ML20064D924
| ML20064D924 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/30/1982 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20064D881 | List: |
| References | |
| NUDOCS 8301040789 | |
| Download: ML20064D924 (100) | |
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i NOVEMBER 1982; .
I, 4
i* SEQUOYAH NUCLEAR PLANT l
l Units 1 and 2 l
VOLUME REDUCTION l AND
., SOLIDIFICATION SYSTEM TENNESSEE VALLEY AUTHORITY REQUEST FOR A LICENSE AMENDMENT NOVEMBER 1982
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- --- -~ -
TABLE OF CON 2EN2S e
1.0 IN'IRODUCTION
, 1.1 Purpose 1.2 Ba ckgro und 1.3 Need 1.4 Scope 2.0 FACILITY DESIGN DESCRIPTION 2 .1 Summary Description 2.2 Structural Design 2.3 Security 2 .4 Fire Protection 2.5 Radiation Protection and ALARA 2.6 Quality Assurance 2 .7 Electrical Requirements 2.8 Equipment Codes 3.0 FACILITY OPERATION 3 .1 Volume Reduction System 3 .2 Solidification System 3.3 Bulk Resin Processing 4.0 RADIOLOGICAL ASSESSMENT 4 .1 Radiological Considerations 4.2 Incremental Occupational Exposures
- k 5.0 ENVIRONMENTAL ASSESSMENT 5 .1 Environmental Impacts of the Proposed Action 5.2 Unavoidable Adver se Environmental Impact s 5.3 Irreversible and Irretrievable Commitments of Resources 6.0 ACCIDENT REVIEW 6 .1 General
! 6.2 Process Accident Postulation 6.3 Proce ss Accidents Considered 6.4 Process Accidents Analyzed 6.5 Handling Accidents 6.6 System Design Saf ety Features to Preclude Accidents l
7.0 DECOMMISSIONING 8.0 REFER ENCES i
9
. , - ~ . . .
LIST OF TABLES l Table No. Title 1.2-1 Anticipated Radwaste To Be Processed By Either The VR or SS
- Per Year 2.1-1 Radionuclide Distribution In Inflow Waste Streams 2 . 8-1 Codes And Standards 4.1-1 SQNP VR Releases From Process Offgases Excluding Resins 4.1-2 SW9P VR Releases - Non-Resin Waste Appendix I Type Evaluation 4.1.1-1 SQNP - LLRW VR Ef fluent Relea ses 4.1.2-1 SONP VR Ef fluent Releases Population Data 4.1.3-1 SQNP VR Annual Individual Doses From Off gas Ef fluents 4.1.3-2 SQNP VR Releases For Non-Resin Incineration Population Doses 5.1.2-1 Prototype System Pollutant Concentrations And Calculated Emission Rates From Radioactive Waste Sources 5.1.2-2 Annual Nonradioactive Emissions From Radioactive Waste -
Sources 6.4-1 Maximum Radioactivity Accumulation In Equipment .'
9 11
_m- ,-. , , _ _ - _ . _ - _ _ _ _ - ,_
LIST CF FIGURES 0
fi.gure No,, Title 9 2.1-1 Volume Reduction And Solidification Facility Equipment 2.1-2 Volume Reduction And Solidification Facility Equipment 2.1-3 Volume Reduction And Solidification Facility Equipment 2.1-4 Volume Reduction And Solidification Facility Equipment 2.1-5 Volume Reduction And Solidification Facility Equipment 2.1-6 Volume Reduction And Solidification Facility Equipment 2 .1 -7 Volume Reduction And Solidification Facility Equipment 2.1-8 Volume Reduction And Solidification Facility Equipment 2.1-9 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 1 of 12) 2.1-10 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 2 of 12) 2.1-11 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 3 of 12) 2.1-12 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 4 of 12) 2.1-13 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, Sheet 5 of 12) 2.1-14 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, Sheet 6 of 12) 2.1-15 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 7 of 12) 2.1-16 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 8 of 12) iii
LIST CF FIGURES (scit'd)
Finure No. Titi, 2.1-17 Volume Reduction P 8 ids (Ref erence AECC No. 1193002. *
(Sheet 9 of 12) 2.1-18 Volume Reduction P 8 ids (Ref erence AECC No. 1193002.
(Sheet 10 of 12) 2.1-19 Volum; Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 11 of 12) 2.1-20 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, (Sheet 12 of 12) 2.1-21 Volume Reduction P 8 ids (Ref erence AECC No. 1193002, 119303) 2.1-22 Solidification System P 8 ids (Ref erence SECo No. D17467, (Sheet 1) 2.1-23 Solidification System P 8 ids (Ref erence SECo No. D17467, (Sheet 2) 2.1-24 Solidification System P 8 ids (Ref erence SECo No. D17467, (Sheet 3) 2.1-25 Solidification System P 8 ids (Ref erence SEco No. LD18183, .
(Sheet 3) 2.1-26 Solidification System P 8 ids (Ref erence SECo No.17467, ,
(Sheet 5) 2.1-27 Solidification System P 8 ids (Ref erence SECo No. LD18183, (Sheet 2) 2.1-28 Solidification System P 8 ids (Ref erence SECo No. E812) 2.1-29 Solidification System P 8 ids (Ref erence SECo No. E813) 2.1-30 Solidification System P 8 ids (Ref erence SECo No. E1005, (Sheet 1) iV a
,--e -
LIST OF FIGURES (cost'd)
F_llure No, IJtle
, 2.1-31 Solidification System P S ids (Ref erence SECo No. E1005, (Sheet 2) 2,2-1 Main Plant Location Of Structures 2.2-2 Saf e Shutdown Earthquake Design Response Spectra Horizontal Motion 2.2-3 Saf e Shutdown Earthquake Design Response Spectra Vertical Motion l
l V
l
SEQUOYAH NUCLEAR PLANT RADI0 ACTIVE W ASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM (VR/SS) e
1.0 INTRODUCTION
1.1 Purnose This document is provided as. supporting information for a pro-posed amendment to the facility operating license for Sequoyah Nuclear Plant (SQNP). The proposed amendment is to allow opera-tion of onsite volume reduction equipment to process low-level radioactive waste (LLRW) at SQNP. This document is intended to be fully adequate for the U.S. Nuclear Regulatory Commission (NRC) staff to make a decision regarding the a c c e pt a b il i ty of the action and authorize the proposed amendment.
1.2 R_ackaround The Tennessee Valley Auth or i ty (TVA) owns SQNP located in Hamilton County, Tennessee. Operation of this plant w ill result in planned and controlled generation of LLRW. This waste primarily consists of ion exchange resins, evaporator concentrates, spent regenerates, contaminated oils, and dry
. active waste as described in Table 1.2-1. For the reasons outlined in Section 1. 3 , 'Need,' TVA is seeking authorization by way of amendment to our facility operating license to operate a i v ol um e reduction system (VR) including a permanently installed incinerator and calciner to process LLRW at SQNP. TVA has completed a preliminary safety review and has determined that NRC approval is required for operation of the volume reduction system j addition.
i The VR i s designed to process and reduce the volume of radioactive materials. Dry active waste and contaminated o il s will be incine ra ted whil e evaporator concentrates and spent regenerates will be calcined. Spent re sins will not be incinerated, but w il l be either dewatered or solidified and packaged in accordance with burial site requirements. The Solidification System (SS) will produce a solidified package that is acceptable for storage onsite or disposal offsite.
- 1. 3 Need Since the startup of SQNP, TV A h a s packaged and shipped LLRW generated at SQNP to commercial radioactive waste disposal sites. Recently, however, significant restrictions have been placed on the volume (ft8) of packaged LLRW that Chem-Nuclear Systems, Inc., (CNSI) will accept for disposal.
J i 1-1 m ._ , , _ _ _ . , . . _ _ - . _ _ . - _ _ _ _ _ - _ _ _ , _ _ - - - - . -- ~ _.
SQNP TV A h a s buil t and received a license to operate an onsite low-level radioactive waste storage facility that w il l reduce our immediate dependence upon the availability of commercial burial facilities.
TV A b e l i e v e s that it is a prudent policy to reduce the volume of LLRW. Therefore, we are requesting approval for the operation of the v ol um e reduction sy st em a ddi ti on. We believe this approach is consistent with the NRC ' Policy Statement on Low-Level Waste V ol um e Reduction' as published in the October 16, 1981 Federal Romister notice FR 51101. This proposal, in conj unction wi th other associated LLRW actions, would be a step towards the NRC stated goals of:
- 1. Extending the operational lifetime of existing commercial low-level disposal sites;
- 2. Reducing the number and/or v ol um e of waste shipments.
- 1. 4 Scope This document is to describe the design and operation of volume-reduction equipment and its associated facility. The information provided consists of the f acility design criteria, the environ-mental and radiological assessments, and a safety or accident analysis, as w ell as information regarding f acility operation and -
decommissioning.
The design basis for the SQNP VR/ SS facility as given in this a document is based on NRC Regulatory Guide 1.143 guidelines.
Regulatory Guide 1.143 was utilized by TVA as a minimum design basis because it was determined to be the most applicable to the nature of the facility, although it was not specifically prepared and issued for this purpose. The actual design parameters em pl oy e d by TVA in the facility's design are in some cases more conservative than those required by Regulatory Guide 1.143.
~
I 1-2 l .
l i
SONP TABLE 1,2-1 F
ANTICIPATED RADWASTE TO BE PROCESSED BY EITilER THE VR OR SS PER YEAR Waste Tyne Ypjuse (Ft8/Yr)
Spent Ion-Exchange Resin 600*
Evaporator Concentrates 3,500b 12,500 Spent Regenerates Dry Active Waste" 36,000 (unc ampa c ted average density, 10 lbs/ft8)
Contaminated Oil 300 Spent Filter Cartridges and 1,000 Other Miscellaneous Articles (to be encapsulated) 1DTAL 53,900
" Dew a t ere d. Volume is twice this value if resin is solidified.
V b Non-solidified volumes.
' Consist s of items such as PVC's, polyethylene boots, rubber shoe covers, rubber hose, pla stic hose (Nalgene), cotton gloves, cotton glove inserts, cotton coveralls, rubber gloves, surgical masks, paper coveralls, wood crates (pine, oak, plywood), sops, brooms, wood used for scaffolding and ladders, laboratory equipment (vials and plastic bottles), and other combustible obj ect s.
- 1-3
SQNP 2.0 1; A t i l. I 'l Y lil.S I G N lil.S CH 11'T I ON e
2I lie,gJJ v D eJJ2J.lR.1.1.9.B This license amendment is intended to incorporate the VR/SS (Volume Reduction and Solidification System) facility into the existing overall plant radwaste facilities previously covered in the Sequoyah Nuclear Plant Final Safety Analysis Report (FSAR).
The contents of this amendment w ill focus entirely on the VR/ SS facility to be added at SQNP. The facility includes process equipment for spent resins; evaporator concentrates; spent regenerates; contaminated oils; and dry active wa ste s which are products of the overall plant operation and maintenance. The VR/SS f a c ili ty w ill be a noncategory I safety-related structure constructed of reinforced concrete and structural steel.
The facility is composed of various sub sy s t em s whi ch are desigaed to collect, treat, volume reduce, recycle, package, and s olid! f y different categories of radioactive material in a safe and economical manner.
The VR is designed to process and reduce the volume of r a di oa c t iv e materials utilizing an incineration and calcination process. The SS will produce a solidified package that is acceptable for storage onsito or disposal offsite. The off gas scrub system w ill collect particulates containing effectively all the radioactive contaminants. This system along with associated radiation control monitoring devices ensures that gaseous e effluents w ill be wi thin acceptable levels.
It is estimated that 53,900 ft8 of wast e will be processed by the VR/SS each year from the two units at SQNP. Table 1.2-1 describes the waste types and volumes. The activity and radionuclide distribution contained in the weste are listed in Table 2.1-1. The waste, before proceasing, will be handled in the manner described in Section 3.0, ' Facility Operations.'
The VR/SS f acili ty will have tw o truck bays to receive waste for processing and to load solidified waste for offsite disposal or onsite storage. Each truck bay is designed to handle a s emi t r a il e r and attached cab. The tw o truck bays will be separated by a shield wall to allow loading of radweste containers on a truck for shipment and simultaneous unloading of other (radioactive or nonradioactive) materials. A crane is supplied to handle drums, shield casks, and other equipment. The handling operations are the same for onsite storage or offsite disposal.
The VR/SS facility storage area is capable of accommodating the solidified product of up to 180 daya of normal operational waste input. This facilitates system operation in the event removal of packaged westes from the area is temporarily delayed or is 2-1
SQNP impractical for short periods.
Preliminary equipment arrangement drawings for the VR/ SS f acility are shown in Figures 2.1-1 through 2.1-8.
2.1.1 Volume Reduction System Description The VR supplied by Aerojet Energy Conversion Company (AECC),
utilizes fluidized bed technology to process a wide variety of low-level radioactive wastes. The AECC VR consists of a fluid bed incinerator, fluid bed dryer, and a common off gas cleanup and f il t er system.
Areas for storage of wastes before processing are provided.
These include a dry waste storage area locsted adjacent to the VR to store bagged uncompacted dry waste with a capacity of seven daya at maximum plant input. Two resin waste co11cetion and storage tanks have a capacity of 5,000 gallons each and are equipped wi th a decenting pump and recirculating pump.
Concentrated liquid w a ste w ill be stored in two 7,500 gallon capacity tanks equipped wi th pumps. Tanks and piping associated w i th the concentrated liquids will be heat traced. The resin storage tanks and the concentrated liquid wa ste storage tanks -
w ill be located in diked rooms which are capable of holding the entire inventory in the event of a pipe or tank rupture.
t Piping and instrumentation diagrams as well as mass energy balance di a g r am s for the VR can be found on Figures 2.1-9 through 2.1-21.
The c a pa bil i ty also exists for the compaction of low radiation level, compressible dry a c t iv e wa s t e into SS gallon drums. An area is provided for remov81 of dry, previously compacted waste from 55 gallon drums. The area is located adjacent to the dry active waste storage area discussed above, and is equipped with air, water, and drain services as well as a vent for collection and treatment of airborne radioactive releases.
The dry act iv e wa stes (e.g., contaminated paper, wood, cardboard, cloth, rubber and plastics, such as polyethylene), and contaminated oil are processed in the fluid bed incinerator vessel and are converted to an ash residue. Liquid wast e s consisting of evaporator concentrates and spent regenerates are processed in the fluid bed dryer and converted to unhydrous, free-flowing salts.
The fluid bed dryer vessel (R-1) used for drying the evaporator concentrates is electrically heated and controlled in several I ways. The airflow is determined by a measured pressure drop across an orifice plate to a proportional fl ow con t roll e r w hi ch regulates the airflow through a butterfly control valve. The bed I
2-2 .
SONP
, temperature is controlled by the preconcentrated feedproportionalfl ow rate input. Thermocouples transmit the temperature to a con troll e r which in turn controls the liquid feed rate.
The fluid bed incinerator (R-3) temperature it controlled using the conden sa t e wa t e r from the condenser (S-3), t h e r e b_y basically controlling the raising and l ow e r i ng of the temperature dueThe to the beating value variation of the dry active waste feed.
signal from the temperature controller is transmitted to a proportional controll e r which operates a flow control valve regulating the condensate through a spray nozzle. The incinerator is refractory lined and equipped wi th an electrical Thereafter, the heater for preheating the air during startup.
combustion of dry active waste or contaminated o ilFuel s generates oil may be sufficient heat energy to maintain the process.
utilized to increase the efficiency of the process.
The incineration of radioactive waste r e sul t s in a volume For the reduction factor of about 100 for dry active waste.
chara ct eriz ed w ast e v ol um e s given in Table 1.2-1, an overall These v ol um e reduction factor of at least 10 can be r e a l iz e d.
estimated volume reduction factors do not take into account the noncombustible and/or noncompactible trash, but do allow for the additional v ol um e of the solidification agent.
The off-gas from each process vessel is processed by an off gas cleanup sy st em. All waste gas from the proce s s will be treated by dry cyclones, venturi scrubbers, demisters, charcoal 8 adsorbers, and HEPA f il t e r s for removal of radioactivity and chemical impurities. Decontamination factors for the off gas cleanup system are based on actual tests conducted by the VR supplier.
The VR controls are located in the VR/ SS control room. The system's main controls are contained in f r ec- s t an di n g NEMA-4 cabincts. Instrumentalaon in the main control panci (CP-1) is composed of solid-state electronic components and is of standard design.
The VR is equipped with control instrumentation which provides for remote, unattended operation, and automatic shutdown in the event of a malfunction. These system features w ill preclude damage to equipment, and provide adequate safety to plant operating personnel. Process temperatures, pressures, and flow rates are monitored u t il iz in g thermocouples, pressure transmitters, and flow transmitters. Instrumentation and controls maintain process parameters (i.e., temperature, chemistry, radioactivity, pressure, and liquid level) within The limits which assure safe and efficient system operation.
maj or proceas parameters are continually recorded. Safe operation of the VR is provided by control sequencing and interlocks which prevent improper operation and cause automatic 2-3
SGNP sy s t em sh u t d ow n if system parameters are not maintained within accepted operating limits. Alarms alert the operator to abnormal conditions.
The VR instrumentation and control sy st em w ill operate in either automatic or manual modes. Al a rm s and/or shutdown are provided for specific out-of-tolerance conditions. Shutdown is automatic when initiated by the operator or by certain ou t-o f- t ol e ran c e conditions. Under manual mode, the startup and shutdown sequence is under operator control. The process logic provides system interlocking required to prevent ou t- of- se q ue n ce operation, and provides automatic regulation of the process control loops.
Access to the control loop setpoints allows adjustment of the system con troll er s wi thin a l l ow a bl e limi t s while the system is operating.
Gaseous w a st e s w il l be continuously monitored for r adi oa c t iv i ty before relesse. Radiation monitoring is discussed further in Section 2.5, ' Radiation Protection and ALARA.' Processing w il l be terminated if the radioactivity l ev el s in the effluent stream would cause offsite doses in excess of regulatory limits. The ga seou s effluent s tre am w ill be released from a vent loca ted and designed to ensure adequate dispersion characteristics.
Generle system descriptions, tests, and other pertinent supporting data are documented in AECC topical reports which have been previously submitted to the NRC. These include Topical Reports Nos. AECC-1-A (September 30, 1975), AECC-2-P (October 15, a 1979), and AECC-3-P (December 1981). These documents supplement the information described herein.
2.1.2 S o l i d_i_f i c a t i o n _ Sy s t e m Defeription The Solidification System ( SS) , supplied by Stock Equipment Company (SECo), will immobilize the salts resulting from the drying of evaporator concentrates and ash resulting from the incineration of dry a c t iv e weste, and contaminated oil. The SS is also capable of solidifying spent resins, evaporated concentrates, spent regenerates, and encapsulating spent f il t er cartridges and other small miscellaneous noncompactible contaminated articles (valves, metal pipes, etc.), into a 55-gallon drum. The primary components of the solidification system include polymer and cement storage, filling, and drumming stations, spent resin storage and decant tanks, a drum inspection station, a crane, and a process control station. Piping and instrumention diagrams for the SS are s h ow n on Figures 2.1-22 through 2.1-31. (Reference SECO Generic Topical Report, SRS-001-P, March 1979, on cement solidification which supplements the information described herein.)
2-4 e
SQNP 2.1.2.1 Polymer and Cement Fillina Stations Polymer and cement filling stations are provided to acasare solidification agent into 55 gallon, tight-head DOT-17C (or s imil a r) drums fitted with a 4-inch threaded bung insert. The polymer filling station consists of a conveyor that transfers empty drums to the fill position, a drip proof fill nozzle to place polymer and promoter within the drum, a scale assembly to verify that the correct amount of solidification agent is within the drum for a select waste stream, a station control console, and a conveyor to transfer prepared drums to the the crane pickup point for processing.
Metering pumps for handling solidification agent chemicals, valving, f il t er s , ventilation systems, reservoirs, and controls are provided. The polymer recirculation / reservoir delivery pump, located at the fill station, w ill have a dual function of delivering polymer from the polymer storage tank to the polymer fill station reservoir and also recirculating the polymer back to the storage tank.
If cement solidification is selected, the drum is conveyed to the cement filling station where dry cement is added. The cement
. filling nozzle has a vent connection leading to a dust collector to prevent dispersion of cement dust.
, 2.1.2.2 Polyser and Cement Drummina Stations The Dry Product / Polymer Drumming Station consists of a l
(
pressurized vessel designed to receive dry products of the volume i
reduction system, deposit them in a SS-gallon drum (prefilled with a binding agent), and thoroughly coat the product s with polymer. The essential components of the station are the shield wall, to which the chamber is mounted; the pressure vessel, which serves as the containment vessel for the coating process; the pivot and lift mechanism used for positioning of the drum w i th in the chamber; the capper /uncapper mechanism; the f ill nozzle / mixer drive; a control sy s t em of pressure balance sensors for dust control; and a system of pipes and nozzles for internal washdown.
The drumming station enclosure w il l be a pressure vessel. The access ha t ch will be of ' pressure tight' design, and the drain w ill be equipped with a full flow plug-type valve with a remote manual actuator. The fill nozzle and pressure tight dry product valve separating the drumming station from the product storage hoppe r w ill be designed to handle dry product. The f ill nozzle w il l be heated to prevent condensation from accumulating and causing a buildup of dry product on the nozzle. The primary seal, preventing dust from escaping, will be a diaphragm built into the drum which seals on the dry product fill nozzle.
2-5
SQNP The Wet Waste /Coment Drumming Station is an enolosed, vented.
atmospheric a s sembly designed to uncap $$ gallon, closed top
- drums, fill the drums, mix the contents, and recap the drums.
The assembly is completely enclosed to prevent any escape of radioactive liquid or gas.
The vessel is attached to the processing side of the steel shield w all, wi th driv e mot or s, limit switches, sensors, and controls on the opposite (safe) side of the shield w all . The vessel is stainless steel. Internal surfaces are free of crevices to limit i potential radioactive particle crud traps.
Two platforms are mounted on the sides of the vessel hatch. One i platform is a setdown position to facilitate loading the drum processing vessel. The second platform is equipped with load cells f or w eighing f ill e d drums plus a detector for measuring the drum radiation level before storage. This platform arrangement minimizes drum processing vessel loading and unloading time. The scale and radiation detector are connected to digital solid state readouts on the control console.
1 2.1.2.3 Scent Rosin Storane and Decent Tanks Tw o (2) 5,000 ga11on, decanting-type holding tanks w il l be provided for the storage and handling of resins. Each tank is ~
equipped w ith a mixer assembly, decant arm sy s t em and associated hardware, decant pump, and decontamination s p r ay s . A separate i
centrifugal pump w ith manif old-valved piping will be provided for
- each tank. Resins can be recirculated through the sampling station and reagent addition station, back to the 5,000-ga11on tank, or they can be transferred to the second 5,000 ga11on tank if necessary. Volumes of these tanks w ill allow a ISO-day decay of shor t-live d ra dionuclide s based on input volumes in table
! 1.2-1. The holding tank wast es can also be pumped to the 500-i gallon decanting station tank for batch processing before drumming.
The 500 gallon decanting station tank accurately proportions re sin wa ste and water to ensure the proper feed for j solidif ica tion w ith cement. It is a closed stainless steel cylindrical vessel, approxima t ely 4 ' 6" diameter x 5' high, with j a semi-elliptical upper head, and a conical lower head. It includes a movable decanting nozzle, level sensors, and a mechanical mixer.
, 2.1.2.4 Drum _Insreotion Station j The Drum Inspection Station enclosure consists of a 12-inch thick steel shield wall which is welded to A3"x the 1/4-inch thick steel 52" vertical access
! plate sides and rear w all assembly.
j opening for swipe applicator tool entry is provided to one side i of the shield wall . The bottom of the enclosure w el ds en t is 2-6 .
I n-., ,-.. -- _ - - . , , . . - -- ,. ., --.,_..__--.-.---_,_-,.,~,-..__n_ , _ - - . - _ - , - - - - . _ , , - . , e n-,
SQNP constructed from 3/16-inch steel plate and is equipped with a drain connection. The entire top of the drum inspection station enclosure remains open to provide access for SS gallon dr um loading and unloading to and from the enclosure.
The motor-driven turntable assembly (1,000-pound drum capacity) located in the center of the inspection station is provided for both clockwise and counter-clockwise drum rotation. During the drum sw i pe test, the drum is rotated to present the entire drum external surface area to the swipe pad for accurate testing.
2.1.2.5 Crane A bridge crane is provided to transfer drums, shielded casks, and other materials / equipment in the ra di oa c t iv e processing and storage areas. The crane is equipped with a 7-1/ 2-ton h oi s t w i th a drum grab and TV camera with remote and local control c a pa bil i ty . A target grid system (located above the crane) with mounted TV cameras provides accurate location ca pab ili ty. The drum grab may be easily loca t ed within 1/ 4-inch tolerance which ensurea safety and prompt remote operation. The crane is dasigned to be washed down for decontamination.
. 2.1.2.6 Controls All control and indicating devices required for remote operation of the crane, decant station, drumming stations, and sl ur ry tanks are located on the solidification system control console. The crane control section includes the TV moni t or s wi th their control units. The drum processing control section contains a graphic i
panel of the solidification system and all manual switches and visual indicators for, operating the drumming and decanting stations.
2.2 Structural Desian 2.2.1 General The VR/ SS facility will be a noncategory I safety-related structure constructed of reinforced concrete and structural steel. It w ill be located adj acent to the Condensate Demine raliz e r Wa s t e Eva pora t or Building (see Figure 2.2-1) and designed to prevent collapse on the adj ace nt Category I structure, piping, and electrical conduit. All structural sy st ems shall be designed to withstand the design basis events, 1 normal, severe environmental, extreme environmental loads, and combinations of the above loads as described in the f ollowing sections.
2-7
SQNP 2.2.2 Desian Basis Eventi 2.2.2.1 Deslan Basis Earthauske 2.2.2.1.1 Earthauake Definition The structur e will be analyzed and designed to resist the seismically induced motions of the safe shutdown earthquake (SSE) because of its location adj acent to Category I structures and systems. The SSE is defined as a top of ground motion wi th maximum horizontal and vertical accelerations of 0.25g. Response spectra for the three statistically independent artificial accelerograms, two horizont al and one vertical, were developed and are included as Figures 2.2-2 and 2.2-3. Each record has a total duration of 22 seconds. The three earthquake components are assumed to occur simultaneously.
2.2.2.1.2 Seismic Ansivsis The seismic analysis of the structure will be based upon dynamic analysis using an idealized mathematical model. In developing the model, the location and mass of the equipment w il l be considered. A sufficient number of ma s s points, located at positions of mass concentration such as floors, will be chosen so that all significant modes of vibration are adequately defined.
In general, to adequetely define the frequency of the highest -
mode to be used in the analysis to within 10 percent, the minimum number of lump masses is twice the mode number. For example, if the first three translational modes are to be used in the .
analysis, at least six lumped masses w il l be included in the model.
The mass of equipment, components, or sy st em s w ill be included directly with the appropriate lumped mass. After the locations of the ma ss points have been established, the number of dynamic degrees of freedom a s socia ted wi th each ma s s w ill be considered.
Six degrees of freedom exist for all mass points, i.e., three t ra nsl a tional and three rotational.
The inertial properties of the model s will be characterized by the mass, eccentricity, and mass moment of inertia of each mass point. Stiffness proper tie s w ill be characterized by th e length, moment of inertia, shear shape factor, torsion constant, Young's modulus, and shear modulus. Vertical modes of the structure w il l be comput e d and their effects included in the structural response.
The structural response w ill be computed by the response spectrum modal analysis technique considering three components of the earthquake acting simultaneously. The total structural response (deflections, a cc el e ra t ions, stresses, etc.) w ill be computed from the individual modal response by the methods described in 2-8
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NRC Regulatory Guide 1.92,~' Combining Mods 1 Response and Spatial-Components in Seismic Response Analysis.' }
2.2.2.1.3 Structure-Foggjetlon Interactica .
['
Soil-structure interaction will be taken into acconut by coupilag A finite the structural model with the foundation medium.
element or an equivalent analysis as di a'c[n a s e d in NRC Standa rde Review Plan 3.7.2, ' Seismic System Analyst ~s,' w ill be used. -
The acceleration at the top of the rp co,a d surface w ill be considered tt_be deconvoluted through the soll to the bottom
, boundary (bedrock). For analysis purposeilthe bettom of the base The
' slab w ill be the assumed t,o p of graend mo' pion e l e'v a t i o n .
artificially produced accelecograss will Ao consid6cid the input motion a f the . top of the ground surf a ce"ty'd w ill be used to generate the time histories of the acceletstiens This analysis is influenced at the bottom boundary by deconvolution analysis.
by the accuracy of the determination of the in situ soil properties... ground water, slanted s o il,,l ay e r s ,
- oil density .
v a ri a t i ona and v a ri a ti ons - in b'o th finished grgde elevation and bottom bo und a ry ,( b e dr o c k ) e ! ,e v a t i o n . 'Th e r e f or's , the soil properties a n d ,t h e depth,of roll beneath the structur e will be varied using son'nd enginetrine,Jrl5 ment to obtain different
~
bottom bounda ry moti on h i st ocl e,-vhich w ill be ysed in competing -
~
the structura1 response. ~~/
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2.2.2.1.4 -
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A pile or caisson f orada tion will be jonsidered in the soil-structure dynasio analysis. Stikt,enin~g effect of the soil and p il e or caissor c ombi na t fp an , s w i11' b e considered where the stiffening effect on Tthe soll is s i gni f ic a n t .-
\
2.2.2.2 Desita B3eis Wind The structur e w ill be ~ designe$ to withstand the f,orces exerted by a wind having a maximum speed of 95 mph at 30 feet above the grade elevatton. This design bssis wind 6as/a recurrence i n t 'e t t a l of 100 years. ,
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2.2.2.3 Desian Basis Torpedo ;.<.*p The s t ruc tur el w i11 be designed to with st and the fopce?,rvi$rtedby a .t or na do w ind h av6ngit. perizberay rotational velocity of 290 m (l e s per hourfat, W' radius of 150'. feet from the center of the
/,
t or na do wi th a t'r ta s i a t i o n a l v elc ei ty of 70 mph, and depr e s suriz a tion d ea d of 3 psi st .$ntlined in NRC Regul at ory Guide 1.76, 'Desiga onsis Tornadwif or Nuclear Power Plants.'
Venting w il l be utilized if ne ce s sa ry, to redvce or eliminate any b1 pressure differentials. '
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SONP Int erior wall s, floors, doors, and other internal bu il din g el em ent s w ill be de signed to withstand pr es sure differentials .
caused by any locally unequal depressurization rates that occur during a planned depressurization or before tornado dampers close, where applicable.
Interior w all s, floors, and doors that are between an area designed to depressurize, and one that should not depressurize, w il l be designed for the differential pressure transient.
Tornado missile impact is not required to be considered by NRC Regulatory Guide 1.143, ' Design Guidance for Radioactive.Wasto Management Systems, Structures, and Components Installed i n Light-Water-Cooled Nuclear Plants.' However, some degree of missile protection is inherently provided by the required radiological shielding thickness for the structure.
2.2.2.4 Desian Basis Flood The structur e w ill be located above the design basis flood elevation (E1. 6 87 .5) which is the 500-year recurrence i nterval flood. In addition, the structural adequacy will be verified up to the probable maximum flood as the s truct ur e w ill be allowed to flood.
2.2.2.5 D e_s_i g n Basis Pr_ocinitation The probable maximum precipitation (PNP) is 29.5 inches of
- rainfall during an 8-hour time span w ith a maximum 1-hour depth of 14 inches. G ra din g for the f acility will be such that a buil dup of w a t er around the structure during the PNP will be minimized. The drainage of this ar e a w ill be investigated with respect to effects of PNP drainage in the nuclear plant area to ensure that any change in the PNP elevation in that area does not have an adverse impact on any existing structure.
2.2.3 Loads.,__Defini_t_ ions. and N o m e n c I a_t_u r e 2.2.3.1 Minimpia Live Loads The minimum roof l iv e load is 50 lb/fts, 2.2.3.2 P_recipitation Loads The maximum snow load and ice load for the f acility is less than the minimum roef live load specified in section 2.2.3.1. F.o r
' normal rainfall (4 in/hr), a conventional roof drain and dow n s po ut sy st em w ill discharge all roof runoff into the yard drainsgo system. H ow ev e r , one or more of the f oll ow ing w ill be used to prevent buildup of standing water on th e roof:
2-10 .
- - -c--my
SQNP
- 1. The parapets may be deleted on one or more sides of the building. ,
- 2. The parapet height may be limited to preclude a buildup of water in excess of the structural capacity of the roof for the design l iv e load on the roof.
i
- 3. Souppers may be installed through the parapets to discharge the standing water over the edge of the building.
2.2.3.3 Definitions of Load Terms-The f ollow ing t erms a re used in the load combination equations for this s af e ty-r el a t e d structure:
Norm al loads, which are those loads to be encountered during normal facility operation and include:
D--Dead loads, or their related internal moments and forces including any permanent equipment load.
L--Liv e loads, or their related internal moments and forces including any movabl e equipment loads, and other loads which
- v a ry w ath intensity and occurrence.
To-Thermal effects and loads during normal operating
= conditions, based on the most critical transient or steady-state condition.
Severe environmental loads include:
W--Loads generated by the design ba si s wind.
Extreme environmental loads include:
E--Loads generated by safe shut dow n earthquake.
Wt --Load generated by the design basis tornado.
Other loads:
L c --Construction live loads.
2.2.4 Load Combinations 2.2.4.1 General The required section strength to be used in the design is the maximum value among the several values of U and S2.2.4.3.
determined from the loading combinations of sections 2.2.4.2 and 1 .
e 2-11
SQNP Situations occur where one or more Icada in a loading combination have opposite signs from the other loads in the same combinations. The following situa tions w ill be investigated for possible reversal of net effects, and for determination of maximum moments and forces:
- 1. Area distribution for live load.
- 2. Maximum value of live load.
- 3. Zero value for live load.
Other l oa ds w il l be combined with these live load situations as specified in section 2.2.4.2 and 2.2.4.3.
Creep has an insignificant effect on design of relatively thick reinforced concrete structures because of its relation to stress w i th time and relatively low operating stress conditions, and because it primarily serves to relieve s tre s se s wi thout encroaching on structural safety. It is therefore not considered in the design of the VR/ SS structure.
Where structural effects of shrinkage or differential settlement may be significant, they shall be included with D in equation (1) of section 2.2.4.2. An estimate of shrinkage will be based on a .
realistic assessment of such an effect occurring in service.
2.2.4.2 Load combinations for the Safety-Reisted Concrete ,
Structure The strength design method will be used. The required section strength U. as defined in ACI 318-77, w ill be at least equal to the greatest of load combinations as f oll ow s :
- 1. U= 1.4D + 1.7L
- 2. U= 0.75 ( 1. 4 D + 1. 7 L + 1.7W + 1. 7 To )
- 3. U= D+ L+ E+T o
- 4. U= D+ L+ W t + To
- 5. U= 1.4D + 1.7 L + 1.7W The concrete structure required to contain the maximum expected liquid invent ory w ill mee t the requirements f or wa t e r- ti ght structures.
2-12 .
f
SQNP 2.2.4.3 Load Combination for Safetw-Related Steel Structure The ela stic working stress design methods of Part I of the AISC spe cif ica tions w ill be used where 3 is the required section strength. The f oll owing load combinations shall be considered:
- 1. S=D+ L
- 2. S=D+ L+ W
- 3. 1. 5 S = D+L+To
- 4. 1. S S = D+L+To+W
- 5. 1.6S = D+ L+ To+ E
- 6. 1.6S = D+ L + To + Vt 2.2.5 Foundation 2.2.5.1 General The structure w ill be supported upon a foundation system of reinforced concrete caissons or steel H-piles, which w ill rest upon or socket into sound bedrock.
. 2.2.5.2 Reinforced Concrete Caissons and H-ciles The reinforced concrete caissons or steel H-pil e s w ill be designed to wi th stand all loading combinations as outlined in sections 2.2.4.2 and 2.2.4.3.
For the load on foundation rock or soil, the load combinations in section 2.2.4.2 and 2.2.4.3 w ill be use d wi th unf a c tored loads.
Design a l l ow a b l e s for the rock and soil will be developed ba sed upon information gathered from subsurface investigations and as defined in section 2.5 of the SQNP FSAR. The basis for these design all ow able s w ill be documented for design and verified by additional subsurface investigation before construction, if required.
2.2.6 Structural Concrete All structural ca s t-in-pl a ce concrete shall have a specified minimum design compre s s ive strength of 3000 psi. For verification, concrete cylinders w il l be prepared and tested up to 180 days to determine the strength gain with age. The w eight of concrete w il l be taken as 150 pcf in all structural calculations. Considering the long range strength gain of fly ash concrete, all structural concrete mixes w il l attain a static
! Young 's modulus of 5 x 108 psi. Additional cocerete properties
- are:
l l -
2-13 l
SQNP
- 1. Poisson's Ratio: 'O.15 to 0.20 .
- 2. Thermal Conduc t iv i ty : 1.5 to 1.7 BTU per square foot per hour per 'F per foot.
- 3. Thermal Coefficient of Expansion: 5 x 10 8 inches per inch per 'F.
2.2.7 Steel 2.2.7.1 Reinforcina Steel Reinforcing steel will be Grade 60 deformed bars per specification ASTM A615. For tighter bend and tension toat requirements, supplementary requirement S1 of ASTM A 615-7 9 will apply.
2.2.7.2 Structural Stee1 Roll ed shapes, plates, and bars sh all be fabricated per specification ASTM A36. Fabricated high-strength s t e el w ill be per specification ASTM A572, and bolting w ill be per specification ASTM A325 or A490. Anchor bolt s will be per ASTM A307 or A36. .
2.2.7.3 Shear Ws11s Shear wall s w il l be provided for seismic loads such that the maximum combination of lateral forces are transmitted to the base of the structure. The w all s w il l be designed in accordance with ACI 318-77.
2.3 Security The VR/SS f acility is to be located inside the plant protected area and w ill have the same level of access control as the rest of the plant. The f acili ty is not considered a vital area, so no additional security measures are required.
2 .4 Fire Protection 2.4.1 Water Sunoly The water supply for the fire protection system for the VR/ SS facility is provided by the Sequoyah Nuclear Plant high pressure fire protection (HPFP) system. Refer to SQNP FSAR Section 9.5,
' Fire Protection System,' for a detailed description of the HPFP system.
2-14
l i
SONP f
2.4.2 Automatic Fire Detection Svates An automatic fire detection system is provided for the f acility and is designed in accordance with National Fire Protection Association (NFPA) Standards No. 72D and 72E. The system's initiating devices consist of fire detectors zoned such that a fire location can be identified and fire protection features controlled. In addition, manual alarm stations are provided at egress points from the facility.
The local detection panel is located at the main control point of the v ol um e reduction and solidification building. The detection panel provides local building alarms and a common alarm signal for annunciation in the nuclear plant's main control room.
2.4.3 Portable Fire Extinnuishers Portable fire extinguishers, approved for use on Class A, B, and C fires, are installed within the facility in accordance with the NFPA S tandard No. 10.
2.4.4 A Class III Standmine and Hose System A Class III standpipe and hose system designed in accordance with NFPA S tanda rd No. 14 is provided throughout the f acility.
. 2.4.5 Automatic Preaction Sorinkler System An automatic proaction sprinkler system designed in accordance with NFPA Standard No. 13 is provided throughout the facility, except in isolated rooms containing no combustible material and having limited access. Actuation of the suppression system is by the automatic fire detection system.
2.4.6 Portable Eauipment in addition to a preaction sprinkler system, portable equipment is provided in the vicinity of the Dow Filling Station for apply ing a foam-water solution on a fire involving the solidification binde r which is a styrene monomer cross-linked w i th a vinyl ester resin.
2.4.7 Outside Fire Protection Outside fire protection is provided in accordance w i th NFPA Standard No. 24. Hydrants supplied with hydrant house s with firefighting equipment are appropriately located a round the facility.
1 2-15 i
SQNP 2.5 Radiation Protection and_ALARA 2.5.1 Objectives f o r _ Ex p o s u r_e s 2.5.1.1 O_ble.ct.ives f or__ Expo sure to Plant OccusstJonal__ Workers The facility shall be designed such that exposures to plant radiation worker s during normal operation are in accordance with 10 CFR 20 and the requirements of TVA's radiation protection plan. The requirements given in the latter tw o documents constitute maximum acceptable levels, and not design objectives.
2.5.1.2 O b j e c t _i v e _s _ _ f o r _ E x p o s u r e s _ t o Visitina _ Radiation Workers The f acili ty is designed such that the whole body dose limits for visiting radia tion worker s and TVA employees are limited to:
- 1. 3 00 ares / cal enda r qua rt er, or
- 2. 1250 mrem / calendar quarter if dose records are supplied for the individual (s) for the present calendar quarter. The exposure permitted shall be a dj u s t e d so that the total received shall not exceed the 1250 mrem / calendar quarter.
- 3. 3000 mrem / calendar quarter if the requirements of item 2 and 10 CFR 20.101 (b) are met, and w ri t t en authorization of the individual's employer is obtained.
2.5.1.3 Objectives for Exposures to Nonoccupational Workers and Visitor _s The f acili ty shall be designed such that the whole body dose limits to nonoccupational w orker s and vi si t or s w ill be in accordance with 10 CFR 20.105(a) and 20.105(b)(1) and (2); i.e.,
500 mrem /y r, 2 ar em/ h r, and 100 mrem /7 consecutive daya for unrestricted areas.
2.5.2 D e,s i n n__ O M e c_t i v e s Shielding of the f acility is provided to the design obj ectives described in section 2.5.3, ' Radiation Shielding.' so that the exposure obj ec t iv e s, described above, can be met.
The plant is designed so that the radiation level in hallwaya of buildings containing radioactive equipment does not exceed 1.0 ar em/ hr during normal operation.
Ventilation of the facility is designed such that the concentrations of radioactive materials in areas can be maintaine d w ith in acceptable limits.
2-16
SONP 6 The area radiation and airborne radioactivity monitoring systems w il l be designed to comply with detailed criteria that w il l be developed. These criteria will encompass AL AR A and o ther regulatory requirements.
The solid waste end products, before shipping out for offsite, disposal or storage, w ill be prepared in such a w ay a s to comply with 10 CFR 71, and 49 CFR 171-179, for packaging and transportation of ra di oa c t iv e ma t e ri al s.
2.5.3 Radiation Shieldina The shielding for the f acility is designed in compliance with 10 CFR Part 20 and 10 CFR Part 50, Appendix A, Design Criteria 60 and 63, to ensure that:
- 1. The occupational radiation exposures to individuals in restricted areas are adequately controlled.
- 2. The intakes of radioactive material by individuals in restricted areas are adequately controlled.
- 3. The release of radioactive materials to the environment is adequately controlled.
- 4. Monitoring waste storage is implemented so that conditions leading to excessive radiation levels can be detected.
I Efforts shall be made to insure that occupational radiation exposures at the f a cility will be as l ow as reasonably achievable in compliance w ith NRC Re gul a tory Guide 8.8, and to control the
, spread of contamination. Also, potential radiation damage to
' equipment and materials shall be kept within tolerable limits.
Fabrication and installation of concrete radiation shields shall l be done in accordance with Regulatory Guide 1.69.
2.5.4 Radiation Monitorina The radia tion monitoring system for the VR/ SS includes: area gamma radiation monitoring and airborne particulate monitoring for personnel protection, building vent effluent monitoring for a s se s sme n t of radioactive releases to the environment, and process area monitoring for selected equipment cubicles. Liquid e f fluent s w ill be discharged in accordance with Section 5.1.2.2 Water Quality.
Fixed area radiation monitors and airborne particulate monitors are located in areas occupied by personnel during normal operations and maintenance where changes in operating conditions or equipment failure coul d re s ul t in significant increases in
. exposure to personnel, i
2-17 e7_ --.- - ,yn-. . . - - - - _, - - - . - -
SQNP The buil din g vent e f fluent monitor provides continuous monitoring .
and quantification of radioactivity in effluents released to the environment in a ccordanc e wi th the requirements of NRC Regulatory Guide 1.21. The capability of grab sampling of the effluent is also provided.
Provisions a re made to enable smear surveying and radiation monitoring of each proce s sed wa ste storage container before storage or loading on a truck.
2.6 Quality _ Assurance To ensure confidence in the VR/SS to perform as intended, a quality assurance progr am will be established and documented. As a minimum, this program w il l conform to the guidelines of NRC Re gula tory Guide 1.143, and w ill be incorporated in addition to the codes and standards requirements listed in Table 2.8-1.
2.7 Electrical Reauirement_s The VR/SS f acility will be provided with electrical power supplied from a 16 1/6 .9 kV substation located in the transformer yard south of the turbine building.
2.8 Eautement Codes All VR/SS equipment is designed, procured, constructed, and
- inspected in accordance with the codes and standards identified in Table 2.8-1.
2-18 .
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TABLE 2.1-1
. RADIONUCLIDE DISRIBUTION IN INFLOW WASTE STREAMS Concentrated Spent Trash Total Isotope Liquid (uCi/yr) Regenerant (uCi/yr) (uCi/yr) (uCi/yr)
Br 84 1.3x10j 2.2x10f 35x10l Rb 88 3.6x10 2 2.7x10 2 6.3x10 3 Rb 89 7.3x10 9 1 3x10 9 5.3x108 7 1.4x10 I 131 1.2x10 1.7x10 7 2.5x10 6 I 132 7
4 9x10 8 1.0x10 1.1x10 6.0x1078 7
I 133 1.3x10 4 3 9x10 4 1.7x10 5 I 134 5.2x10 1 3x10 7 7 7.7x106 1.7x10 8 I 135 1.1x10 8 5.7x10 7 6 cs 134 8.tx10 8 2.4x10 4.4x10 6 8.4x10 8 7 1.2x10 cs 136 1.1x10 1.1x10 8 1.6x10 6 cs 137 4.0x10 94 1.2x10 4 3 2x10 4.1x10 94 ca 138 3 0x10 6 2.2x10 5.2x10 7 7
Cr 51 1.5x10 6 7 3x10 5 7.4x106 Mn 54 2.8x10 4 7.1x10 4 3 5x10 5 Mn 56 2.2x10 6 9.8x10 5 1.2x10 6 Fe 59 2.2x10 8.4x10 6 3 0x107 co 58 6.6x10 76 2.2x10 5 4.2x10 7.0x106 5
Co 60 2.9x10 6 6.9x10 5 4 3.6x10 6 Sr 89 8.7x10 5 .0x10 4 5.9x10 3 9.2x10 5 Sr 90 4.4x10 4 1 3x10 3 1.6x10 4.5x10 4 Sr 91 1.8x10 6.0x10 4 2.4x10 5 5 4.5x10 4 Y 90 4.4x10 4 1 3x10 3 Y 91m 1.2x10 1 9x10 5 1.4x10 7 7 Y 91 1 3x10 5.9x10 2 1.4x10 2 Y 92 0 5.2x10 4 5.2x10 6 6 1.8x10 2
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Te 134 1.7x10 1.1x10 8 6 2.8x10f Ba 137m 3 7x10 1.1x10 3.2x10 3.8x10 6 5
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4 CODES AND STANDARDS Welder Design and Qualification Inspection Equipment Fabrication Materials i and Procedures and Testing Pressure Vessels ASME Code ASME Code ASME Code ASME Code Section VIII, Div. 1 Section II Section IX Section VIII, Div. 1 Atmospheric Tanks ASME Code 3 ASME Code 2 ASME Code ASME Code 3 Section III, Class 3 Section II Section IX Section III, Class 3 or API 650, or API 650, or AWWA D-100 2 or AWWA D-100 2 0-15 PSIG Tanks ASME Code 3 ASME Code 2 ASME Code ASME Co.te 3 Section III, Class 3 Section II Section IX Section III, Class 3 or API 6202 or API 6202 g E
o lleat Exchangers ASME Code ASME Code ASME Code ASME Code b Section VIII, Div. 1 Section II Section IX Section VIII, Div. 1 F and TEMA i'~
Piping and Valves ANSI B31.1 ASTM and ASME Code ANSI B31.1
' ASME Code Section IX Section II l
Pumps Ma nu f a ctu re rs ' ASME Code ASME Code ASME Code 3 l
Standards 4 Section II or Section IX Section III, Class 3; Manufacturers' (as required) or Hydraulic Institute Standards i
- 1. Manufacturers' material certificates of compliance with material specifications may be provided in lieu of certified material.
- 2. Fiberglass-reinforced plastic tanks may be used in accordance with appropriate articles of Section 10 of the ASME Boiler and Pressure Vessel Code for applications at ambient temperature.
- 3. ASME Code stand, material traceability, and the quality assurance criteria of Appendix B to 10 C.F.R. Part 50 are not required. Therefore, these components are not classified as ASME Code Class 3.
- 4. Manufacturers' standard for the intended service. Ilydrotesting should be 1.5 times the design pressure.
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m _ _ . _ _ _ _ _ _ _ _ . _ _ A.
SQNP This figure corresponds to AECC drawing number 1193002 Sheet 10 of 12.
In accordance with'10 CFR 2.790 paragraph (b), the information contained in this drawing is judged to be proprietary by AECC. This figure has been submitted by separate letter.
i i
SEQUOYAH NUCLEAR PLANT RADI0 ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM VOLUME REDUCTION P & ID'S ~
FIGURE 2.1- 18 _
2-38 -
. SQNP This figure corresponds to AECC drawing number 1193002 Sheet 11 of 12.
In accordance with 10 CFR 2.790 paragraph (b), the infonmation contained in this drawing is judged to be proprietary by AECC. This figure has been submitted by separate letter.
l l
l SE000YAH NUCLEAR PLANT RADI0 ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM l
l VOLUME REDUCTION i P & ID'S I FIGURE 2.1-19 _
2-39
- , . - - y _ m ----
SQNP This figure corresponds to AECC drawing number 1193002 Sheet 12 of 12.
In accordance with 10 CFR 2.790 paragraph (b), the information contained in this drawing is judced to be proprietary by AECC. This figure has been submitted by separate letter.
4 SE000YAH NUCLEAR PLANT RADI0 ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM VOLUME REDUCTION P & ID'S '
FIGURE 2.1- 20 2-40
i
- SQNP This figure corresponds to AECC drawing number 1193003.
In accordance with 10 CFR 2.790 paragraph (b), the information contained in this drawing is judged to be proprietary by AECC. This figure has been submitted by separate letter.
SE0V0YAH NUCLEAR PLANT RADI0 ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM VOLUME REDUCTION P & ID'S FIGURE 2.1-21 __
2-41
REFERENCE:
Al g
- SYMBOL I
ITEM
@ MOUNTED 0
@ INTERNALL Q LOCALLY M Q AUTO PERM N GATE VALV Q ROTARY PL g SINGLE AC h THREE-WAY T HAND ACTU FLANGE h
& CHECK val FOUR-WAY h FILTER WI MAJOR PRC AUXILIARY
-*-+- PNEUMATIC ELECTRIC
-*-*- CAP I LL AR'1 LL HYDRAULIC w SONIC SIC A.S. AIR SUPPL F.C. FAIL CLO F.O. FAIL OPE:
- DIRECTIO'
) CROSS-0V A DIFFEREN i E29 CH EMIC AL ROTARY P DOUBLE A 242 N GATE VAL l M ROTARY F OG FDUCTOR Opt:] PRESSURE
ISI Y32.20 INSTRUMENTATION
- AND IDENTIFICATION EXPLANATION
- CONTROL CONSOLE SEQUOYAH NUCLEAR PLANT
' PANEL MOUNTED JUNTED lSSIVE SEQUENCE CONTROL-INTERLOCK 7
fG VALVE TING CYLINDER SOLEtiOI D val.VE ATOR ff 60L EN01D val VE Til MANUAL DRAIN EESS Il0WS PROCESS ILOWS SIGNAL SIGNAL TUBlf4G (IlllED SYSTEM)
S IGNAl jf4AL Y
.l D 01 ll0W
SE C0 DRAWING NUMBER D17467, Sheet 1 JMP IING CYl INDER l - NORMAL 1Y CLOSED SEQUOYAH NUCLEAR PLANT RADIDACTIVE WASTE VOLUME REDUCTION UG V Al V! - NORMAL l Y C L OSF11 AND SOLIDIFICATION SYSTEM SOLIDIFICATION SYSTEM I
P & ID'S CON 1R0! VAIVl WITH INDICATOR FIGURE 2.1- 22 ,
i
Y I
I .
/
. TO RAC VENT
, _ _ _ __ __ __ __ r --
L w i
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gi l
es/'b f,;
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> 'y JL STORAGE TANK B
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% \ b
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'T-
, 7 *'-
w 6 .L
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- WATER, LEVEL ) < W -A j ,5p , w?r i s.'.Y. g . 's 50 LIDS' LEVEL
,6 <:iiW ,- . MfF AGITA'OR e e- f SEAL WATER DRAIN
-A _3 I 5000 GALLON 1r I S'ORAGE STATION A c t u'/. A GAS -
'HAWJ[j A 5 RF .5Ukr (V'efkUL -
WAt%E S ,i c,6 qrn , 1, ( F. C .
LOAM U ' '
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[HAlN
. _ 3 ; -- -- - - --
I SEQUOYAH NUCLEAR PLANT I IOACTIVE
) )
TO AECC RESIN FEED kSTEM __
PUMP SS-6 l ,
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Y
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LUB RIC ATING / SE AL i cmcutArm Am sa m ER Pt w PUMP STATION qr WATER SO PSIG O FLOW NOMIN A L -. - -- - . . . -
N/
TO FLOOR DRAIN tr Y SE Co Drawing Number 017467, Sheet 2 SEQUOYAH NUCLEAR PLANT RADIO ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM I
SOLIDIFICATION SYSTEM 2-43 P & ID'S FIG URE 2.1-23 i
m SEQUOYAH NUCL x
/
TO RAOK VENT Sr L
rRQrc I
l' g
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) p:~l '
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)
SPENT RESINS
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MSTE E11BSYST EM '
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, [HAIN 4
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)
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~~
WATER 50 PSIG UNION
~' -- -- -- -
O FLOW NORMAL TO FLOOR DRAIN V
1F SE C0 DRAWING NUMBER D17467, Sheet 3
)
l SEQUOYAH NUCLEAR PLANT RADID ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM i
SOLIDIFICATION SYSTEM P & ID'S FIGURE 2.124 g
SONP This figure corresponds to SECo drawing number LD18183 Sheet 3.
In accordance with 10 CFR 2.790 paragraph (b), the information contained in this drawing is judged to be proprietary by SECo. This figure has been submitted by separate letter.
~
l l
SEQUOYAH NUCLEAR PLANT RADI0 ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM SOLIDIFICATION SYSTEM P & ID'S FIGURE 2.1-25 2-45 L
SONP This figure corresponds to SEco drawing number 17467 Sheet 5.
In accordance with 10 CFR 2.790 paragraph (b), the information contained in this drawing is judged to be proprietary by SECo. This figure has been submitted by separate letter.
/
-9 2
l 1
SEQUOYAH NUCLEAR PLANT RADI0 ACTIVE WASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM SOLIDIFICATION SYSTEM P & ID'S FIGURE 2.1-26 .
l 2-46 .
- SONP c
This figure corresponds to SECo drawing number LD18183 Sheet 2.
In accordance with 10 CFR 2.790 paragraph (b), the information contained in this drawing is judged to be proprietary by SEco. This figure has been submitted by separate letter.
1 i
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SO LIDIFICATION SYSTEM 2-49 P & ID'S f' FIGURE 2.1- 2 9 i
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SEQUOYAH NUCLEAR PLANT l RADIDACTIVE WASTE VOLUME REDUCTION
- AND SOLIDIFICATION SYSTEM "
SOLIDIFICATION SYSTEM P & ID'S '
FIGURE 2.1-30
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SAFE SHUTDOWN EARTHQUAKE DESIGN RESPONSE SPECTR A -
HORIZONTAL MOTION FIGURE 2. 2 - 2 -
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SQNP
- 3.0 FACILITY OPERATIONS 3.1 Volume Reduction Swstem After sufficient waste has been collected, the operator will determine which mode of operation he wishes to use. These are:
(1) drying of evaporator concentrates and/or spent regenerates; (2) simultaneous drying of evaporator concentrates and/or spent regenerates and incineration of dry active waste sad /or contaminated oils; (3) incineration of the dry active waste and/or contaminated oils only; or (4) bypass of the entire WR system.
The first operational mode consists of fluid bed drying of liquid wastes. The evaporator concentrates and spent regenera te s which contain typically 7- to 25-weight percent dissolved solids are pumped from the concentra ted liquid wa ste storage tanks to the venturi scrubber preconcentrator (S-2) by the wast e pump (P-4) as shown in figure 2.1-13. The feedrate to the dryer is automatically controlled by temperature-sensing device s which control the speed of the feed pump. The heat from the drying process w il l be used to preconcentrate the feed to 25- to 28-weight percent. The liquid feed to the drye r will be used as the S-2 off gas scrub solution.
The dry granular bed particles from the dryer are pneumatically i transferred from the fluidized bed to a product storage hopper.
In addition, the over-head gas passes through the gas / solids cyclone wh er e the fines are r emove d and mixed wi th those from the incinerator (R-3) and discharged to a product storage hopper.
The optimum operating mode is for the dryer and incinerator to operate simultaneously. In this mode, the waste heat contained in the incinerator off gas stream is u t il iz e d in the preconcentrator, therefore increasing the liquid input flowrate from the concentrate liquid wa ste storage tanks to the fluid bed dryer sy st em. The scrub solution used to scrub the process off-gas also consists of the incoming liquid wa ste s. After preconcentration, these wastes are then processed in the fluid bed dryer to anhydrous, free-flowing salts. If this is an initial system startup or startup after maintenance has been performed, inert nonradioactive bed ma t erial will be fed into the dryer and incinerator vessels. If used bed material is available, then it will be reintroduced into the vessels as needed. The operator then turns on the electric heating system and blower for both volume reduction subsystems and s tabil iz e s the temperature profile over the system. He then initiates combustible feed to the incinerator and liquid feed to the dryer.
Bags of dry active waste are passed through a metal detector to prevent metal objects from accidentally entering the shredder.
3 -1
SINP -
y; s
u -
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/
If metal objects are detected, tai bA4p are either set aside for ,
compaction or aEe hand sorted beforg Y16cing t h em ';1 n the ~
shredder. Acceptable bags of dry activ e wa ste are'then fed into the shredder and conveyed by way of a trash eleva&ve"(G-1) to trash hoppers ( B-3 A an d H-3 B) . .g ,&
. s q.s All i nc i n e r a t o's, f e e dr a t e s a re manually deforminodqhy the '
operator. The,feedrate'is then set into the controller f o r-continuous metering in the predetermined flow of contamina t ed oil when processing this type of waste. The dry active wa st e is pneumatically fed at a controlled rate to maintain process '
~
temperatures. .
~
After coollag, the s off gas from the incinerator is ducted to.the gas / solids s e p a, r a t o r (S-1) where essentiallyg all of the ash-is removed from thg,af,s stream and dropped int 9 A product storage hopper. The inder of the ash is removed from th e off-gas stream by the r scr e s t'hb s solution in the venturi scrnbher and then is sent to the fluid bed dryer for processing. The jamaining off-gas passes through a second scrubber and HEPA/ch'arso41 filter before it is discharged to the building ventilation system.
The process w il l be simil ar when only'the dryer portionior incinerator portion la used individually. In this mode, either' the evaporator concentr. ate and/or spent regenerate wast e in the _
~
concentrated liquid wa ste storage Labks can be use'd.,as the ~
incoming-liq 71 d w a s ty, s t r e am to the ventari scrubbetr '
preconcentrator for the purpose of s c rubp'id g the off-gas froh the ,
gas / solids ~ separator v The concentrated Ilq'do; produped in the .
venturi scrubber preconcentrator is pumped'bac1 g t g .th e concentrate liquid w a st e ctorage tank forNfuture processing'by '
the fluid bed dryer. .
'[
3.2 S o l i d i fdc ajli on' S y s t og / [, I^ s ,
- & s,
'. v . ,
s The solid w s ec o produpts$ produced in are collected in the paodyct storag#~aopper the 2olume and reduction,ps;ocass solidified'is . ! '-s.
accordance w i th' th e pg o ce s s control pro' gram. The op e r a t o,e .
j initiates the (1111 e g' p r s.c e s s of 55 gallon drum s wi th the binder, j an internal pixe$, a n 6.- A A/ aCditives-to be used in accordance .
l with the procesa control pri g7 am. The pr e f ill e d drums containing(
\ *' ;
binder are then transferrqd from the polymer f il l ing station ts the dry product,druyming sta tion wi th ,A crep.%, The drum is '
i loaded into-tbe' process' chamber wit) the aid of remote television N monitoring and a grid location system.* After the drum is inside '
the processing' station..the operrtor initiates the automatic uncapping, filling, m4liug,'and fec'sp'pfng pts;ess. ~
- The drum containing waste is then removed f tM'; the paoci(&fng station by ,
7 the opera t or wi th the overhead c r a n h . i f h e, d r u m is pogitioned on ' y'7 the radia tion moni toring and, weighing stetA9n.* +7ho w a3 6ht'and ,
dose rate of the drum,are recorded by the s;y;yator and registered p r q .
4 , g 3^2
, .%- ~ -
\ r '
s
, '+ ,' ,
N
- 8
\ m
e SQNP
, in the ca dwa s t e log book and on the storage tag. The tag is then placed on the storage board to indicate the loca tion where the drum is to be stored. The drum can then be picked up and placed in the drum inspection station if de em ed ne ce r sa ry or placed directly into the proper storage location in the VR/SS bu il din g .
When a l oa d o f solidified S5 gallon drums has been produced, they may remain in the VR/SS storage location for decay or be transported either to a licensed nuclear wast e disposal f acility or stored temporarily on site. In either case, when transport is necessary, the operator w il l load the shipping vehicle by use of the t el evi sion moni t or and guidance grid. After all necessary shipping papers and radiation surveys are completed, the shipment w ill be allowed to leave the VR/ SS building.
The resin wast e will be fed into 5,000 gallon resin tanks where samples can be taken and pH a dj us tment s are made. Then the waste w ill be transferred to the SOO gallon decant t ank a nd w a s t e-to-cement ra tio verified. When the proper ratio has been verified, the wast e w ill be metered into a S5 gallon drum containing the proper amount of cement and any additives deemed necessary by the process control program. The 55 gallon drum will then be prepared in the same manner as the drum containing volume reduced waste except cement w il l be used as a binding agent. After processing, the drum w ill be removed from the processing unit and placed in storage in a simil ar manner as that described for v ol um e reduced solidified wa s t e. Evaporator concentrates and spent regenerates can be processed in a simil a r manner.
3.3 Bulk _ Resin _ Processing The ca ra bil i ty will be provided to package and dewater bulk
^
quantitlea of all radioactive spent resins for eventual storage or r er ov al from the plant. Resin slurry will be sluiced from the epent resin storage tank to a licensed shipping container
, consisting of en inner disposable liner w ith an outer reuseable shield. When the container is nearly full, automatic l ev el control valves are closed and the water is removed through internal f il t er s. The fill-and-dewater process is repeated until the desired amount of resin is transferred. The water is sent to a collection tank. A pump is used as required in the dewatering proces2 to meet f re e-st anding w a t er limits at licensed disposal e f a cili tie s. Flush connections w ill be provided to flush lines
,s when sesin transfer is complete.
.I s
s
-~ . s
] p? r t- -
,% x f -
% =
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y
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, p 4 '. 0 R ADIOLOGI C AL ASS ESS MENT / ')
$ j, 4.1'~R ttigloalcol Considerations ,
A f'! A ra nt ological assesament has been performed for the[SQNP site to E fi ratisate potential impacts from the operation of a'VR)SS/'The gaj or medium for potential radiological exposure is via the off-
~ :ta s effluents.
No direct liquid effluent discharges to the enqironment are planned from the VR/ SS: :y st em. The f oll ow ing retential pathways to man were analyzed for individual and prJ pu l a t i on exposure to gaseous effluents: (1) etternal radiation from radioactivity in the air and on the ground; (2) inhalation;
, and (3) ingestion of beef, vegetables, and milk. The estimated routige gaseous effluent r el,e a s e s contained in Ta bl e 4.1-1 w e r e us e d to cal cul at e radiological exposures to , individuals at points P, of p o t q n t.i s1'm a x im um e x po s ur e'. - Lo c a t i on s. f or potentis) maximum
[.
'l
' e x p o e n r e , a r's contained in Table 4.1-2 for the SQNP site. The dose toh th e population is based on, population estimates .i n the,16 compass' sectors for t on 'dow nw ind ' di s t a n c e s out to fifty miles.
r Doses to critical organs were estnulated using the dose factors ano math odol ogy contained in NFC Rep.nlatory Guide 1.109, Revision 1 and NUREG/CR-1004 with certain e x c e'p t i o n s aa f oll ow s :
f.
- r. . . Inhalation doses are based on average individual inhalation ratesi~of 1,400; 5,500; 8,000; and 8,100 as/y, for anfant, ch il d, teen, and. adult, respectively.
g
/ , 2. Po s e s to air are calculated usfag averagefbeta and gamma energies per decay from the TV A nuclide data l ib r a ry .
- 3. The beef sad milk ingestion pathway doses account for actual a n i m a l' feeding factors. A feeding factor ( P# ) has been defined as that fraction of total feed intake an animal s' consumes that is from fresh forage.
> ,e
- 4. Dose calculations for the beef ingestion pa thw ays w er e made for individuals con 4uming meat from beef raised on their (s property. The n o rm el processing route fa for an individaal to slaughter the beef animal, package and freese the meat, 4 and then consume the meat during approximately the next 3-month period. R a d i r,a'ct i v e decay during t h e ~3 -mon th period is c al cul a t e d by: g ,
t l ,
1 90 o/
[ exp(-A it)dt = 1 - e r.'p ( - A i 90) 901 t
}
4-1 l
r . -_
SQNP where A1 is the radiological decay constant (days-2) t is time (days).
This term is multiplied into equation C-14 in Regulatory Guide 1.109. If the beef animals are sold commercially, then individuals would not be exposed continuously to meat from their farm. Consequently, r a di ol o g i c al do se s would be expected to be l ow e r .
4.1.1 Neteorolony Calculations of atmospheric transport, dispersion, and ground deposition are based on annual-average, ground-l evel me te orology, consistent with the straight-line a i rf l ow model discussed in NRC Regulatory Guide 1.111 (Revision 1, J uly 197 7) . Atmospheric releases from the facility are assumed to be continuous.
Estimates of the normalized air concentrations (X/ Q) and the normalized deposition rates (D/Q) are listed in Table 4.1-2 for point of interest locations, and in Tables 4.1.1-1 for population sector annuli.
All doses related to deposition pathways (ground exposure and -
food inges:fon) are estimated using dry deposition. Calculations of wet deposition based on a washout model and recommendations of Engelmann8 indicate that wet deposition is not a significant j portion of total deposition.
4.1.2 Population _ Distribution Population doses were based on the current U.S. population distribution of:
Catenory Ames JA)* Fraction Infant A(2 .034 Child 21A(13 .211 Teen 131A<19 .134 Adult 191A .621
- e.g., someone who is 1 year, 11 months of age is an infant, while someone who is exactly two year s old is a child.
Population data are contained in Table 4.1.2-1, i
4.1.3 Dose E_ stimate _s l
Table 4.1.3-1 gives maximum estimated individual doses due to
, operation of a VR at SQNP and Table 4.1.3-2 gives the l estimated population doses. As can be seen from these tables,
( the maximum calculated air dose (immersion) at the site boundary 4-2 ,
i
SQNP
- from gaseous effluents is 8.1 x 10-8 mrad /yr for SQNP. The maximum calculated individual doses were found to be for individual s with home-use gardens. These doses a re 0.32 mrom/ yr for SQNP. All doses are well within the applicable regulations.
Further, population doses from VR operation are estimated to be 0 .17 m a n- r o m/ y r for SQNP. For a population around SQNP of about 1,100,000 this dose can be compared to doses from natural background of about 1.6 x 108 man-res/yr for a natural background component of 145 mres/yr.
4.1.4 _ Cumulative Immacts For the purposes of determining compliance with 40 CFR 190 limits (25 aren/yr), impacts from all nearby fuel cycle facilities must be summed. The only impacts from nearby fuel cycle facilities w ill be due to the operation of SQNP (FES: 5.6 area /yr) and possible onsite low-level radioactive waste storage modules (< 1 arem/yr) which are predicted to result in a combined dose to the maximum individuals of about 6.6 mres/yr. If these doses are summed wi th those calculated for VR operation (0.32 arem/yr),
then the cumuistive doses are found to be about 7 aren/yr for the SONP site. These doses are below the 40 CFR 190 limits.
- 4.2 Incrosents! Occonstional Exnosures 4.2.1 Exoosure From Routine Onorations k
The occupational exposure to be expected from the operation of this facility depends on the activity of the material being processed, the design of the f acility, and the operational and maintenance requirements of'the equipment. The facility design obj ectives outlined in Section 2.5, ' Radiation Protection and l ALARA,' ensure that the design of the f acility will be such that ALARA principles w il l be observed. In addition, the process equipment is designed so that components containing significant amounts of radioactive material can be remotely drained and flushed (or s im il a rly treated) prior to pe rf orming mainte nance on these components. The compa r tm ent aliz a ti on of the f acility provides assurance that exposure from other components during maintenance w il l be minimal. Exposure due to operational requirement s will be minimized by a high degree of automation of the proceas equipment. Manual operation of process valves and process surveillance (e.g., reading of process instrumentation) w ill be carried out from areas of l ow radioactivity whenever possible.
The measures outlined above give assurance that the occupational exposure resulting from the operation of this f a cili ty will be as low as is reasonably achievable.
d 4-3
Table 4.1-1 SQNP VR RELEASES FROM PROCESS OFFGASES EXCLUDING RESINS VR RELEASES FROM PROCESS OFFCASES EXCLUDING RESIN NUCLIDE RELEASE RATE (CURIES / YEAR) 1 CR 1 7.4Cr-05 2 ps."54~ ~ ' ~ ~3 5CE-0(? --
3 "PI-56 1.20r-07 4 F C -L o 3.00i-CE 5 CD-5N 7.10'.-05 6 C0-60 3 6CE-06 7 ER-84 h.60C-09 E AH-PA 6.30E-CS 9 P F. - P 4 1 3 0F-0 9
~ 10 SC -P 9 9.70L-C6 11 LR c0 4.50E-C 7 12 SR -91 2.40T-0*
,_ - .1 3 - ,Y-90 . , q
..--.--- 4.6 0 f-0 7 15 Y-91 1.400-05 ^
16 Y -92 5.20f-10 17 7W-Q! 1. ' r r . o r, 16 f:" ': ', H 6. l, L f - 3 C -
13 ti - s ' 2.?r"-ci
?O '.-e~~--'3.g,-t3 21 10 '9M 9.700-C4 "
22 TC-99 1 6CE -11 .
23 ff-132 5.7CE-05 - -
24 I-131 3.50E-03 25 1-132 1.500-04
--" 2 6 I -13 3-~~~ 4.30C-04 27 I-134 3.300-07 28 I-135 4.30f-05 29 CS-134 P.40C-04 30 CC-135 1 20: 31 CS-137 4.1CE-03
-3 2 ~C O -13 8 ' 5 3 0 E - 0 e ' ---
33 4A-140 3.F00-er 34 L A -l ' O 3.'Or.og 35 CE-144 a.3 00-C ?
36 PE-144 2. 3 C r -0 7 1.lE-02 4-4 -
Table 4.1-2 4
SQNP VR RELEASES--NON-RESIN WASTE APPENDIX I TYPE EVALUATION I
Pu tt47 n ! % T ANCE' ~~E'L Eilhi 10fi "-'~Ull: DVER-Q ~ ' '~'0$0l/E R10'
$ECTOR (9) Itu i S / t1*
- 31 (1/Mo*2) 1 4.AUD $1TE 80ut:0ARY II 950.
7 L Ala0 SITE BUU'lDA AY
..-6. 6 19E-06 NtiE . 7260. -6. .1.2)E-08 2.1?E-06 5.2dE-09 1 L A N D S I T E 4 i AI.0 S I TE. 8:)UPD A eV G r10L A R Y_. _ _UC__..___ __1310.__
._-6. _
.2.671.-06 Et'E 16B0. -6. _..._ 6.3)E_-09_..,
5 Lt.ND SITE 800rlDARY. .E. 1570. 1 2PE-06 2.64E-09 6 LAND SITE B00h0AAI -6 B.31E-07 ESE 1450. -6. 1.46E-09 7 tt.t.D $1TE 800NUARY SE , 1460 9.20L-07 1 5dE-09 9 LAND $1TE B0dtt0ARY -6. 1.07L-06 SSE 15$0. -6 2.41E-09
__ 9. LAND.51TE_b2VI:DAdY S- 1520... 1.55E-06 3.23E-09 10 t e r.0 SITE 800*43ARY SSW _-6._. .. 2.81E-06 ._. ._ 4. l s E-0 9_
11 LtAD SITE 000f;UARY . 1840. -6.
.SW 2470. 5.26c-06 9.20E-09 12 L AND SITE 807ttuA4Y -6. 1.58E-06 L. S W 910. -6 2.63E-09 13 L AND SITE 80ut1DA8Y . tl 670. 3.h6E-06 3.86E-09 14 L AND SITE 800'!0ARY -6. 4.28E-06 wt4W 650. -6.
3.7*F-09
.15 L AtJD SITE.39&DARY ttW___ 2.93E-06 2.44E-09
)4 LAND IITt 07Ut!DAIY 4 $ 0._ _ . _ -6,._. 3.426-06 17 RESICit4T,CARDEtt NNd 730. -6 .__.3.67E-09
. f4 1344 4.74E-06 6.59E-09 18 RESIDEi47,CARut*1 O. 3.64E-06
.19 RES!0Ef 4T,CARDEN (4ME PS12. G. 7.32E-09 1.56E-06 3 6'eE-09 20 WESIDEt4T, GARDEN,hEEF . . . li E . .. . 3438 55 EP:E P187 . 1 10E-06 2.32E-09
.21 PESIDEtLT 12. 8.53L-07 22 RESIGENT
_L 1812. 0. 1.79E-09 ESE 1812.
..._ _6.65E-07...., ._1.loE-09..,
21 RESIDENT 43. 6.$5E-07 d
24 nESIGENT
___SE 1719 O. 1.11E-09 SSE 2250. 8.24L-07 1.53E-09 25 RESIDEtT,CARDEll. 24 8.6tE-07 24 #ESIDEtti
.$ 7375. O. 1.74E-09 S S W' 2250. 1.490-06 2.0*E-09 O. 3.a8E-06 k 2 7 . 8 E 410 E r.si _ ._ __.
28 RE513Ef47 SW WSW
$ 9.i_ ..___ .. 0 . _ _ . .1.20E-06 6.57E-09 1.93E-09...
21 RESIDEUT,GARDEli 10b7 17
. _ _ . u . . ._ ,. . 9 3 8 . 6 2.52E-06 2 . 9 't E -09 33 PiS IDEt.7,GA* Dele 2.65E-06 31 RESIDENT,GARDEtt ut'W 1812. 12 2.15E-09 t4W 1186. 6.70E-07 4.71E-10 37 RESIDEt4T .
- 12. 1.440-06 tit.W 781. O. 1.40E-09
_ 31 GAR 0Etl. 1_ 4. 30 fi-06 5.90E-09 34 GAa0EN 2 6 5 6,_.__
35 GARDiff ESE 2031. 12.. . _. _3.72h-07. . . ,_6 . 0 3 F - 10.__
30.
_,$E 5.51E-07 9.16E-10 36 GARDEN, BEEF ._ 7062. . O. 6.23E-07 SSE 7344 30. 1.30E-09 37 GAFDEN 8.15E-07 3R GARotti SSW 7750. O. 1.62E-09 SW 3438 2.866-06 4.67E-09 39 GARCEIL__. O. 9.68t-07
_. 3;S y 1067 17 1.49E-09 40 GARDEN t4t:W 1875. 2.82L-06 2.91E-09 41 #EEF 15. 1.17E-06 47 mEEF ut i 2600. 2. 1.41E-09 IJ E 3438 1.76E-06 4.16E-09 43 REEF C. 1.10L-06 44 REEF E P187. 12. 2.32E-09 i
FSE 3125. 5.00E-07 P.40F-10 f
45 N E F f _ _. 55. 2.c5E-07 46 REEr 5{ 2.6 5 6. . _ __._._C 5 . , .. 4 . 2.1E -07 4.40E-10 l S 6553. 46 .. A ,8 6E:10..
47 NEEF 3.44L-07 4a REEF W 730. O. 3.5$E-10 l WSW 70$2. 4.03L-06 3.41E-09 49 REEF 12. 1.06L-06 50 8EF' Wt4W 700. O. 1.01E-09 14W 668. 2.70t-06 2.22E-09 St.PEEF._ O. 3 22L-06 fit W 1524. 3.43E-09 57 HILM COW ADULT 2.___. 1 60L-06 1. 9 9 E -0 9..,
53 MILK COW ADULT i.
ut:E 4219. . _. _ O. 6.50e-07 1.00t-09 54 MILK COW ADULT 4531. 6. 7.77L-07 I.E $625. 61. 1.5/E-09 55 31LK COW ADULT SSW 1514. S.40d-07 9. 7 3 E -10 O.
56 MILK COW ADULT httW 1. 's3 E-0 6 2 . 9 '. E -0 9 l 57 utLK COW ADULT 1815. 18 6.30t-07 f4W 2031. 6 4.44E-10 6.4tt'-07 5.83E-10 l
t i
l e
4-5 l
.o e e m'i ; 3
- # . I i
i
^
TABLE 4.1.1-1 .i e
! i .
- SQNP - LLRW VR EFFLUENT RELEASES ' ' l, I :
l
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- .* N N.e .ee g.eti.eN.e N
O 8 B I 81 8 erI It 14 aas 4 4 O
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- sN N me.se A Pt ers .2 P* 60 =e d # s=e N N P* 8'*
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.m nu as au ins 4 8fl O I O 8 888 Sjl til $10 $ 9
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l8 Se8 86I 4 8nu tot 64 til 9 8 9 5
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. TABLE 4.1.2-1 lI l '
l .c.,v, i
! ; 4 l
- SONP - VR EFFLUENT RELEASES g l i
' e POPULATION DATA _.
.! 1 -
I I -
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i i
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r= cj C age n r ra s e r: nn
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4
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Table 4.1.3-1 SQNP VR - ANNUAL INulVIDUAL DOSI:S FROM OFFGAS EFFLUENTS I ITI.Ul:!:T PATilWAY CUIDELINE* Po!!!T linSE Noble Cases y-Air dose 10 Max. Exp. 8.1 x 10-6 mrad /yr
-6 mrad /yr B-Air dose 20 Max. Exp. 6.9 x 10
~
Total body 5 Residence 3.7 x 10 ' mrem /yr
~
Skin 15 Residence 5.0 x 10 ' mrem /yr Iodines /
Particulates Liver 15 Real 4 -1 (critical organ) Pathway 3.2 x 10 mrem /yr p rffipynl o f _Tpyli nt /P rtit i c ol at t:_E;:ypsures (mrem /yrl Child Adult Vegetable Ingestion 2.9 x 10~1 1.0 x 10~1 Beef 5 ~
Ingestion 4.9 10 4.6 x 10-3 Inhalation 6. 7 x 10
-0 3.5 x 10 ~4 Ground -2 ')
Contamination 2.9 x 10 2.9 x 10~'
Total 3. 2 x 10 -l 1 3 x 10-1 AThese are the annual guidelines per reactor unit for nuclear generating stations defined by Appendix I to 10 CFR 50
- 1. Maximum exposure point is at 950 meters in the N sector.
- 2. Dose from air submersion.
- 3. Receptor is at 2,250 meters in the SSW sector.
- 4. Receptor is at 1,344 meters in the N sector.
- 5. Feef is assumed to be obtained from location at 2,600 meters in the !!!:E sector.
4-8 .
(" g e i
~
W z
u M
M Bone i3 Lrver CHILD TEEN A00LT TOTALS y CHILD TEEN ADULT 10 T 4 '.S INFANT 1hF4hi '
daadtpsgof g'.20E'-59~ '.iSE-09"4 7 77E-09 2.21E-08~3 55!-08'~ ~ 1.20E-097.49E-09~4.77E-09~2.'21 E-0 A ~ 3.55E-08 .c o ^.
7.78E-02 E "1 *4 2 63E-03 1.64E-02' 1 04E-02 4.83E-02 9 0JhI ~ 2 63E-03 1.64!-02 1.04E-02 4.83E-02 7.7t!-02 gS C r*
2 24E-03 9.75E-05 1 48E-03 4 73E-04 1 60E-03 3 65E-03 g M
11n4LAi!CN 1 10E-04 1 45E-03 i.45E-04 4.46!-03 M E a
3 37E-03 1.09E-02 3.3.'E-03 1 14E-02 2.F9I-02 2 69E-03 1.C4E-02 2 29E-03 7.59E-03 2 30E-02' k -f ,
g c0W PILK n 90 W 2.41E-C2 3 75!-02 0.0 R.62E-03 3 02E-03 1 61E-02 2 77E-02 o P2 sn tn u BEEF 1hGESTION 00 8.96E-C3 4.40E-03 5 24E-03' 1.m6E-03 9.40E-03 1 65E-02 @$ b O.0 5.39E-03 2 6eE-03 1.39E-02 2 20!-02 0.0 VEG IhCEST ICN '
..j.. g 4.31E-02 2. lee-02 1 00E-Os i.n!-01 5 4n-03 4.22E-02 1.a1E-02 s.30E-02 1 4,E-01 a w
rai u n.-aEn e.32E-03
.m ee O
Z 5
SQNP
. 5.0 ENVIRONMENTAL ASS ESSMENT 5 .1 Environmental Ino_ acts._of the Pronosed Action 5.1.1 Construction-Related Inonets i Construction impacts a s sociated with this proj e c t include fugitive dust, gaseous emissions, s il t a ti on, noise, socioeconomic, and potential impact on existing structures at Sequoyah Nuclear P l a n t ~.
5.1.1.1 Air Quality The VR/ SS f acility construction a ctivitie s will result in a temporary degradation of the local air quality. Air pollutants genera ted will primarily include: (1) fugitive particulate emissions from activities such as drilling and mixing concrete (in a batch pl ant ); (2) fugitive dust from carth excavation and grading, and wind erosion of disturbed land surfaces; and (3) pa r t ic ul a t e, hydrocarbon (HC), nitrogen oxide (NOx), and c a rbon monoxide (CO) emissions from fossil-fueled construction equipment and construction empl oy e e v eh icl e s.
Disturbed land surf ace s will be sprinkled wi th wa t e r, as ne ce s sa ry, to minimize fugitive dust em i s si on s . Baghouse f il t er s w ill be used to control particulate emissions at the concreto
( batch plant. Any open burning of debris will be done in accordanc e wi th all applicable regulations, and ther e will be no burning during times of an air stagnation advisory.
Overall, construction is expected to have a minor and transitory impact on air quality.
5.1.1.2 Land Use Inoscts The construction of the VR/SS facility as currently conceived w ill require approximately 1 acre of land, all within the SQNP
! reservation boun da ry. The proposed action i nv ol v e s no offsite I
land-use conflicts. The proposed action is compatible with the land-use pl an w ith in the SQNP reservation for the nucl ear plant and its support f a c ili tie s.
5.1.1.3 Siltation i
During construction of this facility, runof f will be drained in a manner that w ill minimize erosion and the amount of sediment
, reaching local bodies of water. Control of construction runoff l will be in accordance with practices developed by the Environmental Protection Agency (EPA) pursuant to the Clean Water Act (Guidelines for Erosion and Sediment Control Plannina and l
Implementation), EPA Environmental Protection Technological Series - EPA-R2-72-015, (August 1972). Applicable requirements l
l 5-1
SDNP designed to prevent pollution from this construction activity will be met. The existing NPDES permit w il l cover any -
construction-related runoff from the proposed action. With these precautions, construction activities are not expected to have a significant impact on water quality.
5.1.1.4 Noise No significant impacts are expected in either environmental or occupational noise.
5 .1.1. 5 Solid Waste There w il l be a small amount of solid wast e generated due to the construction of the VR/ SS f acility. Solid wa st es generated during construction will be h andl ed in accordance w ith applicable Federal, State and local regulations, and TVA policies and practices.
5.1.1.6 Sanitary Waste S an i t a ry wastes generated during construction will be h andl e d in a c cordanc e wi th applicable regulations. During the construction period, portable chemical toilets will be provided for use by construction personnel. ,
5 .1.1. 7 Cultural
~
On April 24, 1980 the Tennessee Stete Historic Preservation Officer c on c ur r e d wi th TV A's determination that construction of this proj ect would have no effect on any site either on or eligible for the National Register of Historic Places.
5.1.1.8 Endanaered and Threatened Species The propo se d proj e c t w ill not contribute to the further decline of any kn ow n populations of Federally listed or proposed endangered or threatened species, or result in modification or destruction of habitat considered critical to the survival of such forms.
5.1.1.9 Floodelsins and Wetlands The site for the proposed action is not located in a floodplain, nor is it expected to directly or indirectly support or encourage floodplain development. There are no wetlands which w ill be affected by the pr oj e c t . Therefore, the proposed action is in compliance with TVA policies on floodplain management and wetlands protection.
5-2 .
SQNP 5.1.1.10 Socioeconomic There is now and will continue to be ongoing construction at SQNP, and there i s manpow e r, housing, and services av a ilabl e in the area to fill the construction and labor skill requirements for the VR/ SS f acility. As a result of an adequate supply of manpower, no overall population increase is expected as a result of this construction activity, and because this plant is near an urban area (Chattanooga, Tennessee), no significant socioeconomic impacts are expected.
5.1.2 Operation of the VR/ SS 5 .1. 2 .1 Air Quality Operation of the VR is expected t o r e sul t in emissions from combustion of wa ste s in the incinerator /calciner subsystem.
Primary pollutants expected to be emitted include SO2, NOx, H C, CO, and particulates. For each of these, relatively small amount s will be emitted. These w il l be released through a stack that is at least 10 feet higher than the building. A semil quantity of other pollutants may be emitted, depending upon the composition of the waste material. Ra di ol o gi c al r el ea se s and
. their impacts are discussed in chapter 4.
Tables 5.1.2-1 and 5.1.2-2 give quantitative inf orma tion on
$t non r a di ol og i c a l air pollutants expected to be emitted by the VR. The emission rates given in Table 5.1.2-1 were taken at a discharge to a stack during actual prototype system process runs. The particulate emission rate wa s estimated using
' Compilation of Air Pollutant Emission Factors' (See footnote C of Table 5.1.2-2) for industrial / commercial refuse incinerators.
Pl anne d pa rt i cul a t e controls for the VR result in a conservative decontamination factor of 1 x 108 l TV A w ill obtain an air permit from the Chattanooga-Hamilton County Air Pollution Control Bureau for the release of nonradiological air pollutants expected to be released by the VR.
5.1.2.2 Water Quality The operation of the VR/ SS will generate small amounts of i
drainage which will be collected in sumps in the VR/SS facility.
l Radioactive and n on-ra dioa ct iv e draina ge will be segregated.
Radioactive draina g e will be pumped to +he existing liquid ra dw a s t e system for treatment, and nonradioactive drainage w il l be pumped to the turbine building sump for any necessary treatment and discharged after meeting applicable NPDES limits.
The capability to treat nonradioactive drainage as radwaste will he provided. Operation of the VR/ SS will not result in an additional NPDES discharge point. The physical and chemical characteristics of the VR/ SS drainage w il l be estimated, EPA will 5-3
l l
SQNP be notified of any changes to existing discharge streams r e sul ti ng from addition of the VR/ SS. .
5.1.2.3 Noise No significant environmental noise impacts are expected. Within TVA, occupational noise is controlled to meet the Occupational Safety and Health Administration (OSHA) guidelines for employee noise exposure.
5 .1. 2 . 4 Solid Weste Masanonent The Resource Conservation and Recovery Act of 1976 (RCRA) specifically excludes nucl ear material regulated under the Atomic Energy Act o f 1954, as amended (which cov er s LLRW) . Because the operation of the VR/ SS will result in no significant additional amounts of solid waste to be handled, other than LLRW, the proposed action does not have solid wast e management impacts associated with it. Should solid and hazardous wastes other than LLRW be generated, th ey would be managed in accordance with applicable EPA regulations for solid and hazardous wa ste s, and TVA policies and practices.
5.2 Unevoid_able Adverse Environmental Inoscts
~
There are no significant environmental impacts a s sociated with the construction and operation of the VR/ SS. During construction some siltation may occur and the release of small amounts of gaseous and particulate pollutants can be expected. No -
significant c umul a t iv e impacts have been identified.
5.3 Irreversible and Irretrievable Commitments of Resources Irreversible and irretrievable commitments of resources will include fuel oils involved in the construction of the proposed facilitie: along with materials used for the construction of the VR/ SS facility.
5-4
. . r s , s Prototype System Pollutant Concentrationsa Calculated Bnission Ratesb Frce Radioactive Waste Sources Contaminated Oil Trash, Resins, Liquid Concentrates Concentration (ppm) Baission Rate (lb/hr) Concentration (ppm) Bnission Rate (lb/hr) so2 <1 < 0.0137 <1 < 0.01395 g < 10 < 0.099 < 20 < 0.1981 co < 100 < 0.0006 < 100 < 0.00066 IC < 10 < 0.2064 < 100 < 0.0349 . .a T
G w
w
.L
- a. The pollutant concentrations for S0 2, NO x, CO, and HC were measured at the prototype system's incinerator discharge and converted to concentrations at the system discharge by incorporating the air dilution that occurs within the system. SO2 was measured downstream of the scrubber.
- b. Enission rates are based upon discharge concentrations and a discharge flow rate of 1,360 f t 3/ min.
- c. These data were collected assuming spent resins would be included as a waste input. Since resins are trot being incinerated, these emission rates re conservative.
=. _ _ _ - _ - _ .. - . -
J Annual Nonradioactive Emissions from Radioactive Waste Sources Trash, Resinsb Liquid Total Annual Emissions (iblyr).
Contat.inated 011 #
(1b/yr) Concentratesc (Ib/yr) 6S 50 7 61 2
868 917 No 49 x
3 3 Co <l 153 255 HC 102 negligible d
Particulates H
h a.
Maximum hours needed to incinerate contaginated oil (494.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />), based upon system charging to cap I
y 4.5 gallons / hour and an estimated 300 f t fyr of oil wastes. Y e "
b.
Since resins are not being incinerated, the annual emission values given are conservative. Y
( "
- c. Assures facility operation for 4380 hours0.0507 days <br />1.217 hours <br />0.00724 weeks <br />0.00167 months <br /> / year.
d.
Emission f actor for particulates (15 lbs/ ton vaste) taken f rom " Compilation of Air Pollutant Emission Factors," Third Edition, Publication No. AP-42, U.S. Environmental Protection Agency Research Triangle Park, North Carolina, February 1980.
Tons Wastes -
Liquid Concentrates 16,000 f t /yr - 552 tons /yr (assuming density of 69 lb/f t )
Combustible Solids - 180 tons /yr 3 9 tons /yr (assuming 60 lb/ft3 density)
Contaminated Oils 300 ft /yr -
Thl cons /yr i 6 Total emissions for particulates include a decontamination factor of 1 x 10 based on previous vendor information. i I
, 0 g
- .e
SQNP 6.0 ACCIDENT REVIEW 6 .1 General Close evaluation of the system revealed several accidents that could result in a release of radiation to the environment. These accidents were reviewed and are discussed below.
6.2 Process Accident Postulatiqn The accidents given considerati on were chosen after a review of the system. Little a ttention was placed on the mechanistic origin of the accident but rather on the result. There are several component s which re t ain radioactive material for a significant time and the failure of which should be considered.
These are as follows:
- 1. Rosin Waste Feed - Rosin slurry is held up in the storage tanks.
- 2. Dry Waste Feed - A volume of dry waste is present in the hoppers (B-3A, H-3B) and feed system. Each dry waste feed hopper (H-3A/B) contains 2,000 pounds of dry waste, consisting of approximately 95 percent nominal 1/2-inch particles, and 5 percent dust.
( 3. Bed Media Storage - Bed storage hoppers (H-4 and B-2) contain the used, cont amina te d, bed media. The incinerator and dryer bed materials are stored in transfer hoppers (H-4 and H-2),
respectively, only when the system is shut down.
- 4. Product Storage Hopper - A significant amount of activity can be contained in the collected product, i
- 5. Process Gas Fil t e r - A small amount of particula t e will be i loaded on the filters and the charcoal iodine adsorber can l contain iodine at any time.
l J 6. Scrub Solution System - The scrub solution in scrubber-preconcentrator (S-2) can contain a significant amount of a c t iv i ty in the form of dissolved solids, particulate, and iodine.
- 7. Process Vessel - The dry waste processor (R-3) contains bed l media which is contaminated after use and w ill contain s
! significant amount of activity. The process is designed to blow process ma terial s overhead rather than to accumulate them in the bed. Therefore, the bed will not contain a large i
quantity of process solids at any point in time, l
I 6 -1
SQNP
~
6.3 P r o c e s s __A s t i_d e n t_s Considered Three scenarios believed to result in the most severe consequences were further investigated. The product st ora ge hopper w as considered because of the potentially high radioactivity of the product; the scrub solution because of the potentially high concentration of dissolved iodine; the process gas f il t e r train because of the long-term collection of particulate before changeout is necessary plus the iodine in the iodine adsorber.
6.3.1 Loss _of Product _from__the Product Storsae_Honner The loss of product from the product storage hopper would result in spillage of dry salts and ash. Since a portion of the spilled material would be entrained in the air, the possibility exists for occupational as well as offsite exposure.
6.3.1.1 Detection _of the Accident If the hopper w ere to fail, several sy st ems would be affected.
The activity rel ea se would be detected by radia tion monit ors.
Shutdown of the sy st em w ould f oll ow by operator action.
6.3.2 Sulli of Scrub _ Solution The scrubber-preconcentrator (S-2) has potentially high concentrations of dissolved iodine. The scrubber (S-4) does not .
contain a significant amount of activity. Although there are 120 gallons of scrubber solution in the S-3/S-4 loop, the concentration of dissolved solids is only in 100-250 ppa range, as shown in Material Balance F l ow Diagram Figure 2.1-20.
During previous radioiodine tracer tests discussed in AECC Topical No. AECC-1-A, it was determined that iodine compounds are present in the sy st em. The amount of iodine held by organic compounds was found to be related to the quantity of oil in the dry e r feed; and could therefore vary with time depending on non-VR conditions. Essentially all iodine would be collected in the first scrubber preconcentrator; the final scrubbe r w ould be expected to collect almost no iodine. The remaining amount w ill pass on to be absorbed on to the charcoal adsorber. A scrubber-preconcentrator and the scrubber vessel could rupture or a pipe transferring high activity and possible volatile solutions could break, dumping the contents onto the floor. This pipe could be on the scrub pump (P-3) discharge side and could pump the entire inventory of the scrub vessels onto the floor.
6-2
4 SGNP 6.3.2.1 Petection of t h a___A c c i d ial Any loss of liquid in significant quantity from the scrubber-preconcentrator vessel or s crubber ve s sel would be detected with the tank level indicator and/or alarm, and the operator would shut down the system. Loss of scrub flow to the venturi in the event the operator does not respond will result in automatic shutdown of the system.
6.3.3 Blowout of the Process Gas Filter The process gas filter train provides long-term collection of particulate, plus holdup of iodine in the charcoal adsorber.
A po st ula ted accident, involving a pressure excursion of undetermined cause and subsequent rupture of the filter housing, could occur and result in the discharge of the contents of the HEPA f il t e r s and of the iodine adsorber.
6.3.3.1 Detection of the Accident This accident would result in a Icss of pressure drop across the HEPA filters that would be detected by the operator. This
, accident would also initiate automatic shutdown due to a high radiation level in the exhaust gas flow.
( 6.4 Process Accidents An s i v m ej The three assumed accident scenarios discussed in Section 6.3 were investigated using conservative assumptions to determine the one which posed the most significant radiological consequence.
This analysis revealed that the accident scenario of loss of product from the product storage hopper could produce the most severe consequences to in plant personnel, and blowout of the l process gas filters could produce the most severe consequences in j unrestricted areas. These consequences are discussed below.
I 6.4.1 Eyposure as_a Consecuence of an Accident The release of radioactive material to the f acility as the result of a failure of one or more system components could result in unintended exposure of the operating personnel. Of a number of possibilities considered, the most severe consequences would result from the rupture of the product hopper; the assumed scenario for and the consequences of such an accident are described below.
It is assumed that the product storage hopper hes accumulated process product which represents one year's radioactivity input (Table 6.4-1). Radioactive decay during the collection time is taken into account. The resulting activity in the product
- storage hopper is also shown in Table 6.4-1.
6-3 i
l
SQNP Following the failure of the product storage hopper, it is assumed that 25 percent of the material in the hopper spills into the cubicle. This material is in the form of small particles; it is assumed that the size distribution of the particles is such that 10 percent of them w ill remain suspended in the air rather than settling out, i.e., 2.5 percent of the radioactivity is airborne. It is further assumed that the building ventilation system would be operating. The ventilation effluent is discharged through a HEPA f il t e r, hence, the activity w ill collect on this f il t e r. A 100-percent collection was conservatively assumed. The resulting dose rate at a distance of tw o feet from the face of the f il ter w a s calculated to be 57 res/ h.
The HEPA fil ter s will be located behind shield walls. Radiation monit or s w ill be provided which will sound a local alarm on high radiation level. This w il l permit personnel who may be performing routine maintenance in this area to exit, thus avoiding an excessive dose. Assuming two minut e s as the egress t im e , total body doses received by any individual would be less than 2 rem, 6.4.2 Doses to Unrestricted Areas Following an Accident The rel ea se of radioactive material to unrestricted areas as a result of the failure of a VR/SS component could result in s exposure of the general public. The most severe consequences would result from the destruction of the process gas filters.
The material released from these f il t e r a can be carried directly from the bu il di ng w i th out having to pass through the filters of the building HVAC system.
The radioisotope inventory on the process gas filters, corresponding to one year's radioactivity input, is given in Table 6.4-1 t oge ther w ith the annual input activity. It is assumed that the full filter inventory is released directly to the environment.
The radioactive material is transported to the unrestricted area, taking account of the prevalent meteorological conditions. For conservatism, the 5th percentile I/O values used in the accident evaluations in the SQNP FSAR, Chapter 15, ' Environmental Consequences of Accidents,' are used here. These values are 1.64 x 10 -8 s/ms for the site boundary and 1.96 x 10-* s/m8 for the low population zone boundary.
Using the assumptions outlined above, the total body dose to an individual at the site boundary, a distance of 556 m, would be 0.01 rem, with the corresponding inhalation dose to the thyroid of 60 rem. The dose received by an individual at the edge of the low population zone (4828 m) would be 0.001 rem total body and 6-4
SGNP 7 .1 rem thyroid.
Maximum exposure limits to the general public as the result of an accident at a nuclear power plant are set forth in 10 CFR 100 and are 25 rem whol e body or 300 ren thyroid. The exposures calculated above ar e well b el ow these limits.
6.5 Handlina Accidents 6.5.1 Dronnina of a Recentiv Filled Product Drum The only operation in the VR/ SS f acility which would have possible radiological consequence is the transfer of recently filled drums using the overhead crane.
The po st ul a t ed accident would be the dropping of a drum just filled with product and solidification agent as it is being transferred by crane to either the drum inspection station or the drum storage area. Since the drum w ill be capped prior to lifting, the drum container should not be breached by a drop.
However if it were breached, plant personnel could remove the waste, repackage i t, and decontaminate the area as required.
Therefore, the radiological consequences of a dropped drum are
- considered to be small.
The design of the facility's crane makes this accident event
', highly improbabl e. The drum grab is rated at one ton and utilizes four clamping j aw s designed to clamp on the upper drum flange at equally spaced locations and to provide equal clamping pressure. A redundant motor operated clamp actuator and load sensing limit sw i t che s provide positive load release control and preclude releasing drums unless firmly supported. Also, a television camera allows the operator to visually verify the drum grab orientation and gripping. Therefore, the probability of a drum being dropped is very low.
6.6 Syst3m Desian Safety Features to Preclude Accident.s 6.6.1 folume Reduction Systen Automatic process shutdown interlocks as discussed below are provided in the VR to preclude damage to the process equipment and prov ide safety to plant personnel in the event of a process upset. Process shutdowns are automatically initiated by the f oll ow in g conditions and preclude startup until the mal f unc t i on has been corrected:
- 1. The entire gas train system pressure is affected by various malfunction conditions such as; high or low fluidizing airflow, high or low pressure drops across the scrubber-preconcentrator, plugged duc tw ork or leaks. Any of these
- failures activate shutdown and individually set alarms 6-5
SQNP facilitating location of trouble spots. ,
, 2. High temperature on the Scrubber-Preconcentrator (S-2).
- 3. Low discharge pressure on the Condenser Pump (P-5).
- 4. Failure of the Air Blower (C-1).
An automatic process shutdown results in immediate s hut d ow n of the f oll ow ing equipment:
- 1. Air Blow er (C-1) 5. Startup Hester (E-4)
- 2. Air Hester (E-1) 6. Dryer Feed Pump (P-2)
- 3. Gas Heater (E-2) 7. Waste Feed Pump (P-4) 4 Bed Heater (E-3) 8. Dry Waste Feeder (B-3A e B) 6.6.2 Solidification Systes In addition to normal process status indications, additional al a rm s and indications are provided. ,Should any of these indications be annunciated, they will alarm and cause en audible signal to be turned on. System f unctions monit ored wi th these indications include: flush w a ter pr es sur e, machinery air pressure, decant tank high level, select decant tank feed, motor -
overload trip, drum process cycle complete, no cap in drum, no fill selection, drum overfill, and drum process fault.
Flush Water _P_ressure is alarmed if water pressure drops b e l ow or rises above recommended pressure. Should either of these conditions occur, a pressure transmitter located in the system line w ill initiate alarm circuitry. In addition, this fault w ill cause drumming station operations and decanting station operations except decant tank filling to be stopped. Once the alarm condition has been corrected, operations can then be reinitiated.
Machine _rv Air Pressors is monitored with a pressure transmitter located near an air regulator used for controlling air pressure for operation of the valve actuators and metering pumps. This transmitter has been set to e n er g iz e alarm circuitry should air pressure supplying the equipment exceed 100 psig or drop below 60 psig.
6-6 +
SQNP The Decent Tsak Hiah Level alarm indicates high level waste conditions w i th in the dooant tank. This alarm is controlled by a sonic sensor mounted at the top of the decant tank which is preset to annunciate a high level condition prior to waste being spilled over into the ov e r fl ow pipe. Instrumentation supplied with this sensor al l ow s for two high-level set points in order to provide advance annunciation to the operator of the approach of an overfilling condition, and to automatically close valvos to stop filling. In addition, contact initiations are provided which may be incorporated into control circuits for liquid system pumps feeding the decant tank.
Select Decant Tank Feed annunciations are alarmed should the operator fail to select a feed stream for filling the decant tank.
Motor Overload Trio alarms are annunciated should any of the f oll ow in g motors have an ov e rl oa d trip: decant mixer drive motor, decant arm drive motor, decant pump motor, pivot drive motor, lift drive motor, clamp drive motor, capper drive motor, and tumble drive motor. In addition to the console alarm display, each motor has been provided with status indications on the electrical cabinet doors where their respective motor
, starters are located. These status indications display whether a run, stop, or motor overload condition exists. This allows the operator to quickly and positively identify which motor ha s i tripped.
Drun Process Cycle Conclete is annunciated when the drum is ready to be removed from the drumming station.
No Cap In_ Drum is annuncia ted whenever the drumming process has gone through the uncapping sequence and no cap has been detected by th e capper. Should this condition exist, the automatic process sequence will stop and not advance to the next operation.
No Fill Selection is annunciated s h oul d the operator fail to select the amount of waste to be pumped into the drum with metering pump control sw i t ch e s . Should this condition occur, the automatic processing sequenc e will stop until the alarm condition has been corrected.
Drum Overfi(1 is annunciated whenever drum pumping operations approach an overfill condition. A sonic sensor mounted in the fill nozzle for the concentrated waste and the decant tank slurries at the drumming station is used to detect drum content
! levels and is preset to initiate alarm circuitry prior to l spillage conditions. Circuitry automatically stops pumping before overfilling occurs.
S 6-7
SQNP Drum Pr_ocess Fault is annuncia ted whenever a problem in the drum ,
processing program e2fsts. This alarm is given in coincidence with all other alarms. Timing relays and interlocks are used in conj unction w ith the automatic sequence program for drumming operation to verify that operations automatically advance as programmed.
The alarm circuitry is int erlocked with station controls to stop drumming station and decanting station operations except decant tank f il l ing . Once the alarm condition has been corrected, station operations can then be reinitiated.
4 e
1 r
l 6-8
4 M
TABLE 6.4-1 MAXIMUM RADIOACTIVITY ACCUMULATION IN EQUIPMENT l
Total Annual Input Maximum Activity in Accumulation in l Isotope Activity (C1/yr) Product Hopper (C1) Process HEPA Filters (Ci)
I-131 1.4(3) 1.1(3) - 7.0(1)
I-132 6.0(1) 3.1(1) 3.1(-3)
I-133 1.7(2) 3 1(1) 2.1(0)
I-134 1 3(-1) 9.9(-4) 6.6(-5)
I-135 1.7(1) 9.8(-1) 6.6(-2)
Cs-134 8.4(2) 8.4(2) 1.9(-1)
Cs-136 1.2(2) 1.0(2) 8.1(-3)
Cs-137 4.1(3) 4.2(3) 4.2(-1)
Cr-51 7.4(1) 6.8(1) 6.8(-3)
Mn-54 3.5(0) 2.6(0) 2.6(-4)
Mn-56 1.2(-1) 2.7(-3) 2.7(-7)
Fe-59 3 0(0) 2.8(0) 2.8(-4)
Co-58 7.1(1) 7.2(1) 7.2(-3)
Co-60 3.6(0) 4.8(0) 4.8(-4)
Sr-89 9 2(0) 8.5(0) 8.5(-4)
SR-90 4.5(-1) 4.9(-1) 4.9(-5)
Y-90 4.6(-1) ~ 4.9 (-1) 4.9(-5)
- Y-91 1.4(1) 1 3(1) 1 3(-3)
Zr-95 1.8(0) 1.7(0) 1.7(-4)
Nb-95m 6.3(-4). 3 8(-4) 3.8(-8)
A Nb-95 2 3(0) 2.2(0) 2.2(-4)
Mo-99 1.0(3) 4.6(2) 4. 6 (-2 )
Tc-99m 9 7(2) 4.4(2) 4.3(-2)
Te-132 5.7(1) 3 0(1) 3 0(-3)
Ba-137m 3 9(3) 3 9(3) 3 9(-1)
Ba-140 3.6(0) 3 0(0) 3 0(-4)
La-140 3 9(0) 3.5(0) 3. 2 (-4)
CE-144 9.2(-1) 8.7(-1) 8.6(-5)
PR-144 9 2(-1) 8. 7 (-1) 8. 6 (- 5 )
1 1.4(3) = 1.4 x 10 3 l
b 6-9
S3NP
'
- 7.0 DECONNISSIONING It is planned to begin use of the LLRW VR/ SS f acility as soon as it is licensed, and to operate it for the remainder of the life of SONP. Near the and of SQNP, a de commis sioning plan w ill be subnitted to NRC which addre s se s all phases of deconmissioning for the f acili ty. This plan may be incorporated into the deconmissioning plan for the entire nuclear plant.
1 i
l l
l l
l l
7-1 i
l
SQNP 8.0 R EF ER EN C ES
- 1. ' Report of the Ta sk G roup on Reference Man,' ICRP Publication
- 23. Pergamon Prese, New York, 1975.
- 2. R. J. Engelmann, 'The Calculation of Precipitation Scavenging,' Meteorology and Atomic Energy, TID-24190, USAEC, 1968.
9 4
G 8-1
. . _ _ _ _ _ - . _ _ _ . .