ML20056E008

Forwards Drafts of Revised Sections 11.2,11.3,11.4 & Associated Drawings That Will Be Incorporated in Amend 32 as non-proprietary.Proprietary Versions of 11.2,11.3 & 11.4 Will Be Retained in GE Design Record files.W/16 Figures

ML20056E008
Person / Time
Site:	05200001
Issue date:	08/16/1993
From:	Fox J GENERAL ELECTRIC CO.
To:	Poslusny C Office of Nuclear Reactor Regulation
References
NUDOCS 9308190180
Download: ML20056E008 (51)

Text

i GENuclear Energy cene aweax company 17E Curner Avenue. kn Jose. CA 9512S August 16,1993 Docket No. STN 52-001 Chet Posiusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated ABWR Schedule - Revised Sections 11.2, 3,11.4 and Associated Drawings

Dear Chet:

Enclosed are drafts of revised Sections 11.2,11.3,11.4 and the associated drawings (Enclosure 1) that will be incorporated in Amendment 32 as non-proprietary.

t The proprietary versions of the 11.2,11.3 and 11.4 will be retained in GE's Design Record Files.

Sincerely, i

<k k Jack Fox Advanced Reactor Programs cc: Alan Beard (GE)

Norman Fletcher (DOE)

Mike Song (GE)

-cn-r-unw is o

\\\\ \\

9308190180 730816 7

\\

PDR ADOCK 05200001 F

A PDR N

23A6100 Rev. 2 ABWR Standard Safety Analysis Report 11.2 Liquid Waste Management 11.2.1 Design Basis 11.2.1.1 Design Objective The Liquid Radwaste System is designed to segregate, collect, store, and process potentially radioactive liquids generated during various modes of typical plant operation: startup. nonnal operation, hot standby, shutdown, and refueling. The system is designed such that it may he operated to maximize the recycling of water within the plant, which would minimize the releases ofliquid to the environment. Maximizing icculing serves to minimize the potential for exposure of persons in unrestricted xcas from the liquid release pathway.

11.2.1.2 Design Criteria The criteria considered in the design of this system include (1) minimization of solid waste shipped for burial, (2) neduction in personnel exposure, (3) minimization of offsite releases, and (4) maximizing the quality ofwatcr returned to the primaiy syMcm.

Per General Design Criterion 60 of 10CFR50 Appendix A, the Ibulwaste System design includes means to suitably contiol the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid wastes produced during nonnal scactor operation, including anticipated operational occurrences. These operational occurrences include condenser !cakage, maintenance activities, and process equipmen t downtime. The Liquid Radwaste System provides one discharge line to the canal.

Radiation monitoring equipment is placed on this line to measure the activity dischanged and to assure that specified limits aie not exceeded. The single discharge line is fed by the hot shower drain (IISD) sample tanks (a very low level radioactivity som cc) or one of the two sample tanks which usually contain condensate quality water.

In addition to providing a means for a controlled (i.e., hatch) discharge, the sample tanks also function as surge tanks to minimize or delay the offsite discharge ofliquid volume for which there is no immediate room available in condensate storage.

Means are piorided for monitoring effluent discharge paths that may be released from nor mal operations, including anticipated operational occurrences and fr om postulated accidents. The monitoring ofliquid release as required by GDC 64 is accomplished in two steps. First, the sources of release are only from either the llSD receiver t;mL or the sample tanks. These tanks have the necessag connections to the sampling system to allow analysis prior to discharge.

The 1 iquid Ituhraste System is designed to treat process liquids with radionuclide (oncentrations associated with the design basis fuel leakage and produce water suitable for accycle to condensate storage. Plant water halance considerations may require the Liquid Waste Management - DRAFT TL24

23A6100 Rev. 2 ABWR StandardSafety Analysis Report 1

discharge of processed liquids to the einirons, in which case umcentrations of radionuclides in the effluent will meet the requirements of 10CFR20. Liquid discharge to the canal may be initiated hom only one sample tank at a time. The discharge sequem e is initiated manually. No single error or failure will result in discharge. The design will maintain occupational exposuie as low as practicable in accordance with NRC Regulatory Guide 8.8 while operating with the design basis fuel leakage.

The low conductivity waste (ILW) filteis, mixed-hed demineralizers and concentrators are pressure vessels.The collection and sample tanks operate at atmospheric pressure.

The Liquid Radwaste System is essentially a manual-start and automatic-stop process.

Process and radiation instruments are described in Section 11.5. The instrumentation allows for the initiation of processing from the >hielded control room area. To ensure that the system perfonns its intended function in the event of failme of key components, iedundancy is prosided.

Input to parallel tankage is a feature of the design. Upon high level signals, inputs are automatically iouted to a parallel tank. Ifinput should continue, high-high level results in annunciation in the radwaste control room. Where practical, individual tanks and process equipment are located in separately shielded rooms. Pumps and valves in general are located in dedicated operating galleries. Piping to and from these pumps and valves penetrate shield walls only to the extent necessary to connect to the process equipment. Runs of piping between process equipment an c contained either within the shielded areas or shielded pipe runs so that operating peisonnel exposure is kept to a ininimuni.

I 11.2.1.2.1 Quality Classification, Construction, and Testing Requirements Equipment and piping at e designed and constructed in accordance with the applicable codes listed in Table 11.2-1. The equipment and piping will comply with the i

requirements of Regulatory Guide 1.143.

Regulatory position C.l.2.1 of Regulatorv Guide 1.!43 requires that high level in the (ondensate storage tank be alarmed. Activities which send water to the condensate storage tank aic controlled either in the radwaste building control room or the main control room. The location of alanus is interpreted to be in the radwaste building control room and the main control room.

11.2.1.2.2 Seismic Design The buildings housing the liquid radwaste processing equipment are designed in au ordance with the Uniform Building Codes. These buildings are not designated as Seismic Category 1. Per iegulatorr position 1.1.3 of Regulatorv Guide 1.43, the base mat and outside walls are Seismic Cauegorv I to a height nec essary to retain spilled liquids within the building.

11.2-2 Liquid Waste Management - DRAFT l

J

23A6100 Rev. 2 ABWR Standard Safety Analysis Report 11.2.1.3 Occupational Exposure I)esign features to minimize occupational exposure include:

(1) 1)esign of equipment to minimize scivice time (2) location ofinstruments acquiring calibration in a central. station outside of equipment cells (3) Arrangement of shiehl wall penetrations to avoid direct exposure to normally occupied ar eas (4) Piping design to minimize crud traps and plateout (there are no socket wehls in contaminated piping systems)

(5) Provision for remote pipe and equipment flushing (6) Utili7ation of remote viewing and handling equipment as appropriate (7) A centralized sampling station to minimize exposure time (H) Controlled tank vents 1)esign of the building ventilation system includes provision for removal of radiohalogens if the actual dose pathways in the environs indicate the potential of exceeding the annual dose objc(tives of 10CFR50 Appendix 1.

11.2.2 System Description The L.iquid Radwaste System is composed of three subsystems designed to collect, treat, and recyde or dischan ge different categories of waste water. The three subsystems are the low Conductivity Subsystem, liigh Conductivity Subsystem, and Detergent Waste Subsystem.

11.2.2.1 Low Conductivity Subsystem This subsystem collect _s and processes clean radwaste (i.e., water of relatively low conductivity). Equipment drains and backwash transfer waterare typical of wastes found in this subsystem. These wastes are collected, filtered for removal ofinsolubles, demineraliicd on a mixed resin, deep-bed deminerali7ers for removal of solubles, processed through a second polishing demineralizer, and then routed to condensate storage unless high conductivity requiies r(cycling for further treatment. A second LCW filter, arranged in parallel with the first, is also provided.

Liquid Weste Management - DR4FT 11.2-3

23A6100 Rev. 2 ABWR Standard Safety Analysis Report 11.2.2.2 High Conductivity Subsystem This subsystem collects and processes dirty adwaste (i.e., water of relatively high conductivity and solids content). Floor drains are typical of wastes found in this subsystem. These wastes are collected, chemically adjusted to a suitable oH for evaporation, and concentrated in a forced-circulation concentrator with a submerged, steatn-heated element to reduce the volume of water containing contaminants and to decontaminate the distillate. The distillate is demineralized to remove any soluble contaminants that could potentially be carried over from the concentrator.

11.2.2.3 Detergent Waste Subsystem This subsystem collects and processes detergent wastes from personnel showers and laundiy operations. Normally, detergent wastes are collected in one of two detergent drain tanks and processed through a detergent filter and discharged.

Decontamination factors used for evaluations of the system are within those values in Table 1-5 of NUREG-0016.

Detergent wastes will be discharged after filtration. However, during periods of high launday use, such as during outages, excess laundry above the capacity of the plant laundry will be sent offsite for processing by a licensed vendor. By administrative control, die amount of activity from both detergent wastes and from the l_CW sample tasks will be limited so that the total annual liquid releases will not exceed 0.1 Ci/ year.

11.2.2.4 Estimated Releases The I.iquid Radwaste System is designed with adequate margin so that liquid waste shouhl not be discharged except as needed to maintain the plant water balance.

Radwaste operational flexibility is required to assure continued plant operation. Under these conditions, discharge of excess water processed through the High Conductivity Subsystem may be desirable.

The various strcam flow rates and the different combinations ofevents that supplywater to the radwaste systern for the treatment have been tabulated.The radwaste system is conservatively designed to handle the largest vohune expected to be produced. The liquid radwaste subsystems have ample capacity to process the maximum daily generation rate ofliquid wastes as shown in Table 11.2-2.

Regeneration of the condensate demineralizers will not be performed. NURECM)016, Rev.1, recommen<1cd complete resin regeneration, which produced a large volume of waste, every three to five days. The resin will be icplaced when nec essary. Titanium-tubed condensers have been virtually leak-free. Also, the use of condensate hollow fiber filters before the condensate demineralizers have reduced the amount ofinsoluble 11.2 4 Liquid Waste Management - DRAFT

23A6100 Rev 2 ABWR Standard Safety Analysis Report solids whic h come into contact with the s esin. As a result, it is expected that resin replacement will be less than once per year.

Decanting of the CUW phase separator is an infrequent event. It is expected to occur 3

once cath six months with an expected volume of 68 m. The LCW Subsystem can process this volume in addition to the other wastes.

The components of the Liquid Radwaste System are si/ed based on processing the maximum daily vohnne within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The criteria is more conseirative than basing the sizing upon normal expected waste volum s.

11.2.2.5 Release Points The release point for liquid discharge to the environment is the discharge of the effluent from the sample tanks or the shower drain sample tanks as indicated on the pioress diagnuu (Figure 11.2-1).

11.2.2.6 Dilution Factors Dilution factors used in evaluating the release ofliquid efiluents are site dependent; however, for the purpose of evaluating the radwaste system against design objeaives stated in Subsection 11.2.1, it is conservatively assumed that the expected 0.1 Ci/yr is 3

released to a discharge canal having a flow of 340 m /hr. Also,it is assumed that a dilution factor of five exists between the discharge canal and subsequent consumption or recreational acthity invohing liquid ellluent. These assumptions are considered very conservative and are expected bound conditions found at any actual site.

If it assumed that 10% of the ucated waste from the high conducthity subsystem is discharged, then the annual acthity release of fission and activation products would be 0.002 cmies (excluding tritium), based on operating with the design basis radioactivity concentrations with an 80% plant capacity factor. The annual average liquid releases and the liquid pathway dose analyses ar e shown in Tables 12.2-22 and 12.2-23. They were calculated assuming release of up to 0.05 Ci/y of detergent waste and 0.05 Ci/y of 3

tr eated HCW. A dilution flow of 340 m /hr for evaluation of compliance with 10CFR'.D and an additional dilution by a factor of ten in the discharge canal for dose evaluations were used. Table 12.2-22 and Table 12.2-23 discharges are in compliance with 10CFR50, Part 50, Appendix 1.

The reactor coolant acthity (RCA) fraction for each substream of the LCW and HCW are shown in Table 11.2-3.

The capabilities of the tank, pumps and other components of the liquid radwaste subsystems are in Table 11.2-4.

t Liquid Was e Management-DRAFT 11.2-5

23A6100 Rev. 2 ABWR standard sarery Anatrsis Report r

11.2.3 Tank Resistance to Vacuum Collapse Severallow pressure tanks in the liquid waste management system and in other systems t hat could contain reat tor water wer e evaluated for potential vacuum collapse. The only tanks in the liquid waste management system that can contain reactor water, diluted with other wastes, are the LCW and HCW collector tanks. These tanks are vented to pierlude vacuum c ollapse. Vessels coded for internal pressuie in excess of 0.35 2

kg/cm g have,in general, been demonstrated to sustain full vacumn.

11.2.4 COL License Information The COL applicant shall provide the following which apply on a plant-specific basis.

(1) Compliance with Appendix 1 to 10CFR50 and the guidelines given in ANSI Std. N13.1," Guide to Sampling Airborne Radioactive Alaterials in Nuclear Facilities", Regulatory Guide (RG) 1.21,"Aleasuring and Reporting Radioactivity in Solid Wastes and Releases of Radioactive 51aterials in Liquid and Gaseous EfIluents from Light-Water-Cooled Nuclear Power Plants", and RG 4.15," Quality Assurance for Radiological N1onitoring Programs (Normal Operation)-Effluent Streams and the Environment" shall be prosided.

(2) A radiation monitor in the discharge line that will automatically terminate liquid waste discharges from the LCW, IICW or deter gent waste subsystem if radiation measurements exceed a predetermined level set by the COL applicant to meet 10CFR20, Appendix li, Table 2, Column 2 for the applicable subsystem shall be provided.

(3) Specific administrative controls and liquid effluent source terms to limit the liquid wastes to 0.1 Ci/yr shall be provided.

(4) Procedm es for demonstration of compliance with 10CFR50 (Appendix 1) i Sections 11 and 111 shall be provided.

(5) Administrative controls to limit the instantaneous disc harge concentrations of the radionuclides in liquid efIluents to an um estricted area to within the limits in 10CFR20. Appendix II, Table 2. Column 2 shall be provided.

(6) Quality assurance (operations) provisions of the liquid radwaste systems shall be provided.

i 11.2 6 Liquid Waste Management - DRAFT l

2346100 Rev 2 ABWR Standard Safety Analysis Report Table 11.2-1 Equipment Codes for Radwaste Equipment (from Table 1, RG 1.143)*

Vender Qualification inspection and and Equipment Design and Fabrication Materials Procedures Testing Pressure Vessels ASME Code Section ASME Code ASME Code ASME Code Section Vill, Div.1 Section 11 Section IX Vill, Div.1 i

t Atmospheric ASME Code Section 111, ASME Code ASME Code ASME Code

• Section Tanks Class 3,or API 650,or Section 11 Section IX 111, Class 3, or API 650, AWWA D-100*

or A\\%VA D-100*

0-15 psig Tanks ASME Code

• Section 111, ASME Codet ASME Code ASME Code' Section i

t Class 3, or API 620 Section 11 Section IX 111, Class 3, or API 620 Heat Exchangers ASME Code Section til, ASME Code ASME Code ASME Code Section Div.1 and TEM A Section il Section IX Vill, Div.1 Piping and ANSI B31.1 ASTM and ASME Code ANSI B31.1 Valves ASME Code Section IX i

Section 11 Pumps Manufacturer's ASME Code ASME Code ASME Cnde' Section Standardsf Section ll or Section IX 111, Ctr,ss 3; or Manufacturer's (as required) Hydraulic Institute Standard 4

i Manufacturer's material certificates of compliance with material specifications may be provided in lieu of certified material.

t Fiberglass-reinforced plastic tanks may be used in accordance with appropriate articles of Section 10 of the ASME Boiler and Pressure Vessel Code for applications at ambient temperature.

• ASME Code stamp, material traceabihty, and the quahty assurance criteria of Appendix B to 10CFR50 are not required. Therefore, these components are not classified as ASME Code Class 3.

f Manufacturer's standard for the intended service. Hydrotesting should be 1.5 times the design pressure.

Table 11.2-2 Capability of Liquid Radwaste Subsystems to Process Expected Wastes Hours to Capacity of Limiting Normal Waste Maximum Daily Process Max.

Subsystem Processing Equipment Generation Rate Generation Rate Daily Rate 3

3 3

3 LCW 30 m /hr 720 m / day 55m / day 615 m / day 20.5 hr 3

3 3

3 HCW 6 m /hr 144 m / day 15 m / day 65 m / day 10.8 hr 3

3 3

3 DW 12 m /hr 288 m / day 31.3 m / day 79 m ! day 6.7 hr Liquid Waste Management-DRAFT t t.2 7

23A6100 Rev. 2 ABWR Standard Safety Analysis Report Table 11.2-3 Reactor Coolant Activity (RCA) Fraction LCW ACTIVITY Drain Volume 3

Area Drain Source Activity m / day Drywell Steam valve seal leakage R

1.5 D/W cooler drain R

2.9 Reactor Building Steam valve seat kakage R x 0.1 1.5 Sampling drain R x 0.1 4.3 CRD pump seal drain R x 0.1 0.2 Others R x 0.1 9.0 Turbine Building Sampling Drain R x 0.001 2.7 Others R x 0.001 12.3 Radwaste Building Sapling Drain R x 0.1 0.05 Others R x 0.1 4.95 01hers R x 0.1 10.0 HCW Activity Reactor Building Floor Drain R x 0.01 5

Turbine 9uilding Floor Drain R x 0.01 5

Service Building Floor Drain R x 0.01 2

Radwaste Building Floor Drain R x 0.01 3

• R = specific activity of reactor water Chemical wastes are expected as fo!Iows:

3 Floor Drain 0.065 m / day 3

Laboratory drain 0.01 m / day Condensate from 3

solidification sys DA2S_rD ld3Y 3

Total 0.101 m / day 11.2 8 Liquid Waste Management - DRAFT

23A6100 Rev. 2 ABWR Standard Safety Analysis Report Table 11.2-4 Capacities of Tanks, Pumps, and Other Components Component Volume or Process Flow Rate LCW System 3

LCW Collector Tanks (two) 430 m / tank 3

LCW Hollow Fiber Filter (two) 15 m / unit 3

LCW Demineralizer (one) 30 m /hr l

3 LCW Backup Demineralizer (one) 36 m /hr 3

LCW Sample Tanks (two) 430 m / tank 3

RW/B LCW Sump 4m 3

RW/B LCW Sump Pumps (two) 10 m /hr/ unit 3

LCW Collector Pumps (two) 220 m /hr/ unit 3

LCW Sample Pumps (two) 220 m /hr/ unit HCW System 3

HCW Collector Tank (two) 45 m / tank 3

HCW Evaporators 3.0 m /hr/ unit 3

HCW Demineralizer 6.0 m /hr 3

HCW Distillate Tank 16 m 3

HCW Collector Pumps (two) 60 m /hr/ unit 3

HCW Distillate Pumps (two) 30 m /hr/ unit 3

HCW Evaporator Recirculation Pumps (two) 600 m /hr/ unit 3

RW/B HCW Sump 4m 3

RW/B Sump Pump (two) 10 m /hr/ unit Waste Sludge System 3

CUW Backwash Receiver Tank 60 m 3

CF Backwash Receiving Tank 60 m 3

CUW Phase Separator (two) 100 m / unit Spent Resin Storage Tank 50 m3 3

CUW Backwash Transfer Pump (two) 120 m /hr/ unit 3

CF Backwach Transfer Pump (two) 120 m /hr/ unit 3

Decant Pump (two) 10 m /hr/ unit 3

Slurry Recirculation Pump (two) 200 m /hr/ unit 3

Studge Pump (two) 10 m /hr/ unit liquid Waste Management - DRAFT 11.2-9

23A6100 Rev. 2 i

ABWR standardsarety Analysis Report Table 11.2-4 Capacities of Tanks, Pumps, and Cther Components (Continued)

Component Volume or Process Flow Rate 3

Spent Resin Slurry Pump (two) 100 m /hr/ unit Concentrated Waste System 3

CONW Liquid Waste Tank (two) 16 m / tank 3

CONW Liquid Waste Pump (two) 32 m /hr/ unit Detergent Waste System HSD Receiver Tank (one) 33 m3 3

HSD Sample Tanks (two) 210 m /each 3

HSD Receiver Pumps (two) 25 m /hr/each 3

HSD Sample Pumps (two) 80 m /hr/each 3

HSD Filters (two) 6 m /hr/each Notes.

(1) Each HSD receiver tank is capable of collecting the normal volume of detergent wastes,11.3 3

m / day. This subsystem collects waste liquids from systems that are normally nonradioactive but may, under certain conditions, come into contact with radioactive liquids. The storm drains are sent to the HSD sample tanks from which it is discharged if desired. If needed, the storm drain water may be treated by the HSD filters prior to discharge.

(2) Water is discharged from this system from the HSD sample tanks.

(3)The following are pro'

.s flow rates. The remainder of the flow is recycled.

Pump Process Flow Process Flow 3

Rate-m /hr Diagram Stream No.

LCW Collector Pumps (two; 30 5

LCW Sample Pumps (two) 40 9

HCW Collector Pumps (two) 6 26 HCW Distillate Pumps (two) 6 29 9)The LCW sample tanks are shared by both the LCW and HCW systems.

k 112-10 Liquid Waste Management-DRAFT

23A6100 Rev. 2 ABWR Standard SafetyAnalysis Report r

The following figurbs are located in Chapter 21 (C size,17" x 22"):

Figure 11.2-1 Radwaste System PFD (Sheet 1)

I

[

I i

f k

l l

Liquid Waste Management - DRAFT 11.2 11/12

23A6100 Rev. 2 ABWR Standard Safety Analysis Report

)

i 11.3 Gaseous Waste Management System 11.3.1 General i

The objectise of the Gaseous Waste Management (GFM) or OfTgas System is to process and c ontrol the release of gaseous radioactive ellluents to the site environs so as to maintain the exposm e of persons in unrestricted areas to radioactive gaseous efiluents as low as s easonably achievable (10CFR50 Appendix 1). This shall be accomplished while maintaining occupational exposure as low as reasonably achievable and without limiting plant operation or availability.

The of fgas System provides for holdup and decay of radioactive gases in the ofTgas from the air ejector system of a nu(lear reactor and (unsists of process equipment along with tuonitosing instnlmentation and control cornponents.

The purpose of the Offgas System is to minimize and conuol the sclease of radioactise i

material into the atmosphere by delaying and filtering the offgas process stream

< ontaining the radioactive isotopes of krypton, xenon, iodine, nitiogen, and oxygen sufficiently to achieve adequate decay before discharge from the plant.

The Offgas Svstem design minimizes the explosion potentialin the OITgas System through recombination of radiolytic hydiogen and oxygen under connolled wnditions.

11.3.2 Design Criteria The Offgas System is designed to limit the dose to offsite persons from routine station icleases to significantir less than the limits specified in 10CFR20 and to operate within the iclevant limits specified in the technical specifications.

As a conservative design basis for the Offgas System, an average annual noble radiogas sour ce term (based on 30-minute decay) of 100,000 pCi/sec of the 1971 mixture will be assumed. Table 11.3-1 provides the design basis noble gas source terms referenced to 30-minute decay. The system is mechanically capable of piocessing three times the somcc term without aflecting delay time of the noble gases. Also listed is the isotopic 3

distribution at t=0. With an air in-leakage of 51 sm /h, this ticatment system results in a delay of E hours for krypton and 42 <tays for xenon.

Using the gisen isotopic ac tivitic:, at the discharge of the OfTgas System, the decontamination fac tor for each noble gas isotope can be detennined.

Subse(tion ;1.1.1.1 presents source terms for normal operational and anticipated

[

occunem e scleases to the primary coolant. The table in this section,if not designated otherwise, is based upon a design basis oflgas release rate of 100,000 pCi/sec of noble gases and 700 pCi/sec of I-131. For nonnal expec red condition, the leak rates and doses aic expec ted to be less than one quarter of the design basis numbers.

Gaseous Waste %nagement System - DRAFT 11.3-1

23A6100 Rev. 2 ABWR Standard Safety Analysis Report The average annual exposure at the site boundasy during normal operation from all gaseous sourt es is not expected to ext ced the dose objectises of 10CFR50 Appendix I in terms of actual doses to actual persons (Subsection 12.2.2A). The radiation dose design basis for the ticated offgas is to provide suflicient holdup until the required f raction of the radionuclides has decayed with the daughter products retained by the (barcoal and the Ihgh Efliciency Particulate Air (HEPA) filter.

The Offgas System equipment is selected, arranged, and shielded to maintain occ upational exposure as low as reasonably achievable in accordance with NRC Regulatory Guide 8.8.

The Offgas System is designed to the requirements of the General Design Criteiia pr eviously desciihed in Subset tion I L2.1.2.

The Offgas System is also designed to the following codes and standards:

i

)

(1)

U.S. Nuclear Regulatory Conunission, Code of Federal Regulations,10CFR20, Standards for Protection Against Radiation; and 10CFR50 Appendix I, Numerical Guides for Design ()hjettives and Limiting Conditions for j

( >pciation to 51ect the "As Low As Is Reasonably Achievable" for Radioactive Slaterial in Light-Water Cooled Nuclear Power Reactor Effluents.

(2) Nuclear Regulatory Conunission (NRC), Regulatory Guide 1.143, Design l

Guidan(c for Radioactive Waste hianagement Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants.

(3) American Society of Alechanical Engineers (ASNIE) Iloiler and Pressme Vessel Code, Sc(tion Vill-Division 1.

(4) American Institute of Steel Construc tion (AlSC),51anual of Steel Constnation,7th Edition.

(5) American National Standards Institute ANSI /ANS-55A, Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants.

11.3.3 Process Description d

11.3.3.1 Process Functions

$1ajor pro (ess functions of the Offgas System inulude the following:

(1) Dilution of air ejector offgas with steam to less than 4% hydrogen by volume (2) Recombination of radiolytic hydrogen and oxygen into water to reduce the gas solume to he ticated and the explosion potential in downstream process components 11.3 2 Gaseous Waste Management System - DRAFT

i 23A6100 Rav. 2 ABWR Standard Safety Analysis Report (3) Two-stage condensate of bulk water vapor first using condensate and then chilled water as the coolan t reducing the gaseous waste sticam temperature to 18'C or less (4) Dynamic adsorption of krypton and xenon isotopes on charcoal at about 38 C (5) Filtration of ofTgas (6) Monitoring of offgas radioactisity levels and hydrogen gas concentration (7) Release of processed offgas to the atmosphere (8) Discharge ofliquids to the main condenser and radwaste systems Major process functions of the ventilation systems are described in Section 9.4.

11.3.3.2 Process Equipment Major pr ocess equipment of the Offgas System consists of the following:

(1) Steam dilutionjets as part of the main condenser air ejector assembly (not a part of the Offgas System)

(2) Recombiners, including a Pr cheater section, a Catalvu section, and a Condenser section (3) Coolcr-condensen s (4) Activated charcoal adsorbers (5) lligh elliciency particulate air (IIEPA) filter j

(6) Monitoring instrumentation (7) Process instrumentation and contiOls Major piocess equipment of the ventilation systems are described in Section 9.4.

i 11.3.3.3 Process Facility The Offgas System process equipment is housed in a reinforced-concrete structure to provide adequate shielding. Charcoal adsorbers are installed in a temperature monitored and controlled vault. The facility is located in the Turbine Building to minimize piping.

Geseous Wasic Management System - DRAFT 11.3-3 4

23A6100 Rev. 2 ABWR Standard Safety Analysis Report Reactor condensate is used as the coolant for the offgas condensers. In this capacity:

(1) The temperature of condensate supplied to the ofTgas condenser should not ext ced Mui"C during periods of normal operation nor 43'C duiing periods of startup (main condenser evacuation) operation.

(2) The pressure of condensate supplied to the oligas condenser should not exceed the design pressure of the condenser.

(3) Reactor condensate isolation valvca should be normally open to both r ecombiner (ondensers.

If any of these conditions cannot be met with reactor condensate, the coolant should be supplied by a closed cooling water system oi ncliability and quality equal to that of r eac tor condensate.

The gaseous waste su cam is then cooled to 18cC or less in the cooler condenser. Chilled l

water (PC) is used from the llNCW System (Subsection 9.2.12). The cooler condenser is located immediately above the offgas condenser and is designed tc n : 1ove any wndensed moisture from the gaseous waste stream. The condensed mo 3ture drains into the offgas condenser where it is sent to the main condenser.

The gaseous waste stream is heated to approximately 38 C by ambient heating in the chaicoal vault.

Chapter 12 provides the radioactisity inventonics of the major Offgas System components dming normal plant operation. Radiation shiciding design provides adequate protection ofinstrumentation and plant personnel required to monitor and operate the system.

11.3.4 Offgas System Description 11.3.4.1 Releases The significant gaseous wastes discharged to the OITgas System during normal plant operation are radiolytic hydrogen and oxygen, main condenser air inleakage, and radioactive isotopes of krypton, xenon, nitrogen and oxygen. The radiation dose from gaseous disc harge is Ininiarily external rather than ingestion or inhalation. When releasing gases from the plant, the plume or cloud is the source of radiation to the ground. The maximum radiation corresponds to the zone of maximum giound concentration. This, in turn,is a function of wind velocity and direction, the presence of building obstructions in the wake and other meteorological conditions in the area.

Fium the foregoing considerations a maximum release rate from the plant stack orvent can be established such that the maximum radiation dose to any area in the environs is riot ex(ceded.

11.3-4 Gaseous Waste Managernent System - DRAFT

t 23A6100 Rev. 2 ABWR Standard Safety Analysis Report Radioacthe particles are present as a result of radioarrive decay from the noble gas parents. These particulates are removed from the offgas stream by the condensation, adsorption, and fihration equipment. Ther efore, elfertively no radioactive particulates are :cleased from the Offgas System to the plant stark or vent.

1 Radioindines (notably 1-131) may be present in significant quantities in the reactor steam and in some extent carried over through the condensation stages of the OITgas l

System. Removal ofiodine takes place in the passage of process gas through the j

activated ( harroal adsor hers, so that essentially no iodine is released from the Offgas j

System to the plant stack or vent.

~1 he < riterion f or release of gaseous wastes to the annosphere, excluding accident sequences,is that maximum external radiation dosage to the environment be i

maintained below the maxinann dose objectives of Appendix 1 to 10CFR50 in terms of at tual doses to actual offsite persons. An instantaneous release rate, established by 10CFR20, of several times the annual average permissible release rate limit may be permitted as long as the annual aserage is not exceeded. Every reasonable effort has l

been made to keep radiation exposures and release of radioactive materials as low as casonably achievable (AIARA). The Offgas System discharge is routed to the plant stac k.

i 11.3.4.2 Process Design 3

The OfTgas System is illustrated in Figure 11.3-1.

l t

The SJ AE suction vahing is constrained to incorporate a minimum time period in bringing the recombiner units from zero to full oflgas flow in order to limit transient stresses. The minimum time period is 60 seconds, equivalent to linear valve characteristics. The SlAE suction vahing and ocam supply vahing is operable from the main contr ol ioom.

e 11.3.4.2.1 Dilution Steam The last stage of the air ejector is:

(1) Nom ondensing (2) Ahvays supplied with suflicient steam to maintain the hydrogen concentration downstream at less than 4% by vohime (3) 1.ocated in close proximity to the previous condensing stage in order to minimi/c the length ofline carrying a detonable mixture H) Provided a back]nessure capability Gaseous Waste Management System - DRAFT 11.3-5

23A6100 Rev. 2 ftBWR Standard Safety Analysis Report l

l l

There is no valve operation or failure mode which could cause the loss of dilution steam while the first-stage SteamJet Air Ejectors (SJAE) are operating. The air ejectors are capable of maintaining required main condenser vacuum concurrent with maxinuun l

ejector backpressure. Steam flow to the last-stage ejector is const2mt during all operating modes of the Offgas System and is not modulated with reactor powerlevel.

A flow meter is provided to measure the dilution steam flow to the last-stage air ejectors.

If the dilution steam flow falls below the specified value, the process offgas line suction valve between the main condenser and SJAE closes automatically. The esent is alarmed in the main contt ol room. The valve will remain closed until proper steam flow has been established. A high dilution steam flow above the specified valve also alarms in the main contr ol i oom.

The SJAE provides superheated steam at the inlet to the preheaters. The driving steam (dilution steam) to the SJAEs is nuclear steam or steam of nuclear quality. Nuclear quality steam is defined as steam having impurities in concentrations not exceeding that of nuclear steam.

Recombiner picheaters preheat gases to about 177 C for eflicient catalytic recombiner operation and to ensme the absence ofliquid water, which suppresses the activity of the recombiner catalyst. Maximum preheater temperature does not exceed 210'C should gas flow bc reduced or stopped. This is accomplished by using a maximum steam 2

pressure of 17.5 kg/cm, saturated. At startup, steam at this pressure is available before the process offgas is routed through the preheater to the recombiner cat;dyst. Electrical picheaters directly exposed to the offgas are not allowed. Each preheater connects to l

an independent final stage air ejector to pennit separate steam heating of both iccombiners dming startup or dning one recombiner while the other is in operation.

1 P cheater steam is nuclear steam for reliability. The picheater is sized to handle a dilution steam load adequately in addition to allowing for 5% plugged tubes.

1 11.3.4.2.2 Hydrogen / Oxygen Recombination Minimum perfonnance criteria for the catalytic recombiners are as follows:

(1) In nor mal full power operation, the hydrogen in the recombiner effluent does 3

not exceed 0.1 % by volume on a moisture-free basis, at the defined,10 m /hr, minimum air flow.

(2) During startup or other reduced power operations (between 1 and 50% of reactor rated power), the hydrogen in the recombiner effluent does not 3

exceed 1.0% by sohune on a moisture free basis at the defined,10 m /hr, minimum air flow.

11.3 6 Gaseous Waste Management System - DRAFT

i 23A6100 Rev. 2 ABWR Standard Safety Analysis Report l

(3) An intentional air bleed equal to minimum air flow is introduced into the i

system upstream of the operating recombiner when the main condenser air 3

inleakage falls below the defined minimum air flow of 10 m /hr. The out-of-senice recombiner catalyst is heated to at least 121*C by diluted steam injection before admitting process gas (containing hydrogen) to the rerombiner. Three temperature sensing elements are provided in each 1

catalyst bed and are located to record the temperature profile from inlet to 3

outlet.

l I

11.3.4.2.3 Condensing The offgas condensers (ool the recombiner efIluent gas to a maximum temperature of 68 C for nonnal operation and 5PC for startup operation. The condenser includes baffles to reduce moisture entrainment in the oligas. The unit is sized to handle the requned dilution steam load,in addition to allowing for 5% plugged tubes. The drain is rapable of draining the entire process condensate, including the 15% exc ess plus 9 m1/hr, hom the unit at both staitup and normal operating conditions, taking into au ount the possibility of condensate flashing in the return line to the main condenser.

The drain also incorporates a flow element so that higher flows due to tube leakage can be casily identified. The drain is a passive loop seal with a block valve operable from the main conuol room.

The gaseous waste stream is then cooled to IS"C or less in the cooler condenser. The cooler condenser is designed to remove any condensed moisture by draining it to the i

of fgas condenser.

1 11.3.4.2.4 Adsorption i

The activated (harcoal uses "arbitrauy" adsorption coefficient Kaib values for krypton i

3 3

and xenon at 25'C of at least 60 and 1170 cm /g, respectively (cm defined at 0 C and 1.0 atmosphere). Separate Karb laboratoq determinations of krypton and xenon are made for each mamifac turer's lot unless the manufacturer can supply pruof comincing I

to the pu rchaser that other lots of the same production nm immediately adjacent to the lot rested ar e equivalent to the lot tested with respect to krypton and xenon adsorption.

]

Other adsorption tests (e.g., dynamic coeflicients) may be acceptable, provided their equivalence to Karb tests for this purpose can be demonstrated. Charcoal particle size is 8-16 mesh (USS) with less than 0.5% under 20 mesh. Moisture content is less than 2%

by weight. Ignition temperattue will be above 150'C in air. Properties of acthated chan oal used in the adsorber vessels are on optimization of the following:

(1) High adsorption for krypton and xenon (2) liigh physical stability (3) liigh surface area Caseous Waste Management System - DRAFT 11.3-7

23A6100 Rev. 2 ABWR Standard Safety Attalysis Report (4) Low pressure drop (5) Low moisture content (6) liigh ignition temperature (7) Dust-free structure The krypton and xenon holdup time is closely approximated by the following equation:

K 51

'3 T=

(11.S1)

V r

whene T

Holdup time of a given gas

=

Rd -

Dynamic adsorption coeflicient for the given gas Weight of charcoal M

=

V Flow rate of the carrier gas in consistent units

=

Dynamic adsorption coeflicient values for xenon and krypton were reported by 11rowning (Reference 11.SI). General Electric has performed pilot plant tests at the Vallecitos Nuclear Center and the results were reported at the 12th AEC Air Cleaning Conference (Reference 11.3-2).

11.3.4.2.5 Fi!tration The filter assembly contains a single high efficiency water-resistant filter element capable of removing at least 99.97% of 0.3 micion particles, as tested at the factory with monmlispersed dioctylphthalate (DOP) smoke The initial flow resistance of the filter 3

does not exceed 2.54 cm water gauge (WG) at a water satmated air flow of 425 m /hr.

An upstream demister pad is not required in the filter assembly. The filter is capable of operating under 100% relative humidity conditions.

11.3.4.2.6 Noble Gas Mixture The fission product nobic gas composition used as the nominal design basis is 100.000 pCi/sec (after 30-minute decay) as defined in Section 11.1. During normal operation with no fuel leaks, a release rate of noble gases of about 100 pCi/sec (after 30-minute decay) may occur due to minute quantities of uranitun contamination. The system is also capable of safe mechanical operation at release rates of up to 400,000 pCi/sec (after 30-minute decay). Ilowever, the limits of Subsection 11.3.4.1 are calculated based upon the design basis acthity releases.

11.3 8 Gaseous Waste Management System - DRAFT

23A6100 Rev. 2 ABWR Standard Safety Analysis Report t

l I

11.3.4.2.7 Air Supply Carrier gas is the airleakage from the main condenser after the radiolytic hydrogen and oxygen are removed by the 1ccombiner. The air inleakage design basis is conservatively 3

assumed to be 18.2 m /hr total.The Sixth Edition ofIIcat Exchange Institute Standards for Steam Surface c ondensers (Reference 11.3-3), Paragraph S1 (c) (2),

indicates that with (criain conditions of stable operation and suitable construction, nonmndensibles (not including radiological decomposition products) shouhl not 3

exceed 10 m /hr fbi large condenscis.

An air bleed supply is prmided for:

3 (1) Dilution of residual hydrogen at air inleakages below 10 m /hr i

(2) Vahc stem sealing (3) Remmbiner startup (4) Illoc king dming maintenance (5) Instnnuent operation 4

(6) Providing an air flow through the standby iccombiner when processing offgas (7) Purging gas mixtures from process and instrument lines prior to maintenance 3

3 For dilution, at operating flows below 10 m /hr, the air bleed is 10 m /hr. Air flow rates f or system purging are specified as nonnal flow. These normal air purge flow rates ar e not used while the system Inocesses reactor offgas. The air is supplied from a mmpressor whic h does not use oil (br lubrication of the compressor cylinder, as oil

]

compr omises the performance of the catalytic s ecombiners and charcoal adsorbers. All sources of air capable of entering the process downsticam of the cooler condenser (i.e.,

valve double stem seals) have a dew point ofless than -l'C. During both startup and 3

nonnal operation,1.7 m /hr of air is bled to the standby recombiner trainjust downstream of the final SJAE suction valve for train pmging after switchover. Flow indicato s ar e provided on all air bleed lines to assure that proper air flow is being deliveied to the pmcess line or equipment. The air supply is protected from back flow of pmcess gas by two check vahes in series or a check valve and a pressure contiol valve 1

in series.

11.3.4.2.8 Charcoal Vault Temperature The charcoal adsorber vault air conditioning system is controlled at any selected temperatur e within a range of 2WC to 41 C. The temperature of the vault is maintained l

as indicated in Subsection 11.3.4.3.13.

Gaseous Waste Management System - DRAFT 11.3 9

i i

23A6100 Rev. 2 ABWR Standard Safety Analysis Report i

11.3.4.2.9 Rangeability The process (an acconunodate reactor operation from 0 to 100% of full power (full power is defined as the Nonnal Operating Case). In normal operation, radiolytic gas production varies linearly with thermal power. The process can acc onunodate an air i

3 How at 10 to 425 m /hr for the full range of reactor power operation.

In addition, the process can mechanically acconunodate a startup high air flow upon initiation of the steamjet air ejectors. This startup air flow results from evacuation of the turbine condensing equipment while the scartor is in the range of about 3 to 7% of rated power.

11.3.4.2.10 Redundancy All active equipment (e.g., pmnps, valves and instnunentation) whose operation is necessary to maintain operability of the Of fgas System is redundant. Passive equipment (e.g., chatcoal adsorber) is not redundant. Instrumentation that performs an information function and is backed up by design considerations or other instnamentation need not be redundant. Instlumentation used to record hydrogen concentration or actisity release (e.g., flow measurement, hydrogen analyzers) is also r edu ndan t.

Design provisions are incorporated which preclude the uncontrolled release of radioat tisity to the emironment as a result of anysingle equipment failure short of the equipment failure accident described in Chapter 15.

Design precautions taken to prevent uncontrolled releases of activity include the following:

(1) The system design minimizes ignition sources so that a hydrogen detonation is highly unlikely even in the event of a recombiner failure.

(2) The system pressure boundary is detonation-resistant in addition to the measure taken to avoid a possible detonation.

(3) All discharge paths to the environment are monitored-the normal effluent path by the Process Radiation Monitoring System and the equipment areas by the Area Radiation Monitoring System.

(4) Dilution steam flow to the SJAE is monitored and alanned, and the vahing is required to be such that loss of dilution steam cannot occurs ithout coincident loss ofinotive steam so that the process gas is sufliciently diluted if it is flowing at all.

11.3-10 Gaseous Waste Management System - DRAFT

i l

23A6100 Rev. 2 ABWR Standard Safety Analysis Report l

l l

l l

l 11.3.4.2.11 Charcoal Adsorber Bypass l

l A piping and vahing arrangement is provided which allows isolation and bypass of the chan oal adsorber vessel most likely to catch fire or become wetted with water, while continuing to process the of fgas flow through the remaining adsorber vessels. A nitrogen purge can be injected upstream of the vault entrance so that further combustion is prevented and the charcoalis cooled below its ignition temperatme.

Capability is provided to employ all or a poition of the charcoal adsorher vessels to treat the of fgas flow during normal or off-standard process operating conditions.

The main purpose of this bypass is to protect the charcoal during preoperational and startup testing when gas activity is zero or very low and when moisture is most likely to enter the charcoal beds. The bypass valve arrangement is such that no single valve failure or valve mis-operation would allow total charcoal hvpass. The bypass mode of

< haitoal operation is not normal for power operation. Ilowever, it may be used if the s esulting actisity release is acceptahic.

11.3.4.2.12 Valves All valves with operators located on the gas process stream are operable from the main wntrol r oom. Wheic radiation levels permit, valves handling process fluids are installed in senic e ancas wheie maintenance can be performed if needed dming operation.

j 11.3.4.2.13 System insulation The ( )f fgas System is adequately insulated, wheic needed. Non-sweating type insulation is used to minimize moisture condensation on external side of piping. Insulation j

requirements are discussed in Subsection 11.3.-l.3.8.

11.3.4.2.14 Nitrogen and Air Purge A nitrogen purge and air supplyline is connected to the offgas processjust upstream of the first inline charcoal adsorber sessel (guaid bed). This arrangement is to allow the vessel to be nitrogen purged after a possible fire is detected or dried with heated air if the chaicoal is wetted, while the offgas flow is bypassed around it and through the remaining (harcoal vessels. Another nitrogen purge line is also providedjust upsticam of the remaining (harcoal adsoiber vessels, which will allow them to be purged, if icquired, without interrupting the processing of of fgas through the first inline charcoal vessel. The isolation valves in the nitrogen and air purge lines and the connection for the gas supply are accessible from outside the charcoal vault.

11.3.4.2.15 Identification of Combustion Hazard All offgas equipment, piping and instnnnent lines that could contain a combustible mixtme of offgas are color mded or marled in some other suitable manner to ider:tify Gaseous Waste Management System - DRAFT 11.3 11

23A6100 Rev. 2 ABWR StandardSafety Analysis Report i

them. Tags are attached to the lines, and adjacent notices are prmided to warn of the hazards of welding in these areas.

11.3.4.3 Mechanical Design Portions of the system potentially contain a highly explosive mixture. Safety considerations require that ignition sources be minimized and that the system have the integrity to sustain an explosion.

Calculation methods for translation of detonation pressures into wall thickness are sunnnarized in the ANSI-55A standard referenced in Subsection 11.3.2. Equipment and piping will be designed and constructed in accordance with the requirements of Table 11.2-1.

11.3.4.3.1 Materials Per Regulatory Guide 1.143, regulatory position 1.1.2, materials for pressure-retaining (omponents of process sys: cms" are selected from those covered by the material specifications listed in Section II, Part A of the ASME 11 oiler and Pressure Vessel Code, except that malleable, wrought or cast-iion materials and plastic pipe are not allowed in this application. The components satisfy all of the mandatory requirements of the material specifications with regard to inanufacture, examination, repair, testing, identification and certification.

ihittle fracture control required of carbon steels used for equipment in the Offgas System is as follows:

(1) For equipment, piping, and valves with operating temperatures 93 C or greater, there are no special requirements.

(2) For equipment, piping, and valves with operating temperatures in the range O to 93^C inclusive, there are no special requirements, except that high quality material is used (e.g., SA 106 pipe is used instead of A-53 material).

11.3.4.3.2 Pressure Relief Adequate pressure reliefis provided at alllocatirms where it is possible to isolate a portion of the system containing a potential heat source. Adequate pressure reliefis also provided downstream of pressure-reducing valves to protect equipment from overpr essure.

• ' Pro (ess system" refers to that portion of the Offgas System that normally processes SJAE offgas.

11.3 12 Gaseous Waste Management System - DRAFT j

i

23A6100 Rev. 2 ABWR Standard Safety Analysis Report 11.3.4.3.3 Equipment Room Ventilation Control The equipment rooms are under positive ventilation control. Emironmental conditions are maintained within the following ranges:

Pressure Relative (static em Humidity Air Turnover Rate Area water gauge)

Temp (*C)

(%)

(room air changes)

Ollgas Illdg.

0.0 to - 0.63 4.4 min 20 min 3/ hour Area, except 21 normal 40 nonnal Equipment Cells 40 max 90 max Char coal

- 0.63 to -1.26 4.4 min 20 min 3/ hour Vault 35 normal 40 normal 65.6 max 70 max Other off gas

- 0.63 to -1.26 4.4 min 20 min 3/ hour i

Equipment Cells 21 normal 40 normal 48.9 max 90 max i

Dificiential pressure between general arcas and equipment cells is at least-6 mm W.G.,

so as to maintain a flow of air from clean areas into potentially contaminated areas. In addition, the general area air ventilation system is capable of removing suflicient heat from the proc ess piping, equipment, motors, and instrumentation so as to maintain the emironmental temperatures in the ranges cited above. All equipment cell and charcoal vault ventilation air is discharged without passing through occupied areas.

11.3.4.3.4 Maintenance Access Equipment will not numally be accessible for maintenance during system operation.

All equipment is available during the annual plant outage. The following are exceptions:

(1) The iedundant offgas recombiner trains are located in separate rooms to allow maintenance access to the standby train when processing offgas in the operable train.

(2) Control valving and hydrogen analyzers are accessible for maintenance during the out-of-service portion of their cycle.

(3) Charcoal vault air conditioning and ventilation equipment are accessible for maintenance during plant operation.

Gaseous Waste Management System - DRAFT 11.3-13 i

23A6100 Rev. 2 ABWR Standard Safety Analysis Report i

3 Maintenance vahing and a 1.7 m /hr air bleed on the process side of each valve are i

provided for items (1) through (3) above. Each air line incorporates a flow indicator, isolation vedve, and appropriate check valve (s).

The Offgas System is designed, constructed and tested to be as leaktight as practicable.

The allowable leakage is a function of the system specific acthity, the ventilation rate of the equipment cells, and the maximum permissible concentration (MPC) of the specific acthity. Field testing of Offgas System leakage has demons' rated a practical limit of detectability of lx10' atm-cc/sec. The major offgas acthities have an MPC of 4

5x10 pCi/cc. This requires isotope identification, which for an offgas system consists of kryptons and xenons (10CFR20, Appendix B, Table 1, Column 1).

Design features which reduce or case required maintenance or which reduce personnel exposure during maintenance include the following:

(1) Redundant components for all active, in-process equipment pieces located in separate shielded cells (2) No rotating equipment in the radioactive process stream but located either where maintenance can be performed while the system is in operation or in non-radioactive streams (3) Block vahes with air bleed pressurization for maintenance which is required during plant operation (4) Shielding of non-radioactive auxiliary subsystems from the radioactive process stream 1

Design features which reduce leakage and releases of radioactive materialinclude the following:

(1) Extremely stringent leak rate requirements placed upon all equipment.

piping and instruments and enforced by requiring as-installed helium leak tests of the entire process system (2) Use of weldedjoints wherever practicable (3) Specification of valve types with extremely low leak rate characteristics (i.e.,

bellows seal, double stem seal, or equal (4) Routing of drains through steam traps to the main condenser (5) Specification of stringent seat-leak characteristics for valves and lines discharging to the environment via other systems 11.3-14 Gaseous Waste Management System - DRAFT

1 23A6100 Rev 2 ABWR Stendard Safety Analysis Report 11.3.4.3.5 Leakage The leakage criteria apply from the SJAE through the filter of the Offgas System, including all process equipment and piping in between. Leakage from the process through purge or tap lines to external atmospheric pressure should be less than 0

0 atm cr/sc< and is not to be detectable by " soap bubble" test.This requirement does not apply to inline process valves. Leakage to a normally occupied area does not exceed l

10"' atm c(/sec. Leakage from the process side of the equipment to the atmospher e at 2

a dif ferential pressure of 0.36 kg/cm is limited to the following maximums:

Leak Rate (atm cc/sec)

Zone Equipment Piece Zone Total 0

lustrument panels 10 1

0 All process valves 10 4

4 SJAE to recombinci exit 10 10 Ret ombiner exit to exit of first (harcoal tank 10 5 x 10-2 4

Exit of first (haunal tank to exit oflast hed 10'2 10~ 3 Exit of last bed to exit of the system 10' 10 l

Insu ument panels (e.g., hydrogen analyzers) connected to process gas are enclosed, the enclosme maintained under a negative pressme, and vented to an equipment vault or to hmlding ventilation. To s educe instnunent line leakage, welded rather than iln caded connec tions are used whereser possible.

j 11.3.4.3.6 Vents and Drains i

Offgas System drains, depending on source, should be routed to either the condenser hotwell or to the Radwaste System. All piping is provided with high point vents and low l

point drains to permit system drainage following the hydrostatic test. These vents and dmins are scal-welded <losed prior to the finalleak test. All piping is pitched to allow draining to the nearest line or equipment drain. A water drain is provided on the process linejust upstream and downstream of the chanoal tanks. The process line to and from the < harc oal adsoibers is sloped so that there are no intervening low spots to 4

ac t as water traps.

11.3.4.3.7 Valves No vahes contiolling the flow of process gas are located in the charcoal adsorber vault.

Gate valves are rising-stem. wedge type Valve operators may be chosen for operating 2

pressure service (about 0.35 kg/cm ) rather than for the ASA rating required of the Gaseous Waste Management System - DRAFT 11.3-15

1 23A6100 Rev. 2 ABWR Standard Safety Analysis Report I

l valve body for explosion resistance. For all valves exposed to process offgas, valve seats (trim) aie all metal and spar k resistant; that is, at least one surface should be fabricated from one of the following materials or equivalent: American Ilrass Co. Everdur, 11eryllium Corp. of America-Ilenico, or Allegheny Ludlum-Nitanol.

j All valves exposed to pr ocess gas have bellows stem seals, double stem seals or equindent. Ilellows design pressure may bc the system operating pressure, provided the bellows seal is backed up by a packirs; seal. Acceptable alternates to bellows seal design are as follows:

l 1

(1) A ndre having a metal diaphragm backed up by a packing gland using Grafoil I

(Union Carbide Corp.) or equindent packing.

]

(2) A valve having a double stem seal and lantern ring tvpc bonnet, with Grafbil or equivalent packing with the lantern ring leakoff connection pressuriicd with nitrogen or air form an oil-free compressor to a pressure exceeding the normal system operating pr essme. The pressurization line includes a flow indicating device mounted on the udre (such as a purge gas rotameter Shuttle and Koerting Type 1875-V or equindent) with a scale in the 0.5 to 1.0 atm-cc/sec range, direct reading.

All valves exposed to process gas, except those specifically designated as control valves incorporate a backscating feature to minimize potential leakage. The bonnet seal of all ndves exposed to process gas are all metal or Grafoil type. It is iccommended that the bonnets of udves in inhabited areas such as instnunent panels he seal welded. All main process line valves are of bolted or welded bonnet design. Pressure seal bonnets are not used.

Valve external leakage is measured using an approved helium leak test procedure. In the case of double stem seal valves. the lantern ring may be pressuri7ed during testing to the pressme it will see in senice, and the vah e shall exhibit neither external leakage in excess of the specified maximum nor inward leakage of pressurizing air in excess of 1.0 atm cc/sec.

+

11.3.4.3.8 Insulation Materials Pipe insulating materials for offgas systems shall be from one of the following types or equivalent: S Glass, Refrasil. Cerufelt, Cerafiber, Marinite, Nextil, Fibr efax, Kaowool, or Nukon. Charcoal adsorber vault thermal insulation,if required, is tesistant to vault radiation levels and is protected against moisture by a vapor banier appropriate to the senice. Chlorides are not primitted in the insulating material applied to stainless steel equipment.

11.3 16 Gaseous Waste Management System - DRAFT

23A6100 Rev. 2 ABWR Standard SafetyAnalysis Report 11.3.4.3.9 Gaskets It is unaaeptable to use gasket sorting techniques to pass the equipment leak test. The required gasket design must have a 95% probability of sealing each time the flanged joint is closed. Process piping and vessels use a metal or spim! wound gasket, incorporating a compression limiting ring.

4 11.3.4.3.10 Flange Surface Finish Flanges used in the process sucam have a maximum surface roughness of 3 pm rms in a circular lay.

11.3.4.3.11 Recombiners The recombiners are mounted with the gas inlet at the bottom. The inlet piping has suflicient drains, traps and moisture separators to prevent liquid water from entering the recombiner vessel during startup. The recombiners are catalytic type with a non-dusting catalyst supported on metallic screens or ribbons. The catalyst is replaceable without requiring replacement of the external pressure vessel.

i Fabrication piocedures will take cognizanc e of catalyst poisons. Frcons, oil, halogens, and welding fumes are to be excluded from the catalyst bed at all times.

Because the possibility exists for all types of catalysts to dust to some degree and then migrate to non-steam-diluted portions of the system downstream of the recombiner, no flow paths exist wheichy unrecombined offgas can bypass the recombiners and ignite due to migrated catalyst.

11.3.4.3.12 Charcoal Adsotber Vessels The c harcoal adsniher beds are to be installed vertically. Bed settling could iesult in gas channeling. Bed settling in horizontal beds could result in excessive gas channeling.

Channeling in the charcoal adsorbers is prevented by supplying an effective flow distributor on the inlet, which has long columns and a high bed-to-particle diameter ratio of approximately 500. Underhill (Reference 11.3-4) has stated that channeling or wall effects may reduce efliciency of the holdup bed if this ratio is not greater than 12.

During transfer of the charcoal into the charcoal adsorber vessels, radial sizing of the l

charcoal will be minimi/ed by pouring the charcoal (by gravity or pneumatically) over a cone or other instrument to spread the granules over the surface. Temperature elements aic installed within the charcoal adsorber vessels in sufficient quantity to monitor the temperature profile with the flow pa h during operation.

1 l

Gaseotis Waste Management System - DRAFT 1L3-17

1 l

23A6100 Rev. 2 ABWH Standard Safety Analysis Report i

11.3.4.3.13 Charcoal Adsorber Vault The ternperature within the ( harwal adsor ber vault is maintained and controlled by appropriate connection (s) to the Turbine Building IIVAC System. The flow rate and temperature of the air supplied to the vauh has the capacity to cool the vault and couipment within from 66'C to 27"C in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The decay heat is sufliciently small that, esen in the no-flow condition, there is no sigmficant loss of adsorbed noble gases due to temperature rise in the adsorbers. The IIVAC design is capable of c ontiolling the vault temperature within 3 C over the range of 27 to 38'C The c harwal adsorbei vault itselfis designed for the temperatme ramge 27 C to 38*C, as it may be necessary to heat a vessel or the vault to 66*C (by the use of portable heaters) to f acilitate drying the charcoal. A smoke detector is installed in the exhaust sentilation duct from the charcoal adsorber vault to detect and provide alarm to the operator, as a (harcoal fisc within the vessel (s) usually results in the burning of the j

exterior painted surface.

j 11.3.4.3.14 Filter Cartridges The of fgas filter car tndge is designed to be readily r emovable from the filter vessel and i epla( cable.

11.3.4.3.15 Weld Inserts Weld inserts, othei than wnsumable ones, are prohibited from being in contact with the pr ocess or process dischanges, unless they ar e ground out af ter the weld is wmpleted.

11.3.4.3.16 Construction of Process Systems i

Picssuic-ictaining components of process systems employwelded construction to the maximum practicable extent. Process piping systerns include the first root valve on satuple and instnunent lines. Process lines are not less than 50 nun nominal pipe sire.,

Sample and instnnnent lines are not considered as portions of the process systems.

i Flangedjoints or suitable rapid diswnnect fittings are not used except where maintenam e requirernents clearly indicate that such construction is preferable.

Sciewed connections in which tincads proside the only seal are not used. Screwed wnnections haded up by seal welding or mechanicaljoints are used only on lines of i

20 nun nominal pipe size. In lines 20 nun or gicater, but less than 65 nun nominal pipe si/c. sodet y pc welds are to be used. In lines 65 mm norninal pipe size and larger, pipe welds are of the buttjoint type.

All welding mustituting the pressure boundarv of pressuic-retaining wmponems will be performed by qualified welders empiming qualified welding procedur es.

1? 3 16 Gaseous Waste Management System - DRAFT 4

4 l

23A6100 Rev. 2 ABWR Standard Safety Analysis Report 1

i i

11.3.4.3.17 Process-Piping Nozzles The pipe-to-shell connections are fabricated with integral reinforcing. Nonic reinfoicing pads are not utilized and are not acceptable.

11.3.4.3.18 Traps All traps incorporate a strainer upstream, in a reasonably accessible location for maintenance, to minimize the chance of debris plugging the trap. Trap designs are not used which,like the inverted-bucket design, incorporate a small, casily plugged orifice.

l The strainer blowdown line and trap bypass line used for trap maintenance is routed hack to the main drain line downstream of the trap to minimize the possibility of escaping process gas.

11.3.4.3.19 Moisture Separator A moistme separator should be incorporated into the cooler-condenser heat exchanger.

l 11.3.5 Other Radioactive Gas Sources I

Radioactive gases are present in the power plant buildings as a result of proc ess leakage j

and steam discharges. The process leakage is the source of the radioactive gases in the air discharged through the ventilation system. The design of the ventilation system is described in Section 9.4, the radiation activity levels from the ventilation systems in Section 12.3, and the ventilation flow rates in Section 9.4.

11.3.6 Instrumentation and Control Control and monitoring of the offgas process equipment is performed both locally and iemotely from the main control room. Generally, system control is from the main control room. Instrument components are installed, wherever possible, in accessible alcas to facilitate operation and maintenance. Only instrument sensing elements are permitted behind shield walls.

The temperature of the gaseous waste stream is measured in the preheater and at various locations in the recombiner to assme that recombination is occurring. The gaseous vaste stream temperature is also measm ed after both the offgas condenser and the cooler condenser to assure the stream is cooled sumciently to remove undesired moisture. All of these temperatures are alarmed in the main control ioom.

The flow rate of the air ejector offgases downstream of the recombiner is continuously recorded. This flow rate, in conjunction with activity concentrations in pCi/cc as measm ed by the monitor downstream of the recombiners and the monitor downstream of the charcoal adsorbeis, will permit monitoring fission gases from the reactor, Gaseous Warte Management System - DRAFT 11.3-19

23A6100 Rev. 2 ABWR Standard Safety Analysis Report calculation of offgas discharge to the vent in pCi/sec and will permit calculation of the (harcoal adsorber system performance.

Instnanentation and control of the ventilation systems are described in Section 9.4.

11.3.7 Quality Control The following, exerpted from ANS-55.4 (Section 11.3.2), prmides quality control featmes to be established for the design, construction, and testing of the Offgas System.

System Designer and Procurer (1) Design and Procurement Document Control: Design and procurement documents shall be independently verified for confonnance to the requirements of this standard by individual (s) within the design organization who ate not the originators of the document. Changes to these documents shall be verified or controlled to maintain conformance to this standard.

(2) Control of Purchased Material, Equipment and Senites: Meastues shall be established to ensure that suppliers c,f material, equipment and construction senices are capable of supplying these items to the quality specified in the procurement documents. This may be done by an evaluation or a sun ey of the suppliers' products and facilities.

(3) Handling, Storage and Shipping: Instructions shall be provided in procmement dormnents to control the handling, storage, shipping and pr esenation of material and equipment to pr event damage, deterioration and reduction of cleanness.

System Constructor (1) Inspection: In addition to required code inspections, a program for inspection of activities affecting quality shall be established and executed by, or for, the organization performing the activity to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity. This shall include the visual inspection of components prior to installation for conformance with procurement documents and the visual inspection ofitems and systems following installation, cleaning and passivation (where applied).

(2) luspection, Test and Operating Status: Measures shall be established to prmide for the identification ofitems which have satisfactorily passed required inspections and tests.

11320 Gaseous Waste Management System - DRAFT

23A6100 Rev. 2 ABWR StandardSafetyAnalysis Report I

(3) Identification and Corrective Action for Items of Nonconformance: Measures shall be established to identify items of nonconformance with regard to the requirements of the procurement documents or applicable codes and i

standards and to identify the action taken to correct such items.

)

Quality control for the ventilation systems is described in Section 9.4.

11.3.8 Seismic Design Offgas System equipment and piping are classified non-Seismi CategoryI.The support elements of the charcoal adsorbers, including legs or skirts, lateral supports (if j

requir ed) and anchor bo! ting, are designed such that the fundamental frequency of the vessels including all support elements, is greater than 33 Hz. The charcoal adsorbers, including sup;, ort elements, are designed to static seismic cocIIicients of 0.2g horizontal and 0.0g s ertical. Stress levels in the charcoal adsor her support elements do not exceed i

1.33 times the allowable stress levels permitted by the AISC Manual of Steel Construction,7th Edition (Section 11.3.2).

Seismic design for the ventilation systems is described in Section 9.4.

I 11.3.9 Testing Shop fabricated equipment and the piping system will pass the required tests for integrity as specified in the pressure integrity design specification. In all cases, pressure-containing butt welds exposed to radioactive gas will have 100% radiography and all other pressure-containing welds will have liquid penetrant or magnetic particle surface i

inspection.

Completed process systems are pressure tested to the maximum practicable extent.

Piping systems are hydrostatically tested in their entirety, utilizing available valves or temporary plugs at atmospheric tank connections. Hydrostatic testing of piping systems l

2 2

is performed at a pressure of 38.7 kg/cm g, which is 1.5 times 25.8 kg/cm, the design pressure of the lowest pressure rated part of the system. The test pressure will be held i

f or a minimum of 30 minutes with no leakage indicated. Hydrostatic testing will not be performed with the recombiner catalyst, the activated carbon or the filter element in place in the system. Pneumatic testing may be substituted for hydrostatic testing in accordance with the applicable Code of Construction. However, any pressure testing j

performed after the activated carbon is in place in the vessels would utilize vaporized liquid nitrogen (not compressed air) to avoid contamination or combustion of the carbon.

The installed Offgas System will be leak tested to verify that the leak criteria of Subsection 11.3.4.3.5 are met. A helium leak test is used. Testing is completed prior to application of thermalinsulation or corrosion protective coating. Surfaces of the Offgas Gaseous Waste Management System - DRAFT 11.3 21

23A6100 Rev. 2 ABWR Standard Safety Analysis Report System to be leak tested will be clean and free of water, oil, grease, paint and other contaminants which would interfere with the leak test.

The object of the preoperation tests is to test installed equipment and piping configurations. Preoperation tests are intended to serify that the equipment was built and installed correttiy. The preoperation tests are not complete design tests nor ftdl range calibrations.

The coolant input temperatm e and flow rate for the offgas condenser and coolcr-condenser will be verified to be in compliance with the design basis. The offgas filter cartridges aie tested for proper scaling and filtration.

The hydrogen analyzers are tested for proper functioning. During operation, the analyzer will be calibrated on the manufacturer's recommended intenal as a minimum.

The equipment operation will be verified at about 10 and 1005T of the normal flow.

Dming icactor startup, after air e,jector cut-in and Offgas System startup, the following will be verified:

(1) Air ejector function, through offgas pressure and flow (2) Preheater operation, through recombiner inlet temperature (3) Catalyst temperature and R efIluent concentration 2

(4) Offgas condenser operation The press us e drops on the offgas will be verified for both startup and normal operation.

In-place testing facilities are provided for testing the integrity ofIhe filter and fiher seal I

af ter installation. Such facilities include a polydisperse dioctylphthalate (DOP) smoke generator, means for smoke injection and dispersion upstream of the filter, and analytical instnunentation for determining DOP smoke concentration upstream and i

downstream of the filter.

Means should be provided for testing the leaktigh tness of the instadled filter when filters are initially installed or when they are replaced. Tests should include the following:

(1) New filters should be factory tested for emciency.

(2) Immediately prior to installation, new filters should be visually inspected for damage using strong backlighting.

(3) After installation and prior to use, the filter should be DOP tested to ensure that it is scaled and that no unseen filter damage exists.

11.3-22 Gaseous Waste Management System - DRAFT

I i

23A6100 Rev. 2 1

ABWR Standard Safety Analysis Report t

1 j

The test at the time of filter installation or seplacement uses 1)OP (dioctylphthalate) l acrosol to deter mine whether the installed filter meets the minimum in-pla(c clIiciency I

4 of 99.97% retention. The DOP test consists of injecting cold (polydisperse) DOP in a l

Iti5 to 33 cubic meters per hour air stream so that it is well mixed when it reaches the fiber. The DOP and air enter the offgas pipe at least eight offgas pipe diameters upsticam of the fiber and inlet sampling point. The outlet sampling point is located at least eight pipe diameters downsucam of the outlet of the filter, and the return line Irom the DOP sampler must be located at least four pipe diameters beyond the outlet l

sampling point. Sampling connet tion fr om the inlet and outlet sampling line should be made through a DOP measuring insinunent to a vacuum pump of 1.3 to 2 cubic meters per hour capacity. The DOP measuring instrument is used to measure individual DOP c oncentrations at the filter inlet and outlet, thereby measuring filter efficiency by j

comparing these concentrations. At the end of the test. the proc ess lines are purged l

with bleed air.

The DOP from fiher testing is not allowed into the activated carbon.

j i

1 Performam e tests during plant operation should (onsist onh of taking filter inlet and outlet samples by drawing them through Millipore filters for laboraton measurement j

of radioactive particles mllected.

Fiher test equipment used with the Offgas System should have the following characteristic s:

i (1) The smoke injection and sample piping shouhl have the same pressure rating as the offgas line through the first valve.

1 (2) The smoke generator and measuring instnunentation, including the vacumn pump, can be made portable for common use on the Standby Gas Treatment Syst em.

(3) The DOP connec tions should be installed so that representative inlet and outlet can be obtained.

i Testing icquirements fin the ventilation systems are listed in Section 9.l.

~

11.3.10 Radioactive Releases 11.3.10.1 Release Points The in-imaiy iclease point for the AIMR plant is the Reactor Building plant stack. This stac k senes as the release point for the Reactor Building, Turbine Building, and Radwaste Building. Other exhaust points for (lean releases are the r oof top vents for the Control and Senke Buildings and the Senice Building health physics room roof vent.

]

The Reat tor Building stack is a roof-mounted steci shell in a steel framework extending Gaseous Waste Management System - DRAFT 11.3-23

23A6100 Rev. 2 ABWR Standard Safety Analysis Report i

to a height of 76m above ground level. The closest plant buildings are the Reactor Building to a height of 37.7m and the Ttubine Building to a height of 43m. A sketch of the layout for the plant is shown in Figure 1.2-1 and a sketch of the stack with perspective to the local buildings is shown in Figure 15.fM.

11.3.10.2 Ventilation Releases j

Ventilation releases anc given in Section 12.2 and assume releases from the plant stack with a total flow rate of at least 566,000 m /hr through a 2.4m diameter circular stack 3

at 76m above ground level. Ventilation releases are assumed to be less than 40 C. The ABWR is licensed for a generic site for which no specific site parameters have been stipulated by the NRC; therefoie, an ambient tempemture of 38'C is assumed based upon Table 2.0-1.

11.3.10.3 Dilution Factors Since the ABWR certification stipulates a generic site and in lieu of NRC guidance on j

meicorological parameters for genetic sites, r ecourse was made to the detennination of the annual aserage dilution factors (y/Qand D/Q) for multiple sites. Using data described in Reference 11.S5 for 26 sites around the U.S. including New York City (derived from Reference 11.S6) and the above parameters, a determination of /Q X

and D/Q variability using code XOQDOQ (Reference 11.37) was made. From this, a minimum y/Q of 2.0 x 10' and a minimum D/Qof 4 x 10* was used.

11.3.10.4 Estimated Doses The calctdated exposures are discussed in Section 12.2.

i 11.3.11 COL License Information The COL applicant shall provide the following which apply on a plant-specific basis-i (1) Compliance with Appendix I to 10CFR50 numerical guidelines for ofTsite radiation doses as a iesult of gaseous or airborne radioactive efIluents during nonnal plant operations, including anticipated operational occurrences shall be provided.

11.3.12 References i

11.31 Browning, W.E., et al., Renwraloffission Product Gasesfrom Reactor Offgas Streams Irv Adwrption, June 11,1959 (ORNL) CF59-6-47.

11.%2 Seigwarth,1).P.. Measurement ofDynamic Adsmption CoefficientsforNoble Gases on Activated Ca ben,12th AEC Air Cleaning Conference.

I 1.S3 Standards for Steam Surface Condensers, Sixth Edition. Heat Exchange Institute, New Yor k, NY (1970).

11.3 24 Gaseous Waste Management System - DRAFT 1

23A6100 Rev. 2 ABWR Standard Safety Analysis Report 11.%4 Under hill, Dwight, et al., Design offission Ga5 Holdup Systems, Proceedings of the Eleventh AEC Air Cleaning Conference,1970, p. 217.

11.% 5 Hall, Irving, et al, Generations ofTyjncalMeteorological Yearsfor 26 SOLMET Stations, Sandia National Laboratory, SAND 78-1601.

l 1.%

Ritchie, Lynn T, et al, Calculations ofReactor.4ccident Consequences Version 2 CIl4C2: Computer Code NUREG/CR02326, February 1983.

11.%7 Sagendos f,J.F., et al XOQDOQ:ComputerProgramfor the MeteorolgicalEvaluatwn of Routine Efpurnt Releasn at Nuclear Power Stations, NUREG/CR-2919, Septeinber 1982.

j t

?

i i

e i

l 1

i Gaseous Waste Management System - DRAFT 11.3-25 4

23A6100 Rev. 2 ABWR Standard Safety Analysis Report ector Offgas Release Rates Per Unit Table 11.3-1 Estimated Air Ej/hr inleakage)

(51 sm Discharge from Charcoal l

T = 30 Adsorber Minutes Isotope Half-Life T=0 pCi/sec pCi/sec pCi/sec Ci/yr*

Kr-85m 1.86 hr 3.4x10 2.9x10 3.8x10*

1.1x10-4 3

3 3

3 1

Kr-85m 4.4 hr 6.1x10 5.6x10 1.2 3.3x10 Kr-85t 10.74 yr 10-20 10-20 20 570 4

4 Kr-87 76 min 2x10 1.5x10 K.r.88 2.79 hr 2x10 1.8x10 2.3x10-2 0.64 4

4 5

2 Kr-89 3.18 min 1.3x10 1.8x10 5

Kr-90 32.3 sec 2.8x10 5

Kr-91 8.6 sec 3.3x10 5

Kr 92 1.84 sec 3.3x10 4

Kr-93 1.29 sec 9.9x10 4

Kr-94 1.0 sec 2.3x10 3

Kr-95 0.5 sec 2.1 ' 0 1

Kr-97 1 see 1.4x10 t

Xe-131m 11.96 day 1.5x10' 1.5x10 2.3 6.6x10 1

1 Xe-133m 2.26 day 2.9x10 2.8x10 1.3x10-2 3.7x10~l 2

2 3

3 2

3 Xe-133 5.27 day 8.2x10 8.2x10 1.2x10 3.5x10 4

3 Xe-135m 15.7 min 2.6x10 6.9x10 4

4 Xe-135 9.16 hr 2.2x10 2.2x10 5

2 Xe-137 3.82 min 1.5x10 6.7x10 4

4 Xe-138 14.2 min 8.9x10 2.1x10 5

Xe-139 40 sec 2.8x10 5

Xe-140 13.6 sec 3.0x10 5

Xe-141 1.72 sec 2.4x10 4

Xe-142 1.22 sec 7.3x10 4

Xe-143 0.96 sec 1.2x10 Xe-144 9 sec 5.6x102 6

5 3

3 TOTALS

~2.5x10

~1.0x10 1.4x10 4.2x10

• This is based on curies present at time of release. No decay in environment is included.

1 Estimated from experimental observations.

11.3-26 Gaseous Waste Management System - DRAFT

23A6100 Rev. 2 ABWR StandardSafety Analysis Report The following figures are located in Chapter 21 (C size,17" x 22"):

~

Figure 11.3-1 Offgas System PFD (Sheet 1) i 1

1 Gaseous Waste Management System - DRAFT 11.3-2728

23A6100 Rev. 2 ABWR Standard Safety Analysis lieport 11.4 Solid Waste Management System The Solid Waste System is designed to proside solidification and packaging for radioactive wastes produced during shutdown.startup, and normal operation and to store these wastes, as required,in the Radwaste Building.

11.4.1 Design Bases 11.4.1.1 Design Objective The Solid Waste System provides the capability for solidifying and packaging wastes h om the Reactor Water Cleanup (CUW) System, the Fuel Pool Cooling and Cleanup Sptem, the Suppression Pool Cleanup System, the Condensate Polishing System, and the R,ulwaste System itsed. Wastes from these systems will consist of spent resin, l

concentrator bottoms and backwash slurries.

1 The Sob 1 Wae System also piovides a means of:

~

(1) Incinerating and packaging combustible dry radioactive materials, such as paper, rags, contaminated clothing, gloves, and shoe (overings (2) Compacting and packaging non-combustible and compressible materials, such as IWAC filters and non-flammable organic materials

~

(3) Pac kaging contaminated metallic materials and incompressible solid objects such as small tools and equipment components I he Solid Waste System is designed so that the failure or maintenance of any frequently used component does not impair system or plant operation. Storage is provided ahead of the piocess equipment to allow holdup for radioactive decay and as required in case of a delay in prmessing due to maintenance.

Drum rapping and siunple :etriend are pedormed locally. The operating philosophy of-

)

the solid radwaste control system is manual start and automatic stop with all fimctions inteilocked to provide a fail-safe mode of Solid Waste Systemoperation.

11.4.1.2 Design Criteria

, dlection, solidification incineration, packaging, and storage of radioactive wastes will

% acrformed to maintain any potentia! radiation exposure to plant personnel as low as asonably achievable ( A1. ARA) in act ordance with Regulatory Guide 8.8 and within

)

. limits of 10CFR20.

Pmportional amounts of wastes and fixative are incorp.> rated into the solid radwaste matrix to a3sure that no free wate. acctunulates in the waste container in compliance with the Branch Te(huical Position ETSit 11-3.

Solid Waste Management Sysrem - DRAFT 11.3 1 i

I

23A6100 Rev. 2 ABWR Standard Safety Analysis Report Packaging and transporting radioactive wastes will be in conformance with 10CFR61.

Packaged wastes will be shipped in conformance with 49CFR173, Subpart 1, limits.

Sullicient onsite storage is prosided to hold at least six months production of radwaste.

The nsdiation monitoring of the solid product generated for shipment offsite (GDC 64) is au omplished by prosiding monitoring desices at the solids container so that, as the container is filled, the waste accumulation is measmed to pievent the container from eu ceding acceptable radiation lesels.

Other criteria that are also applicable to the solid waste portion of the Radwaste System have been discussed previously in Section 11.2.1.2.

11.4.2 System Description 11.4.2.1 General Description The major solid waste equipment consists of the following:

(1) Thin-fihn dayer (2) A waste supply tank and a waste supply pump (3) A moisture separator, a condenser and a vent blower (4) A pelletirer (5) A po.-eder hopper and a bind r measuring hopper (6) A pellet filling machine i

(7) A par ticle filter, IIEPA filter and a filter blower (8) A mixing tank (9) A solidification agent measuring hopper and an additive water tank (10) A drum conveyor assembly (l;) A capping machint i

i (12) A cleaning water tank and a cleaning water pump i

(13) A cleaning water receiving tamk and a decant pump

(!4) An incinerator

~

i i

l (15) Primary and secondary ceramic filters j

(16) A IIEPA filter 11.4 2 Solid Waste Management System - DRAFT

23A6100 Rev. 2 ABWR Standard Safety Analysis Report (17) A dry active waste compactor (18) Cmmertions and auxiliaries for mobile systems Some of the above components may be changed if a solidification agent other than cement-glass is used.

See Table 11.4-2 fi>r an estimat e of expected annual " dry" solid wastes and curie content.

Tanks are si/ed to meet the st< rage requirements ofIITP ETSIl 11.3, Part Ikil.l.

Four weight elements are f astalled to monitor the amount of waste in the container.

Siandard 20e liter diums ar e used in ibis system. Additionally, the pellet-filling machine and a solidification paste pouring station provides a tight fit over the only opening in the solids container so that splashing is essentially precluded. Pellet filling operations ar e presented byinterlock with the weight sensors. Solidification agent pouring operations ar e pr evented by interloc k with the level sensors.

The following design features identified under " Additional Design Features"in llTP E I SIl 11.3, Pari IkV. are incorpor ated into the Solid Waste Systeur (1) All evaporator concentrate piping and tanks are heat traced to prevent the

< oncentrates from solidifying.

(2) Al components and piping whi< h contain slurries have flushing connections.

(3) The storage f acilities for solidification agents a ; in low radiation areas, generally less than 2.5 mlUhr, and have provisions fbr sampling.

(4) All tanks and equijnnent which use compressed gases ihr transport or drying of resins or liner (badges are vented to the plant ventilation exhaust system.

The vents are designed to prevent liquids and solids fr om entering the plant sentilation system.

11.4.2.2 System Operation 11.4.2.2.1 General Requirements The solid wate inanagement system in oc esses both wet and dry solid wastes in compliance with ahe following:

(1) The r c! cases of radioactive materials to an unrestricted area arc within the (oncentration limits of 10CFR20, Appendix 11, Table 11. All solid wasics ar e monitored for radiation before either processing or disposal as nom adioactive waste. It is expected that some dry solid waste will be dispouble as nonradioactive. All liquids and gases from solid waste processing Sohd Waste Management Sysrem - DRAFT 11.K3

23A6100 Rev. 2 ABWR Standard Safety Analysis Report are treated by the liquid waste systent or by the Radwaste lluilding ventilation system.

(2) The Solid Waste Systein has suflicient storage of both unprocessed and processed wastes to deal with both norinal and anticipated operational o< currences. These storage facilities have been designed with adequate shielding to protect the operators froin excessive radiation.

Wast es will F olidified separately by type and source.

11.4.2.2.2 Spent Resins and Sludges The wastes are spent resins, sludges froni powdered resins and filter backwashing and concentrated liquids from the evaporators. The spent resins and sludges inay be treated either by sending them to the thin filni dryer for evaporation or they can be sent to sendor-supplied inobile dewatering systems. The concentrated liquids from the evaporators are sent to the thin fihn dryer.

See Table 1I A-1 for "Expec red Waste Yohnnes Generated Annually by Each " Wet" Solid Waste Source and Tank Capacities" l'o pro < cis the wastes, the operator assmes that he has pellets and solidification agents.

An empty drum is placed on the drum conveyor. Position switches acknowledge the cor rect placement of the drums under the pellet-filling station and the solidification pasic pouring station so that perf ert mating is accomplished to avoid spillage while filling and pouring.

To pt event overfilling the drums, weight elements ar e placed at the pellet-filling station and a level sensor is placed at the solidification paste pouring station. Additionally, radiation monitors are positioned at the end of drmn conveyors so that the radiation resu! ting from mixtur e in the drums and surface contamination of the drums may be monit or ed.

11.4.2.2.3 Dry Active Waste (DAW)

The combustible dry wa_stes are burned by the incinerator and periodically discharged to an ash storage drum. The im ombustible and compressible dry wastes in drums are redu< cd in volmne by using a rotnpartor.

The 1)AW dre us are individually handled with no solidification agent added and can be shipped for burial either separately or with other drums romaining solidified liquid wastes, as r equir ed if 7 Illect silippillg lilflitati(sits.

114-4 Solid Waste Management System - DRAFT

23A6100 Rev. 2 ABWR Standard Safety Analysis Report 11.4.2.2.5 Malfunction Analysis The process system is protected from component failure and operator error through a series of safety interlocks. These assure that the system will operate to solidify waste only if all of the following conditmns are met:

1 (1) A waste container is in place.

)

(2) The mix / fill assembly is covering the container (3) The container is not f ull.

4 l

1 (4) The container is not overweight.

(5) One source of waste is available.

(6) An adequate supply of solidification agent is available and the mixer is operable.

Failure to meet any of the above conditions will stop the operation in progress.

Interruption may occur at any phase and the process is designed so that restart may occur without adverse consequences. Restart may be undertaken at the same point in the process after the failed condition has been semedied.

11.4.2.2.6 Shipment Containers normally can be shipped immediately after solidification, provided the proper shielding is available, without exceeding U.S. Department of Transportation radiation limits. If 49CFR173 dose limitations cannot be met, the containers are stored until the appropriate shielding is available.

Normally, high integrity containers will be shipped promptly after they are filled. If shipment is not prompt, the high integrity containers will be si: red with shielding in the truck area shown in Figure 1.2-23c.

A banier to restrict access shall be placed around the shielding.The radiation dose rate at the hairier shall be 5 mrem /hr or less.

)

1 There ar e three additional storage areas for raulioactive waste awaiting shipment. These

)

wastes will be stored either in drums or boxes. There is space for six drums in the filled drum stoc k area (FDSA) (Figure 1.2-23c). Also, there is space for drums in the MSW moms. Finally, there is space for either boxes or dnun pallets in the solid ~ waste storage area (SWSA) (Figure 1.2-23b).

Solid Waste Management System - ORAFT 11.4-5 i

I 1

I 23A6100 Rev. 2

)

ABWR Sta:sdard SafetyAnalysis Report l

l All mntaminated shipping containers and vehicles used for solid waste handling will be stored in the Radwaste Building. Uncontaminated shipping containers and vehicles may be stored outside.

I 11.4.3 COL License information 11.4.3.1 Plant-Specific Radwaste information i

The COI. applicant shall proside the following which apply on a plant-specific basis:

i

{l) A description of the incinerator complete with the source ofincinerator heat, I

heat source storage facility and specific fire protection features to prevent any undue liic hazard shall be provided.

(2) Demonstration that the wet waste solidification process and the spent resin and sludge dewatering process will result in products that comply with 10CFR61.56 shall he prosided.

(3) Establisinnent and implementation of a process control program (PCP) for solidifying the evaporator concentrates, using an approved solidification agent, and the dewatering piocessing of the spent resins and filter sludges shall be pr ovided.

( 1) A discussion of onsite storage oflow-level waste beyond that discussed in the SSAR shall be provided.

(5) Demonstration that all radioactive waste shipping packages meet the j

icquirements in 10CFR71 shall be piovided l

(6) Based on the as-built design, establish set points for the liquid discharge radiation monitor.

l l

l l

11.4 6 Solid Waste Management System - DRAFT 1

23A6100 Rev. 2 ABWR standardsarety Analysis neport Table 11.4-1 Expected Waste Volume Generated Annually by Each " Wet" Solid i

Waste Source and Tank Capacities Wet Waste Source Volume Generated Specific Activity CUW F/D sludge 4.7 m /y 7.34 x 10 pC/kg 3

7 3

6 FPC F/C sludge 1.8 m /y 1.94 x 10 pC/kg 3

5 Condensate Filter sludge 4.6 m /y 2.40 x 10 pC/kg 3

6 LCW Filter sludge 0.2 m /y 150 x 10 pC/kg 3

Condensate Demineralizer resin 18.0 m /y 5.70 x 10' pC/kg 3

5 LCW Domineralizer resin 5.0 m /y 1.18 x 10 pC/kg 3

HCW Demineralizer resin 2.7 m /y 8.4 pC/kg 3

3 Concentrated Liquid Waste 27.4 m /y 4.67 x 10 pC/kg I

The first four items in the table above are stored in either of two CUW phase separators which 3

I have a cagacity of 4rn each. During a normal period these four wastes are generated at a rate of i

about 2m in 60 days.

3 The waste resins are stored in the spent resin tank which has a capacity of 50m. During a normal 3

period spent resin is generated at a rate of about 2m in 30 days.

3 The concentrated liquid wastes are stored in two storage tanks which have a capacity of 16m 1

each. Thus, at lease six months storage capacity is provided.

Thus, the t,torage requirements in BTP ETSB 11.3, Part B.lli.1 are met.

Table 11.4-2 Estimate of Expected Annual " Dry" Solid Wastes and Curie Content Dry Waste Source Volume Generated Total Curies 3

Combustible waste 225 m /y 1.6 3

Compactible waste 38 m /y 0.3 3

Other waste 100 m /y 7.0 I

t Sohd Waste tsianagement Systam - DRAFT 11.6 7/8

OVERSIZE DOCUMENT PAGE PULLED 1

SEE APERTURE CARDS 4

NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS 930F/90 /Yo-ol -/f APERTURE CARD /HARD COPY AVAILABLE FROM RECORDS AND REPORTS MANAGEMENT BRANCH f

]

l

-