W3P83-2108, Forwards Rev to FSAR Chapter 11,in Response to 830328 Request for Addl Info Re Changes to Waste Mgt Sys.Revs Will Be Included in FSAR Amend 33,scheduled for Aug 1983
| ML20077G189 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/25/1983 |
| From: | Drummond F LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| W3P83-2108, NUDOCS 8308030405 | |
| Download: ML20077G189 (42) | |
Text
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_,0 U I S I A N A / 24a cecAno~oe erneer e ao oox eooe P O W E R & L 1 G H T / New CaLEANS LOUGANA 70174-8000 9 (504]368-2345 MIDDLE SOUTH LALmES SYSTEM July 25, 1983 W3P83-2108 Q-3-A29.11 Director of Nuclear Reactor Regulation Attention: Mr. G. W. Knighton, Chief Licen91rg Branch Number 3 Division of Licensing U.S. Nuclear Regulatcry Commission Washington, D.C. 20555
SUBJECT:
Waterford SES 3 Docket Number 50-382 Waste Management System
Reference:
Letter dated March 28, 1983 from G. W. Knighton to L. V. Maurin
Dear Sir:
The referenced letter requested additional information concerning changes made to the Waterford 3 Waste Management Syctem. Per discussions with the NRC re-viewer, Mr. Jack Hayes, we are hereby providing our response in the form of revisions to FSAR Chapter 11. However, the following information is not appro-priate for inclusion to the FSAR and is therefore being included in this letter:
LP&L has entered into negotiations with two vendors, Chem-Nuclear Systems, Inc. and Hittman Nuclear-Development Corporation, to provide a standby demineralizer system and a portable solidifica-tion system. LP&L's intent is to ensure that the portable solidi-fication system is installed at Waterford 3 at the time of fuel load. Contract negotiations for the two systems are proceeding concurrently. However, it is LP&L's intent at this time to rely on the installed waste concentrators; although provisions for con-necting a standby demineralizer are being made, it is not expected to be needed except under unusual circumstances.
Following selection of the portable solidification system vendor, the NRC will be notified and the PCP submitted for review.
We hope that this information satisfactorily addresses your concerns. The en-closed FSAR revisions, as modified to address any future questions, will be included in FSAR Amendment 33 which is currently scheduled for August 1983.
Very truly yours, f f '
f f M swr m \
F. . Drummond Project Support Manager-Nuclear QQO V ;
FJD/RMF/ssd cc: E. L. Blake, W. M. Stevenson, J. Wilson (NRC), J. Hayes (NRC), L. Constable 8308030405 830725 PDR ADOCK 05000382 J WTG ~
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- Insert A to Page'11.2-2 The installed treatment method for liquid waste is the waste concentrator. It-is not anticipated that standby demineralizers will be kept on-site continously, but that they will be available from a vendor if circumstances require their use.
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F WSES-FSAR-UNIT-3 steam activity). Since the activity will be extremely low, it will be reutinely discharged unprocessed after monitoring. However, if monitoring rcveals significant levels of activity the sump water will be routed to the 4 Wnste Management System.
11.2.1.5 Waste Management System (WMS) and Boron Management System (BMS)
The BMS and the liquid subsystem of the WMS are designed with suf ficient 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, one of the boric acid concentrators can be substituted so that the pro-cessed fluid will experience the same high overall DF prior to being dis-charged. As an additional measure of assurance that liquid wastes can be processed during all plant conditions, piping taps have been installed in g the LWMS process stream to allow use of a standby portable demineralizer system should the need arise /In the case of the WMS, if a filter cartridge must be changed or an ion-exchanger bed be replaced, sufficient tankage is provided to hold the waste so that these operations can be /NsER I performed with no loss of efficiency. The same is true for the BMS with the /)
cdded 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 for high level conditions. The level a'larms 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 and 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 mode while the other 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, cnd 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 27 the water will be reprocessed prior to leaving the building. There fore , the potential release of water by overflowing outside storage tanks would not result in uncontrolled release of radioactive materials. The outside storage tanks have level detection instrumentation which will annunciate under high l
1evel conditions.
Amendment No. 31, (3/83) 11.2-2 f
WSZS- FSAR-U2rI"'-3
. &~ERFORD-3 FSAR 11.2.2.2 Wasta Manarement System na design of :he WMS is prasanted in Figure 11.'2-1.
discharge) are clearly indicated on ther.hrough figure ,
the system (circulating vatar(heavy l syst em interconnec::icas. ne figure indicates all Process data is presented in Tabla 11.2-!0.
identified in Figure 11.2-2 and expectec sourcas Input stres=s int: :he W.S are of vasta influent are listad in Tabla 11.2-4 ,
volumesi and activities peasanted in Taoia 11.2-7 for W.S process equipment.2accatmination factors are 11.2.2.2.1 Miscallaneous Wasi:'a Miscallaneous non-datargent usata is collected in one of two w As wastas are collected, they are processed on a batch basis asta th tanks.
rough an oil separator reduca suspended filter to solids. reduca suspended oil unen required ando a filter t concantrator to esmove dissolved solids sad radioactivity.Me Concentrated wast bottes fra Syscam forthe weste concancrator solidification and disposal. are pumped to the Solid Wast a Management A mixed bed (H-CH form) ion ex-reduce any volatila species unich carry over .
in the Se con =
er distil dansata is collected in one of two unsta condensata tanks for analysia prior to ralsase to the circulating water dischargesampling and . Discharge activity is monitored for radioactivity, as described in Section ..
113 All' potential" bypass routes in the WMS are indicated i Because of the redundancy of equipment; n Figure 11.2-2.
ment will need to be bypassed very frequently. it is not expected that equip-is bypassed shows that for any reason, and sampling of the waste condIf process equipmen ensate tank enn be recycled back th* rough a filter, concentrator, as desired, and collected in the second tank. nger or
~he W.S has sufficient shutdown, and refueling.capacity to accept liquid wasta during startup, 11.2.2. 2.2 Laundry Wasta Licuid detargent vaste from the '.auncr r.,
l laundre su:sp, cent m inated
- snowers, vasta i anc c=ntainated sinks are c= llected in two laundrv
- anks. ~he filtar directlys ac:=aily :s sapled the to assure '.cv activity and then pumoed :::rcugn a
=enitored as described circulating water disenarge. Lisenarge activity is in Section 11.5. Should the need arise , laundrr anc decent mination.vastes can be t
neugn tais is act reccamanded processec practice. using the vaste :=ncentracer, al-
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'4SES-FSAR-UNIT- 3 11.4 SOLID WASTE MANAGEMENT SYSTEM High activity radioactive wastes and low specific activity (LSA) solid radioactive wastes are processed, packaged and stored for subsequent shipment and offsite 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 SRMS are as follows:
a) Provide for receipt and interim storage of concentrates from waste concentrator package and spent resins. The SWMS provides for transferring concentrates from boric acid concentrator packages to SWMS.
b) Provide for holdup capacity for normally radioactive spent resin to allow decay of short-lived radionuclides.
c) Provide for receipt and water content adjustment (dewataring and/or dilution) 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 31 remote handling tools will be used during filter transfer.
/' e) Provide means to compact LSA solid waste such as contaminated 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 offsite 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 49CFR173.393 (1972).
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11.4.2 SWMS DESCRIPTION The SWMS is shown schematically on 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 A
solidified waste product which will be disposed of at a burial site.
comparison of the system requirements versus capabilities is provided in Table 11.4-2.
Amendment No. 31, (3/83) 11.4-1
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WSES-FSAR-UNIT-3 The SWMS will provide interim storage of radwaste and process it in a batch mannsr. The system will put filter cartridges into disposable cask liners.
W3cta evaporator concentrates will be mixed with a solidifying agent in dicpocabla cask liners. The casks and liners will be transferred to a storage cron before chipping.
Beforo starting solidification procedures, the radioactive level and chemical cc=p cition of the wastes will be determined.
/MSERT~L- .
11.4.3 INPLANT SOLIDIFICATION SYSTEM DESCRIPTION Tha 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 solidifying agents. Concentrates are pumped by a positive displacement pump et a controlled rate to the process pump mixer where the wastes are mixed with Portisnd cement. The process pump mixer assures a uniform mixture of waste and Portland cement. Sodium silicate is added downstream of the process pump cixar. Uniformity of mixing is assured by the fluidity of the constituents.
Tha d watering tank, which in used for waste processing but not for waste storege, will be used to provide flexibility and control of the wastes 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 dsairable mixture of wastes in the dewatering tank, the operator can set the tocc1 amount and rate of feed by adjusting the flow ratio of the metering pump 31 to tha 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 centrolled at 140F with adequate heating elements such that the concentrates
, (21,000 ppe boron by weight) do not deposit in the system. Temperature and !
leval of the dewetering tank and concentrate storage tank concentrates 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,
, Tha antire system will be vented through a bag filter located on top of the l 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 ease in i handling, the cement in the storage hopper will be continuously fluidized by a flow aerator located in the bottom of the storage bin.
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l A separate control panel for the cement handling subsystem is provided. This
- pansi 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 undar the fill port or in the event of component salfunction. The fill port A
l 1s equipped with a vented splash guard that seals the liner during filling.
l mixer bypass is provided that permits direct discharge of wastes into the l
11.4-2 Amendment No. 31, (3/83)
Insert 1 - Pg. 11.4-1
- 1. The inplant SWMS is housed in the Reactor Auxiliary Building which meets the seismic criteria of Regulatory Guide 1.143.
- j. Components of the inplant SWMS are classified "NNS" at Waterford 3. (RG 1.26-Quality Group "D"). Further discussion of the conformance of the SWMS with RG 1.143 can be found in the response to NRC question 321.8.
Insert 2 - Pg. 11.4-2 The buildings, systems and facilities described in this section are designed and constructed such that handling waste containers and operating equipment of the SWMS can be done with the least possible personnel exposure in accordance with the ALARA criteria of RG 8.8 and 8.10. In addition, plant procedures specify particular practices for waste handling and monitoring for the various systems and storage areas that also adhere to the ALARA requirements of RG 8.8 and 8.10.
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. ,, WSES-FSAR-UNIT-3 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 liner.
At the completion of each fill cycle, there are provisions for thoroughly flushing with water all portions of the system 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 requirements of 10CFR20 and 10CFR50. These controls minimize the chances of releasing radioactive materials.
Compressad air is required for the cement silo to fluidize the cement and the spent resin storage tank to mix the spent resin. 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 on Figure 1.2-9 the liner is capped and 31
' decontaminated if necessary by remote flexible hoses. The waste from the T. 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. .
11.4.3.2 System Operation and Controls Functional automatic controls are provided by which the operator activates controls sequentially. Interlocks will allov a control to be activated only when the next previous control has been satisfied. A manual mode of operation is provided so that interlocks are bypassed and individual components are operated from the control panel.
The concentrate storage tank and the dewatering tank are provided with level l indicators and alarms 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 of their respective cubicles. Curbing is provided,to 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.
eu kam;ndment No. 31, (3/o_
WSES-FSAR-UNIT-3 11.4.4 SOLIDIFICATION PROGRAM ALTERNATIVES Two systems have been considered for handling solid wastes from plant o perations:
a) The installed plant solidification system, b) Portable solidification systems supplied by contractors. ,
Evaluations of these alternatives covering current regulations on shipping 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 Cartain 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 to address these concerns prior to initial plant startup. Therefore these systems will not be used at this time. The status and ultimate use of this system will be addressed on a backfit basis. Should evaluations at that time indicate the feasibility of routine usage of the installed system, these etacerns shall be resolved prior to use of the system.
11.4.4.2- Portable Solidification System 31 Watsrford 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 w stherproof structure with curbing and a sump system which discharges to the
' LWMS. An overhead bridge ersne is provided for lif ting 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 Figure 11.4-1).
wseer 3 i 11.4.5 PORTABLE SOLIDIFICATION FACILITY i
The function of the Portable Solidification Facility (PSF) is to provide shelter for the contractor's portable solidification equipment and to supply In the necessary service requirements and waste delivery for this system.
addition to service provided to this facility (air, water, electric power), a 10 ton overhead crane is provided to handle the portable solidification squipment.
The bridge crane has full travel over the interior area of the PSF.
Tha operation of waste solidification (and/or resin dewatering) will be performed in a shielded waste liner mounted on a trailer. This trailer shall bs 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 from inside the RAB out to the PSF. Support equipment for the 4
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)
Amendment No. 31, (3/83) 11.4-4
Insert 3 Insert to Pg. 11.4-4 The portable solidification systems represent state-of-the-art technology in equipment design. These systems employ Portland Cement as the solidifying agent with additives specified by the respective vendor process control pro-gram.
Major ccmponents include: cement silo, fillhead assembly, pump and valve skid (s),
control panel and liner shielding cask. When a cask is required, it will stay on a flat bed trailer during the solidification process. Connections between the a in-plant system and portable system equipment are by flexible hoses with a metal shield. The waste concentrates storage and handling portion of the in-plant SWMS is utilized to supply waste feed to the portable solidification system. These parts of the inplant SWMS are situated with appropriate shielding, remote sam-pling, separation of components and accessibility to reduce leakage and facili-tate maintenance and operation in accordance with RG 1.143 and BTP ETSB 11-3.
The operation of a portable system is relatively simple. A Process Control Pro-gram (PCP) is established prior to any actual operation. This PCP includes testing of the operability of the system as well as the compatability of waste and cement. Samples of waste are taken to determine the waste to cement ratio to insure solidification process.
Other items addressed in the PCP include provisions to monitor for agressive chemical waste and their neutralization to prevent degradation of the waste con-tainer and inventory records of waste types, contents etc. and other pertinent data related to the handling and storage of solid waste.
After sampling and analysis, an empty liner is put into the shielding cask.
Radwastewillbesolidigiedprimarilyinlargevolumelinersranginginsize from 50 ft.3 to 300 ft. . There may be special cases where smaller liners or 55 gallon drums will be used to solidify waste.
A predetermined amount of waste concentrate or spent resin is then pumped into the liner through the fillhead assembly. If dewatering is required, it is done at the same time as the liner is being filled. Cement is added to the liner after waste fill is completed. During the cement addition, the fillhead assem-bly drives a disposable mixing device inside the liner to mix the cement and waste. At the end'of the mixing step a homogencus mixture is achieved inside the liner. The liner is then capped and set aside until the cement is cured.
The liner can then be put into interim on-site storage facility or shipped off-site to a burial ground, as desired. .
The basic equipment set up in the PSF will be used to process spent resins into liners and associated preparations for storage and shipment to a burial facility including the dewatering operation to meet the Free Standing Water (FSW) criteria of the intended burial facility.
If the burial site does not accept dewatered resins or the FSW criteria cannot be met, Waterford III will have the ability to solidify resins utilizing the Portable Solidification System.
l l
WSES-FSAR-UNIT-3 The PSF is a pre-engineered, prefabricated sheet metal building with interior dimensions of wide by 55' long with a 30' high eave. The building is located on the oncrete truck platform on the west side of the RAB. The area selected for el ction of the PSF is between the RAB main access doors and the solidificationi area doors at elevation +21 ft. (See Figure 11.4-1)
Wof slab on the west side of the RAB is only 40' wide, so an The existing concre additional 15' by section of slab is added to support the building. A combined foundation and curbing is 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 Regulatory Guide 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 i 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 31
(. 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.
b) Values Of Waste Given By The NRC (See Question 321.22)
The 391 square feet Liner Storage Area in addition to the interim 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 STORAGE A permanent onsite low-level radioactive storage facility is being constructed. However this facility will not be available during the early phases of operation. To provide for temporary storage of solid wastes prior 11.4-5 Amendment No. 31, (3/83)
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q to shipment during the interim period, a designated storage area will be
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provided on the east side of the plant adjacent to the RAB and within the security f ence. A concrete pad with f encing and a locked gate will be '.1 '
constructed in an area accessible to trucks and mobile heavy lif ting equipment.
See Figure 11.4-7 for the location and dimension. -
Solidified concentrates, spent filter cartridges and waste resins will be placed in disposable liners and stored in this area prior co shipment. Only seM4 waste ready f or shipment will be stored in this interim solid waste storage area. 7 Shielding will be provided through the use of "onsite %:> rage containers".
These are reinforced concrete containers with removable Ifds sized to 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. 5 . i s i e a; we-ende-ee ; m.+ is a ad a ; . a ., a c. ?-f e m c.J L _ ..c- .. el
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This interim solid waste storage area will contain stifficlent provisions to store and shield up to 1,200 cabic f t of additional solid was*:e beyond that j' provided within the plant. > Should circumstances dictate, thib area could be '
expanded and additional onsite storage containers procured in a short period
- of time to provide additional atosage capacity. ~
~ 31" 11.4.8 INTERIM DRY (DMPACTED WASTE FACILITY In order to provide additional capacity f or the projected peak volumes of dry compacted waste, Wate rf ord-3 is installing, a metal building f or 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 security f ence between the existing water treatment building and chiller building. The location of the interim f acility is shown on Figure 11.4-3.
A permanent onsite low level radioactive waste storage f acility is being constructed which will include proSisions f or the waste compactor and storage of dry waste, however this f acility will not be available during the early phases of operation. The interim dry compacted waste f acility will support plant operations until that time. These f acilities comply with the intent of NUREG-0787, Wate rf ord-3 Saf ety Evaluation Report , Item 11.2.3.3. ~
11.4.8.1 Interim Dry Compacted Waste Tacility Description The interim metal building meets the applicable requirements of Regulatory Guide 1.14 3 NUREG-0800 SRP 11.4, BTP-ESTB 11-3, Appendix ll.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 airborne radioactive contamination. The compactor room is constructed with smooth, continuous internal surf aces to f acilitate decontamination should it ever be required. The entire building is constructed on a reinf orced concrete slab with curbing such that water is kept from antering the building.
11.4-6 Amendment No. 31, (3/83)
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3% Plant proceduras will contcin. provisions for; periodic direct radiation and sur-L face contamination monitoring to be perfortred on waste stored in this area' to L. 2 ' insure'that the levels are below the limits'of 10 CFR 20.202, 10 CFR 20.205 and
" 49 CFR-173.397.
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! . Insert 5 Pg. 11.4-6 s The OSC design incorporates a.high strength liner for additional leakage pro-l'" tection and provisions for ssmpling and collecting any liquid found in the .0SC cavity. Plantprohdiresrequiresamplingandanalysisofcnyresidualwater l 'i found in on-site ytbrage containers (OSC);drast prior to shipnent and prior to R w $ dispositioning the water. The on-site.st9 rage' containers have a tube extending
\ to the botta of the inner cavity of the30SC's which allows sampling and removing
./ any water found with a portable pump.
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. s i All shipping containers of dewatered resin, as well as solidified waste exceeding radiation limits for unshielded shipments will be placed in OSC's designed for outside field storage. %
. j ;The interim solid Radwaste Storage area slab will have sufficient area to. hold the maximum expected number of containers withott stacking containers. Addi-
! tionally, spacing will be such that at least a two (2) foot clearance will be maintained betvaen' containers to allow for inspection. Plant procedures will 1 contain requirements to not only survey for external radiation and contamination n but also to periodically inspect waste containers to ensure that no container
- deterioration is occuring during temporary storage.
) .. On site storage dontainers have tie down brackets. The interim Solid Radwaste Storage area; slab wf;11 have tie down anchors placed at strategic locations to allow securing any maete, container needing tie down.' As a precaution, against approaching severe weather such as a hurricand', waste containers in use will
!j either be' tied down on the slab or r.aved to-protected storage inside the RAB.
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WSES-FSAR-UNIT-3 iNSB AT 6 The building is 55' by 40' and has suf ficient storage capacity to house 76 6' x 4' x 4' metal boxes of compacted waste. The boxe s a re handle d wi t h a forklift. (See Figure 11.4-4) .
Space has also been provided in the f acility to temporarily store contaminated laund ry. This area is 8' x 22' and walled separately from the waste compaction activities.
g7 7 11.4.8.2 Waste Compactor Description The box compactor utilizes hydraulic pressure to compact low activ,ity solid waste such as contaminated clothing , rags, pape r, 1_ _ _ _ _ _ _, _ and
miscellaneous low-level contaminated material generated by maintenance activities.
The compressible gaste is placed inside a 4' x 4' x 6' metal box and compressed by a vertically moving piston. The hydraulic press contaias its own hood, ventilation f ans and high ef ficiency filter. The displaced air is vented through high ef ficiency filters. Af ter a predetermined waste volume is attained, the container is sealed and placed in storage. The hydraulic press and auxiliaries are skid mounted with start stop switches mounted locally and 31 independently of other solid waste system controls.
11.4.9 RADIGACTIVE FILTER HANDLING Filter c.srtridges may be replaced using a bottom loading filter transf er cask when radiation levels dictate remote handling. Af ter remotely removing bolts on the head of the filter, the filter cartridge *is lif ted 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 necessary and water is supplied to f acilitate decontamination of filter areas. The filter transf er cask and disposable filter cartridge are moved to the solidification area by the filter transfer vehicle. This arrangement minimizes radiation exposure to perconnel and allows the movement of the cask with loaded filters f rom the filter housings to the solidification area.
At the solidification area, the bottom of the cask is removed, an overhead crane is used to lif t the transfer cask containing the filter cartridge into position over a shipping liner and the filter is lowered into the liner. The liner, af ter being sealed, is positioned in a shipping cask or onsite storage container f or shielding and storage prior to shipment.
The filter handling process will be completely tested in all modes of operation to verify preper operation by the startup testing group prior to plant operations, low activity filtcrs, activated charcoal and HEPA filters from plant ventilation -.
systems, 11,4-7 Amendment No. 31, (3/83)
Insert 6 Pg. 11.4-7 The use of curbing to separate the areas within the interim dry compacted waste building was evaluated during the design and determined to be unneces-sary for the following reasona:
a.) The building was designed with special attention given to ensuring that hard driving rain would not penetrate to the interior of the structure.
b.) The building slab has special-curbing and is raised above grade to prevent ground water from flowing into the dry storage area.
c.) The metal box containers containing dry compacted waste stored in this building have their own individual pallets which raise the bottom of the containers four (4) inches off the floor.
d.) The box containers have solid seams and are water tight up to the lid which is four (4) feet off the floor.
in summary, water intrusion should not occur due to the design features of the building.
Insert 7 - Pg. 11.4-7 Contaminated laundry is planned to be handled by one or both of the following methods:
a.) If laundry is processed onsite it will be temporarily stored in the Laundry storage area of the compactor building, when required, in cabinets or compaction boxes and handled in wheeled carts. All of these storage and handling methods keep the contaminated laundry several inches off the floor away from any possible contact with water if it should somehow occur on the floor.
- b.) If an off site laundry service is to be utilized, the laundry will be accumulated in the steel boxes until full, then sealed for l
- shipment. These steel laundry boxes are constructed with six (6) l inch wheels and~ water tight seams up to the lid which would keep the contents dry.
l I Insert 8 Pg. 11.4-7 l
l The compaction box containers are metal however some of the contents are com-bustible. The bulk dry waste material is collected in a large sealed transfer container as it is generated in the RAB. As the waste is removed from the transfer container it is inspected, surveyed for radiation and sorted prior to feeding into the box compactor. Plant procedures provide guidelines for monitoring the dry waste for materials that could cause chemical reactions or spontaneous combustion.
L
WSES-FSAR-UNIT-3
. n 11.4.10 SPENT RESIN TRANSFER 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 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 to the solidification system f) System flushing
. 31 11.4.10.1 System Description t The SRTS consists of the following components: One spent resin i tank, one spent resin transfer pump, two spent resin strainers, and associated y, 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 eluiced to the spent resin tank. Af ter the sluicing operation is complete, excess water is removed from the tank using the tank dewatering 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.
l When a predetermined amount of resin has been collected in the spent resin tank, the resin is pumped to the solidification system by the scent resin transfer pump. This transfer is accomplished by using a bleee 1.ne to the solidification syssem 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 dewstering connection on the spent resin tank. The majority of the 11.4-8 Amendment No. 31, (3/83)
- ~ _ _ _
WSES-FSAR-UNIT-3 residual resin is flushed back to the spent resin tank with the remainder directed to the solidification system.
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 Transfer Pump quantity: one c) Piping and Valves d) Strainers - quantity: two e) Resin Sampling Valve quantity: one f) Sight Glass quantity: one ,
General Description of Each Major Component:
a) Spent Resin Tank i 31 Th.e spent resin tank, fabricated of Type 304 stainless steel, is ;
~ located in the southwest quadrant of the Reactor Auxiliary Building on ;
EL. -35.00 ft as1. The tank is located in a shielded cubicle. The spent resin storage tank has a capacity of 3,200 gallons (427 cu f t). :
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 Reactor Auxiliary l Building just south of the spent resin tank room on EL. -35.00 ft as1. !
The pump has a capacity of 230 gpm and 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 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 l weight polyethylene seats. Valves with air operators are provided with .
limit switches and fail safe provisions where required.
I 1
IL4 9 Amendment No. 31, (3/83)
WSES-FSAR-UNIT-3 d) Strainers Two stainless steel 'Y" type resin strainers sized at 80 mesh prevent resin fines from entering the waste system and the sump system during system drainage and dewatering operations, respectively. The strainer at the dewatering line can be backwashed.
e) kesin Sam'pling Valve The valve is an Isolok liquid / slurry sampler which can extract a 10 cc 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.
, b) Provide for receiving and adjusting water content in the spent resin 31 tank. , ,
c) Provide a means t'o transport resins to the solidification system using a recirculation loop concept.
i 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.
e) The SRTS is located entirely in the seismic Category I Reactor 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.
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 Level alarms alert operators when the interface level of the settled resins.
tanks are nearly full or empty. Appropriate control devices shut off the rasin 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.
11.4-10 Amendment No. 31, (3/83)
. WSES-FSAR-UNIT-3
, The SRTS sizing is based on the following:
Recirculation loop piping is a minimum of three in. 1.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 during pumping.
- Resin slurry feed 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 occurrence. The design and fabrication codes, seismic category, and classification meet the requirements of Regulatory Guide 1.26 (Rev 1) 1.29 (Rev 1), and 1.143 (Rev 1) .
To reduce radioactive releases to the building atmosphere, the following design features have been incorporated into the system design:
a) Venting of the spent resin tank is to the vent gas collection header, 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. 31
\ 11.4.10.4 Instrumentation and Control The control panel for monitoring and controlling the SRTS is located at the solid radwaste area of EL +21.00 ft mal. 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. l The SRTS utilizes a programmable controller (PC) to accomplish the functions ,
required in the different modes of operation. The PC is located in the i control panel located at EL. +21.00 ft in the RAB. A local instrument rack l containing system transmitters is located at EL. -35.00 ft 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. l Spent resin level - A stainless steel float with a transmitter which sends a signal to the control panel is used to measure resin / water interface. The programmable controller compares this signal to the water level. An alarm will be actuated should the water / resin ratio exceed a predetermined limit or i the water level drops below resin level. The instrument has a hand crank to lift the float, if desired, and a local level indicator dial. The stainless steel float is custom-made with a specific gravity of 1.2.
11.4-11 Amendment No. 31, (3/83)
USES-FSAn ""IT-3 s .::e _: e. - ::.e wa;:r actel is ten:turec a;. s 1:terentia pressure 1.s_;.;;r: A transmitter -unds a signal to thu contr:1 panel, which will rec;s;c ;ae :a ny. at algn-nign tank level or trip the pump at low-low tank level.
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 (cavitation).
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.
aP across dewatering strainer - Righ 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. Communication 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 ler.d-shielded shipping casks. The lead shielded shipping casks meet the 31 requirements of specification 55 of 49CFR178.250 (1972).
Solid wastes contained in disposable steel lincrs meet all the requirements 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 E overpa,ck will be rented f rom a licensed radioactive waste disposal company. In addition, all packaged radwaste prepared for shipment will meet the criteria of 10CFR71.
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.
IN.WRT 0 cran; t; lic - "
- .lu ka .. yre.id;d t; c:aur; prop;r h;; hup cf :ncrail :
- o prev ropping a container. In the unlikely event of container e ure, o e solid forr a o liquid spi.1 would occur since the material is handled
.l.4.12 RADI0 ACTIVE MAT HIPPING all wastes will be shipped in dance wit FR requirements. The be monitored and decont ted if required for containers and vehicl waste from offsite shipme
- he shipment of prepackaged solid radioac to
'he p13 94- ite to burial locations will be contracted 4- =""^*A' ara to firms lice "4*h ann 14rokla nnT *=3"1o*4n
. L__ryrr* r dir e c;i~c r e
- e ** '1 -
Amendment No. 31, (3/83) 11.4-12
Insert 9 to Pg. 11.2-12 11.4.11.1 WASTE CONTAINER FAILURE In the unlikely event of waste container failure after final packaging during storage or prior to shipment, plant procedures will be developed to provide instruction on handling, repackaging and/or reprocessing of the waste.
Typical handling of a failure would be as follrws. The liner or drum would be temporarily sealed and if necessary moved to an area affording maximum protec-tion against spillage, spread of contamination and minimizing personnel radia-tion exposure. If the waste material is dewatered resin, the contents can be transferred to a new container, if required. Several options are available to resolve thc container problem including repairing the waste container, placing the damaged waste container and contents into a larger liner or repackaging the waste in a different container. Loose concrete solids can be recast by the addition of fresh cement mixtures.
In case of a unique failure not anticipated in plant procedures, the failed con-tainer would be handled on a case by case basis; Waterford Engineering and
~ Technical personnel would evaluate the situation and determine the best course of action-based on the specific conditions. In no case would the method of resolution fail to meet shipping and burial criteria.
9 F
i I
i I
1 11.4.12 RADI0 ACTIVE MATERIAL SHIPPING All wastes will be shipped in accordance with 49 CFR requirements.
Specific burial site criteria will also be met for packaged waste shipmentincludingtheFreeStandingWa)$er(FSW)limitsforthe intended burial site. The containers and vehicles will be monitored and decontaminated if required prior to off site shipment. The shipment of pre-packaged solid rzdioactive waste from the plant site to burial locacians will be contracted to firms licensed to transport radioactive materials in accordance with applicable DOT regulations.
i I
l
WSES-FSAR-UNIT-3 TABLE 11.4-1 I SOLID WASTE MANAGE *NT SYSTgM (DNPONENT SINtMARY DATA Normal Design Operating Normal l
. Design Pressure Design Pressure Operating Tanks Quantity Code Capacity psia Temp. F pela Temp. F Material p >
Spent Resin 1 ASE Section 3200 gal -
200 #)*TA60S 100 SA 240 Tank Vill Div. 1 Type 304 (1973)
Dewatering Tank 1 AS W Section 100 f t3 Ata 150 Ata 14 0 ASTM A-240 Vill Div. 1 (1973)
Concentrate 1 ASE Section 3000 gal Ata 150 Ata 140 ASTM A-240 Storage Tank Vill Div. 1 (1973)
Cement Silo 1 None 500 ft3 ' At e 14 0 Ata 0-120 ASTM A-36 f Sodium Silicate 1 None 200 ft3 Ata 140 Atm 0-120 ASTM A-16 0
Tank s-l-.
u Design Design Motor Pressure Design Flow Mater- Seal Motor Voltage /
Pumps tJuantity Standards g poia Tamp. F gym tal Type leP I"ha s e/lla Concentrate Storage 1 Manuf acturer's Progressing 100 180 7.5 SS 316 Mech. 2 460/3/60 Tank Metering Pump Standard Cavity Dewatering Tank 1 Ma nu f ac ture r's Progressing 100 180 7.5 SS 316 Mech. 2 460/3/60 Metering Pump S t anda rd Cavity i
Process Mixing 1 Manufacturer's Frogre ssing 100 180 10 SS 316 Mech. 2 460/3/60 Pump Standard Cavity Sodium Silicate Pump 1 Manuf acturer's Progre ssing 100 180 0.75 Cl-Body Mech. 1 460/3/60 Standard Cavity Suna N-Stator 8
it I
a E
a 3
3 e
4
n i .
WSES-FSAR-UNIT-3 TABLE 11.4-2 SOLID WASTC MANAGEENT PROCESS DATA System Requirements Solidification System Capabilities Output of Process Systgas Output Fractiva of Solidified Flow Ft /Yr Process Remar6 s Rate Capacity Used Type of Waste te Wag Ft /Yr gym 31 V. slues Given by NRC (Question 321.22)
- 2/3 of System Design 5 88 Flow Rate (using 7.5 Spent Resins M gpm pump)
Solidified conc. 13.000 Total ,200- 17,9 g[ 5* 49,439 M Dry Waste 10,000 *e 23,520 M **Basedonjilling g o one 96 f t dry waste box per day and 24 5 -
." work days per yea r.
i E 3 liners plus 6-195 f 3t liners stored in the interim solid
- Available shielded storage area = 391 ft 2 go, 9_gg5 gg waste storage area.
- Number of 96 ft3 boxes /yr.
- NRC value of blowdown system resin volume supplemented by resin volumes listed on Table 11.4-4 k
i!.
2 a
.?
3 0
f WSES-FSAR-UNIT-3 /
TABLE 11.4-3 SOLID WAS~E MANAGE 8ENT STORACE CAPACITY .
Type of Waste Ft3/ Year Number of 195 Ft3 Libers /Yr Number of Liner
- Number of Spaces Allocated Months Storage For Storage 31 Ntc VOLUBES (see Table 11.4-2) .gg 3 y Spent Resin M / 1 /
Concentrates 13.300 68 14 2.5 Dry Waste 10,000 105** 76 8.7
- 3 Available shielded storage area = 391 2ft for 9-195 f t3 liners plus 6-195 ft liners stored in the interim solid waste storage area.
g ** Number of 96 it 3bones /yr.
C I
a a
l ,
5
WSES-FSAR-UNIT-3 TABLE 11.4-4 QUANTITIES OF INPUT DURING NORMAL OPERATIONS INCLUDING ANTICIPATED OPERATIONAL OCCURRENCES TO SOLID WASTE MANAGEMENT SYSTEM Type of Waste Form Ouantity (cu. ft./yr)
Spent Resins CVCS Dewatered 108 Boren Management System Dewatered 72 Fuel Pool Syste:2 Dewatered 72 Waste Management System Dewatered 36 Blowdown Systea Dewatered 300 Concentrator Bottoms Baron Recycle System and Liquid Waste Management System 21,000 ppm boron 7030 8 '
Filters Spent Filter Cartridges 12 Cartridges 24,2 011 Separator Filter Cartridges 10 Cartridges 10 Compressible Solids Plastic, Rags, 40,000 Paper, etc.
I i
t
O s
- "p WSES-FSAR-UNIT-3 TABLE,,11.4-5 QUANTITIES OF OUTPUT DURING NORMAL OPERATIONS UTCLUDING ANTICIPATED OPERATIONAL OCCURRENCES FROM SOLID WASTE MANAGEMENT SYSTEM Type of Waste Form Quantity (cu. ft./vr)
Spent Resins Dewatered 588 (2)
Concentrator Bottoms Solidified 13,000 (1) (2)
Filters Dry, Dewatered 34.2 Compressible Solids Compressed in 10,000 (2) boxes (Compaction Factor =4)
(1) Based on a solidified mixture of Concentrate and Cement in the ratio of 1.85:1 (2) Based on semi annual operating reports from nuclear plants through 1979 (NRC Question 321.22)
- -- . . _ . .=. _ _ . -.- _ - __-. -- . -_ . ~ . _ . -__ _.- - _ - - .
if5ES-FSAR-UNIT-3 TABLE 11.4 . L ,
ANNUAL ACTIVITIES (CURIES / YEAR) 0F L'ASTE CONCENTIATOR BOTTOMS TO THE SOLID WASTE MANAGEMENT SYSTEM DURING NORMAL OPERATIONS INCLUDING ANTICIPATED OPERATIONAL OCCURRENCES Noelide Activity Nuclide Activity I-133 2.5 (+1)
Br-84 3.5 (-3)* I-134 1.1 (-1) th-88 1.5 (-1) Cs-134 4.9 (0 )
Sr-89 7.1 (-2) I-135 3.8 (0 )
Sr-90 2.1 (-3) Ca-136 2.3 (0 )
Y-90 2.3 (-3) Ca-137 3.1 (0 )
Y-91 4.1 (0 ) Ba-140 4.1 (-2)
Y-91m 8.3 (-4) La-140 1.6 (-2)
Sr-91 , 1.9 (-2) Pr-143 9.4 (-3 )
Mo-99 6.0 (+1) Ce-144 6.8 (-3)
Ru-103 9.1 (-3) Zr-95 1.2 (-2) 2.1 (-3)
Ru-106 Mn-54 6.6 (-2)
. Ta-129 4.8 (-3) Cr-51 3.9 (-2)
I-131 4.9 (+1) Ca-58 3.4 (-1)
I-132 6.2 (-1) Co-60 4.3 (-2)
Te-132 3.8 (0) Fe-59 2.1 (-2) i l
t i *() Denotes power of 10 o
l 1
l l
,-,--3 , --- ,y., . . e w--,,._,-_,_w- . , , . - _ _ , , , _ - - _ _ _ _ _ . _ _ _ - _ , , . , , -
-,_7. _ _- , - - _ . - - , . _ _ _ , . , ,e. .---_,, .... ,, - - , - -- - ,__w,w--% ,
-m W5ES-FSAR-UNIT-3 TABLE 11 4-7 ANNUAL ACTIVITIES (CURIES / YEAR) OF SPENT RESIN INPUT TO THE SPENT RESIN TANK DURINC NORMAL OPERATIONS INCLUDING AhTICIPATED OPERATIONAL OCCURRENCES **
Nuclide Activity Nuclide Activity Br-84 1.9 (-2)* I-133 1.5 (+2)
Rb-88 4.6 (-1) I-134 5.6 (-1)
Sr-89 8.7 (0 ) cs-134 1.4 (+3) .
Sr-90 1.0 (0 ) I-135 2.0 (+1)
Y-90 2.1 (-2) Cs-136 5.0 (+1)
T-91 .
5.7 (-2) cc-137 1.1 (+3)
Y-91e 4.0~(-3) Be-140 1.4 (0 )
. Sr-91 9.4 ( 2) La-140 1.1 (-1)
Mo-99 5.7 (+2) Pr-143 3.3 (-1)
Ru-103 8.9 (-1) '
ce-144 2.4 (0 )
Ru-106 7.8 (-1) Zr-95 1.9 (0 )
Te-129 2.5 (-2) Ma-54 $
2.4 (0 )
I-131 1.1 (+3) cr-51 .
2.8 (0 )
I-132 3.3 (+0) co-58 5.6 (+1)
Te-132 4.3 (+1) co-60 2.0 (+1)
Fe-59 2.3 (0 )
- () Denotes power of 10
- includes purification, deborating, preconcentrator, boric acid condensate, fuel pool purification, waste condensate and steam gen-erster blowdown ion exchangers.
~
WSES-FSAR-UNIT-3 TABLE 11.4-8 ANNUAL ACTIVITIES (CURIES / YEAR) OF SPENT TILTER CAETRIDGES INPUT TO THE SOLID WASTE MANAGEMENT SYSTEM DURING NORMAL OP"EATIONS INCLCDING ANTICIPATED OPERATIONAL OCCURRENCES Nuclide Activity Nuclide Activity H-3 ** I-133 **
Br-84 ** I-134 **
Rb-88 ** Cs-134 **
Sr-89 ** I-135 **-
Sr-90 ** Cs-136 **.
Y-91 ** Ba-140 **
Y-91m .
- La-140 **
Sr-91 ** -
Pr-143 ** -
Mo-99 ,
- Ce-144 **
Ru-103 ** Zr-95 4.0 (0)*
. Ru-106 m Mn-54 2.9 (+1)
Te-129 ** Cr-51 8.8 (+1)
I-131 ** Co-58 1.2 (+3)
Te-132 ** Co-60 2.0 (+2)
Fe-59 6.0 (+1)
- ( ) Denotes power of 10
- Negligible compared with other nuclides activities listed in this table.
- Includes purification filter, pre-concentrator filter, fuel pool pur- -
ification filter, waste filter, laundry filter, and oil separator filter.
g .J
v USES~-FSAR-UNIT-3 TABLF.11.4-9 BASIS FOR ACTIVITIES PROVIDED IN TABLES 11.4-6 THROUCH 11.4-8 a) General
~
- 1) Activities are based on Reactc7 Coolant System activities provided in Table 11.1-3.
~
- 2) Filters and ica exchangers are assumed to be on the process line 292 days (plant capacity factor of .8) unless otherwise '
noted. *
- 3) The vaste concentrator hgs a bottoms to distillate decontami-nation factor (DF) of 10 and a ecscentration factor (CF) of 20.
- 4) Each ion exchanger res~in bed contains 36 cu. ft. of resin.
- 5) Ion exchanger DF's used for buildup on resins and as upstres=
decontamination factors.
Pool Purifi- Deborating cation, Wasta and Boric Purifi- Condensate Acid Pre-Con cation and Lithium Condensate centrator '
Nuclide I-I I-I I-I , I-I Cs, Eb 2 10 1 100 I 10 10 10 -
10 Other Anions 10 10 10 10 Other Cations 10 10 1 10 Crud 10 10 10 10 Noble gases, tritium 1 1 1 1
- 6) Filter DF's are 10 for crud and unity for all other nuclides.
- 7) Letdown is assumed to be 40 gym.
- 8) Waste to the Baron Management System includes the following:
k'SES-FSAR-UNIT-3 TABLE 11.4-9 (Cont'd)
Fraction cf Source Volume RCS activity
{-
from CVCS 734,000 gpy 1. 0 Reactor Drain Tank 200 spd 1.0 Equipment Drain Tank 50 gpd 0.1 b) Was*te Concentrator Bottoms
- 1) The vaste which ultimately reaches the vaste concentrator bottoms is based on an average of 1375 spd with an activity of 0.08 times that of the Reactor Coolant Systaa (RCS).
- 2) Credit for decay is takta for the time required to fill one 4000 gallon vasta tank.
~
- 3) An upstrema decontamination factor (DF) of 10 is used for the ~
vasta ' filter for crud. No DF is taken f or any other nuclides.
- 4) No credit is taken for any decay once the bottons leave the concentrator.
c) Spent Resin 4 i
, 1) 'The purification ion exchanger (CVCS) dominates the amount of -
activity that enters the spent resin ta12k. Credit is taken for the upstream DF of the purification filter.
- 2) Lithium removal ion exchanger (CVCS)
(a) The lithium removal ion exchanger is assumed to be on line 20 percent of the time. (40 gpm) ( .2) = 6 gpm
~
average .
(b) Credit is taken for upstream DF by the purification filter
- and p,
- rification ion exchanger.
- 3) Deboration ion exchanger (CVCS)
(a) The deborating ion exchanger is assumed to be on line at the end of the core cycle when the boren concentration reaches 30 ppm.
(b) Credit is taken for upstream DF by the purification fil-
. ter and purification ion exchenger.
J
MSES-FSAR-U IT-3 TABLE 11.4-9 (Cont'd) -
- 4) Pre-Concentrator ion exchanger (BMS)
(a) Waste processed through this ion exchanger (see a.8)
(b) Credit is talism for upstream DF by the purification filter and purification ion exchanger.
- 5) Fuel pool purification ion exchanger (FPS)
. (a) The fuel pool water is processed through the ion -
exchanger at 150 gym.
(b) The volume of the spent fuel pool is 312,000 gallons .'
(c) The volume of the refueling cavity pool is 470,000 -
, gallons.
- 6) Boric acid condensate ion exchanger (BMS) and waste condensata ion exchangers -
(a) These ion exchangers are loccted downstream of the dis-tillate of the concentrators. Their contribution to total resin activity is negligible compared to the pre-*
viously listed ion exchangers.
- 7) Blowdown ion exchangers I-j,- ('a ) Based on primary-to-secondary leakage of 100 pounds per N day and one regenerative batch being radioactive.
260 cu ft./yr. of radioactive resin is being collected from steam generator blowdown ion exchangers.
d). Spent Filter Cartridges
- 1) Purification filter (CVCS)
(a) The activity that builds up on the purification filters predominates over the other filters.
(b) The purification filter is assumed to be changed four times per yr.
~
- 2) Fuel pool purification filter (FPS) see c.5.
- 3) Waste filter (W.S) .
(a) Vasta quantities and activities processed through this filter are the same as in b.l.
t a
b J
, , L' SIS-FSAR-15N-3 -
~
_ 4 , TABIZ 11.4-9 (Cont 'd)
L (b) Credit for decay is taken for the time required to fill one 4000 gallon waste tank. .
( 4) Laundry filter (WMS)
(a) The activity built up on this filter is negligible when compared to other filters in system.
1
- 5) Pre-Concentrator filter (BMS) i (a) Waste processed through this filter (see a.8) '
(b) Credit is taken for upstream DF by the purificar1on filter.
- 6) 011 separator filter (WMS)
See d.3.
s ll s
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REACTOR ,
AuxlLIARY l BULDING TURSINE l BUILDING XILIMFICETION 84cti
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i l
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l
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PORTABLE SOL 1DIFICATION SYSTEM SITE PLAN- LOCATION '
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PORTABLE SO.LIDIFICATION SYSTEM PLAN VIEW E L.+21
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