ML20213D925
| ML20213D925 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/23/1981 |
| From: | Kreger W Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0411, CON-WNP-411 NUDOCS 8112020806 | |
| Download: ML20213D925 (27) | |
Text
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r-r DISTRIBUTION:
-400cket Fiel 50-397 ETSB Reading F.ile ETSB Docket File WEKreger CSPaul' Docket flo. 50-397 00T 2 31981 t!E!! ORA!!DU!1 FOR: Robert L. Tedesco, Assistant Director for Licensing, OL FR0ll:
U1111am E. Kreger, Assistant Director for Radiation Protection, DSI
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SUPJECT:
ORAFT ETSB II:PUT TO SAFETY EVALUATIO!! REPORT FOR UPPSS tlVCLEAR PROJECT, UtilT 110. 2
,g3_. sys s
PLAT;T !!A'iE: MPPSS tluclear Project, Unit !!o. 2
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LICEl! sit:G STAGE: OL DOCKET flUMBER(S): 50-397
'!ILEST0!!E tlUf18ER: 24-01 L
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PESP0l!SInLE BRAf;Ct!: LB-1 u,,.
PROJECT !!A!!AGER:
R. Auluck "m-DESCRIPTIO:: OF RESP 0f!SE: Draft Safety Evaluation Report O
REQUESTED CC'iPLETIO!! DATE: October 12, 1931
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REVIEU STATUS: Undergoing Review N.QhX 'P s\\
Enclosed are drafts of sections concernino radioactive waste nananenent (11.1 and 11.2), process and effluent radiological nonitoring (11.3), ESF filter systens (6.5), nain condenser evacuation systen (10.4.2), turbine oland seal systen (10.4.3), and liquid tank failures outside containment (15.7.3), for use in the Safety Evaluation Report for the UPPSS tluclear Project, I! nit I!o. 2.
The applicant has proposed to use state-of-the-art technolony for the liquid, gasenus and solid radt;atte treatment systens and to desiqn the s.vstems to accentable codes and standards. We find these systeas acceptable.
Based on our evaluation, we conclude that the liquid and qaseous radyaste treatnent systems, pronosed for WPPSS tluclear Project, Unit !!o. 2, are capable of naintaininn releases of radioactive naterials in effluents to "as low as is reasonably achievable" levels in accordance with 10 CFR Part 50.34a and con-forn to the requirements of Apnendix I to 10 CF:1 Part 50.
Our analysis of radioactive releases due to liquid tank failures outside con-tainment shows that the provisions incorporated in the applicant's design to nitigate the effects of tank failures involving contaminated liquids are acceptable.
Original signed by J&crwt,,\\ Er W. E. Kreger Willian E. Krener, Assistant Director for Rediation Protection Division of Systens Intecration
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v 6.5 Engineered Safety Feature (ESF) Filter Systems 6.5.1 Summary Description The engineered safety feature (ESF) atmosphere cleanup systems for Washington Nuclear Project (WNP), Unit No. 2, consist of process equipment and instrumentation to control the releases of radio-active materials in gaseous effluents (radioactive iodine and particulate matter) following a design basis accident (DBA). In the WNP-2 application, there are two filtration systems designed for this purpose; the standby gas treatment system (SGTS), and the control room emergency filter system (CREFS).
6.5.2 System Description and Evaluation 6.5.2.1 Standby Gas Treatment System (SGTS)
The function of the standby gas treatment system (SGTS) is to collect and process the leakage of radioactive materials from the primary containment into the secondary containment or reactor building following a loss-of-coolant-accident (LOCA) and also to enable purging of the primary containment through the SGTS filters
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when aTFEorne Fadiation levels within.the primary containment (dry well) are too high to permit purging through the reactor building exhaust system. The SGTS is a redundant system. Each train has a design capacity of 4,457 cfm and includes the following components:
l demister, heating coil, prefilter, high efficiency particulate air (HEPA) filter, two 4-inch deep banks of carbon adsorbers in series, HEPA filter, and fan. Three deluge-type water spray systems are i
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i 6.'5. 2.1 provided for flooding the charcoal in case of fire or overheating.
The equipment and components are designed to Quality Group C and seismic Category I, and are located in a seismic Category I structure.
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i The design of the SGTS was compared to the criteria of Regulatory Guide 1.52(1) and the following deviations were noted:
Section 29: The SGTS system is not instrumented to record pertinent pressure drops and flow rates at the control room. Instrumentation is provided only to alarm abnormal pressure drops, to record alarms (abnormal pressure drop), and to indicate (but not record) system flow rate. The applicant's FSAR notes these deviations but gives no bases or justifications for the deviations. Applicant should provide his rationale for not meeting Section 2g.
Section 21: The FSAR states that SGTS filters can be bypassed for testing but that there is no provision for indication of bypass
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status in control roon (Note 4, page 6.5-20); in effect, this negates the automatic activation of these systems in the event of an accident if the bypass is in use and does not keep the operator informed of system status.
Section 3a: Note 6, page 6.5-20 of the FSAR, indicates that the SGTS demisters are not qualified in accordance with the requirements of MSAR 71-45, but that the manufacturer contends that the addition
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6.5.2.1 of 3 two-inch fiberglass pads "should be approved". Applicant should verify the current status of approval and state any pertinent reasons as to why approval has not been obtained.
Section 4d:
Section 4d of Regulatory Guide 1.52 recommends that each ESF atmosphere cleanup train be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per month, with heaters on, in order to reduce the buildup of moisture on the adsorber and HEPA filters. The purpose of this requirement is the removal of accumulated moisture from the HEPA filter and carbon adsorber components. Applicant, in Note 13, page 6.5-22 of the FSAR, maintains that periodic activation of strip heater., is adequate to maintain the charcoal beds moisture-free and that simultaneous operation of the fans is not required.
'pplicant should provide details of any test data which substantiates his position; otherwise, the Technical Specifications will be conditioned to require operation of each ESF train for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per mcnth.
with heaters on, to reduce moisture buildup.
Testing of ESF atmosphere cleanup system components was reviewed with respect to the criteria of Regulatory Guide 1.52.
Test provisions were in accordance with the criteria with the following exceptions:
- Inplace testing of HEPA filter ~section is in accordance with Military Standard MIL-STD-282, which is incorporated by reference in ANSI N510; however, the listed testing criteria do not make mention of those portions of Position C.S.b of
i 6.5.2.1 Regulatory Guide 1.52, which provide for testing at specific intervals or following painting, fire, or chemical release (this may be an open item or, alternatively, may be in the Tech Specs). To be in conformance with Regulatory Guide 1.52,
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applicant should also reference MIL-F-51068 for testing of HEPA filters.
OPEN ITEM: Does not mention testing requirements for specific intervals between tests and does not specify testing following painting, fire, or chemical release. Testing of HEPA filters should reference MIL-F-50168; alternatively, ANSI N510 could be referenced, which would then incorporate references to both MIL-STD-282 and MIL-F-51068.
Instrumentation requirements for the SGTS were reviewed with respect to the criteria of Regulatory Guide 1.52.
Instrumentation provisions were in accordance with the criteria with the exceptions noted below.
Instrumentation provided for the STGS includes:
- Flow rate, unit outlet. Provides flow rate indication and high/ low op alarms in the main control room. No provisions for recording of flow as recommended in ANSI 509.and Regulatory..
Guide 1.52.
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6.5.2.1
- Pressure Drop (ap). For each element in the SGTS trains, system provides indication, status of operation and high Ap alarms in the main control room. Components covered in-clude roughing filter, upstream HEPA filter, charcoal beds, and downstream HEPA filter. No provisiod noted for recording of any system pressure drops. Alarms of high op are recorded in the plant computer. No provisions for measurement of total pressure drop across complete system. Regula tory Guide 1.52, Section C.2.g, recommends recording of "pertin-I ent" pressure drops at the control room.
OPEN ITEMS: No provision for control room recording of system air flow rates or pressure drops.. No provision for measurement, indication, or recording of total system pressure drop (Eap).
No provision for status indication in control room of deluge valve positions, valve / damper operator position, or fan status.
^ 6.5.2.2 ControT~ Room Emergency Filter System (CREFS)
The function of the control room emergency filter system (CREFS) is to supply non-radioactive air to the control room af ter a DBA and to pressurize the control room. This system will permit operating per-sonnel to remain in the control room following a DB A.
The CREFS is a redundant system, with each system having an intake design capacity of up to 1,000 cfm of air and recirculating design capacity of 1,000 cfm of air. Each system contains the following components:
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e 6-6.5.2.2 prefilter, HEPA filter, carbon adsorber and fan. Heating coils are also prwided for relative humidity control. A deluge water spray system is provided in the event of high temperature or fire in the charcoal b'eds. The equipment and components are designed to Quality Group C and seismic Category I and are loca#ted in a seismic Category I structure.
6.5.3 Findings Subject to resolution of the above open issues, our findings are as follows:
We have detemined that the CREFS and SGTS are designed in accord-ance with the guidelines of Regulatory Guide 1.52 In our evaluation, we have assigned the SG15 system decontamination efficiencies of 99% for elemental and organic iodine and 99% for particulates and have assigned the CREFS system decontamination efficiencies of 95% for elemental and organic iodine and 99% for particulates. Based on this evaluation, we find that the CREFS and SGTS are designed to control the releases of radioactive materials in gaseous effluents in accordance with applicable regulations following a postulated DBA.
. 10.4.2 Main Condenser Evacuation System The main condenser evacuation system is designed to establish and maintain main condenser vacuum by removing noncondensible gases from the main condenser. During normal plant op6 ration, the noncon-densible gases are routed to the RECHAR delay system for processsing and delay prior to release (see Section 11.3 of this SER for des-cription and evaluation). During plant startup and during plant shutdown, main condenser vacuum is achieved or maintained through the use of mechanical or " hogging" pumps, which discharge the noncondensible gases by bypassine the RECHAR off-gas system and venting the gases to the environment through the reactor building elevated release vent.
Two 100 percent capacity steam jet air ejectors (SJAE) are provided.
Each SJAE consists of a tain-element first-stage steam-jet air ejector and a single-element second-stage steam-jet air ejector, which discharges to the off-gas system. Two mechanical vacuum pumps are provided for hogging operation during startup.
The main condenser evacuation system includes equipment and instruments to establish and maintain condenser vacuum and to
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8-10.4.2 prevent an uncontrolled release of radioactive material to the environment. The scope of our review included the system capability to transfer radioactive gases to the gaseous waste processing. system or ventilation exhaust systems, and the design provisions incorporated to monitor and control releases of radioactive materials in effluents. The staff has reviewed the applicant's system descriptions, piping and instrumentation diagrams, and design criteria for the components of the main condenser evacuation system.
The staff concludes that the MCES design is acceptable in that the applicant has met the requirements of General Design Criteria 60 and 64 with respect to the control and monitoring of releases of radioactive materials to the environment by providing a controlled and monitored MCES. The applicant has met the requirements of industrial standard " Standards for Steam Surface Condensers.(2) that has been reviewed by the staff
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and determined to be appropriate for this application.
10.4.3 Turbine Gland Sealing System The turbine gland sealing system (TGSS) is designed to control radioactive steam leakage from, and air leakage into, the turbine.
10.4.3 The components of the system are designed to Quality Group D and to a non-seismic design classification. The turbine gland sealing system consists of two gland seal steam evaporators, seal steam pressure regulators, seal steam header, gland seal steam condenser, and associated piping, valves, and instrumentation. The gland i
seal steam evaporators are heated by extraction steam taken from the high pressure turbine. The outer leakoffs of all high pressure and low pressure turbine glands are routed to the gland seal steam condenser which is discharged to the reactor building elevated release vent by the exhauster blower.
The turbine gland sealing system includes the equipment and instru-ments to provide a source of sealing steam to the annulus space i
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where the turbine and large steam valve shafts penetrate their
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casings. The scope of our review included the source of sealing I
steam and the provisions incorporated to monitor and control releases of radioactive material in effluents.
The staff concludes that the turbine gland sealing system design is acceptable in that the applicant has met the requirements of I
General Design Criteria 60 and 64 with respect to the control and monitoring of releases of radioactive materials to the environment by providing a controlled and monitored turbine gland sealing system.
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11.0 RADI0 ACTIVE WASTE MANAGEMENT 11.1 Summary Description The radioactive waste management systems are designed to provide for the controlled handling and treat:nent of liquid, gaseous and solid wastes. The liquid radioactive wast ( system processes wastes from equipment and floor drains, sample wastes, decontamination and laboratory wastes, regenerant chemical wastes, and shower wastes.
The gaseous radioactive waste system provides holdep capacity to allow decay of short lived noble,gase; from the main condenser air ejector and treatment of ventilation exhausts through HEPA filtery, as necessary to reduce raleases of radioactive materials to "as low cs is reasonably achievable" levels in accordance with 10 CFR Part 20 and 10 CFR Part 50.34a. The solid radioactive waste system provides for the solidification, packaging and storage of radioactive wastes generated during station operation prfor to shipment of f site to a ljgspsedJac111ty for burial.
i The estimated releases of radioactive materials in liquid and gaseous effluents were f.alculated using the BWR GALE Code described in NUREG 0016. " Calculation of Peleases of Radioact,ive Materials in i
Gaseous and Liquid Effluents frcn Bolling Water Reacturs (BWR CALE Code)", January 1978(3)
The principal parameters used in those calculations are given in Table 11.1 of this $ER. The liquid and gaseous source terms are given in Tables L-0 and L-1 of NUREG-0812(4I.
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11.1 Based on our evaluation, as described below, we concluded that the liquid and gaseous radioactive waste treatment systems are capable of maintaining releases of radioactive materials in liquid and gaseous effluents to "as low as is reasonably achievable" levels in accordance with 10 CFR Part 50.34a, and with Sections II. A II.B.
II.C and 11.0 of Appendix I to 10 CFR Part 50; therefore, we concluded that the proposed liquid, gaseous and solid radioactive waste systems and associated process and effluent radiological monitoring and sampling systems are acceptable.
11.2 Liquid Waste Management The liquid waste processing system (LWPS) for the Washington Nuclear Project Unit 2, serves only Unit 2.
The liquid waste processing system consists of process equipment and instrumentation necessary to collect, process, monitor and recycle or dispose of radioactive liquid wastes. The liquid radwaste system is designed to collect
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and proccis wastes based on the origin of the waste in the plant and the expected levels of radioactivity. Liquid waste is processed on a batch basis to permit optimum control of releases. Prior to being released, samples are analyzed to determine the types and amounts of radioactivity present. Based on the results of the analyses, the waste is recycled for eventual reuse in the plant, retained for further processing, or released under controlled con-ditions to the erwironment.
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11.2 A radiation monitor in the discharge line automatically terminates liquid waste discharges if raciation measurements exceed a pre-determined level. The liquid radioactive waste processing system consists of the high purity, low purity, and chemical waste sub-systems. Laboratory, hot shower, and decon} amination wastes are collected in the detergent waste subsystem and are processed through the chemical waste subsystem.
If a laundry facility is added at a later date, effluents will also be processed through the detergent and chemical waste subsystems.
The liquid waste processing system is located in the radwaste and t
control building, the pertinent portions of which are designed to seismic Category I criteria. The proposed seismic design and quality group classification and capacities of principal components con-sidered in the liquid waste processing system evaluation are listed in Table 11.4.
We find the applicant's proposed liquid radioactive
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waste treatment system design to be acceptable in accordance with the guidelines of Regulatory Guide 1.143(5),
11.2 The system design includes measures intended to control the release of radioactive materials due to potential overflows from indoor and outdoor storage tanks. Tank levels are monitored in the radwaste control room and high level alarms are activated should preset levels t
be exceeded. Overflow provisions such as sumps, dikes and overflow lines permit the collection and subsequent processing of tank overflow.
We consider these provisions to be capable of controlling the release of radioactive materials to the environment.
We have determined that the liquid waste processing systems are cap-able of reducing the release of radioactive materials in liquid effluents to concentrations below the limits in 10 CFR Part 20, during periods of fission product leakage from the fuel at design level s.
We conclude that the liquid waste processing systems are capable of
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reducing the releases of radioactive materials in effluents to "as low as is reasonably achievable" levels in accordance with 10 CFR Part 50.34a and, therefore, are acceptable.
11.3 Gaseous Waste Management Tha gaseous radioactive waste processing and plant ventilation systems are designed to collect, store, process, monitor, and dis-charge potentially radioactive gaseous wastes which are generated during normal operation of the plant. The systems consist of
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11.3 equipment and instrumentation necessary to reduce releases of radio-active gases and particulates to the environment. The principal sources of gaseous waste are the effluents from the gaseous waste processing system, condenser mechanical vacuum pumps, and ventilation exhausts from the radwaste and fontrol building, reactor building, drywell (primary containment), and turbine building.
The gasecus waste processing system (GWPS) for Washington Nuclear Project, Unit No. 2, services only WNP-2. The main condenser air ejector low temperature RECHAR system collects, processes and stores fission product gases removed from the main condenser by processing through a recombiner, cooler, and dryer, and then by adsorption and decay through a series of refrigerated charcoal delay tanks. After delay, the gas passes through a HEPA filter and is discharged to the environment through the reactor building elevated release duct.
Ventilation exhaust air from the reactor building is exhausted by two paths, one of which is treated and one which is not treated.
The principal exhaust path is an untreated 100,000 cfm flow through one of two fans; this path also serves as the principal purge path for the reactor building (secondary containment) and for the primary containment (drywell and suppression pool) when airborne radio-activity levels are within limits permitting untreated discharge.
When airborne radioactivity levels exceed control levels (to be
11.3 established in the plant Technical Specifications), purges will be made through the Standby Gas Treatnent System (SGTS). The second exhaust path is the 1,000 cfm vent exhaust system (redundant) which exhausts air from the reactor building sumps and drain headers, passing the collected air through moisture separators, dryers, HEPA filters, and a 2-inch deep charcoal adsorber before exhausting the stream to the main reactor building exhaust system upstream of the ef fluent radiation monitors.
Ventilation exhaust from the radwaste building is passed through HEPA filters before being released to the atmosphere. Ventil ation exhaust from the turbine building is released untreated; however, exhaust air from the turbine building sample room, located in the turbine building, is treated by filtration through a prefilter and HEPA filter before being released into the main turbine building ventilation exhaust system.
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The proposed seismic design and quality group classification and capacities of the principal equipment in the GWPS are listed in Table 11.2.
We find the applicant's design criteria for the gaseous waste processing system and structure housing this system to be in conformance with the guidelines given in Regulatory Guide 1.143(5) and, therefore, acceptable.
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' 11.3 We have detennined that the gaseous waste processing system is capable of reducing the release of radioactive materials in gaseous effluents to concentrations below the limits in 10 CFR Part 20, during periods of fission product leakage from the fuel at design levels, j
We conclude that the GWPS and the plant ventilation systems are capable of reducing radioactive materials in effluents to "as low as is reasonably achievable" levels in accordance with 10 CFR Part 50.34a and, therefore, are acceptable.
11.4 Solid Waste Management System The solid waste system (SWS) for Washington Nuclear Project, Unit No. 2, serves only WNP-2, and is designed to process two general types of solid wastes: " wet" solid wastes which requires solidi-fication prior to shipment, and " dry" solid wastes which require packaging and, in some cases, compaction prior to shipment to a licensed burial facility.
" Dry" solid wastes, consisting mainly of such items as ventilation air filters, contaminated clothing, paper, laboratory glassware, and tools, are compacted in 55 gal drums by a waste compacter. The com-pacter is equipped with a shroud to prevent the escape of radioactive materials during the compaction process. During the compacting operation, the air flow in the vicinity of the compactor is exhausted
11.4 by a fan through a HEPA filter to the radwaste building ventilation system to reduce the potential for airborne radioactive dusts.
" Wet" solid wastes consisting of concentrated chemical waste evapora-tor bottoms, chemical drain tank effluents and spent resin sludges will be treated by a volume reduction and (olidification system at the Washington Nuclear Project, Unit No. 2.
The solidification system will be a cement-silicate system, providing for solidifica-tion of the above wastes in steel containers. The solidifying agent will be a mixture of Portland cement and sodium silicate, with proportions being detemined in accordance with a process con-trol program; the process control program, however, has not as yet been submitted and, therefore, has not been reviewed. Prior to operation, the applicant will be required to submit a process control program to assure complete solidification of all " wet" waste in confomance with the guidelines of Standard Review Plan 11.4 of NURfLO800.6)
The annual production of solid wastes is estimated to be approxi-
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mately 18,000 f t of solidified " wet" wastes, containing approximately 3
2,300 curies of activity, and 16,000 ft of compacted " dry" wastes, containing less than 50 curies of activity. The applicant has pro-3 vided storage space for approximately 3,600 ft of waste, which
11.4 represents approximately 1-1/3 month's capacity at the annual average generation rate. Since the staff's guidance specifies storage space for one month's waste capacity, we find the storage volume adequate for meeting the demands of the plant.
Our findings are as follows:
The solid waste system (SWS) includes the equipment and instrumenta-tion used for the solidification, packaging, and storage of radioactive wastes prior to shipment of fsite for burial. The scope of the review of the SWS includes line diagrams of the system, piping and instru-mentation diagrams (P&lDs), and descriptive information for the SWS and for those auxiliary supporting systems that are essential to the operation of the SWS.
The applicant's proposed design criteria and design bases for the SWS, and the applicant's analysis of those criteria and bases have been reviewed. The capability of the proposed system to process the i
types and volumes of wastes expected during normal operation and anticipated operational occurrences in accordance with General Design Criterion 60, provisions for the handling of wastes relative to the requirements of 10 CFR Parts 20 and 71 and of applicable DOT l
regulations, and the applicant's quality group classification and seismic design relative to Regulatory Guide 1.143, have also been reviewed.
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11.4 The basis for acceptance in our review has been conformance of the applicant's designs, design criteria, and design bases for the solid radwaste system to the regulations and the guides referenced above, as well as to staff technical positions and industry standards.
Based on the foregoing evaluation, we conclyde that the proposed solid radwaste system is acceptable.
11.5 Process and Effluent Radiological Monitoring And Sampling Systems The process and effluent radiological monitoring systems are designed to provide information concerning radioactivity levels in systems throughout the plant, indicate radioactive leakage between systems, monitor equipment performance, and monitor and control radioactivity levels in plant discharges to the environs.
Table 11.3 provides the proposed locations of continuous monitors.
Monitors on certain effluent release lines automatically terminate discharges should radiation levels exceed a predetermined value.
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Systems which are not amenable to continuous monitoring, or for which detailed isotopic analyses are required, are periodically sampled and analyzed in the plant laboratory.
We have reviewed the locations and types of effluent and process monitoring provided. Based on the plant design and on continuous monitoring locations and intermittent sampling locations, we have concluded that all normal and potential release pathways are
11.5 moni to red. We have also detemined that the sampling and monitor-ing provisions are adequate for detecting radioactive material leakage to nomally uncontaminated systems and for monitoring plant processes which could affect radioactivity releases. On this basis, we consider that the monitoring andjampling provisions meet the requirements of General Design Criteria 60, 63 and 64 and the guidelines of Regulatory Guide 1.21,( I and, therefore, are acceptable.
Technical Specifications for the process and effluent radiological monitoring systems, instrumentation, controls and the sampling and analysis programs for the Washington Nuclear Project, Unit No. 2, will be prepared and in force prior to reactor startup.
15.7.3 Postulated Radioactive Releases Due to Liquid Tank Failures The consequences of tank failures for tanks located outside the reactor containment, which could result in releases of liquids l
containing radioactive materials to the environs, were evaluated.
l Considered in our evaluation were (1) the radionuclide inventory in each tank assuming an operating power fission product source tem of 15 uCi/sec-MWt (after 30 minutes decay)..(2) a tank liquid inventory equal to 80% of its design capacity, (3) the mitigating effects of plant design including overflow lines and the location of indoor and outdoor storage tanks in curbed areas tiesigned to retain spillage, and (4) the effects of site geology and hydrology.
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15.7.3 The applicant has incorporated provisions in the design to retain releases from liquid overflows as discussed in Section 11.2 of this SER.
In the event of a spill, we postulated liquid flow directly into the water table below the radwaste bulding, with water move-a ment toward the Columbia River. For our elaluation, we assumed failure of a 20,000 gallon high purity waste collector tank entering the groundwater by seepage through the radwaste building floor. We calculated the liquid transit time for radwaste leakage to the Columbia River to be greater than 2,200 days. No credit was taken for dilution in the groundwater flow. Pending evaluation by the Hydrologic and Geotechnical Engineering Branch, we have tentatively concluded that dilution provided by the Columbia River will insure that concentrations atrany potable ~ water supply offsite will be less than 1% of Part 20 concentrations.
Based on our evaluation, we conclude that a failure of the tank l
will give a concentration at the nearest surface water in an unrestricted area of less than the limits of 10 CFR 20, Appendix B, l...
Table II, Col. 2.
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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TABLE 11.1 PRINCIPAL PARAMETERS USED IN THE CALCULATION OF RADIOACTIVE EFFLUENTS FROM WNP-2 4
Themal power 3458 MWt Capacity factor 0.80 6
Total steam flow (10 LB/hr) 14' 6
Mass water, reactor vessel (10 LB) 0.55 F. P. carryover fraction 0.001 Halogen carryover fracgion 0.02 Cleanup demin flow (10 LB/hr) 0.13 Fraction of feedwater thro gh cond. demin 0.7 Radwaste dilution flow (1 GPM) 4.
Mass, steam, Rx vessel (1 LB) 0.025 Air ejector offgas holdup (hours) 0.17 Reactor b1dg iodine release fraction
- 1.0 Reactor b1dg partic. release fraction
- 1.0 Auxiliary b1dg iodine release fraction
- 1.0 Auxiliary b1dg partic. release fraction
- 1.0 Radwaste b1dg iodine release fraction 1.0 Radwaste b1dg partic. release fraction 0.01 Charcoal delay system 3
Kr adsorption coefficient (cm /g) 105 Xe adsorption coefficient (cm /g) 2410 Number condenser shells 3
Kr holdup time, days 1.855 Xe holdup time, days 42.6 Liquid waste inputs High purity system 2,000 GPD 0.15 PCA 0.01 Discharge fraction 0.4 Days, collection 0.03 Days, decay 100 DF
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10 DF Cs 100 DF Other Nuclides Low purity system 5,700 GPD 0.13 PCA i
1.0 Discharge fraction l
1.4 Days, collection l
0.03 Days, decay 100 DF I
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- For MK, Il containment, combine release values from computer printout for RX Bldg. and Aux. Bldg to obtain MK II containment releases.
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TABLE 11.1 (Continued) i t
Chemical waste system 600 GPD 0.02 PCA I
0.1 Discharge fraction 11 Days, collection 0.83 Days, decay.
100 DF I
100 DF Cs 100 DF Other Nuclides a
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TABLE 11.2 DESIGN PARAMETERS OF PRINCIPAL COMPONENTS ' ONSIDERED IN C
THE EVALUATION OF LIQUID AND GASEOUS RADI0 ACTIVE WASTE TREATMENT SYSTEMS COMPONENT NUMBER CAPACITY, EACH a
LIQUID SYSTEMS EQUIPMENT (HIGH PURITY) DRAIN PROCESSING SYSTEM Waste Collector Tank 1
Pre-Coat Filter
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20,000 gal}ons 188 ft Demineralizer 1
65 ft3 Waste Sample Tanks 2
20,000 gallons Waste Surge Tanks 1
70,000 gallons FLOOR (LOW PURITY) DRAIN PROCESSING SYSTEM Floor Drain Collector Tank 1
20,000 gal}ons Pre-Coat Filter 1
188 ft3 Demineralizer 1
65 f t Sample Tank 1
20,000 gallons CHEMICAL WASTE PROCESSING SYSTEM
. Chemical Waste Tank 2
15,000 gallons Concentrator (Evaporator) 2 10 gpm Distillate Tanks 2
15,000 gallons Concentrated Waste Tank 2
700 gallons GASEOUS SYSTEMS" RECHAR SYSTEM Catalytic Recombiner 2
350 psig, 900 F Design Condenser 1
350 psig, Shell Design Pressure 900 F Design Temp.
Charcoal Adsorber Beds 8
Carbon Steel, 350 psig Design Pressure, 250 F Design Temp.
Charcoal
.'24 tons Activated Carbon l
8Quality Group and Seismic design in accordance with Regulatory Guide 1.143.
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1 TABLE 11.3 PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM Stream Monitored Number Monitor Classification Monitor Sensitivity LIQUID
-6 RHR Standby Service Water 2
Gamma-Sci ntillation 1 x 10 uCi/ml Reactor Building Closed 1
Gamma-Sci ntillation 1 x 10-6 uC1/ml Cooling Water
/
Radwaste Effluent 1
Gamma-Scintillation 1 x 10-6 uCi/ml Circulating Water Effluent 1 Gamma-Sci ntillation 1 x 10-6 uCi/ml Service Water
.1 Gamma-Sci ntillation 1 x 10-6 uti/ml
-0 Turbine Building Sump 3
Gamma-Scintillation 1 x 10 uCi/ml Di scharge Condensate Storage Area 1
Gamma-Sci ntilla tion 1 x 10-0 uCi/ml Floor Drain GASE0US Reactor Building Exhaust 4
Geiger-Mueller (not provided)
Plenum Of fgas Post-Treatment 2
Geiger-Mueller (not provided)
Reactor Building Elevated Vent
-6
~
(Normal raligM 1
Beta-Scintillation 1 x 10 uC1/ml
~~
( Accident range)
Turbine Building Vent
-0 (Normal range) 1 Beta-Scintillation 1 x 10 uCi/ml (Accident range)
Radwaste Building Vent
-0 (Normal range) 1 Beta-Scintillation 1 x 10 uCi/ml (Accident range)
- Applicant has not provided details of design of monitors to meet Sections II.F.1-1 and II.F.1-2 of NUREG-0737.
a r-
.