ML20034E934

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Semiannual Radioactive Effluent Release Rept for Jul-Dec 1992
ML20034E934
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 12/31/1992
From: Floyd E, Kay D, Robert Prince
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
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ML20034E932 List:
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NUDOCS 9303020098
Download: ML20034E934 (38)
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{{#Wiki_filter:_ - - _ _ - _ _ - - - _ _ - - - - _ - _ _. COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 ~ SEMIANNU AL RADIOACTIVE EFFLUENT I RELEASE REPORT I l July 1, '.992 - December 31, 1992 l 1

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Comanche Peak Steam Electric Station Unit 1 Semiannual Radioactive Effluent Release Report July 1,1992 - December 31,1992 i i Prepared By: -~ Date: 2'2 0'73 E. T. Floyd, Staff Health Physicist i Reviewed By: OW (44V Date: 3-23-43 [) D. C. Kay Radiation Protection Supervisor Approved By: y ot7vt Date: 2.-23-'i3 R. J. Prince Radiation Protection Manager

TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS

1.0 INTRODUCTION

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 Abnormal Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 RELATED INFORMATION 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to the Process Control Program 6.3 Changes to the Offsite Dose Calculation Manual 6.4 New Locations for Dose Calculations or Environmental Monitoring 6.5 Liquid Holdup and Gas Storage Tanks 6.6 Noncompliance with Radiological Effluent Control Requirements 6.7 Resin Releases to the LVW Pond l 6.8 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems l i 1 1 j .I

TABLE OF CONTENTS 6.9 Meteorological Monitoring Program 6.10 Assessment of Doses 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary 7.2 Abnormal Batch Liquid and Gaseous Release Summary 7.3 Gaseous Effluents--Summation of All Releases 7.4 Gaseous Effluents--Ground Level Releases 7.5 Liquid Effluents--Summation of All Releases 1 - i 7.6 Liquid Effluents 7.7 Doses From Liquid Effluents 7.8 Doses From Gaseous Effluents; Noble Gas Air Dose 7.9 Doses From Gaseous Effluents; Iodines, Particulates and f Tritium, Adult Age Group t 7.10 Doses From Gaseous Effluents; Iodines, Particulates and. Tritium, Teen Age Group i 7.11 Doses From Gaseous Effluents; Iodines, Particulates and ~ Tritium, Child Age Group 7.12 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Infant Age Group 7.13 Solid Waste and Irradiated Fuel Shipments 8.0 ATTACHMENTS 8.1 Summary of the " Relocation of the Filtur/Demineralizer and Resin Dewatering Skids" Modification 8.2 Dffsite Dose Calculation Manual for CPSES Unit 1 I - i 11 1

ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPSES Comanche Peak Steam Electric Station LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste MPC Maximum Permissible Concentration ODCM Offsite Dose Calculation Manual PET Primary Effluent Tanks REC Radiological Effluent Control SORC Station Operations Review Committee WHUT Wastewater Holdup Tanks WMT Waste Monitor Tanks u lii 1 i

1.0 INTRODUCTION

This Semiannual Radioactive Effluent Release Report, for Comanche Peak Steam Electric Station Unit 1, is submitted as required by Technical Specification 6.9.1.4 and Offsite Dose Calculation Manual (ODCM) Administrative Contro] 6.9.1.4 for the period July 1, 1992 through December 31, 191'2. t Information pertaining to the following areas is included in this report: 1 A summary of the quantities of radioactive liquid and. gaseous effluents released from Unit 1 du. ring the reporting period in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974. 4 A summary of solid waste shipped from Unit 1 in tii9 format shown in Appendix B of Regulatory Guide l'. 21, Revision 1, June 1974, supplemented with three additional categories: class of waste (per 10CFR61), type of container (Strong

Tight, Type A,

Type B) and solidification agent or absorbent. An explanation of why inoperable liquid or gaseous effluent monitoring instrumentation was not corrected within 30 days. Changes to the Process Control Program. Changes to the ODCM in the form of a complete, legible copy of the entire ODCM. A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census. A description of the events leading to liquid holdup tanks _or gas storage tanks exceeding Technical Specification limits. A list and description of abnormal releases of radioactive material from the site to unrestricted areas. A description of resin releases to the LVW Ponds. A description of major changes to radioactive waste treatment systems (liquid, gaseous and solid). An assessment of radiation doses due to the radioactive liquid and gaseous effluents released from CPSES Unit 1 in 1992. i ______________________________._.____._______________________._________________._.________...__.m

l 4 An assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the Site Boundary. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from CPSES Unit 1 releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct I radiation, for the reporting period, to show conformance with 40 CFR 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." 2.0 SUPPLEMENTAL INFORMATION 2.1 Reculatory Limits J The ODCM Radiological Effluent Control 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 Gasos) The dose rate due to radioactive materials 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 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin. The air dose due to noble gases released in i gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following: a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b. During any calendar year: Less'than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation. ' J j i i

2.1.2 Iodine-131. Iodine-133. Tritium and Radioactive Material in Particulate Fom The dose rate due to Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half lives greater than 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. The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and Cl radionuclides in particulate form with half lives greater than 8

days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and b. During any calendar year: Less than or equal to 15 mrems to any organ. 2.1.3 L.icuid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble

gases, the concentration shall be limited to 2.0E-04 pCi/ml total activity.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents

released, from each
unit, to unrestricted areas shall be limited to the following:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and i i b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.,

i ~ 2.1.4 LVW Pond Resin Inventerv l 1 The quantity of radioactive' material contained in resins transferred to the LVW pond shall be j limited by the.following expression:1 t 264/V E; A;/C; < l.0 excluding

tritium, dissolved or entrained t

noble gases and radionuclides with less than an 8 day half life, where: j pond inventory limit for a single A = radionuclide_j (Curies), 10CFR20, Appendix B, Table II Column C = j 2, concentration for a single radionuclide j (gCi/ml), volume of resins in .the pond V = (gallons), and conversion unit (yCi/Ci per al/ gal) 264 = i 2.1.5 Total Dose The annual (calendar year) dose' or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to. radiation from uranium fuel cycle sources shall ~ be limited to less than or-equal to 25 mrems to the whole body or any

organ, except the.

thyroid, which shall be limited to=less than or equal to 75 mrems. 2.2 Maximum Permissible Concentrations 2.2.1 Gaseous Effluents For gaseous effluents, maximum permissibic concentration (MPC) values are not directly used in release rate calculations since the applicable limits. are expressed in terms of i dose rate at the site boundary. t 'I i .a.

l l 2.2.2 Licuid Effluents The~ values specified in 10 CFR Part 20, l Appendix B, Table II, Column 2 are used as the ) MPC for liquid radioactive effluents released to unrestricted areas. A value -'of 2.0E-04 i

  1. Ci/ml is used as the MPC for dissolved'and i

entrained noble gases in liquid effluents. 2.3 Averace Enerav This section is not applicable to the Radiological Effluent Controls contained in Part I of the ODCM for Comanche Peak, Unit 1. .j 2.4 Measurements and Approximations of Total Radioactivity ) i Measurements of total radioactivity in liquid and gaseous I radioactive effluents were accomplished in accordance l with the sampling and analysis requirements of Tables .] 4.11-1 and 4.11-2, respectively, of the CPSES ODCM. b 2.4.1 Licuid Radioactive Effluents l l Each batch release' was sampled and analyzed for gamma emitting radionuclides using_ gamma spectroscopy, prior to release. . Composite samples were analyzed monthly - and quarterly for the Primary Effluent Tanks (PET), Waste Monitor Tanks (WMT), Laundry Holdup and Monitor Tanks (LHMT) and Wastewater Holdup Tanks (WHUT). Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the onsite laboratorysusing liquid scintillation and gas flow proportional l counting techniques, respectively. Composite j samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory (Teledyne Isotopes). The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these _ radionuclides 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 radionuclide present and the total volume of the effluent released during periods of discharge. l-.

For batch releases of powdex resin to the LVW 4 pond, samples were analyzed.for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release. Composite i samples were analyzed quarterly, for Sr-89 and-Sr-90, by an offsite laboratory (Teledyne-Isotopes). For continuous releases to the circulation-water discharge from the LVW pond, daily grab. samples were obtained over the period of pond i discharge. These samples were composited and analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques. Composite samples were also analyzed ~for tritium and gross ' alpha radioactivity using. liquid scintillation and gas flow proportional counting technique's, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 ~ by a contract laboratory. l (Teledyne Isotopes). 2.4.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release. For releases from Waste Gas Decay Tanks, noble gas grab samples-were analyzed for. gamma. emitting radionuclides using gamma spectroscopy.- For releases' from .the - Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for-gamma emitting radionuclides prior to each release with the exception ~ of-Containment vents made as a precursor to ac Containment purge. In these cases,. - samples. collected and analyzed as a prerequisite to the vent were used to estimate total radioactivity released during the subsequent purge. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity-released in the batch mode.

For continuous effluent release

pathways, noble gas and-tritium grab samples were collected and analyzed weekly for -gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, l

respectively. Continuous release pathways were continuously - sampled using radiciodine adsorbers and particulate filters.- The filters were analyzed weekly for I-131. and gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radioiodine adsorber~ and particulate filter _ analyses from:the current week and the average effluent flow.rato for-the previous week were used to determine the total amount of radioactivity released in the continuous mode. Monthly composites-of particulate filters ' were analyced for gross alpha activity, in the onsite laboratory using the gas flow proportional counting technique. Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90.by. an offsite laboratory (Teledyne Isotopes). 2.5 Batch Releases A summary of information for gaseous and liquid batch i releases is' included in Table 7.1. 2.6 Abnormal Releases Abnormal releases are' defined as unplanned or uncontrolled releases of radioactive material from the site boundary. There were three abnormal gaseous effluent releases made during the period covered-by this' report. These events are deceribed in section 6.6.1.of this report. A summary of information for gaseous and liquid abnormal releases is included in Table 7.2. 3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 7.3 and 7.4. All releases -l' of radioactive material in gaseous form are~ considered to be ground level releases. l I 1 - ] n i

4.0-LIOUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 7.5 and 7.6. 5.0 SOLID WASTES The quantities of radioactive material released as ' solid effluents are summarized in Table 7.13. 6.0 RELATED INFORMATION 6.1 Operability of Licuid and Gaseous Monitorina Instrumentation ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 { require an explanation of why designated inoperable liquid and gaseous monitoring instrumentation was not restored to cperable status within thirty days. During the period covered by this

report, there were no instances where this instrumentation was inoperable for more than thirty days.

6.2 Chances to the Process Control Procram There were no changes to the Process Control Program for the period covered by this report. 6.3 Chances to the Offsite Dose Calculation Manual During the period covered by this report, there was one revision to the ODCM. In accordance with ODCM Administrative Control 6.14.c, this change:is submitted ] in the form of a complete copy of the entire ODCM..The ODCM, current as of December 31, 1992, is-contained in. Attachment 8.2. The major changes included in this l revision are summarized below: a. Revision 7a, effective Auaust 7. 1992 - l Two new 30,000 gallon Primary Effluent Tanks (PET) were added to the liquid waste processing system to increase the holdup capacity of processed liquid waste prior'to discharge. Sampling requirements for the PET's were added l to the Radioactive Liquid Waste Sampling and j Analysis Program Table 4.11-1. - _ - - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - _ - - _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ - _ _ - _ _ _ - _ _ _ - - -

6.4 New Locations for Dose Calculations or Environmental Monitorina ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations and/or environmental monitoring, identified by the Land Use Census, to be included in the Semiennual Radioactive Effluent Release Report. The 1992 Land Use Census, which will be included in the 1992 Annual Radiological Environmental Operating

Report, identified new receptor locations for dose calculations and eliminated one existing dairy monitoring station.

These changes were submitted as a revision to the ODCM Part II, Table 2.4 and Table 3.1 respectively. This revision to the ODCM has been submitted as Revision 8 but has not become effective during this reporting period. 6.5 Licuid Holdup and Gas Storace Tanks ODCM Administrative. Control 6.9.1.4 requires a description of the events leading to liquid holdup or gas storage tanks exceeding the Technical Specification limits. Technical Specification 3.11.1 limits the quantity of radioactive material contained in each unprotected outdoor tank to less than or equal to ten

curies, excluding tritium and dissolved or entrained noble gases. Technical Specification 3.11.2.2 limits the quantity of radioactive material contained in each gas storage tank to less than or equal to 200,000 curies of noble gases (considered as Xe-133 equivalent).

These limits were not exceeded during the period covered by this report. 6.6 Noncompliance with Radioloaical Effluent Contro_1 Reauirements This section provides a listing of events that did not comply with the applicable requirements of the Radiological Effluent Controls given in Part I of the CPSES ODCM. Detailed documentation concerning evaluations of these events and corrective actions is maintained onsite. 6.6.1 Abnormal Licuid and Gaseous Releases There were no abnormal liquid effluent releases resulting in release of radioactive material from the site boundary. s u:

Three separate gaseous abnormal permits were processed to document three separate unplanned releases of noble gases to the plant ventilation system. All three releases involved valve lineup operations to vent the pressurizer steam space to the volume control tank using the process sample system. The valve lineups were being performed _ in preparation for the degassing of the Reactor Coolant System. The events were all of short duration and were determined to be caused by a faulty pressure gauge indication and subsequent lifting of a pressure relief valve to relieve excess system pressure. The relief valve lifting caused the release of noble gases from the Reactor Coolant System to the plant ventilation system. Therefore, all three releases were monitored by the plant vent stack radiation monitors. The events were of short duration because the releases were terminated automatically when they had returned to normal pressure and the relief valve closed. The radioactivity released did not exceed any instantaneous dose rate limits or any cumulative dose limits. It should be noted that stack r.onitor high radiation alarms were received in all three events based on exceeding instantaneous default alarm setpoint values. The default alarm setpoints were based on the most conservative noble gas dose conversion factor given in the ODCM. Calculations performed based on the distribution of noble gas isotopes actually present showed that ODCM release rate and dose rate limits were not exceeded. The consequences of the releases are detailed below: a. On October 20,

1992, at approximately 09:40 the South Vent Stack monitors went into high alarm and recorded ' a 9.50E+3 yni/sec release rate with a concentration of 1.67E-4 pCi/ml noble gas.

The noted spike on the radiation monitors started I trending downward only minutes after the initial alarm. Release calculations that were performed after the latest noble gas j spectral data was obtained verified that i ! l

l 1 no limits were exceeded. The g:mma air dose was determined to be 3.87E-03 mrad and the beta air dose was determined to be 3.22E-03 mrad. The - relief valve lifLing was not noted during this event. b. On October 23,

1992, at approximately-07:05 the South Vent stack monitors went into high alarm and recorded a 2.79E+4 pCi/sec release rate with a concentration of 3.72E-4 pCi/ml noble gas.

The noted spike on the radiation monitors started trending downward only minutes after the initial alarm. Release calculations that were performed after the latest noble gas spectral data was obtained verified that no limits were exceeded. The gamma air dose was determined to be 8.75E-03 mrad and the beta air dose was determined to be 7.29E-03 mrad. The relief valve lifting was noticed at this time and the lineup was secured. Excessive gauge fluctuation was noted by the technician as well. c. On October 24,

1992, at approximately 16:02 the South Vent stack monitors went into high alarm and recorded a 1.87E+3 4Ci/sec release rate with a concentration of 5.73E-5 yCi/ml noble gas.

As soon as the relief valve lifted the valve lineup was secured and the release was terminated. Release calculations verified that no limits were exceeded. The gamma air dose was determined to be 5.14E-03 mrad and the beta air dose was determined to be 4.28E-03 mrad. The necessity to degas the Reactor Coolant System caused the following changes to be implemented in order to resolve the relief valve problem. A technical evaluation was performed and the method used was changed to lineup the pressurizer steam space to the Volume Control Tank without going through the process sampling system. A request for a Design Modification was submitted to connect the pressurizer steam space directly to the waste gas system. Procedure reviews were performed'and were determined to be adequate. -.

No - personnel-errors were involved. ' Work j requests were submitted on the pressure regulating

valve, the pressure _ gauge and relief valve to repair, replace or calibrate t

as required. i 6.6.2 Failure to Meet Specified Samolina Reauirements On July 27, 1992, at 07:00 it-was determined i e that the requirement to sample the: plant vent stacks at least once per 24 hours for at least 7 days following a reactor trip had not been accomplished on July 2 6, = 1992,'as required. The reactor trip occurred on July 20, 1992, at' 16:01 and daily samples were being;obtained. The sample due on July 26,

1992, was - not collected as required.

The samples were immediately obtained and no. abnormal conditions existed when analysis was performed. The event was classified as a Plant Incident and an evaluation was performed to determine the reasons, causes and failures contributing to the event. The' root'cause of the event was determined to be personnel error. Additionally, scheduling of chemistry personnel caused insufficient personnel 'on this crew. The sample requirement had : not been discussed in turnover meetings'and there was a lack of attention to detail. Corrective actions included rescheduling'of personnel to staff crews, increased turnover discussions between lead technicians ~and supervisors'and increased attention to the Shift Orders at-turnover. b On October 2, 1992, at 12:30 it was determined-e that an unmonitored potentially radioactive release pathway was created due to problems with water in the condenser off gas monitor and the sample vent line to the primary plant ventilation. This condition required venting of the monitor sample line directly into the Turbine Building instead of out the monitored vent stacks pathway. Immediate corrective actions were taken to expedite-the repairs and noble gas grab samples at the monitor vent point were initiated. ' At no time did the grab samples indicate any radioactivity. A release was not anticipated since secondary sampling has not indicated any primary-to-secondary i leakage. The grab samples continued until the - ] ; 'l l 1

monitor and vent line were repaired -and declared operable. Long term corrective actions included increasing ~the frequency of draining of the discharge header and submittal of a design modification request to increase l. the drain line size and install a constantly l draining loop seal drain. On November 25, 1992, at 14 :00 a Chemistry technician discovered that an auxiliary sample pump being used to satisfy continuous sample requirements of the inoperable South Vent Stack particulate, iodine and. noble gas monitor had blown a fuse. Since the South: Vent Stack monitor was inoperable the auxiliary sample' pump had been installed to provide 4 hour grab samples for Noble gases. and continuous sampling of particulates and iodines. The pump ad previously been running at 10:00 when thE last 4 hour grab sample was collected. Therefore the pump was off for less than 4 hours. The North Vent Stack ' monitoring was not affected by any of the conditions described above. The North Vent Stack was being continuously monitored. The samples taken before and after restoration'of the pump were all " normal" in noble gas activity. There was no particulate or iodine radioactivity measured during this time frame. - Dose. calculations were performed using ' both-North Vent Stack data and grab sample data:to account for the 4 hours of missed sampling. Corrective action was taken to replace - the t fuse and no further problems were encountered. I 6.7 Resin Releases to the LVW Pond 3 A total of 1037 ft of resin was transferred to:the LVW' pond during the period covered by this report. The resultr. of the sample analyses indicate no radioactive material was transferred to the pond. 6.8 Chances to the Liauid, Gaseous and Solid Waste Treatment Systems In accordance with the CPSES Process Control Program,- Section 2.2a, major changes to the Radwaste Treatment-Systems (liquid, gaseous and solid) shall be reported to the Commission in the Semiannual - Radioactive Effluent Release Report for the period in which changes:were reviewed by the SORC. _

l 'l I During this reporting period, one' design modification was implemented..1 contains a. summary of this modification as well.as summaries of applicable-evaluations and justifications supporting the modification. 6.9 Meteoroloaical Monitorina PIogram In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 1992, is retained onsite. This data is available for review by the NRC upon request. 6.10 Assessment of Doses 6.10.1 Doses Due to Liauid Effluents The doses to an adult from the fish and water consumption pathways from Squaw Creek Reservoir were calculated in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 7.7. 6.10.2 Doses Due to Gaseous Effluents The air dose due to' gamma-emissions and the air dose due to beta emissions were calculated using the highest annual average atmospheric dispersion factor at the Site Boundary location, in accordance with the methodology and parameters in the.ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 7.8. 6.10.3 Dose Due to Radiciodines. Tritium and Particulates The doses to an infant, child, teen and adult from radiciodines and particulates, for the pathways listed in Part II, Table 2.3 of the

ODCM, were calculated using the highest dispersion and.

deposition

factors, as appropriate, in accordance with the methodology and parameters in the ODCM.

The results of the calculations are summarized on a quartcrly and annual basis in Tables - 7.9 - through 7.12. _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _

6.10.4 40'CFR 190 Dose Evaluation ODCM Radiological Effluent Control 3.11.4 requires dose evaluations to demonstrate compliance with_40 CFR Part 190 only if the calculated quarterly or. yearly doses exceed two times the applicable quarterly or annual dose limits (see Sections 2.1.1, 2.2.2 and 2.2.3). At no time during 1992 were any of these limits

exceeded, therefore no evaluations are required.

l 6.10.5 Doses to a MEMBER OF THE PUBLIC From b_ctivities Inside the Site Boundary Three activities are considered in this evaluation: fishing on Squaw Creek-Lake, recreation activities at the CPSES employee recreational area and site tours through the CPSES Visitors Center. The highest dose occurred in the evaluation for fishing, resulting in a dose of 2.28E-2 mrem /yr. The dose to a MEMBER OF THE PUBLIC (fisherman) on Squaw Creek Lake was calculated based on fishing twice a week, five hours each day, six months per year. Pathways included' in the calculation were gaseous inhalation and submersion. Liquid pathways are not considered since all doses are calculated at j the point of cirewater discharge into the lake. The dose to a MEMBER OF THE PUBLIC engaged in recreational activities at the CPSES employee recreational park was calculated based on one visit a week, five hours each day, six months per year. Pathways included in-the calculation were gaseous inhalation, submersion and ground plane. The dose to a MEMBER OF THE PUBLIC during site l tours through the CPSES Visitors Center was I calculated based on two visits per year, thirty minutes each visit. Pathways included in the calculation were gaseous inhalation and submersion. All calculations were performed in accordance with the methodology and parameters in the ODCM. SECTION 7.0 TABLES 1 l l

g. Table 7.1 BATCH LIOUID AND' GASEOUS' RELEASE

SUMMARY

Ouarter 3 Ouarter 4 A. Liouid Releases All Sources Number of Batch Releases. 1.75E+02 1.44E+02 Total Time Period For Batch Releases (min) 1.2BE+04 1.50E+04 Maximum Time Period For a Batch Release (min) 8.00E+01 4.59E+02 l Average Time Period For a Batch Release (min) 7.30E+01 1.05E+02-l Minimum Time Period For A Batch Release (min) 2.90E+01 2.10E+01 3 Average Stream Flow During Periods of Release (ft /s) N/A N/A -{ B. Gaseous Releases All Sources l i Number of Batch Releases 1.90E+01 9.00E+00 Total Time Period For Batch Releases (min) 5.34E+03 4.26E+03 Maximum Time Period For A Batch Release (min) 3.77E+02 1.92E+03 Average Time Period For A Batch Release (min) 2.81E+02 4.73E+02 Minimum Time Period For A Batch Release (min) 1.19E+02' 1.77E+02 i l TABLE 7.2 l ABNORMAL BATCH LIOUID AND GASEOUS RELEASE

SUMMARY

Ouarter 3 Ouarter 4 J A. Liauids Number of Releases 0.00E+00 0.00E+00 Total Activity Released, ci 0.00E+00 0.00E+00 ') B. Gases i Number of Releases 0.00E+00 ~3.00E+00 1 Total Activity Released, ci 0.00E+00 7.04E+01-3 l T-1

TABLE 7.3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total 3 4 Error, % 1' } A. Fission and Activation Gases

1. Total release Ci 6.11E+02 7.12E+02 2.35E+01
2. Average release rate for pCi/sec 7.68E+01 8.96E+01 period
3. Percent of ODCM REC limit t

4.38E-02 3.54E-02 (Total Body Dose Rate) l 4. Percent of ODCM REC limit 1.02E-02 1.16E-02 (Skin Dose Rate) B. Iodines

1. Total Iodine-131 Ci 4.02E-04 2.82E-04 1.43E+01
2. Average release rate for pCi/sec 5.06E-05 3.55E-05 period
3. Percent of ODCM REC limit t

5.94E-02 4.17E-02 (Organ Dose Rate) C. Particulates

1. Particulates with half lives Ci 0.00E+00 0.00E+00 N/A

> 8 days

2. Average release rate for pCi/sec 0.00E+00 0.00E+00 period
3. Percent of ODCM REC limit t

0.00E+00 0.00E+00 (Organ Dose Rate)

4. Cross alpha radioactivity Ci 0.00E+00 0.00E+00 D. Tritium
1. Total release ci 8.78E-01 2.94E-01 2.3BE+01
2. Average release rate for pCi/sec 1.10E-01 3.70E-02 period
3. Percent of ODCM REC limit 6.26E-04 2.10E-04 (Organ Dose Rate)

T-2

f TABLE 7.4 1 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES ) t Continuous Mode Batch Mode 'l 2 Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 1. Fission and Activation Gases t Ar-41 Ci 0.00E+00 0.00E+00 5.24E-02 3.98E-01 Kr-85M Ci O.00R+00 0.00E+00 0.00E+00 2.65E+00 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 2.96E+00 Kr-88 Ci 1.59E+01 0.00E+00 0.00E+00 5.52E+00 Xe-131M Ci 0.00E+00 0.00E+00 3.27E-03 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 1.04E+00 Xe-133 Ci 5.44E+02 6.01E+02 1.35E+00 6.19E+01 i t Xe-135M Ci 0.00E+00 0.00E+00 0.00E+00 9.72E-01 Xe-135 C1 4.92E+01 1.92E+01 1.40E-02 1.44E+01' l Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 1.64E+00 Total for period C1 6.09E+02 6.20E+02 1.42E+00 9.15E+01 2. Iodines I-131 Ci 3.95E-04 2.81E-04 6.95E 8.76E-07 I-133 Ci 0.00E+00 0.00E+00 2.80E-07 3.97E-08 i Total for period C1 3.95E-04 2.81E-04 7.23E-06 9.16E-07 i

3. Particulates

{ H-3 Ci 8.77E-01 2.87E-01 1.09E-03 7.76E-03 Rb-88 (Note 1) Ci 0.00E+00 0.00E+00 1.35E-06 0.00E+00 Br-82 (Note 1) CL O.00E+00 0.00E+00 3.72E-07 0.00E+00 Total for period Ci 8.77E-01 2.87E-01 1.09E-03 7.76E-03 Note la Since the half life of these nuclides are less than eight days, the amount released in gaseous effluents is not reported in Table 7.3, item C. For the same reason, these nuclides are not considered in dose calculations. j T-3 l i

-i TABLE 7.5 LIOUID EFFLUENTS--SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total f 3 4 Error, % A. Fission and Activation Products

1. Total release (not including Ci 4.00E-02 1.15E-01 3.03E+01 tritium, gases, alpha)
2. Average diluted yCi/ml 6.25E-10 2.68E-09 concentration during period l
3. Percent of ODCM REC limit 2.95E-02 3.22E-02 B. Tritium 4

e

1. Total release C1 2.39E+02 2.17E+02 1.34E+01

{

2. Average diluted pCi/ml 3.74E-06 5.08E-06 concentration during period i

J

3. Percent of ODCM REC limit 1.25Ee01 1.69E-01 l

C. Dissolved and Entrained Gases

1. Total release ci 9.32E-01 3.30E+00 1.16E+01
2. Average diluted pCi/ml 1.46E-08 7.71E-08 1

concentration during period l

3. Percent of ODCM REC limit 7.28E-03 3.86E-02 D. Gross Alpha Radioactivity
1. Total release C1 0.00E+00 0.00E+00 0.00E+00 E. Volume of waste released Liters 6.87E+06 3.50E+06 2.20E+00 (prior to dilution)

F. Volume dilution of water Liters 6.40E+10 4.28E+10 1.00E+01 used during period (Note 1) Note 1: The dilution volume reported is the total dilution volume during periods when effluent releases were occurring. The additional dilution volume available when there are no effluent releases occurring is not included. T-4

"s l 4YE73 4*9 TIOGIG 3ddI'n3NIS oouayunons wopa ge2oy wopa i gnoITpes uatassap nut 2s one22a2 one22a2 cne22a2 onn22a2 E t C H-E OT O'003+00 O'003+00 c'E63+04 E'IL3+OE l NE-CP 01 O'003+00 O'003+00 O'003+00 8'EP3-05 DJ-SI OT O'003+00 O'003+00 O'003+00 I'653-04 Hu-SP DT O'003+00 O'003+00 E'703-OP E'OC3-OP 30-55 01 O'003+00 O'003+00 I'843-OE ?'II3-OE i ~~ aG-SL 01 O'003+00 O'003+00 I'I53-09 I IP3-OP 3G-58 01 O'003+00 O'003+00 5"963-00 ?'LE3-OE 46-56 01 O'003+00 O'003+00 O'003+00 E'653-OE 00-90 01 O'003+00 O'003+00 8'CI3-07 t'653-OE sa-LS al O'003+00 O'003+00 O'003+00 E'603-OP 44-88 01 O'003+00 0 003+00 8'5E3-05 E'9P3-05 ZJ-65 01 O'003+00 O'003+00 E'903-05 I'PP3-OP N9-65 01 O'003+00 O'003+00 I'L43-OP E'L03-OP HG-66 01 O 003+00 O'003+00 I'6P3-05 S'003-05 as-66H 01 O'003+00 O'003+00 . '4E3-05 t'8L3-05 SU-ILE 01 O'003+00 O'003+00 I'653-09 L'483-09 Iu-ILEH 01 O'003+00 O'003+00 E'LL3-09 6'EL3-09 Su-LLLH 01 O'003+00 O'003+00 O'003t00 E'E63-09 59-icc 01 O'003+00 O'003+00 O'003t00 S'E03-OP sq-LGP OT O'003+00 O'003t00 O'003+00 L'Lca-OE sq-LCS OT O'003+00 O'003+00 E'593-05 C'063-OE 54-L49 RT O'003+00 O'003+00 O'003+00 I'503-OP 59-LCL aT 0 003+00 O'003+00 O'003+00 .I'093-05 I-EEL 01 O'003+00 O'003+00 S'643-OE E'563-OE I-IEE OT O'003+00 O'003+00 I'P83-OP ?'P63-05 as-IEP OT O'003+00 O'003+00 9'E93-OE E ' P 63T as-EE9 01 O'003+00 O'003+00 E'543-OP I'493-09 as-LEL DI O'003+00 O'003+00 E'E03-OE ?'P43-OP as-LE8 01 O'003+00 O'003+00 O'003+00 E'L43-05 IW-LPO 01 O'003+00 O"003+00 L EE3-05 E'403-OP I'w-L P L 01 O'003+00 O'003+00 O'003+00 L 853-OP 4c3eI ;oJ daaloP a1 O'003+00 O'003+00 4'E63+04 d'I43+04 L.- 9

h TABLE 7.6 (Continued) i LIOUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 t 1 I Kr-85 ci 0.00E+00 0.00E+00 6.23E-03 5.91E-03 Kr-85M ci 0.00E+00 0.00E+00 7.47E-05 3.94E-05 j i Kr-88 ci 0.00E+00 0.00E+00 2.41E-05 5.20E-06 Xe-131M c1 0.00E+00 0.00E+00 1.9BE-02 4.72E-02 Ye-133 c1 0.00E+00 0.00E+00 9.01E-01 3.23E+00 f Yo-133M Ci 0.00E400 0.00E+00 4.66E-03 1.83E-02 Xe-135 ci 0.00E+00 0.00E+00 1.99E-04 1.22E-03 Total __.for eeriod ci O_.QQE+0A

0. 00I1QQ__1 J2E-01 3.30E+00 TABLE 7.7 DOSES FROM LIOUID EFFLUENTS (mrem.).

l Organ Bone Liver Whole Thyroid Kidney ' Lung GI-LLI Body guarter 1 1.19E-03 6.59E-02 6.53E-02 6.49E-02 6.49E-02 6.54E-02 7.69E-02 % Limit 2.38E-02 1.32E+00 4.35E+00 1.30E+00 1.30E+00 1.31E+00 1.54E+00 Quarter 2 1.44E-02 8.00E-02 7.33E-02 5.88E-02 6.34E-02 5.83E-02 5.70E-02 % Limit 2.88E-01 1.60E+00 4.89E400 1.18E+00 1.27E+00 1.17E+00 1.14E+00 Quarter 3 2.13E-02 1.06E-01 9.61E-02 7.35E-02 8.05E-02 7.22E-02 6.96E-02 % Limit 4.26E-03 2.12E+00 6.41E+00 1.47E400 1.61E+00 1.44E+00 1.19E+00 Quarter 4 2.12E-03 8.40E-02 8.31E-02 8.62E-02 8.15E-02 8.41E-02 8.65E-02 O Limit 4.24E-02 1.6BE+00 5.54E400 1.72E+00 1.63E+00 1.68E+00 1.73E+00 Total 3.90E-02 3.36E-01 3.18E-01 2.83E-01 2.90E-01 2.80E-01 2.90E-01 1992 .6 % Limit 3.90E-01 3.36E+00 1.06E+01 2.83E+00 2.90E+00 2.80E400 2.90E+00 I T-6 'I

._z-TABLE 7.8 DOSES FROM GASEOUS EFFLUENTS Noble Gas Air Dose (mrad) Air Dose (mrad) Gamma Air Beta Air Quarter 1 3.43E-03 1.83E-02 Percent Limit 6.86E-02 1.83E-01 Quarter 2 4.95E-03 4.73E-02 I Percent Limit d.90E-02 4.73E-01 Quarter 3 5.53E 7.75E-02 Percent Limit 1.11E>00 7.75E-01 Quarter 4 4.46E-02, 8.81E-02 Percent Limit 8.92E-01 8.81E-01 Total 1992 1.0BE 01 2.31E-01 Percent Limit 1.08E+00 1.16E+00 6 4 s 3 3 ? f 5 T-7

i i l. TABLE 7.9 DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Adult Age Group, (mrem) t Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin I Body Qtr-1 1.80E-07 1.44E-04 1.44E-04 2.26E-04 1.45E-04 1.44E-04 1.44E-04 4.92E-09 2.40E-06 1.92E-03 1.92E-03 3.03E-03 1.93E-03 1.92E-03 1.92E-03' 6.56E-08 Limit 9tr-2 2.66E-05 5.44E-04 5.2HE-04 1.27E-02 5.71E-04 5.07E-04 5.17E-04 7.26E, 3.55E-04 7.25E-03 7.04E-03 1.69E-01 7.61E-03 3.80E-05 6.89E-03 9.68E-06 Limit Qtr-3 7.33E-05 4.13E-04 3.69E-04 3.39E-02 4.86E-04 3.10E-04 3.37E-04 2.00E-06 9.77E-04 5.51E-03 4.92E-03 4.52E-01 6.48E-03 4.13E-03 4.49E-03 '2. 67E-05 Limit Ote-4 5.14E-05 1.77E-04 1.46E-04 2.37E-02 2.28E-04 1.05E-04 1.24E-04 1.40E-06 6.85E-04 2.36E-03 1.95E-03 3.16E-01 3.04E-03 1.40E-03 1.65E-03 1.87E-05 Limit Total 1.51E-04 1.28E-03 1.19E-03 7.05E-02 1.43E-03 1.07E-03 1.12E-03 4.13E-06 1992 1.01E-03 8.53E-03 7.93E-03 4.70E-01 9.53E-03 7.13E-03 7.48E-03 2.75E-05 Limit I P e i T-8 l b

TABLE 7.10 ) DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Teen Age Group, (mrem) t Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body j Qtr-1 3.03E-07 1.66E-04 1.66E-04 2.88E-04 1.66E-04 1.66E-04 1.66E-04 4.92E-09 4.04E-06 2.21E-03 2.21E-03 3.84E-03 2.21E-03 2.21E-03 2.21E-03 6.56E-08 [ Limit Qtr-2 4.50E-05 6.44E-04 6.16E-04 1.87E-02 6.89E-04 5.82E-04~ 5.95E-04 7.26E-07' 6.00E-04 8.59E-03 8.21E-03 2.49E-01 9.19E-03 7.76E-03 7.93E-03 9.68E-06 Limit Otr-3 1.24E-04 5.27E-04 4.48E-04 5.02E-02 6.51E-04 3.56E-04 3.90E-04' 2.00E-06 1.65E-03 7.03E-03 5.97E-03 6.09E-01 8.68E-03 4.75E-03 5.20E-03 2.67E-05 Limit Qte-4 8.68E-05 2.40E-04 1.85E-04 3.51E-02 3.27E-04 1.20E-04 1.44E-04 1.40E-06 1.16E-03 3.20E-03 2.47E-03 4.68E-01 4.36E-03 1.60E-03 1.92E-03 1.87E-05 Limit Total 2.56E-04 1.58E-03 1.42E-03 1.04E-02 1.83E-03 1.22E-03 1.30E-03 4.13E-06 1992 1.71E-03 1.05E-02 9.47E-03 6.95E-01 1.22E-02 8.16E-03 8.67E-03 2.75E-05 Limit i 'i i i 3 l I T-9 l 1 i

k. TABLE 7.11 i DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Child Age Group, (mrem) Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin i Body 9tr-1 7.19E-07 2.38E-04 2.38E-04 4.74E-04 2.38E-04 2.37E-04 2.37E-04 4.92E-09 7.59E-06 3.17E-03 3.17E-03 6.32E-03 3.17E-03 3.16E-03 3.16E-03 6 56t.'8 Limit Otr-2 1.07E-04 9.40E-04 8.95E-04 3.60E-02 1.01E-03 8.34E-b. 8.44E-04 7.!hE-L1 1.43E-03 1.25E-02 1.19E-02 4.80E-01 1.35E-02 1.11E-02 1.13E-02 9.68E-06 Limit Qte-3 2.93E-04 8.02E-04 6.76E-04 9.72E-02 9.90E-04 5.10E-04 5.36E-04 ".00E-06 3.91E-03 1.07E-02 9.01E-03 1.30E+00 1.32E-02 6.80E-03 7.15E-03 2.67E-05 Limit 9tr-4 2.06E-04 3.77E-04 2.88E-04 6.80E-02 5.09E-04 1.72E-04 1.90E-04 1.40E-06 0 2.75E-03 5.03E-03 3.84E-03 9.07E-01 6.79E-03 2.29E-03 2.53E-03 1.87E-05 l Limit 1 Total 6.07E-04 2.36E-03 2.10E-03 2.02E-01 2.75E-03 1.75E-03 1.81E-03 4.13E-06 j 1992 4.04E-03 1.57E-02 1.40E-02 1.35E+00 1.83E-02 1.17E-02 1.20E-02 2.75E-05 Limit i i T-10

TABLE 7.12 l DOSES FROM GASEOUS EFFLUENTS Iodines, Particulates and Tritium Infant Age Group, (mrem) Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body Qtr-1 1.41E-06 1.86E-04 1.85E-04 7.29E-04 1.86E-04 1.84E-04 1.84E-04 4.92E-09 1.88E-05 2.48E-03 2.47E-03 9.72E-03 2.4BE-03 2.45E-03 2.45E-03 6.68E-08 Limit Qtr-2 2.09E-04 8.94E-04 7.56E-04 8.15E-02 9.35E-04 6.48E-04 6.57E-04 7.26E-37 2.79E-03 1.19E-02 1.01E-02 1.09E+00 1.25E-02 8.64E-03 8.76E-03' 9.68E-06 Limit Otr-3 5.75E-04 1.07E-03 6.93E-04 2.23E-01 1.19E-03 '3.97E-04 4.21E-04 2.00E-06 7.67E-03 1.43E-02

  • 9.24E-03 2.97E+00 1.59E-02 5.29E-03 5.61E-03 2.67E-05 Limit Otz-4 4.03E-04 6.07E-04 3.42E-04 1.56E-01 6.88E-04 1.34E-04 1.51E-04 1.40E-06 5.37E-03 8.09E-03 4.56E-03 2.08E+00 9.17E-03 1.79E-03 2.01E-03 1.87E-05 Limit Total-1.19E-03 2.76E-03 1.98E-03 4.61E-01 2.99E-03 1.36E-03 1.41E-03 4.13E-06 1992 0

7.92E-03 1.84E-02 1.32E-02 3.07E+00 1.99E-02 9.09E-03 9.42E-03. 2.75E-05 Limit i 9 T-11

TABLE 7.13 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped offsite for Burial or Disposal (Not Irradiated Fuel)

1. Type of waste Unit 6-month Est. Total Period

% Error i

a. rpent resins / filters m'

20.19 10.0 C1 118.97 b. Dry compressible waste, contaminated m' 65.63 10.0 equip., etc. C1 1.195 c. Irradiated components, control rods, m' None N/A etc. Ci N/A d. Other (oil which was incinerated by m' N/A 10.0 processor) C1 2.86E-3 Note: There were no solidification agents or absorbents applied to the solid waste.

2. Estimate of Major Nuclide Nuclide

% Abund. Activity Composition (by type of waste) (C1) a. Spent resins / filters co-60 66.46 79.07 Mn-54 9.03 10.74 Co-58 7.20 8.56 H-3 4.87 5.79 C-14 4.77 5.67 Cs-137 3.17 3.78 Cs-134 2.41 2.86 Others 2.44 2.90 Totals 100% 118.97

b. Dry compressible waste, Fe-55 54.09 6.46E-01 contaminated equipment, etc.

Co-58 17.04 2.04E-02 Co-60 13.97 1.67E-02 Mn-54 3.62 4.32E-03 Ni-63 3.55 4.24E-03 Cr-51 2.38 2.85E-03 Nb-95 2.04 2.44E-03 O hers 3 75 3.89E-03 l Totals 100% 1.195E+0

d. Other (oil which was incinerated H-3 94.55 2.71E-03 by processor)

Fe-55 4.30 1.23E-04 Co-60 _M 3.37E-05 Totals 100% 2.86E-03 T-12

TABLE 7.13 (Continued) SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 3. Solid Waste Disposition Waste Number of DOT Type of Transportation Shipped Burial Class shipments Type container Mode To Site Au 13 LSA Strong-Truck ALARON/ Barnwell tight SEG /Beatty Au 1 LSA Strong-Truck Quad-Barrwell tight rex: As 4 A LSA Poly-PtC Truck Barn-Barnwoll well C 1 >A Poly-H'O iruck Barn-Barnwell LSA well Note: 1. Quantity and activity of DAW was processed and buried by Vendor. 2. Limited quantity - green bag material. B. Irradiated Fuel Shipments Number of Shipmento Transportation Method Destination 0 N/A N/A 77 T-13 4 9

a t i i .l ATTACHMENT 8.1 1 f a Summary of the " Relocation of the 3 I Filter /Demineralizer and.. Resin: Dewatering Skids" Modification j l

I Summary of the Relocation of the Filter /Demineralizer and Resin Dewaterina Skids (CPSES Design Modification No. DM-90-507) 1. Modification Summarv i This Filter /Demineralizer (FDS) and Resin Dewatering Skids modification involved the following changes: a. Provided air, water and electrical services to support the relocation of the FDS and resin dewatering skid into-the Fuel Building, 802' elevation,. barrel pit. b. Installed a concrete pad, swing arm and chainfall for two ,t new " Rad vaults" to be installed permanently in. ' the barrel pit along with the hard piped drains to the floor drain system. c. Removed the FDS from the Hot Machine Shop area'of the' Fuel Building, 810' elevation, where it was previously-installed, to free up needed space in the hot machine shop area. d. Allows for resin transfers and dewatering of resin HIC's to be performed in the barrel pit instead of the Fuel Building, 810' elevation, train bay. This relocation alleviates work restraints in the train bay during resin dewatering evolutions. 2. Modification Justification a. The relocation of the FDS system into the barrel pit frees up the area of the Hot Machine Shop so itican be used by Maintenance personnel without interference during. ) I resin transfers or FDS media replacement. i b. The installation of the two new Rad vaults allows for resin transfers and dewatering at any time so that other evolutions may continue in the_ train bay. ~ q c. Replacement of the FDS media can be performed at any time - j without interfering with the evolutions occurring in the-train bay and hot machine shop area. j d. Dewatering of resins prior to shipment can now be done in the barrel pit with hard piped drain lines to the floor l drain system instead.of hoses. ) e. Manpower required to set up and take down resin fill and dewatering equipment will be reduced. 1 A-1 i a

3. Descrintion of Eauipment. Comoonents and Processes Involved and Interfaces With Other Systems l I The interfaces that are involved with this modification are no different than they were previously. All resin sluice lines and liquid waste processing lines have remained the same as far as interfaces are concerned. All resin handling and liquid processing remains the same but the location for performing these evolutions has changed. 4. Safety Evaluqtion Summary This modification was evaluated pursuant to the-requirements of 10CFR50.59. This safety evaluation (CPSEO Safety Evaluation No. SE-92-122) is summarized below: The barrel pit is a Safe Zone and the installation of the Rad vaults and skids is therefore acceptable. The effect of the weight of the vaults and skids on the floor was analyzed and ~ found acceptable. All new piping, ducts and. conduit is.non-safety related and mounted Seismic Category. II. . The processing of spent resins is enhanced since the train-bay 4111 no longer be required for this activity. No new credible. t railure modes for any of the interfacing plant systems are introduced and there is no potential for any impact on the safety function of any plant structure, system or component, therefore this modification does not constitute an unreviewed safety question. 5. Chances to Predicted Licuid and Gaseous Effluent Releases and Ouantity of Solid Wastes This modification does'not impact the predicted releases of radioactive materials in liquid and gaseous effluents given in Sections 11.2 and 11.3, respectively, of the CPSES ' Safety Analysis Report (SAR) or Section 11.4 for quantities of solid waste. 6. Evaluation of Chances to Previousiv Estinated Exposures to'a Member of the Public and to the General Population + This modification does not impact.the predicted release of radioactive materials as noted in. item 5 above, therefore calculations were not performed to change predicted values in. Section 11A of the CPSES SAR. i f A-2 t

7. Comparison of the Predicted Releases of Radioactive Material for this Chance to the Actual Releases for the Period Prior to When the Chance is Made This modification does not impact the predicted release of. radioactive materials as'noted in item 5 above,- therefore a comparison to the actual releases for the prior period to when the change will-be made is not applicable. 8. Estimate of Exposure to Plant Operatina Personnel as a Result of the Chance This modification was designed to provide better utilization-of space within the hot shop and train bay areas of the Fuel Building. This -will enhance. the work scheduling and performance of personnel by not allowing resin operations to influence other jobs. There should not be any significant change in personnel exposure as a result of this modification. In fact exposures are anticipated to decrease somewhat, since these operations are now conducted in a secluded area and provided with more elaborate shielding which will reduce I exposures to personnel working in adjacent areas. 1 9. Station Operations Review Committee This modification was reviewed and found acceptable by the CPSES Station Operations Review Committee (SORC) at SORC Heeting No. 92-087 held on 26 August 1992. A-3 _ _ _ _. _-_____:__}}

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