W3P83-0325, Forwards Revised Pages from FSAR Sections 11.2 & 11.4. Changes Reflect Latest Design Considerations in Radwaste Mgt & Will Be Incorporated Into Next FSAR Amend

Forwards Revised Pages from FSAR Sections 11.2 & 11.4. Changes Reflect Latest Design Considerations in Radwaste Mgt & Will Be Incorporated Into Next FSAR Amend

ML20083N775
Person / Time
Site:	Waterford
Issue date:	01/27/1983
From:	Maurin L LOUISIANA POWER & LIGHT CO.
To:	Knighton G Office of Nuclear Reactor Regulation
References
W3P83-0325, W3P83-325, NUDOCS 8302030118
Download: ML20083N775 (27)

Text

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o 142 DELARONCE STREET POWER & L1GHT P O. BOX 6008

• NEW ORLEANS. LOUISIANA 70174 * (504) 366-2345 L U iES SYS L. V. MAURIN Vice PresWent Nuclear Operations January 27, 1983 W3P83-0325 3-A1.01.04 Q-3-A29.11 Q-3-A29.18.31 Director of Nuclear Reactor Regulations Attention: Mr. G. Kr.ighton, Chief Licensing Branch No.3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Waterford SES 3 Docket No. 50-382 Waste Management

Dear Sir:

As was discussed with your Mr. Jack Hayes on November 2, 1982, please find attached revised pages from FSAR Section 11.2 and a revised FSAR section 11.4. These changes reflect the latest design considerations in radioactive waste managment at Waterford 3. The attached changes will be incorporated into the FSAR as part of the next amendment, but are forwarded to you now for your review.

Very truly yours, L. V. Maurin LVM/RMF/sw Attachment cc: E. L. Blake, W. M. Stevenson, J. Wilson (NRC) 00I 8302030118 830127 PDR ADOCK 05000382 A PDR

Insert A to Page 11.2-2 As an additional measure of assurance that liquid wastes can be processed during all plant conditions, piping taps have been installed in the LWMS process stream to allow use of a standby portable demineralizer system should the need arise.

Insert B to Page 11.2-7

......the provisions for a standby portable demineralizer.......

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- -- _ . - - .~ .- -.

WSES-FSAR-UNIT-3 steam activity). Since the activity will be extremely low, it will be l routinely discharged unprocessed after monitoring. However, if monitoring 4 reveals significant levels of activity the sump water will he routed to the '

Waste Management System.

11.2.1.5 waste Management System (WS) and Boron Management System (BMS)

The BMS and the liquid subsystem of the WMS are designed with sufficient capacity, redundancy, and flexibility to meet concentration limits of 10CFR20 during periods of equipment downtime when operating at design

, basis fuel leakage of one percent. The BMS has redundancy in its tanks, pumps, filters, ion-exchangers, and concentrators. The WMS has redundancy in its tanks and pumps. If the waste concentrator is down for maintenance, S one of the boric acid concentrators can be substituted so that the pro-y cessed fluid will experience the same high overall DF prior to being dis-M charged.4 In the case of the WMS, if a filter cartridge must be changed or u> cn ion-exchanger bed be replaced, sufficient tank.ge is provided to hold y the waste so that these operations can be performed with no loss of efficiency. The same is true for the BMS with the added advantage of redundant equipment.

The WMS and BMS are located in the seismic Category I Reactor Auxiliary Building.

Tanks outside of containment are provided with level indication and alarms i i

for high level conditions. The level alarms will alert operators when tanks  ;

cre nearly full and transfer flow from a filled tank to alternate tanks may  !

proceed. For cubicles which contain tanks with significant radioactivity [

i cnd thus require shielding, the floors in these cubicles will be pitched to floor drains located at low points to facilitate floor drainage.

Collection tanks and tanks which receive processed waste are generally pro-vided in pairs. The pairing of tanks allows one tank to be in the fill l

mode while the ether tank is in the sampling, recirculation, process, or standby mode. Since the schedule of influent waste (See Table 11.2-3 and 11.2-4) can be processed with approximately 10 percent operational time or less using the subsystems described in Subsection 11.2.2, an empty standby tank would normally be available for any filled tank. Thus, switching from one tank to another will normally prevent overflow of tanks.

The monitor tanks (i.e., boric acid condensate tanks, waste condensate tanks, and laundry tanks) can be sampled prior to discharge or prior to transferring to the outside water storage tanks (i.e., primary water storage tank or the discharge structure). If analysis indicates further processing is required l 27 the water will be reprocessed prior to leaving the building. Therefore, the potential release of water by overflowing outside storage tanks would not result in uncontr'olled release of radioactive materials. The outside storage-tanks have level detection instrumentation which will annunciate under high level conditions.

Tanks (besides the outside storage tanks discussed previously) which are not provided with a backup tank are the eauipment drain tank, spent resin 11.2-2 Amendment No. 27, (4/82) t _ ,. _ _ _ ,_ _ _ _ __ _ _ _ _ . _ _ _ _ ._ _ _ _

WSES- ESAR-UNIT-3 WATERFORD-3 FSAR 11.2.2.2 Waste Management System il The design of the WMS is presented in Figure 11.2-2. Principal flow paths through the system (heavy lines) and the release point (circulating water discharge) are clearly indicated on the figure. The figure indicates all system interconnections.

Process data is presented in Table 11.2-10. Input streams into the WNS are identified in Figure 11.2-2 and expected sources, volumes, and activities of waste influent are listed in Table 11.2-4. Decontamination factors are presented in Table 11.2-7 for WMS process equipment.

11.2.2.2.1 Miscellaneous Waste Miscellaneous non-detergent waste is collected in one of two waste tanks.

As wastes are collected, they are processed on a batch basis through an oil separator filter to reduce suspended oil when required and a filter to reduce suspended solids. The wastes are then processed through a waste  !

concentrator to remove dissolved solids and radioactivity. Concentrated bottoms from the waste concentrator are pumped to the Solid Waste Management System for solidification and disposal. A mixed bed (R-OH form) ion ex-changer is provided in the condensate path from the concentrator to further reduce any volatile species which carry over in the distillate. The con-densate is collected in one of two waste condensate tanks for sampling and i analysis prior to release to the circulating water discharge. Discharge I activity is monitored for radioactivity, as described in Section 11.5. '

, 00 y, All potential bypass routes in the WMS are indicated in Figure 11.2-2.

Q Because of the redundancy of equipment (sharing BMS concentrator if hj necessary) band the waste tank capacities, it is not expected that equip- L M ment will need to be bypassed very frequently. If process equipment is by- '

kk passed for any reason, and sampling of the waste condensate tank shows that i further processing is necessary, the contents of one tank can be recycled back through a filter, concentrator, or ion exchanger as desired, and collected in the second tank. ,

The WMS has sufficient capacity to accept liquid waste during startup, shutdown, and refueling.

11.2.2.2.2 Laundry Waste Liquid detergent waste from the laundry, laundry sump, contaminated abowers, and contaminated sinks are collected in two laundry tanks. The vaste is normally sampled to assure lo'w activity and then pumped through a filter directly to the circulating water discharge. Discharge activity is monitored as described in Section 11.5. Should the need arise, laundry and decontamination vastes can be processed using the waste concentrator, al-though this is not recommended practice.

11.2.2.3 Steam Generator Blowdown System The Steam Generator Blowdown System (SGBS) is described in Section 10.4-8.

The waste removed by the blowdown filters and the waste produced by regen-11.2-7

11.4 SOLID WASTE MANAGEMENT' SYSTEM High activity radioactive wastes and low activity solid radioactive waste are processed, packaged and stored for subsequent shipment and off-site burial by the Solid Waste Management System (SWMS). Wastes include waste concentrator bottoms, spent ion exchange resin, used filter cartridges and miscellaneous refuse.

11.4.1 DESIGN BASES The design bases of the SWMS are as follows:

a) Provide for receiving and interim storage of concentrates from waste concentrator package and spent resins. The SWMS provides for transfering concentrates from boric acid concentrator packages to SWMS.

b) Provide for holdup capacity for normally radioactive spent resin to allow decay of short lived activities.

c) Provide for receiving and adjusting water content (dewatering and/or adding measured amounts of water) of radioactive wastes such as -

spent ' resins .

d) Provide remote means for transferring used filter cartridges from their respective filters to the drumming area. Appropriate lifting grabs and remote tools will be used during filter transfer.

e) Provide means to compact low activity solid waste such as contaminat-ed clothing, rags, paper, laboratory equipment and supply items.

f) Provide means for encapsulation and solidification of wastes in large volume disposable liners for subsequent shipment and off-site burial.

g) Prevent the release of significant quantities of radioactive materials. The overall exposure to the public and operating personnel will be kept within the requirements of 10CFR20 and 10CFR50.

h) Disposal and transportation of wastes from the SWMS including the shipping containers, will satisfy the requirements of 10CFR20, 10CFR71, and 49CRF173.393 (1072).

1) The SWMS components are not safety related and are not designed to seismic Category 1 requirement.

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11.4.2 SWMS DESCRIPTION The SWMS is shown schematically on the Figures 11.2-2 and 11.4-6. Layout drawings are in Section 1.2.

The SWMS will be operated to cast liquid and solid radioactive wastes into a solidified waste product which will be disposed of at a burial site.

A comparison of the system requirements versus capabilities is provided in Table 11.4-2.

The SWMS will provide interim storage of radwaste and process it in a batch manner. The system will put filter cartridges into disposal cask liners. Waste evaporator concentrates will be mixed with a solidifying agent in disposable cask liners. The cask and liners are transferred to a storage area before shipping.

Before starting solidification procedures, the radioactive level and chemical composition of the wastes vill be determined.

11.4.3 INPLANT SOLIDIFICATION SYSTEM DESCRIPTION The evaporator bottoms are collected in the concentrate storage tank. A cement silo is provided for the storage of Portland cement and a sodium silicate tank is provided for storage of sodium silicate. Both are used as the solidifying agent. Concentrates are pumped by a positive displace-ment pump at a controlled rate to the process pump mixer where the wastes are mixed with Portland cement. The process pump mixer assures a uniform mixture of waste and Portland cement. Sodium silicate is added downstream of the process pump mixer. Uniformity of mixing is assured by the fluidity of the constituents.

The dewatering tank, which is used for waste processing but not for waste storage, will be used to provide flexibility and control of waste to be solidified. Desired volumes from the concentrate storage tank can be metered into the dewatering tank or pumped directly to the mixer. After producing a desirable mixture of wastes in the dewatering tank, the opera-tor can set the total amount and rate of feed by adjusting the flow ratio of the metering pump to the mixer and by adjusting the rotary feed valve downstream of the solidifying agent tank.

Both the dewatering tank and the concentrate storage tank are automatically controlled at 140 F with adequate heating elements such that the concentrates (21,000 ppm boron by weight) do not deposit in the system.

Temperature and level of the dewatering tank and concentrate storage tank contents are displayed on the control panel.

The Portland cement will be delivered to the site in a self-unloading bulk truck carrier. A pipe connection will be provided at the unloading station for conveying the cement to a dust-tight bulk storage hopper.

The entire system will be vented through a bag filter located on top of the storage hopper. The atmospheric exhaust from the bag filter will have an outlet dust load of less than 0.02 gram per cubic ft. of air. For 2

ease in handling, the cement in the storage hopper will be continuously fluidized by a flow aerator located in the bottom of the storage bin.

A separate control panel for the cement handling subsystem is provided.

This panel contains the bag filter, aeration blower and cement-level indicators.

A single fill port is provided for packaging all wastes. Interlocks are provided to prevent system operation if no radwaste container is in place under the fill. port or in the event of component malfunction. The fill port is equipped with a vented splash guard that seals the liner during filling. A mixer bypass is ~ provided that permits direct discharge of wastes into the container, if desired. Since a completely mixed liquid stream of waste cement and sodium silicate flows into the container, there is no danger from airborne contamination. Filling of the container is monitored by an ultrasonic level indicator that automatically stops the filling operation when the waste reaches a predetermined level in the drum.

At the completion of each fill cycle provisions are provided for thoroughly flushing with water all portions of the systems that have contained the cement waste mixture. The small contained volume of the mixer permits thorough cleaning with the production of a minimum of added waste.

The entire process, dewatering, mixing and filling will be monitored and controlled from a completely equipped control console by a single operator.

Thus personnel radiation exposures are kept at a minimum within the requirement of 10CRF20 and 10CRF50. These controls minimize the chances of releasing radioactive materials.

Compressed air is required for the cement silo to fluidize the cement and the spent resin storage tank to mix and transfer the spent resin to the dewatering tank. The flow rate of compressed air for the cement silo storage tank is 100 cfm at three psig and for the spent resin tank 15 cfm at 15 psig. The cement silo is dust tight and the entire cement system will be vented through a bag filter located on top of the storage hopper.

At the capper unloading station shown in Figure 1.2-9 the liner is capped and decontaminated if necessary by remote flexible hoses. The waste from the decontaminated liners will be collected through the floor drain to the floor drain sump, and then pumped to the Liquid Waste Management System.

11.4.3.1' Equipment Description Table 11.4-1 gives the list of system components, their capabilities, design pressure, design temperature, flow rates and materials of construction.

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f 11.4.3.2 System OperacI6H aHa Controls Functional automatic controls are provided by which the operator activates controls sequentially. Interlocks will allow a control to be activated only when the next previous control has been satisfied. A manual mode of operation is prcvided so that interlocks are bypassed and iadividual components are operated from the control panel.

The concentrate storage tank and the dewatering tank are provided with

level indication and alarm for;high level conditions. The level alarms will alert operators when tanks are nearly-full. In the event of operator

{~ error or equipment malfunctions (e.g. high level alarm failure) that-may result in overflow of tanks, the concentrate storage tank and the dewatering tank will overflow to the floor in their respective cubicles.

Curbing will prevent the spread of. liquid from the cubicle. This

- provision to prevent entry of the concentrates.into the floor drain system is necessary to prevent potential solidification within the drainage system.

11.4.4 SOLIDIFICATION PROGRAM ALTERNATIVES Two systems have been considered for handling solid wastes from plant operations:

j a) The installed plant solidification system, b) Portable solidification systems supplied by contractors.

. Evaluations of these alternatives covering currect regulations on shipping l, and burial criteria, radiation exposures to operating and maintenance personnel and interim plant storage requirements have been performed.

! 11.4.4.1- Installed Plant Solidification System i Certain design and ALARA concerns have been identified on the Inplant Cement Solidification and handling portion of the SWMS. LP&L has made a decision not tn address these concerns prior to initial plant i;

start'up. Therefore these .ystems will not be used at this time. The i status and ultimate use of this system will be addressed on a backfit basis.. Should evaluations at that indicate.the feasibility of routine usage, these concerns shall be resolved prior to use of the system.

11.4.4.2 Portable Solidification System

- Waterford #3 will utilize a vendor supplied portable solidification system to provide for those plant solidification requirements not satisfied by installed plant equipment. This portable solidification system will be ,

' housed in a weatherproof structure'with curbing and a sump system which 4

Ldischarges to the LWMS. An overhead bridge crane is provided for lifting L

4 requirements up to 10 tons. This structure will be located on the west side of the RAB adjacent to the existing in-plant solidification area (See -TIgure 11.4-1) .

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4 11.4.5 PORTABLE SOLIDIFICATION FACILITY (PSF)

The function of the PSF is to provide shelter for the contractor's portable solidification equipment and to supply the necessary service requirements and waste delivery for this system. In addition to service provided to this facility (air, water, electric power), a ten ton over-head crane is provided to handle the portable solidification equipment.

The bridge crane has full travel over the interior area of the PSF.

The operation of waste solidification (and/or resin dewatering) will be performed in a shielded waste liner mounted upon a trailer. This trailer shall be backed into the PSF and the work performed in this enclosed building. Waste is supplied to the liner by flexible hoses connected to waste transfer lines routed fr:m inside the RAB out to the

PSF. Support equipment for the portable system is mounted on skids.

The PSF will supply space for the trailer, the skid mounted equipment, and materials required by the contractor for solidification. (See Figure 11.4-2)

The PSF is a pre-engineered, prefabricated sheet metal building with interior dimensions of 24' wide by 55' long with a 30' high eave. The building is located on the concrete truck platform on the west side of the RAB. The area selected for erection of the PSF is between the RAB main access doors and the solidification area doors at elevation +21'.

(See Figure 11.4-1)

The existing concrete slab on the west side of the RAB is only 40' wide, so an additional 15' by 24' section of slab is added to support the building.

A combined foundation and curbing ir constructed on this slab to serve both as a point for attaching the building's siding and as curbing to contain any potential spills within the PSF.

The design of the PSF satisfies the applicable requirements of R. G.

1.143, NUREG-0800 BTP-ETSB 11-3 and the applicable ACI and AISC Codes and Standards. The BTP, which specifies minimum requirements for portable solid waste systems, calls for equipment to be located on concrete pads with curbs and drainage provisions for containing radioactive spills. To manage potential spills, a sump is provided in the PSF with provisions to interface with the plant radwaste systems to return any collected liquids.

11.4.6 STORAGE FACILITIES The storage facilities for the solidified waste are shown on the general arrangement drawing Figure 1.2-9. The in-plant Liner Storage Area is a remote shielded storage area totaling 391 square feet for storage of radioactive waste solidified in disposable liners. In addition, an outdoor area has been prepared for storage of additional liners as discussed in Subsection 11.4.7. Solid waste storage capacity is detailed in Table 11.4-3.

a) Solidified Waste Per Design Basis For Waterford SES No. 3 There is sufficient space for over two months of remote and ,

shielded storage for wastes which are normally stored before shipment.

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b) Values of Waste Given By The NRC (See Question 321.22)

.The 391 square feet Liner) Storage Area in. addition to the intermin storage discussed in Subsection 11.4.7 have sufficient capacity for remote and shielded storage of the radioactive-(spent resin and concentrates) waste per NRC given volumes. '

-c) Dry Waste Storage Storage of dry uncompacted and compacted miscellaneous dry wastes is discussed in Subsection 11.4.8.

11.4.7 INTERIM SOLID WASTE STOR4GE A permanent onsite low-level radioactive storage' facility is being constructed. Nowever this facility will not be available during the early phases of operation. To provide for temporary-storage of solid wastes

-prior to shipment during the interim period, a designated storage area will be provided on the East side of the plant adjacent to the RAB and

-within the security fence. A concrete pad with fencing and a locked gate will be constructed in an area accessible to trucks and mobile heavy lifting equipment.

Solidified concentrates, spent filter cartridges and waste resins will be placed in disposable liners and stored in this area prior to shipment.

Only solid waste in acceptable form for shipment will be stored in this interim solid waste storage area.

Shielding will'be provided through the use of "on-site storage containers".

-These are reinforced concrete containers with removable lids sized to j handle the common cask liners and radiation levels currently in use.

These containers are made weatherproof with a. gasket seal between the

, container and lid._ Provisions are made to-sample and remove any water l found between the' disposable liner and onsite storage container.

[ This interim solid waste storage area will contain sufficient provisions i

to. store end shield up to 1000 cu. ft. of additional solid waste.beyond that provided within the plant. Should Waterford experience an extended period in which routine shipments of solid waste to a burial facility j could not be made, this area could be expanded and additional onsite

, storage containers procured'in a short period of~ time.

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11.4.8 INTERIM DRY COMPACTED WASTE FACILITY i-Space available within the reactor auxiliary building may not be sufficient j- for the projected peak volumes of dry compacted waste, therefore, Waterford

- is installing a metal ~ building for interim operations to house a dry

! radioactive waste compactor machine and additional storage area for the compacted dry waste metal boxes. The metal building is located inside the l security fence ~between the existing water treatment building and chiller building. The location of the interim facility is shown on Figure 11.4-3.

A permanent onsite low level-radioactive waste storage facility is being t constructed which will include provisions for the waste compactor and l- storage of dry waste, however this facility will not be available during the 1 6

o early phases of operation. The interim dry compacted waste facility will support plant operations until that time. These facilities comply with the intent of NUREG-0787, Waterford Unit #3 Safety Evaluation Report, item 11.2.3.3.

11.4.1.1 Interim Dry Compacted Waste Facility Description The interim metal building meets the applicable requirements of R. G.

1.143, NUREG-0800 SRP 11.4, BTP-ETSB 11-3, Appendix 11.4A, and the applicable ACI and AISC codes and standards. The metal building is a completely enclosed structure which includes a separate partitioned room housing the compactor machine. The compactor machine has a self contained closed loop ventilation system thus minimizing the risk of air-borne radioactive contamination. The compactor room is constructed with smooth, continuous internal surfaces to facilitate decontamination should it ever be required. The entire building is constructed on a reinforced concrete slab with curbing such that water is kept from entering the building.

The building is 55' by 40' and has sufficient storage capacity to house 76 compacted 6' X 4' X 4' metal waste boxes. The boxes are handled with a forklift. (See Figure 11.4-4).

Space has also been provided in the facility to temporarily store contaminated laundry. This area is 8' x 22' and walled separately from the waste compaction activities.

11.4.8.2 Waste Compactor Description The box compactor utilizes hydraulic pressure to compact low activity solid waste such as contaminated clothing, rags, paper, laboratory waste and miscellaneous low level contaminated material from maintenance activities.

The compressible waste is placed inside a 4' X 4' X 6' metal box and compressed by a vertically moving piston. The hydraulic press contains its own hood, ventilation fans and high efficiency filter. The displaced air is vented through high efficiency filters. After a predetermined waste volume is attained, the container is sealed and placed in storage. The hydraulic press and uaxiliaries are skid mounted with start-stop switches mounted locally and independent of other solid waste system controls.

11.4.9 RADIOACTIVE FILTER HANDLING Filter cartridges are replaced using a bottom loading filter transfer cask. After remotely removing bolts on the head of the filter, the filter cartridge is lifted into the filter transfer cask and the cask is closed.

The disposable filter and the filter transfer cask are placed on the filter transfer vehicle by means of monorails located above the filter cubicles. Remote viewing of these operations will be provided as required and water is supplied to facilitate decontamination of filter areas.

The filter transfer cask and disposable filter cartridge are moved to the solidification area by the filter transfer vehicle. This arrangement minimizes radiation exposure to personnel and allows the movement of the cask with loaded filters from the filter housings to the solidification 7

area.

At the solidification area an overhead crane is used to lif t the transfer cask containing the filter cartridge into position over a shipping liner.

The bottom of the cask is removed and the filter lowered into the liner.

The liner, after being sealed is positioned in a shipping cask or on-site storage container for shielding purposes and storage prior to shipment.

The filter handling process will be completely tested in all modes of operation to verify proper operation by the startup testing group prior to plant operations.

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11.4.10 SPENT RESIN TRANCFER SYSTEM The purpose of the Spent Resin Transfer System (SRTS) is to provide the following services:

a) Collect and store spent radioactive ion exchanger resin from the various nuclear process demineralizers.

b) Transfer resins to the Solidification System.

The SRTS has the following modes of operation:

a) Spent resin tank fill b) . Spent resin tank dewatering c) Spent resin tank water addition d) Resin mixing and recirculation e) Resin transfer mode to the solidification system.

f) System flushing 11.4.10.1 System Description The SRTS consists of the following components: One spent resin collection tani, one spent resin transfer pump, two resin strainers, and associated valves, piping and controls.

Spent ion. exchanger resin from the waste condensate ion exchanger, boric acid condensate demineralizers, preconcentration ion exchangers, fuel pool demineralizers, purification ion exchangers and deborating ion exchangers are sluiced to the Spent Resin Tank. After the sluicing operation is complete, excess water is removed from the tank using the tank de-watering connection and the resin transfer pump. The water is pumped to the waste collection tank via the local sump pump discharge line for processing by the Liquid Waste Management System. The water level in the Spent Resin Tank is maintained such that it covers the top of the settled resin bed.

When a predetermined amount of resin has been collected in the resin storage tank, the resin is pumped to the Solidification System by the Spent Resin Transfer Pump. This transfer is accomplished by taking a bleed line to the solidification system off a recirculation line. A valve is provided in the recirculation line which will create back-pressure in the line when valving is open to the solidification system.

Excess sluice water is pumped from the' system back to the Spent Resin Tank via the recirculation line.

When resin transfer is completed, the system is flushed to remove any residual resin from the piping system. Water in the Spent Resin Tank is supplied either from dewatering operations or water added to the tank specifically for this operation. During flushing, the Spent Resin Transfer Pump takes suction from the dewatering connection on the Spent Resin Tank. The majority of the residual resin is flushed back=to the Resin Storage Tank with the remainder directed to the solidification system.

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t For schematic representation of the SRTS, See Figure 11.4-5..

11.4.10.2 Component Description and Location The major components used within the SRTS are:

a) Spent Resin Tank - quantity: One b) Spent Resin fransf Pump - quantity: One c). Piping and valves id) Strainers - quantity: Two e) .

Resin Sampling Valve f) Sight glass General Description Of Each Major Component a) Spent Resin Tank The Spent Resin Tank, fabricated of type 304 stainless steel, is located in the southwest quadrant of the Reactor Auxiliary building on elevation - 35.00 feet-MSL. The tank is located in a shielded cubicle. The Spent Resin storage tank has a capacity of 3200 gallons (427 cu. ft.).

b) Spent Resin Transfer Pump An open impeller centrifugal type pump with double mechanical.

seal draws suction from the spent resin tank. The pump is located in a shielded area in the southwest quadrant.of the a Reactor Auxiliary Building just south of spent resin tank room on elevation - 35.00 feet MSL.

The pump has a capacity of-230 GPM abd is powered by a 20 hp electric motor, c) Piping And Valves The SRTS piping is fabricated of austenitic stainless steel, type 304, and is designed in accordance with: ANSI B31.1. All piping containing slurry is run utilizing five (5) diameter.

bends, lateral type fittings on branch connections, butt welding and is run in shielded areas and chases to the maximum extent possible.

The process valves are plug type valves with ultra high molecular weight-polyethylene seats. Valves with air operators are provided with limit switches and fail safe provisions where required.

d) Strainers Two (2) stainless steel "Y" type resin strainers sized at 80 mesh prevent resin fines from entering the waste system and the 10

= sump system during system drainage'and dewatering operations, respectively. The strainer at the dewatering line is back-  ;

washable.

e) Resin Sampling Valve The valve is an_Isolok liquid / slurry sampler which can extract a 10 C.C. sample slurry from the recirculation pipe by operating the manual cycle control switch.

- f) Sight Glass A sight glass is located at the inlet header of the Spent Resin

> . Tank to verify resin flow into the tank.

11.4.10.3 Design Basis The SRTS'is designed in'accordance with'the following:

a) Provide holdup capacity for normally radioactive spent resin to allow decay of short lived isotopes.

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- b) Provide for receiving and adjusting water content in the Spent Resin Tank.

1 c) Provide a.means to transport resins to the solidification system-

using a recirculation loop concept.

d) Prevent the release of significant quantities of radioactive

' materials. The overall exposure to the public and operating personnel will be kept within the requirements of 10CFR20 and 10CFR50.

ae) The SRTS is located entirely in the seismic Category I Reactor 4

Auxiliary building. The SRTS components are not safety related and are not designed to seismic Category I requirements.

f) Provide a means for system flush after a resin transfer operation.

4 g) Provide a means for resin slurry sampling.

The Spent Resin Tank is provided with level indication and alarms for high and low' level ~ conditions and is provided with a level device for monitoring the interface level of the settled resins. Level alarms alert operators when tanks'are nearly full or' empty. Aporopriate control devices shut off the resin transfer pump on-low-low-level and' prevent overfilling of the Spent Resin Storage Tank by closing the inlet valve on high-high. tank level. .

The SRTS sizing is based on the following:

- Recirculation loop piping is a minimum of 3 inches.I.D. in order to minimize' the potential .for plugging.

- ' Resin slurry velocity is approximately 10 ft/sec. higher than normal velocity helps insure that resin will remain in suspension

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during pumping.

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- Resin slurry feed l rate to the solidification system is 30 gpm.

The SRTS is located in the Reactor Auxiliary building which is designed to Seismic Category I. Therefore, uncontrolled release to the environs would not occur as a result of a seismic =occurence. The design and fabrication codes, seismic category, and classification, meet the requirements of Regulatory Guide 1.26 (Rev. 1) and 1.29 (Rev. 1).

] .To reduce radioactive.releascs to the building atmosphere, the following design features hart been incorporated into the system design:

. a) Venting of the Spent Resin Tank is to the Vent Gas Collection Header.

r b) The Spent Resin Tank overflow is provided with a loop seal to prevent the escape of radioactive gas.

c) Zero stem leakage valves are used on the process lines.

! 11.4.10.4 INSTRUMENTATION & CONTPOL i

, The control panel for, monitoring and controlling the SRTS is located at i the solid radwaste area of elevation +21' MSL. A mimic graphic panel with control switches, indicating lights, alarms and analog readout provides information to the operator. Operation of the SRTS is automatic with manual initiation at key controlling steps, i.e. start pump or open discharge valve. The operator can also override the automatic sequence, if necessary.

t The SRTS utilizes a programmable controller (PC) to accomplish the functions required in the different modes of operation. The PC is located in the.controi panel located'+21 feet of the RAB. .A local instru-ment rack containing system transmitters is located at elevation -35 feet

. MSL in the RAB just outside the Spent Resin Tank / Pump cubicles.

! The SRTS has two level instruments, one for the spent resin level and the other for water level. These two instruments provide information to the operator to select the appropriate operating mode.

Spent resin level - A stainless steel float with a transmitter is used to. measure resin / water interface. The instrument includes a transmitter

, to send a signal to the control panel. The' programmable controller compares this signal to the water level. Jul alarm will be actuated should the water / resin ratio exceed a predetermined' limit or water level

• drops below resin level. The instrument has a hand crank to lift the. float,

, if desired, and a local dial level indicator. .The stainless steel float is custom-made with a specific gravity of 1.2.

Water level - The water level is monitored by a differential pressure instrument. A transmitter sendsasignal to the contro1~ panel, which

' will isolate the tank at hi-hi tank level or trip the pump at lo-lo tank

level.

12

Pump discharge pressure - Pump discharge pressure is monitored by a pressure transmitter for pump protection. The pump is tripped automatically at high discharge pressure (dead headed) and low discharge pressure (cavi-tation).

Pump seal water pressure - The double mechanical seal is protected by a pressure transmitter. Low pressure signals lack of water in mechanical seal and will trip the pump automatically.

DP across dewatering strainer - High pressure signals that the strainer is clogged and will actuate an alarm.

Programmable controller - A programmable controller having 2K expandable to 8K RAM memory, automatic sequencing, monitoring and alarm. Communica-tion between local instruments and control panel is via a remote I/O system. A CRT with its keyboard may be used to reprogram the automatic sequence and set points.

11.4.11 RADIOACTIVE MATERIAL PACKAGING Packaging containers will consist of disposable steel liners or high integrity containers (HIC). When dose levels dictate shielding these are contained in lead-shielded shipping casks. The lead shielded shipping casks meet the requirements of specification 55 of 49CFR178.250 (1972).

Solid wastes contained in disposable steel liners meets all the require-ments of a specification 7A, Type A package of 49CFR178.350. Most of the waste shipments are expected to be either

" Low Specific Activity" or Type A. Should Type B containers be required, a special Type B overpack will be rented from a licensed radioactive waste disposal company.

Large or highly radioactive components and equipment contaminated during reactor operation and not amenable to compaction either by qualified plant personnel or by outside contractors specializing in radioactive materials handling, are packaged in shipping containers of an appropriate size and design.

Interlocks are provided to assure proper hookup of monorail or crane to liners to prevent dropping a container. In the unlikely event of container rupture, no liquid spillage would occure since the material is handled in the solid form.

11.4.12 RADI0 ACTIVE MATERIAL SHIPPING All wastes will be shipped in accordance with 49CFR requirements. The containers and vehicles will be monitored and decontaminated if required for off-site shipment. The shipment of prepackaged solid radioactive waste from the plant site to burial locations will be contracted to firms licensed to transport radioactive materials in accordance with applicable DOT regulations.

13

o b E' TABLE 11.4 1 SOLID WASTE MANAGEMENT ST' STEM COMPONENT GUM 1 ART DATA Normal Design Operating Moraal Design Pressure Design .Fressure Operating Code Capacity pelt Temp. F peig Temp. F Materlal Tanks Quantity 50 200 12 100 SA 240 Spent Seein  ! ASME Section 3200 set

• Type 304 Tank Will Div, I (1913)

ASME Section 100 ft Ata 150 Ato 140 ASTM A 240 Dewatering Tank 1 Vill Div. 1 (1973) 3000 gal Ate 150 Ata 160 ASTM A-240 Concentrate 1 ASME Section '

Storage Tank Vill Div. 1 (1973) 500 ft 3 Ata 140 Ate 0-120 ASTM A-36 Cement Silo 1 Mone I None 200 ft Ata 140 Ate 0-120 " ASTM A-36 Sodium $111este Tank w Design Design Motor Pressure Deelen Flow Matar- Se al Motor Voltage / .

gelg Temp. F rpm , tal Tyge HP Phase /Hs Fumpo Quantity Standardo Tyge Concentrate Storage 1 Manufacturer's Fangressing 100 180 7.5 ss 316 Mech. 2 460/3/60 Tank Metering Pump St anda rd Cavity I Manufacturer's Progressing 100 180 7.5 s5 316 Mech. 2 460/3/60 Dewatering Tank Metering Pump Standard Cavity Manufacturer's Progressing 100 180 10 SS 316 Mech. 2 460/3/60 Process Mixing 1 '

Fump Standa rd Cavity Sodium Silicate Pump 1 Manufacturer's Progressing 100 10 0 0.75 Cl-sod y Mech, t 46d/3/60 Cavity gana N-Stator ,

Standa rd i

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TABLE.11.4-2 SOLID WASTE MANAGEMENT PROCESS DATA System Requirements Solidification System Capabilities Output of Process SystegsOutput Fraction of Solidified Flow Ft /Yr Process Remarks

. Type of Waste Waste Rate Capacity Used FT3/YR GPM g Values Given by NRC (Question 321.22)

Spent Resins 300

• 2/3 of System Design Solidified conc. 13,300 -

~ Flow rate (using 7.5.

, GPM pump)

Total 13,300 5 49,439 26.9%

Dry waste 10,000 ** 23,520 42.5% Based on filling one 96 ft3 dry waste box per day and 245 work days per year.

t l

_ * -T

TABLE 11.4-3 SOLID WASTE MANAGEMENT STORAGE CAPACITY Type of Waste FT / YEAR fof 195 FT LINERS /YR # of Liner Number of Spaces Allocated Months Storage For Storage NRC VOLUMES (see Table 11.4-2)

Spent Resin 300 2 1 6 Concentrates 13,300 68 14 2.5

- Dry Waste '10,000 105 76 8.7 5

• 3 3 Available shielded storage area = 391 ft for 9-195 ft liners plus 6-195 ft liners stored in the interim solid waste storage area.

• • Number of 96 ft boxes /yr.

i a

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