ML20127M226
| ML20127M226 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 01/18/1993 |
| From: | Edgar J SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19303F231 | List: |
| References | |
| NUDOCS 9301280142 | |
| Download: ML20127M226 (52) | |
Text
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SIEMENS January 10,1993 U.S. Nuclear Rogulatory Cornmission Attn: Mr. John W. N. Hickey, Chlof Fuol Cyclo Safoty Branch Division of Industrial and Medical Nuclear Safoty, NMSS Washington, DC 20555 Licenso No. SNM 1227 Docket No. 701257 Doar Mr. Hickey:
Slomons Power Corporation (SPC) toquests a licenso amendmont to include modifications to the Gadolinia Scrap Rocovory (GSUR) process in the basemont of the ELO Building. The following is a description of those modifications.
Facility Expansion The GSUR contaminated zone is being expanded to approximately twico its curront size. The expansion makes room for: additional process offgas (POG) oquipmont; increasod raffinato storage capacity for monitorod lagoon dischargo; location of an upright contrifuge for LUR operations which are being rolocatod; relocation of equipmont in tho decontamination facility; rolocation of the food drum staging area; incroased drum and pall storago; and relocation of equipment in Room 53 to allow hood expansion, and relocation of the area designated for various chemical ongineering developmont activities. This expansion does not result in a significant increase in capacity. The onclosed Figure 1 shows the planncd layout of GSUR after the modifications are completo.
Theso modifications chango the existing altflow by not allowing airflow from the first floor to tho basomont. After the modifications, the airflows from upstairs and
- downstairs portions of the building will bo separated until they ontor the exhaust stack.
POG Modificatior)
The curront POG system is part of the building HVAC systom; the modification will croato a separato system. The POG system modification is mado up of a now oxhaust system for chemical fumo exhaust which includes ductwork; a mystairo scrubbor, a dissolver offgas scrubber, controls, a rohoater, HEPA filtors, an exhaust fan, and a 50 foot exhaust stack, i
Siemens Power Corporati" Nuclear Division - Engineering and Manufacturing Facility I
9301280142 930118 Richland. WA 993524130 Tel: (509) 375-81 F
) 375-8402 j
2101 Horn Rapids Road. PO Box 130 4f'.hax
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_ January 10,1993 The modified POG system is expected to result in:
1.
Roduction of ammonium nitrato formation in ductwork; 2.
Ammonium nitrate safety when using ammonium carbonato wash solution; 3.
Stack dischargos more roaddy mooting internal guidelines of no visible NOx and Stato regulations limiting cito boundary NOx concentration (loss restrictive than internal); and 4.
Because the scrubber in the modified POG system will bo_ load-based, the amount of liquid offluont will be minimized.
The onclosed Figuro 2 shows the POG system diagram for GSUR.
Raffinato Storoae Raffinato storago will be increased from 40 gallons to 400 gallons to allow quarantine-for samplo results prior to dischargo to lagoon 3 via the ELO sump. This modification -
is dictated by the need to improve monitoring of dischargos to the lagoons and does not increase systom capacity. The new raffinato s,orage includos eight geometrically safe tanks with the attendant controls and pumps.
, Mixer /Settlor Reolacement The mixor/ settler is boing replaced with a new unit which is slightly lErger, but still -
critically safo, in both the settler region and the piping cross connection diameters.
The cross concioction fittings are cajon fittings for improved chemical containment.
The modification is expected to:
1.
Reduco chemical fumo exposuro from leaking fittings; 2.
Reduce process problems, overflows, and chemical exposuro caused by hydraulic limitations;
~
l 3.
Eliminato ammonlum nitrato in ductwork from the combining of carbonato and acid wash venting; and i.
4.
Improve chemical containment with reduced alt flow for scrubbing of tho -
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mixer / settler exhaust.
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January 18,1993 Processlank and Pump Replacoment Most process tanks and pumps are being replaced, because the existing -
polypropylene tanks periodically leak and the resulting fumo containment requires high airflow. The existing pumps are various types all having special material requirements which results in expensive spare parts inventories, inefficient maintenance time usage, and poss!51c installation of incompatible mate.1als. The replacement includes installation of standardized stainless steel tanks and pumps and an improved piping layout.
These replacements are expected to result in:
1.
Reduced rediation exposure due to stainless steel vs. plastic tanks; 2.
Better containment with reduced air flow requirements for scrubbing; 3.
Reduced chemical exposure from leaks; 4.
Increased maintenance efficiency; and 5.
Reduced equipment downtime.
Powder Screenina Station Some of the scrap powder received for recovery requires screening, which is currently done manually at the cost of process downtime and unacceptably high airborno exposure. A powder screening station, which includes a bucket-to-bucket Sweco ccreening station located in the pellet dissolver hood; a bucket tumbler, a scale, and a vacuum cleaner will be added. This station is expected to result in reduced airborne exposure, reduced manpower requirements, and increased process operating time.
Relocation of GSUR Drum Feed Staoino and Eauloment and Tank-1 Hood Exoansion Staged GSUR feed drums, currently located in the hall, will be relocated to Room 57 which will reduce the likelihood of in-transit spacing requirement violations and improve the flow of drums out the airlock. Drum downloading pumps and filters will also be relocated to Room 57 to allow expansion of the Tank-1 dissolver hood in Room 53. This hood expansion is required from'a criticality safety standpoint to' allow.
designat!on of two safe batch work areas. Two safe batch work areas are needed to reduce powder transfers into and out of the work station who coprocessing powder with low concentration UNH solutions. These modifications are expected to result in fewer criticality safety violations and improved flow of drums into and out of the facility,
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January 18,1993 Rolocation of Moo Powder Dissolver Hood The mop powder dissolver hood has boon located temporarily in the decontamination facility in Room 58 lhe dissolving operation is incompatible with decontamination operations scheduled to go into this room. In addition the existing operation will not allow the addition of low concentration UNH solutions to the dissolvor batches for concentration control with the GSUR minimum recycle requirements. The mop powder dissolver hood will, therefore, be modified and relocated in Room 57. Tho -
modification includes hood redesign and controls for low concentration UNH recycle.
Those modifications are expected to:
1.
Facilitato criticality safety minimum spacing and safe batch controls; 2.
Moot minimum GSUR recycle requirements and drum handkng requirements:
3.
Result in impioved dissolver drum lid operation to reduce spills and storage difficultios; and 4.
Improve containment with reduced airflow for scrubbing.
Relocato LUR Centrifune and Dissolvino Operation The LUR contrifugo, curjontly located outsido, was used to recover uranium from lagoon solutions and to, separate rod mud from UNH solutions after mop powder processing. This process step must be relocated ins!de with HEPA filtered exhaust to support mop powdor processing and future LUR operation.. The modification includos-installation of an upright centrifuge, an outlet pump and filters, a bowl cleaning station,-
and vonted location for storing feed / washing and product drums. The LUR dissolving operation requires a drum storage location with ventilation to the dissolver offgas scrubber and aluminum nitrato nonahydrate (ANN) delivery system.
Chemical Enaineerina Development Area Various developmental activities are expected to be conducted in this areac Among activities currently under consideration is a study to develop tne ability to chemically decontaminate HEPA filters.
Included are revised pages 10-6,10-37 through 10-40, 69, 78, and'15-15 through 1517 for
~
the existing licenso and pagos 10-6,10-35 through 10-56,10-82, and 15-38 through 15-44 for -
the August 26,1992 applicatior). Included in the revisions to the August 1992 application are added paragraphs 10.3.8.5 and 10.3.8.6, which were inadvertently left out. Changes made to individual pages are shown by a vertical line in the right margin. Additional pages are included because changes caused succeeding pages to be changed.
January 18,1993 You will note that revised pages 15-15 and 15-16 from the existing license and 15-38 and 15-39 from the August 26,1992 application contain propriotary Information and are so markod.
Enclosed is an affidavit attesting to the confidontiality of the information contalnod in those pages and pages 15-23 and 15-24 submitted on August 26,1992.
SPC expects to be ready to be operational in the modified facility by the end of April 1993.
We would, thereforo, appreciate your expedited review of this request. If you require further Information, please call me at (509) 375-8663.
Very truly yours,
/3.h JhmosW. Edgar Staff Engincor - Licensing JBE:pm l
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4-AFFIDAVE State of Washington )
)ss County of Benton
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I, Robert G. Frain, being first duly sworn, deposes and says:
1.
I am Vice President, Manufacturing of Slemens Power Corporailon, a corporation duly organized and existing under and by virtue of the laws of the State of Delaware, with offices at 2101 Hom Rapids Road, City of Richland, County of Benton, State of Washington, and on whose behalf I make this affidavit.
2.
I am familiar with the contents of the letters of August 26,1992 and January 18, 1993 from Siemens Power Corporation (James B. Edgar,. Staff Engineer, Ucensing) to the U.S. Nuclear Regulatory Commission (Attention: John W.N.
Hickey, Chief, Fuel Cycle Safety Branch, Division of Industrial and Medical Nuclear Safety).-
3.
The information contained in pages 15-23 and 15-24 (dated August 26,1992) -
of NRC Ucense SNM 1227 renewal application, revised pages 15-15 and 15-16 (dated January 18,1993) of existing NRC Ucense SNM-1227, and revised pages.15-38 and 15-39 (dated January 18,- 1993) of NRC Ucense SNM-1227 -
renewal application; (i) has been held in confidence by Siemens Power Corporation pursuant to. Its internal policies, (ii) is the type of information that is.
normally held in confide;nce by Siemens Power Corporation in order to protect it as valuable trade secret which gives a competitive. advantage to Siemens Power Corporation and which information, if given to a competitor, would be valuable to such competitors, without them having to expend any funds and in a!!owing them to know what processes Siemens Power Corporation is -
contemplating (iii) was transmitted to and received by the U.S. Nuclear Regulatory Commission in confidence,'(iv) is not available.from public sources -
and (v) public disclosure of the information would cause harm to Siemens _
Power Corporation by allowing competitors free access to information which Siemens Power Corporation developed at its own time and expense, which' information would not be easily acquired by another company and would give competitors free access, to information on Sicmens Power Corporation's -
manufacturing processes.
F
I um authorized to make the statements that are set forth herein on behalf of Siemens Power Corporation and the statements made in this affidavit are, to the best of knowledge, information and belief, truthful and complete.
Slomens Power Corporation
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Robert G. Frain Printed Name Vice President. Operations Title
/-/2~ 9 3 Date Personally appeared before me Robert G. Frain known or proved to me to be the same person who executed the foregoing instrument and to be the Vice President, Manufacturing of Siemens _ Power Corporation and acknowledged to me that he executed the same as his free -
act and deed and the free act and deed of Siemens Power Corporation.
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- ibed and sworn to before me this
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day o
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of watu Q
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re Notary Public in and for the County of Benton, State of Washington My commission expires the D/
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c Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 - SAFETY DEMONSTRATION ~
REV.
Figure 11 - 10.11 shows the space and equipment devoted to the rod fabrication phase of the manufacturing process. Room 182 is a high bay area, where Room 189 has-headroom of approximstely 9 ft. Pellets are removed from the storage cabinets in Room l
100 and processed through the outgas furnaces in Room-182. After the pellets are outgassed, they are loaded into first-end welded tubes in the rod loading glove boxes.
After rod loading, the second-end weld is made. The rods are then processed through the helium leak check, rod assay tester and rod x-ray equipment which is all located in Room 189.
After the nondestructive testing in Room 169, some types of BWR fuel rods are transferred to Room 110 (the Etch Room) shown on Figure 11-10.12. The rods are cleaned in cleaning solutions and etched to remove any surface contaminants. Offgas
- from the etching equipment is exhausted through a scrubber and HEPA filters. After i etching, the rods are transferred to Room 107 where they are processed through high-pressure, high-temperature autoclaves.- The autoclaves are located in a reinforced concrete pit approximately 20 ft deep. After autoclaving, the rods are transferred through.
various inspection stations to the final rod storage area in Room 193. PWR and nonetched BWR fuel rods, on the other hand, are transferred directly from nondestructive testing in Room 189 to the final inspection table in Room 107 and then to the final rod storage area in Room 193.
The bundle assembly, cleaning, inspection and shipping container loading operations are all done In Room 193 (shown on Figure 11 - 10.13). Rods are moved from_the rod storage area to the rod Insertion tablesi The fuel bundle is assembled on the bundle assembly table and is then lifted to the vertical position on the assembly table and moved onto the bundle inspection granite column. After inspection, the bundle is cleaned, dried, and '
moved to the storage area or to the shipping container loading area where it is prepared i for shipment. Immediately west of Room 193 is Room 195 where cage fabrication work is accomplished, Figure il -10.14 shows the low bay area of the UO Buliding whid is devoted almost 2
exclusively to the various Quality Control and inspection functions that are necessary in the manufacture of nuclear fuel. These areas include chemical and physical testing laboratories, metallurgical laboratories, and a limited number of offices.
The north end Equipment Room and administrative areas are shown on Figures II-10.15 -
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and 11 - 10,16.
t 10.1.3 ELO Buildina Description The current ELO Facility cor,sists of an original building constructed in 1974, and an 2
expansion constructed in 1982. The original facility consists of approximately 6000 ft on 2
the ground floor and 3000 ft in the basement. The addition, which effectively doubled auE e ra m cA:ON DATE; PAGE NO.:
t August 26,1992 10-5 g
SPC ND.3330 947 (R 1/07/92)
Siemens Power Corporation - Nuclear Division ew.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
the building size, utilized the same basic type of construction. The 1982 addition 2
2 consisted of approximately 6000 ft on the ground floor and 4000 ft in the basement.The entire ELO Facility is currently operated as a single facility and treated as such in this j Application.
j l
The floor plan for the ELO Facility is shown on Figure 11 - 10.17. The basement arer s are constructed of poured in-place concrete walls and floor slabs.
The ground floor construction (approximately 70 x 172 x 12 ft high) is of concrete block on poured-in-place skirt walls. The inner side of all exterior walis are insulated and covered with fire-rated gypsum board. The gypsum panel joints are taped and sealed, and the interior surfaces are suitably painted. The interior partitions throughout the building, used for process 4
control, are either concrete block or fire-rated gypsum board. The roof is rnade of steel deck plates supported on steel trusses, covered with insulation, and a 20 year, built-up I roof system. The compressive strength of all concrete exceeds 3000 psi and the concrete floor slabs were designed for 250 psf.
The basement area contains a chemical engineering development area, an engineering machine shop, the Gadolinia Scrap Recovery Facility, and other engineering test facilities.
The first or ground floor contains an instrument laboratory, metallography laboratory, wet chemical laboratories and sevefal engineering offices.
The uranium enrichment in the various laboratories is less than 20 wt% U-235 in solid form, and not more than 5 wt% U-235 in liquid form. Activities include all operational steps of fuel manufacturing and process testing.
10.1.4 Contaminated Clothina Laundry
' The location of the Laundry Facility is shown on Figure 11 - 10.1. The building is a l i combination of a pre-engineered metal building (20 X 30 X 12 feet high) and a concrete l l block structure (16 X 20 X 11 feet high) with a 6'9" x 17'9" airlock which provides for !
! access, yet maintains the proper pressure differentials for contamination control. The !
l exterior walls are 26-gauge sheet metal and concrete block and the roof is 24-gauge i l
! sheet metal, and built up metalinsulated and finished on the interior. The interior of the l roof is a suspended metal ceiling grid with acoustical lay-in panels 5/8-in thick. The !
l i interior of the metal walls are finished with fire-rated gypsum panels. Interior partitions are fire-rated gypsum board on metal studs, Care was used in sealing the sheet metal and
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gypsum panels in order to maintain the required pressure differentials and airflows in the
- metal structure. Allinterior surfscos are taped and sealed and suitably painted. The floor I was made of 3000 psi concrete and designed for 250 psf, f Contaminated clothing is cleaned in a water wash system, surveyed for contamination,
! and returned to use. The effluent is directed to retention tanks where it is sampled prior j to being emptied either to the site lagoon system or the City sewer.
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- me um January 18,1993 l
10-6 l
EPC-ND.3330 947 (R UO7/92)
J
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Siemens Power Corporation - Nuclear Division
- eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227iNRC DOCKET NO. 70-1257 PART ll - SAFEW DEMONSTRATION REV.
I radiation or heat detection in recirculation or exhaust ductwork, or loss of instrument or control air stops the supply fan.
The mezzanine, Machine Shop and test development areas are maintained at -0.n5 inch.
. water gauge in respect to atmosphere and the north-half of the building.
The development laboratory is maintained at between -0.05 and -0.10 inch water gauge in respect to atmosphere and negative to the adjacent Machine Shop area at all times. As long as the K24 supply fan and K25 exhaust fan plena pressures are maintained within Indicated ranges, the building pressure differentials will be maintained.
10.3.7.5 Final HEPA Filter Bank The final HEPA Illter bank for the K25 system is a sheet metal frame and housing that is,
3 fastened to a concrete slab. HEPA filters rated at 1000 ft / min at one-inch water gauge pressure drop are mounted in steel frames. Visual Indicators for reading the pressure drop across the filters are permanently installed, and means are provided for in-place DOS test!ng.
l The HEPA filter medium is 100% moisture resistant fiberglass, pleated over corrugated separators and sealed in fire resistant plywood frames. The individual filters are certified to remove 99.97% of 0.3 micron particles and meet or exceed Military Specification MIL-F 51079.
10.3.8 ELO Addition HVAC Systems T
e Although this building addition is physically attached to the original ELO Building, it has -
! - its own separate HVAC systems: K45 (supply), K46 (exhaust), and K56 (POG exhaust). ]
The building is physically divided with the north portion serving as an office area and the j south portion housing engineering test operations, an Instrument laboratoryiseveral j metallography laboratories and various chemicallaboratories. The north office' portion !
of the building is served by the original ELO Building office (K26) supply system (see s
Figure ll-10.25) and is separated from the laboratory portion by a series of airlocks. The south portion of the building is served by the K45 air supply and K46 and K56 exhaust ;
systems.
I The general features of the ELO Building addition HVAC systems are a once-through i i
ceiling-to-floor altflow (K45) supply air system, a double HEPA filtered (K46) bullding !
l i
exhaust system, and a double HEPA-filtered (K56) POG exhaust system. ~ A simplified ;
schematic of the ELO Building Addition HVAC system is shown in Figure 11-10.26.
l l
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l AMENOMENT APPUCATCN DATE:
' PAGE NOJ SPC-NO.3330 947 (R 1/07/92)
'Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257-p
[
/i PART 11 - SAFETY DEMONSTRATION sev.
b uJh 10.3.8.1 K45 Air Supoly System 3
The K45 air supply system provides about 16,000 ft / min of 100% outside air to the south portion of the ELO addition. Airflo,vs aro dirs0tional from ceiling to near-floor exhaust air.
grills or process hood inlets, and always away from areas of low contamination potential to areas of higher contamination potential.
10.3.8.2 K46 Air Exhaust System.
3 The K46 air exhaust system removes approximately 18,000 ft / min of air supplied from the process areas served by the K45 air supply system. The double filter arrangement in this system consists of the final HEPA filter bank plus individual or smaller filter banks of profilters and HEPA filters in~ the exhaust ducts of the areas or equipment serviced.
Ductwork in the K46 system is made of galvanized steel.
The K46 system exhaust air passes directly from the final filter bank to the exhaust fans
.I l
and is discharged from a stack extending 23 ft above the main portion of the UO Building, or 35 ft above ground elevation. The K46 exhaust system has a single fu$
i capacity fan connected to normal power, 10.3.8.3 K56 Air Exhaust System 3
The K56 air exhaust system provides approximately 1,000 ft / min vent service for chemical sumps and gadolinia scrap recovery process tanks and offgas from the dissolver offgas scrubber. As in the etch process, fumes from these sources are corrosive. The_ exhaust -
is passed through a scrubber, a dryer and double HEPA filters and is discharged through i
a separate stack located on the south side of ELO Building. This stack extends 50 ft I
above ground level. The scrubber is provided to remove 9eid fumes, nitrous oxide and i
entrained organics consisting of dodecane and tributal phosphate. The dryer is used to -
il remove entrained liquids and the filters to remove potential uranium, The ductwork material in the K56 exhaust system is stainless steel for ducts greater than seven inches in diameter, and polyvinyl chloride for ducts less than seven inches in i
i diameter The single K56 exhaust fan is connected to normal power.
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! 10.3.8.4 Systems Controls I
l The HVAC systems are controlled with temperature, pressure and flow sensor actuating l
- valving and damper positions to hold temperatures, prescures, and pressure differentials
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constant in the various building areas. The building ventilation systems are interlocked so that the K46 exhaust system'must be operating before the K45 supply system can be i
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L J
SPC.NO:3330.947 (R1107M)
. SiemenS Power Corporation - Nuclear Division EMF 2
- SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 SAFETY DEMONSTRATION -
REv.
started. Pressure sensors are provided for damper control to maintain a negative pressure (minimum -0.05 inch water gauge) in the laboratory areas relative to the office area and to atmosphere, and to maintain an exhaust duct negative pressure between -4 and -12 inches water gauge. Any loss of instrument air prevents the supply and exhaust systems from operating. Both the K45 supply fan and K46 exhaust fan are interlocked so that a loss of exhaust duct negative pressure above -4 inches water gauge (toward -
zero) will shut down the supply fan or an increase of exhaust duct negative pressure below -12 inches water gauge will shut down the K45 supply fan and the K46 exhaust fan.
The K56 exhaust fan runs continually.
Automatic audio and visual alarms are activated when any supply or exhaust system upset occur. Pressure differential indicating devices and airflow quantity meters are
, located in the controlled zones and/or on the main HVAC panel to provide system and l zone operating conditions.
10.3.8.5 Delune System A deluge system of fog spray nozzles is installed in the exhaust duct a short distance.
I upstream of the final filter banks. If heat detectors indicate a temperature of 140-190 F, i-the deluge spray is automatically activated. Should the deluge system be activated by l
any circumstance, differential pressure readings across the final filters will be taken and in-place DOP/ DOS test made al the earliest opportunity.
10.3.8.6 Final Filter BanN 1
l The final filter bank is encased in a puoured and sealed concrete structure.- HEPA filters 3
- rated at 1000 ft / min at 1-inch H O pressure drop are mounted in welded, steel structural l
2 frames. The HEPA filter medium is 100% moisture-resistant fiberglass, pleated over corrugated separntors and sealed in fire-resistant plywood frames. leh individual filters l
are certified to remvoe 99.97% of 0.3 micron carticles and meet or exceed Military.
A Specification MIL-F-51079.
-10.3.9 Contaminated Clothina Laundry HVAC System The general features of the contaminated clothing laundry HVAC system are a once-i through ceiling-to-floor cirflow supply system (K41) system and a double HEPA filtered - [
' exhaust system (K42). A simplified schematic diagram of the air supply system and the'.
- air exhaust system is shown in ' Figure 11-1_0. 2 7,
i 10.3.9.1 K41 Air Supply Syst m i
' The K41 air supply system suphlies about 1900 ft / min of 100% outside air to the laundry 3
room which is divided into a cleaning area and adjoining sorting area. - Airflows are I
WOOMENT AFPUCATION DATE-PAGE NO4 t
a SPCWO 3330.947 (R4 /0712) s
SiemenS Power Corporatibn - Nuclear Division EuF2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REv.
directional from ceiling to near-floor exhaust air grills or a hood inlet, and always away from areas of low contamination potential to areas of higher contamination potential.
10.3.9.2 K42 Air Exhaust System Air supplied to the cleaning and sorting areas, plus infiltration and dryer exhaust (approximately 4200 ft / min),is exhausted through the K42 exhaust system. The double 3
HEPA filter arrangement in this system consists of the final HEPA filter bank and upstream i primary HEPA filter bank plus individual profilters located in the exhaust ducts of the two
! areas serviced.
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3
! The K42 system exhaust air (approximately 6300 ft / min.) passes from the two stage filter i bank through the main exhaust fan, a duct alt monitor (measuring airflow quantities) and l ls discharged from a stack extending 25 ft above ground on the southwest side of the l building. The K42 exhaust system has one full capacity f an which is connected to normal i
j power. All final HEPA filters are in-place tested and assured to be 99.95% minimum
' efficient for 0.8 micron DOS cold aerosol.
10.3.9.3 Systems Control The HVAC systems are controlled with temperature, pressure and flow sensor actuating
' valving and damper positions to hold temperatures, pressures, and pressure differentials constant in the various building areas. The K41 supply air system is interlocked with the i K42 exhaust system to prevent operation of the K41 supply air system without the K42 i exhaust system operating. Pressure sensors are provided to maintain a minimum
~ negative differential pressure of 0.05 inch water gauge in the cleaning area relative to the l atmosphere, i
j The K41 supply fan is interlocked so that a loss of exhaust duct negative pressure above
-3 inches water gauge (exhaust fan failure) or a signal from the exhaust duct heat i
detector will shut down the K41 air supply system.
Automatic visual alarms are activated when any supply or exhaust system upset occurs.
! Pressure differential indicating ' devices and altflow quantity meters are located on the l
main HVAC panel to provide system and zone operating conditions.
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l 10.3.9.4 HEPA Filter Bank l
1 I
t I The final HEPA filters are enclosed in a sheet metal housing that, in turn, is mounted on i
i structural steel legs fastened to a concrete stab. The HEPA filters are rated at 1000 ft / min at one-inch water gauge pressure drop and are mounted in welded steel frames.
3 i
- Continuous air samplers are installed downstream of the filter bank. Visualindicators for ILWW AMCAt&lCATE
P AGE NO :
January 18,1993 10-38 i
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I SPc ND 3330.947 (R-907S2)
Siemens Power Corporation - Nuclear Division sup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 -
PART 11. SAFETY DEMONSTRATION nev.
reading the pressure drop across the filters are permanently installed, and means are provided for in place DOS testing.
The HEPA filter medium is 100% moisture-resistant fiberglass, pleated over corrugated separators and sealed in fire resistant plywood frames. The individual filters are certified -
to remove 99.97% of 0.3 micron particles and meet or exceed Military Specificawn MIL-F- -
51079.
10.4 Radioactive Waste Handlino The facilities and processes which are invo!voo in the handling of radioactive arc 3 chemical wastes produced by SPC are described in the following sections.
10.4.1 Lanoon System Description
)
l The lagoons provide w 'alnment for all uranium and chemically-contaminated liquid i
wastes generated at SPC.
Natural evaporation, controlled waste addition, waste discharge to the municipal sewer and water additions are used to control the volume of 3
liquid stored in the lagoons. Intpr-lagoon transfers are periodically made for both uranium accountability and volume control purposes.
Sampling between lagoon liners is conducted monthly (unless prevented by freezing weather) to determine if leaks have occurred.
There are six liquid waste storage lagoons, one solids leach pit, and one sand storage pit located along the east boundary of SPC (see Figure ll-10.1). The sand storage pit is
_l-located immediately west 'of Lagoon 3. The solids leach pit is located immediately west
[
of Lagoon 2. The dimension and capacities of the lagoons are:
p e
i Lagoon Dimensions Est. Capacity 10* Gal -
]
{
l 1
240' x 200* x 3* deep 1.4 2
240' x 100' x 3' deep
. 0.7 3
240' x 350' x 5'6" deep 3.5 4
240' x 290' x 6'. deep
. 2.7 SA 240' x 175' x 7'6" deep 1.6 l
SB 240' x 175' x 7'6" deep 1.6 t
Leach Pit 40' x 54' x 8'6" deep 0.06 l
Sand Pit 39' x 300' x 6' deep 0.3 j
I, AuENOMENT APPL'CATON DATE; PAGE NO.:
SPC-ND 3330,947 (41<07/92) -
=
i 4
(
Siemens Power Corporation - Nuclear Division
- eur.2 SPECIAL NUCLEAR MATERlhL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REvi The lagoons and the solids leach pit have a
- sandwich"_ construction; they each have two -
lin9rs made of Impervious material, separated by 6 inches of sand. On Lagoons 1,2 and 3, the " sandwich" rests on an asphalt-type surface known as Petromat. In the sand layer j between the impervious liners is an array of sample heads. The sand storage pit is l single-lined and, therefore, does not have between-liner sampling capabilities. Tubing from each of the heads is routed to the berms on both the east and west side of the l lagoons where small pu'mps can be periodically connected. Some additional sampler heads are located between the original Petromat liner and the lower liner. Lagoon 4 is equipped with three " dry wells" below the bottom linct, Samplers are located in each dry well. All sampler heads are pumped each month using small air-driven pumps (unless prevented by freezing weather) for leak detection purposes.
Lagoons 1 and 2 are used as receivers of ammonir 5 earing solutions from the conversion area with a low-level of uranium and is the feed lacon for the ammonia recovery (AR) process. They have impervious floating covers to contain the ammonia fumes.
Lagoon 3 is a storage lagoon for high uranium content wastes and serves as the feed lagoon to the LUR Facility.
Lagoon 4 is a storage lagoon for low uranium content waste from the LUR process.
Lagoon 4 also serves as the feed lagoon for LUR waste to the AR Facility.-
Lagoon SA is a storage lagoon for waste streams from the AR Facility and miscellaneous low uranium, low ammonia chemical wastes. Disposal of waste from Lagoon SA to the city sewer is accomplished after treatment by lon exchange to remove residual uranium (see Section 10.4.3).
The waste sewering rate is automatically ' controlled by a microprocessor via a flow measuring and control system. The sewered chemical waste:
is volume _ proportionally sampledc The chemical waste is monitored for uranium and 3
! chemical content and sewering rate is controlled based on waste composition so as to f remain within discard limits.
l Lagoon SB is currently used to store high uranium content waste to be treated for i uranium recovery. Once emptied, this lagoon will be used as a batching lagoon in I conjunction with Lagoon SA to receive AR Facility waste for. metered discharge to the city sewer.
l The sand pit is used as a storage pit for sand and sludge that has been removed from
' the liquid storage lagoons during cleanup over the years of operationc I
The solids leach pit is used for decontamination of sand. The process is described in
, detallin Section 10.4.4.
i i
I i
AMENDMENT APPUCATiON DATE:
PAGE NO.:
I i
l January 18,1993 40 i
e
'l -
SPC No.3330 947 (4 t/07/92) l
x Siemens Power C.orporation - Nuclear Division
- eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll - SAFETY DEMONSTRATION
- _nev, 1
Periodically, liquid wasto solutions are transferred from ono lagoon to another for accountability, volume control or maintenance purposes. _ A permanently mounted pump -
with interconnecting piping onablos solution to be pumpod from any lagoon to any other lagoon and also allows recirculation within any lagoon.
10.4.2 Ammonia Recovery (AR) Description 2
The AR process is housed in a 1635 ft insulated stool structure located north of Lagoon 1 (soo Figuro 1110.1). The structuro is designed to withstand UBC Zone li solsmic loading 2
and 20 lb/ft windward pressure. An equipment arrangement is shown on Figure 11-10.28.
The Engineering Flow Diagram is presented on Figuro 1110.29. A brief description of the major equipment plocos is given in Table Il-10.1. The buliding also houses the Lagoon 5A IX Process (see Section 10.4.3).
The unneutralized low uranium content liquid process waste from the feed lagoons (Lagoon 1 or Lagoon 2) is transferred to the food tank which provides approximately one
+
hour surge capacity. Process waste from the LUR operation can b_e added to the feed tank and processed with the conversion process waste = Sodium hydroxide is added to the food tank to replace the ammonium in the ammonium salts, and to keep the pH high to reduce corrosion. The food tank is maintained under a slight vacuum by venting-through a scrubber. Feed solution is pumped via a flow control system and an energy-recovery heat exchanger to the ammonia stripper. The heat exchanger is provided to reduce energy requirements for, the process by using the hot stripper bottoms to preheat the feed solution.
The ammonia stripping column provides for removal of ammonia from the waste solution by countercurrent contact with steam and is designed to produco 20 to 30 wt% ammonia product solution and waste effluent at less than 100 ppm ammonia. The bottoms from the stripper are pumped to the designated waste treatment batching lagoon (SA or 58) or recycled back to the food tank, or the feed lagoon, depending-.on its. ammonia concentration, temperature, and pH.
The air purge system on the pnoumatic instrument lines is designed to prevent backup of process fluids in the event _of excessivo system pressure. A 50 psig rupture disk is provided at the top of the column to prevent overpressurization of the system. Thol pressure relief vents to the atmosphere through the tower roof.
. The condensables from the str,lpper overheads are removed in a downdraft condenser -
f
! and are routed to the distillate tank. An automated dolonized water injection system is 1
provided to improve ' ammonia removal efficiency and to control the ammonia hydroxide -
concentration.
j l
.}-
j uusous~1.r.uc.1,on o 1c:
3, g ce ~o; L.,_ __
SPC NO 3330 947 (4 UO7/92)
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Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 PA{RT ll SAFETY DEMONSTRATION REv.
r A scrubber is provided to remove ammonia from the process vessel offgas. The scrubber bottoms are routed to the food tank. The scrubbed offgas is vented to the atmosphere via the building exhaust fan and stack.
The control system is an electronic digital microprocessor system. The consolo can access process information and display it on the CRT. In case of transmitter failure, the processors will adjust to a safe value that can keep the process from going too far out-of-control. Deviations from set points are alarmed when they surpass their prodotermined limits.
- A steam boiler provides a maximum of 3000 lb/hr of steam to the AR process. Boller pressure control is maintained by SCR's driven from pressure instrumentation. Steam
)! header pressure instrumentation is provided to shut down the process and alarm on low I and high steam pressure.
j
, A 28,000-gallon, aboveground sodium hydroxide storage tank is provided to supply tne
! AR process. The tank is insulated and heated with a S kW heater to maintain the caustic
- temperature above 65'F. All exterior piping is heat-traced and insulated. A safety shower
' is provided at the load in facilities. Operation of the NaOH storage system is monitored and controlled at the control room.
A 28,000-gallon, aboveground stora00 tank is provided to store NH 0H product from the 4
AR process. Facilities are provided to load-out excess ammonium hydroxide for sale off-site. The NH 0H used for recycle to the process is transferred to either of two 10,000-4
, gallon, ammonium hydroxi,de storage tanks.
l
~ A concrete spill containment structure is provided for the outside bulk sodium hydroxide and product ammonium hydroxide storage tanks. The structure is designed to contain j chemicals from a ruptured storage tank.
l The building exhaust system consists of a two-speed fan, temperature controls, an
' ammonia monitor and stack.;
The exhaust fan is normally run on low speed 3
proximately 1700 ft / min). The fan is switched to high speed (approximately 5000
' (ap/ min) if the building exhaust temperature exceeds 110*F. The building exhaust air l tt ammonia monitoring system is set to alarm locally and in the Line 2 Control Room.
' The AR Facility 6te detection and alarm system has been tied into the existing plant i
, systems.
l I
Criticality in the AR system is not deemed credible due to the extremely low concentration of uranium. In addition, the feed tank and stripping column were designed for solids to l
flush through the system. Neverthe!ess, the system is inspected quarterly for signs of January 18,1993 10-42
~
SPC-NO 3330 947 (R 1107/92)
i 1
r Siemens Power Corporation - Nuclear Division EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM,1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REV.
~
buildup of uranium solids. The plant criticality detection and alarm system also covers the AR Facility.
10.4.3 Lanoon 5A IX Process, The Lagoon SA lon exchange system is located in an addition to the Ammonia Recovery Facility (ARF) Building. The addition is 25' x 27' x 20' high. It is a pre-engineered metal I
building located on a concrete stab. A plan view of the addition is shown in Figure ll-10.28. The equipment arrangement is shown in Figure Il10.29b.- The building is insulated and designed to withstand Uniform Building Code Zone 11 seismic loading and a 20 lb/sq. ft. wind. The floor is sealed and caulked to be leak tight. The floor slopes toward the sump area and has a slll or curb for leak containment except for the doorway which is protected by a trench sloped to drain to the main sump. The process equipment is located in the sump area which has a 4 inch recessed floor. The sump pumps to i
Lagoon 3. Controlis automatic, but can be controlled manually. The sump is dec!gned l
to collect minor leaks oflagoon solutions containing uranium and sodium and ammonium y l
sulf ates, fluorides and nitrates and lon exchange reagents _such as sulfuric acid, sodium i
j.
1 l
hydroxide, and water, The sump and floor areas are inspected annually for leaks. Those areas are normally dry, leaks are repered as soon as practical.
Lagoon SA waste solutions scheduled for discharge to the city sewer may be routed through the ion exchange (IX) process located in the ARF Building to further reduce the l-uranium content. The Lagoon SA IX Process consists of two sand filters and an ion
~
exchange column and associated auxillary equipment. The process flow is shown in Figure ll-10.29a. Lagoon SA solution is pumped from the lagoon through the primary filter l
located at the lagoon pump out area to remove small particles and suspended solids.
_ j-The solution then is pumped through the polishing filter in the ARF Building and to the
^
adjacent IX column. Passage through the column reduces the uranium concentration l
I by a factor of about eight or more. The uranium held up on the column is eluted from i'
the column and transferred to Lagoon 3 for later uranium recovery. Lagoon 4 solution may be used as an eluting solution. Other reagents such as carbonate solutions may be j
used. The regeneration cycle of the resin uses sodium hydroxide and sulfuric acid which -
are available at the facility. These are discharged from the resin to Lagoon SA. The -
l'.
l polishing filter is backflushed to Lagoon 3. The Lagoon SA filter is backflushed to Lagoon l
l l
SA. The media of the sand filters is expected to last indefinitely and the resin is expected l
to last at least five years. -If needed, the resin can be disposed of by incineration at - l SWUR.
l e
' Typical uranium concentrations of Lagoon SA solutions fed to the IX column are 1-2 ppm and corresponding effluent concentrations are 0.1-0.2 ppm. During the loading cycle from 500,000 to 1,000,000 gallons of waste solution are passed through the column to load from 4-8 kilograms of uranium on the resin column.
I tacmmwows January 18,1993 10-43 I
j SPc-ND.3330.947 (R4/0792) i
SiemenS Power Corporati6n - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM4227, NRC DOCKET NO. 70-1257 ~
PART 11 - SAFETY DEMONSTRATION REY.
The basis for criticality safety is concentration control. The uranium concentration in any part of the system is maintained at less than 50% of the minimum _ critical concentration.
The highest uranium concentration in the system is that of the loaded ion exchange resin.
, Typical uranium conce: trations of the resin just before elution are less than 10% of the
{ minimum critical concentration. A Criticality Safety Analysis has shown that all parts of l the system are subcritical even under abnormal conditions of the transfer of uranium j bearing lagoon solids to the first sand filter or saturation of the ion exchange resin with __
uranium. The facility is covered by the existing criticality accident detection and alarm-system.
The system is monitored for uranium buildup by sampling the solid phase of Lagoon 5A semiannually and analyzing for uranium. The sand filters and resin bed are also sampled i
and analyzed for uranium semiannually. In addition, the resin is inherently safe since it saturates with uranium at less than 140 gU/t. Buildup of uranium on the column is
' monitored by process control and accountability samples.
For fire detection there are rate-of-rise / fixed temperature detectors in the ceiling. These detectors set off alarms locally, at the Central Guard Station, and the Richland City Fire -
Department. The ion exchange room has a hand-held fire extinguisher. There is a two-hour rated fire wall between the original building and tne new addition and a similar fire wall between the outside storage area for sulfuric acid and the building housing the lon exchange system.
l There are no gaseous or particulate releases since all the radioactive materials are in i liquid form in closed vessels or in large double lined lagoons. The release of radioactive
! materials from process equipment is prevented since all vessels and associated piping
' are designed to withstand a pressure of at least 100 psig versus the maximum pump 3
discharge pressure of 38 psig. Radiation work shall be controlled through the Radiation I Work Permit System. All operations shall be conducted within the ALARA concept.
The environmental impact of the ion exchange process for treating Lagoon SA solution is judged to be insignificant. The equipment is located in a building within the restricted area which is committed to industrial use. The equipment is located in an area specifically designed to contain any spills or leaks. There are no gaseous effluents or l increases in the quantities of radioactive waste generated. All underground transfer lines i entering and leaving :the new facility are completely double-encased (inner pipe -
' surrounded by a sealed secondary plastic containment shell),,with. electronic leak 4
detection systems that alarm locally and in the conversion Une 2 control room. The -
primary pipes are tested hydrostatically annually and the secondary pipes biennially. The :
process generates small quantities of additional chemical wast _es, but this is more than offset by the positive environmental impact of reducing the quantities of uranium l
i discharged to the Richland city landfill.
i AMENOMENT APauCATON OATE.
P AGE NO :
SPC-ND 3MO,947 (R 907/92) w
.wm.--
NT" Siemens Power Corporation - Nuclear Division EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO SNM 1227, NRC COCKET NO. 70-1257 PART ll - SAFET( DEMONSTRATION
- REV, 10.4.4 Lanoon Uranium Recovery (LUR) Facility Description The LUR Facility is provided to recover LEU from stored high uranium content liquid chemical wastes (see Section 1'O.4.1). Following uranium recovery, the waste is treated for ammonia removal (see Section 10.4.2), then disposed to the municipal sewer.
The LUR Facility is located adjacent to Lagoon 4 as showr, on Figure ll10.1. Tne equipment consists of six process vessels, one chemical makeup vessel and associated pumps, piping and litters. A brief description of the major equipment is given in Table ll-10.2 and the equipment layout is depicted in Figure 1110.30. The equipment is not 1
housed, but is pFtlally covered. The process equipment is not freeze-protected and is, j
therefore, shut down and winterized during cold weather, 1
A process flow diagram for the uranium recovery system is presented in Figure 11-10.31.
Approximately 4000-6000 gallons of high uranium content waste is pumped into the precipitator. The uranium is precipitated from solution by addition of a reductant and l
allowed to settle. At the end of the settling period, the supematant is decanted to lagoor, storage. This procedure is repeated until the total precipitate accumulated in the precipita- :
tor vessel reaches the desired batch size. The uranium precipitate is slurried to the 4
d washer tank and water-washed for extraneous chemical removal. The washed precipitate is then slurried into a container / dissolved in aluminum nitrate solution, pumped through a centrifuge to a plastic 55-gallon drum, and placed in storage. The recovered uranium is purified for reuse through existing solvent extraction facilities.
A vont system is in place for terr. oval of NO, fumes generated during the dissolving of the -
precipitate. At this time, an upgrade to the vent system is being planned with a scrubber, HEPA filtration and air sampler, in addition to routine processing of' lagoon solutions, the ' centrifuge at LUR is used for separating mop powder solids after processing in ELO.
The basis for criticality control is mass control. The mass in any vessel is maintained at less than 45% of the minimum mass required for criticality. The typical mass in any vesselis usually less than 30% of the minimum critical mass.= A minimum spacing of 3; ft is maintained between all process vessels.
10.4.5 Solids Uranium Recovery Facility l
'4 The lagoon Solids Uranium Recovery Facility consists of the solids teach pit, the sand trench, and lagoons. Two 48-inch diameter vibrating screens are used to separate the.
solids into fractions; The solids are pumped as a water slurry from the sand trench to the
- vibrating screens. None of these facilities are sheltered, a
i i
MENOMENT ADPUCATON DATE:
PAGE NO.:
January 18,1993 10-45 l
SPC-ND3330.947 (R-1i0h92) 3
Siemens Power Corporation - Nuclear DiviSlon EMF 2J SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO 701257 P RT li-SAFETY DEMONSTRATION REV.
The slimes and fines in the sar$d trench and lagoon solids contain essentially all of the uranium. On a volume bhsis, the slimes and fines are about 20% of the solids volume,-
and the remaining 80% is sand.
In order to facilitate the recovery of the uranium and the disposal of the solid wastes, the solids are separated into five fractions. The separation into the three fractions is achieved by first screening the material to remove the greater than 3/8-inch material. The undersize material is mixed with water and pumped to a 48-inch diameter vibrating screen for separation into greater than 20 mesh, greater than 150 mesh, and less than 150 mesh fraction. A subsequent vibrating screen is used to' separate the greater than 80 and greater than 150 mesh materials and to increase the efficiency with respect to removal of material less than 150 mesh.
The water and less than 150 mesh material bearing the uranium is discharged to Lagoon 3 for temporary storage and future uranium recovery. The greater than 150 mesh fraction is collected in the solids pit. The greater than 80 mesh materialis combined with the greater than 150 mesh. The greater than 20 mesh material is combined with the greater than 3/8-inch material and is held in drums and/or the sand trench until all of the sand is processed. The material is washed with water in a small cement mixer in order to remove the sand and slimes, These solids are discarded as ground cover in the lagoon area.
10.4.6 Solid Waste Uranium Recovery (SWUR) Facility Description l The Solid Waste Uranium Recovery (SWUR) facility is designed to incinerate combustible The j
l uranium-contaminated w'astes for volume reduction and uranium recovery.
l incinerator, though designed.to meet hazardous waste incineration criteria, is not
! permitted as a hazardous waste incinerator. The incinerator and auxiliary systems are
{ located in Room 173 of the Specialty Fuels Building (See Section 10.1.1).
l l The process is divided into four systems: feed preparation, waste incineration, offgas
)
treatments, and ash handling.
)
10.4.6.1 Feed Preparation Solid wastes generated in the n0 clear fuel fabrication activities at SPC are sorted at points ['
of generation to separate dangerous wastes from nondangerous solid wastes. The dangerous wastes are packed in plastic-lined 55-gallon DOT 17H metal drums for onsite l l mixed. waste storage. The nondangerous wastes are sorted into combustible.and noncombustible waste fractions in the UO Building. The noncombustible wastes are 2
surveyed item-by Item for uranium content and packaged for compaction and/or disposal at a licensed radioactive waste burial ground. The combustible wastes are packaged in plastic-lined 55-gallon DOT-17H metal drums' for storage prior to incineration. All AMENDMENT APPUCATON CATE-PAGE No.:
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Siemens; Power Corporation - Nuclear Division
- EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257
PART ll-SAFETY DEMONSTRATION REv_
drummed waste packages are labeled for contents as well as weighed and assayed for uranium content prior to storage, disposal, or incineration.
The combustible waste packages are transferred from storage to the SWUR facility where the contents are again sorted as described above. This second sort provides additional opportunity to verify that no dangerous wastes are present in the feed stream. The '
3 combustible wastes are then packaged into plastic lined 3.5 ft cardboard boxes for feed to the incinerator, The incinerator feed boxes are weighed and assayod for uranium _then conveyed to the incinerator hydraulic ram feeder which is automatically controlled to feed ~
the incinerator primary chamber through a guillotine door, The ram feeder has a sealed -
3 loading hopper and can handle up to one yd feed batches. The guillotine door and ram -
feeder are interlocked to prevent simultaneous opening of both doors. The feed hopper and ram face are automatically inerted using a nitrogen fire suppression system if a fire is detected by a heat detector located on the food hopper.
10.4.6.2 Waste incineration The safe batch incinerator has a nominal capacity of 90 kg/hr of uranium-combustible
. waste consisting of paper, plastics, wood, etc. The incinerator is a commercial controll_ed-air unit modified to minimize ash. holdup and to facilitate good carbon burnout and system cleanout.
The unit consists of primary and ' secondary chambers, each constructed of a carbon steel shell intemally coated with a mastic material for acid gas corrosion protection and lined with both insulating and high density castable refractory selected to minimize permeation of uranium contamination and to provide good service life.
j l Both chambers have propane-fueled burners and combustion air. ports.' The primary-chamber is operated at 1400 F - 1800 F, and the combustion air flow is controlled to near.
stoichiometric requirements to promote quiescent burning with minimal particulate =
. entrainment. Combustion products and pyrolysates are passed to -the secondary j chamber where excess air and high temperature (approximately 2000*F) and a minimum j two-second residence time combine to completely burn all combustible gases, including-
' dioxins which may form from PVC incineration. Alarms and-interlocks are provided to prevent feeding the incinerator if either the primary or secondary chamber temperature i is too low or high; if there is low combustion air pressure; if high pressure occurs in the l primary chamber; if high liquid level occurs in the quench column; or if low liquid level
! occurs in the packed column scrubber. An. extremely high chamber temperature or prcpane bumer malfunction automatically shuts down the incinerator, a;
10.4.6.3 Offoas Treatment-
, The incinerator exhaust gas frorn the secondary chamber contains particulates, vapors, l and gases (including acidic gases) which result from the combustion of the cellulose,
{4uesouent aveucation cars.
l PAGE NO.:
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)g S Ac-NO 3330.947 (R4/07/92)
Siemens Power Corporation Nuclear Division eup.2 SPECIAL NUCLEAR MATER lAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 REv.
PA;RT 11 - SAFETY DEMONSTRATION rubber, and plastics present in the waste feed Cooling of the gases and removal of the acidic gases and potentially radioactive particles is accomplished by syctem components which consist of a quench column, a high-energy venturi scrubber, a packed column, a
! mist eliminator, a reheater and HEPA f;1tration modules.
l The quench column is divided into an upper contacting section and a lower sump section in the contacting section, cooling and saturation of the incinerator exhaust gas occur simultaneously by the evaporation of scrub solution liquid. Excess solution collects in the 10-inch diameter sump section while the saturated gas is routed to the inlet of the
, venturi scrubber. An automatic emergency quench system is provided to supply process l water to the quench column if a high column outlet temperature or loss of normal power l occurs.
I The variable throat, high-energy venturi scrubber, located between the quench coLimn and the packed column, removes more than 99 wt% of the offgas particulates. Scrub j
1 l
solution is injected through a nozzle located upstream of the throat. An alarmed interlock l is provided to prevent feeding the incinerator if the scrub solution flow is low. The j
j packed column is designed to slightly cool the offgas and to remove the acidic gases l from the gas phase by countercurrent contact with recycled scrub solution. The gas is l discharged from the packed column through a polypropylene mist eliminator. Alarmed I interlocks are provided to prevent feeding of the incinerator if a high packed column inlet
' temperature.
l The gas enters the electric reheater where it is warmed to a minimum of 35 C above the saturation temperature. This heating reduces the relative humidity of the gas to prevent i
! wetting of HEPA filters. The reheater is controlled by a silicon controlled rectifier which l
l maintains the proper temperature difference from the reheater inlet to the filter outlet.
- Alarms and interlocks are provided to prevent feeding of the incinerator if a high heater j-j differential temperature or high filter inlet temperature occurs.
l j
i l
l The offgas module contains the prefilter and two banks of HEPA filters. The stainless l
i steel module housing is designed and reinforced to withstand the 150-inch H O vacuum l
2 l to which it may be exposed. DOS testing of the final HEPA filter bank for verification of 99.95% removal efficiency for 0.8 micron particles can be accomplished.
i l Particulates that have been scrubbed from the gas stream are removed from the scrub i
- solution by the filters. The filter elements are made from combustible materials so that j once they are expended, they can be burned in the incinerator. Minimum expected j
replacement period between element changeout is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
i
, The scrub solution liquid is circulated by redundant pumps to insure a continuous stream of scrub solution liquid. Automatic switchover of pumps occurs upon on-line pump failure. Scrub solution liquid is cooled by a plate-type heat exchanger Cooled liquid is j
l 1
P AGE NO; AugsovENT ApptGTON DATE i
SPC-ND.3330.947 $110742)
=
1 SiemenS_ Power Corporation - Nuclear Division EuF2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257'-
PART ll - SAFETY DEMONSTRATION REvi
~
I used to improve acio gas absorption and to reduce the packed column discharge gas temperature. An alarmed interlock is provided to provent foeding the incinerator if a high cooler outlet temperature occurs. Caustic addition to the system is automatically controllod by the pH controller in the packed column, scrub solution liquid line, i
Scrub solution Nacl concentration is maintained at 6% in order to prevent corrosion of metal components. Other major chemical constituents of the scrub solution liquid are Na CO (from CO absorption),and Na SO (from sulfurcompounds presontinthe paper 2
3 2
2 4
' products).
A total dissolved. solids analyzer, which basically works on solution conductivity, is provided to control the blowdown stream. The blowdown stream is proportionally sampled and discharged to SPC's surface impoundment system (see
- Section 10.4.1).
l 10.4.6.4 Ash Handlina
! Ash formed from the combustion of wastos is pushed along tho hearth by incoming foed i and by an internal ash plow. The ash passes through an ash gate into an ash cooling chamber located at the end of the hearth. The cooled ash is discharged periodically into 30-gallon DOT 17 H metai drums. Each ash drum is homogenized and sampled for-uranium and U 2351sotopic content and its net weight is determined. The drums are then j stored for future recovery of the contained uranium.
(
! 10.4.7 Plutonium Contaminated Waste Storaae A waste storage facility is provided for storing Pu-contaminated waste which romains from a previous mixed oxide fuel fabrication facility. The Pu concentration in the contaminated waste is greater than allowed for Class C waste and therefore no disposal site exists which is licensed to receive this waste. The facility is described below and depicted in; i Figure Il-10.2.
h The storage facility is located in Room 162 of the SF Buildingc The facility is a below-grade room (approximately 12 x 20 x 20 ft deep) constructed of reinforned concrete and
- covered by steel floor grating overfald with steel plate. The room contains a sump for liquid collection which is monitored by a liquid level alarm. A sump pump is installed
, which can be manually activated and which discharges to a waste retention tank south l of the UO Building.
2 Drum storage is on steel grating to _ support the drums off the concrete floor and on a f
mezzanine also fabricated of_ steel grating. Ingress and egress for personnel and equipment is from the top of the room.
The room is ventilated. Air is drawn down from the roof and exhausted near floor level through one stage of HEPA filtr'ation into the SF Building exhaust system. The exhaust AMENOMENT AP%CATON DATE, PAGE NOa January 18,1993 10-49
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socwo2no so me
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SiernenS Power Corporation - Nuclear Division Eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 PART li - SAFETY DEMONSTRATION REv.
air is continuously sampled ar d monitored prior to the installed HEPA filter. The air sample is analyzed weekly.
10.5 Elre Protection 10.5.1 Buildina Codes and Standards I
All permanent buildings at the SPC Engineering and Manufacturing Facility were constructed in accordance with the applicable sections of the following building codes and standards.
I UBC (Seismic Zone 11)
Uniform Plumbing Code Uniform Mechanical Code Uniform Fire Code National Fire Codes (NFPA)
National Electrical Code ANSI-C1 ASHRAE Standards Washington Administrative Code, Chapter 296-24 Washington Administrative Code, Chapter 296-44 I
Richland Municipal Code and Zoning Regulations Richland Municipal Ordinances Numbers:
3777 (adopt. Building Code) i 3877 (adopt. Plumbing Code) 3977 (adopt. Mechanical Code) 10.5.2 Fire Protection Llability inspections i SPC has elected to self-insure with regard to property damage. American National l Insurers (ANI) schedules a fire protection audit of its' policy holders, among whom is SPC, approximately every year by an acknowledged fire protection consultant. Richland's Department of Fire and Emergency Services conducts annual fire protection inspections of SPC's Engineering and Manpfacturing Facility.
i l The most recent copies of these audits and inspections is appended (see Appendix A).
10.5.3 Fire Protection Proaram
{
I i
10.5.3.1 Combustible Solid Waste Handlina and Storace j
f Outside metal waste containers are provided by the City of Richland for clean wastes, j Contaminated combustible wastes are properly sorted into metal boxes or drums, sealed V-
. PAG: NOx
! AMENOMENT APPUCATCN DATE i
sPC.NO 3330.947 (R-1tC7/92}
. SiemenS Power Corporation - Nuclear DiviSica gg.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO.'70.1257 i
PART ll-SAFETY DEMONSTRATION REV.
and stored on an outside pad for future uranium recovery _ or disposal por approved procedures. Combustible wastes generated inside the process and other buildings (either clean or contaminated) are collected in metal waste containers and emptied daily -
into the appropriate waste stor$ge containers.
10,5.3.2 Flammable Llauld Storace Flammable liquids are stored in ' approved safety containers or cabinets near the final-use location. Additional storage for flammabis liquids is provided for in approved safety-cabinets in the warehouse complex.
10.5.3.3 Combustibio Llauld Storane Combustible liquids are stored in approved metal containers near the final-use location.
Additional storage for combustible liquids is provided for in fire-resistant metal warehouses located away from any radioactive material storage areas.
10.5.3.4 Fire Prevention The manifolds for supplying combustible gases to the facility, including backup hydrogen for the sintering furnaces, are located outside the main building structure. All combustible gas distribution piping meets applicable NFPA codes.
Combustible gas burn-off devices and combustible gas dstection equipment are used where necessary to prevent explosion and Cres around sintering furnaces and ovens.
l_
The HEPA exhaust filters in the UO and SF Buildings are protected from high.
2 temperatures and burning debris in the event of fire by automatic deluge systems in the exhaust plenums immediately upstream of the final filter bank.
10.5.3.5 Fire Detection end Alarm Rate-of-rise / fixed temperature heat detectors are used in the facility to detect fires. : This -
fire alarm equipment is installed to provido automatic, as well as manual alarm signals in event of a fire. The system includes an annunciator in the Central Guard Station which i
l _ indicates which zone in the system has actuated (see Figure ll-10.32). A signal is also.
l automatically transmitted to the Richland Fire Department._ The fire alarm is a single-strike
! gong (2 strokes /sec). The fire alarm system is inspected and tested in accordance with
! the applicable, preventive maintenance procedures.
I i
l
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AMENOMD47 ADPUCAYtCN DATE:
PAGE NO.:
.l SPC-ND:3330.947 (R 1/07/92)
Siemens Power Corporation - Nuclear Division
.. -EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257-PART 11 - SAFETY DEMONSTRATION REv.
10.5.3.6 Fire Defenses SPC s Engineering and Menufacturing Facility is located within the city limits of Richland and thus, is served by the Richland Fire Department. The Washington Surveying and Rating Bureau has graded the City as Class 3 in its last survey, The closest Richland fire station is located at the intersection of McMurray and Jadwin Avenue, about 5 road-miles j
from the plant.
The Fire Department estimates running time to the plant to be approximately 6 minutes.
J The City has Mutual Assistance Agreements with surrounding communities, counties and the DOE (which has a fire station at the Hanford 300 Area located 2 miles northeast of the plant site). The DOE fire-fighting staff is well-trained in nuclear fire safety precautions
~'
and has available equiprnent for radioactive fire fighting. The Richland Fire Department '
receives annual training in radiological safety precautions from SPC personnel.
The plant site is fed water from'the north Richland water grid through 10-inch diameter water pipes which enter the plant site from the north and south. The plant loop to the hydrants is an 8-inch diameter pipe. There are 13 fire hydrants on plant site (see Figure 1
ll 10.18). There are Multipurpose ABC, Halon, Met-L-x, CO, BC Dry Chemical, Purple-K 2
Dry Chemical, and AFFF fire extinguishers provided throughout the facility at selected locations. These fire extinguishers are inspected and tested in accordance with the L1 applicable preventive maintenance procedure.
-l SPC's Plant Emergency Response Teams (PERT) receive annual training in or incipient il i fire-fighting techniques. The Richland Fire Department has the main responsibility for fighting fires on the plant ' site.
~
10.5.3.7 Responsibilities j
The Manager of Safety, Security, and Ucensing has the responsibility for inspecting and i
. testing the plant fire extinguishers.
I The Manager of Plant Engineering has the responsibility for inspecting and testing the plant fire alarm system.
10.6 Criticality Accident Alarm System
(
' The criticality accident alarm system used in the SPC facilities employs neutron criticality i detectors (NCDs), which are operated in two-out-of n (where n = 3 to 6 per comparator l
, panet) coincidence to minimize the possibility of spurious trips due to NCD malfunction j
or response to radiation other than neutrons characteristic of a criticality accident.
i L
tumouesmac4ron oire.
pace no.:
SPC-ND-3330.947 (R-1/07!92) t
i-Siemens Power Corporation Nuclear Division sur.;>
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257-l PART 11 SAFETY DEMONSTRATION REVm The SPC criticality accident alarm system consists of NCDs, comparator units, associated control panels, an annunciator panel, and howlers. Each comparator unit is capable of monitoring the failure and trip signals of up to six NCDs.
Each NC. consists of a BF or Ho3 ube (externally moderated) with associated pulso t
3 amplifior. Jp circuits, performanco audit circuits, and associated power suppilos.
Falluto audit circuits chock the operation of each BF tubo, pulso amplifier, multivibrator, 3
and low and high voltage suppilos by requiring a minimum background count rate of 100 counts por minute. This background count rato is provided by an internal radiation sourco in each BF tubo. If the minimum background is not detected by tho audit circult, 3
a failuro (indicating malfunction) is signaled. Such failuro signals do not interforo with operation of the criticality accident alarm system.
Because tho trip circuitry is not audited, redundant trip circu!ts are provided in each NCD.
Failuro and trip signals from all NCDs are fod to comparator units. Rodundant trip detection is provided in the comparator units. The comparator panels display all failuro and trip signals. When two or more NCDs connocted to the samo comparator unit are tripped, tho criticality accident alarm (howlers) is activated.
An annunciator unit monitors the status of the comparator units, and an audible alarm is -
actuated in the Contral Guard Station in the event that the annunciator unit detocts either a failure or trip signal.
The minimum detectable criticality burst width for the SPC criticality accident alarm system -
is 50 microsoconds.
An overall system rollability test le conducted quarterly.
The trip point of each NCD ls sbt sufficiently high to minimize falso alarms. The system is designed to trip the alarms within 0.5 seconds when exposed at 5% above the trip
- point, 1
f I
January 18,1993 10 53 sPC ND.3330 947 (Rm0M2) i
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s SiemenS Power Corporation - Nuclear Division a4 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 l
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PART 11 - SAFETY DEMONSTRATION
-r _..
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i PART ll SAFETY DEMONSTRATION Table 1110.1 Ammonia Recovery Major Equipment I
i 38' X 2' diameter i
1.
Strip Colun',a l
22 tray Outlet Domister Food Tank 11.5' X 8' diamotor i
3,300 gallons l
Agitated i
i 3
Scrubber Bottom - 10' X 18" diameter i
I 8' packing
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8' packing i
4.
Distillate Tank 9' X 3' diamotor l
400 gallons j
i 5.
Ammonium Hydroxido Storage Tank 24' X 14' diameter j
i 28,000 6.
Sodium Hydroxido Storage Tank 24' X 14' diameter 28,000 gallons I
0 7.
Cooling Tower 2.5 X 10 BTU /HR i
8.
Transformer 1000 kVA l
9.
Steam Boiler 945 Kw i
I i
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' I AUI Aw snVE NT AW C ATON OAlf January 18,1993 10-54 l
A SPC ND 333*j 947 :R-uC7$2)
l Diemens Power Corporation - Nuclear Division Fur 2 SPECiAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i
j PART 11 SAFETY DEMONSTRATION REV.
PART 11. SAFETY DEMONSTRATION Table 1110.2 LUR Process Equlpment t
I TANKS i
T-650 Precipitator #1 (6.000 gallon) i T-651 Precipitator #2 (6,000 gallon)
T-652 Precipitator Washef #1 (350 gallon)
T453 Precipitato Washer #2 (350 gallon)
T 054 Filter Wash Tank #1 (70 gallon)
T455 Filter Wash Tank #2 (70 gallon)
T 656 Precipitation Agent M!x Tank (50 gallon)
T-660 Dissolver Vessel (100 gallon)
T461 Dissolver Vessel (100 gallon)
T 662 Dissolver Vessel (100 gallon)
T-663 Dissolver Vessel (100 0allon)
PUMPS P-650 Precipitator #1 Slurry Pump P451 Precipitator #2 Slurry Pump P452 Precipitator Washer Decant Pump P453.1 Decant Product Pump (port ible)
I ANN Pump (portable)
P453.2 P 654 Filter Wash Pump #1 P455 Filter Wash Pump #2 P456-Precipitation Agent Makeup Pump P457 Precipitation Decant Pump 7
P458 Lagoon Waste Feed Pump P-659 LUR Waste Transfer Pump FILTERS. '
i F452 Washer Decant Filter (25 30 micron)
F 657,1 Precipitation Decant Fittor (5-10 micron)
F457.2 Precipitation Decant Filter (5-10 micron)
F457.3 Precipitation Decant Filter (13 micron)
F457.4 Precipitation Decant Filter (13 micron)
F 658 Lagoon Feed Filter (200 mesh)
AGITATORS A 650
'Precipitator #1 Agitator A451 Precipitator #2 Agitator A 652 Precipitator Washer #1' Agitator A453 Precipitator Washer #2 Agitator A454
_ Filtor Washer #1 Agitator l'
A 655 Filter Wacher #2 Agitator i
A456 Mix Tank Agitator I
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January 18,1993 55 w-( *.
SPC-ND.3330 9471R UO7/92) l L--
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SiemenS Power Corporation - Nucl0ar DMSlon sun.2 SPECIAL NUCLEAR MATERidL LICENSE NO. SNM 1227, NRC DOCKET NO,701257 i
PART ll SAFETY DEMONSTRATION REV.
LIST OF FIGURES FIGUGE i
1110.1 Plant Equipmont Layout Sito Plan 11-1 0. 2 Plant Equipment Specialty Fuel Building 1110.3 Plant Equipment Layout UO Building Il-10.4 Plant Equipmont Layout UO Building 1110.5 Plant Equipment Layout UO Building ll 10.6 Plant Equipment Layout UO Building ll 10.7 Plant Equipment Lay'out UO Building ll 10.8 Plant Equipment Layout UO Building ll 10.9 Plant Equipment Layout UO Building 1110.10 Plant Equipment Layout UO Building 11-10.11 Plant Equipmont Layout UO Building ll 10.12 Plant Equipment Layout UO Building Il 10.13 Plant Equipment Layout UO Building ll 10.14 Plant Equipment Layout UO Building ll 10.15 Plant Equipmont Layout UO Building 1110.16 Plant Equipment Layout U Building 1110.17 Plant Equipment Layout EL Building ll-10.18 Horn Rapids Road Sito_ Arrangemont Firo and Water Supply ll 10.18a Horn Rapids Road Site Arrangement Sanitary Drain 1110.19 Simplified Schematic HVAC System - SF 3ullding SWUR Facility 1110.20 Simpliflod Schomatic HVAC System SF Building Production Facility ll 10.21 Simplified Schematic HVAC System Original UO Building 2
1110.22 Simplified Schomatic HVAC System - UOp Building Line 2 Conversion Area 1110.23 Simplified Schomatic HVAC System Mafn (South) Addition l
1110.24' Simplified Schomatic HVAC System U O Facility a8 1110.25 Simplified Schematic' HVAC System ELO Building 11-10.26 Simplified Schematic HVAC Systom_ ELO Building Addition-1110.27 Simpliflod Schematic HVAC Sy,,..;;,- Contaminated Clothing Laundry Facility ll 10.27a Simplified Schematic - SWUR Incinerator Shroud Cooling System ll 10.28 Plant Equipment Layout ARF _ Building ll 10.29 Ammonia Recovery Waste Management Facility Engineering Flow Diagram Il 10.29a Flow Diagram Lagoon SA Sower lon Exchange Project 1110.30 Plant Equipment Layout - LUR Facility 11-10.31-Engineering Flow Diagram - LUR Production Facility ll 10.32 Fire Alarm System l
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Slomens Power Corporation - Nuclear Division ew.2 SPEOIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REv.
15.3.1.2.5 Eersonnel Monitoring All personnelwear a TLD dosimotor for the purposo of recording exposure to ionizing radiation. The dosimotor is processed at intervals described in Paragraph 3.2.5.2 of Chapter 3 of Part 1.
15.3.1.2.0 Dionssay/Lunn Counts - Urino specimons from all employcos who routinofy work in the contaminated radioactivo material areas of the ELO Building are obtained and analyzed on a routino frequency. Additionally lung counts are rout:nely performed. The frequency and associated action levels of urinalysis and lung counts are described in Paragraph 3.2.7 of Chapter 3 of Part 1.
15.3.1.2.7 Rnspiratory Protection Respiratory protectivo equipment is available and may bo used in accordance with approved proceduros and within ostablished limits. Paragraph 3.2.3 of Chaptor 3 of Part I describes the limits above which respiratory protection is required.
15.3.1.3 Fire Protection Tho floor plan for the ELO Facility is shown on Figure 1110.17. The basement aroca are constructed of poured in-place concreto walls and floor slabs. The ground floor construction (approximately 70 x 172 x 12 ft high) is of concrete block on pourod-in-place -
skirt walls. The inner sido of all exterior walls are insulated and covered with fire rated gypsum board. The gypsum panelJoints aro tapod and sealod, and the interior surfaces are suitably painted. The interior partitions throughout the building, used for process control, are either concrote block or fire rated gypsum board. The roof is made of stee!
dock platos supported on stool trusses, covered with insulation, and a 20-year, builtup roof system.
The fire loading of the building is kept to a minimum through monthly inspections described in Paragraph 2.6.4 of Chapter 2 of Part 1.
Firo extinguishers are strategically positioned throughout the building and inspected monthly. Fixedhato-of-rise temperature sensors throughout the building provide fire alarm capabill,ty.
15.3.1.4 Environmental Safety 15.3.1.4.1 Containment / Confinement Material processed in the ELO Building is i
l contained or confined in open or closed primary containors for UO or U 033 2
powders and UO Pollets; tanks for uranyl nitrate (UNH); tubular glass, j
2 plastic, fiberglass or metal columns for various solutions going through i
solvent extraction or lon exchange; hoods for powder and pellets; and j
furnaces for calcining powder and sintering pellets.
.j AMENOMENT APPt4ATON DATE:
PAGE NO.:
i
. August 26,1992 15-37 SPC ND 3330 947 (R.t974h
SiemonS Power Corporation - Nuclear Division eg.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i
PART11 SAFETY DEMONSTRATION nev.
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15.3.3 Laboratory Operation 6 15.3.3.1 Description of Operations The laboratorios in the ELO Building are research and development facilities supporting all the steps of the fuel manufacturing process as well as materials rosearch.
15.3.3.2 Criticality Safety I
All the laboratorios operato under either safe batch or safe slab controls, in those i laboratories where more than one safe batch is allowed, spacing between safe batches is maintained. Spacing is also maintained between safe slabs and other types of arrays, i
15.3.3.3 Radiation Protection i
! In those laboratories which handle readily dispersible uranium HEPA filtered exhaust hoods are used to confino such material. Radiation survey equipment is provided and surveys are required when leaving a contaminated area. Air sampling and regular i
equipmont/ facility survoys are also undertaken.
I 15.3.3.4 Fire Protection l Fixed /rato-of rise temperature sensors which activate fire c! arms are present in the
- laboratories as are portable fire extinguishers.
15.3.3.5 Environmental Safety
! Uquid offluents which could contain eranium go through the ELO sump. Gaseous
! effluents are doublo HEPA filterod.
l 15.4 Warehousina and Storace 15.4.1 Warehouses i
15.4.1.1 General Safety Conditions There are three warehouses where SNM is routinely handled and stored: the Radioactive Materials Storage Warehouse; the Fuels Storage Warehouse; and the UNH Drum Storago l
Warehouse. The safety conditions for those warehouses will be discussed collectively.
l I
The Radioactive Materials Warehouse is used to lead containers of pellots into.outor containers for shipping. it is also used to store archive sample and drums and buckets
! of UO and U 0 powder and UO Pellets.
2 33 2
I tMENDedENT APPLCATION DATE-PAGE No.:
January 18,1993 15-40 j
sPC ND:3330 947 (R.uo742)
_m SiemenS Power Corporation - Nuclear Division ew.a SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 f..
PART ll. SAFETY DEMONSTRATION REV-Ig___
4 l SPC produces UNH solutions as an intormedicto product from the solvent extraction recovery of uranium from gadolinia bearing materials and form lagoon recovery product solutions. The UNH Drum Storage Warehouse provides heated storago so tho drums of UNH can be safely stored and handled during subfreezing weather.
Tho Fuels Storago Warehouse is usod for unloading and storing incoming scrap prior to its being recovered.
15.4.1.1.1
.Criticanty Safety Criticality Safety for powder and pollets includes mass, moderation control and nuclear polson mechanical devices for largo barrels; mass and spacing for buckets; mass, geometry (slab height) and spacing for innor shipping containers; and uranium concentration and slab height for UNH drums. Enrichment controls are also employod.
15.4.1.1.2 Eadiation Protectio _n The uranium is stored in closed containers. Routine monthly surveys as well as survoys on incoming and outgoing containers are performed to ensure that thoro had been no loss of containment of contents-.
15.4.1.1.3 Fire Protection The warehouses are constructed to be noncombustible and are equipped with fixed temperature /rato-of rlso detectors which trigger tho fire alarm. There are also manual fire alarms and portable fire extinguishers in the warehouses. Flammable liquids are stored in firo proof cabinets.
15.4.1.1.4 Environmental Saf,ety Inner shipping containers of uranium brought into those warehouses are closed.,
incoming outer shipping containers are opened and surveyed for contamination. Loose contamination is vacuumed by a vacuum equipped with a HEPA filter, f.
i 15.4.2 Storace Areas i
15.4.2.1 General Safety Conditions Thore are several pormanent and temporary storage areas on the SPC site. -Theso !
includo UFg cylinder storage (discussed in 15.1.2.1), loaded fuel assembly shipping container storage, loaded powder and pellet shipping container storage, scrap and waste f drum storage, and other temporary storage areas (e.g. sea containers).
AMENDMENT APouCATON DATE PAGE NO2 January 18,1993 15-41 j
SPC-ND 3330 947 (Rr v0W92)
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Siemens Power Corporation - Nuclear Division
- sur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PARTll SAFETY DEMONSTRATION REV.
l 15.4.2.1.1Criticaj lv Safety Loaded shipping containers are stored in arrays which are limited in sizo by the criticality safety limits proscribed by the NRC/ DOT container cortificatos. Other storago arrays (o.g.
scrap and wasto drums and bner pollot shipping containers) are controllod by goometry, onrichment end mass por contsiner limits.
15.4.2.1.2 Badiation Protec11oj The uranium is in closed containers and is surveyed for radioactivo contamination prior to going into storago. The areas are also routinoly (monthly or quarterly) surveyod.
15.4.2.1.3 Fire Protection l
Tho covered shipping container storage area is equipped with a sprinkler system. Thoro-are fuol assembly shipping containers with woodon ovorpacks stored there. All other shipping containers are all metal and thorofore noncombustible.
15.4.2.1.4 Environmental Safety Tho uranium is contained in closed containers.
15.4.3 Laaoons and Lenoon Systems 15.4.3.1 General Safety Conditions j
l Thoro are six lagoons, the sand trench, and the leach pit plus two uranium recovery
' systems, LUR and the Lagoon SA IX, whero SNM in varying concentrations is stored and rocovered. The safety conditlohs of those areas are discussed collectively.
Lagoons - There are six lagoons in the lagoon system. Each lagoon is double lined with cither hypalon or high density polyethyleno (HDPE) and two of the lagoons have an HDPE covering. Between the liners is a leak detection system. Below the bottom liner is a potromat liner which is also equipped with a leak detection system, The lagoons accept waste from various chemical operations. The wastos a:s segregated according to their sourco and chemical content for reprocessing to reclaim usable. constituents.-
After recovery, the waste is then prepared for sewering to the Richland public sowor-system. Fencos have bon orocted around the lagoons and appropriato radiological L-warning signs exist.
[
Sand Tronch - The sand tronclI holds sand which was removed from various lagoons during the mid 1970's. _The sand is washed with water to remove most of the chemical l'
AMENDMENT APPLCATON DATE.
PAQs NO.:
g January 18,1993 15-42
. t SPC ND.3330 947 (4'.07/92:
A
Siemens Power Corporation - Nuclear Division ra r.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227 NRC DOCKET NO. 701257 PART ll SAFETY DEMONSTRATION REV.
and radiological contaminants and scrooned. The finos and water go to Lagoon 3 and the solids go to the loach pit.
Loach Pit Tho loach pit collects washed sand from the sand tronch oporations. Any liquid which drains from tho sand is pumped to Lagoon 3. The sand is usod as backfill in the commercial radioactivo burial facility at Hanford, Washington.
Lagoon Uranlurn Rocovery (LUR) System In the LUR process, Lagoon 3 solution is pumpod to tanks in the LUR facility. Sodium hydrosulfito is then added to procipitato the uranium. (Other motals as impuritlos also precipitato.) The liquid is decanted and pumpod l to Lagoon 4 and the solids are contrifugod. The contrato is pumped to Lagoon 4 and the i solids ate placed into a drum whero they are dissolved using aluminum nitrato. Onco the I solids aro dissolved, the uranium is recovered by solvent extraction.
Lagoon SA lon Exchango (lX) System Effluent from Lagoon SA is fod to tho Lagoon SA IX column to removo uranium beforo tho offluent is sont to the Richland public sower system. The offluont is normally loss than 2 pprn uranium as it is fod to the IX column and loss than 0.1 ppm uranium as it leaves the IX column. Optimum uranlum removal is obtained at 8<pH<12. When the IX rovin is loaded, clution and regonoration are performed and all liquid streams are sont to Lagoon 3.
15.4.3.1.1 Criticality Saje_ty Criticality safety is assured for the lagoons, sand tronch and teach pit by uranium concentration control inputs to the lagoons are monitored and the concentrations are i
- limited to 1000 ppm U. Lagooh 3 is the only one of theso areas that approachos ihls j limit. Tho lagoon, both solution and sludge, are sampled somlannually and the samplos-l analyzed for U concontration. Procipitating agents aro controlled in Lagoon 3 to koop the
! U in solution and pH is controlled in all lagoons.
The Lagoon SA IX system critic'ality safoty is assured by limiting the U concentration to loss then 140 gulf. This concentration is safe for all vossols in the system. The lagoon solids, the sand from the sancjl filtors and the IX resin are all samplod and analyzed somlannually to confirm this concentration limit.
Criticality safoty in the LUR process is assured by maintaining safe batches in all vossols and adoquate spacing between vessels. Batch controlis maintained by analyzing the l lagoon solution which enters the system to determino how much solution-can be j
l processed while maintaining a_ safe batch.
in all thoso areas the enrichmeryt is limited to SE AdNDUENT APPLCAf ON C ATE:
PAGE NO2 January 18,1993 15 __
SPC-NO.3330 rM7 @ t>0742)
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. -i Siemens Power Corporation - Nuclear Division gar.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll. SAFETY DEMONSTRATION REY.
j 15.4.3.1.2 Radiation Protection The lagoons are within SPC's fenced area and bird alarms ato in use to koop them away from tho wator. The sand tronch is covered. In the LUR and Lagoon 5A IX areas the U-bearing solutions aro in closed contalnors.
15.4.3.1.3 Firo Safety Firo in the lagoons and trenches is not crediblo. Tho Lagoon 5A IX system building contains manual and fixed /rato-of riso temperature sensors to alarm _ a fao and the building is rated noncombustible. The LUR cperation is outdoors and the structuros and equipment aro noncombustiblo.! Thoro aro portablo fire extinguishers available at both the Lagoon 5A IX and LUR.
15.4.3.1 e4 Environmental Safe 3 The lagoons and loach pit are double lined with a leak detection system between the liners to detect leaks prior to reaching groundwater. The sand pit has a singlo linor and is covered when it contains contaminated sand. In addition there are a number of groundwater sampling wells associated with the lagoon system (soo Chaptor 5). -
The Lagoon SA IX system resides in a building addition to the Ammonia Recovery Facility.
The addition is built on a scaled concrete floor with curbs which drains to a main sump.
All U-bearing material is in closed containers or process vessols, in the LUR area, once the solution is pumped from the lagoon, it is maintained in closed process vessels or containers.
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Siemens Power Corporation - Nuclear Division eur.3 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO,701257 PART ll SAFETY DEMONSTRATION nev.
i Fuel rod tubing is processed through the Tube Cloaning Facility (Figuro 11-10.10) prior to insortion into the manufacturing stream. Tho tubing is cleanad and inspected before it is transferred to Room 182 for first ond wolding. Figuro 1110.10 also shows tho equipment arrangement of the south Equipmont Room and the administrativo area on the second floor.
Figuro fi-10.11 shows the space and equipmont dovoted to the rod fabrication -
'l phaso of the rnanufacturing process. Room 182 is a high bay aroa, whero Room 189 has hondroom of ~9 ft. Pollets are removod from the storago cabinets in Room 100 and i
processed through the outgas fumacos in Room 182. After the pollots are outgassed, they are loadod into first-end wolded tubos in the rod loriding glovo boxes. After rod loading, the second end wold is made. The rods are then processed through the helium loak chock, rod assay tester and rod x-ray equipment which is alllocated in Room 189.
After the nondostructivo testing in Room 189, the BWR fuel rods are transferred i to Room 110 (the Etch Room) shown on Figuro ll10.12. The rods aro cleaned in j
cleaning so!utions and etched to removo any surface contaminants, Olfgas from the-otching equipment is exhausted through a scrubber and HEPA filtors. - After etching, the.
t rods are transferred to Room 107_ where they aro processed through high prossure, high-tomporaturo autoclavos. The autoclavos are located in a rolnforced concreto pit ~20 ft doop, Attor autoclaving, the rods are transferred through various Inspection stations to the final rod storago area in Room 193. Aftor the nondestructivo testing in Room 189, the PWR fuoi rods are transforred directly to tho final rod storago area in Room 193.
The bundle assembly, cleaning, inspection and shipping container loading operations are all dono in Room 193 (shown on Figure 11-10.13), Rods are moved from the rod storago area to the rod insortion tables. The fuel bundio is assembled on the bundio assombly table and is then lifted to the vertical position on tho assembly table and moved onto,the bundle inspection granito column. After. Inspection,_ the bundio is -
cleanod, dried, and movod to the storage area or to the shipping container loading area where it is prepared for shipment. Immediately west of Room 193 is Room 195 where cago and spacer fabrication work is accomplished.
Figure 11-10.14 shows the low bay area of the UO Building that is devoted almost -
2 exclusively to tho various Quality Control and inspection functions that are necessary in the manufacturo of nuclear fuel. These areas and/or functions include a physical testing laboratory, metallurgical laboratories, and_a limited number of officos, i
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Siemens Power Corporation - Nuclear Division en2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO.701257 PART 11 - SAFETY DEMONSTRATION REv.
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I Tho north end Equipment Room and administrative areas are shown on Figuros
{ ll 10.15 and 1110.16.
1 10.1.3 ELO Buildina Description The curront ELO Facility consists of an original building constructed in 1974, and an expansion constructed in 1982. Tho original facility consists of ~6000 ft2 on the 2
ground floor and ~3000 ft in tho basomont. Tho addition, which offectively doubled the i
building sizo, utilized the same basic typo of construction. The 1902 addition consisted 2
2 l of ~6000 ft on the ground floor and 4000 ft in tho basoment. The entiro ELO Facility is
' currently operated as a singlo facility and will be treated as such In this Application.
The floor plan for tho ELO Facility is shown on Figure 1110.17. The basomont i
arcas are constructed of pourod in place concroto walls and floor slabs. Tho ground floor construction (~70 x 172 x 12 ft high) is of concreto block on pourod in placo skirt walls.
The innor sido of all cxterior walls are insulated and covorod with firo-rated gypsum board.
Tho gypsum panol joints are tapoa and scalod, and the Interior surfaces are cultably painted. Tho interior partitions throughout the building, used for process control, are olthor concreto block or fire-rated gypsum board. The roof is made of stoel dock platos, supported on stool trussos, covered with insulation, and a 20-year, built up roof system, The compressivo strength of all concreto will exceed 3000 psi and the concrete floor slabs woro designed for 250 psf.
Tho basement area contains a chemical engineoring development area, an engincoring machine shop, the Gadolinia Scrap Rocovery Facility, and other en0 neering l
test facilities. The first or ground fioor contains an Instrument laboratory, metallo0raphy laboratory, wet chemicallaboratorles and several engineering offices, e
~
Tho uranium enrichment in tho various laboratorios is <20 wt% U-235 In solid i
form, and not more than 5 wt% U-235 in liquid form. Activities include all operational
{
stops of fuel manufacturing and process testing.
10.1.4 Contaminated Clothlno laundrv The location of the Laundry Facility is shown on Figure 1110.1 The building is a pre-engineered metal building (12 x 20 x 30 ft high) with a G'9" x 17'9" airlock which.
i provides for access, yet maintains the proper pressure differentials for contamination
, control. The exterior walls are 26-gauge sheet metal and the roof is 24-gauge sheet-j
{ metal, insulated and finished on,the interior. The interior of the roof is a suspended metal -
i
' ceiling grid with acoustical lay-in panels o
- -c" January 18,1993 10-6 t
sPC ND,3330 947 (R*0742)
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Siemens Power Corporation - Nuclear Division Eur.2 i
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll SAFETY DEMONSTRATION nty.
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10.3.7.5 Final HEPA Filter Bank l
t The final HEPA filter bank for tho K25 system is a shoot metal framo and housing I that is fastened to a concreto slab. HEPA filtors rated at 1000 ft / min at 1 inch H O 3
2 pressuro drop are mounted in stool framos. Visualindicators for reading the pressuro drop across the filters are permanently Installed, and means aro provided for in-placo DOP/ DOS testing.
The HEPA filter medium is 100% moisturo resistant fiberglass, ploated over corrugated separators and scaled in firo-resistant plywood framos. The individual filters l are cortified to removo 99.97% of 0.3 micron particles and moet or exceed Military e
I Specification MIL F 51079.
t 10.3.8 ELO Addition HVAC Svstoms Although this building ahdition is physically attached to the original ELO Building, it has its own separato HVAC systems: K45 (supply), K46 (exhaust), and K56 (POG j
oxhaust). Tho building is physically divided with the north portion serving as an office area and the south portion housing ongineering test oporations, an instrument laboratory, several motallography laboratories and various chemical laboratorios. The north office portion of the building is served by the _ original ELO Building offico (K26) supply system (sco Figure 11-10.25) and is separated from the laboratory portion by a sorios of airlocks.
The south portion of the building is served by the K45 air supply and K46 and K56 oxhaust systems.
The gonoral featutos of.the ELO Building addition HVAC systems are a once-through ceiling to-floor airflow (K45) supply air system, a double HEPA filtered (K46) i building exhaust system, and a doublo HEPA-fi!!ored (K56) POG oxhaust system.L A lI simplified schematio of the ELO Building Addition HVAC system is 'shown in Figuro -
11-10.26.
10.3.8.1 K45 Air Supolv Svstom 3
The K45 air supply system provides about 16,000 ft / min of 100% outsido air to l'
the south portion of the ELO addition. Airflows are directional from colling to near floor.
L exhaust air grills or process. hood Inlets, and always away from areas of low contamination potential to areas of higher contamination potential.
l 1
10.3.8.2 K46' Air Exhaust System The K46 air exhaust system removes approximately 17,000 ft / min of alt supplied ll 3
from-the process areas served by the K45 air supply system. The double filter -
arrangement in this system consists of the final HEPA filter bank plus individual or' smaller AMENOMENT APPUCATiONDATE:
P AGE NO :
January 18,1993
= 10-37
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sPCWD WWt (MMD
Siemens Power Corporation - Nuclear Division ag.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REV.
p________--
fittor banks of profiltors and HEPA fittors in tho oxhaust ducts of tho areas or equipment
' servicod. Ductwork in the K46 system is made of galvanized stool.
The K46 syrtem oxhaust air passes dirocily from the final fiitor bank to the oxhaust fans and is discharged from a stack extending 23 ft above the main portion of the UO Building, or 35 ft abovo ground elevation. Tho K46 oxhaust system has a single fuh capacity fan connected to normal power, 10.3.0.3 K56 Air Exhaust System 3
Tho K56 air exhaust system providos approximately 1,000 ft / min vont servico for chomlcal sumps and gadolinia scrap recovery process tanks and effgas-from the dissolver offgas scrubbor. As in the etch process, fumes from thoso sources are corrosivo. The exhaust is passed through a scrubbor, a dryer and double HEPA filters and is dischargod through a separato stack located on the south side of ELO Building.
j This stack extends 50 ft abovo ground lovel. Tho scrubbor is provided to remove acid fumes, nitrous oxido and entralned organics consisting of dodecano and tributal-
[
phosphate. The dryer is used to removo entrained liquids and the filters to removo potential uranium.
The ductwork material in tho K50 exhaust system is stainless stool for ducts l Oronter than sovon inchos in diameter, and polyvinyl chlorido for ducts loss than seven Inches in diamotor. The singlo K56 exhaust fan is connected to normal power.
l 10.3.8.4 Svstoms Controls The HVAC systems are controlled with temperature, pressure and flow sensor
- actuating valving and damper positions to hold temperatures, pressures, and pressuro i
differentials constant in tho various building areas. The building ventilation systems are interlocked so that the K46 exhaust system must bo operating beforo the K45 supply j
system can be startod. Pressuro sonsors are provided for damper controlio maintain a negative pressure (minimum 0.05 inch water gauge)in the laboratory areas relative to the = '
office area and to atmosphere, and to maintain an exhaust duct negativo pressuro between -4 and 12 inches water gaugo. Any loss of instrument air prevents the supply _
and exhaust systems from operating Both the K45 supply tan and K46 exhaust fan are
- Interlocked so that a loss of exhaust duct negative pressure abovo 4 inches water gaugo l
l p(toward zero) will shut down the supply fan or an increase of exhaust duct l
t.
ressure below -12 inchos water gauge will shut down the K45 supply fan and the K46 l
! exhaust fan. The K56 exhaust fan runs continually.
i Automatic audio and visual alarms are activated when any supply or exhaust j
system upset occur. Pressure differentialIndicating devices and airflow quantity meters i
j I
J
' AMENDMLNT APPUCATON DATL PAGE NO.;
January 18,1993 38 l
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SPc-No:3330 9n tFtuoW92)
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SiemenS Power Corporation - Nuclear Division EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REv.
are located in the controllod zones and/or on the main HVAC panoi to provide system and zono operating conditions.
! 10.3.8.5 Doivoo Sysjojn A dolugo system of fog spray nozzlos is installod in tho oxhaust duct a short distance upstream of the final filter banks. If heat detoctors indicato a temperaturo of 140-190*F, the delugo spray is automatically activated. Should tho delugo system be activated by any circumstanco, differential pressure readings across tho final filters will be taken and in placo DOP/ DOS test mado at the earliost opportunity.
10.3.8.6 Final Filter Bank l
Tho final filter bank is encased in a puoured and scaled concroto structure. HEPA 3
! filtors rated at 1000 ft / min at 1 inch H O pressure drop are mounted in wolded, stool 2
j structural framos. Tho HEPA filter medium is 100% moisturo-rosistant fiberglass, ploated i over corrugated separators and sealed in firo-resistant plywood framos. Toh individual filtors are cortified to romvoo 99.97% of 0.3 micron particlos and moot or exceed Miittany Specification MIL F 51079, 10.3.9 Contaminated Clothina Laundry HVAC System i
The general features of.the contaminated clothing laundry HVAC system are a
" onco-through," colling to floor'alrflow supply system and a singlo sta@, HEPA-filtered exhaust system. A simplified schematic diagram of the K41 air supply system and tho K42 a!r exhaust system is shown in Figure 1110.27, 10.3.9.1 K41 Air Supply System 3
The K41 air supply system supplies about 1900 't / min ol100% outside air to the cleaning room and adjoining sorting room. Altflows are trectior al from colling to near-floor exhaust alt grills or hood inlets, and always away fron; enas of low contamination potential to areas of higher contamination potential.
10.3.9.2 K42 Air Exhaust System 3
Air suppiled to the cleaning and sorting rooms, plus infiltration (~2100 ft / min), is -
r exhausted through the K42 oxhaust system. - The single HEPA filter arrangemont in this.
_1 system consists of the final HEPA filter bank and individual profilters located in the
- t exhaust ducts of the two rooms servicod.
The K42 system exhaus't air passos from the final filter bank through a duct alt
'l.
monitor (measures airflow quantities), the main exhaust fan, and is discharged from a j
AMENDUENT M* PLICATION DATEc PAGE NOa January 18,1993 10-39 SPC ND 3330 947 $ 1!0792:.
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Siemens Powor Corporation - Nuclear Division gg.a SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll SAFEW DEMONSTRATION ntv.
_ _.__ _. _. _.I_ _,
i stack oxtending 25 ft aboveground on the southwest sido of tho building. Tho K42 I
< exhaust system has orio full-capacity fan which is connected to normal power. All final
, HEPA filters are in-placo tested and assured to bo 99.95% (minimum) officient for 0.0 l micron DOP/ DOS cold acrosol.
! 10.3.9.3 Sy_stoms Control i
The HVAC systems aro olaborately controlled with temperaturo, pressure and flow sensor actuating valving and damper positions to hold temperaturo, pressuros, and pressuro diffotontials constant in the various building areas. Tho K41 supply air system i
i is interlocked with the K42 oxhaust system to provent operation of the K41 supply air system without the K42 oxhaust system operating. Prossuro sonsors are provided to
- maintain a minimum nogativo differential pressuro of 0.05 lnch water gaugo in the cleaning i room relativo to tho sorting room. The sorting room is maintained at approximately -0.02
' to 0.05 inch water gaugo in respect to atmosphere.
i Tho K41 supply fan is interlocked so that a loss of oxhaust duct negativo prossuro abovo -3 inchos water gaugo (exhaust fan failure) or a signal from the exhaust duct heat l
l dotector will shutdown tho K41 air supply system.
Automatic visual alarms are activated when any supply or exhaust system upset occurs. Pressuro differential indicating devices and airflow quantity motors are located i
j on tho main PVAC panol to provido system and zono operating conditions.
10.3.9.4 HEPA Filter _ Banh i
i j
The final HEPA filters are onclosed in a shoot metal housing that, in tum, is
- mounted on structural stoollogs fastened to a concreto stab, Tho HEPA filtors are rated 3
{ at 1000 ft / min at 1 inch H O pressuro drop and are mounted in welded stool framos.
2 l Continuous air samplers are installed downstream of the filter bank. Visualindicators for
! reading the pressure drop across the filters are permanontly installed, and means aro i
provided for in placo DOP/ DOS testing.
l The HEPA filtor modium is 100% moisture-resistant fiberglass, ploated over j
, corrugated separators and scaled in tiro resistant plywood framos. The individual filters
! are cortified to removo 99.97% of 0.3 micron particles and moot or exceed Military l Specification MIL F-51079.
I 10.4 Radioactivo Wasto Handlino 4
l The facilities and processes which are involved in the handling of radioactive and
! chemical wastos produced by Advanced Nuclear Fuels in Richland, Washington are j
described in the following sections.
j ww w meum on
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l pu on l
January 18,1993 i
10-40 1
SPC ND 3330 947 (R 907521
SiemenS Power Corporation - Nuclear Division Eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REV -
are stored in a planar array of closed containors which ato free of significant, external I contamination, l
A Criticality Safety Analysis has boon performod on such a temporary storage facility. It was dotormined that criticality safety is assured by controls on the geometry of the containers, the not weight of the contained uranium oxido, the H/U within the containor, and the restriction that the containers be arranged only in a sing!o tior planar array. Storago requiroments are posted at tho storago sito.
15.10 UNH Drum Storano Warehouso Slomons Nucioar Power produces uranyl nitrate solutions (UNH) as an
, intermodlato product from the solvont extraction recovery of uranium from gadolinia =
1 boaring materials and from lagoon recovery product solutions. The UNH Drum Storago i
i i
Warehouso providos heated storage so the drums of UNH can be safoly stored and l
handlod during sub-freezing weather.
l A criticality safety analysis has been performed for such storago.
It _was f
dolormined that criticality safoty can be assured by maintaining the drums in a single tior l
and at a uranium concentration of <140 gU/t and <5 wt% U 235. The drum array is i-suberitical even if significant ovaporation takes place or if the uranium in a single dium l
f Is completely precipitated, l
The concroto floor is curbed and coated to provido secondary leak containment i
and facilitato decontamination of possible spills.
j i
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AMENDMENT APP BATON DATE:
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_ January 18.1993 15 17--
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