ML20046B613
| ML20046B613 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 07/23/1993 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML20046B611 | List: |
| References | |
| NUDOCS 9308050245 | |
| Download: ML20046B613 (38) | |
Text
_
"SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i
PART I - LICENoE CONDITIONS REv.
21 1
r_____
TABLE l-1.1 Specific Locations of Authorized Activities Location SNM Authorized Activity l SF Building Pu and PuO -UO Storage and repackaging.
2 2
l contaminated waste i
UO (up to 19.99 wt% U-Storage, blending, pressing,.
2 i
235) sintering, fuel rod loading and l
downloading, fuel rod welding, fuel element assembly; process tests; associated quality control activities.
j I
i Uranium Compounds (up to Waste storage, sorting, 5 wt% U-235) incineration, packaging, and l
j associated quality control activities.
t l
UO Building Uranium Compounds (up to All operational steps of fuel 2
! (including Powder 5 wt% U-235) manufacturing from UF -UO g
2
- Storage) conversion to packaging i
finished fuel elements, scrap recycling and reprocessing; process tests; associated quality control activities.
[
UO (5 to 19.99 wt% U-235)
All operational steps of fuel i
I 2
i manufacturing involving UO ;
I I
2 including associated quality j
j control activities.
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! ELO Building Uranium Compound (up to All operational steps of fuel j
19.99 wt% U-235) manufacturing involving I
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uranium compounds; f
i including process tests and scrap reprocessing.
I i
FCTF Building UO (up to 5 wi% U-235)
Hydraulic flow tests involving I
2 single fuel elements.
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'AM[bbbbPUCATON DATE.
July 23,1993
' PAGE NO.:
j$h
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9308050245 930723 9
src-ND:3330 947 (R-v07/92)
PDR ADOCK 07001257 f
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SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 r
PART ll-SAFETY DEMONSTRATION REv.
h l 10.3.7.5 Final HEPA Filter Bank i
The final HEPA filter bank for the K25 system is a sheet metal frame and housing 3
i that is fastened to a concrete slab. HEPA filters rated at 1000 ft / min at 1-inch H O 2
! 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 DOP/ 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 l
I are certified to remove 99.97% of 0.3 micron particles and meet or exceed Military i
l Specification MIL-F-51079.
j l
10.3.8 ELO Addition HVAC Systems I
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 l
exhaust). The building is physically divided with the north portion serving as an office j
l area and the south portion housing engineering test operations, ar, instrument laboratory, i several metallography laboratories and various chemical laboratories. The north office portion of the building is served by the original ELO Building office (K26) supply system (see 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.
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The general features of the ELO Building addition HVAC systems are a once-l l
l through ceiling-to-floor airflow (K45) supply air system, a double HEPA filtered (K46) l l
- building exhaust system, and a double HEPA-filtered (K56) POG exhaust system. A l sirr.plified schematic of the ELO Building Addition HVAC system is shown in Figure l
' 11-10.26.
i The powder screening station has a vacuum cleaner system associated with it
! which has a HEPA filtered exhaust. The HEPA filter is in-place tested for efficiency and j the vacuum exhausts into the room.
l I
i l 10.3.8.1 K45 Air Supply System l
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i 3
The K45 air supply system provides about 16,000 ft / min of 100% outside air to l
l the south portion of the ELO addition. Airflows aro directional from ceiling to near-floor j
j exhaust air grills or process hood inlets, ano always away from areas of low i
' contamination potential to areas of higher contamination potential.
1 l
l j
AMEfOME NT ATLIC.ATION DATE:
PAGE NO.:
SPC-ND-3330.947 (R-1/07'92)
t SiemenS Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION i
- ngy,
[_
l 10.3.8.2 K46 Air Exhaust System The K46 air exhaust syste'm removes approximately 17,000 ft / min of air supplied
}
[
3 l from the process areas served by the K45 air supply system. The double filter i
arrangement in this system consists of the final HEPA filter bank plus individual or smaller filter banks of prefilters 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 and is discharged from a stack extending 23 ft above the main portion of the UO p
Building, or 35 ft above ground elevation. The K46 exhaust system has a single full
- capacity fan connected to normal power.
10.3.8.3 K56 Air Exhaust System I
I 3
i The K56 air exhaust system provides approximately 1,000 ft / min vent service for j chemical sumps and gadolinia scrap recovery process tanks and offgas from the i dissolver offgas scrubber. As in the etch process, fumes from these sources are l
i corrosive. The exhaust is passed through a scrubber, a heater and double HEPA filters l and is discharged through a separate stack located on the south side of ELO Building.
j This stack extends 50 ft above ground level. The scrubber is provided to remove acid
! fumes, nitrous oxide and entrained organics consisting of dodecane and tributal i phosphate. The heater is used to remove entrained liquids and the filters to remove potential uranium.
I The ductwork material in the K56 exhaust system is stainless steel for ducts l greater than seven inches in diameter, and polyvinyl chloride for ducts less than seven I
j inches in diameter. The single K56 exhaust fan is connected to normal power.
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j 10.3.8.4 Systems Controls l
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The HVAC systems are controlled with temperature, pressure and flow sensor j
} actuating valving and damper pos!! ions to hold temperatures, pressures, and pressure
. differentials 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 -
j system can be 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 j
office area and to atmosphere, and to maintain an exhaust duct negative pressure j
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 j
! (toward zero) will shut down the supply fan or an increase of exhaust duct negative i
t I
wsE* " "
l July 23,1993 10-38 u_.
L J
SPC ND 3330 947 (R 1/07S?)
i
I
.SiernenS Power Corporation - Nuclear Division EM F-2 SPECIAL NUCLEAR MATERIAL LICENSE NO SNM-1227, NRC DOCKET NO. 70-1257 P
PART 11 - SAFETY DEMONSTRATION ngy.
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 i
and zone operating conditions.
(
}l 10.3.8.5 Deluce System i
l A deluge system of fog spray nozzles is installed in the exhaust duct in the K46 l
l system a short distance upstream of the final filter banks. If heat detectors indicate a l temperature of 140-190 F, the deluge spray is automatically activated. Should the deluge l system be activated by any circumstance, differential pressure readings across the final j
j filters will be taken and in-place DOP/ DOS test made at the earliest opportunity.
I j
10.3.8.6 Final Filter Bank The final filter banks in both the K46 and K56 systems are encased in a poured 3
and sealed concrete structure. HEPA filters rated at 1000 ft / min at 1-inch H O pressure 2
drop are mounted in welded, steel structural frames. 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 remvoe 99.97% of 0.3
- micron particles and meet or exceed Military Specification MIL-F-51079.
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' 10.3.9 Contaminated Clothina Laundry HVAC System -
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I The general features of the contaminated clothing laundry HVAC system are a l "once-through," ceiling-to-floor aidlow supply system and a single stage, HEPA-filtered f
l
! exhaust system. A simplified schematic diagram of the K41 air supply system and the K42 air exhaust system is shown in Figure 11-10.27.
10.3.9.1 K41 Air Supply System j
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i The K41 air supply system supplies about 1900 ft / min of 100% outside air to the
! cleaning room and adjoining sorting room. Airflows are directional from ceiling to near-I I
} floor exhaust air grills or hood inlets, and always away from areas of low contamination l
}
potential to areas of higher contamination potential.
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10.3.9.2 K42 Air Exhaust System 7
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l Air supplied to the cleaning and sorting rooms, plus infiltration (~2100 ft / min), is j
! exhausted through the K42 exhaust system. The single HEPA filter arrangement in this l
i A NhNbff APPLICATON DATE:
PAGE NO.:
SPC ND:3330.947 (R4/07/92j
SiemenS Power Corporation - Nuclear Division e u r.2 j
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 j
PART 11 - SAFETY DEMONSTRATION
- ngy, I
i system consists of the final HEPA filter bank and individual prefilters located in the 1 exhaust ducts of the two rooms serviced.
j i
The K42 system exhaust air passes from the final filter bank through a duct air monitor (measures airflow quantities), the main exhaust fan, and is discharged from a stack extending 25 ft aboveground on the southwest side of the building. The K42 exhaust system has one full-capacity fan which is connected to normal power. All final HEPA filters are in-place tested and assured to be 99.95% (minimum) efficient for 0.8 micron DOP/ DOS cold aerosol.
10.3.9.3 Systems Control The HVAC systems are elaborately controlled with temperature, pressure and flow sensor actuating valving and damper positions to hold temperature, pressures, and i pressure differentials constant in the various building areas. The K41 supply air system l is interlocked with the K42 exhaust system to prevent operation of the K41 supply air j system without the K42 exhaust system operating. Pressure sensors are provided to
! maintain a minimum negative differential pressure of 0.05 inch water gauge in the cleaning l
room relative to the sorting room. The sorting room is maintained at approximately -0.02 to -0.05 inch water gauge in respect to atmosphere.
[
The K41 supply fan is interlocked so that a toss of exhaust duct negative pressure above -3 inches water gauge (exhaust fan failure) or a signal from the exhaust duct heat detector will shutdown the K41 air supply system.
Automatic visual alarms are activated when any supply or exhaust system upset i occurs. Pressure differential indicating devices and airflow quantity meters are located 1
! on the main HVAC panel to provide system and zone operating conditions.
10.3.9.4 HEPA Filter Bank l
The final HEPA filters are enclosed in a sheet metal housing that, in turn, is j
mounted on structural steellegs fastened to a concrete slab. The HEPA filters are rated 3
at 1000 ft / min at 1-inch H O pressure drop and are mounted in welded steel frames.
2
, Continuous air samplers are installed downstream of the filter bank. Visualindicators for
. i reading the pressure drop across the filters are permanently installed, and means are I
provided for in-place DOP/ DOS testing.
I 1
The HEPA filter medium is 100% moisture-resistant fiberglass, pleated over l
j i corrJgated separators and sealed in fire-resistant plywood frames. The individual filters l
l are certified to temove 99.97% of 0.3 micron particles and meet or exceed Military l
. ! Specification MIL-F-51079.
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3 AM NDMENT APPLICATION DATE:
PAGE NO.:
1 srcm33acAnaam i
E SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION
- nev, i
10.4 Radioactive Waste Handlina r
i The facilities and processes which are involved in the handling of radioactive and
! chemical wastes produced by Advanced Nuclear Fuels in Richland, Washington are described in the fo!!owing sections.
10.4.1 Lacoon System Description j
The lagoons provide containment for all uranium and chemically-contaminated l liquid wastes generated at Advanced Nuclear Fuels. Natural evaporation, cuntrolled
! waste addition, waste discharge to the municipal sewer and water additions are used to control the volume of liquid stored in the lagoons. Inter-lagoon transfers are periodically 3
- made for both uranium accountability and volume control purposes. Sampling between l
j lagoon liners is conducted monthly to determine if leaks have occurred.
l i
There are six !iquid waste storage lagoons, one solids leach pit, and one sand
, storage pit located along the east boundary of Advanced Nuclear Fuels (see Figure j 11-10.1). The sand storage pit is located irr nodiately west of Lagoon 3. The solids J.ach l
! pit is located immediately west of Lagoc.12. The dimension and capacities o; ne
' lagoons are:
l Estimated Capacity j
6 Laaoon Dimensions 10 Gallons i
l 1
240' x 200' x 3' deep 1.4 2
240' x 100' x 3' deep 0.7 t
3 240' x 350' x 5'6" deep 3.5 1
4 240' x 290' x 6' deep 2.7 l
l 5A 240' x 175' x 7'6" deep 1.6 l
5B 240' x 175' x 7'6" deep 1.6 Leach Pit 40' x 54' x 8'6" deep 0.06 Sand Pit 39' x 300' x 6' deep 0.3 i
j The lagoons and the solids teach pit have a " sandwich" construction; they each
' have two liners made of Hypalon 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 between the Hypalon liners is an array of sample heads. The sand storage l
l pit is single-lined and, therefore, does not have between-liner sampling capabilities.
i i Tubing fro n each of the heads is routed to the berms on both the east and west side of i
l the lagoons where small pumps can be periodically connected. Some additional sampler l
I heads are located between the original Petromat liner and the lower Hypalon liner.
Lagoon 4 is equipped with three " dry wells" below the bottom Hypalon liner. Samplers l
l are located in each dry well. All sampler heads are pumped each month for leak detection j
)
I purposes using small air-driven pumps.
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t Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257
'l PART II - SAFETY DEMONSTRATION nev.
21 s_
purifying it through use of a solvent extraction system.
The clean UNH from this operation is then reacted with aqueous ammonia to form ammonium diuranate.
The precipitate is then centrifuged, dried, and calcined to 00, all within the Scrap Recovery Facility.
2 As in the case of the UNH Facility discussed above, criticality safety is assured in the Scrap Recovery Facility through control of equipment and tank locations and geometry.
Batching of the dissolver is strictly controlled, and product UO is handled only in safe batches. Both 2
the hooding and process equipment are exhausted through liEPA filters, and l protective clothing and eye protection are required for operating personnel safety.
I i
j 15.8.4 Gadolinia Scran Recovnry A separate facility is provided in the ELO Building for recovery of gadolinia scrap from the NAF operation.
This facility, equipped with a dissolver, filtration equipment, and solvent extraction system, produces gadolinia-free uranyl nitrate. The uranyl nitrate may be converted to U'.2 in the Scrap Recovery Facility, or in either conversion line.
Criticality safety in the Gadolinia Recovery Facility is provided by control of the geometry of the solvent extraction equipment and the dissolver, as well as through control of feed and product solution uranium concentration (mass). All process vessels except the powder dissolver and
. the 55 gallon UNH product drums are geometrically safe for the achievable l uranium concentrations of the solutions in the gadolinia recovery process.
j l Safe concentration in the powder dissolver is maintained by batch control j of the powder added to-the dissolver.
Concentration in the UNH product-drums is controlled by specific gravity measurement of the UNH prior to I
its transfer into drums. The amount of tributyl phosphate (TBP) specified for solvent extraction limits the theoretical maximum U concentration of l
the product to slightly more than 20% of the critical concentration in a i
fully reflected 55 gallon drum.
A HEPA-filtered exhaust hood is provided around the dissolver, and l protective clothing and eye protection are required for personnel i operating in the area.
Survey equipment is provided at the exit of this area to monitor hands, clothing, and feet on egress.
15.9 Temporary Storace l
l Advanced Nuclear Fuels produces, among other products, sintered j
uranium oxide pellets for shipment off-site.
There are occasions when l
l pellet production exceeds normal storage capacity and temporary storage l
facilities are required.
In those cases,' the pellets are stored in a l
I PA E NO,:
AMENDMENT APPUCATON DATE:
My8 1993 lbl5 t_._
J SPC-ND 3330.947 (R-1/07/92)
t 1
Siemens Power Corporation - Nuclear Division EM F-2 f
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
I PART II - SAFETY DEMONSTRATION l agv.
I 21 t
I planar array of closed containers which are free of significant, external
' contamination.
A Criticality Safety Analysis has been performed on such a temporary storage facility. It was determined that criticality safety is assured by control s on the geometry of the containers, the net weight of the contained uranium oxide, the H/U within the container, and the restriction that the containers be arranged only in a single-tier planar array.
Storage requirements are posted at the storage site.
- i 15.10 UNH Drum Storace Warehouse l
Siemens Nuclear Power produces uranyl nitrate solutions (UNH) as an I
! intermediate product from the solvent extraction recovery of uranium from I gadolinia bearing materials and from lagoon recovery product solutions.
l The UNH Drum Storage Warehouse provides heated storage so the drums of UNH can be safely stored and handled during sub-freezing weather.
I A criticality safety analysis has been performed for such storage.
It was determined that criticality safety can be assured by maintaining the drums in a single tier and at a uranium concentration of <140 gU/t and
<5 wt% U-235.
The drum array is subtritical even if significant evaporation takes place or if the uranium in a single drum is completely
! precipitated.
I j
The concrete floor is curbed and coated to provide secondary leak
' containment and facilitate decontamination of possible spills.
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[ AMENDVDd AMCMIM DME:
July 23, 1993 15-16 PAGE NO :
l l
... ~. _ _
SPC-ND:3330 947 (R-UO7/92)
SiemenS Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION ggy.
l radiation or heat detection in recirculation or exhaust ductwork, or loss of instrument or
- control air stops the supply fan.
l
< The mezzanine, Machine Shop and test development areas are ma ntained at -0.05 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 l respect to atmosphere and negative to the adjacent Machine Shop area at all times. As j long as the K24 supply fan and K25 exhaust fan plena pressures are maintained within j indicated ranges, the building pressure differentials will be maintained.
.i 10.3.7.5 Final HEPA Filter Bank l
I l The final HEPA filter bank for the K25 system is a sheet metal frame and housing that is 3
I fastened to a concrete slab. HEPA filters rated at 1000 ft / min at one-inch water gauge s
pressure drop are mounted in steel frames. Visual indicators for reading the pressure l
drop across the filters are permanently installed, and means are provided for in-place l
l DOS testing.
l e
The HEPA filter medium is 100% moisture resistant fiberglass, pleated over corrugated l
l separators and scaled in fire-resistant plywood frames. The individual filters are certified i
to remove 99.97% of 0.3 micron particles and meet or exceed Military Specificatior; l
i t MIL-F-51079.
10.3.8 ELO Addition HVAC Systems 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 l
, south portion housing engineering test operations, an instrument laboratory, several j
l
! metallography laboratories and various chemicallaboratories. The north office portion l
l of the building is served by the original ELO Building office d.
, supply system (see
' Figure 11-10.25) and is separated from the laboratory portion by a series of airlocks. The j
j south portion of the building is served by the K45 air supply and K46 and K56 exhaust
- systems, j
i The general features of the ELO Building addition HVAC systems are a once-through l
l ceiling-to-floor airflow (K45) supply air system, a double HEPA filtered (K46) building l
j exhaust systera, and a double HEPA-filtered (K56) POG exhaust system. A simplified i
j schematic of the ELO Building Addition HVAC system is shown in Figure ll-10.26.
l l
\\
The powder screening station has a vacuum cleaner system associated with it which has l
i
' a HEPA filtered exhaust. The HEPA filter is in-place tested for efficiency and the vacuum j
exhausts hto the room.
i AVE A3 PLICATION DAir.
Julp~2371993-~~
-]isiih TO35'
~
l o _._ ___
SPC ND.3330 947 (R 1/07W)
P SiemenS Power Corporation - Nuclear Division EuF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION ggy.
F 1
1 i 10.3.8.1 K45 Air Supply System l
l The K45 air supply system provides about 16,000 ft / min of 100% outside air to the south 3
j portion of the ELO addition. Airflows are directional 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.
l 10.3.8.2 K46 Air Exhaust System I
3 l 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 j
- prefilters and HEPA filters in the exhaust ducts of the areas or equipment serviced.
i l Ductwork in the K46 system is made of galvanized steel.
j i The K46 system exhaust air passes directly from the final filter bank to the exhaust fans and is discharged from a stack extending 23 ft above the main portion of the UO2 i Building, or 35 ft above ground elevation. The K46 exhaust system has a single full l capacity fan connected to normal power.
l
{ 10.3.8.3 K56 Air Exhaust System
! The K56 air exhaust system provides approximately 1,000 ft / min vent service for chemical 3
t l
sumps and gadolinia scrap recovery process tanks and offgas from the dissolver offgas l
scrubber. As in the etch process, fumes from these sources are corrosive. The exhaust j
i
, is passed through a scrubber, a heater and double HEPA filters and is discharged
]
l l through a separate stack located on the south side of ELO Building. This stack extends i
50 ft above ground level. The scrubber is provided to remove acid fumes, nitrous oxide I
j and entrained organics consisting of dodecane and tributal phosphate. The heater is j
used in remove entrained liquids and the filters to remove potential uranium.
l i
)
l The ductv'ork material in the K56 exhaust system is stainless steel for ducts greater than j
' seven inches in diameter, and polyvinyl chloride for ducts less than seven inches in diameter. The single K56 exhaust fan is connected to normal power.
l i
10.3.8.4 Systems Controls i
j i
i.
- The HVAC systems are controlled with temperature, pressure and flow sensor actuating l
l valving and damper positions to hold temperatures, pressures, and pressure differentials i
j constant in the various building areas. The building ventilation systems are interlocked i
j
! so that the K46 exhaust system must be operating before the K45 supply system can be i
t
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l ANWT A% CATION Dale JU19~23^1993
--~T ract No :
70-3'S l
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t SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REv.
l J
-y
~_
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 i 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 l
l 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 l
i 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 l
upset occur. Pressure differential indicating devices and airflow quantity meters are i
located in the controlled zones and/or on the main HVAC panel to provide system and l
zone operating conditions.
j
- 10.3.8.5 Deluae System l
l I
' A deluge system of fog spray nozzles is installed in the exhaust duct in the K46 system l
j a short distance upstream of the final filter banks. If heat detectors indicate a temperature
' of 140-190 F, the deluge spray is automatically activated. Should the deluge system be j
activated by any circumstance, differential pressure readings across the final filters will be j
l taken and in-place DOP/ DOS test made at the earliest opportunity.
I 10.3.8.6 Final Filter Bank j
i The final filter banks in both the K46 and K56 systems are encased in a poured and i
l 3
sealed concrete structure. HEPA filters rated at 1000 ft / min at 1-inch H O pressure drop j
2 are mounted in welded, steel structural frames. The HEPA filter medium is 100%
j i
moisture-resistant fiberglass, pleated over corrugated separators and sealed in fire-resistant plywood frames. The individual filters are certified to remvoe 99.97% of 0.3 micron particles and meet or exceed Military Specification MIL-F-51079.
10.3.9 Contaminated Clothina Laundry HVAC System
{
I 1 The general features of the contaminated clothing laundry HVAC system are a once-l through ceiling-to-floor airflow supply system (K41) system and a double HEPA filtered l
1 I
exhaust system (K42). A simplified schematic diagram of the air supply system and the air exhaust system is shown in Figure 11-10.27.
10.3.9.1 K41 Air Supply System l
3 I
The K41 air supply system supplies about 1900 ft / min of 100% outside air to the laundry i
i room which is divided into a cleaning area and adjoining sorting area. Airflows are I
i Fiu~siMEheccecE~-- ~
Ju19~ 23E1993
~~ -
TFior e -1047
____-_~.__---_---i----
SPC-ND 3330 947 (R-vo792)
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION ney.
i i
f i 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.
I 10.3.9.2 K42 Air Exhaust System l
t i Air supplied to the cleaning and sorting areas, plus infiltration and dryer exhaust 3
j (approximately 4200 ft / min),is exhausted through the K42 exhaust system. The double l
! HEPA filter arrangement in this system consists of the final HEPA filter bank and upstream i primary HEPA filter bank plus individual prefilters located in the exhaust ducts of the two I
l l areas serviced.
I 3
I The K42 system exhaust air (approximately 6300 ft / min.) passes from the two stage filter bank through the main exhaust fan, a duct air monitor (measuring airflow quantities) and is discharged from a stack extending 25 ft above ground on the southwest side of the 3
i building. The K42 exhaust system has one full-capacity fan which is connected to normal l
~
power. All final HEPA filters are in-place tested and assured to be 99.95% minimum 3
efficient for 0.8 micron DOS cold aerosol.
l 10.3.9.3 Systems Control I
i 1
l l The HVAC systems are controlled with temperature, pressure and flow senser actuating i 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 K42 exhaust system to prevent operation of the K41 supply air system without the K42 exhaust system operating. Pressure sensors are provided to maintain a minimum l negative differential pressure of 0.05 inch water gauge in the cleaning area relative to the l
j l atmosphere.
l The K41 supply fan is interlocked so that a loss of exhaust duct negative pressure above i
l
-3 inches water gauge (exhaust fan failure) or a signal from the exhaust duct heat l
i i detector will shut down the K41 air supply system.
i t
Automatic visual alarms are activated when any supply c: exhaust system upset occurs, 1
j Pressure differential indicating devices and airflow quantity meters are located on the main HVAC panel to provide system and zone operating conditions.
i l 10.3.9.4 HEPA Filter Bank i
, The final HEPA filters are enclosed in a sheet metal housing that, in turn, is mounted on structural steel legs fastened to a concrete slab. The HEPA filters are rated at 1000 ft / min at one-inch water gauge pressure drop and are mounted in welded steel frames.
l 3
l Continuous air samplers are installed downstream of the filter bank. Visualindicators for i
I AVENDMENT APPUCATION DATE.
July 23,1993 f N NoI 10-38
)
~
SPC-ND:3330 947 (R-1/07192)
Siemens Power Corporation - Nuclear Division EMF-2 I
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION
- ggy, l
! reading the pressure drop across the filters are permanently installed, and means are l provided for in-place DOS testing.
4 i
o 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.
i 10.4 Radioactive Waste Handlina j
! The facilities and processes which are involved in the handling of radioactive and
}
' chemical wastes produced by SPC are described in the following sections.
I i
i 1 10.4.1 l_aaoon System Description l
The lagoons provide containment for all uranium and chemically-contaminated liquid wastes generated at SPC.
Natural evaporation, controlled waste addition, waste i
discharge to the municipal sewer and water additions are used to control the volume of j
l liquid stored in the lagoons. Inter-lagoon transfers are periodically made for both uranium l
l 3
1 l accountability and volume control purposes.
Sampling between lagoon liners is l conducted monthly (unless prevented by freezing weather) to determine if leaks have
- occurred.
j i
There are six liquid waste storage lagoons, one solids leach pit, and one sand storage l
l l
i l
i i pit located along the east boundary of SPC (see Figure 11-10.1). The sand storage pit is located immediately west of Lagoon 3. The solids leach pit is located immediately west I
of Lagoon 2. The dimension and capacities of the lagoons are:
f l
i Lagoon Dimensions Est. Capacity 10* Gat
{
l 1
240' x 200' x 3' deep 1.4 1
2 240' x 100' x 3' deep 0.7 l
l l'
3 240' x 350' x 5'6" deep 3.5 i
4 240' x 290' x 6' deep 2.7 j
j l
5A 240' x 175' x 7'6" deep 1.6 i
l SB 240' x 175' x 7'6" deep 1.6 f
Leach Pit 40' x 54' x 8'6" deep 0.06 i
i Sand Pit 39' x 300' x 6' deep 0.3 l
l i
i t
f AkbENT APPLICATm[h[
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PAGE CJ 0 39 u _ _..
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i SPC-ND.3330 947 (R-tio7S2) i
i i
Siemens Power Corporation - Nuclear Division eug.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION
- ggy,
[ The lagoons and the solids leach pit have a " sandwich" construction; they each hav l liners 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 between the impervious liners is an array of sample heads. The sand storage pit is j single-lined and, therefore, does not have between-liner sampling capabilities. Tubing i
j from each of the heads is routed to the berms on both the east and west side of the l lagoons where small pumps can be periodically connected. Some additional sampler
! heads are located between the original Petromat liner and the lower liner.1.agoon 4 is l equipped with three " dry wells" below the bottom liner. Samplers are located in each dry i well. All sampler heads are pumped each month using small air-driven pumps (unless prevented by freezing weather) for leak detection purposes.
I l
> Lagoods 1 and 2 are used as receivers of ammonia-bearing solutions from the conversion area with a low-level of uranium and is the feed lagoon for the ammonia recovery (AR) l process. They have impervious floating covers to contain the ammonia fumes, i
j 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.
l l Lagoon 4 also serves as the feed lagoon for LUR waste to the AR Facility.
i
low uranium, low ammonia chemical wastes. Disposal of waste from Lagoon 5A to the city sewer is accomplished after treatment by ion exchange to remove residual uranium
! (see Section 10.4.3).
The waste sewering rate is automatically controlled by a 7
i microprocessor via a flow measuring and control system. The sewered chemical waste i
is volume proportionally sampled. The chemical waste is monitored for uranium and l
l
! chemical content and sewering rate is controlled based on waste composition so as to j
l l remain within discard limits.
l l Lagoon 5B is currently used to store high uranium content waste to be treated for j
l uranium recovery. Once emptied, this lagoon will be used as a batching lagoon in i
- conjunction with Lagoon 5A 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. l the liquid storage lagoons during cleanup over the years of operation.
i
+
The solids leach pit is used for decontamination of sand. The process is described in detailin Section 10.4.4.
1
{
i i
PAGE NO.:
f0-40 i
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{ IWENDMENi APPUCATION DATE:
July 7371993~
I k. ____
1 sPC ND: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 q
PART 11 - SAFETY DEMONSTRATION
- ngy, l
! Periodically, liquid waste solutions are transferred from one lagoon to another for l accountability, volume control or maintenance purposes. A permanently mounted pump
~ with interconnecting piping enables solution to be pumped 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 steel structure located north of Lagoon 1 (see Figure 11-10.1). The structure is designed to withstand UBC Zone 11 seismic loading 2
and 20 lb/ft windward pressure. An equipment arrangement is shown on Figure 11-10.28.
i The Engineering Flow Diagram is presented on Figure 11-10.29. A brief description of the major equipment pieces is given in Table 11-10.1. The building also houses the Lagoon I SA IX Process (see Section 10.4.3).
t The unneutralized low uranium content liquid process waste from the feed lagoons
- (Lagoon 1 or Lagoon 2) is transferred to the feed tank which provides approximately one j hour surge capacity. Process waste from the LUR operation can be added to the feed tank and processed with the conversion process waste. Sodium hydroxide is added to the feed tank to replace the ammonium in the ammonium salts, and to keep the pH high to reduce corrosion. The feed tank is maintained under a slight vacuum by venting.
- through a scrubber. Feed solution is pumped via a flow control system and an energy i
l 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.
ll
! The ammonia stripping column provides for removal of ammonia from the waste solution f
3 j by countercurrent contact with steam and is designed to produce 20 to 30 wt% ammonia i
i product solution and waste effluent at less than 100 ppm ammonia. The bottoms from l
l
' the stripper are pumped to the designated waste treatment batching lagoon (SA or 58)
I l'
or recycled back to the feed tank, or the feed lagoon, depending on its ammonia concentration, temperature, and pH.
i
~
l
! The air purge system on the pneumatic instrument lines is designed to prevent backup
- of process fluids in the event of excessive system pressure. A 50 psig rupture disk is s
! provided at the top of the column to prevent overpressurization of the system. The i
i pressure relief vents to the atmosphere through the tower roof.
j l
The condensables from the stripper overheads are removed in a downdraft condenser i
and are routed to the distillate tank. An automated deionized water injection system is I
provic'ed to improve ammonia removal efficiency and to control the ammonia hydroxide i
concentration, j
i l
l I
{AkMMC AMCAMN dam
~
~JUIy 2 993 PAGE NO2 10-41 1
t SPC ND 3330 947 (R1/0F9h i
Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
q PART 11 - SAFETY DEMONSTRATION
- ggy, A scrubber is provided to remove ammonia from the process vessel offgas. The scrubber bottoms are routed to the feed 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 console can j
access process information and display it on the CRT. In case of transmitter failure, the j
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 predetermined limits.
A steam boiler provides a maximum of 3000 lb/hr of steam to the AR process. Boiler i
pressure control is maintained by SCR's driven from pressure instrumentation. Steam I
+
j header pressure instrumentation is provided to shut down the process and alarm on low l
l and high steam pressure.
i l A 28,000-gallon, aboveground sodium hydroxide storage tank is provided to supply the l AR process. The tank is insulated and heated with a 5 kW heater to rnaintain the caustic l
temperature above 65 F. All exterior piping is heat-traced and insulated. A safety shower j
t l is provided at the load-in facilities. Operation of the NaOH storage system is monitored l
l and controlled at the control room.
r A 28,000-gallon, aboveground storage 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 hydroxide storage tanks.
i l A concrete spill containment structure is provided for the outside bulk sodium hydroxide l
i
' and product ammonium hydroxide storage tanks. The structure is designed to contain i
chemicals from a ruptured storage tank.
l
! The building exhaust system consists of a two-speed fan, temperature controls, an i
ammonia monitor and stack.
The exhaust fan is normally run on low speed l
3 (approximately 1700 ft / min). The fan is switched to high speed (approximately 5000 ft / min) if the building exhaust temperature exceeds 110 F. The building exhaust air i
l ammonia monitoring system is set to alarm locally and in the Line 2 Control Room.
)
The AR Facility fire detection and alarm system has been tied into the existing plant i systems.
i 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 flush through the system. Nevertheless, the system is inspected quarterly for signs of j
i i
1 M-k JuFf23 T993
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AMENDMENT APPUCATION DATE:
PAGE NO.:
SPC ND:3330 947 (R-1/07/9?)
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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
- ngy, t
! buildup of uranium solids. The plant criticality detection and alarm system also covers i
j the AR Facility.
i 10.4.3 Laaoon 5A IX Process The Lagoon 5A 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.
! building located on a concrete slab. A plan view of the addition is shown in Figure 11-10.28. The equipment arrangement is shown in Figure ll-10.29b. 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 scaled and caulked to be leak tight. The floor slopes I
j toward the sump area and has a sill or curb for leak containment except for the doorway j 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 Lagoon 3. Control is automatic, but can be controlled manually. The sump is designed l to collect minor leaks of lagoon solutions containing uranium and sodium and ammonium j sulfates, fluorides and nitrates and ion exchange reagents such as sulfuric acid, sodium l hydroxide, and water. The sump and floor areas are inspected annually for leaks. Those j areas are normally dry, leaks are repaired as soon as practical.
d 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 5A IX Process consists _of two sand filters and an ion exchange column and associated auxiliary equipment. The process flow is shown in l
i Figure ll-10.29a. Lagoon 5A colution is pumped from the lagoon through the primary filter j
j l
located at the lagoon pump out area to remove small particles and suspended solids.
l l 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
' 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 1
are available at the facility. These are discharged from the resin to Lagoon 5A. The i
j polishing filter is backflushed to Lagoon 3. The Lagoon 5A filter is backflushed to Lagoon
! SA. The media of the sand filters is expected to last indefinitely and the resin is expected to last at least five years. If needed, the resin can be disposed of by incineration at I SWUR.
2 I
l
, Typical uranium concentrations of Lagoon SA solutions fed to the IX column are 1-2 ppm l
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.
l i
i i
t fdELTshTMCATm DATE:
July 23l1993 I PAGE Nb j Q.4 SPC ND:3330.947 (R-1/07/92) -
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION l ggy.
l 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 concentrations 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 the system are suberitical even under abnormal conditions of the iransfer of uranium bearing lagoon solids to the first sand filter or raturation 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 SA l
i semiannually and analyzing for uranium. The sand filters and resin bed are also sampled I
j and analyzed for uranium semiannually. In addition, the resin is inherently safe since it j saturates with uranium at less than 140 gUh. Buildup of uranium on the column is j 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 i
Department. The ion exchange room has a hand-held fire extinguisher. There is a two-hour rated fire wall between the original building and the new addition and a similar fire wall between the outside storage area for sulfuric acid and the building housing the ion exchange system.
i
! 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 l
l are designed to withstand a pressure of at least 100 psig versus the maximum pump i
! 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.
i i
1 J
j The environmentalimpact of the ion exchange process for treating Lagoon 5A solution l is judged to be insignificant. The equipment is located in a building within the restricted j area which is committed to industrial use. The equipment is located in an area j specifically designed to contain any spus or leaks. There are no gaseous effluents or
! increases in the quantities of radioactive waste generated. All underground transfer lines j entering and leaving the new facility are completely double-encased (inner pipe i surrounded by a sealed secondary plastic containment shell), with electronic leak detection systems that alarm locally and in the conversion Line 2 control room. The j
j primary pipes are tested hydrostatically annually and the secondary pipes biennially. The process generates small quantities of additional chemical wastes, but this is more than i
j offset by the positive environmental impact of reducing the quantities of uranium discharged to the Richland city landfill.
I I
duk$(llN PACE NOJ (h[
i AMENDMENT APPUCAiF1DATE:
SPc-ND:3330.947 (R UD7/92)
Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll - SAFETY DEMONSTRATION REv.
10.4.4 Laaoon Uranium Recovery (LUR) Facility Description i
The LUR Facility is provided to recover LEU from stored high uranium content liquid i chemical wastes (see Section 10.4.1). Following uranium recovery, the waste is treated t
l for ammonia removal (see Section 10.4.2), then disposed to the municipal sewer.
i The LUR Facility is located adjacent to Lagoon 4 as shown on Figure 11-10.1. The j equipment consists of six process vessels, one chemical makeup vessel and associated i pumps, piping and filters. A brief description of the major equipment is given in Table l 11-10.2 and the equipment layout is depicted in Figure 11-10.30. The equipment is not i housed, but is partially covered. The process equipment is not freeze-protected and is, i therefore, shut down and winterized during cold weather.
j l
1 l A process flow diagram for the uranium recovery system is presented in Figure 11-10.31.
i Approximately 4000-6000 gallons of high uranium content waste is pumped into the
}
l 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 supernatant is decanted to lagoon l storage.This procedure is repeated until the total precipitate accumulated in the precipita-i j tor vessel reaches the desired batch size. The uranium precipitate is slurried to the washer tank and water-washed for extraneous chemical removal. The washed precipitate t
is then slurried into a container, dissolved in aluminum nitrate solution, pumped through t
l is purified for reuse through existing solvent extraction facilities.
l a centrifuge to a plastic 55-gallon drum, and placed in storage. The recovered uranium l
A vent system is in place for removal of NO, fumes generated during the dissolving of the -
l precipitate. At this time, an upgrade to the vent system is being planned with a scrubber, I
f HEPA filtration and air sampler.
i
- in addition to routine processing of lagoon solutions, the centrifuge at LUR is used for l
~ separating mop powder solids after processing in ELO.
l i
The basis for criticality control is mass control. The mass in any vessel is maintained at r
bss than 45% of the minimum mass required for criticality. The typical mass in any-l 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
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 i
solids into fractions. The solids are pumped as a water slurry from the sand trenc.h to the i
vibrating screens. None of these facilities are sheltered.
j l
I l
1 1
!TESTuisvucco~ oce JUTF 2 Kiss 3
] east "o :
10-45
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t I
l., _.._,_
SPC-ND.3330.947 (R-1/07/92)
SiemenS Power Corporation - Nuclear Division gug.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 t
PART ll - SAFETY DEMONSTRATION REV.
[ The slimes and fines in the sand trench and lagoon so! ids contain essentially all of the
{
i uranium. On a volume basis, the slimes and fines are about 20% of the solids volume, and the remaining 80% is sand.
l 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 l
l 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 e.nd i greater than 150 mesh materials and to increase the efficiency with respect to removal of materialless than 150 mesh.
The water and less than 150 mesh material bearing the uranium is discharged to 1.agoon
- 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 l remove the sand and slimes. These solids are discarded as ground cover in the lagoon
}
j area.
} 10.4.6 Solid Waste Uranium Recovery (SWUR) Facility Description j
l
! The Solid Waste Uranium Recovery (SWUR) facility is designed to incinerate combustible
- uranium-contaminated wastes for volume reduction and uranium recovery.
The
! incinerator, though designed to meet hazardous waste incineration criteria, is not permitted as a hazardous waste incinerator. The incinerator and auxiliary systems are i located in Room 173 of the Specialty Fuels Building (See Section 10.1.1).
3 l The process is divided into four systems: feed preparation, waste incineration, offgas j treatments, and ash handling.
i 10.4.6.1 Feed Preparation i Solid wastes generated in the nuclear fuel fabrication activities at SPC are sorted at points
[ of generation to separate dangerous wastes from nondangerous solid wastes. The l
< dangerous wastes are packed in plastic-lined 55-gallon DOT 17H metal drums for onsite i
j mixed waste storage. The nondangerous wastes are sorted into combustible and l 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 l
! at a licensed radicactive waste burial ground. The combustible wastes are packeged in I
All
}
j plastic-lined 55-gallon DOT 17H metal drums for storage prior to incineration.
i ssoutvr AmeATIONDATE:
July 23,1993
"^GE 'd 1046 L_
SPc-ND:3330 947 (R-1/07S2)
i Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION aev.
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 i
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 assayed for uranium then conveyed to the incinerator hydraulic ram feeder which is automatically contro!!ed 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 hre 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 feed hopper.
I
! 10.4.G.2 Waste incineration t
l The safe batch incinerator has a nominal capacity of 90 kg/hr of uranium-combustib waste consisting ot oa'ier, plastics, wood, etc. The incinerator is a commercial controlled-air unit modified to minimize ash holdup and to facilitate good carbon burnout and i
system cleanout.
The unit consists of primary and secondary chambers, each constructed of a carbon steel shellinternally 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.
' Both chambers have propane-fueled burners and combustion air ports. The primary j
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 chamber where excess air and high temperature (approximately 2000 F) and a mini. mum 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 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 l
occurs in the packed column scrubber. An extremely high chamber temperature or l
propane burner malfunction automatically shuts down the incinerator.
i s
10.4.6.3 Offnas Treatment l ' The incinerator exhaust gas from the secondary chamber contains particulates, vapors, l
! and gases (including acidic gases) which result from the combustion of the cellulose, i
i i
1 s
IautNouta T ^"PticAToN o^TE:
July 23,1993 l
PAGE NO; 10-47 SPC ND3330.947 (R-1/07/92)
)
i!
Siemens Power Corporation - Nuclear Division eaa-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1T.57 f
PART 11 - SAFETY DEMONSTRATION ngy.
?
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 system components which consist of a quench column, a high-energy venturi scrubber, a packed column, a mist eliminator, a reheater and HEPA filtration modules.
l The quench column is divided into an upper cos..drig section and a lower sump section. In the contacting section, cooling and saturation of the incinerator exhaust pas 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 water to the quench column if a high column outlet temperature or loss of normal power j
occurs.
j The variable throat, high-energy venturi scrubber, located between the quench column f
and the packed column, removes more than 99 wt% of the offgas particulates. Scrub l solution is injected through a nozzle located upstream of the throat. An alarmed interlock I
j is provided to prevent feeding the incinerator if the scrub solution flow is low. The packed _ column is designed to slightly cool the offgas and to remove the acidic gases from the gas phase by countercurrent contact with recycled scrub solution. The gas is discharged from the packed column through a polypropylene mist eliminator. Alarmed interlocks are provided to prevent feeding of the incinerata if a high packed column inlet j
temperature.
The gas enters the electric reheater where it is warmed to a minimum of 15 C above the saturation temperature. This heating reduces the relative humidity of the gas to prevent 1
I wetting of HEPA filters. The reheater is controlled by a silicon controlled rectifier whici.
I I
maintains the proper temperature difference from the reheater inlet to the filter outlet i
Alarms and interlocks are provided to prevent feeding of the incinerator if a high heatei
{
'}'
differential temperature or high filter inlet temperature occurs.
The offgas module contains the prefilter and two banks of HEPA filters. The stainless l
steel module housing is designed and reinforced to withstand the 150-inch H O vacuum 2
to which it may be exposed. DOS testing of the final HEPA filter bank for verification of l
99.95% removal efficiency for 0.8 micron particles can be accomplished.
j Particulates that have been scrubbed from the gas stream are removed from the scrub
- solution by the filters. The filter elements are made from combustible materials so that i
once they are expended, they can be burned in the incinerator. Minimum expected 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 i
f l The scrub solution liquid is circulated by redundant pumps to insure a continuous stream i
! of scrub solution liquid. Automatic switchover of pumps occurs upon on-line pump l
l failure. Scrub solution liquid is cooled by a plate-type heat exchanger. Cooled liquid is' i
+
PAGE NO.:
jQ43 July 23,1993 wtxovemmmm on L_.,
l SPC-ND3330.947 (R-1/07/92) a
'i
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
l l
PART 11 - SAFETY DEMONSTRATION nev.
a c
used to improve acid gas absorption and to reduce the packed column discharge gas temperature. An alarmed interlock is provided to prevent feeding the incinerator if a high cooler outlet temperature occurs. Caustic addition to the system is automatically controlled by the pH controller in the packed column, scrub solution liquid line.
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 l Na CO (fromCO absorption),and Na SO (fromsulfurcompoundspresentinthe paper 2
3 2
2 4
products).
A total dissolved cotids analyzer, which basically works on solution conductivity, is provided to control the blowdown stream. The blowdown stream is
[
j proportionally sampled and discharged to SPC's surface impoundment system (see
- i j Section 10.4.1).
1 10.4.6.4 Ash Handlina i
Ash formed from the combustion of wastes is pushed along the hearth by incoming feed 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 i
30-gallon DOT 17-H metal drums. Each ash drum is homogenized and sampled for l
uranium and U-235 isotopic content and its net weight is determined. The drums are then stored for future recovery of the contained uranium.
10.4.7 Plutonium-Contaminated Waste Storaae l
A waste storage facility is provided for storing Pu-contaminated waste which remains from
! a previous mixed oxide fuel fabrication facility. The Pu concentration in the contaminated
{
j 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 Figure 11-10.2.
i i
r I
The storage facility is located in Room 162 of the SF Building. The facility is a below-l grade room (approximately 12 x 20 x 20 ft deep) constructed of reinforced concrete and j covered by steel floor grating overlaid with steel plate. The room contains a sump for i
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.
l 2
1
- _ Drum storage is on steel grating to support the drums off the concrete floor and on a j
l mezzanine also fabricated of steel grating. Ingress and egress for personnel and i equipment is from the top of the room.
1 l
l l The room is ventilated. Air is drawn down from the roof and exhausted i
l through one stage of HEPA filtration into the SF Building exhaust system. The exhaust
[ ANNT APPLCATA DATE:
July 23,1993 10-49 PA E NO.:
i SPC-ND:3330.947 (R V0792)
SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 I
PART 11 - SAFETY DEMONSTRATION nev.
L-air is continuously sampled and monitored prior to the installeo HEPA filter. The air sample is analyzed weekly.
10.5 Fire Protection 10.5.1 Buildina Codes and Standards 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 i
l UBC (Seismic Zone 11) l l
+
Uniform Plumbing Code
+
l Uniform Mechanical Code
+
Uniform Fire Code
+
National Fire Codes (NFPA)
+
National Electrical Code ANSI-C1
+
ASHRAE Standards
+
Washington Administrative Code, Chapter 296-24
+
j Washington Administrative Code, Chapter 296-44
+
Richland Municipal Code and Zoning Regulations
+
Richland Municipal Ordinances Numbers:
I 3777 (adopt. Building Code) 3877 (adopt. Plumbing Code) j 3977 (adopt. Mechanical Code)
! 10.5.2 Fire Protection Liability inspections I
5 l
l l SPC has elected to self-insure with regard to property damage. American Na:ional
! Insurers (ANI) schedules a fire protection audit of its' policy holders, among whom is SPC, l approximately every year by an acknowledged fire protection consultant. Richland's l Department of Fire and Emergency Services conducts annual fire protection inspections of SPC's Engineering and Manufacturing Facility.
The most recent copies of these audits and inspections is appended (see Appendix A).
! 10.5.3 Fire Protection Proaram 10.5.3.1 Combustible Solid Waste Handlina and Storaae i
i Outside metal waste containers are provided by the City of Richland for clean wastes.
l j Contaminated combustible wastes are properly sorted into metal boxes or drums, sealed i
l___._s MENDVENT APPUCATION DATE:
July 23,1993 l PA E NO.:
10-50 1
I
__J SPC-ND.3330.947 (R-1"l7/92)
SiemenS Power Corporation - Nuclear Division EM F-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 F
I PART 11 - SAFETY DEMONSTRATION nev.
I J
and stored on an outside pad for future uranium recovery or disposal per approved t
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 storage containers.
10.5.3.2 Flammable Liauld Storace i
Flammable liquids are stored in approved safety containers or cabinets near the final-use location. Additional storage for flammable liquids is provided for in approved safety cabinets in the warehouse complex.
I 10.5.3.3 Combustible Liould Storace l Combust!ble liquids are stored in approved metal containers near the final-use location.
l j 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 t
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 i
, - gas distribution piping meets applicable NFPA codes.
I i
j Combustible gas burn-off devices and combustible gas detection equipment are used
! where necessary to prevent explosion and fires 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 and Alarm
. Rate-of-rise / fixed temperature heat detectors are used in the facility to detect fires. This
_ l fire alarm equipment is installed to provide automatic, as well as manual alarm signals in l.
j event of a fire. The system includes an annunciator in the Central Guard Station which i
I indicates which zone in the system has actuated (see Figure 1110.32). A signal is also l
l automatically transmitted to the Richland Fire Department. The fire alarm is a single-strike i
j gong (2 strokes /sec). The fire alarm system is inspected and tested in accordance with l
i the applicable, preventive maintenance procedures.
]
i l
i I
{wtatm amcarm o4Te July 23,1993 PAGE NO.:
j Q_$j I
SPc-ND;3330 947 (R U07'92)
I
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll - SAFETY DEMONSTRATION
- ggy, Ii 10.5.3.6 Fire Defenses SPC's Engineering and Manufacturing Facility is located within the city hmits 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 from the plant.
t l The Fire Department estimates running time to the plant to be approximately 6 minutes.
! and has available equipment 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 j hydrants is an 8-inch diameter pipe. There are 13 fire hydrants on plant site (see Figure j
l Il-10.18). There are Multipurpose ABC, Halon, Met-L-x, CO, BC Dry Chemical, Purple-K l
l l
2
! Dry Chemical, and AFFF fire extinguishers provided throughout the facility at selected j
j locations. These fire extinguishers are inspected and tested in accordance with the 1
j applicable, preventive maintenance procedure.
l SPC's Plant Emergency Response Teams (PERT) receive annual training in or incipient fire-fighting techniques. The Richland Fire Department has the main responsibility for 3
l fighting fires on the plant site.
I l
I i
i 10.5.3.7 Responsibilities i
I i
l The Manager of Safety, Security, and Licensing has the respor.sibility for inspecting and l testing the plant fire extinguishers.
The Manager of Plant Engineering has the responsibility for inspecting and testing the j plant fire alarm system.
i l
l 10.6 ' Criticality Accidcnt Alarm System 1
j
} The criticality accident alarm system used in the SPC facilities employs neutron criticality l
' detectors (NCDs), which are operated in two-out-of-n (where n = 3 to 6 per comparator
, panel) 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.
l i
l
[Lwwm AmWONDAm PAGE NO/
L_
July 23,1993 10-52 SPC ND:3330.947 (R-907'92) -
I
i SiemenS Power Corporation - Nuclear Division EM F-2 i
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 r
PART 11 - SAFETY DEMONSTRATION ngy.
The SPC criticality accident alarm system e nsists of NCDs, comparator units, associated control panets, an annunciator panel, anc he.vlers. Each comparator unit is capable of monitoring the failure and trip signals of Jp to six NCDs.
Each NCD consists of a BF or He tube (externally moderated) with associated pulse 3
3 amplifiers, trip circuits, performance audit circuits, and associated power supplies.
Failure audit circuits check the operation of each BF tube, pulse amplifier, multivibrator, 3
and low and high voltage supplies by requiring a minimum background count rate of 100 counts per minute. This background count rate is provided by an internal radiation source in each BF tube. If the minimum background is not detected by the audit circuit, 3
a failure (indicating malfunction) is signaled. Such failure signals do not interfere with operation of the criticality accident alarm system.
Because the trip circuitry is not audited, redundant trip circuits are provided in each NCD.
Failure and trip signals from all NCDs are fed to comparator units. Redundant trip detection is provided in the comparator units. The comparator panels display all failure and trip signals. When two or more NCDs connected to the same comparator unit are l
tripped, the criticality accident alarm (howlers) is activated.
An annunciator unit monitors the status of the comparator units, and an audible alarm is actuated in the Central Guard Station in the event that the annunciator unit detects either a failure or trip signal.
l The minimum detectable criticality burst width for the SPC criticality accident alarm system l is 50 microseconds.
I i
' An overall system reliability test is conducted quarterly.
i i
The trip point of each NCD is set sufficiently high to minimize false alarms. The system l
f l
is designed to trip the alarms within 0.5 seconds when exposed at 5% above the trip i
point.
i i
{
l l
l I
i t
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i i
1 i
4 4
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[ AMENDMENT APPLCATON DATE:
PAGE NO.:
L July 23,1993 10-52a l
SPC-ND:3330.947 (R-907/92) i
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I b
i l
The concrete floors in the ELO Building are sealed to be liquid tight and l
there are no floor drains. Liqr.id effluents which could contain uranium or other hazardous material are treated to reduce such materials to levels within regulatory limits prior to discharge.
l 15.3.1.4.2 Heatina. Ventilation and Air Conditionina (HVAC) - The ELO Building has l
two independent HVAC systems. The north side of the building is basically an office / service area recirculating-type (K26) supply system. with an i
unfiltered exhaust. The south half of the building is a research and development area with combination once-through and recirculation supply (K24), and a double HEPA filtered (K25) exhaust system. The north and
)
south sides of the building are isolated with a structural wall and access to i
the south side is gained via an airlock. A simplified schematic diagram of
]
these HVAC systems is shown in Figure Il-10.25.
i 15.3.2 Gadolinia Scrap Recoverv 15.3.2.1 Process Description f
I i 15.3.2.1.1 Summarv - A separate facility is provided in the ELO Building for recovery of l
gadolinia scrap from the NAF operation. This facility, equipped with powder and UO2 pellet dissolvers, filtration equipment, and a solvent extraction l
l system, produces gadolinia-free UNH. The UNH may be converted to UO l
2 in the Scrap Recovery Facility, or in either conversion line.
i l 15.3.2.1.2 Dissolution - Uranium scrap is processed through one of three dissolution I
stations: the mop powder dissolver which dissolves highly contaminated-uranium powders; the pellet dissolver; and the TK-1 dissolver for dissolution of pure, clean uranium powders.
j i
i
, 15.3.2.1.3 Filtration - The UNH product from all dissolution processes is filtered prior l
l l
to being sent to solvent extraction.
l 15.3.2.1.4 Solvent Extraction - Solvent extraction consists cf 15 stages (five each of extraction, scrubbing, and stripping) which remove impurities from the UNH solution. The extractant is a mixture of tributyi phosphate (TBP) and I
dodecane. Stages are also provided to condition the extractant for reuse.
15.3.2.2 Criticality Safety i
I
- Criticality safety in the Gadolinia Recovery Facility is provided by control of the geometry
- of the solvent extraction equipment and the dissolvers, as well as through control of feed i and product so!ution uranium concentration (mass). All process vessels except the l
._L i
[boma macom July 23,1993 15-38 i
SPC-ND 3330.947 (R 1/07/92) t e
i SiemenS Power Corporation - Nuclear Division gy.2 SPE^%L NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i
i f
PART ll - SAFETY DEMONSTRATION ggy.
i J
1 l powder dissolver and the 55 gallon UNH product drums are geometrically safe for the i achievable uranium concentrations of the solutions in the gadolinia recovery process.
l Safe concentration in the powder dissolver is maintained by batch control of the powder added to the dissolver. Concentration in the UNH product drums is controlled by specifin t
1 gravity measurement of the UNH prior to its transfer into drums. The amount of tributyl l
l phosphate (TBP) specified for solvent extraction limits the theoretical maimum U i
concentration of the product to slightly more than 20% of the critical concentration in a l
l fully reflected 55 gallon drum.
l i' 15.3.2.3 Radiation Protection j
l l
I
! A HEPA filtered exhaust hood is provided around the dissolver, and protective clothing l
and eye protection are required for personnel operating in the area. Survey equipment l
j is provided at the exit of this area to monitor hands, clothing, and feet on egress.
i 15.3.2.4 Fire Protection Fixed / rate-of-rise temperature sensors which activ6te fire alarms are present in the f laboratories as are portable fire extinguishers.
l l
\\
l 15.3.2.5 Environmental Protection i
Gaseous emissions from dissolver activities are passed through a scrubber to remove l
l l most of the noxious fumes and gases. The scrubbed gaseous streams then join the j
j normal room ventilation stream and are double HEPA filtered before going to the i
atmosphere. An isokinetic sampler is installed in the main exhaust stack.
i All liquid waste streams are sampled and analyzed for uranium content. Allliquid wastes
! are sent to Lagoon 3 for further processing and future uranium recovery.
l Combustible solid wastes are packaged and sent to SWUR for volume reduction and t
eventual reprocessing for uranium recovery. Noncombustible solid waste is sent for
{
i permanent disposal.
15.3.3 Laboratory Operations l
15.3.3.1 Description of Operations l
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The laboratories in the ELO Building are research and development facilities supporting n'i the steps of the fuel manufacturing process as well as materials research.
l AVENOMLNT APPLtCAilON DATE:
l PAGE NO.;
July 23,1993 l
15-39 SPC-ND:3330.947 (R UO7/92)
SiemenS Power Corporation - Nuclear Division eug.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 e
PART 11 - SAFETY DEMONSTRATION ggy r
i 15.3.3.2 Criticality Safety l
All the laboratories operate under either safe batch or safe slab controls. In those laboratories where more than one safe batch is allowed, spacing between safe batches l is maintained. Spacing is also maintained between nafe slabs and other types of arrays.
i i 15.3.3.3 Radiation Protection l
1 i
l In those laboratories which handle readily dispersible uranium HEPA filtered exhaust
- hoods are used to confine such material. Radiation survey equipment is provided and I
surveys are required when leaving a contaminated area. Air sampling and regular i
equipment / facility surveys are also undertaken.
i 15.3.3.4 Fire Protection i
I 1
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i Fixed / rate-of-rise temperature sensors which activate fire alarms are present in the laboratories as are portable fire extinguishers.
{ 15.3.3.5 Environmental Safety i
l Liquid effluents which could contain uranium go through the ELO sump. Gaseous l
l
' effluents are double HEPA filtered.
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! 15.4 Warehousina and Storaae l
i 15.4.1 Warehouses
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15.4.1.1 General Safety Conditions l
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- There are three warehouses where SNM is routinely handled and stored
- the Radioactive j
l Materials Storage Warehouse; the Fuels Storage Warebause; and the UNH Drum Storage
- Warehouse. The safety conditions for these warehorses will be discussed collectively, j
i l
i The Radioactive Materials Warehouse is used to load containers of pellets into outer l
containers for shipping. It is also used to store archive sample and drums and buckets i
2 3 8 Powder and UO pellets.
l l
of UO and U 0 2
I SPC produces UNH' solutions as an intermediate product from the solvent extraction l
i recovery of uranium from gadolinia bearing materials and form lagoon recovery product solutions. The UNH Drum Storage Warehouse provides heated storage so the drums of j
UNH can be safely stored and handled during subfreezing weather.
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d I
pad UA[AfA WCATON DAf[
~ PAGE NOa SPC ND 3330 947 (R+07/92)
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION
- ggy, I
l The Fuels Storage Warehouse is used for unloading and storing incoming scrap prior to l its being recovered.
I l
15.4.1.1.1 Criticality Safety
{
l l Criticality Safety for powder and pellets includes mass, moderation control and nuclear j poison mechanical devices for large barrels; mass and spacing for buckets; mass, geometry (slab height) and spacing for inner shipping containers; and uranium concentration and slab height for UNH drums. Enrichment controls are also employed.
15.4.1.1.2 Radiation Protection I
l The uranium is stored in closed containers. Routine monthly surveys as well as surveys j on incoming and outgoing containers are performed to ensure that there had been no j
- loss of containment of contents.
I i
15.4.1.1.3 Fire Protection l The warehouses are constructed to be noncombustible and are equipped with fixed l temperature / rate-of-rise detectors which trigger the fire alarm. There are also manual fire i
l alarms and portable fire extinguishers in the warehouses. Flammable liquids are stored
- in fire proof cabinets.
i
! 15.4.1.1.4 Environmortal Safety i inner shipping containers of uranium brought into these 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.
1
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! 15.4.2 Storane Areas I
i I 15.4.2.1 General Safety Conditions i
l There are several permanent and temporary storage areas on the SPC site. These
{ include UF cylinder storage (discussed in 15.1.2.1), loaded fuel assembly shipping g
i container storage, loaded powder and pellet shipping container storage, scrap and waste i drum storage, and other temporary storage areas (e.g. sea containers).
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July 23,1993
]""
' AMi55UINT APPtchdNhTk:
15 41 I _ _._._ _.
1-SPC-ND 3330.947 (FF UO7/92)
i SiemenS Power Corporation - Nuclear Division eup.2
. SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION nev.
l 15.4.2.1.1 Criticality Safety i
Loaded shipping containers are stored in arrays which are limited in size by the criticality l
safety limits prescribed by the NRC/ DOT container certificates. Other storage arrays (e.g.
scrap and waste drums and inner pellet shipping containers) are controlled by geometry, enrichment and mass per container limits.
15.4.2.1.2 Radiation Protection The uranium is in closed containers and is surveyed for radioactive contamination prior to going into storage. The areas are also routinely (monthly or quarterly) surveyed.
15.4.2.1.3 Fire Protection The covered shipping container storage area is equipped with a sprinkler system. There are fuel assembly shipping containers with wooden overpacks stored there. All other j shipping containers are all metal and therefore noncombustible.
i l 15.4.2.1.4 Environmental Safety The uranium is contained in closed containers.
j 15.4.3 Laaoons and Laaoon Systems I
l
)
15.4.3.1 General Safety Conditions I
l There are six lagoons, the sand trench, and the leach pit plus two uranium recovery j
j systems, LUR and the Lagoon 5A IX, where SNM in varying concentrations is stored and l
recovered. The safety conditions of these areas are discussed collectively.
l l
]
e Lagoons -_There are six lagoons in the lagoon system. Each lagoon is double lined with l
either hypalon or high density polyethylene (HDPE) and two of the lagoons have an HDPE covering. Between the liners is a leak detection system. Below the bottom liner l
is a petromat liner which is also equipped with a leak detection system. The lagoons j
{ accept waste from various chemical operations. The wastes are segregated according j
' to their source and chemical content for reprocessing to reclaim usable constituents l
After recovery, the waste is then prepared for sewering to the Richland public sewer i
j
, system. Fences have been erected around the lagoons and appropriate radiological j
' waming signs exist.
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Sand Trench - The sand trench 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 j
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ALAENDMENT APPitCATION DATE:
l PAGE NC;;
July 23,1993 l
15-42 SPC-ND:3330947 (R 1/0792)
-)
Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 q
I PART ll - SAFETY DEMONSTRATION
, sev.
i t
l and radiological contaminants and screened. The fines and water go to Lagoon 3 and
! the solids go to the leach pit.
Leach Pit - The leach pit collects washed sand from the sand trench operations. Any i
liquid which drains from the sand is pumped to Lagoon 3. The sand is used as backfill in the commercial radioactive burial facility at Hanford, Washington.
Lagoon Uranium Recovery (LUR) System - In the LUR process, Lagoon 3 solution is pumped to tanks in the LUR facility. Sodium hydrosulGio is then added to precipitate the uranium. (Other metals as impurities also precipitate.) The liquid is decanted and pumped 2
l l to Lagoon 4 and the solids are centrifuged. The centrate is pumped to Lagoon 4 and the solids are p! aced into a drum where they are dissolved using aluminum nitrate. Once the I
i solids are dissolved, the uranium is recovered by solvent extraction.
! Lagoon 5A lon Exchange (IX) System - Effluent from Lagoon SA is fed to the Lagoon 5A
! IX column to remove uranium before the effluent is sent to the Richland public sewer l
j system. The effluent is normally less than 2 ppm uranium as it is fed to the IX column
' and less than 0.1 ppm uranium as it leaves the IX column. Optimum uranium removal is 3
obtained at 8<pH<12. When the IX resin is loaded, elution and regeneration are I
performed and all liquid streams are sent to Lagoon 3.
15.4.3.1.1 Criticality Safety 1
, Criticality safety is assured for the lagoons, sand trench and teach pit by uranium l
i concentration control. Inputs to the lagoons are monitored and the concentrations are i
l limited to 1000 ppm U. Lagoon 3 is the only one of these areas that approaches this l
! limit. The lagoon, both solution and sludge, are sampled semiannually and the samples i
i analyzed for U concentration. Precipitating agents are controlled in Lagoon 3 to keep the U in solution and pH is controlled in all lagoons.
t l
4 The Lagoon SA IX system criticality safety is assured by limiting the U concentration to less then 140 gU/t. This concentration is safe for all vessels in the system. The lagoon solids, the sand from the sand filters and the IX resin are all sampled and analyzed semiannually to confirm this concentration limit.
- Criticality safety in the LUR process is assured by maintaining safe batches in all vessels j
i
+ and adequate spacing between vessels. Batch control is maintained by analyzing the j
lagoon solution which enters the system to determine how much solution can be q
processed while maintaining a safe batch.
j 1
l In all these areas the enrichment is limited to 5%.
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$ AMENDMENT APPL CATON DATE.
)
i July 23,1993 l PAGE NO.:
15-43 i
L_
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SPC-ND3330.947 (R-vo7W)
Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION
- ggy, a
- 15.4.3.1.2 Radiation Protection l
The lagoons are within SPC's fenced area and bird alarms are in use to keep them away i
from the water. The sand trench is covered. in the LUR and Lagoon SA IX areas the U-j bearing solutions are in clossd containers.
15.4.3.1.3 Fire Safety Fire in the iagoons and trenches is not credible. The Lagoon 5A IX system building
! contains manual and fixed / rate-of-rise temperature sensors to alarm a fire and the building
. is rated noncombustible. The LUR operation is outdoors and the structures and
{ equipment are noncombustible. There are portable fire extinguishers available at both the j Lagoon SA IX and LUR.
I l 15.4.3.1.4 Environmental Safety I
l i
l The lagoons and leach pit are double lined with a leak detection system between the l
3 l liners to detect leaks prior to reaching groundwater. The sand pit has a single liner and j
s is covered when it contains contaminated sand. In addition there are a number of i
l groundwater sampling wells associated with (he lagoon system (see Chapter 5).
I
- The Lagoon SA IX system resides in a building addition to the Ammonia Recovery Facility.
l The addition is buiit on a sealed concrete floor with curbs which drains to a main sump.
l All U-bearing material is in closed containers or process vessels. In the LUR area, once s
' the solution is pumped from the lagoon, it is maintained in closed process vessels or l
i
. containers.
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I i AMENDMENT APPLCATC% DATE:
Pb3E NO.:
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July 23,1993 15-44 l
SPC-NDX30.947 (R-1!07'9?)
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