ML17332A252
| ML17332A252 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/03/1994 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17332A248 | List: |
| References | |
| 12-PMP-3150-PCP, NUDOCS 9408190202 | |
| Download: ML17332A252 (22) | |
Text
Attachment 5 to AEP:NRC:1093 Proposed Changes to the Process Control Program in Response to Generic Letter 89-01 9408190202 940803 PDR ADOCK 05000315 p PDR
12 PMP 3 150 PCP. 100 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER EFFECTIVE CHANGE SHEETS Page 1 of 10 Revision 3 Page 2 of 10 Revision 3
.Page 3 of 10 Revision 3 Page 4 of 10 Revision 3 Page 5 of 10 Revision 3 Page 6 of 10 Revision 3 Page 7 of 10 Revision 3 Page 8 of 10 Revision 3 Page 9 of 10 Revision 3 Page 10 of 10 Revision 3 APPENDIX A Page 1 of 5 Revision 3 Page 2 of 5 Revision 3 Page 3 of 5 Revision 3 Page 4 of 5 Revision 3 Page 5 of 5 Revision 3 APPENDIX B Page 1 of 2 Revision 3 Page 2 of 2 Revision 3 APPENDIX C Page 1 of 1 Revision 3 Page 1 of 1 Revision 3
12 PMP 3150 PCP. 100 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT
1.0 TITLE
RADIOACTIVE WASTE PROCESS CONTROL. PROGRAM
2.0 OBJECTIVE
2.1 To give instructions for the processing of radioactive waste such that all plant generated radioactive wastes will be in compliance with applicable codes, standards, and processing/burial site criteria prior to shipment.
2.2 This procedure impacts and directs the activities of the Radiation Protection, Operations and Chemistry Departments only, therefore other interfacing Departments rev1ews are not required for this or further revisions.
3.0 REFERENCES
3.1 Code of Federal Regulations, Title 10.
3.2 Code of Federal Regulations, Title 49.
3.3 Code of Federal Regulations, Title 40.
3.4 State of South Carolina, Radioactive Materials License 897.
3.5 State of Washington, Radioactive Materials License gWN-I019-02.
3.6 USNRC Technical Position on Waste Form, Revision 0.
3.7 Vendor Radwaste Handling Service Manuals.
3.8 PMI-3150, Packaging and Shipment of Radioactive .,
Materials and Waste.
3.9 FSAR, Chapter 11, Waste Disposal and Radiation Protection Systems.
3.10 D. C. Cook Plant Technical Specifications.
3.11 I.E. Bulletin No. 79-19, Low Level Radioactive Waste Disposal.
3.12 USNRC Generic Letter 89-01.
4.0 DETAILED PROCEDURE 4.1 Res onsibilities 4.1.1 Appendix A of this procedure, identifies departmental responsibilities as they pertain to radwaste processing.
Page 1 of 10 Revision 3
12 PMP 3150 PCP. 100 4.2 Limitations Precautions 4.2.1 Cleaning solutions, oil and all other petroleum products shall not be allowed to enter the radioactive waste processing system (i.e., floor drains,>open systems, . . . ).
4.2.2 Consideration has been given to our waste management program to ensure that actions have been implemented to segregate hazardous wastes as defined by the EPA Regulations, from low level radioactive wastes. Appendix B of this procedure, outlines this mixed waste program.
4.3 Li uid Processin 4 ~ 3 ~ 1 Plant liquid waste processing equipment is designed to process liquid wastes in the chemical and physical forms which exist in the plant's operating systems.
4.3.2 Administrative procedures shall dictate the plant's operating systems'hemical parameters and sampling requirements to insure that the systems are operated within these parameters.
4.3.3 Liquids which could be detrimental to the waste processing system shall be prevented from entering the liquid waste system.
4.3.4 Liquid wastes will be collected in waste holding tanks in the 'Auxilia'ry Building.
4.3.5 The liquid wastes will then be processed via one of two methods; 4.3.5.1 Liquid Radwaste Demineralizer System,. or 4.3.5.2 Waste Evaporator System.
4.3.6 Procedures shall be written and maintained for the operation of these systems.
4.3.6.1 Appendix C, gives operating parameters that will be complied with during operation of the Waste Evaporator System.
Page 2 of 10 Revision 3
12 PMP 3 150 PCP. 100 4.3.7 Both liquid processing systems are designed to reduce the liquid waste's radioactivity to levels acceptable for release to the environment as defined by 10 CFR 20, Appendix B and D.C. Cook Plant Technical Specifications.
4 '.8 Spent radioactive resins produced from operation of the Liquid Radwaste demineralizer System, shall be processed in accordance with Section 4.5 of this procedure.
4.3.9 Waste evaporator bottoms produced from operation of the Waste Evaporator System, shall be processed via one of two methods; 4.3.9.1 Waste evaporator bottoms may be recycled back into the Liquid Waste Processing System, then processed again by the Liquid Radwaste Demineralizer System; or 4.3.9.2 The waste evaporator bottoms may be solidified in accordance with Section 4.4 of this procedure.
4.4 Solidifications 4.4. 1 The SOLIDIFICATION process is the process of converting radioactive liquids, resins, and other miscellaneous wastes (i.e. boric acid, sludge, . . . ) into an acceptable form for shipping and burial as required by'-10 CFR Parts 20, 61, and 71.
F 4.2 The waste to be solidified will be transferred to a container suitable for shipping the waste in compliance with applicable codes and standards.
4.4.3 Prior to starting any solidification process, the waste shall be sampled. The sample results should be within the limits listed in Appendix C, Table 2 to insure proper solidification.
4 ' ' Using these sample results, a solidification method approved by the applicable regulatory authorities shall be chosen.
4.4.5 A test solidification specimen shall be prepar'ed for each container prior to attempting solidification of the liner.
Page 3 of 10 Revision 3
12 PMP 3150 PCP. 100 4.4.6 For high activity wastes, it. is acceptable to non-radioactive samples. These. samples...
should be as close to the, actual waste in their physical and chemical properties as possible.
4.4.7 The test solidification will be considered acceptable if; 4.4.7.1 There is no free standing water, and 4.4.7.2 visual inspection, the waste that it would hold its Upon appears shape if removed vessel, and from the test 4.4.7.3 It resists penetration.
4.4.8 An acceptable solidification will ensure <
0.54 free standing water, and "stability" as defined by 10 CFR 61 when required.
4.4.9 If the test solidification fails any one of the criteria listed in Step 4.4.7, xt is unacceptable.
4.4.10 If the test solidification specimen, is unacceptable, prepare another specimen taking into consideration; 4.4.10.1 Adjusting the pH of the waste.
4.4.10.2 Adjusting the waste to solidification agent ratio.
4.4.11 The waste container will be solidified using the solidification parametersas determined in the acceptable test solidification specimen.
4.4.12 Containers of solidified wastes shall be held a minimum of 24 hours prior to shipment.
- 4. 4. 13 The Radwaste Solidification System shall 92be demonstrated operable at least once per days by one of the following methods:
4.4.13.1 Operating the system, or 4.4.13.2 Verifying the existence of a valid contract for solidification to be performed by a contractor.
4.4.14 If after repeated attempts a waste container cannot be solidified or if the radwaste soldification system cannot, be demonstrated to be operable; 4.4.14.1 Declare the system inoperable Page 4 of 10 Revision 3
12 PNP 3150 PCP. 100 4.4.14.2 Suspend all shipments of defectively solidified waste, and 4 '.14.3 Take action to return the system to operability.
- 4. 4. 15 With the solid radwaste system inoperable for more than 31 days, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report which includes the following information:
4.4.15.1 Identification of the inoperable equipment or subsystems and the reason for inoperability:
4.4.15.2 Action(s) taken to restore the inoperable equipment to operable status, 4.4.15.3 A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and 4.4.15.4 Summary description of action(s) taken to prevent a recurrence.
4.4.16 Procedures shall be written and maintained to cover the following topics as a minimum:
4.4.16.1 Test Solidifications.
4.4.16.2 Acceptability of Solidification Test Specimens.
4.4.16.3 Solidification of Containers. Containing Radioactive Waste.
4.5 S ent Resins and Slud es 4.5. 1 Spent resins and sludges will be transferred to a container suitable for shipping the waste in compliance with applicable codes and standards.
4.5.2 Normally the transfer is accomplished by sluicing the resin/sludge from the Spent, Resin Storage Tank, directly from a demineralizer or hoding .tank to the shipping container.
4.5.3 The container selected to be used will be selected taking into consideration the volume of resin/sludge to be sluiced, dewatering or solidifying requirements, and stability requirements as defined by 10 CFR 61.
Page 5 of 10 Revision 3
12 PMP 3150 PCP. 100 4.5.4 Solidification of spent resins/sludge is acceptable, however, resins will normally be dewatered and sludge will attempt to be dewatered prior to solidification.
4.5.5 Dewatering of spent -resins/sludge may be accomplished via one of the following methods; 4.5.5.1 , Pumping of'"aor draining. water from the bottom hi:gh""'integrity container using a dragon system installed in the high integrity container, or 4.5.5.2 Heat enhanced dewatering, where moisture is driven off by the introduction of warm air into a high integrity container.
4.5.6 Zn all cases, when high integrity containers are dewatered, they shall be dewatered to 1 '~o free standing water by volume.
4.5.7 Procedures shall be written and maintained to cover the following topics as a minimum; 4.5.7.1 Transfer of resins to shipping containers.
4.5.7.2 Dewatering of resins/sludge in high integrity containers.
4.5.7.3 Verification of < 1.0~ free standing Water in high integrity containers.
4.6 Contaminated Oils 4.6.1 Contaminated oils are burned in the Plant Heating Boiler.
4.6.2 Prior to placing the oil in the Plant Heating Boiler Storage Tank, a guantitative and qualitative radioisotopxc analysis is required.
4.6.3 The isotopic analysis and volume of oil is used to determine the total activity to be released via the heating boiler's exhaust.
4.6.4 The activity released shall be within limits delineated zn D. C. Cook Plant Technical Specifications.
4.7 Com ressible Wastes 4.7. 1 Contaminated and potentially contaminated compressible wastes are collected from var>.ous areas in the Auxiliary Building, and are normally taken to the Drumming Rooms.
Page 6 of 10 Revision 3
12 PMP 3150 PCP. 100 4.7.2 The waste is segregated to remove reusable non-compliance with Federal and Burial Site Regulations, (i.e , liquids, paint, etc. . )
4.7.3 The waste may be processed either of two ways; 4.7.3.1 Compacted in qualified shipping containers for burial, or 4.7.3.2 Packaged and shipped to a contracted radwaste processor for further processing, volume reduction, packaging, and eventual shipment to a burial site.
4.7.4 Procedures shall be written and maintained to cover the following topics as a minimum; 4.7.4.1 Packaging of waste in shipping containers.
4.7.4.2 Documentation of container contents, radiological data, container qualification, and volume.
4.8 Non-Com ressible Wastes 4.8.1 Contaminated and potentially contaminated non-compressible wastes are collected from various areas in the Auxiliary Building, and are normally taken to the Drumming Rooms.
4.8.2 The waste is segregated to remove reusable materials and materials which would be in non-compliance with Federal and Burial Site Regulate.ons.
4.8.3 The waste may be handled either of two ways; 4.8.3.1 Packaged in qualified shipping containers for burial, or 4.8 '.2 Packaged and shipped to a contracted'radwaste processor for further processing, volume reduction, packaging, and eventual shipment to a burial site.
4.8.4 Procedures shall be written and maintained to cover the following topics as a minimum; 4.8.4.1 Packaging of non-compressible waste in shxppxng containers.
4.8.4.2 Documentation of container contents, radiological data, container qualification, and volume.
Page 7 of 10 Revision 3
12 PMP 3150 PCP. 100 4.9 Waste Filters 4.9.1 Absolute air filters and HEPA filters may be processed as compressible and/or non-compressible wastes.
4.9.2 Filters with an activity halflife of <1.0 pCi/cc of all radioisotopes with a of >5 years, may be handled as compressible or non-compressible wastes.
4.9.3 Filters with an activity of >1.0 pCi/cc of all radioisotopes with a halflife of >5 years, must be stabilized prior to shipment for disposal.
4.9.4 Once changed, the waste filters are normally placed in a drum and stored until they are packaged for shipment.
4.9.5 At the time of final packaging for shipment, the filter shall be verified free of water.
4.9.6 Liquid process filters shall be packaged for shipment only in qualified shipping containers.
4.9.7 The container selected to be used will be selected taking into consideration the volume of filters to be disposed of, dewatering or solidification requirements, and stability requirements as defined by 10CFR61.
4.9.8 Procedures shall be written and maintained to cover the following topics~ as a minimum; 4.9.8.1 Venting, draining, and changing of liquid process filters.
4.10 Stabilization of Unstable Wastes 4.10.1 Class A waste with a total activity of > 1.0 pCi/cc, and all Class B and C waste must be stabilized in accordance with 10 CFR61 and the applicable burial site criteria.
- 4. 10.2 Stabilization shall be achieved by packaging the waste in approved high integrity containers or by using an approved solidification process.
Page 8 of 10 Revision 3
12 PMP 3150 PCP. 100 5.0 REPORTING 5.1 Documentation 5.1.1 Documentation shall be maintained for the following topics; 5.1.1.1 Radiological data associated with each waste package.
5.1.1.2 Package contents.
5.1.1.3 Processed waste effluents released.
to the environment, (i.e., liquid releases . . . ).
5.1.1.4 Solidification data.
5.1.1.5 Dewatering data.
5.1.1.6 Weights and/or volumes of waste packaged.
5.2 ~ --Aii gona~~ effluent report shall be sent to the NRC annually.
This report shall include the following information for each type of solid waste shipped off-site during the report period;
- 5. 2. 1 Volume (cubic meters),
5.2.2 Total curie quantity (specify whether determined by measurement or estimate),
5.2.3 Principle radionuclides (specify whether determined by measurement or estimate),
5.2.4 Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
5.2.5 Type of container (e.g., LSA, Type A, Type B, Large Quantity),
5.2.6 Solidification agent (e.g., cement).
5.3 An Annual Operating Report shall be sent to the NRC annually. This report shall include the following information regarding major changes to the Solid Rad Waste Treatment Systems initiated by the Plant; 5.3. 1 A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; Page 9 of 10 Revision 3
12 PMP 3150 PCP. 100 5.3.2 Sufficient detailed information to totally support. the- reason for the change without benefit of additional or supplemental information; 5.3.3 A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; 5.3.4 An evaluation of the change which shows the predicted quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; 5.3.5 An evaluation of the change which shows the expected maximum exposure to individuals in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; 5.3.6 A comparison of the predicted releases of radioactive materials in solid wastes to the
.actual releases for the period prior to when the changes are to be made; 5.3.7 An estimate of the exposure to plant operating personnel as a result of the change; and 5.3.8 Documentation of the fact. that the change was reviewed and found acceptable by the PNSRC.
5.4 For Commission initiated changes to the Solid Rad Waste Treatment System, the applicability of the change to the facility shall be determined by the PNSRC after consideration of the facility design, and the Plant shall provide the Commission with written notification of. its determination of applicability. including any necessary revisions to reflect facility design.
Page 10 of 10 Revision 3
12 PMP 3150 PCP. 100 APPENDIX A RESPONSIBILITIES FOR THE PROCESSING OF LI UID WASTES AND THEIR BY-PRODUCT WASTES PROCEDURES FOR PROCESS SUPERVISED AND/OR PROCESS PERFORMED BY MAINTAINED BY VERIFIED BY Operate Rad Waste Evaporator Operations Operations Shift Supervisor/Ass.
SS 0 erations Transfer Evaporator Bottoms Operations Operations Shift Supervisor/Ass.
SS 0 erations Monitor Chemical and Rad Chemistry Chemistry Chemistry Supervisor/
Activity Parameters of Rad Rad Material Control Waste Demineralizers Operate Rad Waste Rad Material Rad Material Rad Material Control Demineralizers Control Control Monitor Rad Activity Parameters Chemistry Chemistry Chemistry Supervisor/
of Rad Waste Demineralizers Rad Material Control Sluice Rad Waste Demineralizer Rad Material Rad Material Rad Material Control Resins Control Control Packaging of Rad Waste Rad Material Rad Material Rad Material Control Demineralizer Resins Control Control Packaging of Waste Evaporator Rad Material Rad Material Rad Material Control Bottoms Control Control Solidification of Waste Rad Material Rad Material Rad Material Control-Eva orator Bottoms Control Control Test Solidifications Rad.-Material Rad Material Rad Material Control Control Control Verification of Test Rad Material Rad Material Rad Material Control Solidifications Control Control Verification of Solidifications Rad.Material Rad Material Rad Material Control Control Control Determine Curie Content of Rad Material Rad Material Rad Material Control Packa es Control Control Page 1 of 5 Revision 3
12 PMP 3150 PCP.100 APPENDIX A RESPONSIBILITIES FOR THE TRANSFER AND PROCESSING OF'SPENT RESINS PROCEDURES FOR PROCESS SUPERVISED AND OR PROCESS PERFORMED BY MAINTAINED BY VERIFIED BY Sluice Resin from Plant Operations Op'erations S Operations Demineralizer to SRST V Radiation rot.
Sluice Resin from Plant Operations Operations S Operations Demineralizer to a HIC V Radiation rot./
Rad Material Control Sluice Resin from SRST to a HIC Rad Material Rad Material Rad Material C ntrol Control Control Dewatering Using Installed Rad Material Rad Material Rad Material C ntrol Drain System Control Control Dewatering Using Heat Enhanced Rad Material Rad Material Rad Material C ntrol Method Control Control Dewatering Verifications Rad Material Rad Material Rad Material C ntrol Control Control Sampling of Resin Rad Material Rad Material Rad Material Co ntrol Control Control Quantitative and Qualitative Chemistry Chemistry Chemistry Isotopic Analysis of Waste Resin Determine Curie Content of the Rad Material Rad Material Rad Material Co ntrol Packages Control Control Page 2 of 5 Revision 3
12 PMP 3150 PCP.100 APPENDIX A RESPONSIBILITIES FOR THE PROCESSING OF COMPRESSIBLE AND NO -COMPRESSIBLE WASTES PROCEDURES FOR PROCESS SUPERVISED AND/OR PROCESS PERFORMED BY MAINTAINED BY VERIFIED BY Collection and Transfer of Rad Material Rad Material Rad Material Control/RP Waste to Processing Area Control/RP Control/RP Segregation of Non-Compliance Rad Material Rad Material Rad Material Control Materials Control Control Compaction of Compressible Rad Material Rad Material Rad Material Control Waste Control Control Packaging for Shipment to Rad Material Rad Material Rad Material Contro'l a Processor Control Control Packaging of Non-Compressibles Rad Material Rad Material Rad Material Control for Burial Control Control Isotopic Analysis of Waste Chemistry/RP Chemistry/RP Chemistry/RP Determine Curie Content of Rad Material Rad Material Rad Material Contro'l Package Control Control Page 3 of 5 Revision 3
12 PMP 3150 PCP.100 APPENDIX A RESPONSIBILITIES FOR THE PROCESSING OF CONTAMINATED WASTE OIL PROCEDURES FOR PROCESS SUPERVISED AND/OR PROCESS PERFORMED BY MAINTAINED BY VERIFIED,. BY Transfer of Oil to Heating Rad Material Rad Material Rad Material Control Boiler Storage Tank Control/ Control Maintenance/
Construction Isotopic Analysis of Oil Chemistry Chemistry Chemistry Activity Released Determination Rad Material Rad Material Rad Material Control Control Control Page 4 of 5 Revision 3
12 PMP 3150 PCP.100 APPENDIX A RESPONSIBILITIES FOR T E PROCESSING OF HASTE FILTERS PROCEDURES FOR PROCESS SUPERVISED AND/OR PROCESS PERFORMED BY MAINTAINED BY VERIFIED BY Venting and Draining of Filter Operations Operations Operations Housing Changeout and Transfer of RP RP RP/
Filter Radiation Protection Packaging of Filters for Rad Material Rad Material Rad Material Control Shipment Control Control Isotopic Analysis of Filter Chemistry/RP Chemistry/RP Chemistry/RP Verification of Filter Rad Material Rad Material Rad Material Control Drainage Control Control Determine Curie Content of Rad Material Rad Material Rad Material ontrol Package Control Control Page 5 of 5 Revision 3
12 PMP 3150 PCP. 100 APPENDIX B MIXED WASTE PROGRAM 1.0 ~Pur oee 1.1 This program .is designed to establish guidelines and procedural requirements which will provide adequate assurance that the plant is in compliance with current restrictions on the burial of low-level radioactive waste mixed with hazardous materials. These requirements are applicable to all radioactive wastes packaged for burial.
- 2. 0 ~Polio 2.1 All chemicals used within the controlled area of the plant will be utilized in accordance with PMI-2160, which includes restrictions on their disposal.
3.0 Definitions F 1 Mixed Waste - Mixed low-level radioactive and hazardous waste (mixed waste) is waste that satisfies .the definition of low-level radioactive waste .(LLW) in the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) and contains hazardous waste that either (1) is listed as a hazardous waste in Subpart D of 40 CFR Part 261 or (2) causes the LLW to exhibit any of the hazardous waste characteristics identified in Subpart C of 40 CFR Part 261.
3.2 Hazardous Characteristics The four characteristics that a waste may exhibit that result in classified as a hazardous waste are:
it being ignitability (Part 263,.21); corrosivity (Part 261.22); reactivity (Part 261.23); and EP toxicity (Part 261.24).
4.0 Identification of Mixed Waste 4.1 Determine which waste streams have the =potential for containing mixed waste. This determination should be done by applying knowledge of the hazard characteristic of the waste in light of the materials or the processes used.
Page 1'f 2 Revision 3
12 PMP 3150 PCP.100 APPENDIX B 4.2 Determine whether the radioactive waste contains any hazardous wastes specifically listed in Subpart D of 40 CFR Part 261, from PMI-2160, Chemical Permits.
4.3 Determine whether the radioactive waste contains hazardous waste that causes the waste to exhibit any of the hazardous waste characteristics identified in Subpart C of 40 CFR 261 by collecting representative samples for testing.
4.4 Samples shall be processed into their normal form for transportation and burial. For example, sludges are solidified for burial so the sample should be solidified prior to testing. The parameters used to solidify the sample should be the same as would be used for full scale processing.
4.5 Have the final waste form samples analyzed for a particular hazardous chemical if one has been identified in 4.3, or for the hazardous characteristics of 4.4.
4.6 If the analysis classified as a results in the waste not being mixed waste it may be disposed under normal plant procedures.
4 ' If the analysis results in the waste being classified as a mixed waste it should be held on site until such time that an appropriate disposal facility is available, unless approved per Section 6.0.
5.0 Sam lin Fre uenc 5.1 As a minimum, samples of radwaste resin, evaporator concentrates and sludges, if available, should be collected annually and sent offsite for RCRA Waste Characterization.
tions 6.1 The Barnwell burial site (licensee: Chem. Nuclear) may receive waste that has been treated by acceptable methods to render it non-hazardous and therefore not subject to the jurisdiction of the Resources Conservation and Recovery Act (RCRA). Waste which may contain discreet quantities of hazardous or toxic materials may be evaluated for disposal by Chem-Nuclear and such evaluations provided to the South Carolina Department of Health and Environmental Control (DHEC) for consideration of approval.
Page 2 of 2 Revision 3
12 PMP 3150 PCP. 100 APPENDIX C PARAMETERS FOR THE OPERATION OF THE WASTE EVAPORATOR SYSTEM The limit of volume reduction for the Waste Evaporator System is dependent on the concentration of various chemical and radiochemical parameters.
The boron concentration should be kept within the limits listed in Table 1, to prevent crystallization of boron in the evaporator package. If the boron concentration increases above this limit, sodium hydroxide should be added to maintain an acceptable pH and to convert the boric acid to a more soluble form.
The concentration of chlorides should be kept below the limit listed in Table 1. Chlorides must be controlled to prevent corrosion of the evaporator's internal components.
The gross By activity of the evaporator bottoms should be kept below the limit listed in Table 1. The activity is maintained, to insure that the evaporator bottoms may be solidified and shipped in compliance with applicable regulations.
Samples will he taken periodically by the Chemistry Section during waste evaporator operation to monitor these chemical and radiochemical parameters.
Prior to attempting solidification of waste evaporator bottoms, the bottoms should be sampled and found to be within the limits listed in Table 2.
TABLE 1 Boron Concentration 25,000 ppm pH 7.4 9.2 Gross Sy Total 0. 2 pCi/cc Chlorides 10, 000 ppm TABLE '2 Boron Concentration 0 40,000 ppm pH 7.4 9.2 or > 11.5
- Radionuclides with A 0.05 1.0E-4 pCi/gm
- Radionuclides with A > 0.05 and < 1.0 5.0E-3 pCi/gm
- Radionuclides with A 1.0 3. OE-1 pCi/gm Chlorides 0 10,000 ppm
- A defined in 10 CFR 71, Appendix A.
Page 1 of 1 Revision 3
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