ML20034F525
| ML20034F525 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1992 |
| From: | Burski R ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F193-0117, W3F193-117, NUDOCS 9303030351 | |
| Download: ML20034F525 (60) | |
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I e a W3F193-0117 A4.05 QA March 1, 1993 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 i
Semiannual Radioactive Effluent Release Report
~
Gentlemen:
i Attached is the Semiannual Radioactive Effluent Release Report for the period July 1 through December 31, 1992.
This report is submitted in accordance with Waterford 3 Technical Specification 6.9.1.8.
If you have any questions, please contact C.J. Thomas at (504) 739-6531.
Very truly yours,
.p R.F. Burski
[
Director, Nuclear Safety RFB/CJT/ssf Attachment cc:
(w/ Attachment)
J.L. Milhoan, NRC Region IV NRC Resident Inspectors Office (w/o Attachment)
D.L. Wigginton, NRC-NRR R.B. McGehee i
N.S. Reynolds l
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9303030351 921231 1
PDR ADOCK 050003B2 j!.
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Report i
July 1, 1992 - December 31, 1992 i
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q Waterford 3 SES
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TABLE OF CONTENTS
- 1. 0 SCOPE f
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits I
I 2.2 Maximum Permissible Concentrations j
i 2.3 Average Energy t
2.4 Measurements and Approximations of Total Radioactivity f
2.5 Batch Releases i
f 2.6 Unplanned Abnormal Releases i
3.0 GASEOUS EFFLUENTS i
4.0 LIQUID EFFLUENTS
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5.0 SOLID WASTES I
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6.0 METEOROLOGICAL DATA
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7.0 ASSESSMENT
OF DOSES i
7.1 Doses due to Gaseous Effluents
.l 7.2 Doses due to Liquid Effluents j
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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
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8.4 Report of Technical Specification Required Instrument Inoperability 8.5 Activity Released via Secondary Pathways 8.6 Missed Effluent Samples j
8.7 Additional Information l
8.8 Corrections to Semiannual Radioactive Release Reports 8.9 Gas Decay Tank Releases 9.0 TABLES i
10.0 ATTACHMENTS i
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1.0 SCOPE r
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This Semiannual Radioactive Effluent Release Report is submitted as i
required by Waterford 3's Technical Specification 6.9.1.8.
It covers the f
period from July 1, 1992 through December 31, 1992.
Information in this report is presented in the format outlined in Appendix B of Regulatory i
Guide 1.21.
j 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 1992;.
f (3) Assessment of radiation doses due to liquid and gaseous radioactive l
effluents released during 1992, (4) Explanation of why certain effluent instrumentation was not restored l
to operable status within the time specified in the ACTION. Statement, as per UNT-005-014, Offsite Dose Calculation Manual (ODCM),
Specification 5.6.1 and 5.6.2; 1
(5) A summary of the quantities of radioactive gaseous effluents released from identified miscellaneous secondary release pathways for 1992; f
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(6) A summary of changes to the Process Control Program during this j
reporting period.
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2.0 SUPPLEMENTAL INFOPJiATION i
2.1 Regulatory Limits i
i The Limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
f These limits are addressed in UNT-005-014, Offsite Dose Calculation l
Manual.
1 2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in-l gaseous effluents from the site to areas at and beyond the i
site boundary shall be limited to less than or equal to 500
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mrem /yr to the total body and less than or equal to 3000 i
I mrem /yr to the skin.
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The air dose due to noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be j
limited to the following:
i a.
During any calendar quarter: Less than or equal to 5 i
mrad for gamma radiation and less than or equal to 10 i
mrad for beta radiation and,
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During any calendar year: Less than-or equal to 10 mrad I
for gamma radiation and less than or equal to 20 mrad for beta radiation.
2.1.2 Jodines; Particulates,lialf Lives > 8 Days; and Tritium The dose rate due to Iodine-131 and 133, tritium, and all j
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.
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-i 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 ir. gaseous effluents i
i released to areas at and beyond the site. boundary shall be
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limited to the following i
k 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 f
to any organ.
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2.1.3 Liquid Effluents The concentration of radioactive material relea' sed in liquid j
effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table e
11, Column 2 for radionuclides other than dissolved or j
entrained noble gases. For dissolved or entrained noble l
gases, the concentration shall be limited to 2.0E-4 pCi/ml l
total activity.
i The dose or dose commitment to a member of the public from
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radioactive materials in liquid effluents released to
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t unrestricted areas shall be limited to the following.
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a.
During any calendar quarter to less than or equal to 1.5 l
mrem to the total body and less than or equal to 5 mrem to any organ, and l
b.
During any calendar year to less than or equal to 3 mrem
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to the whole body and to less than or equal to 10 mrem to i
any organ.
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2.1.4 Uranium Fuel Cycle Sources l
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The dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel
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cycle sources shall be limited to less than or equal to 25 1
mrem to the. total body or any organ (except the thyroid, i
which shall be limited to less than or equal to.75 mrem) over 12 consecutive months.
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2.2 Maximum Permissible Concentrations i
2.2.1 Fission and Activation Gases; Iodines; and Particulates, Half Lives > 8 Days l
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 11, 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 l
liquid effluents.
2.3 Average Energy This is not applicable to Waterford 3's Effluent Specifications.
E-Bars are not required to be calculated from ef fluent release data.
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l 2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 5.3-1 and 5.4-1 of UNT-005-014, Offsite Dose Calculation Manual.
i 2.4.1 Fission and Activation Gases (Noble Gases)
S for continuous 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 j
i 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 t
batch releases, a gas grab sample 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 I
I 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 determined radionuclide concentrations j
and effluent volume discharged were used to calculate the l
t previous week's activity released.
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I 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 l
subsequent releases until the next scheduled analysis was
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perfo rmed.
l Grab samples of continuous and batch releases were analyzed monthly for tritium. The determined concentrations were l
used to estimate tritium activity in subsequent releases f
until the next scheduled analysis was performed.
i 2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and j
f analyzed using gamma spectroscopy. The measured concentra-tions were used to determine radionuclide concentrations in the previous week's releases. For batch releases, gamma analysis was performed on the sample prior to release.
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 j
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
.l released quantities of these isotopes in liquid effluents i
during the current month or quarter.
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The total radioactivity in liquid effluent releases was 1
determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent f
discharged.
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2.5 Batch Releases A summary of.information for gaseous and liquid batch releases is included in Table 1.
2.6 Unplanned / Abnormal Releases During this reporting period, there.was one abnormal release. A liquid radioactive release was performed with the radiation monitor setpoint incorrectly specified.
Licensee Event Report (LER) Number 92-007 documents this event. A discussion is provided below.
On July 17, 1992, a liquid radioactive waste release was performed from Waste Condensate Tank 'A' to the Circulating Water System. 1The associated radiation monitor high alarm setpoint was incorrectly adjusted to a value that was ten times higher than the calculated setpoint. During the release, the radioactivity concentration monitored remained well below the calculated setpoint. At no time were any Offsite Dose Calculation Manual (ODCM) dose or concentration limits exceeded.
Description of Event:
On July 17, 1992, Health Physics department made preparations to' release Waste Condensate Tank 'A' (WCT A) to the Mississippi River via the Circulating Water System. A computer hard disk failure on July 15, 1992, placed the computer used to perform release permits and effluent calculations out of commision. Release permits had to be calculated manually in accordance with HP-001-231,- Liquid Radioactive Release Permit (Manual), and HP-001-235, Calculation.and Adjustment of Radiation Monitoring Setpoints. The pre-release permit (LB92081) was generated manually at approximately 1300 on July 17, 1992. The radiation monitor setpoint was correctly calculated to be 3.34 E-3 pCi/ml. However, the HP technician who-performed the calculation incorrectly transcribed the setpoint to the front page of the release permit as 3.43E-2 pCi/ml..
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i Description of Event (cont'd):
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i discrepancy was identified by a separate reviewer, (HP Engineer) who i
signed the release permit and returned it to the HP-technician for
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correction. The HP Technician corrected the mantissa,.but failed to-
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recognize that the exponent was ten times too high. The release
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permit was not returned to the reviewer, since the signature was complete, to ensure that the corrections were satisfactory.
i Consequently, the release permit specified'an incorrect setpoint of l
3.34 E-2 pCi/ml.
HP adjusted the high alarm setpoint for the effluent radiation' l
t monitor PRM-1RE-0647 to 3.34E-2 pCi/ml. The. release was commenced at 1546 on July 17, 1992 by Operations personnel in the control-room. Dilution flow for the release was maintained at 1.0E+6
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gal / min for entire duration. Also~10 min Radiation Monitor System trends and Radiation Recorder, LWM-IFRR-0647, indicate that the l
f liquid was uniformly mixed..
Both of these instruments indicate that l
radioactivity levels remained somewhat steady at approximately f
5.25 E-4 pCi/ml throughout the release. Also, these records indicate.
that the radioactivity levels never exceeded the alert alarm limit of j
6.00 E-4 pCi/ml, nor the calculated (true) High Alarm Value of 3.34E-3 pCi/ml. Operations terminated the release at 2020 on July 17, 1992. The release permit war closed out manually on July 19 at j
approximately 1500.
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I At 0913 on July 20, 1992 the HP Engineer who reviewed the release
-l permit (LB92081) noticed that the high alarm setpoint was I
j incorrect. The engineer discovered the discrepancy while preparing e
t to update the repaired effluents computer system with manually i
calculated permit data.
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i Cause of Event:
The root cause of this event is personnel error. Release permits are typically computer generated as per HP-001-233, Liquid i
Radioactive Releaser Permit (Computer). With failure of the HP l
Computer System, HP department was forced to use manual calculations t
or simple personal computer spreadsheets that perform the requirements I
of HP-001-231 and HP-001-235. The setpoint calculation is an attachment to the release permit. The number generated _during the j
setpoint calculation must be copied to the release permit cover sheet. This was done incorrectly. A contributing cause of this event involves the reviewer. Although the reviewer identified the
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error he did not ensure that the error was corrected before signing the release permit. Had this been done, the event may have been prevented.
Corrective Action:
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All manually calculated release permits were reviewed for errors and
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the release information was entered into the H.P. computer system.
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i All manually calculated release permits now require supervisory oversight before the release.
Individuals involved in the release permit errors were counseled on the importance of self-checks and permit reviews.
j 1-l Actions Taken to Prevent Recurrence
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HP standing instructions were updated to include new requiements for manually calculated release permits. These instructions required j
g that an on-duty HP Supervisor review the release permit and that the permit not be delivered to operations until the HP Supervisor had
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arrived on-site and the final review had been completed.
Procedure changes to HP-001-231 and HP-001-235 have been completed to 1
incorporate human f actors into the manual release permit calculation i
and review process.
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i 3.0 GASEOUS EFFLUENTS I
The quantities of radioactive material released in gaseous effluents are summarized in Tables IA, 1B, and 1C.
Note that there were no elevated re-i leases, since all Waterford 3 releases are considered to be at ground level.
T The estimated total error in % is based upon several statistical uncertain-i ties due to sample counting, efficiency, volume, etc.
i 4.0 LIQUID EFFLUENTS l
The quantities of radioactive material released-in liquid effluents are
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summarized in Tables 2A and 2B.
The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.
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. and 5
Alaron Corp. These waste forms are identified in Table 3 and volumes
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reported reflect the volume of waste shipped offsite, not final disposal
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c volumes. Final disposal volumes are reported as they become available.
The estimated total error in % is based upon several statistical l
e uncertainties due to sample counting, efficiency, volume, etc.
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6.0 METEOROLOGICAL DATA In Table 4 the hourly meteorological data from January 1, 1992 through l
December 31, 1992, is presented in the form of joint frequency distribu-tions of wind speed, wind direction, and atmospheric stability. The-Waterford-3 data recovery results by parameter are as follows:
Parameter Annual Data Recovery Rate Delta T 100.0%
Wind Speed 100.0%
Wind Direction 100.0%
Overall*
100.0%
- Simultaneous occurrence of valid data for all three parameters.
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7.0 ASSESSMENT
OF DOSES l
i 7.1 Dose Due to Gaseous Effluents i
7.1.1 Air Doses at the Site Boundary i
Air doses from gaseous effluents were evaluated at the closest l
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 f
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-'
t ing the plant. The location that would have the highest dose 1
would be that location having the most restrictive (largest)
X/Q value. Based on actual meteorological data collected
.I during 1992, this location was determined to be in the NNE l
4 sector at a distance of 966 meters from the plant.
Doses were I
assessed at this location in accordance with the methodology i
described in the Waterford 3 Offsite Dose Calculation Manual considering only beta and gamma exposures in air due to noble gas. The results of these assessments for the year 1992 are summarized as follows:
i Beta air dose:
0.83 mrad Gamma air dose:
0.67 mrad f
The beta and gamma air doses are 4.2% and 6.7% of the Annual i
Dose Limits, respectively. The results of the dose calculations t
by quarter are summarized in Table 5.
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7.1.2 Maximum Organ Dose to the Critical Receptor i
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The maximum organ dose to a MEMBER OF THE PUBLIC from I-131, j
I-133, tritium, and all radionuclides'in particulate form j
with half-lives greater than 8 days in gaseous effluents
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released to areas at and beyond the site boundary was deter-I I
mined for 1992.
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An assessment of the maximum organ dose was performed for t
the critical receptor. The critical receptor was assumed to
!t be located at the nearest residence to the plant having the j
most restrictive atmospheric dispersion (X/Q) and deposition l
(D/Q) parameters. Furthermore, it was assumed that the j
receptor living at this residence consumed food products that were either raised or produced at this residence. Using l
land use census and meteorological data for 1992, the residence 4
with the highest X/Q and D/Q values was determined to be in j
the N sector at a distance of 1448 meters. The dose calcula-tion was performed in accordance with the methodology described-i
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in the Waterford 3 Offsite Dose Calculation Manual considering l
t the inhalation, ground plane exposure, and ingestion pathways, 1.
r The maximum organ dose to the critical receptor was determined to be 0.28 mrem to the infant thyroid. This represents 1.9%
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of the Annual Dose Limit. Dose calculation results are j
i summarized by quarters in Table 5.
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7.2 Doses Due to Liquid Effluents 3
The annual doses to the maximum exposed individual resulting from i
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-exposure to liquid effluents released during 1992 from Waterford 3 i
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were 0.16 mrem total body and 0.22 mrem to the maximum exposed organ (liver). These values are 5.3% and 2.2% respectively, of the Annual
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i Dose Limits. Dose calculation results are summarized by quarters in
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t Table 5.
The doses were calculated in accordance with the methodology l
described in the Waterford 3 Offsite Dose Calculation Manual.
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7.3 40 CFR Part 190 Dose Evaluation j
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!l In accordance with Waterford 3 Offsite Dose Calculation Manual, l
Section 5.5.2, dose evaluations to demonstrate compliance with Surveil-l 1
q lance Requirements 5.5.1.a and 5.5.1.b of the ODCM, dealing with dose
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from the uranium fuel cycle, need to be performed only if quarterly l
t doses exceed 3 mrem to the total body (liquid releases), 10 mrem to i
t any organ (liquid releases), 10 mrad gamma air dose, 20 mrad beta j
air dose, or 15 mrem to any organ from radiciodines and particulates.
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At no time during 1992 were any of these limits exceeded; therefore, J
j no evaluations were required.
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f 7.4 Doses to Public Inside the Site Boundary
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a The Member of the Public inside the site boundary expected to have j
the maximum exposure due to gaseous effluents would be an employee 4
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at Waterford 1 and 2 fossil fuel plants, located in the NW sector,
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approximately 670 meters from the plant.
Based on an assumed occup-l 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 f
1 adults, the maximum organ dose would be less than 0.034 mrem to the thyroid. Total body and skin doses were calculated to be 0.07 and j
I 0.15 mrem, respectively. These doses were calculated according to the methodology described in the Waterford 3 Offsite Dose Calculation f
Manual considering only the inhalation and ground plane exposure l
1 pathways.
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8.0 RELATED INFORMATION f
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8.1 Changes to the Process Control Program
-i There were minor changes to the Process Control Program during the j
reporting period. Vendor information was changed in procedure RW-001-210, Process Control Program, to reflect the current contract service company.
Copies of the changes to the Process Control I
Program are included in Attachment 10.1.
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4 8.2 Changes to the Offsite Dose Calculation Manual t
There were no changes to the Offsite Dose Calculation Manual during j
the reporting period.
l 8.3 Unavailability of REMP Milk Samples l
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i Due to the unavailability of three milk sampling locations within five j
kilometers of the plant, Broad Leaf sampling is performed in accordance 1
i with ODCM Table 5.8-1.
Milk is collected, when available, from the l
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j control location and two identified sampling locations as indicated t
in Waterford 3 Offsite Dose Calculation Manual, Attachment 6.14.
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3 8.4 Report of Required Effluent Instrument Inoperability t
ODCM Specifications, 5.6.1.b and 5.6.2.b requires reporting
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in the Semiannual Radioactive Effluent Release Report'of why desig-l nated inoperable effluent monitoring instrumentation was not restored l
to operability within the time specified in the ACTION Statement.
l During the reporting period, there were no cases.when instrumentation was not restored to operability within the time specified.
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8.5 Activity Released Via Secondary Pathways
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The following secondary release paths were continuously monitored for
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radioactivity:
- 1) the Hot Machine Shop Exhaust (AH-35), 2) Decontam-ination Shop Exhaust (AH-34), 3) the RAB H&V Equipment Room Ventilation r
system Exhaust (E-41A and E-41B); and 4) the Switchgear/ Cable Vault
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Area Ventilation System (AH-25).
Continuous sampling for these areas is maintained in order to demonstrate the operability of installed j
treatment systems and to verify integrity of barriers separating f
primary and secondary ventilation systems.
Sampling for these areas i
1 was limited to continuous particulate and iodine sampling and monthly
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noble gas grab sampling. The activity released via these secondary pathways resulted from routine operations and remained below significant levels. Table 6 contains a summary of activity released during 1992.
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r 8.6 Missed Effluent Samples:
t 8.6.1 No liquid or gaseous effluent samples were missed during this f
reporting period.
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8.7 Additional Information The most recent Reactor Coolant System E-Bar calculation was 0.416 MeV/ Disintegration from a sample obtained on December 20, 1992.
Reactor Coolant System E-Bar is supplied for information only and
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is not used for effluent dose calculations.
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8.8 Corrections to Semiannual Radioactive Release Reports l
Corrections to Table 3 of Semi Annual Radioactive Release Report f
covering the period from January 1, 1992 to June 30, 1992 are f
presented in attachment 10.2.
These changes are due to submittal of I
actual burial volumes and activities from volume reduction and i
disposal facilities, which was not available when the last report was submitted to the Nuclear Regulatory Commission.
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.i 8.9 Cas Decay Tank Releases I
-i Release of a Gas Decay Tank is sometimes complicated by leakage from another tank. Design Change #3091 proposed replacement of components made of carbon steel with' stainless. steel. This' design
- l change was cancelled. Administrative. controls are currently in i
i' effect to implement precautions associated with releases of Gas i
Decay Tanks.
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i 9.0 TABLES 1
Batch Release Summary
- j 1A Semiannual Summation of all Releases by Quarter - All Airborne l
Effluents IB Semiannual Airborne Continuous Elevated and Ground Level Releases
'i IC Semiannual Airborne Batch Elevated and Ground Level Releases i
2A Semiannual Summation of All Releases by Quarter - All Liquid i
Effluents t
2B Semiannual Liquid Continuous and Batch Releases l
3 Solid Waste Shipped Offsite for Disposal 4
Joint Frequency Distribution of Meteorological Data f
5 Dose Calculation Results for 1992 6.
Activity Calculations for Secondary ReJaase Pathways for 1992 10.0 ATTACHMENTS i
1 10.1 Changes to Process Control Program; July 1,1992 to i
r December 31, 1992 (13 pages) l 6
10.2 Corrections to Table 3 of Semiannual Radioactive Release Report of t
January 1, - June 30, 1992 Submittal of burial volumes and
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r activities from volume reduction and disposal facilities.
(3 pages)~
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TABLE 1 e
(1 of 1) i t
REPET CATEIXRY
- BATCH RE11ASE SLffMRY RELEASE POINT
- ALL l
TYPE OF RE11ASE
- BATCH LIQUID A E GASE0LS PERIOD START TIE
- 4368:00 WS = 12:00AM JULY 1.1992 PERIOD DO TIE
- 8783:59 IRS = 11:59PM DEEENIER 31. 1992 i
LIQU:D RELEASES
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f fGEIER OF RELEASES 111 TOTAL TIE FOR ALL RELEASES :
28876.0 MIWTES a
rmXIftf1 TIE FOR A RElfASE :
319.0 MIRITES AVERAGE TIE FOR A RELEASE :
260.1 MIRITES MIN!ftf1 TIE FW A RELEASE :
104.0 MIRITES AVERAGE STREAM RSI 830857.8 GPM i
GASERS RELEASES
{
RMER OF RELEASES 4
TOTAL TIE F(R ALL RELEASES :
1575.0 MIRITES i
f14XIftf1 TIE FOR A RELEASE :
600.0 MIRITES AVERAGE TIE FOR A RELEASE :
393.8 MIRITES MIN!!tf1 TIE FOR A RELEASE :
180.0 MIWTES i
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f TABII 1A 1
(1 of 1) i I
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r REPORT CATEIDRY
- SEM1AMAL SumATION IF ALL RELEASES BY DlMRIER i
TYPE OF ACTIVITY
- ALL AIRBCRE EFTUENTS r
REPCRTIE PERl(D
- QUARTER 0 3 #0 QuRRTER 6 4
- LHIT :00ARTER 3 :QuRRTER 4 :EST.TUTAL:
I
- MllRS
- MUtS
- ERR (R % :
e TYPE OF EFTUENT
- 4345-6552 :6553-8760 :
A. FISS!DN AM) ACTIVATION PR00lCTS
- 1. TOTAL RELEASE
- CLRIES
- 6.83E 01 : 1.26E 01 : 1.5DE 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :lCI/SEC : B.60E 00 : 1.59E 80 :
i
- 3. PERCENT OF AFPLICABLE LIMIT WA WA t
i E
B. RADIO!! DIES
- 1. TUTAL 10 DIE-131
- CURIES
- 7.78E-07 : 1.26E-05 : 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :lE!/SEC : 9.79E-08 : 1.59E-06 :
i i
- 3. PERCENT OF APPLICAELE LIMIT WA WA l
i i
C. PARTIClLATES f
- 1. PARTICliATES(HALF-LIVES)B DAYS) :CLRIES
- 9.53E-06 : 3.06E-06 : 1.50E 01:
t
- 2. #JERAGE RELEASE RATE FOR PERIOD : LEI /SEC
.__-06 : 3.ESE _07 :
- 1.20E
- 3. PERCENT OF APPLICABLI LIMIT WA WA
- 4. GROSS ALP m RA010 ACTIVITY
- CLRIES
- 3.99E-06 : 5.07E-06 :
1 D. TRITitM
- 1. TDTAL RELEASE
- CURIES. : 9.40E 01 : 7.91E 00 : 1.50E 01:
- 2. #JERAGE RELEASE RATE FOR PERIOD :lE!/SEC : 1.19E 01 : 9.95E-01 :
- 3. PERCENT OF APPLICA11I LIMIT WA WA l
W21419HP 19 l
l I
TABLE IB i
(1 of 1)
REPORT CATEGOPY
- SEF11#MML AIRBORIE CONTIRIOUS ELEUATED #O ERul#O
- ifUEl. RELEASES. TOTALS FOR EACH lull 0E RELEASED.
TYPE OF ACTIVITY
- FISSIDH GASES. ICDIES. #0 PARTIClLATES REPCRTlHG PERIID
- QUARTER 4 3 #0 QUARTER 4 4 i
- ELEURTED RELEASES : GRulDO RELEASES :
l
- LMIT
- 0UARTER 3 :0UARTER 4 :0UARTER 3 : QUARTER 4 :
- HOLRS
- 60LRS
- leLRS
. :iGRS i
NJCLIDE
- 4345-6552 :6553-8760 :4345-6552 :6553-8760 :
j FISSIDH GASES l
XE-133
- CLRIES : 0.00E-01 : 0.00E-01 : 5.16E 01 : 6.05E 80 :
1 XE-135
- CLRIES : 0.00E-01 : 0.00E-01 : 1.2BE 01 : 6.39E 00 :
TOTAL FOR PERIOD
- QRIES : 0.00E-01 : 0.00E-01 : 6.45E 01 : 1.24E 01 :
10 DIES 1-131
- CURIES : 0.00E-01 : 0.00E-01 : 7.7BE-07 : 1.26E-05 :
PARTIClLATES H-3
- CLRIES : 0.00E-01 : 0.00E-01 : 9.48E 01 : 7.91E 00 :-
CD-58
- CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.26E-06 :
00-60
- ClRIES : 0.0DE-01 : 0.00E-01 : 0.00E-01 : 5.31E-07 :
Rll-103
- ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 9.41E-07 :
CS-134
- (1 RIES : 0.00E-01 : 0.00E-01 : 3.37E-07 : 2.96E-07 :
- CLEIES : 0.00E-01 : 0.00E-01 : 9.79E-07 : 0.00E-01 :
- CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.48E-DB :
G ALPH4
- CLRIES : 0.00E-01 : 0.00E-01 : 3.99E-06 : 5.07E-06 :
BR-82
- CLRIES : 0.0DE-01 : 0.00E-01 : 8.21E-06 : 0.00E-01 :
TOTAL FOR PERICD
- CLRIES : 0.00E-01 : 0.00E-01 : 9.48E 01 : 7.91E 00 :
f d
i W21419HP 20 l
i
i TABLE IC l
(1 of 1) 3 t
- SDilAMIAL AIREGBE BATCH ELEUATED M 910lH) i
- LEVEL RELEASES. TOTALS FOR EACH NO.lDE RELEASED.
i TYPE (F ACTIVITY
- FISSION GASES.10 DIES. E PARTICtLATES i
REPORTlHG PERIOD
- QUARTER 4 3 6 QUARTER 4 4 t.t
- D.EVATED RELIASES : GROLN) RELIASES :
i
- tNIT
- QUARTER 3 : QUARTER 4 : QUARTER 3 : QUARTER 4 :
l
- KluRS
- lGRS
- H0lRS
- lGRS i
14JCLlDE
- 4345-6552 :6553-8760 :4345-6552 :6553-8760 :
-l FISSION GASES t
KR-65
- C! RIES : 0.00E-01 : 0.CDE-01 : 0.DDE-01 : 4.63E-02 :
1 XE-131M
- C! RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.73E-03 :
i XE-133M
- CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.22E-05 :
XE-133
- CLRIES : 0.00E-01 : 0.00E-01 : 3.16E 00 : 1.56E-01 :
l XE-135
- CURIES : 0.00E-01 : 0.0DE-01 : 1.34E-01 : 0.00E-01 :
AR-41
- CLRIES : 0.00E-01 : 0.00E-01 : 5.37E-01 : 0.00E-01 :
TOTAL FIR PERIOD
- ClRIES : 0.00E-01 : 0.00E-01 : 3.BJE 00 : 2.00E-01 :
1(DIES l
10E l
l 3
i PARTIClLATES H-3
- CLRIES : 0.00E-01 : 0.00E-01 : 1.26E-02 : 0.00E-01
}
r j
f l
i t
l i
i
)
l l
1 1
i l
i l
W21419HP 21 i
4
i
?
s TABLE 2A l
l (1 of 1)
REPORT CATEE(Rf
- SEMIMM#t. SIM1ATION OF ALL RELEASES BY OtMRTER i
TYPE OF ACTIVITY
- ALL LI0ll!D EFF1.1DTS e
REPORTIE PERI (D
- QlMRTER 4 3 AE QUARTER 4 4
[
INIT :0LARTDt 3 :QtmRTER 4 :EST. TOTAL:
- ELRS
- K1RS
- ERR (R t :
TYPE OF EFFLIENT
_ ___ -6552 :6% 3-8760 :
- 4345 A. FISSION AE ACTIURTION PR:DLETS I
- 1. TOTAL RELEASE (ET IELtDIE TRITilfi. GASES, ALPH4)
- CLRIES
- 4.72E-01 : 5.29E-01 : 1.50E 01:
?
- 2. AVERAGE DILilTED CONCENTRATION
)
DLRIE PERl(D
- ltin1L
_-09 : 1.97E _08 :
- 7.3BE
- 3. PERCENT OF APPLICABLE LIMIT 4
WA WA b
B. TRITitt!
- 1. TOTAL RELEASE
- CLRIES
- 1.75E 02 : 2.47E 01 : 1.5DE 01:
i
- 2. AVERAGE DILUTED COEENTRAT!DN f
DLRIE PERIOD
- tEI4L
- 2.74E-06 : 9.17E-07 :
- 3. PERCENT OF APPLICABLE LIMIT WA
- WA i
C. DISSOLVED #0 ENTRA!ED GASES
- 1. TDTAL RELEASE
- CURIES
- 1.51E 00 : 1.54E-02 : 1.5DE 01:
- 2. AVERAGE DILUTED COMINTRATIDH DLRINE PER100
- tEI4L
- 2.36E-08 : 5.71E-10 :
i
- 3. PERCENT OF APPLICABLE LIMIT WA
- WA ~i D. GRDSS ALPHA RADI0 ACTIVITY
- 1. TOTAL RELEASE
- CURIES
- 0.00E-01 : 0.00E-01 : 1.50E 01:
4 f
E. ESTE UOL RELEASED (PRE-DILUTib0 : GAL : 7.90E 05 : 4.97E 05 : 1.50E 01:
F. UDLifE OF DILUTION ETER USED
- 1.69E 10 : 7.11E 09 : 1.5DE 01:
i i
I i
i W21419HP 22
'l
i TABLE 2B (1 of 2) s REPORT CATEEDRY
- SEMIA>4Ut. LIRllD CONTIMluS M BATDI RELEASES l'
- TDTALS FIR EACH EELIDE REl. EASED.
TYPE OF ACTIVITY
- ALL RADIO U 2.! DES REPORTING PERIOD
- QUARTER 4 3 APO QUARTER 4 4 l
- CONTINUQUS REEASES :
BATCH RELIASES :
- LHIT
- QUARTER 3 :00ARTER 4 : QUARTER 3 : QUARTER 4 :
- KILRS
- 10lRS
- HOLRS
- l(llRS MILIDE
- 4345-6H2 :6H3-8760 :4345-6H2 :6H3-8760 :
ALL RELIDES H-3
- CLRIES : 0.00E-01 : 0.00E-01 : 1.75E 02 : 2.47E 01 :
h24
- CLRIES : 0.00E-01 : 0.00E-01 : 2.59E-04 : 3.92E-04 :
CR-51 CLRIES : 0.00E-01 : 0.00E-01 : 1.33E-02 : 4.75E-02 :
% 54
- CLRIES : 0.00E-01 : 0.00E-01 : 2.56E-03 : 6.03E-03 :
- CLRIES : 0.00E-01 : 0.00E-01 : 1.10E-01 : 2.19E-02 :
- CLRIES : 0.00E-01 : 0.00E-01 : 4.83E-03 : 8.17E-03 :
CSSB
- CURIES : 0.00E-01 2 0.00E-01 : 9.ME-02 : 1.93E-01 :
00-60
- CLEIES : 0.00E-01 : 0.00E-01 : 1.6BE-02 : 2.83E-02 :
ZH-65
- CLRIES : 0.00E-01 : 0.00E-01 : 3.69E-86 : 0.00E-01 :
RB-BB
- CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.52E-03 :
SR-89
- CLRIES : 0.00E-01 : 0.00E-01 : 7.57E-05 : 3.1BE-05 :
SR-92
- CLRIES : 0.00E-01 : 0.00E-01 : 7.96E-05 : 2.70E-04 :.
ZR-95
- CLRIES : 0.00E-01 : 0.00E-01 : 4.23E-03 : 1.73E-02 :
ZR-97
- CLE!ES : 0.00E-01 : 0.00E-01 : 2.00E-04 : 0.00E-01 :
E 95
- CLRIES : 0.00E-01 : 0.00E-01 : 7.30E-03 : 2.97E-02 6 99
- CLRIES : 0.00E-01 : 0.00E-01 : 6.91E-03 : 0.00E-01 :
TC-99M
- CLRIES : 0.00E-01 : 0.00E-01 : 5.77E-04 : 0.00E-01 ;
6 103
- CLRIES : 8.00E-01 : 0.00E-01 : 9.6BE-05 : 6.25E-04 :
% 206
- CURIES : 0.00E-01 : 0.00E-01 : 5.56E-04 : 7.34E-04 :
AG-110M
- CLEIES : 0.00E-01 : 0.00E-01 : 5.75E-04 : 2.39E-03 :
TE-132
- CLRIES : 0.00E-01 : 0.00E-01 : 5.65E-04 : 7.74E-05 :
1-131
- CLRIES : 0.00E-01 : 0.0dE-01 : 9.44E-02 : 3.27E-03 :
1-132
- ClR!ES : 0.00E-01 : 0.00E-01 : 1.00E-03 : 4.46E-05 :
1-133
- CLRIES : 0.00E-01 : 0.00E-01 : 4.61E-02 : 0.00E-01 :
1-1M
- CURIES : 0.00E-01 : 0.00E-01 : 2.85E-03 : 0.00E-01 :
CS-134
- CURIES : 0.00E-01 : 0.00E-01 : 1.14E-04 : 1.B4E-02 :
05-136
- CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.92E-05 :
- CURIES : 0.00E-01 : 0.00E-01 : 6.6?E-04 2.13E-02 :
b i
4 W21419HP 23 i
i I
I i
TABLE 2B l
(2 of 2) i i
k i
)
REPORT CATEIKRY
- SEMIMM1AL LIQUID EllNTIR10US NO BATCH RELEASES
- T01ALS FOR EACH MICLIDE RELEASED.
l TYPE OF ACTIVITY
- ALL RAD 10EICLIDES t
REPORTIM; PERIOD
- QU $TER 4 3 N O QUARTER 4 4 l
b
- CONT!RIOUS RELEASES :
BATCH RELEASES :
- INIT
- 0UARTER 3 :00ARTER 4 : QUARTER 3 :0UARTER 4 :
- MILRS
- HOLRS
- H0lRS
- KluRS RILIDE
- 4345-6552 :6553-8760 :4345-6552 16553-8760 :
ALL HUCLIDES CONTIRED 84-140
- CLRIES : 0.00E-01 : 0.00E-01 : 7.41E-04 : 0.00E-01 :
LA-140
- CLRIES : 0.00E-01 : 0.00E-01 : 4.33E-04 : 1.34E-04 :
LA-142.
- CURIES : 0.00E-01 : 0.00E-01 : 3.35E-04 : 0.00E-01 :
CE-144
- ClRIES : 0.00E-01 : 0.00E-01 : 1.7BE-04 : 3.92E-04 :
l W-187
- CURIES : 0.00E-01 : 0.00E-01 : 1.45E-03 : 0.00E-01 :
W-239
- CLRIES : 0.00E-01 : 0.00E-01 : 4.36E-04 : 0.00E-01 :
KR-B5M
- ClRIES : 0.00E-01 : 0.00E-01 : 1.72E-04 : 4.09E-05 :
- CLRIES : 0.00E-01 : 0.00E-01 : 2.04E-02 : 0.00E-01 :
KR-89
- CtRIES : 0.00E-01 : 0.00E-01 : 7.31E-05 : 4.49E-05 :
XE-131M
- CURIES : 0.00E-01 : 0.00E-01 : 1.3BE-02 : 0.00E-01 :
i XE-133M CLRIES : 0.00E-01 : 0.00E-01 : 1.55E-02 : 2.97E-04 :
XE-133
- CLRIES : 0.00E-01 : 0.00E-01 : 1.44E 00 : 1.11E-02 :
XE-135
- CLRIES : 0.00E-01 : 0.00E-01 : 1.90E-02 : 3.77E-03 :
AR-41
- CLRIES : 0.00E-01 : 0.00E-01 : 1.06E-05 : 7.73E-05 :
a ES-57
- CURIES : 0.00E-01 : 0.00E-01 : 1.82E-04 : 5.22E-04 :
- l
% 124
- CLRIES : 0.00E-01 : 0.00E-01 : 0.64E-03 : 1.44E-02 :
i SH-113
- CURIES : 0.00E-01 0.00E-01 : 1.60E-03 : 5.37E-03 :
% 97
- CURIES : 0.00E-01 : 0.00E-01 : 1.02E-03 : 5.36E-03 :
E 122
- CLRIES : 0.00E-01 : 0.00E-01 : 1.17E-02 : 7.34E-04 :
I
% 125
- CLRIES : 0.00E-01 : 0.00E-01 : 3.5BE-02 : 9.97E-02 :
E 127
- CLRIES : 0.00E-01 : 0.00E-01 : 4.56E-04 : 0.00E-01 :
BR-82
- CLRIES : 0.00E-01 : 0.00E-01 : 3.76E-04 : 0.00E-01 :
)
% 126
- CLRIES : 0.00E-01 : 0.00E-01 : 1.07E-03 : 3.BDE-04 :
l
._ _-01 1.77E 02 2.52E 01 :
l 0.00E 0.00E _01 :
TOTAL FOR PERIOD
- ClRIES :
i I
r t
)
[
i I
t t
f W21419HP 24
[
i
c i
i TABLE 3-(1 of 11) l i
t SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL l
DURING PERIOD.7/1/92 THRU 12/31/92 l
WASTE CONTAINER WASTE TOTAL 3
3 TYPE VOLUME (ft )
VOLUME (m )
ACTIVITY (Ci)
ERROR i
i (B) Non Compacted Dry 1040 29.4 4.62E-2
- 1 125%
Activity Waste Shipped to Scientific Ecology 23.33 4.30E-2 125%'
)
Group for Volume Burial Volume Buried Activity.
Reduction
- t 1
(B) Non Compacted Dry 1040 714.43 3.21E+0 *1 125%
1 Activity Waste
{
Shipped to l
t Alaron Corp for Volume 119.71 3.16 125%
Reduction
- Burial Volume Buried Activity
?
i (A) Powder Resin Dewatered 95 5.38 1.04E-5 *2 125%
l in a B-25 Box 5.38 8.80E.!
Burial Volume Buried Activity:
125%-
.f i
(A) SGBD Bead Resin Dewatered 207.4 11.08 7.55E-5
- 2 125%
j in a Steel Liner i
i'
}
- Waste volumes shipped'for volume reduction do not reflect final burial waste volumes unless otherwise stated.
l
- 1 Activity determined by estimations.
i
- 2 Activity determined-by measurements.
l i
W21419HP 25 i
l TABLE'3 (2 of 11) i SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/92 THRU 12/31/92
.i 1
i WASTE CONTAINER WASTE TOTAL 3
3 TYPE VOLUME (ft )
VOLUME (m )-
ACTIVITY (Ci)
ERROR.
(
i (A) Resin Waste Management 170.8 19.35 7.53E+02
- 2 125%
Resin Dewatered in a High Integrity i
Container (Bead Resin) 7 i
i (A) Mechanical Filters 120.3 3.4 1.51E+02
- 2 125%
Dewatered Shipped in a High Integrity Container 6
(A) Liquid Waste Management 170.8 9.67 7.53E+00
- 2
-125%
j Resin Dewatered in a High Integrity Container (Bead Resin) l 1
i a
(D). Waste Oil Shipped to 7.5 11.16 9.05E-2
- 1 125%
'i Scientific Ecology Group for Incineration
- Incinerated
']ncinerated l
I
- Waste volumes shipped for volume reduction do not reflect-final burial waste volumes unless otherwise stated.
l
- 1 Activity determined by estimations.
-l
- 2' Activity determined by measurements.
l l
W21419HP 26
j
-)
TABLE 3 l
(3 of.11) e SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL J
DURING PERIOD 7/1/92 THRU 12/31/92 l
WASTE TYPE NUCLIDE NAME
% ABUNDANCE CURIES i
i (A) Mechanical Filters Fe-55 37.585%
5.69E+01 Dewatered Shipped in
.Co-58 36.528%
5.53E+01 a High Integrity Co-604 7.200%
1.09E+01 l
Container Ni-63 6.262%
-9.48E+00 Cr-51 2.741%
4.15E+00 Be-7 2.569%
3.89E+00 Mn-54 1.632%
2.47E+00 Zr-95 1.493%
2.26E+00 i
Sn-113
.931%
1.41E+00 i
Nb-95
.912%
1.38E+00 Ru-106
.506%
7.66E l C-14
.388%
5.87E-01 i
Sb-125
.373%
5.65E-01 Fe-59
.320%
4.84E-01 Ce-144-
.235%
3.56E-01 i
Pu-241
.111%'
.1.68E-01 l
.091%
1.38E-01 l
Sr-89
.072%
1.09E-01 Sr-90
.028%
4.26E-02 Cs-134
.010%
1.58E-02 Cm-242
.009%
1.32E-02 i
Cm-243/44
.002%
3.62E-03 Pu-238
.001%
1.72E-03 Pu239/40
.001%
1.33E-03.
.000%
6.67E-04 j
Pu-242
.000%
8.13E-06 1
i i
l i
W21419HP 27 i
t
i TABLE 3
{
(4 of 11)'
j SOLID WASTE _ SHIPPED OFFSITE FOR DISPOSAL
.j DURING PERIOD 7/1/92 THRU 12/31/92
-l WASTE TYPE NUCLIDE NAME
% ABUNDANCE
. CURIES l
t t
i (A) Resin Waste Management Co-58 68.246%
5.11E+02 i
Resin Dewatered in a Ni-63 11.282%
- 8.44E+01 High Integrity Container Cs-137 5.155%-
3.86E+01
-l (Bead Resin)
Fe-55 4.465%
3.34E+01 i
Co-60 3.287%
2.46E+01 Cs-134 3.137%
2.35E+01
[
Mn-54 2.555%
1.91E+01
-[
Sb-125 1.412%
1.06E+01 Co-57
.182%
-1.36E+00 l
Fe-59
.096%
7.21E !
.079%
5.94E-01
[
Ce-144
'050%
3.77E-01 l
Sr-89
.026%
1.95E-01 j
.025%
1.87E-01 i
.002%
1.76E-02 Pu-238
.000%
3.45E-04 Cm243/44
.000%
2.06E-04
[
Pu239/40
.000%
_1.68E-04 l
.000%
6.52E-05 Tc-99
.000%
5.19E-05 i
i i
i S
W21419HP 28 1
I i
TABLE 3 f
(5 of 11)'
i SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL l
DURING PERIOD 7/1/92 THRU 12/31/92 I
WASTE TYPE NUCLIDE NAME
% ABUNDANCE CURIES l
i i
l (A) Liquid Waste Management Co-58 50.709%
6.59E+00 i
Resin dewatered in a Cs-137 21.655%
2.81E+00
]
High Integrity Container Co-60 7.367%
9.57E-01 (Bead Resin)
Ni-63 6.039%
7.84E-01 j
Fe-55 5.833%
7.58E-01 l
Cs-134 4.751%
6.17E-01 Mn-54 2.514%
3.27E-01 Nb-95
.513%
6.67E-02 l
Ce-144
.273%
3.55E-02
{
Sb-125
.131%
1.70E-02 i
.105%
1.37E-02 l
.054%
7.08E-03 l
.054%
6.99E-03 t
Pu-238
.000%
9.64E-06 Pu-239/40
.000%
6.43E-06 Tc-99
.000%
5.30E-06 Cm243/44
.000%
4.03E-06 Am-241
.000%
1.87E-06 t
I I
t i
1 k
i i
i l
I i
W21419HP 29 l
1
.i l
TABLE 3 (6 of 11) l i
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/92 THRU 12/31/92 l
i i
WASTE TYPE NUCLIDE NAME
% ABUNDANCE CURIES
.I (A) Powdex Resin Dewatered Cs-137 63.7%.
6.60E-06 Shipped in a B-25 Box Cs-134 27.8%
2.88E-06 l
Ce-144 4.5%
4.63E-07 H-3 2.7%
2.83E-07 (A) Steam Generator Blow Cs-137 47.7%
3.60E-05; Down Resin Dewatered Cs-134 24.0%
1.81E-05 j
in a steel liner Co-60 12.1%
9.16E Co-58 9.9%.
.7.50E-06 Mn-54 4.5%
3.40E-06 Ni-63 1.6%
1.23E-06
{
i i
(B) Non Compacted Dry Co-58 41.1%
6.49E-01 i
Activcity Waste Shipped Co-60 28.5%
4.50E-01
?
to Scientific Ecology Cs-137 12.2%
1.92E-01 Group and Alaron Corp.
Cs-134 6.0%
9.48E-02 (Sea Land Container)
Mn-54 5.5%
8.69E-02
~
Ni-63 3.8%
6.00E-02 Fe-55 1.7%
2.68E-02 Co-57 1.0%
1.58E-02 k
i s
l f
W21419HP 30 f
.~,
d TABLE 3 l
(7 of 11) i SOLID-WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/92 THRU 12/31/92 j
1 WASTE TYPE NUCLIDE NAME
% ABUNDANCE CURIES l
'l l
i (B) Non Compacted Mn-54 5.51%
9.25E-02 Dry Activity Waste Fe-55' 1.73%
2.90E i Shipped to Alaron Co-57 1.02%
1.72E-02 Corp. (Strong-Tight Package) Co-58 41.23%
6.92E-01 Co-60 28.42%
4.77E Ni-63 3.81%
6.39E-02 i
.03%
.4.48E-04
{
.02%
3.35E-04 i
Cs-134 6.02%
1.01E-01 l
Cs-137 12.21%
2.05E-01 l
i (D) Oil Shipped to Cs-137 40.5%
3.67E-02 j
Scientific Ecology Co-60 31.9%
-2.89E-02 Group for Incineration Co-58 9.4%
8.55E-03:
Cs-134
'7.8%-
7.02E-03
.j Ni-63 4.3%
3.88E-03 i
Fe-55 1.9%
1.75E-03 Sb-125 1.9%
1.69E-03 I
l l
1 i
i i
i i
ij W21419HP 31 I
e
'll
. TABLE 3' (8 of 11)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/92 THRU 12/31/92 l
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION l
v i
l i
l 7
Sole Use Cask Barnwell, SC-f 3
-Sole Use Flatbed Oakridge, TN 13 Sole Use Flatbed Wampum, PA t
l f
WASTE
- OF TYPE OF i
CLASS SHIPMENTS TYPE CONTAINER.
MODE DESTINATION l
l t
B 3
7A LSA Poly - HIC Truck Barnwell, SC AU 3
Type-A Poly - HIC Truck Barnwell, SC C
1 Type-B Poly - HIC Truck Barnwell, SC l
AU 13 LSA Strong-Tight Truck Wampum, PA j
AU 3
LSA Strong-Tight Truck OakRidge, TN 1
i
}
I 1
W21419HP 32 n
f TABLE 3 i
(9 of 11)
~;
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL.
DURING PERIOD 7/1/92 THRU 12/31/92
]
?
t i
SUMMARY
BY MAJOR WASTE TYPES j
i (A) Spent Resins, Filter Sludges, Evaporator Bottoms, etc.
(B) Dry Compressible Waste, Contaminated Equipment, etc.
'f (C) Irriaded Components, Control Rods, etc.
(D) Other (Waste Oil)
I P
WASTE WASTE TOTAL TYPE VOLUME (M )
ACTIVITY (Ci)
ERROR I
3 t
i (A) 48.88 9.13E+02 125%
J (B) 143.04*
125%
l Burial Volume 3.25E+00 3
(C)
NDNE N/A N/A
{
i (D) 0.0 8.85E-02 125%
t Incinerated Incinerated i
~
i
- Includes all Type (B) waste volume.
l W21419EP 33 l
i
~
m.
- =,..,
h TABLE 3 (10 of 11).
l SOLID WASTE SHIPPED OFFSITE'FOR DISPOSAL DURING PERIOD 7/1/92 THRU 12/31/92 i
SUMMARY
BY MAJOR WASTE TYPE (Cont'd) i WASTE TYPE NUCLIDE NAME
% ABUNDANCE CURIES I
(A)
Co-57 0.15 1.36E+00 Co-58 62.75 5.73E+02 Co-60 3.99 3.65E+01
~
Cs-134 2.64 2.41E+01-Cs-137 4.55 4.15E+01 i'
Fe-55 9.97 9.11E+01 Mn-54 2.40 2.19E+01 i
Ni-63 10.37 9.47E+01 E+0 i
- 5
.22 1
Nb-95 0.16 1.45E+00 I
Zr-95 0.25 2.26E+00' Sr-89 0.03 3.04E-01 Sr-90 0.03 2.43E-01 i
Ru-106 0.08 7.66E-01 Sn-113 0.15 1.41E+00 Ce-144 0.08 7.69E-01 Cr-51 0.45 4.15E+00 t
11-3 0.00 2.46E-02' Be-7 0.43 3.89E+00 C-14 0.13 1.19E+00 Tc-99 0.00 5.72E-05 Pu-238 0.00
-2.07E-03 Pu-239/240 0.00 1.50E-03 Pu-241 0.02 1 68E-01 l
Pu-242 0.00 8.13E-06 Am-241 0.00 7.34E-04 Cm-242 0.00 1.32E-02 Cm-243/244 0.00 3.83E-03 (B)
Co-57 1.01 3.30E-02 Co-58 41.21 1.34E+00 l
Co-60 28.49 9.27E-01 Cs-134 6.02 1.96E-01 Cs-137 12.20 3.97E-01' i
I Fe-55 1.71 5.58E-02' Mn-54 5.51 1.79E-01 Ni-63 3.81 1.24E-01 H-3 0.01 4.48E-04 l
C-14 0.01 3.35E-04 l
W21419HP 34 1
_j
l TABLE 3 (11 of 11)
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/92 THRU 12/31/92 1
h
SUMMARY
BY MAJOR WASTE TYPE (Cont'd)
-[
t i
WASTE TYPE NUCLIDE NAME-
% ABUNDANCE CURIES i
t (D)
Co-58 9.66 18.55E-03 Co-60 32.66 2.89E-02 Cs-134 7.93 7.02E-03 f
Cs-137 41.47 3.67E-02 Fe-55 1.98 1.75E-03 Ni-63 4.38 3.88E-03 j
Sb-125 1.91 1.69E-03 i
~
f l
l l
i W21419HP 35
TABLE 4 (1 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA Joint frem ency distribution of wind speed and direction'in hours 01-01-92 00:00to 12-31-92 23:59 Pasquilt Class A Wind Speed (M/S) at 10-m Level Wind Direction.35.50.51.75.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1 7.0 7.1-10 10.1-13 13.1-18.0 >18.0 Totat N
0 0
0 2
6 17 15 10 0
0 0
0 50 KNE O
O O
1 4
22 31 6
0 0
0 0
64 NE O
O O
2 3
39 61 10 0
0 0
0 115 ENE D
0 0
0 0
3 14 1
2 0
0-0 20 E
O O
O O
O O
1 0
0 1
0 0
2 ESE O
O O
O 1
0 1
0 0
0 0
0 2
SE O
O O
O O
O 2
3 0
0 0
0 5
SSE O
O 0
0 2
4 12 3
0 0
0 0
21 S
0 0
0 0
0 5
18 2
0 0
0 0
25 SSW D
D 0
1 3
4 6
1 0
0 0
0 15 SW D
0 0
1 4
13 8
0 0
0 0
0 26 WSW D
0 0
2 7
15 7
0 0
0 0
0 31 W
D 0
0 2
3 17 5
0 0
0 0
0 27 WW D
0 0
0 4
8 3
0 0
0 0
0 15 NW 0
0 1
1 5
3 1
0 0
0 0
0 11 NWW D
D 0
0 4
14 21 10 4
0 0
0 53 Total 0
0 1
12 46 164 206 46 6
1 0
0 432 Nwber of calms for A Stability:
0 Joint frecpency distribution of wind speed and direction in hours 01-01-92 00:00to 12-31-92 23:59 Pasqu!LL Class B Wind speed (M/S) at 10-m Level Direction.35.50.51.75.76-1.0 1.1-1.5 1.6 2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10 10.1 13 13.1-18.0 >18.0 Total N
O O
0 2
6 13 11 4
2 0
0 0
35 NNE D
0 0
0 6
11 13 4
0 0
0 0
34 NE O
O O
2 3
29 24 6
0 0
0 n
64 ENE O
O O
1 1
2 1
1 0
0 0
0 6
E O
O O
O 2
2 0
1 0
0 0
0 5
ESE O
O O
O 1
3 9
2 0
0 0
0 15 SE 0
0 0
1 1
4 14 6
0 0
0 0
26 SSE O
O O
O 1
4 7
3 0
0 0
0 15 5
0 0
0 0
0 4
12 0
0 0
0 0
16 SSW D
0 0
5 2
5 9
2 0
0 0
0 23 SW 0
0 0
0 3
21 12 0
0 0
0 0
36 WSW D
0 0
3 7
5 16 0
0 0
0 0
31 W
D 0
0 2
7 12 9
0 0
0 0
0 30 WWW D
0 0
2 4
4 4
1 0
0 0
0 15 NW D
0 0
1 2
2 1
1 0
0 0
0 7
KNW D
0 0
1 5
to 12 2
1 0
0 0
31 Total 0
0 0
20 51 131 154 33 3
0 0
0 392 Nmber of calms for B Stability:
0 W21419HP 36
I TABI.E 4 (2.of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA t
i i
Joint frecpency distribution of wind speed and direction in hours 01-01-92 00:00to 12-31 92 23:59 PaSqJitt Class C Wind Speed (M/S) at 10-m Level Wind Direction.35.50.51. 75.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1 7.0 7.1 10 10.1-13 13.1 18.0 >18.0 Total N
0 0
0 1
3 7
16 1
1 0
0 0
29 NNE D
0 0
3 7
16 13 3
0 0
0 0
42 NE O
O O
2 4
28 24 1
0 0
0 0
59 i
ENE D
0 0
1 1
2 7
0 1
0 0
0 12
~
E O
O O
2 0
2 3
0 0
0 0
0 7
ESE O
O O
O O
O 11 3
0 0
0 0
14 f
SE O
O 0
2 1
1 14 3
2 1
0 0
24 SSE D
0 0
1 0
4 7
1 0
0 0
0 13 5
0 0
1 1
1 6
12 6
0 0
0 0
27 i
SSW 0
0 0
0 0
5 11 2
0 0
0 0
18 SW D
0 0
2 2
12 13 2
0 0
0 0
31 WSW 0
0 0
0 2
11 16 0
0 0
0 0
29 W
D 0
0 1
1 7
8 0
0 0
0 0
17 WWW D
0 1
2 1
5 2
0 0
0 0
0 11 NW D
0 0
0 1
4 5
0 0
0 0
0 10 NNW D
0 0
0 1
5 11 9
2 0
0 0
28 Total 0
0 2
18 25 115 173 31 6
1 0
0 371 kmber of calms for C Stability:
1 Joint frequency distribution of wind speed and direction in hours 01-01-92 00:00to 12-31-92 23:59 Pasgalt! Class D Wind Speed (M/S) at 10-m Level Wind Direction.35.50.51.75.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10 10.1-13 13.1-18.0 >18.0 Total N
1 2
6 15 18 60 1 04 57 6
0 0
0 269 NNE D
0 5
20 25 51 111 36 12 0
0 0
260 i
NE D
0 7
12 23 100 151 36 13 1
0 0
343 ENE D
1 1
9 6
25 B4 15 4
0 0
0 145 E
O 1
3 1
5 10 35 6
0 0
0 0
61 ESE O
O O
6 1
9 63 24 0
1 0
0 1D4 SE 1
1 4
8 8
27 92 28 4
3 1
0 177 r
J SSE O
O 2
6 17 53 79 24 9
0 0
0 190 S
1 0
0 13 13 51 53 26 11 0
0 0
168 SSW 1
1 2
12 22 24 27 5
3 0
0 0
97 i
SW 1
1 4
8 17 40 48 5
0 0
0 0
124 I
VSW D
0 1
13 12 30 33 5
2 0
0 0
96
{
W D
3 3
20 17 30 16 7
0 0
0 0
96 WWW 0
0 3
11 6
25 27 5
0 0
0 0
77 NW D
1 3
4 15 26 49 18 2
0 0
0 118 NNW D
0 3
5 11 43 75 44 11 0
0 0
192
+
Total 5
11 47 163 216 604 1047 341 77 5
1 0
2517 Nmber of calms for 0 Stability:
2 f
W21419HP 37
TABLE 4 (4 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA l
Joint frequency distribution of wird speed and direction in hours 01-01-92 00:00to 12-31-92 23:59 Pasquilt Class G r
Wind Speed (M/S) at 10-m Level i
Wind Direction.35.50.51.75.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10 10.1-13 13.1-18.0 >18.0 Total N
O 5
7 4
1 1
0 0
0 0
0 0
18 WNE O
1 2
3 1
1 0
0 0
0 0
0 8
NE O
1 3
4 3
1 0
0 0
0 0
0 12 ENE O
0 2
1 0
1 0
0 0
0 0
0 4
E D
1 1
0 0
0 0
0 0
0 0
0 2
ESE O
O O
1 0
0 0
0 0
0 0
0 1
SE D
1 2
0 2
1 0
0 0
0 0
0 6
SSE 1
4 6
12 9
2 0
0 0
0 0
0 34 s
4 13 23 24 4
0 0
0 0
0 0
0 68 ssW 11 16 28 24 5
1 0
0 0
0 0
0 85 SW 5
21 23 11 0
0 0
0 0
0 0
0 60 WSW 14 22 19 6
1 0
0 0
0 0
0 0
62 W
19 31 25 5
3 0
0 0
0 0
0 0
83 kmW to 11 11 2
1 0
0 0
0 0
0 0
35 NW 6
6 7
5 1
0 0
0 0
0 0
0 25 WNW 8
6 6
7 4
1 0
0 0
0 0
0 32 Total 78 139 165 109 35 9
0 0
0 0
0 0
535 Number of calms for G stability:
50 Total vaild hours for alt stabilities =
87S4 Total invaild hours for att stabilities =
0 6
L e
W21419HP 39
TABLE 5 (1 of 2)
DOSE CALCULATION RESULTS FOR 1992 (DOSES DUE TO GASEOUS RADI0 ACTIVE EFFLUENTS)
- (Nii 1 ** QUARTER 2 0F 19?2 *e Se (NIT 1 ** OLARTER 1 0F 1992 **
DOSE FROM RADIDi(DIES. PARTICtLATES. AfD TRITim DDSE FROM RA01010 DIES. PARTICLLATES. AHD TRITilft AT CONTROLLIE LDCATION:
AT CONTROLLIE LOCATION:
TOTAL DOSE (t1 REM) FOR B0HE
- 1.7175E-05 TOTAL DOSE (tREM) FOR BOE
- 2.0503E-05 TOTAL DOSE (tREM) FOR LIVER
- 8.1395E-02 TOTAL DOSE (EEM) FOR LIVER
- 9.8197E-02 TOTAL DOSE (FREM) FOR TOTAL BODY
- 8.1383E-02 TOTAL DOSE (tREM) FOR TOTAL BODY
- 9.8179E-02 TOTAL DOSE (tREM) FOR TifYRDID
- 8.4204E-02 TDTAL DOSE (fREM) FOR THYRDID
- 9.817BE-02 TOTAL DOSE (tREM) FDR KIDEY
- 9.8183E-02 TOTAL DOSE (tREM) FOR KIDHEY
- 8.1391E-02 TDTAL DDSE (rREM) FOR LING
- 8.1380E-02 TOTAL DOSE (rREM) FOR LLNG
- 9.8180E-02 TOTAL DOSE (tREM) FOR GI-LLI
- 8.1379E-02 TOTAL DOSE (MREM) FOR GI-LLI
- 9.817BE-02 KiBLE GAS DOSE AT SITE BOUK)ARY:
K]BLE GAS DOSE AT SITE BMOARY:
TOTfL BODY DOSE TOTAL (tREM)
- 5.6634E-01 TOTAL BODY DOSE TOTAL (tREM)
- 1.3866E-02 SKIN DOSE TOTAL (tREM) 1.1019E 00 SKIN DOSE TDTAL (MREM)
- 3.0943E-02 R]8LE GAS AIRDOSE AT SITE BOLNDARY:
t0BLE GAS AIRDOSE AT SITE B03 04RY:
TOTAL Gaff % AIR 00SE (tRAD)
- 6.0902E-01 TOTAL Gaff % AIR 00SE (FRAD)
- 1.5366E-02 TOTAL ETA AIRDOSE (FRAD)
- 7.1754E-01 TOTAL BETA AIRDOSE trRAD)
- 2.8736E-02
- e LNIT 1 ** QL M TER 3 0F 1992 *e
- LHIT 1 ** QUARTER 4 0F 1992 **
DOSE FROM RAD 1010 DIES. PARTICULATES. AND TRITim DOSE FROM RADID10 DIES. PARTICULATES. NO TRITitti AT CONTROLLIE LDCATION:
AT CONTROLLIE LOCATION:
TOTAL DOSE (t1 REM) FOR BONE
- 5.2477E-05 TOTAL DOSE (MREM) FOR BOE
- 4.4711E-05 WTAL DOSE (tREM) FOR LIVER
- 8.1651E-02 TOTAL DOSE (tREM) FOR LIVER
- 6.8556E-03 TOTAL 00SE (tREM) FOR TOTAL BODY
- 8.1602E-02 TOTAL DOSE (t1 Reft) FOR TOTAL BODY
- 6.8304E-03 ETAL DOSE (tREM) FOR THYRDID
- 8.2120E-02 TOTAL DOSE (tREM) FOR THYROID
- 1.5275E-02 TOTAL DOSE (tREM) FOR KIDHEY
- 8.1613E-02 TOTAL DOSE (FREN) FOR KIDEY
- 6.8503E-03 VOTAL 00SE (tREM) FOR LLNG
- 8.160}E-02 TOTAL DOSE (tREM) FDR LtH;
- 6.8196E-03 TOTAL DOSE (MREM) FOR GI-LL1
- 8.159BE-02 TOTAL DOSE (MREti) FOR GI-LLI
- 6.81BIE-03 RELE GAS DOSE AT SITE BOUR)ARY:
IOBLE GAS DOSE AT SITE BOL)OARY:
TDTAL BODY DOSE TOTAL (tREM)
- 3.2309E-02 TOTAL BODY DOSE TOTAL (tREM)
- 9.7621E-03 SKIH DOSE TDTAL (tREti)
- 7.06BSE-02 SKIN DOSE TOTAL (tREM)
- 2.1797E-02 NDBLE GAS AIRDOSE AT SITE 80llOARY:
K)BLE GAS AIRDOSE AT SITE BOUNDMY:
TOIAL Gaff % AIRDOSE (MRAD)
- 3.5BB6E-02 TDTAL GAtt% AIRDOSE (tRAD)
- 1.0542E-02 TOTAL BETA AIRDOSE (tRAD)
- 6.6484E-02 TOTAL BETA A!RDOSE (tRAD)
- 1.6282E-02
- LN!T 1 ** TDTALS FOR 1992 *e DOSE FROM RAD 101001ES. PARTICtLATES. AND TRITltri AT CONTROLLIE LOCATION:
TOTAL DOSE (tREM) FOR 80E
- 1.3487E-04 TOTAL DOSE (rREM) FOR LIVER
- 2.6810E-01 TOTAL DOSE (tREM) FOR TOTAL 00DY
- 2.6800E-01 TDTAL DOSE (rREM) FOR THYROID
- 2.797BE-01 TOTAL DOSE (t1 REM) FOR KIDHEY
- 2.6804E-01 TOTAL DOSE (MREM) FOR Lt#G
- 2.679BE-01 TOTAL DOSE (t1 REM) FOR SI-LLI
- 2.6797E-01 R) ELE GAS DDSE AT SITE BDOARY:
TOTAL BODY DOSE TOTAL (MREM)
- 6.222BE-01 SKIN DOSE TOTAL (r1 REM)
- 1.2254E 00 NOBLE GAS AIRDOSE AT SITE B000ARY:
TOTAL Gaff % AIR 00SE (FRAD)
- 6.7082E-01 TOTAL BETA AIRDOSE (tRAD)
- 8.2904E-01 W21419HP 40
i i
TABLE 5 (2 of 2) j DOSE CALCULATION RESULTS FOR 1992 (DOSES DUE TO LIQUID RADI0 ACTIVE EFFLUENTS)
{
I
- lHIT 1 ** QUARTER 1 0F 1992 **
TOTAL DOSE (f1 REM) FOR BOE
- 3.137BE-03 TUTAL DOSE (fREM) FOR LIVER
- 4.8672E-03 i
TOTAL DOSE (fREM) FOR TOTAL BODY
- 3.353}E-03 TOTAL DOSE (fREM) FIR TRYRDID
- 0.6443E-04 i
TOTAL DOSE (PREM) FOR KIDEY
- 1.7904E-03 TOTAL DOSE (PREM) FIR LIM;
- 8.0782E-04 TOTAL DOSE (fREM) FOR GI-LLI
- 2.9813E-03 j
- LHIT 1 ** QUARTER 2 (F 1992 **
TOTAL DOSE (fREM) FOR BOE
- 2.7636E-03 TOTAL DOSE (fREM) FOR LIVER
- 4.4105E-03 TOTAL DOSE (fREM) FOR TOTAL BODY
- 3.1248E-03 i
TUTAL DOSE (PREM) FOR THYRDID
- 1.5458E-03 TOTAL DOSE (PREM) FOR KIDEY
- 1.576BE-03 TDTAL DOSE (fREM) FOR LIMi
- 6.3550E-04 TDTAL DOSE (fREM) FOR GI-LLI
- 1.2510E-03 i
- LHIT 1 ** QUARTER 3 0F 1992 **
TOTAL DOSE (fREM) FOR BOE
- 1.7935E-03 TOTAL DOSE (fREM) FOR LIVER
- 2.7480E-03 TOTAL DOSE (fREM) FDR TOTAL BCDY
- 1.9924E-03 TOTAL DOSE (fREM) FOR TRYRDID
- 3.451}E-02 TOTAL DOSE (fREM) FOR KIDEY
- 1.1607E-03 i
TOTAL DOSE (fREM) FOR LtHi
- 5.7591E-04
^
TOTAL DOSE (fREM) FOR SI-LLI
- 3.642iI-03
- [ NIT 1 ** QUARTER 4 0F 1992 **
TOTAL DOSE (fREM) FOR BOE
- 1.1567E-01 TDTAL DOSE (f1 Reft) FOR LIVER
- 2.0592E-01 TOTAL DOSE (fREM) FOR TOTAL BODY
- 1.5311E-01 TOTAL DOSE (fREM) FOR THYRDID
- 2.0522E-03 i
TOTAL DOSE (IREM) FOR KIDEY
- 6.0061E-02 1
TOTAL DOSE (PREM) FOR LIMi
- 2.2689E-02
~
TDTAL 00SE (FREM) FDR GI-LLI
- 1.2224E-02 I
- LNIT 1 ** TOTALS FOR 1992 **
TOTAL DDSE (fREM) FOR BOE
- 1.2336E-01 i
TDTAL DOSE (PREM) FOR LIVER
- 2.1796E-D1
+
TOTAL DOSE (f1 Reft) FOR TOTAL BODY
- 1.614BE-01 i
TDTAL DOSE (fREM) FOR THYRDID
- 3.8976E-02 TOTAL DOSE (f1 REM) FOR KIDHEY
- 7.2579E-02 TOTAL DOSE (fREM) FOR LLN;
- 2.470BE-02 TOTAL DOSE (fREM) FOR GI-LLI
- 2.0099E-02 9
i i
I V2141911P 41
-i
.i TABLE 6 i
(1 of 1)
ACTIVITY CALCULATIONS FOR SECONDARY l
RELEASE PATHWAYS FOR 1992 i
i VENTILATION SYSTEM TOTAL ACTIVITY RELEASED DURING 1992 (Curies) l l
t I-131 1-133 Co-58 Xe-133
[
SWITCHGEAR AREA VENT (AH-25)
<LLD
<LLD
<LLD
<LLD l
t
+46 H&V EQUIPMENT ROOM (E-41A&B) <LLD
<LLD
<LLD'
<LLD i
HOT MACHINE SHOP (AH-35) 3.09E-6 <LLD
<LLD
<LLD i
DECONTAMINATION SHOP (AH-34) 6.09E-6 <LLD 6.05E-8 (LLD i
i TOTALS 9.18E-6 <LLD 6.05E-8
<LLD b
i i
I 1
j l
l
~
1 I
l l
W21419HP 42 l
1
)
i
a
?
i-F ATTACEMENT 10.1 (13 PAGES) i j-4 i
I a.
.I
+
t '
e i
j i
-l 1-i i
i i
1:
s j
i I
i i
r i
-i 1
CHANGE 5 TO RW-001-210,.
l l
3 i
i i
l PROCESS CONTROL PROGRAM (PCP) s 0
1 it 1
s i
i i
-l 1
i.
July 1, 1992 To December 31, 1992 l,
t t
4,
-l a
l i
)
I ti j
i 1
1-1 J
t i
1 i
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i 4
1 J
]-
l 1
J i
I 1
i 1-l a
(
l a
s V21419HP 43 i-l
PORC AhTs-PORE---S/E REVIEW AND APPROVAL SHEET REVIEW OF: RW-001-210 - (Change 1)
PORC 2
Process Control Program (Rev. 4)
PORC - S/C D The PORC or PORC S/C has reviewed this item and determined that a Safety /
Commitment Review was performed (if applicable), thzt a Safety Evaluation was performed (if applicable), that an unreviewed safety question does not exist, and that nuclear safety is/was not adversely affected.
PORC MEMBER SIGNATURE MEMBER YES NO i
Maintenance Superintendent g
gg f
/
Operations Radiation Protection Q[p l
Superintendent
~
x Superintendent
[
\\
Quality Assurance
),
/ /
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Member
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Plant Engineering l
Superintendent
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i PORC-S/C Member j
PORC-S/C Member PORC-S/C Member i
Meeting No.92-070 Item No.
VIII-A Date:
7/23/92 This item is recommended for approval? 2 YES D NO This item requires SRC/NRC review prior to implementation? O YES 2 NO If yes, ensure documentation supporting review is attached.
SIGNATURE RECOMMENDED FOR APPROVAL YES NO DATE PORC-S/C Chairman g y
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PORC Chairman Comments:
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Approved by
/b7_/h Date
/ General Manager Plant Operations j
UNT-001-004 Revision 13 Attach.ent 6.1 (1 of 1) i 27 1
I WATERFORD 3 SES y',
rh* Block:
PLANT OPERATING MANUAL PORC CHANGE / REVISION / DELETION REQUEST PORC-S/C hccess Orn4-c}
bcoram Procecure No. :
1 \\-cN
.O i e Title :
-J Effecuve Date :
(If diffemnt fro:n approval daIc.)
COMPLETE A. B. and C :
A. N=e No. :
I
@ Permane Devianon Exp:ra: ion Date :
B. Revmon No. :
d C. Delenon :
O YES
@ NO I ln d d ro o c n c c_ d i j r,
Yn DESCRIPTION OF OIANGE. REVISION OR DELETION r i n t e - - m -,1 <-
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l a b - e e-REASON POR CIANGE. REVISION OR DELETION C, tv' ~
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DATE :
l ORKENA"IUR :
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DATE : 4-2F 9 2
- A 4
w TEGINK'AL
/l-GRDfJP }{EAD REVIEW :
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Ni DATE:
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- TEMPORARY APPROVAL GF.G :
DATE :
DATE:
- TEMPORARY APPPDVAL:
- Refer to paragrapns 3.215 anc 5.3.2.5: for Temporary Approval Eecurrements.
UNT-001-003 Revision 14 Atta cc=ent e.4 (1 of 1) 34
i Admiri-trative Procedure RW-001-210 Process Control Program Revision 4
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TABLE OF CONTENTS l
t 1.0 PURPOSE
2.0 REFERENCES
3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE
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5.1 Program Description s.2 Solidification Process Parameters 5.3 Administrative Cc,trols 5.4 Waste Characterization and Classification 5.5 Quality Assurance i
6.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Q
Title Revision 4 b
N 1-11 Revision 4
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Administrative Procedure RW-001-210 l
l Process Control Program Revision 4 l
i 1.0 PURPOSE 1.1 The purpose of Waterford Steam Electric Station - Unit Number 3
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i (Waterford 3) Process Control Program (PCP) is to describe the i
e program which provides reasonable assurance of the complete stabili-(
zation and/or solidification, as applicable of various radioactive
" wet wastes" which may include resin slurries and evaporator bottoms are in accordance with applicable Department of Transportation.(DOT),
f a
Nuclear Regulatory Commission (NRC), State and licensed burial j
facilities acceptance criteria for packaging and shipment to an approved burial site.
Compliance with these criteria will be achieved through implementation of the PCP and related Waterford 3 and vendor
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supplied procedures.
Containers engineered and built to comply with i
the stability requirement may be used.
Waterford 3 SES typically j
relies on Vendor supplied systems and/or services for stabilization and solidification services.
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2.0 REFERENCES
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2.1 Vaterford 3 Documents j
4 2.1.1 FSAR Chapter 11.4, Solid Waste Management System a
2.1.2 FSAR Chapter 13.4, Review and Audit
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j 2.1.3 FSAR Chapter 13.2, Training 2.1.4 FSAR Chapter 13.5, Plant Procedures 2.1.5 Nuclear Operations Management Manual,Section VI, Chapter 5 i
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t Administrative Procedure RW-001-210 l
Process Control Program Revision 4 2.2 Vendor Controlled Documents l
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q O L a m Nuclea r.Sy.s L em.s IN c., Dav1-D l' D ?ncesp Ecubro$
Tcpical Repo,rt on ^
2.2.1 L': Techn 'egie: Ccr TR002, Prcce n o ny 4 s tems.
CNSZ $. retien, la.s te.
N frc4 ram {eelificd Redieective Wostc i
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Proaess l'cntre) 7 {l Cl, e m -tvua te a r.syx l a,n s In c.
Tcchnelegice Cer :: t:en FI-OL,b s*rocccc Con $no th 2.2.2 U:
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Art y ram Sz.e flNSI f.em e n t Sol;d
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fer Derctering Liner eith U? Te -hnelegico Corporet. fee--Interncic,-
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U I2! Tcchselegics Corporetivu' l
2.2.3 Scientific Ecology Group, Inc., OP-4.34, Process Control Program for Dewatering Bead or Powdered Resin with Quick Dry l
Dewatering System No 8814.
2.2.4 Scientific Ecology Group, Inc., OP-4.31, Operating Procedure J
for SEG Rad Vaste Solidification System.
2.2.5 Scientific Ecology Group, Inc., OP-4.30, Process Control i
Program for Rad Waste Solidification Service 2.2.6 RW-2-401, Use of Radman Operating Program 2.2.7 RW-2-411, Use of Radman Data Base Manager and Recover I
2.2.8 RW-2-110, Waste Sample Collection and Isotope Evaluation
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2.3 Other Documents i
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2.3.1 10CFR61, Licensing Requirements for Land Disposal of Radio-active Waste 2.3.2 10CFR20.311, Transfer for disposal and manifests l
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2.3.3 10CFR71.91, Records i
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Administrative Procedure RU-001-210-Process Control Program Revision 4 3.0 DEFINITIONS 3.3 Stability means structural' stability as per 10CFR61.2 3.2 Solidification means the immobilization of wet radioactive wastes such as evaporator bottoms, spent resins, sludges, and reverse osmosis concentrates as a result of a process of mixing the waste type with a solidification agent (s) to meet the requirements of the i
licensed disposal site and 10CFR61.
t 4.0 RESPONSIBILITIES i
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4.1 Radiation Protection Superintendent j
4.1.1 The Radiation Protection Superintendent is responsible for the overall effective management of the plant Process Control Program. The Radiation Protection Superintendent ensures that changes are initiated to the Process Control Program procedures when necessary and that appropriate Health Physics f
support is provided.
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4.2 Lead Supervisor-Radwaste 4.2.1 The Lead Supervisor-Radwaste who reports to the Radiation
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Protection Superintendent holds key responsibilities for implementation of the Process Control Program such as:
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4.2.1.1 The preparation, review and approval of the Process j
Control Program procedures pertaining to the processing and packaging, of radioactive materiale; i
4.2.1.2 Data collection, trend analysis, long-term planning, and problem solving for the plant Process Control i
Program; 9
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Administrative Procedure RW-001-210 Process Control Program Revision 4 l
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4.2.1.3 Managing radwaste stabilization, dewatering and i
packaging; i
4.2.1.4 Preparing procedures for stabilization, dewatering and packaging; l
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t 4.2.1.s Interfacing with other groups as necessary to analyze i
t and resolve problems relating to the Process Control j
program such as the design of Radwaste Systems and Equipment; i
i 4.2.1.6 Preparing periodic reports summarizing the Process i
Control Program; 5
l 4.2.1.7 Procurement of materials and supplies required for implementation and maintenance of the Process Control Program 4.2.1.8 That personnel receive appropriate training and are 4
qualified for their respective duties; i
4.2.1.9 Adequate staffing and sufficient resources for i
f efficient and economic operation of the Process Control Program.
4.3 Operations Superintendent i
4.3.1 The Operations Superintendent is responsible for the effective j
operations of permanent plant radwaste systems and will r
coordinate radwaste activities with the radwaste department.
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i Administrative Procedure RW-001-210 Process Control Program Revision 4 l
4.4 Plant Chemist 4.4.1 The Plant Chemist is responsible for interfacing with the I
Radwaste Engineer on items or problems relating to radwaste processes and chemistry controls or chemical reactions and performing chemical and radiochemical analyses of samples of radioactive waste or materials.
4.5 Quality Assurance I
4.5.1 Quality Assurance is responsible for:
4.5.1.1 Assessing the implementation and effectiveness of the quality assurance aspects of the Process Control Program through regular audits and selective I
monitoring of activities.
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4.6 Director Operations Support & Assessment 4.6.1 The Director of Operation Support & Assessment is responsible
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for providing the following services:
t 4.6.1.1 State-of-the-art technical advise, support, and I
assistance as required; 4.6.1.2 Licensing and regulatory compliance support; and I
4.6.1.3 Appraising the Waterford-3 Process Control Program and recommending improvements.
i 4.6.2 The Operations Support and Assessment staff interfaces directly with the plant staff in providing these services.
5.0 PROCEDURE
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1 5.1 Program Description 6
l Administrative Procedure RW-001-210 Process Control Program Revision 4 l-f 5.1.1 Solidification System
Description:
Waterford 3 utilizes vendor supplied portable solidification equipment for radioactive waste solidification. References 2.2.1, 2.2.4 and 2.2.5 provide a general description of respec-l tive vendor solidification processes and process control I
features; Reference 2.2.6 describes the method which will be utilized to classify wastes in accordance with 10CFR61; and i
Reference 2.1.1 through 2.1.5 are Waterford 3 documents which '
l either implement or describe activities which provide reasonable assurance that wastes are solidified or dewatered in accordance i
with all applicable regulations and criteria.
5.1.2 Sources of Waterford 3 Stabilization / Solidification Feeds:
The Cement solidification will be used to stabilize resins, i
evaporator bottoms and boric acid concentrates. During resin f
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stabilization, vendor equipment will be connected to the Resin Waste Management System outlet to allow for the transfer of
[i resin. Vendor equipment will be connected to the Solid waste Management System outlet when evaporator bottoms from the rad-
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4 waste evaporator and boric acid concentrates from the Boron Management System evaporator are to be stabilized. Solidi-i i
feation using Aquaset/Petroset media will be used to process i
resins, oil, water / acid, evaporator bottoms and boric acid concentrates. This process will not be connected to any plant i
i vaste systems and will be processed on a batch basis.
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Administrative Procedure RW-001-210 Process Control Program Revision 4 l
f 5.2 Solidification Process Parameters:
5.2.1 Solidification formulas and solidification process parameters are incorporated into the applicable vendor process control
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program. No exceptions or deviations from vendor supplied procedures or topical reports are anticipated for stabilized waste. The formulas are used to calculate the ratio of waste, cement, water and other reagents required to achieve an acceptable solidified product.
Compatibility requirements of the waste stream with respect to the solidification media are described in the vendor process controls program. Waste e
stream parameters are adjusted as necessary to meet these
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requirements.
1 5.2.2 Test solidifications are performed on waste stream samples to j
veriiy vendor calculated solidification formulas.
5.2.3 Radioactive wastes shall be solidified or dewatered in accordance with the process control program to meet shipping and transportation requirements during transit, and disposal l
site requirements when received at the disposal site.
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5.2.4 With solidification or dewatering not meeting disposal site and shipping and transportation requirements, suspend j
shipment of the inadequately processed wastes and correct the process control program, the procedures, and/or the solid waste system as necessary to prevent recurrence.
5.2.5 With solidification or dewatering not performed in accordance with the process control program, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and perform appropriate corrective action if required.
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Administrative Procedure RW-001-210 Process Control Program Revision 4 l
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5.2.6 Solidification of at least one representative test specimen j
from at least every tenth batch of each type of wet I
radioactive wastes (e.g., filter sludges, spent resins,.
evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the vendor's l-process control program.
1 5.2.7 If the initial test specimen from a batch of waste fails to verify solidification, the process control program shall provi?e for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens 7
demonstrate solidification. The process control program may j
be modified if practical to assure solidification of subsequent
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batches of waste.
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5.2.8 If any test specimen fails to verify solidification, the i
solidification of the batch under test shall be suspended until such time as additional test specimens can be l
obtained, alternative solidification parameters can be determined in accordance with the vendors process control program, and a subsequent test verifies solidification.
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Solidification of the batch may then be resumed using the alternative solidification parameters determined by the process control program.
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Administrative Procedure RW-001-210 Process Control Program Revision 4 l
5.3 Administrative Controls 5.3.1 Administrative controls utilized to insure compliance with applicable state and federal regulations and burial site criteria are detailed in the radioactive waste solidification surveillance procedure (s). These implementing document (s) f for radicactive waste solidification and dewatering describes l
the requirements which must be met prior to processing radio-active waste, as well as the condition of the solidified or dewatered waste. Test solidifications, full scale calcula-tions and operation of the solidification equipment are performed by vendor personnel.
Dewatering operations will be performed by vendor personnel or by qualified Plant staff.
Plant staff provides Health Physics and Quality Assurance coverage, operates plant radioactive waste systems, collects l
waste stream samples and performs isotopic analyses. Copies of all referenced documents are available on site for use by j
personnel engaged in solidification activities.
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1 5.3.2 Changes to this Process Control Program shall be described in the semi-annual Radioactive Effluent Release Report for the period in which the change is made.
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5. 4-Waste Characterization and Classification l
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5.4.1 Waste Classification I
i 5.4.1.1 Solidified wastes are classified in accordance with l
the requirements of 10CFR61.55, as implemented by j
reference 2.2.6 and plant waste classification and characterization procedure (s).
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Administrative Procedure RW-001-210 Process Control Program Revision 4 l
5.4.1.2 Annual analysis will be performed on the waste streams to determine the isotopic abundance of gamma emitting isotopes in the streams as described in Reference 2.2.8.
Scaling factors for the non-gamma emitting and transuranic constituents will be developed from this annual analysis using References 2.2.6 and 2.2.7.
The activity of each radionuclide in the solidified waste will be deter-mined by a core sample or a calculational method employing the percent abundance and scaling factors with a dose to curie conversion factor as described in Reference 2.2.6.
5.4.2 Waste Characteristics 5.4.2.1 Solidified wastes will meet the characteristics of 10CFR61.56(a).
Stabilized wastes will meet the characteristics of 10CFR61.56(b). Waste containers will be labelled to identify the waste class.
5.4.2.2 The manifesting requirements of 10CFR20.311 are implemented and records are maintained in accordance with 10CFR71.91.
5.5 Quality Assurance 5.5.1 Quality Assurance related activities for the Radioactive Waste Program are implemented as described in the Nuclear Operations Management Manual (Reference 2.1.5).
These activities provide verification that the solidified wastes meet applicable state and federal regulations and burial site criteria.
6.0 ATTACIIMENTS NOKE 11
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ATTACIRIENT 10.2 (1 PAGE) l i
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CORRECTIONS TO TABLE 3 i
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SEMIANNUAL RADI0 ACTIVE RELEASE REPORT l
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i January 1, 1992 to June 30, 1992 k
h Submittal of Burial Volumes and Activities from.
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j Volume reduction and. disposal facilities.
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_-.a.-.._-,...._.____._..__:-.____
i TABLE 3 l
(1 of 12)
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SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/92 THRU 6/30/92 WASTE CONTAlNER WASTE TOTAL TYPE VOLUME (ft )
VOLUME (m )
ACTIVITY (Ci)
ERROR I
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(B) Non Compacted Dry 1040 29.44 1.65E-2
- 2 125%
i Activity Waste
-l Shipped to l
Scientific Ecology
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Group for volume 10.94 5.61E-2 reduction (Sea Land Burial Volume Burial Activity Container)*
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f (B) Non Compacted Dry 95 10.7 2.00E-4 *2 i25%
Activity Waste j
Shipped to l
Scientific Ecology f
Group for Volume 10.7 2.00E-4 Reduction (B-25 Box)*
Burial Volume-Burial Activity l
- Waste volumes shipped for volume reduction do not reflect final burial waste volumes unless otherwise stated.
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- 1 Activity determined by estimations.
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- 2 Activity determined by measurements.
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