ML20205C420
| ML20205C420 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/01/1986 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20205C401 | List: |
| References | |
| PROC-860801, NUDOCS 8608120325 | |
| Download: ML20205C420 (76) | |
Text
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1 B.V.P.S. - 0.M. 1.18.1 -
O DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION OPERATING MANUAL CHAPTER 18 PROCESS CONTROL PROGRAM UNIT #1 QA CATEGORY I G
1 0F 71 ISSUE 2
. REVISION 8 8608120325 860801 -
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i B.V.P.S. - 0.M. 1.18.1 CHAPTER 18 PROCESS CONTROL PROGRAM TABLE OF CONTENTS 4
M I. PURPOSE 3 of 71
, II. SOLID NASTE DISPOSAL SYSTEM DESCRIPTION 4 of 71 i
A. Function '4 of 71 B. Summary of System Operations 4 of 71 4 III. OPERATIONS PERFORMED TO VERIFY SOLIDIFICATION OF RESIN WASTES 6 of 71 l A. Feed Rate Control 6 of 71
! B. Operator Follow 6 of 71
- C. Final Inspection 6 of 71 IV. DISPOSAL OF SOLID OBJECTS IN CONCRETE LINERS 8 of 71
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V. CRITICAL ITEMS LIST 9 of 71 VI. LIMITATIONS AND SURVEILLANCE REQUIREMENT 10 of 71 A. Limitations 10 of 71
- B. Surveillance Requirements 10 of 71 TABLE 1 - System Paran.eters Pertinent to the Process Control Program 11 of 71 FIGURE 1 - Beaver Valley #1 Unit Solidification System 12 of 71
) APPENDIX A - ATCOR Engineered Systems, Inc. ,
- Report of Test Data - 10CFR Waste Form Compliance 13 of 71 t
APPENDIX B - P.C.P. Requirement Matrix 1 of 3 l
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0 J-4 o B.V.P.S. - 0.fl. 1.18.1
. . o j' PROCESS CONTROL PROGRA!! (continued)
, I. PURPOSE i
! 1. To provide appropriate radwaste system feed rates necessary to achieve the waste to cement ratios required to assure solidification of liquid radioactive wastes.
-2. To provide transfer of resins from system Ion Exchangers and the Resin Hold Tank (SW-TK-2)'to high integrity containers.
- 3. To provide results of tests performed to determine the waste to cement ratio required for solidification of the radioactive wastes (evaporator bottoms, boric acid and spent resins) generated at Beaver Valley. These results form the basis for set points indicated in Chapter 18 (Solid Waste Disposal System) of the Unit j 1 Operating Manual.
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- 4. To indicate the requirements for disposal of radioactive filter cartridges, rags and other solid objects in the matrix of the solidified concrete.
- 5. To indicate critical set points and limitations for operation of the radwaste solidification system. l
] 6. To indicate surveillance requirements for solidified waste shipped
< off-site.
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- PROCESS CONTROL PROGRAM (continued)
II. SOLID WASTE DISPOSAL SYSTEM DESCRIPTION A. FUNCTION The Solid Waste Disposal System (SWS) is designed to provide holdup, packaging, and storage facilities for the eventual off-site shipment and ultimate disposal of radioac'tive waste material.
Liquid wastes are immobilized in a concrete matrix using a ATCOR solidification system provided for this purpose. A facility is also provided to wash shipping containers after loading to prevent release of activity to the environment.
B.
SUMMARY
OF SYSTEM OPERATIONS The waste solidification system consists of a cement storage bin, cement feeder, mixer-feeder, resin waste hold tank, evaporator bottoms hold tank, resin hold and bottoms hold tank feed pumps, and the necessary piping, valves and instruments for the system to function. This equipment is used to immobilize the following wastes: (1) spent resin, (2) concentrated liquid wastes, and (3) solid wastes such as filter cartridges and polyethylene bags containing contaminated rags or other radioactive debris. Solid wastes are contained within an open-mesh metal basket located in
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the approximate center of the concrete liner. The basket is suspended of f the bottom so that the concrete mixture will totally surround the basket.
Wastes are solidified in a carbon steel liner which hcs a total capacity of approximately 65 cubic feet. This liner is moved into position under the mi,xer-feeder by transfer cart through remote control operation. Where solid waste disposal is involved,
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the metal basket containing the wastes is placed within the concrete liner prior to moving the liner into position. Transport of the liner is performed with the operator stationed behind a concrete wall at the waste solidification control panel. A television camera is provided for operator view of operations involved with solidification.
Liquid wastes requiring solidification come from either the evaporator bottoms hold tank or the resin waste hold tank.
Schematic design of the overall system is shewn in Figure 1.
System parameters are listed in Table 1. Equipment design requires that each waste form be processed separately. Though capable of automatic operation, the system is operated in the manual mode to ensure that the system is operating properly and that the set points for cement-liquid waste ratios are as required to achieve solidification. Operator attention is required to actuate the controls for each stop of the operation. Metered flow of cement and waste solution are combined at the mixer-feeder which discharges into the steel liner. Cement feed is maintained 4 0F 71 ISSUE 2 REVISION 8
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,[ B.V.P.S. - 0.M. 1.18.1 z PROCESS CONTROL PROGRAM (continued) ;
at a constant rate for all solidification operations. Liquid waste flows are adjusted as required to provide waste to cement ratio specified in the Operating Manual.
After the liner has been filled with concrete, it is covered with a lid and the liner is moved from the loading area. The liner is allowed to set for five days or more. While the controls exercised in maintaining a proper cement / liquid ratio ensure solidification, an inspection of containers from each shipment is also performed to check for free water. In the event that water is present, cement will be added as required to achieve a water free mix. The lid is then fastened in place and sealed to the liner with a metal seal. The outside of the liner is washed with a series of spray nozzles to remove any surface contamination resulting from loading operations. A smear check is performed prior to moving the liner from the loading area to the clean side.
The sampling system consists of the appropriate valves and sink located at the discharge of the metering pumps (SW-P-6) and (SW-P-7). When the desired amount of waste for solidification is in the hold tanks (SW-TK-2) resin hold tank or the bottoms hold tank (SW-TK-8), these tanks are mixed to a desired consistance by running the agitator in the resin hold tank or recirculating the bottoms hold tank as per the operating manual. Before the solidification process begins a sample is obtained for ratio / analysis of radionuclides, and concentration of Boric Acid.
The system is being designed with the appropriate valving and piping for transferring from any group of Ion Exchanger to a high integrity container. The system will also have the appropriate piping and valves to transfer resin from the resin hold tank (SW-TK-2) to a high integrity container.
After the resin are transferred into a high integrity container, there are appropriate pumps, valves and piping to de-water back to the resin hold tank. The procedures for transferring resin will be located in the Operating Manual. The procedures for the use and handling of High Integrity Containers for disposal will be located in the Operating Manual Section 4 or the appropriate vendors procedures. It will be the responsibility of the Site Radioactive Waste Coordinator to maintain the proper Certificate of Compliances and procedures for the use of High Integrity Containers.
5 0F 71 ,
ISSL'E 2 REVISION 8
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PROCESS CONTROL PROGRAM (continued)
III. OPERATIONS PERFORMED TO VERIFY SOLIDIFICATION OF RESIN WASTES A. FEED RATE CONTROL Three separate feed rates combine to makeup the resin concrete mixture formed in the mixer-feeder of the solidification system.
These are as follows:
- 1. Cement Feed Pump The feed rate of this pump is adjustable over a wide range.
Flow is held constant at a dial setting as noted in Chapter 18 of the Operating Manual. With this setting, the pump will deliver the proper amount (1bs) of cement per minute.
- 2. Waste Hold Tank Metering Pumps l
l The metering pumps are a variable speed pump being able to l adjust from a minimum to a maximum feed rate in GPM. The maximum feed rates will be noted in the Operating Manual.
l l 3. Seal Water Flow to Pump l
l This flow is held constant at the minimum flow requirements to protect pump bearings. Flow adjustment is made using a low range flow meter.
l NOTE: Excessive seal water flow will change the W/C and ,
l therefore, limits noted in operating procedure must l be followed.
I B. OPERATOR FOLLOW j i
! As described above, solidification of resin wastes is achieved by l combining two constant flow rate systems with one adjustable flow l
l system (waste metering pump). The liquid waste to cement ratio is i
maintained within a relatively narrow band in the range where ,
l solidification is known to occur on a consistent basis. With only )
l one control valve to adjust, the operator can maintain close !
l surveillance of solidification operations. Full time operator
! attention is maintained since the system is operated in the manual mode. The system holds at the completion of each step until the operator activates a control to continue the sequence of operations.
C. FINAL INSPECTION As a final check, a visual inspection is performed to determine the presence of free liquid prior to shipment of the full liner.
l 6 0F 71, ISSUE 2 l REVISION 8 i
B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued)
If free water exists, dry cement is manually added to achieve solidification of this water, if needed.
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7 0F 71 ISSUE 2 REVISION 8
- a B.V.P.S. - 0.M. 1.18.1
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PROCESS CONTROL PROGRAM (continued) .
i IV. DISPOSAL OF SOLID OBJECTS IN CONCRETE LINERS i'
Solid wastes such as filter cartridges and contaminated rags or other radioactive debris will, on occasion, be placed within an open-mesh metal basket and immobill:ed in the concrete of the waste being
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solidified. The basket is suspended off the bottom so that the concrete mixture will surround the wastes in the basket. Liners that 4 contain solid objects will be so id'entified. Radcon will be notified prior to placing solids into a liner to enable appropriate sampling.
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j' PROCESS CONTROL PROGRAM (continued)
V. CRITICAL ITEMS LIST The following list indicates set points and items in the solidification system operating procedures (Chapter 18 - Solid Waste Disposal System).
Close operator follow is required in these areas to assure proper operation of the system and to verify solidification of resin hold tank or evaporator bottom hold tank wastes.
A 1. Feed rate of the cement feed pump is held constant at a dial setting as indicated in the operating procedures for all solidification operations performed at Beaver Valley. Any variation in this dial setting will affect solidification of the waste. Since this is an adjustable pump, the dial setting should be checked prior to performing solidification.
- 2. The correct resin-water ratio must be maintained as indicated in the operating procedure. Insufficient water can result in the loss of water from the resin beads during the hydration process involved as the concrete sets. The hydrated resin can swell on i subsequent exposure to water creating tensile forces which can i damage concrete integrity. Too much water can result in free water on the top of the liner.
- 3. Seal water flow to the metering pumps must be held at a minimum as indicated in the operating procedure. Excessive seal water flow will change the W/C ratio, thus can affect solidification of waste.
- 4. The evaporator bottoms hold tank metering pump must not exceed the maximum flow rate. Flow rate requirements are identified in the Operating Procedure. .
- 5. Boric acid determinations are required during evaporation to control a boric acid concentration in the nominal 10 to 12% range at the waste tank.
- 6. Samples are taken prior to solidification and used for determining Isotopic Analysis. The samples from the evaporator bottoms tank are also used to check that boric concentrations do not exceed 12*.
- 7. Contaminated oil or items with contaminated oil in them will be processed by an approved method. !
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B.V.P.S. - 0.M. 1.18.1
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PROCESS CONTROL PROGRAM (continued)
VI. LIMITATIONS AND SURVEILLANCE REQUIREMENTS A. LIMITATIONS
- 1. If solid wastes (e.g., filters cartridges, rags, etc.) are l immobilzed in the concrete matrix, the wastes will be l contained within an open mesh matal basket located in the approximate center of the concrete liner. The basket is suspended off the bottom so that the concrete mixture will surround the basket.
- 2. The waste in the liner must be solified and have no free water as determined by visual inspection prior to sealing the liner. The liner is inspected for free water prior to I sealing which occurs 5 days or more after the liner is filled.
- 3. The high integrity containers will be dewatered to meet any of the vendors or disposal site criteria for disposal.
B. SURVEILLANCE REQUIREMENTS
- 1. The Effluent and Waste Disposal S'emi-annual Report shall include the following information for each type of solid -
waste shipped off-site during the report period:
- a. Container volume
- b. Total curie quantity (determined by measurement or estimate)
- c. Principal radionuclides (determined by measurement or estimato) -
- d. Type of waste (e.g., spent resin, evaporator bottoms)
- e. Type of container
- f. Solidification agent
- 2. The metering pumps (resin, bottoms, cement) will be anually checked for the proper waste and cement discharge per Chapter 1.55A.4 OST 1.18.2.
- 3. Functional Tests will be performed for waste stability every 10th batch or annually which ever accures more frequently by 1.53A.4 OST 1.18.1.
10 0F 71 ISSUE 2 REVISION 8 l
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B.V.P.S. - 0.M. 1.18.1 e .
PROCESS CONTROL PROGRAM (continued)
TABLE 1 l SYSTEM PARAMETERS PERTI. VENT TO THE
' PROCESS CONTROL PROGRAM l Liner capacity Approximately 65 cubic ft. i Liner dimension 49 inches diameter x 62 inches high Liner weight (fully loaded) Approximately 6000 lbs f Shipping container types for 1.5 inches steel ,
liner (if necessary) 1.5 inches lead equivalent 4 inches lead equivalent Vendors containers as required Spent resin (bead form)
Evaporator bottoms which can contain boric acid Solidification material Cement (Specification provided by ATCOR)
Solid wastes immobilized Filter, cartridges, rags,.etc.
In liner Waste to cement (W/C ratio Class A .5 for evaporator bottoms) by weight Class B/C .4 4
W/C ratio for resin wastes Class B/C 0.51 by weight Maximum boric acid concen- 12% concentration by sampling tration in evaporator bottoms before solidification hold tank .
Detection of free water Visual inspection on liner prior to sealing the lid
- Dewatered resin By measuring the last pumping Curie content in liner Determine by analysis of the waste solution or estimated, based on gamma survey performed after l solidification i Identification on principle Estimated by gamma ray spectrum of radionuclides waste prior to or after concentration !
by ratio and analysis, and by sampling of waste before solidification 11 0F 71 ISSUE 2 REVISION 8 i
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RESIN y BOTTOMS H O l.D E HOLD CEMENT 1
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- BEAVER VAL LEY # I UNIT .
SOLIDIFICATION SYSTEM .
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APPENDIX A ATCOR ENGINEERED SYSTEMS, INC.
REPORT OF TEST DATA 10CFR61 WASTE FORM COMPLIANCE 13 0F 71 ISSUE 2 REVISION S
- B.V.P.S. - 0.t!. 1.18.1 ,
PROCESS CONTROL PROGRA!! (continued) 1 1 I. INTRODUCTION l Testing has been performed for Beaver Valley Unit #1 to determine the V/C ratios required to assura solidification of resin and evaporator bottom waste solutions using cement as the immobilizing agent.
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- B.V.P.S. - 0.?!. 1.18.1 ATCOR ENGINEERED SYSTE!!S, INC.
REPORT OF TEST DATA 10CFR61 WASTE FOR21 C0?!PLIANCE APRIL 1985 by ATCOR ENGINEERED SYSTE!!S, INC.
AVON, CONNECTICUT 06001 15 0F 71 ISSUE 2 REVISION 8
B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued)
TABLE OF CUKTENTS Page I. INTRODUCTION i7 of 71 i
II. WASTE AND SOLIDIFICATION MEDIA FORMULAS 17 of 71 III. CERTIFICATION TESTING 23 of 71 i
Compressive Strength 23 of 71 Irradiation 24 of 71
, Biodegradation 24 of 71 90-Day Leachability 2S of 71 Water Immersion 27 of 71 Thermal Degradation 27 of 71 Free-Standing Liquids 28 of 71 IV. FULL SCALE TEST DATA 28 of 71 V. WASTE STREAM VARIATIONS 31 of 71 VI.
SUMMARY
31 of 71 APPENDICES:
1 l A. Leach Tests - Data & Calculations 32 of 71 j' B. Irradiation 36 of 71 C. Biodegradation 44 of 71 D. Full Scale Solidification Test Program 48 of 71 E. Quality Assurance Data 69 of 71 F. References 70 of 71 l l
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B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued)
I. INTRODUCTION The ATCOR Process Control Program for cement solidification was evaluated according to the guidance of the NRC Technical Position Paper on Waste Form, Section C. This addendum documents the test results obtained for generic ATCOR solidification formulas including concentrates, resi'n beads, and filter sludges for qualification of Class "B" and "C" wasts under the 10CFR61 waste stability criteria.
With the exception of irradiation and biodegradation studies performed respectively by the Oak Ridge National Laboratories and the ' University of South Carolina, all laboratory scale tests were conducted by Chem-Nuclear Systems. The full scale tests were conducted at the ATCOR full scale solidification plant located in Bloomfield, CT. Core borings and plastic 2" x 2" standard cube samples obtained during the pour were taken by an independent concrete testing laboratory, Henry Souther Laboratory, Inc. in Bloomfield, Connecticut. This laboratory also performed the compressive test.
Reference is made throughout this document in Chem-Nuclear Systems, Inc. (CNSI). ATCOR's parent company who performed the laboratory scale portions of the test program.
II. WASTE AND SOLIDIFICATION MEDIA FORMULAS Efforts were made to determine waste stream formulations through examination of ATCOR and its parent company, CNSI, operating experience
, and consultation with utility representatives. The concentration of boric acid waste was based on optimum performance of existing radwaste evaporators. The compositions of demineralization media and filter precoat slurries vary considerably but are composed of two basic types.
. 1. Bead Resin - Bead resins are used to demineralize liquid radwaste I
by exchanging nonradioactive ions with radioactive ions. The 3 resins are usually organic in composition and spherical in
- configuration.
- 2. Filter Sludge (Powdex) - Examples of filter sludge media include Powdex (finely crushed organic resin bead), Ecodex and -Solkafloc (fibrous, orgdnic material), and diatomaceous earth (D.E., a s111ccous material). The precoat in suspension deposits on a filter element that then becomes the filter layer. As this filter layer builds up, the contaminants are trapped. Eventually, the buildup of filter media reduces the overall efficiency of the filter and the precoat media is backflushed and discarded.
The filter sludge media waste test sample was based on concentrations of the various types of media used at an operating plant. Mixed bed resin beads were chosen for test since they are the most common waste form.
- 17 0F 71 ISSUE 2 REVISION 8 e r~- -
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B.V.P.S. - 0.M. 1.10.1 .
PROCESS CONTROL PROGRAM (continued)
Based on the above discussion, ATCOR chose to select several mix formulas bracketing the targeted or anticipated waste forms for filter sludge (powdex) and mixed bed resin. This was done to demonstrate that flow variations which occur as a normal event in any plant operation would still produce an acceptable, stable, free-standing product which would conform to the 10CFR61 and Branch Technical Position ,
I requirements.
Test specimens were prepared in accordance with the CNSI Process Control Program (SD-0P-003) previously approved in CNSI Topical Report No. 2-4313-01354-OlPA. An exothermic reaction will be produced as a result of the chemical reactions associated with hydration. The rate of heat dissipation from a large waste liner or 55 gallon drum will be .
lower then heat transfer from the small sample container. Therefore.
the sealed sample container is place in a thermostatically controlled oven for at least 48 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to simulate the higher temperature which would exist in an actual liner liner or drum.
This process of oven curing has been justified in light of the following presentation. The Concrete Construction Handbook, 2nd Edition, Joseph J. Waddell Editor-in-Chief, 1974; Section 6, Figure 13, entitled "Effect of Steam Curing at Temperatures Below 200*F on the Compressive Strength of Concrete at Early Ages". This figure provides the following correlation for elevated cure temperatures to those obtained for a 3-day cure at 70*F.
Cure Time for 80?.
Cure Temperature of 3-Day Strength 70* F 50 Hours I 100* F 32 Hours 130" F 24 Hours Based on the measured exothermic reactions of cement solidified waste in bulk containers, the use of conditioning ovens at about 140-160*F permits evaluation of samples in 8-24 hours.
The samples are then allowed to cool to ambient temperature prior to unsealing. Coment/ waste mixtures in large volumes cure rapidly and attain full strength in much less time than the 28-30 days cure time normally associated with construction concrete.
Curing is the complex process during which the cement and waste mixture interacts to form insoluble mineral compounds providing a gel which ultimately forms a hard, water-free product. During this process, it is important that enough water is present in the mixture to allow complete hydration of the cement. Therefore, it is necessary to seal the sample container to prevent any evaporation of liquid.
18 0F 71 ISSUE 2 REVISION 8
B.V.P.S. - 0.H. 1.18.1 PROCESS CONTROL PROGRAM (continued) 1 CSSI Product development laboratory has performed comparative compressive tests on simulated wastes using Portland types 1, II and
< III cements. Test results have been comparable among all three types of cement. The following, tables illustrate the similarity of chemical composition of Portland types I, II and III cements.
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PROCESS CONTROL PROGRA>l (continued)
PRINCIPAL CO>tPOUNDS PRESENT IN PORTLAND CEMENTS Compound Formula Abbreviation t
Tricalcium Silcate 3Ca0'S10: CS 3 s
l Dicalcium Silicate 2Ca0'S10: CS Tricalcium Aluminate 3Ca0*A1:0 3 CA 3
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Tetracalcium Aluminoferrite 4Ca0*A1:03 *Fe 0 3 C.AF COMPOUND C051 POSITION OF PORTLAND CEMENTS Tvpo of Coment Comoound Composition. *.
) I. Normal 45 27 11 8 II. Modified 44 31 7 13 III. High Early Strength 53 19 10 7 IV. Low Heat 20 52 6 14 V. Sulfate Resistant 38 43 4 8 Brookhaven National Laboratories has reported on radwaste solidification test perfomed using Portland I, II and III cements. These test also confirm that comparable results for leach testing, water-immersion and compressive strength are obtained for all three cement types.**
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- Evaluation of Isotope Migration --
Land Burial: Water Chemistry at Commercially Operated Low Level Radioactive Waste Disposal Sites. A.
Weiss and P. Columbo, Nureg/CR 1289 (Upton, NT: Brookhaven National Laboratory) 4 4
20 0F 71 ISSUE 2 REVISION 8 i
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.- B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRA!! (continued)
The binder used in this test program was a Portland Type I based masonry cement manufactured by the Western Lime & Cement Co. of West Bend, Wisconsin and identified at 1-1-0 Type ".'1" masons mix. This mix represents equal volumes of Type I Portland cement and Type S double hydrated dolometic lime. The constituents of this cement are listed below:
I TABLE 3 MASONRY CEMENT Test Results Determined Constituents
- Silicas (SiO2 ) 0.92*.
Iron (Fe:03 ) 0.26*. .
Aluminum (A1:03 2.02*.
Calcium (Ca0) 42.97*
Magnesium (Mg0) 27.40*.
Total Sulphur (S) Less than 0.01*.
Sulphur Trioxide (S03 ) Less than 0.01*.
Phosphorus (P2 0s) 0.002*.
Strontium 0xide (Sr0) 0.26*
Manganese (Mn) 0.015*.
Ferrous Iron (Fe) 0.04*.
j Water at 120*C Trace Water - Total 24.36*
- Insoluble Matter 0 . 05*.
l Loss on Ignition 26.05*
1 Available Lime Index (Ca(OH)2 44.78*.
i NOTE: All determinations have been made according to methods prescribed by the American Society for Testing and Materials.
Information obtained from:
WESTERN LIME & CEMENT CO., Box 2076, Milwaukee, Wisconsin 53201 - Miracle Lime 210F 71 ISSUE 2
_ REVISION 8
B.V.P.S. - 0.M. 1.18.1 . .
PROCESS CONTROL PROGRAM (continued)
- The following formulas present the waste types, waste volumes used, bindars and binder volumes used. These formulas are used for .all the laboratory i testing contained in this report.
Filter Sludge (Powdex) Formulas Tested Graver Anion Powdex 72 gm Graver Cation Powdex 144 gm Ecodex 100 gm Ecosorb 76 gm .
Solka Floc 8 gm Water Containing 8 gm Na2SO. 1100 gm* ,
Binder:
!!asonry Cement See following mix ratio Mix 1 - Measure 1500 ml of filter sludge waste and mix with 1335 gm of masonry cement.
Mix 2 - Measure 1500 ml of filter sludge waste and mix with 1150 gm of masonry cement.
Mixed Bed Resin Beads Formulas Tested Dcmineralized Water 260 gm Dow Mr-3 Virgin Beads - Mixed Bed 400 gm 50*. Anion - 50". Cation 10*. Sodium Sulfate Solution 13 gm*
Slaked Lime 65 gm*
Binder:
Masonry Cement See Following riix Ratio Mix 1 - Measure 465 ml of settled beads and 180 ml of excess water.
Add 654 gm of masonry cement.
$ 511x 2 - Measure 375 ml of settled beads and 225 ml of excess water.
Add 654 gm of masonry cement.
Mix 3 - Measure 330 ml of settled beads and 270 ml of excess water.
Add 654 gm of masonry cement.
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22 0F 71 ISSUE 2 l REVISION 8 m - y + - - - - - y. -, - - y 9my - - ~ %
- ' B.V.P.S. - 0.M. 1.18'.1 PROCESS CONTROL PROGRAM (continued) i Concentrates Formulas Tested 4
- 12*. Boric Acid Solution @ 170* F 503 ml l'
Binder:
Masonry Cement 800 gm
- The addition of Na:SC. or (Ca(OH) resulted in approximately 80 percent depletion of the demineralization media to simulate typical plant wastes.
4 THE AMOUNTS OF WASTE AND BINDERS USED ARE TYPICAL " LUES AND MAY VARY SLIGHTLY DEPENDING ON THE WASTE COMPOSITION.
J III. LABORATORY SCALE CERTIFICATION TESTING The following waste form test results pertaining'to the 10CFR61 Branch 4 Technical Position demonstrate conformance in all areas. All testing was performed by ATCOR's parent company, CNSI, with the exception of biodegradation and irradiation. ;
- 1. Compressive Strength Criteria Test specimens were tested for compressive strength in accordance with ASTM C39. All solidification test specimens exhibited values greatly exceeding the 50 lbs/in* requirement. The resulty of average initial break strength for the thermal cycling, irradiation and water immersion test samples prior to testing are shown below.
Compressive Strength 2
l Waste Form (Ibs/in Concentrates-12 wet boric acid j 67*. Waste Loading by Volume 1718 Mixed Resin Beads-Mix No. 1 72% Waste Loading by Volume 791 Mixed Resin Beads-Mix No. 2 76*. Waste Loading by Volume 913
, Mixed Resin Beads-Mix No. 3 76% Waste Loading by Volume 759 Filter Sludge-Mix No. 1
- 78*. Waste Loading by Volume 835 23 0F 71 ISSUE 2 8
REVISION 8
B.V.P.S. - 0.M. 1.18.1 ',',
PROCESS CONTROL PROGRAM (continued)
Compressive Strength Waste Form (1bs/in*
Filter Sludge-Mix No. 2 81*. Waste Loading by Volume 587
- 2. Irradiation to 10' Rads Test specimans were irradiated to an exposure of 10' rads with a spent fuel element at the Oak Ridge National Laboratories. The irradiation chamber contained a neutron shield to enusre that the sample was exposed only to gamma radiation and was aircooled to limit ambient temperatures to 150* F. After irradiation, the compressive strength of the test specimens was determined in accordance with ASTil C39. The results were well above the 50 lbs/in* requirement and are listed below.
Compressive Compressive Strength Strength Before After Irradiation Irradiation Waste Form 11bs/in8 ) (1bs/in2 )
Concentrates-12 wt'a boric acid 67*. Waste Loading by Volume 1481 2500 Mixed Resin Beads-Mix No. 1 72*. Waste Loading by Volume 779 775 Mixed Resin Beads-Mix No. 2 7o*. Wa te Loading by Volume 1028 1106 Mixed Resin Beads-Mix No. 3 76*. Waste Loading by Volume 763 1050 Filter Sludge-Mix No. 1 78*. Waste Loading by Volume 909 1806 Filter Sludge-Mix No. 2 81* Waste Loading by Volume 863 1000
- 3. Biodegration Studies Test specimens were subjected to biodegradation studies by the University of South Carolina Biology Department. The testing was conducted in accordance with modified ASTM standards. Test data is based on fungi and bacteria species and strains specified in the ASTM standards. After 21 days of incubation, no significant culture growth on the surface of the cement billets was visible nor was any significant strength loss detected for any of the waste forms tested.
24 0F 71 ISSUE 2 REVISION 8 ,
.s B.V.P.S. - 0.H. 1.18.1 I' PROCESS CONTROL PROGRAM (continued)
These biological results are predictable considering the high pH generated by cement in contact with aqueous systems (see attached report by the University of South Carolina, Appendix C).
i .
In no case was there any macroscopic or microscopic sign of fungal or bacterial growth during or at the end of the 21 day incubation period.
The results are summarized in the following table.
Compressive Compressive Compressive Strength Strength Strength Before After After
. Biodegradation Biodegradation Biodegradation (Fungi) (Bacteria) 2 2
Waste Form (lbs/in )*
2 (1bs/in )* (1bs/in )*
Concentrates-12 wt% boric acid 67*. Waste Loading by V 1 2627 2387 1910 Mixed Resin Beads-Mix No. 1
. 72* Waste Loading by Volume 96 92 101 i
Mixed Resin Beads-Mix No. 2 3 76% Waste Loading by Volume 98 96 98 d Mixed Resin Beads-Mix No. 3 i 76*. Waste Loading by Volume 112 173 173 Filter Sludge-Mix No. 1 78*. Vaste Loading by Volume 1234 1141 982 4
Filter Sludge-Mix No. 2 81*. Waste Loading by Volume 1353 1273 1326
- Compressive strength were determined by the University of South Carolina Civil Engineering Department.
- 4. 90 Day Leachability Leach test specimens were prepared and each was spiked with approximately 0.5 mil 11 curies of radiotracers Cs-137, Co-60, and Sr-85.
The surface to volume ratio for the leach test specimens was 1.25. The test specimens were immersed in 2200 ml of leachant consisting of
- demineralized water.
The leach testing was conducted'in accordance with ANS 16.1, draft 3, and was continued for a duration of 90 days. Leachant samples were analyzed by gamma-ray spectroscopy using a 3X3 NaI(Th) well-detector calibrated with an NBS Traceable Standard. As shown in the following table, waste foraulas exhibited leachability index values of 6 or above, thereby meeting the Branch Technical Position requirements.
25 0F 71 ISSUE 2 REVISION 8
. 9
,. - -- ' ~ , , ,,- , -,.,n , . , , - - . , . , , -- - - - - - , .m ----r,
i B.V.P.S. - 0.M. 1.18.1 ",,
PROCESS CONTROL PROGRAM (continued) -
A Quality Control Program was established for the radiochemical measurements using USNRC Regulatory Guide 4.15 as a reference. The release of Co-60 from test specimens for all waste forms (except the 12 wtt boric acid formula), as determined from leachant sample analysis, was found to be below the Minimum Detectable Level for the gammi spectroscopy system. No measurable release of Co-60 was observed for any of the waste forms examined during the 90 day period of leach testing with the exception of PWR concentrate 12% boric acid. The leaching rates of Cs-137 and Sr-85 for all waste forms are reported in the next table. The leachability index (Negative Log of the Diffusivity) did not fall below the minimum value of 6 for any formula tested. ,
Co- Cs-137 Sr-85 Waste Form Index Index Index Concentrates-12 wt% boric acid )
67*. Vaste Loading by Volume 10.1 6.2 9.8 Mixed Resin Beads-Mix No. 1 72% Waste Loading by Volume
- 7.0 9.3 Mixed Resin Beads-Mix No. 2 76% Waste Loading by Volume
- 7.0 9.3 Mixed Resin Beads-Mix No. 3 76% Waste Loading by Volume
- 6.8 9.3 Filter Sludge-Mix No. 1 l
78% Waste Loading by Volume
- 6.4 S.8 Filter Sludge-Mix No. 2 81% Waste Loading by Volume
- 6.4 8.6
- Co-60 was below the lower limit of detection.
A Icach test program conducted in 1981 examined the effects of employing Icachants other than deionized water. Leach tests were run on duplicate formulas at three different pH values (4,7 and 10). The values were selected based upon pH values measured at existing shallow land burial trenches. Sodium hydroxide, potassium hydroxide, nitric acid and sulfuric acid were used to adjust the water pH. There were no significant differences among the results obtained with the various leachants. Based upon these results, the decision was made not to perform leach testing using synthesized sea water. It is concluded that leachability measurements, based upon use of deionized water, adequately definas expected waste form behavior under typical land burial conditions.
26 0F 71 ISSUE 2 REVISION 8
1
.- B.V.P.S. - 0.M. 1.18.1 o .
PROCESS CONTROL PROGRAM (continued)
- 5. Water Immersion for 90 Davs Test specimens of each waste form were immersed in water for a period of 90 days. Compressive strength determinations were made at various time intervals during this period. All test specimens exhibited compressive strength values well above the minimum 50 lbs/in requirement. Visual examination of the test specimens indicated no loss of product integrity.
Compressive Compress ive Strength Strength Before After Immersion Immersion z
Waste Form (1bs/in 2) .(lbs/in )
Concentrates-12 wt'. boric acid 67% Waste Loading by Volume 2400 3050 Mixed Resin Beads-Mix No. 1 72% Waste Loading by Volume 750 631 Mixed Resin Beads-Mix No. 2 7o% Waste Loading by Volume 900 650 Mixed Resin Beads-Mix No. 3 76% Waste Loading by Volume 838 635 Filter Sludge-Mix No. l 78% Waste Loading by Volume 660 472 Filter Sludge-Mix No. 2 81% Waste Loading by Volume 335 491
- 6. Thermal Degradation , ,
Test specimens were subjected to thermal degradation testing which consisted of a series of 30 thermal cycles in accordance with section 5.4.1 through 5.4.4 of ASTM B553. The high and low temperature limits were 60 C and -40*C respectively. Visual ' examination of the test specimens after completion of the 30 cycles indicated no product deterioration. There was, however, surface cracking on most of the test samples. Three specimens were tested for each waste formula.
Compressive strength samples were run at various times to determine if any degradation was occuring. Average results after 30 cycles were presented in the following table:
27 0F 71 ISSUE 2
, REVISION 8 l
_ _ _ _ _ __ . - . ]
y.
B.V.P.S. - 0.M. 1.18.1 . .
PROCESS CONTROL PROGRAM (continued)
I Compressive Compressive Strength Strength Before Thermal After Thermal Degradation Degradation Waste Form (1bs/in 2) (lbs/in )
8 Concentrates-12 wtt boric acid 67% Waste Loading by Volume 1273 2085 Mixed Resin Beads-Mix No. 1 72% Waste Loading by Volume 844 589 Mixed Resin Beads-Mix No. 2 76% Waste Loading by Volume 812 477 i
Mixed Resin Beads-Mix No. 3 76% Waste Loading by Volume 676 366 Filter Sludge-Mix No. 1 78% Waste Loading by Volume 939 501 1
Filter Sludge-Mix No. 2 81% Waste Loading by Volume 573 414
- 7. Free Standing Liquids Test specimens of cement solidified waste forms did not exhibit free standing liquids.
IV. FULL SCALE TEST DATA Full scale test were conducted in ATCOR's full sclae pilot plant located in Bloomfield, Connecticut. A test program was prepared (presented in Appendix D) to control preparation of waste, document equipment calibration and identify flow rates based on the formulas used in the laboratory scale tests. A Process & Instrument Diagram of the test equipment is depicted in Figure I, Appendix D. Formulas used in the full scale tests are identified in Sections V & IV.
The waste and cement were mixed and discharged into a 55 gallon drum which was then capped and left sealed for 48 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The caps were then removed and the drums examined for free liquid. No drum exhibited any trace of liquid on the surface. The samples were then allowed to cure for approximately 28 days.
Two different types of samples were taken:
- 1. Plastic samoles - The plastic samples were standard 2 inch x 2 inch cube grab samples taken during the middle third of- the pour at the discretion of the testing laboratory. The samples were 28 0F 71 ISSUE 2
. REVISION 8
-n -A *-~-i- m w - y e v- --
g
.s e B .V. P.S . - 0.!!. 1.18.1
=* PROCESS CONTROL PROGRA!! (continued) tagged by inserting a fine wire with sample ID into the cube.
They were retained at the pilot plant for a minimum of 71 hours8.217593e-4 days <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br /> and then transported to Henry Souther Laboratory. After approximately 2? days, the cube samples were subjected to a compression test. The above samples were taken because the ambient temperatures at the pilot plant ranged from 40*F to 65'F.
l This would tend to retard the curing process and was viewed as backup information to the core samples.
i
- 2. Core samples - After a cure time of approximately 28 days, the tops of the metal drums were cut away and a hole burned into the lower third of the drum to extract a vertical and radial core sample. The radial sample location was randomly selected.
Technicians from Henry Souther Laboratory took the core samples using a 2 inch coring bit. The samples were marked with -a dye marker as to the location and from which drum they were removed.
i The identification was as follows:
Waste Type Resin 1 A j l l A Vertical j Drum No. l l B. Vertical 1 i l
Compression tests were conducted per AST!! C-39.
The following table presents the full scale compression tests results and, as indicated, all formulas passed the minimum requirements as outlined in the 10CFR61 Branch Technical Position.
l l
4 I
I 29 0F 71 ISSUE 2 REVISION 8 I
0 e
)
COMPRESSIVE TEST RESLA_TS OF FLA_L SCALE 10CFR61 MIXES TYPE OF l WASTE FORM COMPRESSIVE STRENGTH PSI l
I DRLN NO. / DATE CAST l 1 /1-31-85 l 2 /1-31-85 1 3 /1-31-85 l l l l l 12 WT % l CORE
- l VERTICAL l 297 l 2308 l 2745 BORIC l SAMPLE l l l l ACID l l RADIAL l 296 312 l 1441 1 I l l l TEST CLA3ES l l l : l l TAKEN l CUBE 1 l 1025 l 1200 i 1300 1 DURING l l l ; l l POUR I CLBE 2 l 1250 l 1650 i l 800 -
l l l l ll
, l DRtN to. / DATE CAST 2 / l-25-85 i 3 /1-25-85: 1. 4 /1-29-85 m o l I l I I <
o l CORE
- l VERTICAL l 103 i Na data
- l 853 :o
[
RESIN l SAWLE l
l l RADIAL l
l 187 l
879 l ll 715 m
l l l l I TEST CUBES l l l l P l TAKEN I CtBE 1 1 625 l 500 1 525 ?
l DLRING l l l l l POLR I CtBE 2 l 375 1 375 l 400 I I I I DRtH to. / DATE CAST l 1 / 2-13-85 1 2 /2-13-85 3 / 2-13-85 1 i I i l
- l VERTICAL 151 136 135 l CORE l l l FILTER l SAMPLE l l l l SLtBCE l l RADIAL 103 1 424 l 188 I I ,
I l TEST CLBES l l l l l TAKEN I ClBE 1 1 500 l 400 l 600 1 DtH IllG l l l l l PotH l CtA3E 2 1 425 l 450 l 450 l l l l l yl Samples taken at ATCOR's Pilot Plant by Henry Souther's Lab, Inc., an independent testing laboratory.
!N
- Vertical and radial compressive data ls the average of two compressive tests from the ,same core, m Z
, -= _ - . - - . .. ._ -__ - - - _______
.s B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued)
V. VARIATIONS IN WASTE STREAM CONCENTRATIONS Variations in concentrations of boric acid waste steams from radwaste evaporators are commonly encountered. Solidification tests conducted in ATCOR's laboratory at Avon, Connecticut on nonradioactive boric acid waste ranging from S to 12 wt *. concentrations solidified with 0*. free liquid. This data, in conjunction with the full scale test data supports the conclusion that the 12 wt % boric acid can be utilized for j boric acid concentrations up to 12 wt
- to produce a solidified product .
. which will pass all 10CFR61 test criteria. In the case of resin and filter sludge, the variations in media are infinite.
For the resin form.ulas, mix 1 and 2 were selected to demonstrate full scale solidification. These formulas correspond to 72 and 76 volume percent waste loadings.
A single filter sludge formula was tested which represented the
- conditions with the highest waste loading (waste to cement ratio). The basis for this is that if the greatest waste loading was acceptable then lesser waste loadings which have passed the laboratory scale tests would also be acceptable for full scale operation. Therefore, filter sludge (Powdex) formula mix 2 was employed in the full scale tests.
VI. In summary, the data presented in this report illustrates ATCOR's ability to meet or exceed the 10CFR61 test requirements for a wide variety of waste forms found in the nuclear industry. The table below shows the flow rates used in the fullscale tests and must be adherred to.
Vaste Type Waste Flow GPM Masonary Cement lbs/ min 12 wt'. Boric Acid 3.0 2*. -41 i 3*.
Resin 4.7 2* 41 t 3*.
Filter Sludge 6.2 2*. 41 3%
31 0F 71 ISSUE 2
. REVISION 8
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B.V.P.S. - 0.M. l',18.1 1 4 *-
/.
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/ LEACH TEST RESUt.TS
/
LEACH TEST IDENTIFICATION NUfGER 8oRsC Ocnb i ? (J #/.
LA80RATORY notERE TESTS PERFORMED C. O S 1
, f ANALYST 'A m l.1 9 e aJ Ix ** d DATE RESULTS REPORTED Part A. Description of Leach Specimen Specinea Identification leuaber Bo ra.s c A cl) t7 uJT.'A Proportion of Waste Incorporated La Misture Weight 1 L7 volume 2 (Based on' initial volumes)
Type of waste Chemical and Radioisotopic Composition, and Specific Activity of the Waste 2. c o vrr/. o/ a ho rs e seero soi u riou c~ i T o *
- s p r x.r n u.o r n. 456 2c) o f' e ,- r 3~7 wac n ck et s r--e = o u ocL net as co- Lo t;pe and composition of the Solidification Agent Koo e of s?o re v e:i e e m E u,- -
Frepa:ation et Specimen A dd +1e usatle +n a / o.2 e m / n/A &ic h o a Es t~ . Ad M AFsna ry eFMfAJr Q A/D 09 J 1. 7'rA Ass nG= r ' 9 h r*
rend oe + +a at 25a ont ' s /A s sis t edh m AP D tfA c_ . P>Ar e He e : :, ra) ou n.res) er ise sac *f" 4..'r 01 A rs . ~Peo c .se do eeeu Ae 2. A r r .
Shape and Dimensions of Specimos ,
Sphere, diameter, d (ca) =
Cylinder, diameter, d (ca) = &
length, 1 (ca) = -
Parallelepiped, leegth, 1 (ca) = ,
width, w (es) = ,&
height, h (ca) =
Other Shape Dimensions Initial Weight of Speciana V (g) = M C C3 3 w volume of Specimen *, V (caI ) = 2. f f ~
Surface Area of Specimen *, S (es2 ) = 220 Storage Conditiene srer*d iou & sa. As en Duas ric e u r d o e , ,a e C o r~ e at u s caat r o n Pe e r a n . 94 et~ c oa /s ur semr/r u/ A r '
l'P os ode d aud iM me d sa+e la _
a / Ae ed sas +A i leees i in e!* t' e/,
L 211 wi adXb A h SA.sQ E4.uld J i a Description of Leachant l Leash Interval Temp. Electrical Ceedestivity Volume, v g (3) ('C) ( ahe/ca) (al) 1 J:L /est #4sas 2. o '
A 1.c o 2 7. 2. > a st +wu 2o 1%oo 3 11 t e ms ea s,u n.o s too 4 21 vss ana 1.0 2 2 oo 5 21 Leni ska J s.* 1200 6 2. 2. I es e e-08 4/ e.O i 'l o n 1 t.1. Les e M4M *L . o '1 TO O 5 7 2. L,se
- A reev '10 MOc 9 L1_ . Lev fi n a) coo 2. % O O 10 Calculated from dimensions of specimen.
32 of 71 ISSUE 2 _
REVISION '8
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LEACH TEST RESULTS LEACH TEST IDENTIFICATION NUMBER
[or/c A e/D / 2. 40 7- */.
LABORATORY imERE TESTS PERFORMED a AJS /
l ANALisi Aou/A ~Eo <DI A N d OATE RESULTS REPORTED Part B. Description of Leach Test Procedure Speciana Preparatios* E4/We /95 Pelf T M
~
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- A e r ,re vise l .n+rered TA
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+= or er /.
Analytical Techniquest Counting Instrument Identification and Calibraties 4 A/ar.54,,a 7x4 Ala)frA) de frefe r* 4 use p enw>A r e t > sw ot -we s e rra r a ca. e - r 14A oy f) .4 0' D
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Constituent as, Analytical Procedure, Standard Deviaties of Method I
l Constituent g a . Analyti d h d ure. S W d M N M W M i
e If different from " Preparation of Speciana" in Part A.
33 of 71 ISSUE 2 REVISION .8
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34 of 71 ISSUE 2 REVISION 8-
LEACH TEST Rs .c. i doe /c W/O /2 (v T T<> ,
LEACel TEST 10EllilFICAil001 IluMsEn LARORATORY lelERE TESTS PERf0RfE0 dsa /SE I
An41.t$1 Pcso/n Pcos /nno d DATE RE5UI.75 REPORTED Part C. Emperleental Data' Cometitsent Amelysed, ,
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i
l B.V.P.S. - 0.M. 1.18. b APPENDIX B .
Manufacturer: Chem-Nuclear Systems Analytical Chemistry Division .
Oak Ridge National Laboratory Barnwell, SC Date: 9/18/84 REPORT OF IRRADIATION, DECONTAMINATION, AND DBA TESTING i The irradiation, decontamination, and design basis accident (DBA) tests a re ' conducted, respectively, in accordance with The American Society for Testing and Materials (ASTM) Standard Methods D4082-83, D4256-83, and D3911-80. The tests are also designed to meet specifications set in both !
ANSI report N101.2-1972, Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Facilities, and N5.12-1974, Protective Coatings (Paints) for the Nuclear Industry. The DBA test spray solution and the test
- conditions are listed in Tables 1 and 2. After both DBA and irradiation tests, coatings are examined for signs of chalkingt blistering, cracking,
~
peeling, delamination, and flaking, according to ASTM standards where applicable. All except the decontamination test panels are returned to the coating manufacturer.
Irradiation tests are run using a spent fuel assembly, removed from the
. High-Flux Isotope Reactor (HFIR) at ORNL, as the sogs;ce of radiation. These fuel assemblies are stored under 20 ft of demineraliked water. The fuel is 93% enriched U-235 as U 03 8 combined with aluminum. The spent fuel as-semblies are removed after each 23-megawatt-day period. Irradiation is done using gamma energy from accumulated mixed fission products. This more read-ily simulates conditions around a reactor than does a cobalt source. Also, the higher gasma activity affords shorter irradiation time to achieve accu-mulated dose. The doge rate four days after removal of a fuel assembly from the reactor is 1 x 100 rad /h.
The fuel assembly is 20 in. high. A 20-f t-long, 3-1/2-in.-diameter pipe, with one end capped, is used for air irradiation tests. The capped end is lowered into the 4-in. opening at the center of the fuel assembly.
I The open end, above water level, is covered with an 0-ring-sealed flenge to which is attached a steel cable and an air outlet hose. The air inlet is located at the bottom of the pipe. Test specimens are connected to the bottom of the cable and lowered into the radiation field. Also at the center of the fuel assembly is a stainless steel-clad cadmium tube used as a neutron absorber. This prevents contamination of the test specimens by induced radiation.
The decontamination procedure is as follows: a mixture of fission product nuclides (aged greater than 90 d and less then 3 y) is neutralized to pH 4 and imediately applied to the test specimens. The specimens are previously degreased in alcohol. After the contaminated spot is air dried, activities of four of the nuclides are measured by counting with a Ge(L1) detector and a multichannel pulse-height analyzer. Specimens are then sus-l pended in a beaker of water at 25'C and washed by stirring for 10 min. The specimens are removed, and the backs are rinsed in water, air dried, and counted as above. Ratios of the activities before, to those after the de-contamination are reported as decontamination factors (DF) for water. The j
decontamination and counting steps in 25 and 80*C acids are repeated, and the respective decontamination factors a're calculated. Total overall DF is calculated as the ratio of total activity at the beginning of the test to total activity at completion of the three washing steps. All activities are corrected for decay between counts. A computer has been programmed to do all Evaluated
- Evaluatedh MI[A ISSUE 2 -
36 of 71 g g REVISION 8
.~
B.V.P.S. - 0.'M. 1.18.1 L' Manufacturer: Chem-Nuclear Systems Analytical Chemistry Division Oak Ridge National Laboratory Barnwell, SC Date: 9/18/84 SYSTEM IDENTIFICATION Steel panel x Concrete block l
RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method No. 2 0921; ASTM Standard Method 04082-83; ORML Log Book No. A1001382 9-12-4 .
Initial dose rate: 1.0 x 107 rad /h Test conducted in: x air water Sample No. Cumulative dose (rad) Test results ATCOR Boric #1-A 1 x 108 RADS Sample intact, no defects ATCOR Boric #1-B 1 x 108 RADS Sample intact, no defects Evaluated /T'..f. Mw u..w Evaluated .2Vb'." -[- / . c./;
Approved ~
L 37 of 71 ISSUE 2 REVISION 8;
B.V.P.S. - 0.M. 1.18.1<.
Manufacturer: ' Chem-Nuclear Systems , Analytical Chemistry Divir. ion
- Oak Ridge National Laboratory Barnwell, SC Date: 9/18/84 SYSTEM IDENTIFICATION Steel panel x Concrete block 1
RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method'No. 2 0921; ASTM Standard Method D4082-83; ORNL Log Book No. A1001382 9-13-4 .
ej Initial dose rate: 1.32 x 107 rad /h '
\
Test conducted in: x air water Sample No. Cumulative dose (rad) Test results ATCOR2P-A(aced 1 x 108 RADS Sample intact, no defects ATCOR 2P-8 (&da.) 1 x 108 RADS Sample intact, no defects Evaluated & A ,ef <m % .,cc.d Evaluated .F/M', 8-dNI Approved 1
38 of 71 ISSUE 2 REVISION 8 g _ _______N--_ . - . -
,, B.V.P.S - 0.M. 1.18.1 Manufacturer: Chem-Nuclear Systems Analytical Chemistry Division Oak Ridge National Laboratory Barnwell, SC Date: 9/18/84 SYSTEM IDENTIFICATION Steel panel x Concrete block RADIATION TOLERANCE TEST ORNL Haster Analytical Manual Method No. 2 0921; AST* 6tandard Method 04082-83; ORNL Log Book No. A1001382 9-11-4 .
Initial dose rate: 1.03 x 107 rad /h .
Test conducted in: x air water Sample No. Cumulative dose (rad) Test results ATCORPowde$1-A 1 x 108 RADS. Sample intact, no defects ATCOR Powder 1-8 1 x 108 RADS Sample intact, no defects l
~~
9 )
- Evaluated /. /
- a -rev.
. , j
. U.N ..dd-4..
Evaluated Approved I ;y I l 39 of 71 ISSUE 2 REVISION 8,
- l l
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B.V.P.S. - 0.M. 1.18'.'l r
Manufacturer: Chem-Nuclear Systems Analytical Chemistry Division '
Oak Ridge National Laboratory Barnwell, SC Date: 9/12/84 SYSTEM IDENTIFICATION Steel panel x Concrete block l
l l
l RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method No. 2 0901; ASTp Standard tiethod D4082-83; ORNL Log Book No. A1001382 9-12 4 .
Initial dose rate: 1.0 x 107 rad /h .
Test conducted in: x air water l
l l
Sample No. Cumulative dose (rad) Test results l ATCORPowde$#2-A 1 x 108 RADS Sample intact, no defects ,
ATCOR Powde) #2-B 1 x 108 RADS Sample intact, no defects
- in l Evaluated M ' /. de u.~- l Evaluated E [ / s- [I ,d '
Approved [M u_w '
I 40 of 71 ISSUE 2 REVISION 8 n ~- - , .-- _.-- -,. ,. y - - , , -
-w w--.,,,.
B.U.P.S. - 0.M. 1.18.1 Manufacturer: Chem-Nuclear Systems Analytical Chemistry Division
- Oak Ridge National Laboratory Barnwell, SC Date: 9/18/84 SYSTEM IDENTIFICATION Steel panel x Concrete block l
l j
RADIATION TOLERANCE TEST ORNL Master D4082-83; ORNLAnalytical Log BookManual Method No. A1001382 No.4 2 0921; ASTpl Standard Method 9-17 . .
Initial dose rate: 1.20 x 107 rad /h Test conducted in: x air water Sample No. Cuculative dose (rad) Test results ATCOR RESIN 1-A 1 x 108 RADS Sample intact, no defects ATCOR RESIN 1-B 1 x 108 RADS Sample intact, no defects Evaluated 4,~.9 e ; -
- 4.-sr e Evaluated '
/'/5 8h Aa/L Approved M
\
41 of 71 ISSUE 2 REVISION 8
B.V.P.S. - 0.M. 1.18.4
. Manufacturer: Chem-Nuclear Systems Analytical Chemistry Division Dak Ridge National Latpratory Barnwell , SC - Date: 9/17/84 l
SYSTEM IDENTIFICATION Steel panel x Concrete block l
i RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method No. 2 0921; ASTM Standard Method D4082-83; ORNL Log Book No. A1001382 9-17 4 . "! j Initial dose rate: 0.9 x 107 rad /h Test conducted in: 'x air water Sample No. Cumulative dose (rad) Test results ATCOR RESIN 2-A 1 x 108 RADS Sanple intact, no defects ATCOR RESIN 2-B 1 x 108 RADS Sample intact, no defects n
Evaluated M ,' [ 1la -a. . .-
Eva1uated }~X'f0.. #!-!.eb' Approved 2 m L
42 of 71 ISSUE 2 REVISION 8
. B.V.P.S. - 0.M. 1.18.1 i
Manufacturer: Chem-Nuclear Systems Ariflytical Chemistry Division Oak Ridge National Laboratory Barnwell, SC Date: 9/18/84 SYSTEM IDENTIFICATION Stee,1 panel x Concrete block RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method No. 2 0921; ASM Standard Method 04082-83; ORNL Log Book No. A1001382 9-17-4 .
Initial dose rate: 0.9 x 107 rad /h Test conducted in: x air water Sample No. Cumulative dose (rad) ' Test results ,
l ATCOR RESIN 3-A 1 x 108 RA05 Sample intact, no defects ;
ATCOR RESIN 3-8 1 x 108 RADS Sample intact, no defects
- c, Q Evaluated X.I.. MZ - a'- -
Evaluated .M I" d -ed Sn A Approved e -
l 43 of 71 ISSUE 2 REVISION 8.
B.V.P.S. - 0.M. 1.1&.1 L !. t..._
APPENDIX C UNIVERSITY Olr SOUTH CAROLINA l'/\R R 3 ;- ,3 Co tu u s e A, s. c. a s s o s DETARTMENT OF BIOLOGY (8031 777-4141 -
27 March 1985 Mr. David Thorpe Chem-Nuclear Systems 220 Stoneridge Drive '
Columbia, SC 29210 l
Dear Mr. Thorpe:
The following is a report on biodegradation studies of ATCOR cement samples submitted to me. As you will note in the report, there was no indication of degradation by either fungi or bacteria. However, water damage was apparent in some formulae.
Sincerely,
/
Gf G.T. Cowley Assistant Professor and Assistant Chairman GTC:tdp Enclosure 44 of 71 ISSUE 2 REVISION 8 The Unsweremy of south Carshne: USC Ashen: Usc sameneschse. Amensente: Usc soeufort Usc Ceevnese: Ceesses _
Carehne Castage. Comsey; Usc Laneesser: Usc scenereurs usC surneer: Usc Union: ens the Messeery Cow
B . V. P.S . - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued)
- . f Summary of Microbial Degradation Tests l on ATCOR Cement Samples {
i Seven sets of ten cement samples were tested for microbial degradation i
according to codified ASTM standards. The modification was the replacement of an agar medium by a liquid medium. This modification was employed to assure adequate moisture for fungal and bacterial growth over the entire cement surface. Temperature and humidity levels were monitored and maintained at ASTM requirements throughout the 21 day incubation period.
The fungi and bacteria used were those species and strains specified in the
- ASTM standards. Compressive strength tests were performed in the USC Civil Engineering Department.
The resin containing samples ATl and AT2 were redone on an agar medium since they swelled and crumbled in liquid.
The cement samples were ATCOR samples labeled Powdex 1, Powdex 2, Charcoal. Boric vil, Boric #2-P AT1, AT2, and AT3. The last three were resin containing samples.
In no case was there any macroscopic or microscopic sign of fungal or bacterial growth during, or at the end of the 21 day incubation period.
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After 3 Weeks Incubation Untreated Uninolculated Fungi Uninoculated Bacteria Sample Control 30*C 30*C 37'C 37*C .
Powdex 1 1234 1154 1141 955 982 1313 1273 1273 1326 4 Powdex 2 1353
- 2785 2811 2785 2765 !"
Charcoal 1343 u Boric #1 2627 2228 2387 1910 1910 o x
Boric #2-P 1114 875 955 796 822
~
ATI 96 96 92 111 101 AT2 98 101 ,
96 96 98 AT3 112 126 173 141 173
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]* PROCESS CONTROL PROGRAM (continued) .
l Breakage was consistently be shear fracture, although some surface crumbling was apparent in incubated samples AT1 and AT2. According to the i t-test there were no significant differences betweren unionculated controls and inoculated samples at either 30*C (fungi) or 37*C (bacteria). Thus, no significant microbial degradation occurred.
However, there was some apparent water damage to both unioculated and inoculated samples in some sets, as indicated by significant differences (5*. level) betweren as received controls and incubated samples.
Apparent Water Damage Sample Treatment Powdex 1 Incubation at 37*C Boric #1 Incubation at 30*C and 37*C Boric #2-P Incubation at 30*C and 37*
f AT1 and AT2 Crumbled in liquid medium -
i l Although there was some surface crumbling in AT1 and AT2 samples on an agar medium, indicative of moisture damage, there was no reduction in strength. .
Charcoal and AT3 samp'les strength increased significantly during incubation at,both temperatures.
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47 0F 71 ISSUE 2 REVISION 8 i
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B.V.P.S. - 0.M. 1.k8.1
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APPENDIX D ATCOR FULL SCALE SOLIDIFICATION TEST PROGRAM FOR QUALIFICATION OF MASO M Y CEMENT WASTE FORMS TO 10 CFR 61 l
Prepared By: ,, Date: f-/J'8f PrQ6ect Enginear Approved by: /
Engineering Manager Date: 7/[M Approved by: M / %te: 5-/4-65 w
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.- B.V.P.S. - 0 . !! . 1.18.1 PROCESS CONTROL PROGRAM (continued)
' TABLE OF CONTENTS SECTION TITLE PAGE
1.0 INTRODUCTION
50 of 71 2.0 CEMENT FEEDER CALIBRATION 51 of 71 3.0 PREPARATION OF BORIC ACID WASTE 52 of 71 4.0 PREPARATION AND CONDITIONING OF BEAD RESIN WASTE 53 of 71 5.0 PREPARATION AND CONDITIONING OF FILTER SLUDGE WASTE 54 of 71 6.0 VASTE METERING PUMP CALIBRATION , 55 of 71 7.0 TEST PROCEDURE 56 of 71
't LIST OF TABLES -
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TABLE I. CHEMICALS USED FOR FULL SCALE TESTS 57 of 71 II. CALIBRATION OF CEMENT FEEDER 58 of 71
- III. CALIBRATION OF WASTE METERING PUMP FOR BORIC ACID WASTE 59 of 71.
IV. CALIBRATION OF WASTE METERING PUMP FOR RESIN BEAD WASTE 60 of 71 V. CALIBRATION OF WASTE METERING PUMP FOR FILTER SLUDGE WASTE 61 of 71 VI. FULL SCALE TEST DATA 62 of 71 LIST OF FIGURES J
l FIGURE I
]' I. FULL SCALE SYSTEM P & ID 63 of 71 II. CEMENT FEEDER CALIBRATION 64 of 71 III. WASTE TANK LEVEL VS VOLUME 65 of 71 IV. WASTE FEED PUMP RPM VS GPM FOR BORIC ACID 66 of 71 V. WASTE FEED PUMP RPM VS GPM FOR RESIN BEADS 67'of 71 VI. WASTE FEED PUMP RPM VS GPM FOR FILTER SLUDGE 68 of 71 1
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B.V.P.S. - 0.M. 1.18.1 - .
I PROCESS CONTROL PROGRAM (continued)
1.0 INTRODUCTION
This test program wf11 examine the full scale solidification of radioactive waste in masonry cement. The waste types considered include 12*. boric acid solution, bead resin, and filter sludges. the formulations used are based on proportions which have successfully
! passed the laboratory scale tests required for 10CFR61 compliance. The test system is shown on Figure 1. The system consists of a hot water i supply tank, a 55 gallon chemical mixing tank with transfer pump, a
! waste tank with metering pump, a , cement bin and feeder, and an intensive mixer. The chemicals and p*oportions used for each waste
- type are listed in Table 1.
I The following materials should also be available:
- 50 gallon drums and lids j - 1000 lb capacity scale
- large plastic bags for dry chemical calibration
- - thermometer 1 - stop watch l
- calculator i
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1 50 0F 71 ISSUE 2
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B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued) 2.0 CEMENT FEEDER CALIBRATION 4 2.1 Before filling the feeder with cement, check the dial settings required to chieve the RPM of values given in Table II and record
! results. Fill the feeder bin with cement.
2.2 Disconnect the outlet from the cement feeder and connect a large plastic bag to the outlet.
2.3 Set the feeder for a low speed, approximately 25 RPM, start the bin activator and cement feeder. Record the time to fill bag.
l 2.4 When - the - bag is full, stop the bin activator and feeder. Record the elapsed time and weigh the bag.
2.5 Cement feed = s ample weight-bag weight / test time. Record the cement feed rate in Table II.
2.6 Reload the cement in the bin.
2.7 Repeat the test at medium and high speeds, approximately 60 and 120 RPM. .
1 2.8 Plot a curve of RPM vs. feed rate (Figure II).
J 2.9 The required cement feed rate is 40 lb/ min. _
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! 2.10 Reconnect the cement feeder outlet.
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51 0F 71 ISSUE 2 REVISION 8 l e
B.V.P.S. - 0.t!. 1.18.1 .
. PROCESS -CONTROL PROGRA>! (continued) 3.0 PREPARATION OF BORIC ACID WASTE 3.1 Prepare a batch of 12*. wt boric acid solution as follows:
Add 2403 lb (238 gal) hot water to the chemical addition tank and mix with 327 lb of boric acid in six increments as follows:
?! ark the 48 gallon level on the chemical mixing tank by adding water until the drum weighs 400 1/2 lb and mix in 54.5 lb of boric acid.
. Ensure temperature is 1o0* ' t 5 F. Blix each of the six batches thoroughly and pump into the waste tank. !!easure and record the pH.
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52 0F 71 ISSUE 2 REVISION 8 i i
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B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued) 4.0 PREPARATION AND CONDITIONING OF BEAD RESIN WASTE 4.1 Prepare a batch of bead resin waste as follows:
Fill the chemical addition tank approximately 1/2 full with resin j beads. Fill the remainder of the tank with water. Mix the slurry thoroughly and transfer to the waste tank. Prepare approximately ten batches in this manner.
j 4.2 Allow the slurry to settle in the waste tank. Dewater the settled sinrry until the solids are just barely covered with liquid.
4.3 Note the level of resin beads and determine the volume from the waste tank volume vs level curve (Figure III). This is the dewatered volume.
The conditioned resin level can be found per the method below:
The total height of the waste feed tank is 69.25 inches. Calculate the volume of water to be added.
- Measure distance from top of tank to dewate' red resin beads.
69.25 inches - distance to dewatered resin = dewatered resin level.
- From curve (Fig. III) read volume of dewatered resin.
- Dewatered resin volume x conditioning factor * - conditioned resin volume.
From. Curve (Fig.III) determine the required tank resin volume 4 level for the conditioned resin volume.
Add water to that level.
I 4.4 Start the agitator and mix the slurry thoroughly.
4 I
- Conditioning factors used in this test were varied from 1.4 to 1.6.
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. REVISION 8 i
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B.V.P.S. - 0.H. 1.18.1 '.',
s PROCESS CONTROL PROGRAM (continued) 5.0 PREPARATION AND CONDITIONING OF FILTER SLUDGE WASTE i 5.1 Blend the following formulation to simulate a typical filter sludge mixture:
i
- Exodex 350 lb i
Ecosorb 270 lb Anion Powdex 250 lb i
e Cation Powdex 500 lb
- Solka Flock 30 lb Anhydrous Na
- SO. 30 lb
] 5.2 Prepare a batch of filter sludge waste as follows:
f Fill the chemical addition tank approximately 1/2 full with the i material blended in 5.1 above. Fill the remainder of the tank with j water. Mix the slurry thoroughly and transfer to the waste tank.
, Prepare at least six batches in this manner.
i 5.3 Allow the slurry to settle in the waste tank. Dewater the settled j slurry until the solids are just barely covered with liquid.
5.4 Start the agitator and mix the slurry thoroughly.
1 1
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54 0F 71 ISSUE 2
. REVISION 8
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B.V.P.S. - 0.M. 1.18.1 PROCESS CONTROL PROGRAM (continued) o.G h*aSTE METERING PUMP CALIBRATION (ROBBINS & MEYERS MODEL IFFJ6)
I
! 6.1 With the waste tank outlet valva closed, fill the waste tank with waste solution prepared in Section 3.0, 4.0 or 5.0.
T 6.2 Remove the pump discharge connection from the intensive mixer and direct it to a 55 gallon drum (obtain a tare weight for the drum).
6.3 Set the pump to 50 RPM. Start the pump and record time to fill the drum approximately 1/2 way.
,4 7 , , (full drum wt - drum tare wt)
Time To Fill 6.5 Repeat the test for medium and high speeds (150 and 250 RPM) and record
., the data (Table III, IV or V). Graph the points to develop a curve of RPM vs. flow rate (Figures IV, V VI).
6.6 The waste flow rate should be as follows:
6.7.1 _3_ gal / min for boric acid waste (Figure IV) 6.7.2 4.7 gal / min for bead resing (Figure V) ,
6.7.3 6.2' gal / min for filter sludges frigure VI) 6.7 Reconnect the waste pump discharge to the incensive mixer.
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i 55 0F 71 ISSUE 2 i REVISION 8
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B.V.P.S. - 0.M. 1.18.1 . .
PROCESS CONTROL PROGRAM (continued) 7.0 TEST PROCEDL'RE
.7.1 With a drum in place for filling, start the intensive mixer.
7.2 Simultaneously start the waste metering pump and feeders (ensure valve line-up is correct from the waste tank and that the waste metering pump rpm is set as determined in section 6.0 above).
7.3 While one drum is filling, another drum should be lined up to replace the one being filled. Record the test data in Table VI. Fill ,
approximately 3 drums with each waste type. Label each drum with waste i type and drum number of that run.
7.4 Immediately after each run, stop the waste pump and feeders. With the mixer feeder still running, flush with fresh water into an empty drum for approximately 1 minute.
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.- B.V.P.S. - 0.t!. 1.18.1 PROCESS CONTROL PROGRA?! (continued)
TABLE 1 CHE}!ICALS USED FOR FULL SCALE TESTS A. Boric Acid (H B0 ) 12 kT *.
3 Water @ 165* F 2403 lbs (288 gal)
Boric Acid (granular) 327 lbs Binder
!!asonry Cement
- B. Bead Resin Waste Resin Beads (mixed bod) 50*. Anion, 50*. Cation Binder
?!asonry Cement
- C. Filter Sludge Waste Ecodex 350 lbs Ecosorb 270 lbs Anion Powdex 250 lbs Cation Powdex 500 lbs Solka floc 30 lbs Anhydrous Sodium Sulfate (Na:SO.) 30 lbs to depete resin Binder
!!asonry Cement *
- Portland Cement + Lime, 1:1 Technician Quality Assurance l
57 0F 71
- ISSLT 2 REVISION 8 e
. B.V.P.S. - 0.tl. 1.18.1
- PROCESS CONTROL PROGRAtt (continued)
! TABLE II l CALIBRATION OF CE}!ENT FEEDER Cement
}- Feed Rate
- Ave. Cement Approx. Time Weight Weight / Time Feed Rate Trial (A RE Dial Setting (?!in) (1bs) lbs/ min Ibs/ min i
) 1 29 2 1/2 1 20.25 20.25 2 28 2 1/2 1 19.5 19.5 19.7 4
3 28 2 1/2 1 19.25 19.25 4
1- 54 4 1/2 1 32.0 32.0 l 2 54 4 1/2 1 33.75 33.75 32.7 3 54 4 1/2 1 32.25 32.25 j 1 112 6 1/2 1 64.0 64.0 l 2 112 6 1/2 1 67.0 67.0 66 4
l 3 112 6 1/2 1 67.0 67.0 Test Point 65 5+ 5 204.75 40.95 40.95
- See Plot Figure II i
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58 0F 71 ISSUE 2 1 REVISION 8.
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B . V . P . S . - 0. ?! . 1.18.1 PROCESS CONTROL PROGRABI (continued)
TABLE III CALIBRATION OF WASTE .':ETERING PU!P Boric Acid Waste pH: 3 Waste Weight: 8.714 lbs/ gal Waste Flow Rate Trial se R_Pj'1 Dial Setting Time (min) Weight (1b) Vf.ight/ Time Gal /ffin 1 40 1 1 18.75 18.75 2.15 2 40 1 1 19 19 2.18 3 40 1 1 19.25 18.75 2.15 1 62 2 1 29.75 29.75 3.41 2 62 2 1 29.5 29.5 3.39
- 3. 62 2 1 30 30 3.44 1 95 3 1 43 43 4.94 2 95 3 1 42.25 42.25 4.85 3 95 3 .
1 44 44 5.05 1 160 4 1 59 59 6.77 2 330 6 1/2 1 144.5 144.5 16.6 Technician Quality Assurance I
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e, D.V.P.S. - 0. t! . 1.18.1 . .
PROCESS CONTROL PROGRABI (continued)
TABLE IV CALIBRATION OF WASTE ?!ETERING PU.'iP Bead Resin Waste Weight: 9.039 lbs/ gal Flow Rate Trial # R_Pr!
P Dial Setting Time (min) Weight (1b) Weight / Time Gal /tfin 1 66 2 1 29.y 29.25 3.24 2 6o 2 1 29.75 29.75 3.29 3 66 2 2 57.5 28.75 3.18 1 97 3 1 42.75 42.75 4.73 2 97 3 2 86.75 43.4 4.80 3 98 3 1 43.25 43.25 4.78 1 134 4 1 60.2 60.2 6.66 2 135 4 1 59.5 59.5 6.58 3 259 6 1 108 108 11.95 eig t- s al Gal /?jin = x Time-!!in 9.039 lbs Technician Quality Assurance 60 0F 71 ISSUE 2 REVISION 8
B.V.P.S. - 0 . .'! . 1.18.1 PROCESS CONTROL PROGRA?! (continued)
TABLE V CALIBRATION OF WASTE ?!ETERING PC'IP Filter Sludges Waste Weight: 8.65 lbs/ gal Flow Rate Trial # RPj! Dial Setting Time (min) Weight (1b) Weight / Time Gal /flin 1 o0 2 1 27.75 27.75 3.2 2 o0 2 1 28.5 28.5 3.3 3 60 2 1 28.5 28.5 3.3 1 118 3 3/4 1 50.75 50.75 5.86 2 119 3 3/4 1 54.0 54.0 6.26 3 121 3 3/4 1 53.25 53.25 6.15 1 180 5 1 81.0 81.0 9.38 2 ISO 5 1 79.25 79.25 9.17 3 180 5 1 79.75 79.75 9.22 Technician Quality Assurance 61 0F 71 ISSUE 2 REVISION 8 f
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APPENDIX E l PQA 8504-7 l A CHEM NUCLEAR COMPANY ,_
135 Der #ng Dnve e Avon. CT 08001 -
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- April 3,1985
. .e.
l LocA w : .'
To: C. teolf. 0.A. Manager
- 5. Cannata, Q.C. Engineer LocA m : l FnoM:
SUSJECT: Survey of Henry Souther Testing Labs in Bloomfield, CT i
The results of the On 4/1/85 I performed a survey of Souther Testing Labs.
survey are as follows:
o The lab was recertified on November 6.1984 by the U.S. Department of Commerce Sureau of Standards as required by the State of Connecticut.
o The equipment used for testing our samples has been certified.
Calibration Date: 9/25/84 Re-Calibration Due: 9/25/85 Equipment Serial No. 50235-6 Calibrated by Tinius Olsen Calibration Service o All testing is perfonned in accordance with ASTM and American Concrete Institute standards.
All reference o Shop testing technicians appear to be very proficient.
codes and standards are included on the test reports.
- . :.+b. ;: -
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~ 69 of 71 ISSUE 2 REVISION 8
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b B.V.P.S. - 0.M. 1.18.1 . i PROCESS CONTROL PROGhl31 (continued)
APPENDIN F REFERENCES
- 1. CNSI Procedure AQ-AD-001
- 2. CNSI Procedure, SD-TP-001, " Measurement of the Leachability of Solidified Low Level Radioactive Waste".
- 3. Title 10 CFR Part ol.
- 4. 10 CFR Part ol Waste Form Branch Technical Position (with supplementary guidance).
- 5. NRC Generic Letter 84-12 of 30 April, 1984.
- 6. CNSI-WR-C-01-NP, " Waste Form Certification--Cement".
- 7. NUREG-0800, Standard Review Plan.
- 8. ANS 55.1, "American National Standard for Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants," American Nuclear Society, 1979.
- 9. ASTM C39, " Compressive Strength of Cylindrical Concrete Specimens",
American Society for Testing and Materials, 1979.
- 10. ASTM D1074, "Ccmpression Strength of Bituminous Mixtures", American
~
Society for Testing and Materials" 1980.
- 11. ASTM G21, " Determining Resistance of Synthetic Polymeric Materials to Fungi", American Society for Testing and Materials, 1970. ,
- 12. ASTM G22, " Determining Resistance of Plastics to Bacteria", American )
Society for Testing and Materials, 1976. j
- 13. R. Bartha, D. Pramer, " Features of the Flask and Method for Measruing the Persistence and Biological Effects of Pesticides in Soils, Soil Science 100 (1), pp. 68-70, 1965.
- 14. ANS 16.1, " Measurement of the Leachability of Solidified Low-Level Radioactive Wastes", American Nuclear Society Draft Standard, April 1981.
- 15. AST?! B553, " Thermal Cycling of Electroplated Plastics, "American Society for Testing and Materials, 1979.
- 16. CN-AD-018, Inspection Program.
70 0F 71 ISSUE 2 REVISION 8
,/ S.V.P.S. - 0.M. 1.15.1 a .
PROCESS CONTROL PROGRAM (continued) 2.20 QA-AD-007. Supplier Audit Procedure.
I 71 0F 71 ISSUE 2 j REVISION 8 !
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APPENDIX B PROCESS AND CONTROL PROGRAM REQUIREMENT MATRIX 1 of 4 ISSUE 2 REVISION 8 1
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B.V.P.S. - 0.M. 1.18.1 ,
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PROCESS AND CONTROL PROGRAM (continued) $
APPENDIX B - P.C.P. Requirement Matrix
. I Requirement Reference Addressed By:
Doctment(s ) OP Marmaal !
Radeon Marmal i
- 1) Wasta mast be -10CFR61.55 RQt Chapter 3 I classified aa -South Carolina DHEC RP 3.31 and RP 3.35 Class A,8, or C. License 097 Condition 31
-10CFR20.311 I i
- 1) Weste classified -10CPR61.55 (2) OM 1.18.1 and Rot Qimpter 3, as Class B or C -10CFR61.54 Appendia A RP 3.31, RP 3.35 must meet more -Final Weste Classification CM 1.18.6 See I riSorous and Wasta Fors TecJmical requirements on Position Papers - Branch wasta form. Technical Position (BTP)
South Carolirs."n5C 097
- 3) Specific wasta Branch Tachniemi rot Qupter 3 j characteristics Position (RTP) RF .31 I and waste fors 10CFR61.56 performance Scuth Carolina IREC 097 requirements -
stability by waste form.
V 3A) Solidified waste OF Manual 1.18.1 + App A specimens should (shows 1718 psi (ASDt C39)l have compressive CP leamm1 1.28.6 J strengths of at l
least 50 psi.
l
- 35) Specimens should I 0F Marmaal 1.18.1 + App A ha , compressive (shows 2500 psi after strength of 50 psi exposure to los Rads (Y) after exposure to 0F Manual 1.18.6 J 10s Rads (Y).
V 3C) Following Bio- BTP OF Manual 1.18.1 + App A degradation 10CFR61.54 (shows 2387 psi after fungal testing, specimens South Carolina DHEC 097 test 1910 after bacterial should have test.)
compressive strength greatar OF Manual 1.18.4 J than 50 psi.
3D) f-hability fndag, OF Manual 1.18.1 + App A (LIX) calcularad (shows: Ituclide LIX per AltS16.1 should Co 10.1 be greater than 6. Cs 137 6.2 se ss ,,5) 0F Masmaal 1.18.4 J V
2 of 4 ISSUE 2 REVISION 8
\
B.V.P.S. - 0.M. 1.18.1 7
PROCESS CONTROL PROGRAM (continued) 9.. ', ' ' '
- i APPENDIX B - P.C.P. Requirement Matrix Itaquirement Reference Addressed By:
Document (s) OP Manual Radeon Manual l 3E) Following 90 day CP Manual 1.18.1 + App A (nin) immarsion (shows 3050 psi) i test, specimen should demon- 0F Manual 1.18.4 J l
strata compres- ;
sive strength of 50 ps1.
t 3F) After 30 thermal 0F Marmaal 1.18.1 + App A cycles (608 C (shows compressive sta ngth ,
to -40 8 C) to be 2005 psi aftar cycles) l I
compressive strength should OP Manual 1.18.4 J be greater than 50 psi. i 3G) Wata specimens STP OF Manual 1.18.1 + App A should have less 10CFR61.56 (shows no free liquids) t than 0.5 percent South Carolina DHIC 097 by voltme as f 0F Marnaal 1.18.6 J l freestanding liquid as measured by 2 ANS$5.1 l 3H) Generic test data CP Marmasi 1.18.1 + App A may be used for Osapter 55A Sec h qualifying the OST 1.18.1 process control program. Fre- OST 1.18.2 quant requalifi-cation to demonstrata stability is expected to be unnecessary.
However, PCPS should include provisions to periodically demonstrate that the solidifica-tion system is functiwting properly and wasta products
(
contimas to meet 10CFR61 stability requiremmets.
V '
3 of 4 ISSUE 2 REVISION 8 -
W
B.V.P.S. - 0.M. 1.18.1 9, PROCESS CONTROL PROGRAM (Continued) )$ .
APPENDIX B - P.C.P. Requirement Matrix tequirement Reference Addressed By:
Docuent(s) 0F Manual Radeon Manual
- 4) Wasta form BTF
+
requirements - 10CFR61.56 stability by South Carolina IEEEC 097 ,
container or structure.
4A) HICS are OF Mamsal 1.18.1 certified as 0F Marmaal 1.18.4Y meeting specific 0F Mesmat 1.18.4 AF structural requirements by issuance of certifications.
- 48) IIIC specific or Mamaal 1.18.1 handling and 0F Marnaal 1.18.4Y de ntaring 0F Masmaal 1.18.4 AF processes to meet _#
free water requirements, W 118ht exposun requirements and l other content i
requirements are contained in Chee-Nuclear procedures incorporated actually or by i reference in CF Marmaal.
- 5) Radioactive 10CFR20.311 ROI Qimpter 3 material mast be 10CFR71 as applicable RP3.1,3.2,3.9, properly labeled, 10CFR61 3.11,3.12,3.16, marked, packaged, 10CFR61.55,61.56,61.51 3.17,3.22,3.23, and prepared for 49CFR170-174,178 3.24,3.27.3.28, transport. South Carolina DEBC 097 3.29, 3.30, 3.31, 3.33,3.35
- 6) Radioactive 10GR20.311 Rot Qimpter 3 estarial ship- 10CFR71.5 RP3.6,3.32,3.35 ments aust be 49CFR Subpart C unless accompanied by escepted properly aw e e d Scieth Carolina IIIEC 097 u .s. y
- 7) Other issues 10CFR20 0F Meaual 1.18.1 + App A Radeon Mesmaal relating tr *3ne 10CFR71 Qimpter 3 Sec 3 L _i of 10CFR61 0F W1 1.18.4 all sections All procedures radioactive 49CFR170-178 material, South Carolina IIIEC 097 Qasyter SSA, Sec 4 including radio-active mates not Applicable OSTs specifically mentioned.
ISSUE 2 4 of 4 REVISION 8 _-
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