ML20135H818

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Forwards Revised FSAR Sections 1.2.10.3,11.4 & 12.2.1.15,in Response to NRC Request for Addl Info Re Solid Radwaste Sys Requirements to Meet SRP Criteria,Per SER Outstanding Issue 14.Info Will Be Incorporated in Future FSAR Amend
ML20135H818
Person / Time
Site: Seabrook  
Issue date: 09/20/1985
From: Devincentis J
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To: Knighton G
Office of Nuclear Reactor Regulation
References
SBN-873, NUDOCS 8509240265
Download: ML20135H818 (93)
v • d • e


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I SEABROOK STATION Engineering Office Pub 5C Service of New Hampshko New Hampshire Yankee Division September 20, 1985 SBN-873 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-582), dated November 22, 1983, "Seabrook Station Solid Radwaste Handling System," J. DeVincentis to G. W. Knighton (c) PSNH Letter (SBN-626), dated February 15,1984, " Amendment 52 to March 30, 1973, Application to Construct and Operate Seabrook Station Unit 1 and Unit 2," W. P. Johnson to G. W. Knighton

Subject:

Seabrook Station Solid Radwaste Handling System (SER Outstanding Issue No. 14)

Dear Sir:

Subsequent to the issuance of FSAR Amendment No. 52 [ Reference (c)], your staff indicated that additional detail of the Solid Radwaste System was required to meet the criteria provided in the Standard Review Plan (SRPs).

Accordingly, please find enclosed revised FSAR Sections 1.2.10.3 (Enclosure 1); 11.4 (Enclosure 2) and 12.2.1.15 (Enclosure 3) which are responsive to the staff's comment. This information will be incorporated into the FSAR by a future amendment.

At the recent Caseload Forecast Panel Meeting, we indicated that the Waste Solidification System was being scheduled so that it would be available for use prior to commercial operation of Unit 1.

However, provisions are still being maintained to use a mobile services contract to process waste as

'necessary at the time of Unit 1 startup. As provided in Reference (c), if a mobile services contract is awarded, the applicable Process Control Program will be submitted to the NRC within 30 days of the contract award. It should be noted that the need for a mobile service will be continuously evaluated based on the availability of the Waste Solidification System.

8;S39240265 850920 i

PDR ADOCK 05000443 Qc0 E

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P.O. Box 300 Seabrook. NH 03874 Telephone (603) 474-9521

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United States Nuclear Regulatory Commission September 20, 1985 Attention:

Mr. George W. Knighton Page 2 The enclosed completes our commitments made in RAIs 460.1 and 460.33, as well as resolving the outstanding issue identified in Seabrook's SER Section 11.4.

Accordingly, we respectively request that your staff review the enclosed so that the resolution of this issue can be included in the next supplement to the SER.

Very truly you s,

,<[r-John DeVincentis, Director Engineering and Licensing Enclosures cc: Atomic Safety and Licensing Board Service List

Vi111cn S. Jordan, ill Donald I. Chick Dicne Curran Tov: hanege r

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Earnon, Weiss & Jordan Tov: ef Exeter 20001 S. Street, N.W.

10 Ircut Street Su'ite 430 Exeter, NE 03E33 Washington, D.C.

20009 Ere::vood ioard of Selectnen Robert C. ?erlis RED ' alton Road U.S. Nuclear Regulatory Co==ission

'Ere::vood, NE 03E33 Offic,e of the Executive Legal Director Washington, DC 20555 Richard E. Sullivan, Mayor City Eall Robert A. Zackus, Isquire Newhryport, EA 01950 1161ovell Street P.O. Box 516 Calvin A. Canney Manchester, NE 03105 City Manager City Eall -

Philip Ahrens,' Esquire 126 Daniel Street Assistabt Attorney General Por:snouth, NE 03801 Augusta, EI 04333 Dana lisbee, Isquire Mr.' John -1. Tanzer As sistant Attorney General Designated Representative of Office of the Attorn'ey General the Town of Ea=pton 205 State House Annex 5 Horningside Drive Con:c d, NE 03301 Eanpton, NE 03842

~

Ante Ver'ge, Chairpersen Roberta C. Pevear Board of Select =en Designated Repyesentative of Toc Eall -

the Town cf Eanpton Falls South Ea=pton, NE 03S27 Drinkvater. Road Hampton Talls, NE 03844 Patrick J. McKeon

~

i Seleetnen's Office 10 Central Road Mr's. Sandra Cavutis ~

Rye, NH 03870 Designated Representative of the Toirn of Kensington

- RTD 1 Carele T. Kagan, Esquire East Kingston, NE 03827 Atusic Safety and 1.ieensing Board Panel U.S. Nuclear Regulatory Co ission Jci Ann Sbotwell,.Isquire.

.uashington, DC 20555 Assistadt Attorney General Envirormental Protection Bureau Er. Angi Machiros Department of the Attorney General Chairman of the Board of-Seleetnen One. Ashburton Place,19th Iloor Tov: of Newbury Boston, MA 02108 Neubery, NA 01950 Toe: Manager's Office Senator Cordon J. Bunphrey Toun Eall - Friend Street -

U.S. Senate Washington, ?DC s 20510

-a=%ry, MA 01913

('dTIE:

rom 3 crack)

Senator Gordon J. Hunphrey Diana P. Randall 1 Pillsbury Street.

. - 70 Collins Street Coic~ord, NH 03301 Seabrook, NE 03874

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1.2.10.3 Solid Waste Management System The solid waste management system consists of the following subsystems:

spent resin sluicing, Dry Active Waste (DAW) v'olume reduction, alternate solidification, and volume reduction and solidification in asphalt.

Volume reduction and solidification is further broken down to:

waste concentrates handling, spent resin handling, liquid waste volume reduction, and material handling. This system is common to both reactor units.

If this permanently installed system is not completed to a point which allows vaste to be processed by fuel load, mobile solidification services will be made available for Unit I fuel load.

A detailed discussion on the solid waste management system is presented in Section 11.4.

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SBN-873. ENCLOSURE 2 Revised FSAR Section 11.4 Solid Waste Management System Note: Extensive Revision I i

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FSAR 6 11.4 SOLID WASTE MANACENEhT SYSTEM 11.4.1 Desian Basis 11.4.1.1 Design Obiective and Criteria 4 A single solid waste management system is provided to serve two nuclear generating units. The solid waste management system processes waste liquids, spent resins and dry wastes for disposal off-site. The system is designed and operated to meet the limits for controlled releases of radioactive liquids from the site forth in Seabrook Technical Specifications. set The solid waste management system is designed in accordance with 10 CFR 20; Regulatory Guides 1.143, 8.8, and 8.10; Standard Review Plan 11.4; Branch Technical Position 11.3; and ANSI /ANS 55.1. A generic topical report discussing the Waste Chem volume reduction and solidification system was accepted by the NRC on April 12, 1978. Consideration of operation, mainte-nance, and accident conditions have been factored into the system design to maintain radiation levels as low as reasonable achievable. Equipment layout and shielding are designed to limit radiation levels in areas accessible by the operator during a solidification operation to less than 15 ares /hr, and in the radwaste control room levels are less.than 2.5 meem/hr. Handling, storage, and shipping of radioactive waste will be performed in conformance with 10 CFR 50, 61, and 71. The containers used for solid waste storage and off-site shipment will be either 55 gallon drums, or 85 ft 3 containers, and nominal 100 ft3 boxes. These containers are designed to meet the appropriate requirements of 49 CFR 171-179 (Departwent of Transportation Radioactive Material Regulations), and 10 CFR 71 (Packaging of Radioactive Materials for Transport). System design incorporates backup processing capability for the WL, BRS and SB evaporators via the liquid waste volume reduction subsystem. A 10CFR61 wasteform qualification program is currently being conducted to demonstrate vasteform compliance to the NRC branch technical position on wasteform for Class 8 and C waste. The FSAR will be amended to reference the results of the wasteform qualification program when it is completed. Additionally, a process control plan (PCP) will be implemented to ensure compliance with 10CFR61 wasteform requirements. Waste will be classified persuant to'10CFR61 classification requirements by use.of isotopic inferral/ correlation techniques in conjunction with periodic i calib, ration programs. 1 11.4-1 l

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FSAR SW9EIPNP i The solid waste management system is comprised of several subsystems as ) follows: 1 Spent Resin Sluicing DAW Volume Reduction Alternate Solidification Volume Reduction and Solidification in Asphalt j volumne reduction and solidification in asphalt consists of: i i 1. Waste concentrates handling l 4 1 1 2. Spent resin handling 3. Liquid waste volume reduction j 4. Material handling t o l The system also provides the necessary instrumentation and connections for adequate control and monitoring of wet radwaste for delivery to contracted nobile solidification services equipment via the Alternate Solidification j Station. } These subsystems are all interrelated with the exception of the DAW Volume j Reduction which operates independently of any other subsystem. i a. Permanently Installed Waste Processing Subsystems Using Asphalt l l 7 i The various wet and dry solid radioactive wastes produced by the two nuclear generating units are processed by either a single i permanently installed solid waste management system or by using l the services of a mobile solidification contractor. The solid waste management system, located in the waste processing building 1 I (WPB) coamson to both units, provides the following functions. i 1. Collection and storage of spent resins from plant i l demineralizers. { 2. Collection and storage of concentrated wastes containing up i i to 12 wt! boric acid. P 3. Volume reduction to the maximum extent practical of all j liquid concentrates and spent resins produced by the i generating units. 4. Solidification of volume reduced waste, using an asphalt { binder, as necessary, for of f-site disposal in accordance i i with the requirements of 10 CFR 61. t t 4 { 11.4-2

i S81&2 Wimmeumulueta FSAR W j 1 5. Encapsulation / solidification, using an asphalt binder, of non-compactible vaste such as spent filter cartridges and like items generated during plant operation and maintenance. 6. Volume reduction of compactible dry active vastes for on-site storage or off-site burial. j 7. Limited temporary onsite storage for solidified in asphalt low level wet waste, with a capacity for 2.9 years for 1 unit and 1.5 years for 2 units. This is based on design volumes. The solid waste management system is non-Nuclear Safety and non-Seismic, and is designed in accordance with the requirements as set forth in NRC Regulatory Cuide 1.143. The operation of the system has no effect on the capability to bring the plant to a safe shutdown condition. r b. Alternate Weste Processinz Via Mobile Contractor The processing of wet vastes and encapsulatable dry waste, in final preparation for on-site storage and eventual off-site shipment for disposal, may be accomplished utilizing the services of a contractor using mobile equipment. Available contractor mobile equipment 4 j will utilize an approved solidification agent, with cement being the more likely binder. If the permanently installed system is not completed by Unit 1 fuel load, contracted mobile solidifi-cation services will be made available. The mobile solidification vendor wasteform qualification program will be placed on file for NRC review. Permanently installed solid waste management system equipment needed for proper connections to and monitoring of waste inputs made to the mobile solidification services contractor equipeent which will be operational prior to Unit 1 fuel load is listed in Table 11.4-1. The station services and equipment necessary for the operation of the mobile solidification services to process liquid concentrates, spent resin or spent filter cartridge type waste are designed tos 1. Deliver liquid radwaste to an alternate mobile solidification system in the truck bay. 2. Solidify completely all radioactive wa'ste concentrates and chemical wastes. 3. Solidify non-compressible contaminated items such as spent filter cartridges and other items generated during plant operation and maintenance. 4. Package the solidified radioactive waste in containers suitable for transportation to a licensed burial site. i i I 11.4-3

- ~~.. - -. I i.s SB 1 & 2 M i FSAR 6 l Temporary on-site storage o waste, which has been solidified with cement by the alternate processing mode, of a minimum of thirty days is available in the waste proegseing building. Additional on-site storage will be provided as re'q'uired. The station services for the mobile solidification system are I shared by both units. The mobile system will have the capability to solidify an input volume of at least 16,000 ft /yr of waste 3 consisting primarily of spent resin and 12 wt! boric acid concen-l. trates, and to encapsulate and solidify 600 ft /yr of spent filter 3 cartridges, contaminated and/or activated tools and other equipment. l The resin sluice tanks (2) can accosusodate one year's supply for l both units. Spent resin can also be dewatered with a mobile solidi-l -fication service. i 11.4.1.2 System Inputs The solid waste management system has several input sources. The following subsections discuss these inputs on a yearly operational basis, including maintenance and anticipated transients. Tables 11.4-2 and 11.4-3 list the maximum and expected volumes and activity, respectively, for each source. The bases and assumptions used in determining the solid waste activities for I off-site shipment for each waste type are listed in Table 11.4-4. The bases i and assumptions used for determining the waste activities inside of each major subsystes component are presented in Subsection 12.2. Radionuclide 3 j concentrations and volumes are consistent with reactor operating experience l presented in NUREC/CR-0144, ORNL-4924, and N'fREC/CR-1759. process flow t diagrams for the solid waste management system are shown in Figure 11.4-3 { (Sheets 1 & 2). P&lD's for the system are given by Figures 11.4-1 (Sheets 1 thru 8) and 11.4-2. Layouts identifing packaging, shipping, and storage j areas are given by Figures 1.2-22 thru 1.2-30. i i a. Dry Active Wastes I j Dry active wastes are classified into two categories. The two { categories are (1) non-compactible and (2) compactible. Examples i of non-compactible wastes would include small items such as used handtools which cannot be economically decontaminated, electrical connectors, wood, et. al. from contaminated areas. Examples of } compactible vastes would include paper, polyethylene, tape, anti-l contamination clothing, gloves, and shoe covers that are contani-nated and/or beyond repair. The activity concentrations for off-i site shipment, after processing, are listed in Table 11.4-5 l j assuming twice the expected waste' generation volumes as the maximum. 4 b. Spent Domineraliser Resine I The resin sluice tanks, located in the WpB at elevation (-)31' i l provide the collection point for spent resins. The spent resin transfer pump takes suction on either of these tanks and transfers 3 11.4-4 t i

i SB 1 & 2 6 FSAR 6 resin to the resin hopper at elevation 53'. After the resin hopper is filled, resin is processed by dewatering via the resin dewatering pump. The hopper fill operation is repeated until the proper resin slurry density is obtaihed-in the resin hopper. The normal resin process path is to the resin centrifuge. Trans-port water is drivec from the resin in the centrifuge and the resin free falls into the evaporator / extruder where it is homo-geneously mixed with asphalt binder in an approximate one-to-one ratio, by weight, and is then discharged into an appropriate shipping container. The function of the centrifuge is to remove transport water from the resin slurry, and thereby increase the system throughput by reducing the evaporative demand on the evaporator / extruder. As an alternative, resin slurry can also be fed directly to the evaporator / extruder via the concentrates metering pump. Resin slurties can also be pumped to the alternate solidification station located in the truck bay via'the resin centrifuge metering pump, for either solidification or devatering in a disposable container. At the alternate solidification station, a contractor with mobile waste processing equipment would then proceed to homogeneously mix the slurries with seueen a solidification binder and then package it in an appropriate shipping container. Spent resins from the following demineralizers are collected in the spent resin sluice tanks prior to processing: 1. S pent fuel pool demineralizer, 2. Chemical volume control system demineralizers, 3. Liquid waste system demineralizer, and the 4. Boron recovery system demineralizers. The design and expected activity concentrations for off-site ship-ment, after processing, are listed in Table 11.4-6 and 11.4-7. c. Evaporator Bottoms and Other The waste concentrates tank at elevation (-)31' collects the evaporator bottoms and chemical drains from evaporators and drain tanks located throughout the plant. Concentrates are transferrad l to the waste feed tanks on elevation 53'. Once in these tanks, pH i l l 11.4-5

\\ SB 1 & 2 6 3 FSAR 6 ) is adjusted and the concentrates can be fed to the crystallizer, i or directly to the evaporator / extruder or to the alternate solidi-fication station. Chemically neutralized concentrates fed to the evaporator / extruder are homogeneously mixed with asphalt binder in a one-to-one ratio of solids to asphalt by weight, and discharged into appropriate approved containers. At the alternate solidification station, a l contractor with mobile waste processing equipment would homo- ~ geneously mix the concentrates with either'an acceptable binder and package them into appropriate shipping containers. The normal design operating mode is to process these concentrates 4 through the crystallizer producing a concentrated bottoms of 35-50% total dissolved solids. These bottoms are then fed to the evaporator / extruder for further volume reduction by the removal of water, and solidification of the radsalts. The concentrates collected for processing in the solid waste management system on a batch basis, include evaporator bottoms and chemical drains from the following systems: 4 1. Liquid waste, 2. Boron recovery, 3. Steam generator blowdown, and I 4. Floor and equipment drains. Other vaste inputs handled by the system include the spent filters from various radioactive and/or potentially radioactive process l systems from throughout the plant. Typically spent filter car-tridges and other similar waste items are processed via the utiliza-tion of a technique of encapsulation and solidification, using either cement or asphalt binder, within a filter basket placed inside a 55 gallon drum or other container as needed. The design and expected activity concentrations of evaporator bottoms, chemical drains, and encapsultated and solidified waste for off-site shipment, after processing and binding with either asphalt or cement, are listed in Table 11.4-8 and 11.4-9, respectively. 11.4.2

System Description

l The[solidwastemanagementsystemisaplantsystemdesignedforthemanage-ment of the final processing of wet or dry solid radwastes produced by two nuc1*eir generating units at a common' location within the waste processing building. Wet solid radwastes include spent demineralizer resins, concen-trates from evaporator bottoms, chemical wastes, spent filter cartridges, i 11.4-6 l l

SB 1 & 2 eummutumummte FSAR W SD and miscellaneous vastes from floor and equipment drains. Spent demineralizer resins are handled by one or more dewatering steps prior to being mixed with an asphalt binder using a screw evaporator / extruder or fed directly,to_ mobile equipment for devatering and/or solidification with either M or other approved binder. Concentrates at 12-50 wtZ solids concentration are chemically adjusted, as necessary, then fed to the evaporator / extruder for the removal of water and mixing uith the asphalt binder or fed directly to mobile equip-ment for mixing with binder. Dry solid waste includes both compactible and non-compactible trash. Transfer of wet wastes to contracted mobile services equipment is accomplished via use of the alternate solidification concen-trates feed and the centrifugal metering pump and is controlled from a dedicated alternate solidification control panel located in the loading dock at elevation 25' of the vaste processing building. The solid waste management system is located in a separately shielded areas of the vaste processing building at the (-)31', 25', 42'-5", 53, and 55' elevations in the southwest corner of the building. Radwaste originating from sources from within the two unit plant is controlled by this system for processing either by permanently installed equipment and or by contracted mobile solidification services. Wet radwastes for ultimate solidification and/or volume reduction into appropriate storage / shipping containers is collected into various tanks located at elevation (-)31' prior to transfer to the solid waste management system for processing. Personnel exposure is kept as low as reasonably achievable by the use of concrete shielding, by the use of closed circuit television cameras, by the provision of a separately shielded processed waste container storage area, and by the provision of a separately shielded loading dock area. Radioactive solid waste equipment parameters are summarized in Table 11.4-10. 11.4.2.1 Component Descriptions The following are descriptions of major permanently installed mechanical system components. a. Spent Resin Hopper (WS-TK-81) The spent resin hopper is located at elevation 53' of the WPB. It has a working capacity of 934 gallons. The hopper accepts radwaste in the form of a spent resin slurry directly from the spent resin sluice tank. A volume reduction of this vaste is accomplished in the hopper using an integral mixer, a dewatering screen, and decantation. A solids concentration of 15 stZ is expected. During recirculation pH is adjusted, if required. The normal disposition of the devatered slurry produced by the hopper is feed to the centrifuge. Decant is returned eto one of the resin sluice tanks. The hopper includes permanently installed internal sparging nozzles to permit remote decontamination after each use. 11.4-7

s. SB 1 & 2 6 FSAR 6 b. Resin Centrifuge (WS-MM-611) The resin centrifuge is located above floor elevation 55' of the WPB. The unit has a maximum processing. capacity of 4.7 gpm of resin slurry feed at a dry solids concentration of 10 wt%. It produces a processed effluent at a rate of 440 pounds per hour at a dry solids concentration of 50 wtZ fo'r fed to the evaporator / extruder and mixing with asphalt. This volume reduction is accomplished via the use of centrifugal forces to separate the liquid and solid phases of the resin slurry feed. Resin slurry feed is taken directly from the spent resin hopper recirculation .for processing. Decant is returned to one of the resin sluice tanks. c. Crystallizer (WS-EV-6) The principal components of the crystallizer are located above floor elevation 55' of the WPB. The crystallizer is a low head, submerged tube, forced circulation package with a separate entrainment separator. The crystallizer has a working capacity of 1200 gallons; 600 gallons within the vapor body and another 600 gallons within its associated heater and recirculation piping. Its external two pass horizontal heater utilizes the plant auxil-isry steam system. Steam is applied to the shell side of the heater where it condenses on the outside of the tubes and trans-fers heat to the liquor circulating inside the tubes. The steam condensate is then removed from the shell side of the heater and returned to the condensate storage tank. The liquor circulating through the tubes is not allowed to boil. After the liquor passes through the heater, it enters the vapor body where it releases water vapor to the entrainment separator, crystallizer condenser, and subcooler. The recirculation pump, vapor body, and heater are designed to process undissolved solids, with the capability to crystallize inorganic salts in typical PWR process waste concen-trates. d. Waste Feed Tanks (WS-TK-198A,B) The two waste feed tanks are located at elevation 53' of the WPB. They each have a working capacity of 1,000 gallons for processing of radwaste originating from various plant evaporators and drain tanks. These tanks accept radwaste directly from the 6,000 gallon. waste concentrates tank. When the waste feed tanks are filled to work,ing level a sample is taken from their recirculation loop, their pH is adjusted, as necessary, and their contents are homogeneously mixed by a mixing-educ$ tor located inside the tank at the inlet nozzle. Their contents are then fed, normally on a batch basis, to the crystallizer system. Bottoms from the crystallizer are subsequently transferred to the concentrates bottoms tank prior to processing through the evaporator / extruder. i 11.4-8 l

o SB 1 & 2 m FSAR 6 The contents of the waste feed tanks are kept heated in preparation for pre-concentration volume-reduction in the crystallizer vapor body, using electric strip heater el,ements wrapped around their girth. A dip pipe is provided in each't'ank for level indication. A permanently installed spray ball assembly is also included within the top of each tank for the purpose of providing a remote decon-tamination capability af ter the processing of each batch of radwaste concentrates. e. Concentrates Bottoms Tank (WS-TK-200) The concentrates bottoms tank is located at elevation 53' of the WPB. It has a working capacity of 1,000 gallons. It receives bottoms directly from the crystallizer vapor body after the desired solids concentration has been attained. The tank is necessary for holdup prior to feed to the evaporator / extruder for final volume reduction and solidification via blending with asphalt. The holdup is required primarily, because of the difference in processing rates of the evaporator / extruder and the crystallizer vapor body. It also allows final chemistry adjustments, as necessary, prior to processing through the evaporator / extruder. The tank is kept electrically heated during processing. The tank is decontaminated remotely after each batch by using a built-in spray arrangement located in the top of the vessel. The contents of the tanks are kept homogenously mixed by use of a mechanical agitator during feed to the evaporator / extruder. f. Evaporator / Extruder (WS-EV-7) The evaporator / extruder is located at elevation 42'-5" of the WPB. It combines volume reduction and solidification with asphalt (bitumen) of either spent resin slurries or waste concentrates. Both the radwastes and the asphalt (heated to 3250F) are fed simultaneously into the twin screw, steam heated, eight section evaporator / extruder where the associated transport water and entrained moisture is evaporated and vented through the three steam domes during the blending process. Up to 99.5% of the associated free water is removed at the rate of 21 gallons per hour for a resin waste stream or at the rate of 32 gallons per hour from a concentrates waste stream. Product discharge rate into shipping containers varies from about 9.25 to 27.5 gallons per hou'r, dep'ending upon the speed of the screws and the feed stream solids concentration. Total residence time of material inside the evaporator / extruder is on the order of one minute and the total inventory of the unit'when full of asphalt and waste is less than one gallon. The solids to asphalt weight ratio fed into the storage / shipping containers will vary up to one-to-one as determined by waste feed radioactivity concentration and weight percent solids loading. The evaporator / extruder is 11.4-9 l

SB 1 & 2 FSAR 6 remotely controlled and has a variable speed motor drive. The unit can operate either continuously or in an on-off mode. If feed is stopped, it will continue to operate and self-clean within approximately one minute. Should po'wer 'or steam fai1ure occur allowing an asphalt mixture to harden inside of the>, extruder, simple heating to the process temperature af ter repairs restores it to normal operation, (eva ponded g. Asphalt Storage Tank (WS-TK-201) The asphalt storage tank is located at elevation 20' of a separate asphalt storage building adjacent to the southwest corner of the WPB. It has a working capacity of 7000 gallons. This capacity is adequate to meet normal plant processing requirements for about four months. The tank utilizes steam panels to permit heating using steam provided by the dedicated auxiliary boiler. The tank is designed to receive asphalt from a vendor's tank truck at a fill rate of 100 gpm, while simultaneously recirculating and straining the influx. The recirculation permits the rapid achievement of a homogeneous temperature distribution within the tank. Recirculation will be at a rate of 20 to 25 gpm. Fill strainers are designed to remove any foreign particles which could be present in the influx. Recirculation strainers are designed to remove foreign matter missed by the fill strainers. h. Auxiliary Boiler Skid (WS-SKD-112) The auxiliary boiler skid is located at elevation 53' of the WPB. The skid includes the electrically heated auxiliary boiler, the condensate return tank, two boiler feed pumps, blowdown tank and sample cooler plus associated valves and motors. The auxiliary boiler is designed to deliver steam at a rate of 5,000 pounds per hour at an operating pressure of 275 psig and an operating tempera-ture of 4100F as needed to maintain asphalt within system piping and equipment in a molten condition for extended periods. i. Chemical Feed Skid (WS-SKD-115) The chemical feed skid is located at elevation 53' of the WPB. The skid includes the chemical feed tank and the chemical feed pump, plus associated valves and motors. The chemical feed tank is designed with a working capacity of 50' gallons and provides chemical feed to the auxiliary boiler. $ j. Caustic Skid (WS-SKD-111) The caustic skid is located at elevation 53' of the WPB. The skid includes the caustic day tank and the caustic metering pump, plus associated valves and motor. The caustic day tank is designed with a working capacity of 200 gallons and can supply caustic to the vaste feed tanks, spent resin hopper, and the concentrates bottom tank. 11.4-10

SB 1 & 2 e6 FSAR 6 k. Vent Hood Assembly (WS-MM-615) The vent hood assembly is located at elevation 42'-5" of the WPB. The vent hood assembly is designed t'o fit over the container (s) to be filled, and exhaust any off-gassing of volatile vapors or steam carry-over at the evaporator / extruder discharge port or from the waste container being filled, to the WPB ventilation exhaust filter system. The vent hood assembly is equipped with redundant level probes and a camera for visual level inspection. 1. Compactor & Ancillary Equipment (WS-MM-722) The compactor and its ancillary equipment is located on elevation 25' of the WPB within the shielded loading dock area due east of the truck bay. The compactor is a standard electro-mechanically driven device for hydraulic compression of dry active wastes into 100 ft3 LSA boxes. Depending upon the type of dry material to be processed, volume reduction ratios ranging from 4:1 to 10:1 may be achieved. An expected average weight per box of compacted waste of approximately 3600' pounds is achieved with the use of anti-spring back devices. Ancillary equipment includes a two horse power air vacuum pump, a furnace filter and absolute filter for the containment of contaminants generated during use, and a hydraulic unit. m. Material Handling A 30 ton bridge crane, WS-CR-35, 55 gallon drum conveyors, a 7\\ ton self propelled transporter cart, a process aisle overhead monorail, and fork lifts are provided for in plant movement of solid waste containers. These items, in conjunction with the use of closed circuit television monitors, shielding and remote operation capability provide as low as reasonably achieveable radiation protection for plant or contractor personnel. 11.4.2.2 Operating Procedures The solid wastes listed in Subsection 11.4.1.2 are handled according to their abysical properties. The system is used intermittently and requires one full time operator in attendance during steady state system operation. Control of the system is remote-manual. The entire volume reduction, solidification and drum handling systems are controlled remotely from two control panels' in the shielded control room of the. waste processing building (WPB). Waste solidification processing is controlled from a single panel which integrates all the process subsystems. A programmable controller provides for automatic operation after manual startup of the system. Interlocks and permissives prohibit inadvertent or improper operation of subsystems and 11.4-11 l

SB 1 & 2 m FSAR 6 l also form the basis of the solidification process control program. Details of the process control program for the use of permanently installed equipment utilizing an asphalt binder are given in a separate process control document. Details of a process control program for the use of contracted mobile solidification or dewatering services will be placed on file for NRC review. The overall radwaste management system is designed to provide maximum flexi-bility in the processing of the various waste streams. Spent resins are processed by devatering, volume reduction and solidification. Evaporstor i bottoms and chemical wastes are processed by volume reduction and solidifica-tion. Both vaste types are capable of being pumped to an alternate solidifi-cation station in the truck bay area for solidification, or in the case of resin dewatering, into a dry form. a. Waste Concentrates Handling Subsystem The vaste concentrates tank receives concentrated non-recyclable vastes from the liquid waste evaporator, the two boron recovery evaporators, the three steam generator blowdown evaporators, the chemical drain treatment tanks, the floor drain tanks and return from the vaste feed tanks. Concentrates in the tank are heated by electric tracing to prevent solidification of concentrated material. A waste concentrate) transfer pump is provided for recirculation of the waste concentrates tank and transfer of the waste concen-trates to the waste feed tanks. The overflow from the waste feed tanks is directed back to the vaste concentrates tank. The overflow from the vaste concentrates tank is directed to a floor drain. The pre-concentrated liquid waste solution is pumped from the waste feed tanks to the crystallizer to remove excess water more quickly i with the final waste volume reduction and solidification achieved upon subsequent delivery to either the permanently installed evaporator / extruder using an asphalt binder or alternately upon delivery to contracted mobile equipment for binding with an approved binder. The radioactive vaste in the form of a slurry, containing 35-50% total dissolved solids by weight, is pumped to either the permanently installed asphalt evaporator / extruder by the --*- ' r concentrates metering pump or to the alternate solidification station using alternate solidification concentrates feed pump. b. Spent Resin Handling Subsystem The purpose of the spent resin devatering subsystem is to remove the spent resins from the various demineralizers in the radioactive liquid clean-up systems, to store the resin for a time sufficient to reduce the radiation levels to an acceptable level, and then to pump the spent resin to the spent resin hopper where it is prepared for solidification and offsite disposal. i l 11.4-12

1 1 SB 1 & 2 m FSAR sentpuMWP 1 i l The four basic operations performed by the system are: 1. Removal of spent resin from the demineralizers in various . radioactive liquid waste cleanup gystems in the primary, auxiliary and waste processing buildings by a sluicing opera-tion, and storage of these resins in the spent resin sluice tanks. 2. Post-sluicing clean-up of the resin sluice piping to lower the radiation levels, by recirculating the sluice water through the pipes and then through the resin sluice filter. 3. Recirculating the liquid in the sluice tanks ekumagtumuhumuuuuuun admess and transferring the contents from one tank to the other, to equalize bulk or dose. 4. Transport of the spent resin from the sluice tanks by the spent resin transfer pump for devatering via the spent resin hopper and/or the centrifuge, with the final waste volume reduction and solidification upon delivery to either the permanently installed evaporator / extruder using an asphalt binder or alternately upon delivery to contracted mobile equip-ment for binding with an approved solidification agent, or dewatering in a disposable liner. The spent resin hopper receives waste from the spent resin sluice tanks. The agitator in the hopper keeps solids and spent resin in suspension, and the spent resin dewatering pump and pump suction screen allows for removal of water from the resin slurry. The spent resin hopper is vented to the plant vent via the aerated vent header. Samples can be drawn from the recirculation line from the hopper for direct analysis of radionuclides, waste, and spent resin concentrations, as well as total activity level. Direct sampling also determines the process control requirements and container shield requirements. The spent resin is pumped from the spent resin hopper in the form of a bead resin slurry by the resin recirculation and the resin centrifuge metering pumps. c. Liquid Waste Volume Reduction Subsystem The liquid waste volume reduction-subsystem provides for the concen-tration of various liquid wastes from a nominal 5-12 wt% total dissolved solids to 35-50 wt% total dissolved solids. This concen-tration is accomplished by a 5 gpm forced circulation evaporator / crystallizer operating on plant auxiliary steam. The prime function of the crystallizer is to quickly remove excess l water from the liquid waste stream prior to feeding the asphalt evaporator / extruder, which has a comparatively low evaporation l 11.4-13

SB 1 & 2 9ngummanum FSAR 6 rate. The crystallizer also provides for a means of volume reduc-tion independent of the evaporator / extruder operation and, in addition, allows for a reduced demand on the station's existing upstream evaporators. Feed from the waste feed tanks enters the recirculation loop of the crystallizer and mixes with the recirculation flow prior to entering the heater. This stream then enters the vapor body where part of the flow flashes to steam. The flashed steam then enters the entrainment separator where it passes through distillation trays and a desister pad and then enters the condenser skid and ultimately returns to the plant liquid waste system or discharges to the circulating water system. Bottoms from the crystallizer are pumped from the main recircula-tion loop to the crystallizer bottoms tank by the crystallizer drain pump. System operation is dependent upon the amount of vaste available for volume reduction. System is capable of continuous operation with periodic bottoms blowdown. However, the crystallizer will normally be run on a batch basis, concentrating to the maximum extent practical and then shutting down. The entire contents of the 6000 gallon waste concentrates storage tank can be volume reduced in the crystallizer and stored in the crystallizer bottoms tank prior to processing through the extruder / evaporator. d. Asphalt Volume Reduction and Solidification Subsystem The evaporator / extruder is the main component of this subsystem and the heart of the entire volume reduction and solidification process. It is located in the WPB at elevation 42'-5". In the evaporator / extruder the vaste stream (concentrates or resin) mixes with asphalt which is then heated by steam to evaporate the remaining water in the mix. The resulting matrix contains approximately 50% dried residual waste and 50% asphalt by weight and is deposited into either 55 gallon drums or 85 ft3 containers. As the matrix cools from the operating temperature, solidification takes place due to the thermoplastic properties of asphalt. Water evaporated from the vaste during volume reduction is condensed in the three evaporator / extruder steam domes and is gravity drained to the floor drain tanks. e Steam for this process is supplied by an electric auxiliary boiler at'4100F and 275 psig. Asphalt is supplied from the 7,000 gallon asphalt storage tank located in a separate building at grade just south of the WPB. Asphalt lines are steam traced using the high temperature steam from the solid waste auxiliary boiler. Plant 11.4-14

v --

SB 1 & 2 6 FSAR 6 auxiliary. steam is provided as a backup system in case the solid waste system auxiliary boiler needs to be shut down for maintenance. Normally, 55 gallon drums are utiliz'ed for disposal of solidified waste. However, the ability to utilize 85 ft3 containers is provided. The following steps are required in order to align the system for usage with 85 ft3 containers; (1) The drum capper i station is relocated to the position required for functioning with 85 ft3 containers. The cap stack unit is removed. (2) The 55 gallon drum turntable station is removed by unbolting the four flanged end connections. (3) The drum grab and rotator unit is changed out via the 30 ton overhead crane in order to enable use of the large container lifting rig. (4) A vent hood extension is added in order to properly interface the fill port to the large container. (5) The 85 ft3 container will be loaded onto and off of the transfer cart via the overhead crane. (6) The waste solidifi-cation control panel settings are adjusted for 85 ft3 container } operation. Material Handling Subsystem e. The components of this subsystem are all located within the WPB at floor elevation 25', except for the radwaste crane which sits at 7 elevation 73'. The empty drum conveyor is loaded from the solid waste control room with empty drums (6 minimum, 10 maximum) prior to the start of solidification operations. The drum hoist and grab lifts empty drums from the empty drum conveyor and places them on the turntable prior to fill operation. The evaporator / extruder utilizes a one-step volume reduction and solidification process that operates continuously. The drum handling subsystem is designed to allow continuous flow of drums through the process area so as to take full advantage of the benefits that continuous system operation provides. Operation of the evaporator / extruder will cause a ' drum to fill with the asphalt / waste mixture. After a drum has been filled, the turntable rotates an empty drum into the fill position and the i filled drum into the pickup position on the turntable. Multiple fill passes on the turntable ensure maximum fill efficiency in each drum. The drum hoist and grab lifts the full drum and places it on the full drum conveyor. At this time an empty drum may be placed on the turntable if continuous operation beyond the six drum capacity of the turntable is anticipated. The drip pan ' mechanism is provided for product collection during drum indexing. l The pan with drippings is depo ~ sited into the next empty drum af ter indexing. All drum movement operations on the drum conveyors and turntable are manual start with automatic stop. All drum lifting and capping 11.4-15 h _.-s_ ,e 6 g n, - - .c. ,y_

SB 1 & 2 6 FSAR 6 operations are manually controlled. Crane operation is manually controlled with specific lockouts to prevent crane travel with load in down position and to prevent collisions with walls. On the full drum conveyor the drum moves to the capping station where the capper is activated to pick up a cap from the cap stack and place it on the drum and crimp it in place. After capping, the swipe station turntable allows the drum to spin. A swipe may be taken, at this time, by'the swipe manipulator to check for external contamination. The drum is then transferred to the end of the full drums conveyor where the overhead radwaste crane can pick it up and place it in the storage area. All drum handling and process operations can be visually monitored via closed circuit television. A lead glass window on the fill aisle wall also provides direct visual observation of the capping and swipe operations. As an alternative to filling drums, 85 ft3 liners may be used. Liners will be located under the evaporator / extruder discharge by the transfer cart. The cart also moves liners to'the capping and crane pickup positions. The use of liners or drums will be dictated by disposal economics. ? f. Dry Active Wastes (DAW) Volume Reduction Subsystem A single subsystem for dry active waste is provided to serve two nuclear generating units. The subsystem utilizes a 100 ft3 box compactor with anti-spring back devices. It will be fully operational for the processing of all contaminated and/or potentially contaminated compactible and non-compactible trash at Unit 1 fuel load. The subsystem handles typical trash collected at this operating plant with an average collected density of 7 to 10 lbs/ft3 with a final waste density of approximately 30 to 40 lbs/ft3 This system combines reliable forty year service life with maximum operator safety, compacting efficiency and ALARA exposure time. The compactor exhaust system operates to prevent dust from escaping during trash handling and is complete with fan, fan motor, prefilter, absolute filter and connects to the duct in the Filter Drum Storage Area Exhaust System.

  • 'g.

Alternate Solidification Waste concentrates or resin slurries prepared as described above will be delivered to the alternate solidification station, located 1 11.4-16

SB 1 & 2 M FSAR 6 in the truck bay area for processing via a mobile solidification / or resin dewatering services contractor. Also provided will be flush water, vent lines, resin water return lines, isolation valves, and a control panel for the pumps and valves. TVo small panels in the truck bay supplement the main control and drum handling panels by providing functional control over waste flow to the alternate solidification station and control of crane movements in the truck bay area only. 11.4.2.3 System Controls, Protective Devices, and Instrumentation The solid waste management system has design provisions incorporated to reduce leakage, control the unplanned release of radioactive materials, and facilitate operation and maintenance in accordance with the guidelines of Regulatory Guide 1.143. Mechanical protective devices and/or instrumentation incorporated for the reduction of leakage potential and for control of the potential for uncontrolled releases of radioactive materials include: (a) a 100 micron filter array attached to the suction side of each of the two resin sluice pumps preventing resin movement except by the system; (b) system piping normally containing resin or concentrates has butt welds and five diameter bends; (c) a double mechanical seal for system pumps to prevent any leakage at the shaft; and (d) a vent hood assembly which is designed to collect off-gases, e) seal water to most pumps is a closed system with individual seal water tanks. The remainder have a dead end seal water design. Mechanical protective devices and/or instrumentation incorporated for the facilitation of operation and maintenance include; (a) maintenance of a low pressure nitrogen blanket in each of the two resin sluice tanks at all times to prevent the possibility of the formation of an explosive hydrogen / oxygen mixture; (b) equipment within the system has high point vents and low point drain valves; (c) equipment layout is arranged such that radiation exposure during handling, volume reduction, or solidification operations is limited to less than 15 mrem /hr in operator occupied areas; (d) redundant disposal container level probes and television cameras provided for monitoring to minimize the potential for spills due to overflows during filling; and (e) a 'i 30 ton indexed radwaste crane which is remotely controlled from a shielded control station viewed through closed circuit television cameras; and (f) tank cubicles incorporate concrete curbs to further aid in controlling radioactive releases in the event of an overflow. Radiation levels are monitored near the spent resin hopper cubicle and in the filling area by detectors permanently located in each of these areas. Local indication alarms are provided.- Contents of the hopper, the bottom tank, and the waste feed tanks are moni-tored for pH, with remote indication at the shielded waste solidification ~ control panel. I 11.4-17

SB 1 & 2 6 FSAR 6 Instrumentation is provided to monitor the pressure, level and temperature in various parts of the system to aid safe operation of the system from the main control panel. Upon loss of power or air, the system reverts to the safe position. In addition, due to the complexity of the resin sluice system and number of systems with which it interfaces, administrative procedures will be developed requiring a valve line-up inspection prior to any sluicing operation to insure that: 1. Operating systems under pressure do not become lined up to the sluice' system. 2. Sluice water is not pumped into an operational system which is shut dova and depressurized. 3. The sluice pump suction is not lined up with one sluice tank and the return flow to the other tank. Periodic testing is performed in accordance with established station proce-dures and includes: hydrostatically testing each component in the system and inspecting for leak tightness; operationally testing components; and the testing of the response and setpoints of instrumentation with alarm features. 11.4.2.4 Maximum and Expected Processed Waste Volumes The maximum and expected volumes of radioactive solid wastes available for off-site shipment annually, for each source, are presented in Table 11.4-11 considering the use of either an asphalt or a cement binder. The projected annual volumes are based on uniform one-to-one mixing ratio for a comeercial asphalt with the maximum practical volume reduction of all wet solid plant wastes or a one-and-one-half-to-one mixing ratio using a cement binder without volume reduction. For spent demineralizer resins, the minimum L expected applied volume reduction will be a factor of 1.85 and for evapo-rator bottoms and other, the minimum volume reduction will be 6.3. For compressible dry wastes, the minimum expected volume reduction will be 4. 3 It is expected that, using an asphalt binder, 21 containers with a 85 ft capacity or 233 drums with a 55 gallon (7.35 f t3) capacity will be needed t for wet radwastes such as spent resins and evaporator bottoms and for encapsulation of other wastes such as spent filter cartridges, contaminated tool, etc. Seventy boxes with a 100 ftJ capacity will be needed for all dry wastes such as swipes, rags, anti-contamination clothing, etc., on an annual ba sis. It q expected that, using a cement binder, 110 containers with an 85 ft3 capacity or 1268 drums with a 55 gallon capacity would be needed for wet radwaste and non-compressible vastes on an annual basis, for both units. 11.4-18

SB 1 & 2 N FSAR 6 11.4.2.5 Packing Spent resins, evaporator bottoms and miscellaneou,s chemical wastes are solidi-fied in 55 gallon drums or 85 ft3 containers. The containers are filled remote-manually from behind a shield wall using closed circuit television to avoid unnecessary exposure. Spent cartridge filters may be encapsulated and shipped in 55 gallon drums; dry low-level wastes are compacted to the maximum extent practical and shipped in 100 ft3 boxes. Filled containers are shipped as required in appropriate overpacks and shields. Solid waste containers, shipping casks, and methods of packaging will meet applicable state and Federal regulations, including 10 CFR 71. 11.4.2.6 Storage Facilities Processed solid radioactive wastes, except trash, are stored in 55 gallon drums and 85 ft3 shipping containers in the shielded storage room in the ground floor storage area at elevation 25' of the waste processing building next to the loading dock area. The weight of the containers being stored will not exceed the floor loading capacity of the storage area. Additional storage capability will be provided, as necessary, on a timely basis. Containers use steel and lead shield overpacks in thicknesses as necessary to reduce contact radiation level. The shipment of solid radwaste does not disturb normal plant operations. Means of in plant transport includes fork lifts, monorails and a bridge crane. Loaded trucks may stay overnight inside the enclosed radioactive material loading dock area, which is a restricted area with controlled access. Spent filter ' cartridges from Unit #2 PAB will be transported to the WPB in the spent filter transfer cask via flat bed truck. DAW from Unit #2 will be transported to the WPB in 55 gal. drums with removable lids via flat bed t ruck. 11.4.2.7 Shipment Radwaste from the radioactive material storage area will be loaded on trucks in the loading dock area of the waste processing building. The containers are monitored for surface contamination, decontaminated if necessary, and released for transport to a licensed radioactive waste disposal site. The design and expected curie contents of these shipments are presented in Table 11.4-12. Wastes will be shipped in accordance with applicable NRC, Department of Transportation, and State regulations. 11.4.3 References (1) Kibbey, A.H. and Godbee, H.W., "A Critical Review of Solid Radio-active Waste Practices at Nuclear Power Plants," ORNL-4924, March 1974. t i 11.4-19 i

i SB 1 & 2 6 FSAR W (2) Kibbey, A.H., et. al., "A Review of Solid Radioactive Weste Practices", NUREC/CR-0144, October 1978. (3) Wild, R.E., et. al., " Data Base for Radioactive Waste Management / Waste Source Options Report", NUREC/CR-1759, November 1981. (4) NWT Corporation, " Solid Radwante Radionuclide Measurements", EPRI NP-2734, Project 1568-1, Nov. 1982. '(5) Waste Chem (WPC), "Radwaste Volume Reduction and Solidification System", WPC-VRS-001, Rev. 1, May, 1978. e 11.4-20

SB 1 & 2 m FSAR Eeutgusteep TABLE 11.4-1 PERMANENTLY INSTALLED EQUIPMENT NEEDED FOR PROCESSINC WET WASTE VIA ALTERNATE MOBILE SOLID.IFICATION SYSTEM Component Quantity Tanks: Spent resin hopper 1 Waste concentrates 1 Spent resin sluice 2 Waste feed 2 Pumps: Waste feed recirculation 2 Resin dewatering 1 Waste concentrates transfer 1 Spent resin transfer 1 Spent resin sluice 2 Spent resin recirculation 1 Resin centrifuge metering 1 Alternate solidification concentrates feed 1 Filters: Spent resin sluice 1 i Panels: 1 Crane control station 1 Crane power 1 Alternate solidification 1 Station feed control 1 Metering pumps SCR 1 1 Auxiliary boiler control 1 f Others: 30 ton bridge crane 1 71 ton transporter cart 1 Spent filter transfer cask 1 ,, ~,, - -+-s~ .-e

6 SB 1 & 2 6 FSAR l TABLE 11.4-2 VOLUMETRIC INPUTS TO SOLID WASTE MANAGEMENT SYSTEM FOR BOTH i l Design Annual Expected Annual Volume (cf/yr)* Volume (cf/yr) Sources 28,800 14,400 Dry active vastes 8,800 4,400 a) Non-compactible trash 10,000 20,000 b) Compactible trash 4,300 1,400 Spent Demineralizer Resin's Evaporator Bottoms and Othe 13,000 4,200 (at 12 v/o solids concentration) 9 A ekhIg{12.tA CWm4ys 46,100 20,000 TOTALS

resins,
  • The system design processing rate for evaporator bottoms and spentto process all of the is sufficient using permanently installed equipment, This is design level quantities within 1664 hours of operation per year.

equivalent to a 19% annual useage factor. F l I f i ,--w. ,_m4

SB 1 & 2 6 FSAR subymoppy TABLE 11.4-3 ACTIVITY INPUTS TO SOLID WASTE MANAGEMENT SYSTEM FOR BOTH UNITS Design Expected Annual Annual Sources Activity (Ci/yr) Activity (Ci/yr) Dry Active Wastes 1.4+02* 7.2+01 Spent Demineralizer Resins 2.4+04 1.3+03 I git Evaporator Bottoms 3 O_:.5 l ft03 f,0 + 0'?_ (at 12 w/o solids concentration) -u. =, -w a TOTALS 7 ,W I l E. s t a it t.i t i ( c c)) f 3 d 7 40I l ) I'l4cq 1.6j + C 3

  • l.4+02 = 1.8x102 I

I l l r p l ,,,,n -e,,

,----,,s-n

i SB 1 & 2 summausummungen FSAR W TABLE 11.4-4 BASES AND ASSUMPTIONS FOR DETERMINING SOLID WASTES ACTIVITIES Design 1% failed fuel Expected 0.12% failed fuel Volume Reduction Factors Compactible dry active waste 4 to 10 Bead resins in asphalt 1.85 minimum Evaporator concentrates in asphalt 6.3 minimum Radwaste in cement 1.0 Waste to Einder Mix Ratios, by Volume Asphalt I to 1 minimum Cement 1.5 to 1 minimum Waste Container Fill Fractions Bead resins in asphalt 91% average Evaporator concentrates in asphalt 93% average Radwaste in cement 93% average Decay of Filled Containers Awaiting Shipout Dry active wastes none Bead resins 60 days minimum Evaporator concentrates 30 days minimum Densities Non-compactible trash 10.0 lbs/cf Compactible trash 37.4 lbs/cf Encapsulated and solidified filter cartridges 37.4 lbs/cf Depleted bead resins 56.8 lbs/cf Evaporator concentrates 62.4 lbs/cf Miscellaneous Plant availability is eighty percent. Each non regenerable demineralizer is changed annually. Thirty" filter cartridges are expected to be shipped from both units annually. Time needed to fill each 55 gallon drum of waste for shipout, uaing asphalt binder, is 2 hours minimum; 6 hours maximum. Time needed to fill each 85 cubic foot container of waste for shipout, using cement binder, is nominally 45 minutes.

'P SB 1 & 2 N FSAR 6 i TABLE 11.4-5 ACTIVITY OF DRY ACTIVE WASTES ** NON-COMPACTIBLE TRASH Isotope uCi/cc Isotope uCi/cc I-131 497.03-041$ Fe-59 8.44-03 Cs-134 2.32-02 Cr-51 8.59-02 Cs-137 3.83-02 Zn-65 1.05-03 '~' Mn-54 7.28-02 Others 4.23-03 Co-58 1.41-02 Total 3.53-01 Co-60 1.04-01 i 4 COMPACTIBLE TRASH 4 Isotope uCi/cc Isotope uCi/cc 1 I-131 3.06-05 Fe-59 3.67-04 Cs-134 1.01-03 Cr-51 3.73-03 i Cs-137 1.67-03 Zn-65 4.58-05 Mn-54 3.16-03 Other 1.84-04 Co-58 6.12-04 Total 1.53-02 Co-60 4.50-03 l f i

  • 7.03-04 = 7.03x10-4
    • based on Table 11.4-4 i

r me I

SB 1 & 2 6 FSAR assaymesse TABLE 11.4-6 DESIGN ACTIVITY OF SPENT DEMINERALIZER RESINS PROCESSED USINC ASPHALT BINDER Isotope uCi/cc Isotope uCi/cc I-131 1.1+00* Te-132 2.2-05 Sr-89 6.2-01 Ba-140 1.8-02 90 3.1-01 Ce-144 4.9-01 Y-91 1.5-01 Mn-54 8.9-01 Zr-95 2.0-01 Co-58 8.4+00 Nb-95 2.4-01 60 1.3+00 Mo-99 6.2-06 Fe-59 1.7-01 Cs-134 6.9-01 Cr-51 4.9-02 136 1.1-01 TOTAL 1.2+02 137 4.2+01 PROCESSED USINC CEMENT BINDER VIA ALTERNATE MOBILE EQUIPMENT Isotope uCi/cc Isotope uCi/cc I-131 3.4-01 Te-132 7.1-06 Sr-89 2.0-01 Ba-140 5.8-03 90 1.0-01 Cc-144 1.6-01 Y-91 4.9-02 Mn-54 2.9-01 Zr-95 6.3-02 Co-58 2.7+00 Nb-95 7.8-02 60 4.1-01 Mo-99 2.0-06 Fe-59 5.3-02 Cs-134 2.2+01 Cr-51 1.6-02 136 3.5-02 TOTAL 4.0+01 e 137 1.4+01

  • 1.1+00 = 1.1x100

SB 1 & 2 6 FSAR 6 TABLE I1.4-7 EXPECTED ACTIVITY OF SPENT DEMINERALIZER RESINS PROCESSED USING ASPHALT BINDER Isotope uCi/cc Isotope uCi/cc I-131 1.3-0l* Te-132 2.9-06 Sr-89 7.8-02 Ba-140 2.2-03 90 4.0-02 Ce-144 6.2-02 Y-91 1.9-02 Mn-54 8.9-01 Zr-95 2.4-02 Co-58 8.4+00 Nb-95 3.1-02 60 1.3+00 Mo-99 7.8-07 Fe-59 1.7-01 Cs-134 8.6+00 Cr-51 4.9-02 136 1.4-02 TOTAL 2.4+01 137 5.3+00 PROCESSED USING CEMENT BINDTR VIA ALTERNATE MOBILE EQUIPMENT Isotope uCi/cc Isotope uCi/cc I-131 4.3-02 Te-132 8.9-07 Sr-89 2.5-02 Ba-140 7.3-04 90 1.3-02 Ce-144 2.0-02 Y-91 6.1-03 Hn-54 2.9-01 Zr-95 7.9-03 Co-58 2.7+00 Nb-95 9.8-03 60 4.1-01 Mo-99 2.5-07 Fe-59 5.3-02 Cs-134 2.8-00 Cr-51 1.6-02 136 4.4-03 TOTAL 8.2+00 137 1.8+00 I

  • l.3-01 = 1.3x10-1

SB 1 & 2 m FSAR 6 TABLE 11.4-8 DESIGN ACTIVITY OF EVAPORATOR BOTTOMS & OTHER** EVAP BTMS & CHEMICAL VASTES PROCESSED USING ASPHALT BINDER Isotope uCi/cc Isotope uCi/cc I-131 8.6-01 & Te-132 8.1-04 Sr-89 2.0-02 Ba-140 3.1-03 90 2.0-03 Ce-144 4.0-03 Y-91 3.1-02 Mn-54 7.6-03 Zr-95 3.6-03 Co-58 1.6-01 Nb-95 5.7-03 60 8.1-03 Ho-99 2.9-03 Fe-59 4.8-03 Cs-134 5.7+0 Cr-51 2.4-03 136 2.2-01 TOTAL 1.0+01 137 3.1+0 EVAP BDfS & CHEMICAL WASTES PROCESSED USING CEMENT BINDER VIA ALTERNATE MOBILE EQUIPMENT Isotope uCi/cc Isotope uCi/cc I-131 8.3-02 Te-132 7.8-05 Sr-89 1.9-03 Ba-140 2.9-04 90 1.9-04 Cc-144 3.8-04 Y-91 2.9-03 Hn-54 7.4-04 Zr-95 3.5-04 Co-58 1.5-02 Nb-95 5.5-04 60 7.8- 04 Mo-99 2.6-04 Fe-59 4.5-04 Cs-134 5.5-01 Cr-51 2.3-04 136 2.1-02 TOTAL 1.0-00 137 3.1-01 P y g4.ol t &. 410 43 # 01 M 6xitr I

    • based on Table 11.4-4

a. SB 1 & 2 6 FSAR 6 TABLE 11.4-9 EXPECTED ACTIVITY OF EVAPORATOR BOTTOMS & OTHER** EVAP BTMS & CHEMICAL WASTES PROCESSED USING ASPHALT BINDER Isotope uCi/cc Isotope uCi/cc I-131 1.1-01

  • Te-132 1.0- 04 Sr-89 2.6-03 Ba-140 3.8-04 90 2.6-04 Ce-144 5.0-04 Y-91 3.8-03 Hn-54 7.6-03 Zr-95 4.5-04 Co-58 1.6-01 Nb-95 7.1-04 60 8.3-03 Mo-99 3.5-04 Fe-59 4.8-03 Cs-134 7.1-01 Cr-51 2.4-03 136 2.9-02 TOTAL 1.4+00 137 4.0-01 EVAP BTMS & CHEMICAL WASTES PROCESSED USING CEMENT BINDER VIA ALTERNATE MOBILE EQUI.' MENT Isotope uCi/cc Isotope uCi/cc I-131 1.0-02 Te-132 9.7-06 Sr-89 2.4-04 Ba-140 3.6-05 90 2.4-05 Ce-144 4.8-05 Y-91 3.6-04 Hn-54 7.4-04 Zr-95 4.5-05 Co-58 1.5-02 Nb-95 6.9-05 60 7.8-04 Ho-99 3.3-05 Fe-59 4.5-04 Cs-134 6.9-02 Cr-51 2.3-04 136 3.6-03 TOTAL 1.4-01 137 3.8-02

=4 g s.I-01 1 I. l

  • IG
  • 4,5-02 =-475x10- V
    • based on Table 11.4-4

SB 1 & 2 N FSAR 6 TABLE 11.4-10 (Sheet 1 of 6) SOLID WASTE MANACEMENT SYSTEM EQUIPMENT PARAMETERS Tanks Waste Concentrates Tank (1-WS-TK-76) Capacity 6750 gallons - maximum 6000 gallons - working Material Incoloy 825 Design / Operating Pressure 15 psig/ atmos Design / Operating Temperature 2500F/1800F Design Code ASME VIII - Div. 1 Minimum Holdup Time 2.0 Hrs. Waste Feed Tanks (1-WS-TK-198A & B) Capacity (each) 1320 gallons - maximum 1000 gallons - working Material Incoloy 825 Design / Operating Pressure 14.7 psig/ atmos Design / Operating Temperature 2650F/1800F Design Code ASME VIII Div. 1 - Nonstamped Minimum Holdup Time 23.8 Hrs. Bottoms Collection Tank (1-WS-TK-200) Capacity 1300 gallons - maximum 1000 gallons - working Material Incoloy 825 Design / Operating Pressure 5 psig/0.5 psig Design / Operating Temperature 2500F/2000F Design Code ASME VIII - Div. 1 Minimum Holdup Time 23.8 Hrs. Caustic Day Tank (1-WS-TK-199) Capacity 250 gallons - maximum 200 gallons - working Material (Plastic) Design / Operating Pressure (Atmos / atmos) Design / Operating Temperature 2000F/1500F Design Code Mfr. Std. Eafet'y Class NNS

SB 1 & 2 6 FSAR 6 TABLE 11.*-10 (Sheet 2 of 6) Resin Hopper (1-WS-TK-81) Capacity 934 gallons Design Operating Pressure Atmos./ atmos. Material Incoloy 825 Design Operating Temperature 2000F/2000F Design Code ASME VIII Minimum Holdup Time 31.1 Hrs. Crystallizer Distillate Tank (1-WS-TK-210) Capacity 30 gallons Material 304L Stainless Steel Design / Operating Pressure 30 psig/Atmes. Design Operating Temperature 2200F/1300F Design Code ASME VIII Asphalt Storap.e Tank (1-WS-TK-201) Capacity 7400 gallons - maximum 7000 gallons - working Material ASTM A285 Design / Operating Pressure Atmos./ atmos. Design / Operating Temp. 4250F/3250F Design Code API 650 Auxiliary Boiler Condensate Return Tank (1-WS-TK-202) Capacity 40 gallons Material ASTM A36 Operating Pressure Atmos. Operating Temperature 2100F Design Code Mfr. Standards Spent Resin Sluice Tanks (RS-RK-79A,B) capacity 9500 gal. Material 304 SS Design / Operating Press 150/5 psis Design / Operating Temp. 1500F Desi,gn Code ASME VIII Pump's Concentrates Transfer Pump (1-WS-P-354) Type Centrifugal Design Flow 50 gpm

SB 1 & 2 6 FSAR 6 TABLE 11.4-10 (Sheet 3 of 6) Waste Feed Recirculation Pumps (1-WS-P-332A & 8), Type Centrifugal Design Flow 50 gpm Caustic Metering Pump (1-WS-P-333) Type Progressive Cavity Design Flow 2 gpm Alternate Station Concentrates Feed Pump (1-WS-P-346) Type Progressive Cavity Design Flow 18 gpm Spent Resin Transfer Pump (1-WS-P-331) Type Progressive Cavity Design Flow 100 gpm Spent Resin Dewatering Pump (1-WS-P-353) Type In-line Centrifugal Design Flow 10 gpm Spent Resin Recirculation Pump (1-WS-P-342) Type Progressive Cavity Design Flow 50 gpm Resin Centrifuge Metering Pump (1-WS-P-338) Type Progressive Cavity Design Flow 1-10 gpm Crystallizer Recirculation Pump (1-WS-P-334) Type Centrifugal Design Flow 1800 gpm Crystallizer Distillate Pump (1-WS-P-335) Type Centrifugal Desig'n Flow 5 spm Crystallizer Reflux Pump (1-WS-P-352) Type Diaphragm Design Flow 1 apm l 1 L

SB 1 & 2 h FSAR 6 TABLE 11.4-10 (Sheet 4 of 6) Crystallizer Drain Pump (1-WS-P-347) Type Centrifugal Design Flow 1 gpm Asphalt Recirculation Pump (1-WS-P-339) Type Progressive Cavity Design Flow 20 gpm Asphalt Metering Pump (1-WS-P-340) Type Progressive Cavity Design Flow 3-30 gpm Auxiliary Boiler Feed Pumps (1-WS-P-341 A & B) Type Centrifugal Design Flow 9 gpm Spent Resin Sluice Pumps (WS-P-13 A, B) Type Centrifugal Design Flow 250 gpm Heat Exchangers, Coolers, Heaters, etc. Crystallizer Condenser (1-WS-E-158) Design Code ASME VIII, Div. 1 TEMA R Shell Side Tube Side Fluid Process Vapor Cooling Water Design Flow (2685 f/hr) (150 gpm) Design Temp 2500F 2000F Operating Temperature 2130F 1250F Design Pressure 30 psig 150 psig Operating Pressure Atmos. 60 psig Matgrial 304 S/S Carbon Steel Crystallizer Subcooler (1-WS-E-160) Design Code ASME VIII, Div. 1 TEMA R

F TABLE 11.4-10 (Sheet 5 of 6) Shell Side Tube Side Fluid Distillate Cooling Water Design Flow (2185 f/hr) (150 gpm) Design Temperature 2500F 2000F Operating Temperature 2120F 850F Design Pressure 150 psig 150 psig Operating Pressure 100 psig 100 psig Material 304 S/S Carbon Steel Crystallizer Heater (1-WS-E-156) Design Code ASME VIII, Div. 1 TEMA R Shell Side Tube Side Fluid Steam Concentrates Design Flow (3500 f/hr) (1200 gpm) Design Temperature 3000F 3000F Operating Temperature 2980F 2200F Design Pressure 150 psig 50 psig Operating Pressure 50 psig 15 psig Material Carbon Steel Inconel 625 Crystallizer Vapor Body (1-WS-EV-6) Material Inconel 625 Capacity (600). gallons - vapor body working 1200 gallons - vapor body, heater, recirculation pipe flooded Design Code ASME VIII, Div. 1 Design / Operating Pressure 30 psig/15 psia l Design / Operating Temperature 3000F/2220F Entrainment Separator (1-WS-E-157) Capacity 2695 #/hr. Volume (20) gallons - working , (300) gallons - flooded Desi,gn Code ASME VIII, Div. I Design Pressure Full vacuum to 30 psig Operating Pressure Atmos. l l Design Temperature 2700F l Operating Temperature 2130F l \\

_. _ _. ~ . SB 1 & 2 6 FSAR 6 TABLE 11.4-10 (Sheet 6 of 6) Auxiliary Boiler Vessel (1-WS-E-159) Capacity - Steam 5000 f/Hr. Operating Pressure 275 psig Operating Temperature 4100F Design Code ASME VIII Other Components Resin Centrifuge (1-WS-MM-611) Type Horizontal Capacity (4.7) gpm Operating Pressure Atmos. Operating Temperature Ambient Design Code Mfr. Std. Evaporator / Extruder Capacity Range (9.25 to 27.5) gph Operating Pressure Atmos. Operating Temp. 2800F Design Code DIN Shipping Containers Types 55 gallon drums, 100 ft3 LSA boxes, and 85 ft3 liners with associated shield Resin Filter (RS-F-19) Type Backflushable, vedgewire Design Code ASME VIII P

g. .v e TABLE 11.4-11 SilIPPING VOLUMES FOR BOTil UNITS PROCESSED USING ASPIIALT PROCESSED USING CEMENT BINDER VIA PERMANENTLY BINDER VIA ALTERNATE INSTALLED EQUIPMENT MOBILE EQUIPMENT Design Expected Design Expected Annual Annual Annual Annual Volume (ft3) Volume (ft3) Volume (fe3) Voluse (ft3) Sources Dry Active Waste,s a) Non-compactible Trash 8,800 4,400 8,800 4,400 b) Compactible Trash 5,100 2,600 5,100 2,600 s- $e Spent Demineralizer Resins 2,300 770 7,200 2,400 n 28,000 (p goo Evaporator Bottoms & Other 1,900 630 f^,^^0- -5,,500 Encapsulated and Solidified Filter Cartridges 600 300 600 300 TOTALS 18,700 8,700 '!,7 0- !!,000- &Z,"200 l(o,500 t

e _ TABLE 11.4-12 ANNUAL ACTIVITY AVAILABLE FOR OFF-SITE SHIPMENT FOR BOTH UNITS (Ci/yr) Dry Active Wastes Spent Demin Resins (l) Evap. Bottoms & Other(2) Isotope Design Expected Design Expected Design Expected Design _ Expected Totals I-131 2.9-1* 1.4-1 6.9+1 2.9+0 4.8+01 2.0+00 1.2+02 5.0+00 Sr-89 4.1+1 1.7+0 1.1+00 4.5-02 4.2+01 1.7+0 Sr-90 91 2.0+1 8.3-1 1.1-01 4.5-01 2.0+1 1.3+00 1.0+1 4.2-1 1.7+00 6.9-01 1.2+01 1.1+00 Zr-95 1.3+1 5.4-1 2.0-01 8.3-02 1.3+1 6.2-01 Nb-95 1.6+1 6.7-1 3.1-01 1.3-02 1.6+1 6.8-1 Mo-99 4.0-4 5.1-5 1.5-01 6.4-03 1.5-01 6.4-03 Cs-134 9.5+0 4.8+0 4.5+3 1.9+2 3.1+02 1.3+01 4.8+03 2.1+02 136 7.1+0 3.0-1 1.2+01 5.0+00 1.9+01 5.3+00 137 1.6+1 7.8+0 2.7+3 1.1+2 1.7+02 7.1+00 2.9+03 1.2+2 Te-132 1.4-3 5.8-5. 4.3-02 1.8-03 4.4-02 1.8-03 5-Ba-140 1.2+0 5.0-2 1.7-01 6.9-03 1.2+01 5.6-02 $ o-Ce-144 3.2+1 1.3+0 2.1-01 9.0-03 3.2+1 1.3+0 Mn-54 3'. 0 + 1 1.5+1 5.8+1 1.9+1 4.0-01 1.4-01 8.8+1 3.4+1 Co-58 5.8+0 2.9+0 5.5+2 1.8+2 8.6+00 2.9+00 5.6+D2 1.8+2 w 60 4.2+1 2.1+1 8.2+1 2.7+1 4.3-01 1.4-01 1.2+2 4.8+1 Fe-59 3.5+0 1.7+0 1.1+1 3.7+0 2.6-01 8.8-02 1.5+1 5.5+00 Cr-51 3.5+1 1.8+1 3.2+0 1.1+0 1.3-01 4.3-02 3.8+1 1.9+1 Zn-65 4.4-1 2.2-1 Others 1.7+0 8.6-1 4.4-1 2.2-1 TOTALS 1.4+2 7.2+1 8.1+3 5.4+2 5.5+02 1.1+01 8.8+03 6.3+02 1.7+0 8.6-1

  • 2.9-1 = 2.9x10-1 (1)

Sixty days decay minimum prior to shipout, t (2) Thirty days decay minimum prior to shipout.

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SBN-873 ENCLOSURE 3 Revised FSAR Section 12.2.1.5 i Source Terms for Solid Waste Management System Notes Extensive Revision 1 1 a

o SB 1 & 2 6 FSAR W b. Waste Gas Dryers The specific isotopic shielding source term for these components is assumed to be the same as that for the vaste gas chillers, i.e. taking no credit for iodine removal by the iodine guard beds. Each dryer contains 29% aluminosilicate by volume. The calculated isotopic inventory is presented in Table 12.2-27. c. Iodine Guard Beds The equilibrium accumulation of iodines at a gas flow of 0.75 scfm is used for the shielding source term for these components. The isotopic inventory used for shielding calculations is presented in Table 12.2-27. d. Carbon Delay Beds The source term for these components is based on a delay per bed of 12 days for Xenon and 17 hours for Krypton at a flow rate of 0.75 scfm. The shielding inventory for each of the beds is given in Table 12.2-27. e. Hydrogen Surge Tank ~ Shielding for this tank is based on the inventory of isotopes given in Table 12.2-27. This source term assumes that the tank is filled with gas at the specific activity calculated for the outlet of the fif th carbon delay bed at tank design pressure. f. Regenerative Compressor Shielding for this component is based on the same specific source term as for the waste gas dryers, given in Table 12.2-27. g. HEPA Filter l The source term for this filter was calculated on the assumption that one percent of the inventory in the last carbon delay bed is transported with charcoal fines to the filter cartridge. No credit is taken for decay of isotopes af ter leaving the carbon delay bed. The shielding design inventory is given in ' Table 12.2-27. ~ 12.'2.1.15 Source Terms for Solid waste Management System The source terms used for shielding calculations for the equipment in the Solid Waste Management System are listed in Table 12.2-29; the shielding l geometry and dimensions for these equipment are presented in Table 12.2-30. l The locations'of these. equipment are shown in Figures 12.3-8 thru 12.3-11. 4lIP i 1 l 12.2-15

) SB 1 & 2 M FSAR W l a. Waste Concentrates Tank, Waste Concentrates Transfer Pump The waste concentrates tank has a wo,rking capacity of 6000 gallons, and can hold roughly four batches of evaporator bottoms. The shielding source terms are based upon two batches of bottoms from the boron recovery evaporator, and one batch each from the liquid waste evaporator and the steam generator blowdown evaporator. No radioactive decay during transit has been considered. b. Waste Feed Tanks and Waste Feed Recirculation Pumps I The input stream to these tanks contains about 12% solids, by veight; after preparation / processing in the tanks, the output stream contains about 10.4% solids, by weight. The shielding source terms for these equipment are about 0.87 of those for the vaste concentrates tank described in (a) above. c. Spent Resin Transfer Pump, Spent Resin Hopper, Spent Resin Recircu-lation Pump, and Resin Centrifuge Metering Pump The shielding source terms for these equipment are the same as those for the spent resin sluice tank described in Subsection 12.2.1.9. d. Spent Resin Centrifuge The input resin slurry contains about 15% of resin, by weight; after the dewatering process, the remaining contents at the discharge from the centrifuge are about 50% resin, by weight (with no transport water). Therefore, the shielding source terms for the spent resin centrifuge are 3.3 times those for the spent resin hopper described in (c) above, Waste Crystallizer / Evaporator, Crystallizer Recirculation Pump, e. and Crystallizer Drain Pump The input vaste concentrates contains about 10.4% solids, by weight; after crystallizer / evaporation, the remaining slurry is about 35-50% total dissolved solids, by weight. Therefore, the shielding source terms for these equipment are 2.9 times those for the waste feed tanks described in (b). ,f. Concentrates Bottom Tank, Concent-rates Bottom Tank Recirculation Pump, Waste Metering Pump, and Alternate Station Concentrates Feed Pump The shielding source terms for these equipment are the same as those for the waste crystallizer / evaporator described in (e) above. Y I 12.2-16 1 I

SB 1 & 2 6 FSAR M g. Entrainment Separator, Crystallizer Condenser (Shell Side), Crystallizer Distillate Tank, Crystallizer Distillate Pumps, and Crystallizer Subcooler (Shell Side) These equipment are not expected to'contain significant radioac-tivity; the fluids are expected to contain about 1 ppm of solids, by weight. The shielding source terms for the equipment are about 8.3x10-6 of that for the vaste concentrates tank described in (a). h. Spent Resin Dewatering Pump This equipment is not expected to carry significant radioactivity. For conservatism, and consistently with the guidance given by NUREG-0017, the shielding source terms for this equipment are taken to be the same as those for the resin sluice pump described in Subsection 12.2.1.9. i. Crystallizer Reflux Pot and Crystallizer Reflux Pump These equipment are not expected to contain significant radioac-tivity. The shielding source terms for these equipment are taken to be the same as those for the crystallizer distillate tank described in (g). j. Extruder In the extruder, spent resins or crystallizer bottoms are mixed with the asphalt binder in a one-to-one ratio, by weight. The shielding source terms for this equipment are 0.5 times those for the spent resin centrifuge described in (d). 12.2.2 Airborne Radioactive Material Sources ll$p The major source of airborne contamination during normal operation is leakage of radioactive fluid from equipment and valves. Other sources from antici-pated occurrences include opening of sealed equipment and evaporation during fuel handling. Accident sources such as DBA, fuel handling accident, and radwaste system failures are discussed in Chapter 15. 12.2.2.1 Design Bases The concentration of airborne radioactive materials is one of the bases for the, design of the plant ventilation systems. The ventilation systems will maintain concentrations below the limits set by 10CFR20 in areas normally occup,ied by operating personnel, and provide the capability to reduce levels in areas not normally occupied within a reasonable period of time after equip-ment shutdown. Air flow is directed from areas of high occupancy and low airborne radioactive concentrations to areas of increasing contamination and lower occupancy requirements. Design basis maximum leakage rates to various buildings and compartments were chosen in accordance with NUREG-0017, as referenced by Regulatory Guide 1.112. Specific isotopic activity of the fluid leakage is based on 0.25% fuel clad defects, as discussed in Subsection 11.1.1. 12.2-16a

i SB 1 & 2 N FSAR TABLE 12.2-15 SOURCE TERMS FOR SPENT RESIN SLUICE SYSTEM 1. Spent Resin Sluice Tank and Spent Resin Transfer Pump Isotope Total (Ci) Conc. (uCi/gm) Cr-51 1.5(+1) 8.1(-1) Mn-54 6.6(+1) 3.6(+0) Mn-56 Co-58 9.9(+2) 5.4(+1)- Fe-59 2.8(+1) 1.5(+0) Co-60 8.4(+1) 4.6(+0) Sr-89 9.1(+1) 4.9(+0) Sr-90 2.0(+1) 1.1(+0) Y-90 2.0(+1) 1.1(+0) Sr-91 Y-91 2.0(+1) 1.1(+0) Y-92 Zr-95 2.4(+1) 1.3(+0) Nb-95 1.3(+1) 7.1(-1) Mo-99 1.3(+3) 7.1(+1) I-131 1.2(+4) 6.5(+2) Te-132 5.3(+2) 2.9(+1) I-132 5.3(+2) 2.9(+1) l I-133 l I-134 Cs-134 4.7(+3) 2.6(+2) I-135 Cs-136 1.7(+2) 9.2(+0) Cs-137 2.7(+3) 1.5(+2) Ba-140 3.1(+1) 1.7(+0) l La-140 3.1(+1) 1.7(+0) l Ce-144 3.6(+1) 2.0(+0) l Total 2.4(+4) 1.3(+3) Spent Resin Sluice Pump Concentrations are 10-4that of those. of sluice tank. O I 1 l

SB 1 & 2 M FSAR 6 TABLE 12.2-29 (Sheet 1 of 2) SHIELDING SOURCE TERMS FOR EQUT.PMENT IN 501:ID WASTE MANAGEMENT SYSTEM Nuclide Shielding Source Terms (uCi/gm) (a) (b) (c) (d) (e) 1-131 1.2+01* 1.0+01 6.5+02 2.2+03 3.5+01 132 4.7-01 4.1-01 2.9+01 9.7+01 1.4+00 Sr-89 3.0-02 2.6-03 4.9+00 1.6+01 8.8-02 90 2.0-03 1.7-03 1.1+00 3.7+00 5.8-03 Y-90 2.1-03 1.8-03 1.1+00 3.7+00 6.1-03 91 4.4-02 3.8-02 1.1+00 3.7+00 1.3-01 Zr-95 5.3-03 4.6-03 1.3+00 4.3+00 1.5-02 Nb-95 6.7-03 5.8-03 7.1-01 2.4+00 2.0-02 Mo-99 5.4+00 4.7+00 7.1+01 2.4+02 1.6+01 Cs-134 5.9+00 5.1+00 2.6+02 8.7+02 1.7+01 136 1.1+00 9.5-01 9.2+00 3.1+01 3.2+00 137 3.2+00 2.8+00 1.5+02 5.0+02 9.3+00 Te-132 4.7-01 4.1-01

2. 9 +01 9.7+01 1.4+00 Ba-140 1.6-02 1.4-02 1.7+00 5.7+00 4.7-02 La-140 1.4-02 1.2-02 1.7+00 5.7+00 4.1-02 Ce-144 4.4-03 3.8-03 2.0+00 6.7+00 1.3-02 Mn-54 8.0-03 6.9-03 3.6+00 1.2+01 2.3-02 Co-58 2.1-01 1.8-01 5.4+01 1.8+02 6.1-01 60 8.5-03 7.4-03 4.6+00 1.5+01 2.5-02 Fe-59 7.5-03 6.5-03 1.5+00 5.0+00 2.2-02 Cr-51 5.3-03 4.6-03 8.1-01 2.7+00 1.5-02
  • 1.2+01 = 1.2x101 Notes:

(a) Waste Concentrates Tank and Waste Conc. Transfer Pump (b) Waste Feed Tanks and Waste Feed Recir. Pump (c) Spent Resin Transfer Pump, Spent Resin' Hopper, Spent Resin Recir. Pump, and Fesin Centrifuge Metering Pump (d) Spent Resin Centrifuge (e), Waste Crystallizer / Evaporator, Crystallizer Recir. Pump, and Crystallizer . Drain Pump EEE

SB 1 & 2 FSAR TABLE 12.2-29 (Sheet 2 of 2) Nuclide Shielding Source Terms (uCi/gm) (f) (g) (h) (i) (j) I-131 3.5+01 1.0-04 1.6-01 1.0-04 1.1+03 132 1.4+00 3.9-06 7.3-03 3.9-06 4.9+01 Sr-89 8.8-02 2.5-07 1.3-03 2.5-07 8.0+00 90 5.8-03 1.7-08 2.7-C4 1.7-08 1.9+00 Y-90 6.1-03 1.8-08 2.7-04 1.8-08 1.9+00 91 1.3-01 3.7-07 2.7-04 3.7-07 1.9+00 Zr-95 1.5-02 4.4-08 3.3-04 4.4-08 2.2+00 Nb-95 2.0-02 5.6-08 1.8-04 5.6-08 1.2+00 Mo-99 1.6+01 4.5-05 1.8-02 4.5-05 1.2+02 Cs-134 1.7+01 4.9-05 6.5-02 4.9-05 4.4+02 136 3.2+00 9.2-06 2.4-03 9.2-06 1.6+01 137 9.3+00 2.7-05 3.7-02 2.7-05 2.5+02 Te-132 1.4+00 3.9-06 7.3-03 3.9-06 4.9+01 Ba-140 4.7-02 1.3-07 4.3-04 1.3-07 2.9+00 La-140 4.1-02 1.2-07 4.3-04 1.2-07 2.9+00 Ce-144 1.3-02 3.7-08 5.0-04 3.7-08 3.4+00 Mn-54 2.3-02 6.7-08 9.0-04 6.7-08 6.0+00 Co-58 6.1-01 1.8-06 1.4-02 1.8-06 9.0+01 60 2.5-02 7.1-08 1.2-03 7.1-08 7.5+00 Fe-59 2.2-02 6.3-08 3.8-04 6.3-08 2.5+00 Cr-51 1.5-02 4.4-08 2.1-04 4.4-08 1.4+00 Notes: (f) Conc. Bottom Tank, Conc. Bottom Tank Recir. Pump, Waste Metering Pump, and Alternate Station Conc. Feed Pump (g) Entrainment Separator, Crystallizer Condensor (Shell Side), Crystallizer Dist. Tank, Crystallizer Dist. Pump, and Crystallizer Subcooler (Shell Side) (h)[SpentResinDevateringPump (i) Crystallizer Reflux Pot and Crystallizer Reflux Pump (j)

  • Extruder S

l

~ SB 1 & 2 6 FSAR M TABLE 12.2-30 (Sheet 1 of 3) CEONETRY OF EQUIPMENT IN SOLID WA$TE MANAGEMENT SYSTEM Waste Concentrates Tank Diameter 10 ft. Height 11 ft. 9 in. Waste Concentrates Transfer Pump Diameter (internal) 4 in. Length 17 in. Waste Feed Tank (s) Diameter 5 ft. Height (including heads) 9 ft. 10 in. Waste Feed Recire'ulation Pump (s) Diameter (internal) 2 in. Leegth I ft. 6 in. Spent Resin Transfer Pump Diameter (internal) 2 in. Length 6 ft. Spent Resin Hopper Diameter 5 ft. l Height (cylinder) 6 ft. l Height (cone) 3 ft. t Soent Resin Recirculation Pump l Diameter 3 in. l Length 3 ft. 9 in. Resia Centrifuge Metering-lump ~ Diameter (internal) 2 in. c - Length I ft. 9 in. Spent Resin Centrifuge Diameter of bowl 1 ft. Depth of bowl 1 ft. 3 in. 9

c SB 1 & 2 6 FSAR TABLE 12.2-30 (Sheet 2 of 3) Evaporator / Crystallizer vapor Body Diameter 3 ft. Height (cylinder) 9 ft. 6 in. Height (cone) 2 ft. 9 in. Crystalliser Recirculation Pump Diameter (internal) 10 in. Length 6 ft. Crystallizer Drain Pump Diameter (internal) 1 in. Length 3 ft. Concentrates Botton Tank Diameter 5 ft. Height 8 ft. 6 in. Concentrates Botton Tank Recirculation Pump Diameter (internal) 1 in. Length 3 ft. 6 in. Waste Metering Pump Diameter (internal) 3/4 in. Length I ft. 6 in. Alternate Station Concentrates Feed Pump Diameter (internal) 2h in. Length 4 ft. 6 in. Entrainment Separator Diameter

  • 2 ft.

Height (including heads) 12 ft. 6 in, e Crystalliser Condenser Diameter 13 in. Height 11 ft. 6 in. l

o F TABLE 12.2-30 (Sheet 3 of 3) Crystallizer Subcooler Diameter 6 in. Height 11 ft. 6 in. Spent Resin Dewatering Pump Diameter (internal) 1 in. Length I ft. 3 in. Crystallizer Reflux Pot Diameter 1 ft. 6 in. Height (head to head) 29 in. Crystallizer Reflux Pump Diameter (internal) 1 in. Length I ft. Evaporator / Extruder Diameter (internal) 2 in. Length 15 ft. 9 in. i l l I l l l l i _ _}}

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