ML19329B938
| ML19329B938 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/14/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19329B937 | List: |
| References | |
| NUDOCS 8002070535 | |
| Download: ML19329B938 (13) | |
Text
i f hl% k 11.0 RADIDACTIVE WASTE MANAGEMENT
.1 Suw.ary 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 pemit was issued, the applicant has modified the radwaste system to reduce radioact-i releases. These modifications include installation of an evaporator distillate poli; m -u demineralizer in the liquid radwaste system and charcoal filters in the gaseous eeew; and containment purge systems. The design criteria of the liquid, gaseous, and soli radwaste system exponents have also been upgraded.
The liquid waste system will process liquid waste streams such as reactor coolant letdown, equipment and floor drains, leakage from equipment, condensate demineralize-backwash wastes, decontamination and laboratory waste liquids, and laundry and showe-waste water. The treated liquid waste will be recycled for reuse if the reactor coc balance requires makeup and if the water quality is adequate. Tre liquid waste sys:-
will process waste liquid utilizing evaporation, demineralization, and filtration fc -
removal of radioactive material, chemical impurities, and particulates.
Gaseous wastes will be generated during the operation of the plant from degassing of primary coolant from displacement of liquid storage tank cover gases, froa the main steam condenser air ejector, from venting of equipment handling radioactive material:
and from leakage of systems and components coritaining radioactive material. The gaseous waste system will remove radioactive materials from gaseous streams by fil-tration, and holdup for radioactive decay. The treated gas streams will be releasec the environment through the station vent.
Solid wastes will be generated during plant operation and will consist of radioactiv-material from liquid waste evaporator concentrates, spent resins, spent filter car-tridges, and contaminated items such as clothing, equipment, and tools. Treatment w-consist of solidification of wet solid wastes and compaction of dry solid wastes.
Disposal will consist of packaging and shipping to a licensed burial site.
14 5 f e ~1" O The ca ility n the liquid nd gaseous ra% active - te treatr,t syste to mee*.
2 the ose des,n objectiv of Appendix i o 10 CFR.0 will be iscussa in a sucpleg t this r ort.
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t INSERT 1 In the FES, we indicated that we had not completed our review of the radwaste systems to meet the requirements of Appendix I of 10 CFR Part 50, issued May 5,1975, since the assumptions and models for calculating radioactive effluent releases sere being reassessed. We have completed the reassessment of our models and assumptions, and the i
applicant has chosen to comply with the September 4, 1975 a=endment to Appendix I rather than submit a cost-benefit analysis as required by Paragraph II.D.
On this basis, we have reassessed the radwaste systems using source terms calculated with the revised models and methodology described in NUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWRs),"
April 1976. The source term for Unit No.1 is given in Appendix A of this report.
Based on our reassessment, the liquid radioactive waste management systems are capable of maintaining releases of radioactive material in liquid effluents such that the total body dose to an individual in an unrestricted area will not exceed 3 mrem or any organ dose greater than 10 mrem /yr from Unit No.1 in accordance with Section II.A of Appendix I to 10 CFR Part 50.
Based on our reassessment, the gaseous radioactive waste management systems are capable of maintaining releases of radioactive materials in gaseous effluents such that air doses in the unrestricted area wil: not exceed 10 mrads/yr for gamma radiation, 20 mrads/yr for beta radiation, or 15 mrem /yr for radiciodine and radioactive particulates from Unit No.1 in accordance with Sections II.B and II.C of Appendix I to 10 CFR Part 50. Also, the calculated release of radioactive materials in liquid effluents from Unit No. 1, l
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2-exclusive of tritium and dissolved gases, will be less than 5 C1/yr/ reactor, and the total body and any organ dose will be less than 5 mrem /yr frem Unit No.1, in accordance with the option to Section II.D of Appendix 1 as provided for in the Annex to Appendix I.
Also, the effluents from Unit No. I will not result in an annual gamma air dose greater than 6
10 mrads, a beta air dose greater than 20 mrads, a release of iodine-131 greater than 1 Ci/ reactor, or a dose from radioiodine and radioactive particulates released greater than 15 nrem, in accordance with the option to Section II.D of Appendix I.
Therefore, we conclude that the liquid and gaseous radwaste treatment systems of Davis-Besse, Unit No. I are capable of reducing gaseous radioactive effluents to as low as is reasonably achievable levels in accordance with 10 CFR Part 50.34a, Appendix ! to 10 CFR Part 50, and the Annex to Appendix I to 10 CFR Part 50.
i Based on our evaluation, as described below, we find the liquid and solid radwaste and associated process and effluent radiological monitoring systems to be acceptable. Mcwever, we find the gaseous radwaste system I
to be unacceptable because of the potential for gaseous releases due to I
I hydrogen explosions.
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Liquid Waste The liquid radioactive wasta systems are described in.the Final Environmental Stateme-related to operation of Davis Besse Nuclear Power Station Unit 1, October 1975. Subse quent to our construction pemit review of this facility, the systas mas modified to include an evaporator condensate demineralizer in the Miscellaneous Liquid Radicactive Waste portion of the system. The demineralizer will be a mixed bed resin type with a 40 gpm design flow and a 14 cu.ft. resin volume.
The design criteria of major processing equipment in the liquid radwaste system were upgraded to the American Society of Mechanical Engineers standards, Section !!I, Clas-I r.u.
III which more than meet the guidelines of Branch Technical Position ETSB 11-1, "Desi Guidance for Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear Power Plants.".dehmMessesuddhW The addition of the demineralizer was considered in the Final Environmental Statement We calculate that approxi the opeping license and was included in that evaluation.
mately 2:38 curies per year, excluding tritium and dissolved gases, will be released from the liquid radioactive waste systems to the environment. To account for ageip' operational occurrences and equipment downtime, we i,ngreased this estimate to est cur We estimate the tritium release will be 5Ei: curies per year based on data per year.
obtained from operating pressurized water reactors. S
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-samene We have determined that during periods of fission product leakage from the fuel at de levels, releases of radioactive materials in linuid effluents will be within the reau ments specified in 10 CFR Part 20.106.
The liquid radwaste system includes the equipment and instrumentation to control the release of radioactive materials in liquid effluents. The scope of our review inclue the system's capability to reduce releases of radioactive materials in liquid effluer to as low as practicable levels in accordance with 10 CFR Part 20 considering antici; operational occurrences, and the design provisions incorporated to preclude uncontro:
releases of radioactive materials in liquids oue to leakage or overflows in accordanc with General Design Criterion 50 and the quality group classification and seismic design criteria in conformance with the guidelines of the Branch Technical Position,
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, ETSB 11-1, " Design guidance for radioactivejaste management systems installed in li; water-cooled nuclear power plants." UE/
Included in the review were piping and instrumentation diagrams, schematic diagrams, and descriptive information from the Final Safety Analysis Report for the Davis Besse facility.
The basis for our acceptance is that the applicant's design, design criteria, and design bases for tne liquid radwaste system confoms to the Comission's Regulaticns.
as well as to Comission staff positions and industry standards.
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3ased on our evahJation sumarized above, we conclude that the massen.epeeeensensia_
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g liquid radyste system ame acceptable.
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.3 Gaseous Waste
.3.1 Description and Evaluation I
The gaseous radioactive waste system and building ventilation systems are described it the Final Environmental Statement for the operating license of the Davis Besse facilii lSinceourconstructionpermitreview,theapplicantmodified the gaseous radwaste system to include a charcoal filter downstream of the waste gas decay tanks.
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The components in the gaseous waste system which delay or filter process gas are designed to the American Society of Mechanical Engineers Standards,Section III, Class
- - - - - - - - !!! standards which more than meet the guidelines of Branch Technical Position ETSB 11-1, s'.e d, l,
~n1SeitX r &.he modifications to the systems were considered in the Final Environmental Statement
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_ _ - - - and were included in that evaluation. We calculate that approximately
^ curies per o.za year of noble gases and 9ueR curies per year of Iodine-131 will be released from the gaseous radwaste system to the environment. The applicant estimates that tuur curies per year of noble gases and Jh=te curies per year of Iodine-131 will be released from i
the system.
~~~ We have determined that during periods of fission product leakage from the fuel at design levels the releases of radioactive materials in gaseous effluents will be withi the requirements specified in 10 CFR Part 20.106.
~ ~~~ ~~--~ The gaseous radwaste system includes the equipment and instrumentation to control the release of radioactive materials in gaseous effluents. The scope of our review inclu:
-.- -' the system's capability to reduce releases of radioactive materials in gaseous effluer to as low as practicable levels in accordance with 10 CFR Part 20 considering antici-pated operational occurrences and the quality group and seismic design criteria. Our
. _ _ _ review included an evaluation of effluent releases based on the modified treatment Effluent releases for pathways due to process vents and leakage affectin{
p rocesses.
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building ventilation systems sere considered. Included in our review were piping and instrumentation diagrams, schematic diagrams, and descriptive information from the Final Safety Analysis Report for the Davis Besse facility.
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i INSERT 2 The gaseous waste system consists of 2 compressors, one surge tank, and three waste gas decay tanks. None of the Gws components are designed to withstand a hydrogen explosion. The system will be designed to a
operate at positive pressure with a nitrogen blanketing system to prevent air (oxygen) buildup as a result of infiltration. The system design includes one oxygen analyter which will initiate an alarm if orygen concentrations vary beyond the design concentration limits.
The system design will limit the concentration by providing for dilution with nitrogen. It is our position that the GWS be designed to withstand a hydrogen explosion or be provided with redundant instru-mentation to annunciate and prevent the buildup of potentially explosive mixtures. We find the design provisions incorporated to reduce the potential of a hydrogen explosion to be unacceptable.
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i The basis fer our acceptance is that the applicant's designs, design criteria, and design bases for the gaseous waste system confonn to the applicable Comission Reg-s ulations as well as to Comission staff technical positions and industry standards.
Based on our evaluation sumarized above, wJ concludejhat the pgpooseAmodified gaseous radwaste system is y* unacceptable because of the potential for geseous releases due to hydrogen erplosions.
1 Solid Waste System d
4.1 Description and Evaluation 6
The solid waste system is designed to collect, monitor, process, package, and provide temporary storage for radioactive solid waste prior to offsite shipment for disposal accordance with applicable regulations.
Radioactive solid wastes resulting from operation of the plant include concentrates from the radwaste evaporators, spent resins, spent filter cartridges, and contaminate dry waste such as disposable filters, clothing, equipment, and tools. The solid radw system uses a solidification system in which the evaporator concentrates, spent resir.
and high activity filter cartridges will be mixed with the solidifying agent, loaded 50 cubic foot cask liners and stored prior to shipment. Low activity filter cartrid; will be loaded into 55 gallon drums. Dry wastes will be compacted into 55 gallon dru and stored for shipment. The high radioactivity level drums will be handled by use c remote handling equipment.
The equipment in the solid waste system which handle liquid wastes is designed to the Arerican Society of Mechanical Engineers Standards, Section !!!, Class III which mort than meet the guidelines of BTP ETSB 11-1. E d. L Based on the operating experience of similar plants we estimate that annual disposal will be 13000 cubic feet of high level wastes and 4100 cubic feet of dry compacted waste. Our estimates of total activity after 180 days decay is 1600 curies per year.
Based on operating experience at other plants and the capacity of the druming static the applicant estimates 500 drums of high level and 150 drums of low level waste (48; 3
ft ) will be shipped annually to a licensed burial ground. All solid waste will be packaged and shipped in conformance with all applicable Comission and Department of Transportation regulations.
The solid radwaste system includes the equipment and instrumentation for solidifying and packaging radioactive wastes prior to shipment for offsite burial. Our review included an evaluation of the system's capability for processing the types and volure of wastes expected during nonnal operation. Anticipated operational occurrences are accordance with General Design Criterion 60, the quality group design criteria, and t provisions for handling wastes with regard to the requirements of 10 CFR Parts 20 arc 71, and 140 CFR Parts 170-189.
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i Included in our raview were piping and instrumentation diagrams, schematic diagrams, and descriptive information from the Final Safety Analysis Report for the Davis Besse facility.
The basis for our acceptance is that the applicant's designs, design criteria, and design bases for the solid radwaste system confom to the Commission's Regulations referenced above, as well as Comission staff technical positions and industry standards.
Based on our evaluation surxiarized above, we conclude that the proposed solid radwast.
system is acceptable.
5 Process and Effluent Monitoring 5.1 Description and Evaluation In our evaluation of the process and effluent monitoring system we considered the system's ability to (1) monitor all normal and potential pathways for release of radioactive materials to the environment, (2) control the release of radicactive materials to the environment, and (3) monitor the perftmance 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 plar.t. and indicate radioactive leakage between systems. The system wil' monitor equipment perfomance and monitor and control radioactivity levels in pit.nt discharges to the environs.
Scintillation detectors will be used for monitoring liquids and for monitoring radioactive gases and particulates in vent effluents. Gaseous iodine will be col-lected in replaceable, impregnated charcoal adsorbers which will be cantinuously monitored while in use by scintillation detect' rs. Systems which are rot amenable t:
o continuous monitoring or for which detailed isotopic analyses are required will be periodically sampled and analyzed in the plant laboratory.
Table 11.1 indicates the locations and types of continuous monitors. Monitcrs on effluent release lines will automatically terminate discharges should radiation levels exceed a predetemined value.
We have reviewed the locations and types of effluent and process monitoring providec-Based on the plant design and on the continuous monitoring locations and intemitten:
sampling locations, we have concluded that all nomal and potential release pathways will be monitored. We have also determined that the sampling and monitoring pro-visions will be adequate for detecting radioactive material leakage to nomally uncontaminated systems and for monitoring plant processes which affect radioactivity releases. On this basis, we conclude the monitoring and sampling provisions meet tN requirements of General Oesign Criteria 13, 60 and 64 and the guidelines of Regulatcr Guide 1.21 " Measuring. Evaluating, and Reporting Radioactivity in Solid Wastes aad Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-2 Nuclear Power Plants."
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I Table 11.1 Process and Effluent Monitoring itream Monitored Detector Type teactor Coolant Purification System Scintillation
- omponent Cooling Water Scintillation Steam Headers Scintillation
>ervice Water Discharge Header Scintillation iiscellaneous Racwaste Effluent Scintillation
- 1ean Radwaste Effluent Scintillation itation Liquid Radwaste Effluent Scintillation ladioactive Waste Gas Discharge Scintillation uel Handling Area Exhaust (Particulate)
Scintillation T
(Iodine)
Scintillation (Gas)
Scintillation tadwaste Area Exhaust (Particulate, Scintillation
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Scintillation (Gas)
Scintillation itation Vent Stack (Particulate)
Scintillation (Iodine)
Scintillation (Gas)
Scintillation
.ontainment (Particulate)
Scintillation (Iodine)
Scintillation (Gas)
Scintillation
'ondenser Vacuum Pump Discharge Scintillation 1
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5.2 Process and Effluent Radiological Monitorino Evaluation Findings The provisions for process and effluent radiological monitoring include the instrumen-tation and controls for monitoring and controlling the releases of radioactive materi-in olant effluents and monitoring the level of radioactivity in process streams. The scope of our review included the provisions for monitoring and controlling the releas-of radioactive materials in plant effluents in accordance with General Design Criteri; 60 and 64 and Regulatory Guide 1.21, and for monitoring radioactivity levels within t-plant in process streams in accordance with General Design Criterion 13.
6 The basis for our acceptance is that of the applicant's design, design criteria, and design bases to the Commission's Regulations as set forth in the General Design Crite' for the process and effluent monitoring system and to the applicable Regulatory Guide referenced above, as well as to Commission staff positions and industry standards.
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l Appendix A TABLE 1 Calculated Releases of Radioactive Material in Caseoua Effluents from Oavis-Bense Nuclear Station, Unit No.1 (C1/yr/ unit)
Decay Building ventilation Air Ejector Radionuclide Tanks Reactor Auxiliary Turbine Off-cas Total Kr-83m a
a a
a a
a Kr-85m a
1 2
a 1
4 Kr-65 350 46 2
a a
400 Kr-87 a
a 1
a a
1 Kr-88 a
2 4
a 3
9 Kr-89 a
a a
a a
a Ie-1313 5
37 2
a 1
45 Ie-133m a
32 4
a 3
39 Ie-133 9
4700 320 a
200 5200 Ze-135m a
a a
a a
a Ie-135 a
9 7
a 4
20 Ze-137 a
a a
a a
Ze-138 a
a a
a a
1.3(-1)D 5.4(-2) 1.1(-3) 3.4(-2) 2.2(-1)
I-131 a
I-133 a
2.8(-2) 7(-2) 1.4(-3) 4.4(-2) 1.4(-1)
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Mn-54 4.5(-5) 2.2(-4) 1.8(-4) e c
4.4(-4)
Fe-59 1.5(-5) 7.5(-5) 6(-5) e u
1.5(-4)
Co-58 1.5(-4) 7.5(-4) 6(-4) e c
1.5(-3)
Co-60 7(-5) 3.4(-4) 2.7(-4) e c
6.8(-4)
Sr-89 3.3(-6) 1.7(-5) 1.3C-5) e e
3.3(-5)
St-90 6(-7)
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2.4(-6) e c
6(-6)
Cs-134 4.5(-5) 2. 2 '-4 )
1.8(-4) e e
4.4(-4)
Cs-137 7.5(-5) 3.8(-4) 3(-4) e c
7.5(-4)
C-14 7
1 a
a a
8 Ar-41 a
25 a
a a
25 3-3 e
280 230 e
c 560 a = less than 1.0 Ci/yr for noble gases and carbon-14, less than 10-* Ci/yr for iodine
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b = exponential notation; 1.0(-<+) = 1.0 x 10 c = less than 1 of total for this nuclide i
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I Appendix A TA3LE 2 Calculated Releases Of Radioactive Materials li Liquid Ef fluents From Davis-Besse. Unit No.1 i
Nue t tea ci/yr/ unit.
Nuclide Ci / vr /ur.it Corrosion & Activation Fission Products (cont'd)
Products Cr-51 2.2(-4)'
Te-129 1.1(-4)
Mn-54 1(-3)
I-130 1.3(-4)
Fe-55 2.2(-4)
Te-1313 6(-5)
Fe-59 1.2(-4)
Te-131 1(-5)
Co-58 6.1(-3)
I-131 6.5(-2)
Co-60 9.0(-3)
Te-132 1.4(-3)
Zr-95 1.4(-3)
I-132 2.5(-3)
Nb-95 2(-3)
I-133 3.6(-2)
Np-239 6(-5)
I-134 1(-5)
Cs-134 2(-2)
I-135 6.3(-3)
Fission Products Cs-136 2.4(-3)
Cs-137 2.9(-2) 3a-1373 5(-3) sr-43 3(-5)
Ba-140 2(-5) ab-86 2(-3)
La-140 2(-5) l Sr-89 5f-5)
Ce-144 5.2(-3)
Sr-91 1(-5)
All Others 6(-5)
Mo-99 3.1(-2)
Total Tc-993 2.1(-2) except Tritium 0.25
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Ru-103 1.5(-4)
Ru-106 2.4(-3)
Tritium 550 As-110m 4.4(-4)
Te-127m 3(-5)
Te-127 5(-5)
Te-129m 1.7(-4) a = exponential notation; 1.0(-4) = 1.0 x 10 '
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-5 b= cuclides whose release rates are less than 10 Ci/yr are not listed individually but are included in the category "All others".
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I 15.'7'fostulated Radioactive Releases Due to Licuid Tank Failures The consequences of component f ailures which could result in release
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6 of liquida containing radioactive materials to the environs were evaluated for components located outside the reactor contaidment.
Considered in the evaluation were (1) the radionuclide invectory in each component assuming a 1:~ operating power fission product mource ters, (2) a component liquid inventory equal to 80% of its fesign capacity, (3) the mitigating ef fects of plant design including the location of storage tanks in curbed areas designed to retain spillage, and (4) the effects of site geology and hydrology.
The applicant has incorperated previsions in the design to retain releases from liquid overflows as discussed in section 11.2.1 of this SER. The site is adjacent to Lake Erie. In the event of a spill resulting in radionuclides entering the ground, water, the ground
, vater flow will move the spillage towards Lake Erie.
Based on our evaluation, the potential tank f ailure resulting in the greatest quantity of activity released to the environment is failure of one cf the clean vaste receiver tanks. The tank is assmeed to contain ra'ionuclides at 50 percent of primary coolant activity levels Joe ene design basis fission product inventory stated above. In our evaluation.,we have determined the liquid transit time for the leakage to the reservoir to be 72 years. Considering the leakage transit time, the calculated radiennelide concentrations in Lake Erie result in values that are small fractions of the limits of 10 CyR Part 20, Appendix B, Table II, Column 2, for unrestricted areas.
a Based on the foregoing evaluation, we conclude that the provisions incorporated in the applicant's design to mitigate the effects of component failures involving contaminated liquids, are acceptable.
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