ML20054M211
| ML20054M211 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/25/1982 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20054M210 | List: |
| References | |
| B4-1160002-4, NUDOCS 8207120099 | |
| Download: ML20054M211 (22) | |
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Process Control Program i for RADI0 ACTIVE SOLID WASTE SYSTEM l
Shoreham Nuclear Power Station - Unit 1 Long Island Lighting Company l
June 25, 1982 i
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C20712OO99 820701 PDR ADOCK 05000322 A PDR B4-1160002-4 4
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CONTENTS 1
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- 1. PURPOSE . . . . . . . . . . . .. . .. ... . . . . ... .1
- 2. SCOPE . .......................... 1
- 3. SOLIDIFICATION SYSTEM PROCESS CONTROL . . ... ... .. . .3 3.1 SOLIDIFICATION SYSTEM DESCRIPTION. . .. . ..... . .3 3.1.1 System Testing . ..... ... . ... ... 3 3.2 SAMPLING AND TEST REQUIREMENTS . . ... . ...... 4 3.2.1 Liquids. . . . . .. . .. . .. .... ... 5 3.2.2 Wet Solids . . . .. ... . .. . ...... 5 3.3 SAMPLE SOLIDIFICATION TESTS. ...... . ...... 5 l
3.3.1 Liquids. . . . . .. ... .... ...... 5 3.3.2 Wet Solids . . . .. . .... . . ...... 5 3.3.3 Test Results . . ..... ... ... . ... 5 3.4 SOLIDIFICATION SYSTEM OPERATION. . ... . ...... 6 t
3.5 DISPOSAL OF FILTER CARTRIDGES. . . .. . . ...... 6
- 4. RADWASTE FILTER SYSTEM PROCESS CONTROL. .. . . ...... 7 4.1 RADWASTE FILTER SYSTEM DESCRIPTION . . . . .. . ... 7 4.2 SYSTEM TESTING . . . . . .. . .. ... ... . ... 7 4.3 PROCESS OPERATION. . . . ..... .. . .. .. ... 7 4.4 DEWATERING PROCEDURE . . .. ... . .. . .. . ... 7 4.5 ACTIVITY LIMITS. . . . . .. ..... . . ...... .8
- 5. FLOOR DRAIN FILTER SYSTEM PROCESS CONTROL . . . ... ... 8 5.1 FLOOR DRAIN FILTER SYSTEM DESCRIPTION. . . .. .... 8 l
5.2 SYSTEM TESTING . . . . . ..... ... . ... ... 8 5.3 PROCESS OPERATION. . . . . . . . . . . . . ... ... 8 5.4 DEWATERING PROCEDURE . . ..... ... . ... .. . .8 5.5 ACTIVITY LIMITS. . . . . .. ... . .. . . . .... 9 l
l 6. RESIN DEWATERING SYSTEM PROCESS CONTROL . . . . ..... . .9 i
- 6.1 RESIN DEWATERING SYSTEM DESCRIPTION. . . .. . .. . .9 6.2 SYSTEM TESTING . . . . . .. .. . . . . . .. .... 9 I 6.3 PROCESS OPERATION. . . . .. . . . . . . . .. ... . .9 6.4 DEWATERING PROCEDURE . . . . .. . .. .. .. . .. . .9 i 6.5 ACTIVITY LIMITS. . . . . . . .. . . . . . .. . . . . . 10
! 7. ALTERNATE PROCESS CONTROL ARRANGEMENTS .. . ... ... . . 10 t
I 7.1 PROCESS OPERATION. . . . . . . . . . . . .. . . ... . 10
- 8. REFERENCES. . . . . . . . . . .. ... . . . . .. . . . . 10 APPENDIX A - Sample Bench Tests. . . . . . . . . . .. . . . . . . A-1
- APPENDIX B - Activity Limits . . . . .. . . . . . . . . . . . . . B-1 B4-1160002-4
'. 1. PURPOSE
- A simplified functional diagram is shown in Figure 1. The Process Control Program for Shoreham Nuclear Power Station Unit 1 (SNPS-1) provides assurance of consistent quality waste product which is acceptable for shipment and burial by:
- Providing assurance that various waste types produced at SNPS will satisfactorily solidify.
- Providing a method by which sample batch solidification of liquid wastes (evaporator bottoms) or other wet solids may be performed to check process parameters for assurance of satisfactory solidification.
Providing maximum activity limits for different waste classes allowed for burial at disposal sites.
Providing reasonable assurance that dewatered waste products have less than 0.5 percent freestanding water by volume if packaged in something other than a high integrity container (HIC), or less than 1 percent freestanding water if packaged in a HIC.
- 2. SCOPE Boundary conditions (in the form of process parameters for the waste solidification system) were established within the scope of this Process Control Program such that operation within these limits gives assurance that solidification is complete. Boundary conditions for solidification were determined by chemical tests conducted with typical constituents in the liquid waste streams. These boundary conditions establish measurable physical parameters such as chemical content of the liquid waste being solidified (pH, oil, glycol, citric acid concent, etc.), chemical quality of solidification agents and liquid waste to solidification agent ratios. A boundary matrix of these physical parameters was established. The appropriate waste to solidification ratio is determined by chemically analyzing the liquid or " wet solid" waste streams via plant operating procedures and comparing the results with the established boundary matrix for each type of waste to be solidified.
B4-1160002-4 1
R ADWASTE FILTERS FLOOR DRAIN FILTER COM PACTOR O O SHIPPING s CONTAINER 5
YY SHIPPING SILO CONTAINER VENT SHIPPING CONTAINERS FILTER FROM PHASE SEPARATORS O CEMENT DEWATERING SPEM RESW MODE STORAGE SPENT FROM RADWASTE DEMlli. SILO
- RESIN RETURN
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TANK LINE FROM COND DEMIN. SYSTEM '. \/ o FROM FUEL POOL DEMIN. - O fRANSFER SPENT RESIN SLUDGE PUMP CEMENT BLOWER
_ ,, BATCH BlN WASTE TO WASTE COLLECTOR TANKS D WATERING
CEMENT SPENT RESlN - r TANK DECANT 4 6
' d FEEDER PUMP WASTE %
METER ,
FROM EVAPOR ATIONS PUMP g & WASTE 3 MIXER EVAPOR ATOR I BOTTOMS 0TTOM SOLID RADWASTE SYSTEM TANK METER PUMP SHORIHAM NUCLEAR POWER STATION pp CONTAIN ER UNIT 1 LONG ISLAND LIGHTING COMPANY
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- 3. SOLIDIFI'ATION C SYSTEM PROCESS CONTROL 3.1 SOLIDIFICATION SYSTEM DESCRIPTION l
The radioactive waste solidification system provides a complete system to package either radioactive evaporator bottoms (regenerant chemicals and floor drain concentrates) or resins / sludges for disposal.
The radioactive waste solidification system mixes separate feeds of slurried or concentrated radioactive waste and dry cement in a small-volume continuous mixer.
Normal operation of the system includes direct filling of dry masonry cement into the cement storage silo from a bulk cement truck and transfer of a process quantity to the cement batch bin. Waste flows are fixed by preset metering pumps. Flows are also monitored by tachometers installed on the control panel. The resin / sludge is processed from the waste dewatering tank and evaporator bottoms are processed from the evaporator bottoms system.
Cement and evaporator bottoms or resin / sludge are introduced.into the mixer / feeder unit for thorough mixing and discharge into the container to be filled. The small-volume continuous mixer limits the surface contact of the wet cement and also limits the quantity of wet cement in the system at any time. A manual handcrank is provided to permit emptying the mixer / feeder by the operator in case of power loss or equipment malfunction.
Flush water connections are provided inside the mixer / feeder to remove cement residue. The cement-bearing flush water is collected in an empty container and incorporated into the following cement batch.
Functional controls sequence entire operations and interlocks minimize unsafe conditions or operator error. Safety features include:
Filling cannot take place unless the fill pipe is properly inserted into the container fill opening.
- An ultrasonic level sensor, and timer monitor waste level in the container to prevent overflowing. Cement-bearing flush water cannot be discharged unless a receptacle is in place.
The process control program and plant operating procedures must be strictly followed, however, to ensure correct solidification.
3.1.1 System Testing Thorough bench testing and full scale testing of typical materials will be performed to verify that disposal criteria will be met.
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3.2 SAMPLING AND TEST REQUIREMENTS Prior to solidification of a batch, a sample must be obtained and chemically analyzed to determine appropriate waste / cement ratios.
The " Waste Packaging Process Control Form" is then completed and signed by the Radiochemistry Engineer or designee.
s Solidification of a batch begins after a sample has been obtained and chemically analyzed (solidification tested if necessary). The " Waste Packaging Process Control Form" is then completed and signed by the Chief Radiation Chemist or a designee.
- If the results of the sample chemical analysis indicate that the waste batch chemistry fails to fall within the solidification test boundaries, the Waste Packaging Process Control Form cannot be completed until new sample solidification tests are run to establish appropriate cement / waste ratios.
Sample solidification is performed in accordance with a controlled plant operating procedure:
SP 73.014.01 - Radwaste Sample Solidification Test l
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- 3.2.1 -Liquids
- Liquids are considered as the evaporator concentrates. _ Prior to solidification of each batch of liquids, radioisotopic and chemical analysis sampling is perfomed in accordance with controlled plant operating procedures:
SP 72.002.18 - Radwaste Solidification Sampling SP 78.051.28 - Liquid Sample Gamma Spectral Analysis SP 78.030.30 - PH Determination 3.2.2 Wet Solids 4
Wet solids consist of spent resins and reactor water clean up sludge.
Prior to solidification of each batch of wet solids, radioisotopic and chemical analysis sampling is perfomed in accordance with control-led plant operating procedures:
SP 72.002.18 - Radwaste Solidification Sampling SP 78.051.28 - Liquid Sample, Gamma Spectral Analysis SP 78.030.35 - Solids Determination Sample' solidification tests were performed at SNPS-1 to determine boundary conditions for solidification.
3.3 SAMPLE SOLIDIFICATION TESTS 3.3.1 Liquids Liquid solidification bench tests were based en the two evaporator concentrate streams:
18 percent (weight) sodium sulfate expected from liquid waste i
evaporator 25 percent (weight) sodium sulfate expected from regenerant l chemical evaporator.
3.3.2 let Solids Bench tested resin wastes consisted of Ecodex precoat material and bead resin to be used at SNPS-1. Tests were performed on Ecodex precoat material and bead resins. It is anticipated full scale i testing will indicate a specific amount of " free" water above the
! settled solids volume is necessary to ensure proper solidification
! and waste / cement paste processing consistency.
3.3.3 Test Results The results of the bench tests indicate that good solidification with no freestanding water can be achieved at pH>5 by maintaining the fol-lowing weight / cement (W/C) ratios:
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. W/C 18% Na2SO 4 1.0 ,
25% Na2SO 4 0.9-1.1 Ecodex and Bead Resin 0.8-1.3 Solidification tests were also performed to ensure that within th; limits tested, the presence of excess flush water, citric acid, oil and/or glycol would not inhibit solidification of the waste types above. Results of these tests indicate solidification with no freestanding water can be achieved at pH>5 by maintaining the fol-lowing W/C ratios:
25% Na2SO 4 Bead Resin & Ecodex W/C2 W/C Citric Acid (1% by volume of 4 weight % 1.1 1.3 citric acid)
Excess Flush Water (less than 3.6% 1.1 1.3 by weight)
Oil (less than 1% by weight) 1.1 1.3 Glycol (less than 1% by weight) 1.1 1.3 Sample bench test boundary parameters and testing results for evaporator bottoms, filter media (Ecodex), and bead resin are listed in Appendix A.
3.4 SOLIDIFICATION SYSTEM OPERATION The SNPS-1 controlled plant operating procedures, SP 23.713.01-Solid Radwaste System, and SP 23.719.01-Liquid Radwaste Evaporator Bottoms are followed to assure that equipment performance and operation con-sistently produce acceptable burial products.
3.5 DISPOSAL OF FILTER CARTRIDGES Solids wastes, such as filter cartridges, solidified samples or other radioactive debris will be immobilized in concrete used to solidify evaporator bottoms wastes in accordance with plant operating pro-cedures SP (later) (Filter Cartridge Disposal), and SP 23.713.01, Solid Radwaste System. Resin-cement mixtures will not be used for this purpose because of the relatively high activity levels asso-ciated with resin wastes.
All solids are placed within an open-mesh metal basket located in the approximate center of the liner. The basket is suspended off the bottom so that the concrete mixture will totally surround the wastes in the basket. Liners that contain solid objects are specifically identified.
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- 4. RADWASTE FILTER SYSTEM PROCESS CONTROL 4.1 RADWASTE FILTER SYSTEM DESCRIPTION The radwaste filter system is used to process the following combined liquid radwaste streams which result from operation of the plant:
Low conductivity equipment drains
- Low conductivity wastes from the condensate demineralizer regeneration systems Ultrasonic resin cleaner backwash Decanted liquid from the phase separator to spent resin tank
- Blowdown from the reactor water cleanup, residual heat removal, and fuel pool cooling and cleanup The radwaste filter units are vertically mounted with horizontal filter discs stacked on an axially located hollow shaft. The filter assembly is spun to remove the precoat and filter residue cakes from the filter discs.
The complete filtering cycle is fully automated and controlled from the Radwaste Filter Panel Board. The precoated filter receives input from the liquid waste feed tank. At a preset condition such as high pressure drop across the filter, maximum cake thickness attained, or preestablished time interval, input from the liquid waste feed tank is discontinued. The cake is air dried, discharged, and the cycle repeated.
The filter assembly is designed for air drying the filter cake and for discharging the dry filter cake into a waste shipping container.
4.2 SYSTEM TESTING Full scale testing will be performed to verify that disposal criteria are met.
4.3 PROCESS OPERATION Controlled plant operating procedure S.P. 23.710.01 - Low Conductivity Liquid Raduaste System, is strictly followed to assure that equipment performance and operation consistently produce dry products.
4.4 DEWATERING PROCEDURE Dewatering liners ensure an acceptable filter cake product with less than 0.5 percent freestanding water in accordance with controlled plant operating procedure S.P. (later) (Dewatering Filter Cake).
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- A rastri'ction of the burial site at Barnwell, South Carolina requires that any filter media'used for liquid filtration must be stabilized by solidification in an approved media or disposed of in a HIC if the activity concentration of nuclides with greater than 5 year half-lives is more than 1pCi/cc by waste volume (to a maximum of 350pci/cc) and have less than 1 percent freestanding water. Filter media less than IpCi/cc by waste volume and less than 0.5 percent freestanding water can be dewatered in carbon steel containers.
4.5 ACTIVITY LIMITS Waste activity will be sampled per SP 72.002.18 - Radwaste Solidifi-cation Sampling and analyzed per SP 78.051.28 - Liquid Sample, Gamma Spectral Analysis in accordance with classification limits as defined in Appendix B.
- 5. FLOOR DRAIN FILTER PROCESS CONTROL 5.1 FLOOR DRAIN FILTER SYSTEM DESCRIPTION The floor drain filter system processes the liquid radwaste resulting from operation and maintenance of the station and consists of efflu-ents from the floor land laundry drains.
The filter is a horizontal traveling screen type equipped with air drying prior to filter cake discharge.
The filter cycle is fully automated. Upon an initiating signal, the precoated filter receives wastes from the feed tank. At a preset condition such as high pressure drop across the filter for a pre-established time interval, input from the feed tank and the body feed tank are discontinued. The cake is air-dried, discharged, and the cycle repeated. This sequence continues until it is either manually or automatically terminated. Automatic termination is by a low level signal from the liquid waste feed tank.
The filter assembly is designed for air drying the filter cake and air-aided discharge of the cake (without backflushing) into a ship-ping container.
5.2 SYSTEM TESTING Full scale tests will be performed to verify that disposal criteria are met.
5.3 PROCESS OPERATION Controlled plant operating procedure S.P. 23.711.01 - High Conductivity Liquid Radwaste System, is strictly followed to assure that equipment i performance a.nd operation consistently produce dry burial products.
l 5.4 DEWATERING PROCEDURE Dewatering liners ensure an acceptable filter cake product with less than 0.5 percent freestanding water in accordance with a controlled plant operating procedure S.P. (later) (Dewatering Filter Cake).
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A restriction of thm burial site at Barnwall, South Carolina rzquires that any filter media used for liquid filtration must be stabilized by solidification in an approved media or disposed of in a HIC if the activity concentration of nuclides with greater than 5 year half-lives is more than 1pCi/cc by waste volume (to a maximum of 350pCi/cc) and have less than 1 percent freestanding water. Filter media less than IpCi/cc by waste volume and less than 0.5 percent freestanding water can be dewatered in carbon steel containers.
5.5 ACTIVITY LIMITS Waste activity will be sampled per SP 72.002.18 - Radwaste Solidifi-cation Sampling and analyzed per SP 78.051.28 - Liquid Sample, Gamma Spectral Analysis in accordance with classification limits as defined in Appendix B.
- 6. RESIN DEWATERING SYSTEM PROCESS CONTROL 6.1 RESIN DEWATERING SYSTEM DESCRIPTION As an alternative to solidification, resin from the batch dewatering tank can be dewatered in a high integrity container to less than 1 percent freestanding water.
6.2 SYSTEM TESTING Full scale testing of high integrity containers will be performed to verify that disposal criteria are met.
6.3 PROCESS OPERATION The following controlled plant operating procedures apply:
S.P. (later) - (Dewatering Spent Resin)
S.P. 23.713.01 - Solid Radwaste System S.P. 23.718.01 - Liquid Radwaste Spent Resin These procedures will be followed to assure that equipment per-formance and operation consistently produce acceptable products.
6.4 DEWATERING PROCEDURE Dewatering liners ensure an acceptable burial product in accordance with a controlled plant operating procedure S.P. (later) (Dewatering Spent Resin).
A restriction of the burial site at Barnwell, South Carolina requires that any resin used for liquid processing must be stabilized by solidification in an approved media or disposed of in a HIC if the activity concentration of nuclides with greater than.5 year half-lives is more than 1pCi/cc by waste volume (to a maximum of 350pci/cc) and I have less than 1 percent freestanding water.
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6.5 ACTIVITY LIMITS Waste activity will be sampled per SP 72.002.18 - Radwaste Solidifi-cation Sampling and analyzed per SP 78.051.28 - Liquid Sample, Gamma Spectral Analysis in accordance with classification limits as defined in Appendix B.
- 7. ALTERNATE PROCESS CONTROL ARRANGEMENTS 7.1 PROCESS OPERATION In instances where additional vendor equipment is used, vendor.
operating procedures or the process control program will be followed to assure that equipment performance and operation consistently produce acceptable products.
- 8. REFERENCES SP 23.710.01 Low Conductivity Liquid Radwaste SP 23.711.01 High Conductivity Liquid Radwaste SP 23.713.01 Solid Radwaste System SP 23.718.01 Liquid Radwaste Spent Resin SP 23.719.01 Liquid Radwaste Evaporator Bottoms SP 72.002.18 Radwaste Solidification Sampling SP 73.014.01 Radwaste Sample Solidification Test SP 78.030.30 PH Determination SP 78.030.35 Solids Determination SP 78.051.28 Liquid Sample, Gamma Spectral Analysis
! SP (later) (Chemical Analysis - Wet Solids) l SP (later) (Filter Cartridge Disposal)
SP (later) (Dewatering Filter Cake)
SP (later) (Dewatering Spent Resin)
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APPENDIX A SAMPLE BENCH TESTS f
B4-1160002-4
. SAMPLE TESTS -
Samples were prepared at SNPS-1 of 18 percent sodium sulfate, 25 percent (by weight) of sodium sulfate, bead resin and powdered resin (Ecodex) at a pH range of 4-10 and with waste to cement (W/C) ratios of 0.8-1.3 (by volume). Testa at SNPS-1 have shown that for 18 percent (by weight) samples of sodium sulfate solidification is possible at a pH range of 4-10 and a W/C ratio of 1.0. Samples of 25 percent (by weight) sodium sulfate can be solidified at a pH range of 4-10 and a W/C ratio of 0.9-1.1 with the most economical W/C ratio of 1.1.
Ecodex and bead resin tested at pH values greater than 5 at W/C ratios of 0.8 to 1.3 produced a freestanding monolith with no free-standing water.
Additional samples of the previous listed sludges were taken con-taining such contaminents as oil, glycol, and citric acid at pH values greater than 5 and W/C ratios of 1.1 to 1.3. In each case, upon solidification, a freestanding monolith with no freestanding water was produced. Additional bench testing may expand the baseline W/C ratio data given.
B4-1160002-4 A-1
TABLE A1 EVAPORATOR BOTTOM SOLIDIFICATION TESTS 18 PERCENT DISSOLVED AND SUSPENDED SOLIDS W/C Ratio Sample pH (by volume) Results After 24 Hours 1 4.0 0.9 *NFSW, **FSS 2 4.0 1.0 NFSW, FSS 3 4.0 1.1 NFSW, Shatters easily 4 5.0 0.9 NFSW, FSS
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5 5.0 1.0 NFSW, FSS 6 5.0 1.1 NFSW, FSS 7 7.0 0.9 NFSW, FSS 8 7.0 1.0 NFSW, FSS 9 7.0 1.1 NFSW, FSS 10 9.0 0.9 NFSW, FSS 11 9.0 1.0 NFSW, FSS 12 9.0 1.1 NFSk, FSS 13 10.0 0.9 NFSW, FSS 14 10.0 1.0 NFSW, FSS 15 10.0 1.1 NFSW, FSS 1
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- NFSW = NO FREESTANDING WATER
- FSS = FREESTANDING SOLID B4-1160002-4A
. .- .. . TABLE A2 EVAPORATOR BOTTOM SOLIDIFICATION TESTS 25 PERCENT Na2SO 4
, W/C Ratio Sample gH (by volume) Results After 24 Hours 16 4.0 0.9 *NFSW, **FSS 17 4.0 1.0 NFSW, FSS 18 4.0 1.1 NFSW, FSS 19 5.0 0.9 NFSW, FSS 20 5.0 1.0 NFSW, FSS 21 5.0 1.1- NFSW, FSS 22 7.0 0.9 NFSW, FSS 23 7.0 1.0 NFSW, FSS 24 7.0 1.1 NFSW, FSS 25 9.0 0.9 NFSW, FSS 26 9.0 1.0 NFSW, FSS 27 9.0 1.1 NFSW, FSS 28 10.0 0.9 gr 3w, p33 l
29 10.0 1.0 NFSW, FSS 30 10.0 1.1 NFSW, FSS
- NFSW = NO FREESTANDING WATER
- FSS = FREESTANDING SOLID B4-1160002-4A L
s . TM E A3 FILTER SLUDGE SOLIDIFICATION TESTS ECODEX W/C Ratio
' Sample pH (by volume) Results After 24 Hours 31 7.0 0.8 *NFSW, **FSS 32 7.0 1.0 NFSW, FSS 33 7.0 1.3 NFSW, FSS -
41 5.5 0.8 NFSW, FSS 42 5.5 1.2 'NFSW, FSS
- NFSW = NO FREESTANDING WATER
- FSS = FREESTANDING SOLID B4-1160002-4A
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5 - TABLE A4 RESIN SOLIDIFICATION TESTS i
BEAD W/C Ratio-Sample g (by volume) Results After 24' Hours 34 7.0 0.8 Not enough water to entirely i wet cement 35 7.0 1.0 *NFSW,- **FSS 36 7.0 1.3 .NFSW, FSS t
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- NFSW = NO FREESTANDING WATER
- FSS = FREESTANDING SOLID j B4-1160002-4A
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TABLE A5 FILTER, SLUDGE, AND RESIN SOLIDIFICATION TESTS 50 PERCENT ECODEX, 50 PERCENT BEAD RESIN SLURRY W/C Ratio Sample pH (by volume) Results After 24 Hours 37 7.0 0.8 *NFSW **FSS 38 7.0 1.0 NFSW FSS 39 7.0 1.30 NFSW FSS 1
- NFSW = NO FREESTANDING WATER
- FSS = FREESTANDING SOLID B4-1160002-4A
TABLE A6 i SOLIDIFICATION TESTS WITil CONTAMINANTS .
25 PERCENT Na2 SO4 , ECODEX, AND BEAD RESIN CONTAMINANTS W/C Ratio Sample WASTE TYPE (ml) gli (by volume) Results After 24 llours 43 25% Na2SO 4 9 ml . 1120 9.0 1.1 *NFSW, **FSS 44 25% Na2SO 4 11 ml . ***C . A . + 9 ml . 1120 9.0 1.1 NFSW, FSS -
45 25% Na2SO 4 2.5 ml. Oil = 1% 9.0 1.1 NFSW, FSS 46 25% Na2SO 4 2.5 ml. Glycol = 1% 9.0 1.1 NFSW, FSS 47 Ecodex 9 ml . 1120 >5.0 1.30 NFSW, FSS 48 Ecodex 11 ml . C. A. + 9 ml .1120 >5.0 1.30 NFSW, FSS 49 Ecodex 2.5 ml. Oil = 1% >5.0 1.30 NFSW, FSS 50 Ecodex 2.5 ml. Glycol = 1% >5.0 1.30 NFSW, FSS 51 Bead Resin 9 ml . II 20 >7.0 1.30 NFSW, FSS 52 Bead Resin 11 ml. C.A. + 9 ml. !!2 0 >7.0 1.30 NFSW, FSS 53 Bead Resin 2.5 ml. Oil = 1% >7.0 1.30 NFSW, FSS 54 Bead Resin 2.5 ml. Glycol = 1% >7.0 1.30 NFSW, FSS
- NFSW = NO FREESTANDING WATER
- FSS = FREESTINDING SOLID
- C.A. = Citric Acid B4-1160002-4A -
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r APPENDIX B ACTIVITY LIMITS i
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, ACTIVITY LIMITS The maximum activity limits of the radioisotopic concentrations of waste which will be allowed in each waste classification are shown in Table Bl.
l TABLE B1 10CFR61 CLASSIFICATION OF WASTE ACTIVITY LIMITS BY RADI0 ISOTOPE Class A Class B . Class C Nuclide (pCi/cma) (pCi/cm3 ) (pCi/cm3 )
Any with half-life
<5 yrs 700 70,000 Theoretical maximum specific activity H-3 40 108 Theoretical maximum specific activity C-14 0.8 0.8 0.8 Ni-59 2.2 2.2 2.2 Co-60 700 70,000 Theoretical maximum specific activity Ni-63 3.5 70 70 Nb-94 0.002. 0.002 0.002 Sr-90 0.04 150 700 Tc-99 0.3 0.3 0.3 I-129 0.008 0.008 '0.008 Cs-135 84 84 84 Cs-137 1.0 44 4600 (Uranium) -
0.04 0.04 0.04 Alpha Transuranics: less than 10 nonocurie per gram all classes Pu-241: less than 350 nanocuries per gram all classes Notes: a. Concentrations may be averaged over package
- b. Class A waste is segregated at the disposal site and disposed of with minimum requirements on form and characteristics.
- c. Class B waste must meet both minimum and stability requirements on form and characteristics.
- d. Class C waste must meet more rigorous requirements on waste form and stability and must protect against inadvertent intrusion.
B4-1160002-4 B-1