ML19270F243

Forwards Initial Response to Effluent Treatment Sys Branch Question (Q320.8) Re Solidification Process Control Program.Response Will Be Transmitted to NRC in FSAR Amend 4

ML19270F243
Person / Time
Site:	Comanche Peak
Issue date:	01/31/1979
From:	Leonard E TEXAS UTILITIES SERVICES, INC.
To:	Naventi R Office of Nuclear Reactor Regulation
References
TXX-2946, NUDOCS 7902050188
Download: ML19270F243 (35)

Text

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TEXAS UTILITIES SERVICES INC.

2001 11RY AN TO% EH D \l.1.Ah, TE N As 7520t TXX-2946 January 31, 1979 Mr. R. Naventi Licensing Project Manager Light Water Reactors Branch No. 4 Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 COMANCHE PEAK STEAM ELECTRIC STATION NRC EFFLUENT TREATMENT SYSTEM BRANCH QUESTION DOCKET NOS. 50-445 & 50-446 FILE NO. 10010

Dear. Mr. R tenti:

Enclosed is our initial response to ETSB question (Q320.8). As agreed, this is being transmitted to you by letter to expedite response time. This response will be retransmitted to the Commission in FSAR Amendment 4.

If you have any questions about this matter, please contact this office.

Sincerely, e42nSAl E. J. Leonard EJL:tls Enclosure cc: H. C. Schmidt 99o205 01%% \

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CPSES/FSAR Q320.8 Your response ta Question 320.7 on the solidification process control program and the parameters to be considered for the solidification of waste is not adequate. Provide more detail concerning the process control program including the following:

a. Data concerning the expected waste types to be processed. The process control program should be based on tests perfonned with simulated waste fonnulations based on the exracted inputs. You should discuss hou the process control program considers the chemical constituents of the waste stream, the pit of the waste stream, boric acid content, solids content of the waste, cncentration and type of radwaste, curing time, etc.

b. Data concerning the solidification agents (VF +

catalyst) to waste ratios to be used. The process control program should consider the correct ratios

, for the various input types and contaminant levels.

c. Data concerning the effects of various contaminants on the solidification process. Specifically, address oil and detergent content in wastes, lab chemicals, and non-depleted ion-exchange resins.

d. Discuss the experimental procedures to be used in your process control program. Discuss sampling of the waste input to the SRS as it relates to your process control progran to assure a satisfactory

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solidified product. Where will the waste be sampled?

320-9 JANUARY'31, 1979

CPSES/fSAR Discuss how the results of the process control progra:n will be analyzed and used as operational considerations.

R320.8 See revised Section 11.4.

320-10 JANUARY 31, 1979

CPSES/FSAR 11.4 SOLID WA5TE IW1AGEl'E!!T SYSTEM The solid vaste management system (SWMS) is des.igned to control, collect, handle, process, pa~ckage, and temporarily store, prior to offsite shipment, solid radioactive waste generated as a rosult of normal operation, including anticipated operational occurrences. The SWMS is a major subsystem of the WPS. The SWMS consists of the Radioactive Waste Solidification System (RWSS) and the waste baling subsystem. The RWSS, located in the Fuel Building, is designed to serve Units 1 and 2. The waste baling si.bsystem has a baler located in each Containment Building and in the Fuel Building.

11.4.1 DESIG:1 BASES 11.4.1.1 , Design Ob.iectives The design objectives of the RWSS and waste balers are to meet the requireaents of 10 CFR Parts 20, 50, and 71 and United States Department of Transportation (DOT) liazardous Materials Regulation 49 CFR Parts 170 through 178. The details of the RWSS and the baling l 4 subsystem are shown in ATCOR topical report no.132A and Figure 11.4-2 fQ320.8 respectively.

The RWSS is designed to safely package spent resins spent filter cartridges, evaporator concentrates, reverso osmosis wastes, and 4 chenical drain tank contents in 50-f t3 containers with cement as the Q320.8 solidifying agent.

The baling subsystem uses a compactor type-baler to package low-radiation-level compressible wastes such as paper, disposable clothing, rags, towels, floor coverings, shoe covers, plastics, cloth smears, and respirator filters in 55-gal drums. These wastes are products of plant operation and maintenance.

11.4-1 AMEllDMEflT 4 JAflUARY 31, 1979

CPSES/FSAR The radiation exposure to operating personnel during any maintenance, decontamination, or nonnal operation is limited to 25 prem/hr.

Radiation monitoring is conducted as described .in Section 11.5.

11.4.1.2 Design Criteria The input to the SWMS is from various sources. The incompressible solids and liquids are solidified in disposable containers while the.

compressible solid wastes are collected and compressed (baled) into drums. The various sources, quantities, and activit. levels are detailed in Table 11.4-1. Maximum volanes may be produced as a result of excessive equipaent leakage, steam generator tube leakage, and so forth. Spent filter gartridges are expected to be changed once every two years.

The principal nuclides shipped from the plantsite include the following:

Iodine-131 Iron-59 Cesi um-134 Manganese-54 Cesi un-136 Manganese-56 Cesium-137 Molybdenum-99 Cobalt-58 Strontium-89 Cobalt-60 Strontium-90 Iron-55 Chromi um-51 Hydrogen-3 JANUARY 31. 1979 11.4-2

.CPSES/FSAR The seismic design classification of tha Fuel building housing the SWMS is discussed in Section 3.2. The seismic design and equipment design codes for the RWWS components and piping are in accordance with ETSB.

Technical position 11-1.

11.4.2 SYSTEM DESCRIPTION

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11.4.2.1 Solidification System Description Refer to ATCOR topical report 132A.

11.4.2.2 Spent Filter Cartridge Assembly Processing A filter transfer cask and other accessory equipnent are used to remove and transport spent filter cartridge assunblies from filter housings to the solidification area. The filter transfer cask is positioned alongside the filter compartment concrete shield plug of the 4 Q320.1 filter to be changed. The shield plug is lifted and placed down beyond the work perimeter. The filter housing bolts are disengaged, and the filter housing head is moved to allow removal of the spent filter cartridge assembly. The filter transfer cask is moved until it is positioned so that the centerline of the cask is aligned with the ctaterline of the spent filter cartridge assembly. The filter transfer cask shield door or b.ase is opened, and the integral hoist is lowered to engage the cartridge assembly. The grappled cartridge assembly is then raised into the shield cavity and the shield door closed to contain any liquids or particulates that may drip during transit. A monorail is used to move the filter transfer cask to the hatchway

.through which the cask is lowered until it is located above a waiting disposable container with shipping shield placed on a flat bed cart.

When centered above the container opening, the contained spent fil cer cartridge assembly is lowered into the disposable container. The filter transfer cask is decontaminated in a manner allowing the decontanination water to enter the container.. The flat bed cart is 11.4-3 AMENDMENT 4 JANUARY 31, 1979

CPSES/FSAR then moved to the solidification area where the container with shipping shield is transferred to the container filling position for solidifica-tion with additional radioactive waste and solidifying agent mixture.

11.4.2.3 Large Solid Waste Materials and Equipment Large waste materials and special equipment that have been neutron activated during reactor operation (e.g., core components) are handled and packaged in a safe manner on a case-by-case basis.

11.4.2.4 Baling Subsystem Description The process flow diagram of this subsystem is shown on Figure 11.4-2, and the physical layout is shown on Figure 1.2-15, 1.2-21 and 1.2-38.

Baling of compressible low-radiation-level solid wastes into druns is accomplished in the following manner.

4 Solid wastes are inserted in an open drun. Subsequently, the drum is Q320.8 placed in the baler, and the shroud door is closed. An operator initiates the compaction process by positioning an up/down switch in the position _ thus energizing the hydraulic punp motor. The hydraulic pressure forces-the ran down into the drun, thereby comfressing the wastes. To retract the ran, the operator positions the switch in the up position. The shroud door is opened, and additional wastes are added to the drun. The cycle is repeated until the drun is full, the lid is installed, and the clamping ring is tightened. Drums are then stored pending shipnent.

The Fuel Building baler's shroud is ducted to the plaat ventilation system to remove dust or particles that may be enitced from the drum during compression of the wastes. The Containment balers are not ducted to the ventilation system; however, each-baler has its own self contained exhaust air filtration system. The air filtration systen AMENDMEh' 4 11.4-4 JANUARY 31, 1979

CPSES/FSAR onsists of a prefilter and a HEPA filter in series. This provision eliminates any potential hazard frou airborne radioactivit.y. In addition, the assembly incorporates a fail-safe suitch that does not permit baler operation with the baler door open.

11.4.2.5 Component Description All components which are located in the Fuel Building are at elevations of 810, 822, and 010 feet. The Containment balers are at elevation 915 ft in each Containment.

Design parameters of the RWSS component. are listed in ATCOR topical report No. 132A. Other associated components of the SUMS are as follous:

1. Co:. tainers The 50-ft3 , mild steel, disposable containers used for solidified 4 wastes are of strong, tight construction, suitable for storage Q320.8 and disposal by buriul. The containers are remotely capped and are equipped with renotely operated quick disconnect fittings on

. top to handle all fill, vent, and instrunentation connections.

The containers are provided with the necessary lifting attnchments, and a 4-in recess surrounds the disconnect fittings to arrest any accidental spills.

The drun, used for dry solid waste, consists of a DOT-17H-55 gallon drum, drum lid, lid gasket, and closing ring. The drum is capped nanually.

2. Shipping Shields The shipping shields are used to protect personnel from radiation exposure during shipment and other operational' handling of the 11.4 -:i AMENEMENT 4 JANUARY 31, 1979

CPSES/FSAR filled containers. The shields have a lead core with inner and outer shells of steel and are designed to accommodate standard 50-ft disposable containers. Lifting devices are penaanently attached to the shields and are capable of supporting 1-1/2 times the weight of the loaded shipping shield. Shields of the 4-in thick size are provided for in-plant use only.

3. Filter Transfer Cask One filter transfer cask is provided to be used as a shielding and carrier vehicle to protect personnel from radiation exposure while transferring spent filter cartridges from the filter housing to the drumming area. Movenent of the filter transfer cask is by a monorail. The cask is provided with a removable drip pan to collect any dripping liquid from the filter cartridges. The cask is designed with a stainless steel interior 4

and flush connections located on the top of the cask to Q320.8 facilitate washdown and decontamination. The grapple assembly that is used to lift the filter cartridge is permanently attached to the inside of the cask. The grapple has a fail-safe feature which locks the filter in place in the event of power failure.

4. Flat-Bed Cart One rail-mounted flat-bed cart is provioed to transport disposable containers with shipping shields between the hatchway

• (for filter cartridges), the drunning, and the loading _ areas.

4 Q320.8 *The cart has three individual drive systems: continuous forward

• and reverse, creep forward and reverse, and manual saergency

• override.

AMENDMENT 4 11.4-6 JANUARY 31, 1979

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'CPSES/fSAR

5. Baler The baler is a commercially available assembly used in conjunction with standard 55-gal drums which receive the low radiation level, solid, compressible wastes. Compaction of the wastes is perfonned af ter an amount of waste sufficient to fill a drua has been accumulated.

11.4.2.6 Other Design Features

1. Process Control Program Refer to ATCOR topical report No.132A.

2. Free Liquid 4 Q320.8 Refer to ATCOR topical report No.132A.

3. Overflow ~of Tanks Refer to ATCOR topical report No.132A.

4. Tanks Using Compressed Gases Compressed gas is not directly used in any SWhS tank. However, the waste blending tank is vented to the plant ventilation systen since bead resin slurry is transported to the waste blending tank from the spent resin storage tanks by means of nitrogen gas pressure. The voluae and flow rate of the gas used for

' transferring one batch is estimated to be 1200 scf at 50 scfm, with two of batches per year. The expected radionuclide concentration of the vent gases will be negligible. The treatment provided (atmospheric cleanup system) for the vent gases _is described in Section 9.4. .

11.4-7 AMENDMENT 4 JANUARY 31, 1979

CPSES/FSAR 11.4.2.7 Packaging, Storage, and Shipmeit

1. Packaging The SWMS product is a burial package which is classified as a special form of packaged hazardous material in accordance with 49 CFR Part 173. A DOT pennit for each containor is not required, since containers are shipped as a group enclosed within a lead shielding or overpack for which a DOT penait is obtained.

The contents in the containers are solid; therefore, there is no danger of radioactive spills caused by dropping of containers.

2. Storage Sufficient storage capacity is provided for forty 50 ft containers and twenty-five 55-gal druns. Adequate shielding is 4 supplied to reduce exposure to personnel outside the drunning Q320.8 station to approximately 10 mren/hr. The locations of the solidification room and the drun storage area within the plant are shown on the general arrangenent drawing, Figure 1.2-38.

Storage time is a variable and depends on shipnent schedules which the operating facility has contracted. Radioactive decay, as a function of the storage interval, is considered to be minimal, and credit for the decay is not taken during shielding cal cul ations.

Prior to renoval of a drun for shipment, drun smear samples are taken to detennine the surface activ.ity. If required, the drum surface is washed; the water is collected in a sunp and later punped to the LWPS. Af ter washing, smear samples are taken again to determine if the desired decontamination has been achieved.

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AMENDMENT 4 11.4-8 JANUARY 31, 1979

cit i/i RR

3. Shi p ient Ra.fwastes are stored in a designated storage area in the Fuel Building as sho,m on Figure 1.2-38. Shipnent of the radwaste originates from the north end of the Fuel Building by either rail or truck. All raduaste shipner.ts are in compliance with the regulatory standards and requirenents_of the IIRC, DCT, and the Texas Regulations for Radiation Control, and are consistent wi_th the methods discussed in Environ.nental Survey of Transportation of Radioactive fiaterials to and from t;uclear Power Plants and with the Draft Environmental Statement Concerning Proposed Rulenaking Action.

11.4.2.8 Instrumentation and Control The instrumentation and controls of the RWSS are designed by the

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4 equipment supplier and are detailed in the ATCOR topical report 132A. Q320.8 11.4.2.9 Safety Evaluation This RUSS and the balers are not safety-related and cannot affect the safe shutdown of the plant or the operation of other systems which are required to safely shut down the plant. Failures of the RUSS that can cause potential problems in daily operation of the RUSS and increase normal operator exposure have been analyzed and are discussed in the ATCOR topical report fio. 132A.

11.4-9 AMENDiiEi;T 4 jai 1UARY 31, 1979