/q E/q I/q s/q
) 10cAfros raen s TE (witEs) (nETEas) (sEc/Cas.ntrEE)
Wo DEcAT (SEC/ css.nETEs) (sEc/ css.nITEE) (ret so.wtT!a) -l l 2.269 Oaf SECAT s.000 SAT SEcAT j ee9EftsTIs oesteLETEn otetETEo 9 ctLE cows rW 1.10 1779. 2.tt-06 2.15-06 1.85-06 7.6E-99
). c1LE C0es se 4.49 70st, s.3E-of 1.3E-07 9.9E-es 2.8t-te
} MILE C047 E 3.30 3311. 6.35-07 6.1E-97 4.9E-97 6.4E-to
) TESETABLE CAEBEN W l.10 1770. 5.1E-06 5.1E-06 4.5E-96 1.15 03
) TECETASLE CARDEN WWE 1.30 2092. 3.75-64 3.73-96 3. 2E-46 6.1E-09
) TE!ETASLE CARDEW KE 1.99 1699. 6.95-04 6.98-06 6.15-06 1.25-98 l TECETABLE CARDEN EVE 9.94 1448. 1.0E-95 9.9E-96 8.8E-06 1.7E 93 l- VECETABLE CARDEN I 3.20 St49. 6.7E-97 6.4E-e7 3.2E-07 6.8E-10 l' VE2ETABLE S&tDEN ESE 1.30 3701. 8.15-87 7.9E-07 6.6E-07 1.lt-09 i
TECETASLE CAESEE SE 2.30 3791. 7.55-07 7.3E-07 6.15-07 t.3E-09 TECETASLE CARDEK 5 0.99 1440, 5.2E-04 5.25-06 4.6E-06 2.25-98 l TEGETABLE CARDEN 88W 0.90 1448. 4.1E-06 4.0E-06 3.68-04 1.55-08
~TE2ETABLE C4E9EN SV E.90 1648. 4.3E-06 4.38-06 3.8E-06 2.!E-08 J TEGETASLE CAR 953 WSW e.90 1444. 3.68-06 3.65-06 3.1E-06 2.15-08 TETETASLE CAISEN N 1.19 1779. t.6E-06 f.65-06 1.4E-06 3.95-09 TECETABLE CARDEN WWW e.90 1448. 2.75-64 2.7E-06 2.4E-46 . 1.15-08 VECETABLE CARDEN - 59 9.90 1448. 3.3E-96 3.2E-94 2.9E-04 1.3E-08 2.56 TEGETABLE CARDEN RESIEENCES ENE 3 0.40 4823.
8287.
4.1E-67 1.fE-85 4.0E-97 1.1E-05 1.3E-07 9.55-06 1.2E-09 2.6E-04 k RESIDENCES 998 0.80 1187 1.15-45 1.1E-45 1.95-45 2.15-98' RESIDESCES NE 0.96 1440. S.9E-84 8.8E-06 7.8E-06 1.6E-98 IIst9Escts ENE 0.99 1440. 1.0E-95 9.9E-96 S.st-04 1.75-98 8tts18EWCES E 2.20 3541. 1.3E-06 1.3E-96 1.lt-96 1.6E-09 Es10EscEs Est 3.20 5150, 4.58-87 4.3E-97 3.5E-97 5.2E-10
.ISISESCEs SE 3.99 6276. 2.9E-07 2.et-07 2.25-47 3.SE-19 RESIDESCES W 1.94 1699. 2.9E-e4 2.8E-06 1.85-06 7.68-99 EESIDEWCES WWW _9.90 1464. 2.7E-96 2.7E-94 2.4E-04 1.85-08 CE510ENCES WW 9.90 1448. 3.35-06 3.2E-96 2.9E-96 1.3E46 RES!9EBCES SWW 3.00 4828. 2.9E-87 2.85-97 2.35-07 7.9E-10 SITE 5093341Y N G.80 1287. 1.85-45 1.85-05 9.55-06 2.6E-08 SITE 899EDARY WWE 0.64 966. 2.9E-05 t 9E-05 t.8E-05 3.65-00 SITE SOUN9 ART BE 0.66 966. I.9E-95 2.0E-95 1.OE-93 3.6E-08
$1TE SOUNDARY EWE 4.60 966. 2. 3E -0 5 2.3E-95 2.95-E5 3.9E-04 Q s1TE 808N5417 E e.80 8287, 1.28-65 1.2E-45 1.15-05 2.15-98 SITE SO95DARY ESE 0.60 964. g.45-45 1.4E-e5 1.3E-05 2.75-98 sETE 990NDARE SE 0.64 966. 1.35-05 8.3E-05 l.2E-05 3.15-90 SITE togeDARY SSE 9.40 1287. 7.25-96 7.2E-96 6.48-96 2.3E-98 SITE B0059A27 s 1.60 2575. 1.45-86 1.4E-06 1.25-96 3.tt-49 SITE 599E945Y ssW 3.10 4909. 3.8E-47 2.95-07 2.45-07 7.15-19 SETE BOWNBART SW 3.49 5472. 2.6E*e7 2.65-07 2.08-97 8.25-19 SITE meted &RY usw t.54 24t4 t.1E-06 1.1E-06 9.6E-07 5.78-99 SITE 80UEDatY W t.00 1699. 2.9E-06 2.0E-96 1.8E-96 7.68-09 5ITE focEDARY F3U 9.80 1287. 3.35-06 3.5E-96 3.15-06 1.5E-04 llTE SODEo&EY WW 9.49 3287. 4.35-96 4.3E-06 3.8E-96 1. 7 E-08
$ITE S9GEDatY WWW S.90 1440. 3.7E-06 3.65-06 3.25-06 1.55-08 ABS SWILDISC FAEANETERSs OEast cE1 Cat (mETEss) e.99 str. W129 aElesT (wETEas 19.9
>1 tester (wETEas 0.9e as1Letse mEtcut (xtTEEst 6t.0 017 TELEctTY (x87Eas) 9.9e Stee.uts. css.ste. AREA (30.NETE28) 2468.0 53AT E5158195 BATE (CAL /SEC) 0.0 OCW70 LEVEL RELE4SES.
HP-1-230 Revision 6 Attachment 10.1 (1 of 1) j 46A
=' TABLE 3 SAMPLE LOCATION TABLE-LOCATION- LOCATION MILES FROM SECTOR NUMBER DESCRIPTION -PLANT DIRECTION DIRECT RADIATION (TLD)
A-2 (Eastbank)~On fence enclosure surrounding 1.1 N water tower west of Little Gypsy opposite Etinenne St. Access from River Road (LA 628). The TLD's are located on the (S) fence opposite the entrance gate to the water tower.
B-1 (Eastbank) On fence enclosing the . 0.8 NNE transmission tower 0.3 miles west (up-river) from Little Gypsy. Access from River Road
-(LA 628). TLD's are located at SW corner of fence enclosure.
(Eastbank) On fence enclosing the Little
~
C 0.8 NE '
Gypsy Cooling Water Intake. Access is i from River Road (LA 628) across from Little Gypsy Power Station entrance. -
TLD's are on the south side (inside) of
'the Cooling Water Intake fence enclosure, directly opposite the entrance gate.
~
~
D (Eastbank-) Located e6-USGS-W64eess-Peet- 1.1 ENE h .., T a approximately 0.3 miles g east of Little Gypsy Power Station. p Access from River Road (LA 628) near the -
west end of the Bonne Carre Spillway. e-TLD's are on the i :t c' +' *=~ayp dda E-1 "J $ le U h ll sM " d W ') g .
(Westbank) Located on utility pole 0.2 E j
along River Road (LA 18) approximately 0.3 miles east of Waterford 3 plant entrance. Access from LA 18. TLD's are
. on the third utility pole east of the construction entrance road.
F (Westbank)-Located on fence enclosure 1.1 ESE surrounding the LP&L substation on LA ,
3142. Access from LA 3142 approximately l 0.2 miles south of LA 18. TLD's are on the southeast corner of the fence i enclosure.
HP-1-230 Revision 6 Attachment 10.3 (1 of 7) 49
TABM 3 (Continued)
W .ATION LOCATION MILES FR0ici RfBER SECTOR
_ DESCRIPTION PLANT DIRECTION F-4 (Westbank) Located on utility pole behind 3.5 ESE' blonde brick house on Aquarius St. in Hahnville. Access from River Road (LA 18) and turn onto Oak St. Follow Oak St. to Hickory St., turn right on Hickory St.
.and follow to Aquarius St. and turn left.
Blonde brick house is second house on right (west) side of Aquarius St. heading south.
]
G-4 (Westbank) Located on' railroad sign 3.2 SE northwest side of LA 3160/ railroad track c intersection. Access from either LA 3127 % !
or River Road (LA 18) onto LA 3160. ~D H-6 (Westbank) Located on a 5.7 SSE sign on the southw[rt side of the second canal bridge east of LA.3160 along LA t 3127. ~ .- y P-6 (Westbank) Located on utility pole at 5.5 WNW southwest corner of LA 640/ railroad
- track intersection. Utility pole is .
just west of LA 640 and east of radio transmission tower.
Q (Westbank-) Located on fence post 5.0 NW surrounding (green) river marker on levee just east of Edgard. Fence post is located along River Road (LA
- 18) across from the Webre's house.
R-6 (Eastbank) Located on fence enclosing 5.3 NNW LP&L Laydown Yard on IA 3223 in La Place.
Access from Hwy 61 onto Elm St. (LA 3223),
take Elm St. to the northeast corner of LA 3223/ railroad intersection. TLD's are located on the southeast corner of fence enclosure.
F-9 (Eastbank) Located on entrance gate 8.2 ESE to Destrehan Substation. Access from River Road (LA 48), approximate 0.3 miles east of Luling-Destrahan Ferry, onto Destrehan Road (west of Bunge Corp. Grain Elevator), and proceed to substation gate.
HP-1-230 Revisica 6 Attachment 10.3 (4 of 7) 52
l~ r.
,. TABLE 3 (Continued)
'OCATION
. LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION Fish q FH-1* Upstream of the plant intake structure.
FH-2 Downstream of the plant intake structure.
1 Waterborne GWJ-1 (Westbank) Located at 40 Arpent Canal 0.3 south of the plant. Access from LA %
3127 through LP&L Gate 8. The canal is .
northwest of.the shell access road / railroad track inte.-section'.
DWG-2 (Westbank). Located at the Union Carbide 2.0 EbE SWG-2 drinking water canal. Access from LA 3142 through Gate 28.
.SHWE-3 (Westbank) Located at the Foot Ferry 3.0 E Landing off of LA 18 in Taft.
SHWJ-1 (Westbank) Located at 40 arpent canal 1.0 S south of plant. Access thru LP&L gate 8 off of LA 3127).
DWE-5 (Eastbank).' Located at the St. Charles 4.5 E SWE Parish Waterworks off of River Road '
8~
(LA 48) near New Sarpy. -
DWP-7* (Westbank) Located at the St. John Parish 6.5 W NW SWP-7 Waterworks off of LA 18 in Edgard, cy[$
..:c-y
- DENOTES CONTROL LOCATIONS
/
,. n' l
HP-1-230 Revision 6 Attachment 10.3 (7 of 7) 55
r;'- -
t(
.,in c
I,'
,t, l*
1
'x
. i, o
~ ATTACHMENT 2 CORRECTIONS TO TIE SEMIANNUAL RADI0 ACTIVE EFFLUENT FILEASE REPORT FOR TIE PERIOD OF JANUARY 1 TO JUNE 30, 1988 W310526HP
__ ___. _ _ _ _ _ _ _ _ _ _ . - - - I
o r
~
s I-TABLE 3 fv' (3 of 4) i Estimates of Major Nuclides By Waste Type NUCLIDE PERCENT CURIES NAME ABUNDANCE Liquid Waste Co-58 44.772% 1.04E+01 Management Cs-137 24.087% 5.59E+00 System Spent Cs-134 13.003% 3.02E+00 Resin Solidified Fe-55 8.306% 1.93E+00 With Cement Co-60 3.135% 7.28E-01 I-131 2.550% 5.92E-01 Ni-63 1.860% 4.32E-01 Mn-54 1.666% 3.87E-01 H-3 .474% 1.10E-01 C-14 .148% 3.43E-02 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 Pu-241 .000% 0.00E+00 Cm-242 .000% 0.00E+00 NUCLIDE PERCENT CURIES NAME ABUNDANCE Resin Waste Management Cs-13/ 47.281% 8.29E+01
& Liquid Waste Cs-134 24.753% 4.34E+01 Management Spent Resin Co-58 11.578% 2.03E+01 Solidified with Cement Ni-63 6.160% 1.08E+01 Co-60 3.867% 6.78E+00 Mn-54 3.222% 5.65E+00 Fe-55 3.091% 5.42E+00 C-14 .029% 5.08E-02 H-3 .020% 3.47E-02 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 Pu-241 .000% 0.00E+00 Cm-242 .000% 0.00E+00 W310526HP 37
1 I ,
Raf;r: 10CFR50.36a LOUISIANA POWER & L1GHT / 317BARONNESTREET
- P. O. BOX 60340 NEW ORLEANS, LOUISIANA 70160 * (504)595-3100 00?$EsNU March 1, 1989 W3P89-0044 g A4.05 i
QA U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Semlannual Radioactive Effluent Release Report Enclosed is the subject report on effluent releases which covers the period of July 1 through December 31, 1988. This report is submitted per Section 6.9.1.8 in the Waterford 3 Technical Specifications (NUREG-lll7) of Appendix A to Facility Operating License No. NPF-38 and 10CFR50.36a(a)(2),
pursuant to 10CFR50.4.
Very truly yours, I
R.F. urski Manager Nuclear Safety & Regulatory Affairs RFB:BGM:ssf Enclosure cc (w/ enclosure): R.D. Martin, NRC Region IV NRC Resident Inspectors Office cc (w/o enclosure): J.A. Calvo, NRC-NRR D.L. Wigginton, NRC-NRR E.L. Blake W.M. Stevenson "AN EQUAL OPPORTUNITY EMPLOYER'8 :
I 9