ML19329C598
| ML19329C598 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/12/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19329C597 | List: |
| References | |
| NUDOCS 8002180116 | |
| Download: ML19329C598 (14) | |
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SAFETY EVAI.UATION RETORT FOR DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 Docket No. 50-346 11.0 Radioactive Waste Management 11.1 Summary Description The radioactive waste management systems are designed to provide for the controlled handling and treatment of liquid, gaseous, and solid wastes.
Since the Construction Permit was issued, the applicant has modified the radwaste system to reduce radioactive releases to levels which will meet our "as low as practicable" guidelines. These modifications include installation of an evaporator distillate polishing demineralizer in the liquid radwaste system, charcoal filters in the gaseous radwaste and containment purge systems, and a solidification system. The design criteria of the liquid, gaseous, and solid radwaste system components have also been upgraded. The liquid waste system processes liquid waste streams such as reactor coolant letdown, equipment and floor drainc, leakage from equipment, condensate deminerali=er backwash wastes, decontamination and laboratory waste liquids, and laundry and shower waste water. The treated liquid waste is recycled for reuse if the reactor coolant balance requires makeup and if the water quality is adequate.
The liquid vaste system processes waste liquid utili=ing evaporation, dcmineralization, and filtration for removal of radioactive material, chemical impurities, and particulates.
Gaseous wastes are generated during the operation of the plant from degassing of primary coolaat f roa displace:.. eat ;: 1 quid storc;2 8 0 0 218 0 lId"
e 2-tank cover gases, from the main steam condenser air ejector, from venting of equipment handling radioactive caterials, and from leakage of systems and co=ponents containing radioactive material.
The gaseous waste system removes radioactive materials from gaseous streams by filtration, and holdup for radioactivity decay. The treated gas streams are released to the environment through the station vent.
Solid wastes are generated during plant operation and consist of radioactive material from liquid waste evaporator concentrates,.
spent resins, spent filter cartridges and contaminated items such as clothing, equipment, and tools. Treatment consists of solidifi-cation of wet solid wastes and compaction of dry solid wastes.
Disposal consists of packaging and shipping to a licensed burial site.
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s The design objectives for the Davis-Besse Nuclear Power Station, Unit 1 are to meet the requirements of "as low as practicable" in 10 CFR Part 20, and 10 CF" Part 50.
Based on our evaluation 4
of the systems and its modifications, we find that the liquid, gaseous, rnd solid radwaste systems meet our "as low as practicable" guidelines and are acceptable.
11.2 Liquid Uaste Summary 11.2.1 Description and Evaluation The modified liquid radioactive waste systems are described in the i
r'.n21 Statement for the operatir; li:ense stage (r:S-3L).
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to the publication of the Safety Evaluation Report for the construction permit (SER-CP), the system was modified to include an evaporator condensate domineralizer in the Miscellaneous Liquid Radioactive Waste portion of the liquid radwaste system.
The demineralizer will be a nixed bed resin type with a 40 gym design i
flow and a 14 cu.ft. resin volume.
1 The design critetia of major processing equipment in the i'
liquid raduaste system was upgraded to AS'T Section III, Class III,
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standards which more than meet the guidulines of Branch Technical Position ETSB 11-1, " Design Guidance for Radioactive Waste Management Systems Installed in Light-Uater-Cooled Nuclear Power Plants",
i The addition of the demineralizer was considered in the FES-OL Tl
'and was included in that evaluation. We calculated that approximately
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0.13 Ci/yr excluding tritium and dissolved gases will be released from the modified liquid radioactive waste systems to the i
environment. To compensate for anticipated operational occurrences l
and equipment downtime, we normalized this value to 0.3 C1/yr.
We estimate the average annual release of tritium will be 350 Ci based
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on data for operating pressurized unter reactors. The applicant j
E estimates that 0.45 Ci/yr excluding tritium and dissolved gases, p
1 and 346 C1/yr of tritium will be released from the system.
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Based on our evaluation of radioactive materials in liquid effluent.
we calculate that the *.: hole body and critical organ doscs will bc e
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less than 5 mrem /yr at or beyond the site boundary, and that the system will be capable of limiting the release of radioactive materials in liquid effluents to 1 css than 5 Ci/yr/ unit.
We have reviewed the effects of reactor operation with 1" of the operating fission product inventory in the core being released to the primary coolant. We have determined, under these conditions, the concentrations of radioactive materials in liquid effluents will be a small fraction of the limits in 10 CFR Part 20, Tabic 2, Column II.
.2 Findings _
The liquid rad:?nste cyctem includes the equipeent and inctrurentation to control the release of radioactive materials'in liquid effluents.
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The scope of our review includad the system's capability to reduce l
releases of radioactive materials in 'iquid effluents to "as low ac practicable" Icvels in accordance with 10 CFR Parts 20 and 50.36a, considering normal operation and anticipated operational occurrencer.
and the design provisions incorporcred to preclude uncontrolled releases of radioactive materials in liquids due to leakage or overflows in accordance with General Design Criterion 60 and the quality group classification and seismic design criteria in conformance with the guidelines of BTP ETSB 11-1.
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The review has included an evaluation effluent releases based on the nndifiad system.
In:1ud:d in the revieu ::cre piping.:n: in trum.:nt:.t..m 1
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' diagrams, schematic diagrams, and descriptive information from the FSAR.
The basis for acceptance in our review has been conformance of
.the applicant's design, design criteria, and design bases for the liquid radwaste system to the Commission's Regulations and to applicable Regulatory Guides, as referenced above, as well as staff technical positions and industry standards.
Based on the foregoing evaluation, we conclude that the proposed modified liquid radwaste system is acceptable.
11.3 Gascous 1.'aste 11.3.1 Description and Evaluation The modified gaseous radioactive waste system and building ventilation systems s're described in the FES-OL.
The applicant in the FSAR issued subsequent to the SER-CP, proposed modifications to the gaseous radwaste system to include a charcoal filter downstream of the waste gas decay tanks. The charcoal filter will be of the deep bed type, with a 10-inch (24 cm) depth and a 50 cfm flow rate. The Emergency Ventilation System (EVS) was also codified to permit the flow of containment building purge system air through the EVS charcoal filters during normal plant operation.
In addition, the components in the gaseous waste system which delay or filter orocess gas will be designed to ASME III, Class III standards uhich more than caet se guidelines of Lranch Technical
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i Positign, ETSB 11-1.
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The modifications to the systems were considered in the FES-OL f
t and were included in that evaluation.
In the evaluation, we cal
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culated that approximately 3345 C1/yr of noble gases and 0.074 i
i Ci/yr of I-131 will be released,from the modified gaseous radwaste
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1 system to the environment. The applicant estimated that 4550 Ci/yr of noble gases and 0.119 Ci/yr of I-131 will be released from the system.
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Based on our evaluation of the modified gaseous was.te system we i
calculate that the annual air dose due to gamma radiation at or j
beyond the site boundary should not exceed 10 mrads, the annual air dose due to beta radiation at or beyond the site boundaly should not exceed 20 mrads, the annual thyroid dose to an indicidual should 4
not exceed 15 mrces by all considered pathways, and the annual total 4
j quantity of iodine-131 released will not exceed 1 C1.
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l We have reviewed the effects of reactor operation with 1% of the I
operating fission product inventory in the core being released to the primary coolant. We have determined, under these conditions, 1
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be a small fraction of the limits in 10 CFR Part 20, Table 2, Column II.
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1 11.3.2 Caseous Radwaste System Evaluation Findines j
1 The gaseous radwaste system includes the equipment and instrumer:ation i
to control the release of radioactive materials in gaseous effluents.
l The scope of our review included the system's capability to 1
i reduce releases of radioactive materials in gaseous effluents to "as low as practicable" levels in accordance with 10 CFR Parts 20 i
and 50.36a considering normal operation and anticipated operational i
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occurrences and the quality group and seismic design criteria.
The review has included an evaluation of effluent releases based on the
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modified treatment processes and considering pathways due to process vents and leakage affecting building ventilation systems.
Included in the review were piping and instrumentation diagrams, schematic diagrams, and descriptive information from the FSAR.
4 The basis for acceptance in our review has been conformance of the applicant's designs, design criteria, and design bases for the gaseous waste system to the applicable Commission Reguictions and Regulatory Guides referenced above, as well as to staff technical positions and industry standards.
't Based on the foregoing evaluation, we conclude that the proposed j
modified gaseous radwaste system is acceptable.
11.4 Solid Easte System 11.4.1 Descriptf.on and Evaluation i
The solid waste system is designed to collect monitor, process.
package, and provide temporary storage for radioactive solid vaste l
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j prior to offsite shipment for disposal in accordance with l
1 applicable regulations.
l Radioactive solid wastes resulting from operation of the plant l
include concentrates from the radwaste evaporators, spent resins, i
spent filter cartridges, and contaminated dry waste such as disposable filters, clothing, equipment, and tools.
The original solid radwaste system has been modified to use a solidification system in which the evaporator concentrates, spent resins and high activity filter cartridges will be mised with the solidifying agent, loaded 3
in 50 ft cask liners, and stored prior to shipment. Low activity filter cartridges will be loaded in'to 55 gal. drums.
Dry wastes will be compacted into 55 gal, drums and stored for shipment. The high radioactivity level drums will be handled by use of remote I
handling equipment.
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l The equipment in the solid waste system which handle liquid wastes will be designed to AS!2 III, Class III standards which more than meet the guidelines of Branch Technical Position ETSB 11-1.
1 In our evaluation, we estimated annual disposal based on the oper-f, i
experience of similar plants will be 235 drums of high icvel waste i
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and 600 drums of dry compacted waste. The total activity after 180 i
r days decay was estimated to be 2500 curies per year.
Based on operating experience at otherplants and the capacity of the dru= ming station, the applicant estimated 500 drums of high icvel.md e
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. 3 end 150 drums of low level waste (4800 ft ) will be shipped annually to a licensed burial ground. All solid waste will be packaged and shipped in conformance with 11 applicable AEC and DOT regulations.
11.4.2 Solid Raduaste System Evaluation Findines The solid radwaste system includes the equipment and instrumentation for solidifying and packaging radioactive wastes prior to shipment offsite for burial. The review has included an evaluation of the modified system's capability for processing the types and volumes of wastes expected during normal operation and anticipated operational occurrences in accordance with Cencral Design Criterion 60, the quality group design criteria, and the provisions for handling wastes with regard to the requirements of 10 CFR Parts 20 and 71, and 40 CFR Parts 170-189.
Included in the review were piping and instrumentation diagrams, schematic diagrams, and descriptive information from the FSAR.
The basis for acceptance in our review is conformance of the appli-cant's designs, design criteria, and design bases for the solid radwaste system to the Coumission's Regulations and the applicable Regulatory Guides, as referenced above, as well as staff technical j
positions and industry standards.
Based on the foregoing evaluation, we conclude that the proposed solid raduaste system is acceptable.
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11.5 Process and Ef fluent Monitoring 11.5.1 Description and Evaluation In our evaluation of the process and effluent =onitoring system we have considered the system's capability 1) to monitor all normal and potential pathuays for release of radioactive materials to the environment, 2) to control the release of radioactive materials to the environment, and 3) to monitor the performance of process equipment and detect radioactive material leakage between systems.
The process and effluents radiological monitoring system will be designed to provide information concerning radioactivity levels in systems throughout the plant, indicate radioactive leahage between systems, monitor equipment performance, and monitor and control radioactivity 1cvels in plant discharges to the environs.
Scintil'[tiondetectorswillbeusedformonitoringliquidsand for monitoring radioactive gescs and particulates in vent effluents.
Gaseous iodine vill be collected in replaccable, impregncted charcoal adsorbers which will be continuously monitored while in use by scintillation detectors.
Systems which are not amenabic to contin-uous monitoring or for which detailed isotopic analyses are required will be periodically sampled and analyzed in the plant laboratory.
Table 11.5-1 indicates the proposed locations and types of continuous monitors. Monitors on effluent release lines will automatically terminate discharges should r '.i..tlen icv 21s exce:d a prehtamin i.
value.
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1 We have reviewed the locations and types of effluent and process monitoring provided. Based on the plant design and on the contin-3 4
uous monitoring locations and intermittant sampling locations, we, l
have concluded that all normal and potential release pathways will
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be monitored. We have aisc determined that the sampling and monitoring provisions will be adequate for detecti.1g radioactive material i
leakage to normally uncontaminated systems and for monitoring plant I
processes which affect radioactivity releases. On this basis we consider the monitoring and sampling provisions to meet the l
requirements of General Design Criteria 13, 60 and 64 and the i
guidelines of Regulatory Guide 1.21.
i 11.5.2 Process and Effluent Radiolonical Monitorine Evaluation Findines I
The provisions for process and effluent radiological monitoring include J
'the instru=entation and controls for monitoring and controlling the i
j releases of radioactive materials in plant effluents and monitoring the 4
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level of radioactivity in process streams. The scope of our review i
included the provisions for monitoring and controlling the release 4
l of radioactive materials in plant effluents in accordance with General Design Criteria 60 and 64 and Regulatory Guide 1.21, and for monitoring radioactivity levels within the plant in process streams r
t in accordance with General Design Criterion 13.
The basis for acceptance in our review has been conformance of the l
applicant's design, design criteria, and design bases for the process and eifluent monitoring systems to the Cor.cission's Regula:ica:
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., as set forth in the General Design Criteria and to applicable Regulatory Guides, as referenced above, as well as staff technical positions and industry standards.
Based on the foregoing evaluation, we conclude that the proposed provisions for monitoring process and effluent streams are acceptabic.
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.. Table 11.5-1 Process and Effluent Manitoring s
Stream Monitored Detector Type Reactor Coolant Purification System Scintillation Component Cooling Water Scintillation Steam Headers Scintillation Service Water Discharge Header Scintillation Miscellaneous Radwaste Effluent Scintillation Clean Radtraste Effluent Scintillation Station Liquia Radwaste Effluent Scintillation Radioac'ive Waste Gas Discharge Scintillation t
Fuel llandling Arca Exhaust (Particulate)
Scintillation (Iodine)
Scintillation (Cas)
Scintillation Radwaste Arca Exhaust (Particulate)
Scintillation (Iodine)
Scintillation (Cas)
Scintillation Station Vent Stack (Particulate)
Scintillation (Iodine)
Scintillation (Cas)
Scintillation Containment (Particulate)
Scintillation (Iodine)
Scintillation (Gas)
Scintillation Condencer Vacuum Pump Discharge Scintillation l
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IIIBLIOGRAPlff 1.
United States Atomic Energy.ummission, " Final Environnental Statement Concerning Proposed Rule Making Action: Numerical Guides for Design Objectives and Limiting Conditions to Meet the Criterion "As Low As Practicable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents, UASH-1258, USAEC, Washington, D.C., July 1973.
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