ML13329A481
| ML13329A481 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/17/1984 |
| From: | Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13324A473 | List: |
| References | |
| SO1-VII-8.5.1, TAC-57810, NUDOCS 8411070010 | |
| Download: ML13329A481 (61) | |
Text
.NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 1 OF 61 EFFECTIVE DATE PROCESS CONTROL PROGRAM FOR SAN ONOFRE UNIT 1 TABLE OF CONTENTS SECTION PAGE 1.0 OBJECTIVES 2
2.0 REFERENCES
2 2.1 Licensing Commitments 2
2.2 Procedures 2
2.3 Other 2
3.0 PREREQUISITES RECEIVED COM 3
4.0 PRECAUTIONS OCT 17 1984 5.0 CHECKLIST SITE FILE COPY4 6.0 PROCEDURE 4
6.1
System Description
4 6.2 Requirements for Sample Testing 8
6.3 Sample Acceptance Criteria 10 6.4 Requirements for Sample Verification 10 6.5 Test Documentation 11 7.0 RECORDS 11 ATTACHMENTS 1
Equipment Recommended for Testing Sample 12 2
PCP Solidification of Boric Acid Concentrates 13 3
PCP Solidifications of Particulate Wastes (Resin Beads, Powdex, Diatomaceous Earth Slurries, and Other Particulate Wastes) 22 4
PCP for Preparation of Fluid Mixture for In-situ Solidifications 34 5
PCP Solidifications of Particulate Wastes Class A Unstable Waste Form Only (Resin Bonds, Powdex, Diatomaceous Earth Slurries, and Other Particulate Wastes) 38 6
PCP Solidification of Miscellaneous Aqueous Wastes Class A Unstable Waste Form Only 47 7
Liner and Cask Calculations 54 8
Data Record Form 55 9
Developmental Resources 60 070010 841102 PDR ADOCK 05000206 PD PDR
-F QA PROGRAM AFFECTING 0275e
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 2 OF 61 PROCESS CONTROL PROGRAM FOR SAN ONOFRE UNIT 1 1.0 OBJECTIVES 1.1 The purpose of the Process Control Program for San Onofre Unit No. 1, is to establish a set of process parameters which provide reasonable assurance of complete solidification of various liquid radioactive "wet wastes" including resin slurries, tank and sump sludges, filters; and Class B and Class C waste requiring stabilization (i.e., encapsulation), in accordance with applicable Department of Transportation (DOT) and California State Regulations and Nuclear Regulatory Commission (NRC) and licensed burial Facilities' acceptance criteria for packaging and shipment to an approved offsite burial site.
1.2 This instruction shall be used by all personnel operating the CNSI cement solidification unit. This procedure is applicable to all liners listed on Attachment 5.
2.0 REFERENCES
2.1 Licensing Commitments 2.1.1 SONGS 1 Technical Specifications Section 3.19 "Solid Radioactive Waste," (when implemented) 2.1.2 Final Safety Analysis Report for San Onofre Unit 1 2.1.3 Topical Quality Assurance Manual for San Onofre Unit 1, Unit 2, and Unit 3 2.2 Procedures 2.2.1 S0123-VII-8.1, Solid Radioactive Waste Packaging, Labeling and Shipping 2.2.2 S0123-VII-8.5.2, "Radwaste Solidification with CNSI Portable Solidification Unit (PSU-C-125) (when issued) 2.2.3 S0123-SD-OP-063, "Assembly and Disassembly Procedure for CNSI Portable Cement Solidification Unit No. 125" 2.3 Other 2.3.1 10 CFR Part, 20, Standards for Protection Against Radiation 2.3.2 Chem-Nuclear Topical Report CNSI-WF-C-01-NP "10 CFR 61 Waste Form Certification-Cement," November 30, 1983 2.3.3 CNSI Topical Report, CNSI-2, 4313-01354-OIP-A January 1983, Revision 2
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 3 OF 61 3.0 PREREQUISITIES 3.1 Prior to use of an uncontrolled (pink) copy of this Station Document to perform work, verify it is current by utilizing one of the following methods:
3.1.1
.Checking a controlled copy and any TCNs; 3.1.2 Accessing an SCE Document Configuration System (SDCS) TSO Terminal; 3.1.3 Referencing a current (within one week) Configuration Control Log and associated daily update; 3.1.4 Contacting CDM by telephone or through counter inquiry; 3.1.5 Obtaining an uncontrolled (pink) copy of the Station Document from CDM.
3.2 The Station Manager shall assure the performance of a review by a qualified individual/organization of changes to the Process Control Program. Change(s) shall be submitted to the USNRC in the semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.
3.3 The CNSI operator shall ensure that additives received comply with the chemical composition necessary for this process. Conditioning chemicals are purchased from reputable suppliers and, in most cases, are available through national distribution networks. The final reliability criteria is the satisfactory performance of the chemical in a laboratory solidification formula containing material sampled from the actual bags or drums intended for subsequent use.
3.4 The CNSI operator shall ensure that all the necessary equipment described in Attachment 1 are available or SCE/CNSI approved substitutes are available.
3.5 Ensure Attachments 1 through 6 are consistent with the latest
.revision of the CNSI Process Control Program for cement solidification units and Reference 2.3.2.
3.6 A Radiation Exposure Permit SO(123) 100 must be obtained prior to commencing this procedure.
3.7 The Portable cement solidification unit shall have been assembled and tested in accordance with Reference 2.2.3.
3.8 Ensure QC inspector is present when portions of the procedure are being performed which contain Quality Hold Points (QHP).
Inspections required shall be documented on Data Record Form for this procedure.
3.8 An ALARA review must be performed prior to beginning this Procedure.
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 4 OF 61 3.0 PREREQUISITIES (Continued)
HP 3.9 Ensure scale used to weigh process chemicals for test samples has been verified accurate prior to each use, over the scale range, using certified.standard weights. Scale accuracy will be + 1% of the standard weight used.
4.0 PRECAUTIONS 4.1 The chemicals and cement used are considered non-toxic and safe to handle, however, care should be used to avoid breathing dust, follow the safety precautions outlined in the appropriate Radwaste Solidification procedures, Reference 2.2.2 (S0123-VII-8.5.2).
4.2 If difficulties are encountered with any part of this verification procedure or unexpected results are obtained, contact the Chem Nuclear Solidification Manager, or Supervisor, and the SCE Radwaste Supervisor or his designee.
4.3 The CNSI technician(s) shall be subject to the applicable Health Physics and safety precautions of the Health Physics Program.
4.4 Laboratory gloves, face shield and an apron shall be worn by the CNSI technician(s) while handling, collecting and testing of all samples.
4.5 Health Physics personnel shall ensure that radiologically clean and contaminated zones are established in the sample process area to prevent the possible spread of contamination.
5.0 CHECKLIST 5.1 Data Record Form 6.0 PROCEDURE 6.1 SYSTEM DESCRIPTION 6.1.1 Process Description The process used at San Onofre Unit 1 is the CNSI Cement Solidification Unit. This unit is specifically designed to facilitate solidification of various radioactive wastes, including ion exchange resin slurries, tank and sump sludges, filters, and Class B and Class C waste requiring stabilization (encapsulation).
Immobilization of the waste is accomplished using readily available Portland cement in conjunction with hydrated lime and particular process additives. The waste is solidified in a disposable liner which may already contain some of the required conditioning chemicals. Pre-installed mixer blades permit continuous agitation until a thick cement paste has formed that will set to a hard, uniform, water-free matrix. The end product is a true cement structure formed in accordance with established principals of concrete techgology.
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 5 OF 61 6.0 PROCEDURE (Continued) 6.1.2 Process Parameters
.1 Portland Cement combines with water through several intermediate reactions to form stable hydrates.from chemically combined mixtures of calcium, silicon, aluminum, and iron oxides. These reactions are exothermic (heat producing) and do not progress rapidly unless a strongly alkaline pH (11-12) is maintained.
Waste streams may contain certain metallic radionuclides that are chemically bonded (and not leached) in the cement structure without loss of product strength.
Other waste chemicals can significantly accelerate or retard cement set, and must be controlled by the addition of selected chemical agents.
.2 Judicious control of total cement content maximizes waste volume efficiency and minimizes heat development for large volume solidifications. Preferred waste to additive solidification ratios have been determined by the CNSI Research and Development Program, but it is recognized that waste stream composition and density are variable, and that verification of the solidification formula is necessary for each new lot of waste liquid.
This important consideration is detailed by waste form in Attachments 2 through 6.
6.1.3 Solidification Unit Description
.1 The CNSI Cement Solidification Unit System contains all piping, support, control and monitoring equipment necessary to solidify either radioactive liquid waste or Class B or Class C waste requiring stabilization (encapsulation) using the cement process.
.2 The unit is composed of several processing systems, each controlling a specific function of the cement process.
These subsystems include waste transfer, chemical addition, cement conveyor, vent, and dewater systems.
Control functions for the unit are incorporated into the pneumatic and main control panels. The following services are provided which satisfy the interface requirements for the portable cement solidification unit:
.2.1 General Requirements:
.2.1.1 480V AC (3 Phase 100 amps)
.2.1.2 120V AC ("House Current")
.2.1.3 Resin Dewater Return 1/2" connection 150#
R. F. flange
.2.1.4 Service Water - connection 3/4" quick disconnect fitting, minimum 30 gpm at > 80 psig
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 6.OF 61 6.0 PROCEDURE (Continued) 6.1.3.2.1.5 Plant OFF Gas - connection 2 1/2" quick disconnect 0
fitting
.2.1.6 Plant Waste -
1-1/2" connection 150# R. F. flange
.2.1.7 Service Air - 3/4" quick disconnect, 75 CFM 100 +/- 20 psig
.2.2 Appropriate communication systems will be provided between the plant.operator and the CNSI mobile unit operator. Telephone service will be provided for local and long, distance business calls.
.2.3 Prior arrangements for shipping of the solidified material will be made by SCE. An approved vendor will provide the shipping casks.
.2.4 SCE is prepared to accept cement shipments prior to the arrival of the unit onsite. Cement for solidification has already arrived and is stored for use in the bulk cement storage trailer.
.2.5 A Radiation Exposure Permit (REP) must be obtained before any radwaste solidification operations begins.
.2.6 SCE shall provide to the CNSI operator(s), in the same manner as available for plant personnel, any clothing or equipment necessary for radiation protection.
.2.7 A Red Badge Zone will be established around the processing area.
.2.8 SCE personnel have designated an area to be used for test solidification.
.2.9 SCE will provide crane services, torque wrenches and other necessary materials for loading the liners and preparing the solidified waste for shipment.
.2.10 SCE will have available a forklift capable of 4,000 pounds at 6 foot movement arm to unload the removable skids and place them in position for full-scale solidification.
.3 The equipment, components and structures that interface with the mobile cement solidification system comply with the applicable criteria of Regulatory Guide 1.143, Revision 1, Branch Technical position ETBS 11-3, Final Safety Analysis Report for San Onofre Unit 1, TQAM for SONGS Units 1, 2 and 3, ALARA Program for San Onofre Unit 1, and Health Physics Program for San Onofre Unit 1.
0II
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 7 OF 61 6.0 PROCEDURE (Continued) 6.1.3.4 Most of the unit components are arranged on portable frameworks (skids) to provide flexibility of operations for either indoor or outdoor use. The cement conveyor, control panel, pump skid, hydraulic skid and fil.lhead contain most of the major elements of the mobile unit.
.5 A closed-circuit television system is an integral part of the unit and allows the operator to monitor the solidification process.
6.1.4 System Operation
.1 Before beginning any solidification operations with the Cement Solidification Unit, the CNSI operator shall complete a successful sample verification in accordance with the Sample Verification Procedure described in Sections 6.2 through 6.4.
.2 The sample solidification calculations are recorded on a SCE/CNSI Solidification Worksheet. Full scale solidification values are determined from Attachments 2 through 6.
.3 Actual full scale solidification shall then be conducted in accordance with the Radwaste Solidification Procedure Reference 2.2.2 (S0123-VII-8.5.2) using the parameters calculated on SCE/CNSI Solidification Worksheets.
.4 Dewatering of resin or other slurries to be solidified will be performed in specially designed CNSI cement solidification liners in accordance with Reference 2.2.2.
The dewatering line from the solidification system will be returned to the applicable portion of the Plant system for the waste stream being transferred in accordance with the proper transfer procedure.
.5 The primary waste streams to be solidified by the CNSI cement solidification system will come from the following tanks: Spent Resin Storage Tank, the Liquid Waste Hold-up Tanks, and the Monitor Tank. Other wastes to be solidified will include cartridge filters, misc. sludges, filter media and class 8 and C wastes required to be stabilized by 10 CFR Part 61.
6.1.5 Sequence of Operation The conditioning chemicals may be preloaded into the liner or added to the waste while mixing. The addition of chemicals or waste may be interrupted at any time. The mixer may also be secured during waste or pretreatment chemical addition with no effect on the process, however, it must remain in operation during the addition of solidification chemicals and/or cement.
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 8 OF 61 6.0 PROCEDURE (Continued) 6.1.6 Waste-to-Cement Ratio (by volume)
The normal volume ratio of waste to solidification components will be approximately 2 to 1 up to 3 to 1 for liquids, resins, powdex and other solids. It Is necessary to control the waste-to-cement ratios at certified levels to ensure product integrity and to meet burial requirements.
6.1.7 Cure Time Cure time will usually be 12 to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> as shown by a continuing temperature rise. The liner should be ventilated until temperature begins to decrease indicating safe completion of the solidification process.
6.1.8 Shipping The finished product will be shipped in accordance with Reference 2.2.1 (S0123-VII-8.1) and will comply with applicable DOT regulations, state regulations, NRC and burial facility acceptance criteria, 10 CFR Part 61, and 10 CFR 20.311 for packaging and shipment to an approved offsite burial site.
6.2 REQUIREMENTS FOR SAMPLE TESTING 6.2.1 Representive Sampling
.1 Due to the importance of obtaining a representative sample for waste classification (Reference 2.1.1) and to use in the verification procedure, the Radwaste Health Physics personnel shall confirm that the sample is representative of the contents of the selected waste storage tank (as listed in step 6.1.4.5) or the shipping container.
.2 If possible, samples shall be drawn after the contents of the selected waste storage tank have been adequately mixed. The system will be shifted directly from recirculation/agitation mode to the transfer mode and a representative sample shall be taken.
.3 For miscellaneous sludges, liquids, and storage tanks which do not allow adequate mixing of the contents, samples will be taken after the waste has been transferred into the shipping container as follows:
.3.1 After the shipping container has received all the waste, the contents of the shipping container shall be mixed, with the installed mixing system, for a minimum of 15 minutes.
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 9 OF 61 6.0 PROCEDURE (Continued) 6.2.1.3.2 A grab sample will be taken as soon as possible after completion of mixing.'
.3.3 For any additional transfers of the same waste stream, which are controlled by the sample taken in step 6.2.1.3.2 and in accordance with step 6.4.3, a grab sample will be taken during the transfer of each consecutive shipping container to verify proper classification and that the process parameters have not changed. If the process parameters have changed from the initial sample, a new verification sample is required.
.4 For wastes requiring encapsulation (i.e., filters, wet solids with special nuclear material, and other Class B and C solids) a representative sample will be taken prior to loading waste into the specially designed solidification liner. This sample will be used for the Verification sample.
.5 Any one of a number of operations involving the selected waste storage tank or the shipping container may negate the previous sample results. These operations include the following:
.5.1 introduction of additional waste into the selected storage tank or shipping container after verification sample was taken;
.5.2 securing of recirculation and/or transfer while drawing the verification sample.
.6 If any of the situations listed above or a situation deemed, by the Radwaste Supervisor or his designee, to be detrimental should occur, it will be necessary to repeat the sample process and sample verification procedure of Section 6.5 in order to re-establish the solidification process parameters.
6.2.2 Waste Identification
.1 The Chemistry Department shall provide chemical analyses. These analyses will provide the basic chemical composition and properties of the selected QHP waste stream as requested by the Radwaste Group. The CNSI operator shall record the chemical composition and properties on Attachments 2 through 6 as required and may confirm waste density and pH as necessary.
NOTE:
Waste containing oil above one percent by volume shall not be solidified by this PCP.
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 10 OF 61 6.0 PROCEDURE (Continued) 6.2.3 Equipment Equipment required for the sample verification procedure is listed in Attachment 1. The table indicates the recommended quantity to begin a verification p'ocedure.
HP The CNSI operator shall ensure that all necessary equipment is available or SCE/CNSI approved substitutes are available.
6.3 Sample Acceptance Criteria 6.3.1 The sample verification (CNSI, SCE/QC) is performed by examination of lab compositions containing actual waste material. The test confirms the correct process constituents.
The acceptance criteria for a good solidified product are as follows:
QHP
.1 Visual inspection of the end product after solidification indicates a uniform, dry, free-standing monolith; QHP
.2 The end product resists penetration when probed with a spatula or other firm object.
6.4 Requirements for Sample Verification 6.4.1 Verify that all materials listed in Attachment 1 are HP available and ready to use in the area selected by the Health Physics Group for solidification testing.
6.4.2 Be prepared to complete the test procedures outlined in Attachments 2 through 6, as applicable, when conducting sample verifications.
6.4.3 Sample Requirements
.1 A sample shall be solidified prior to the initial full scale solidification of a particular waste stream. If the test sample meets the acceptance criteria and there is no change in the chemical composition of the waste as verified by Radwaste Health Physics personnel (Ref. step 6.2),
test results and full scale solidification parameters will be considered reproducible. Thereafter, a sample solidification will be conducted prior to the tenth batch solidified from the same source of waste.
.2 If any test sample fails to meet the acceptance criteria, the full scale solidification shall be suspended until a new sample is obtained in accordance with step 6.2, alternate parameters are established for the waste stream, and a subsequent test sample meets the acceptance criteria. Full scale solidification can then be resumed using the alternate solidification parameters as determined by the verification procedure.
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 11 OF 61 6.0 PROCEDURE (Continued) 6.4.3.3 If the initial test sample from a batch of waste fails to meet the acceptance criteria, a test sample shall be performed prior to full scale solidification for each consecutive batch of the same type of waste until at least 3 consecutive initial test samples meet the acceptance criteria.
.4 The CNSI operator and the Radwaste Health Physics Personnel shall ensure, as much as possible, that the test sample is representative (i.e., thoroughly mixed)
(Ref: step 6.2).
6.5 TEST DOCUMENTATION 6.5.1 Calculate and record the available information on the QHP CNSI/SCE Solidification Worksheets for all waste type sample verifications.
6.5.2 Use the appropriate attachment (Attachments 2 through 6) for test instructions and documentation for the various waste forms to be solidified.
7.0 RECORDS 7.1 All forms for each solidification must be gathered and filed with the shipping papers in a single package in CDM. This will require coordination with the Radwaste Foreman and QC.
7.2 The CNSI operator shall forward a copy of each completed CNSI/SCE Solidification Worksheet to the Chem-Nuclear Manager, Solidification Services and the SCE Radwaste Supervisor for review following completion of liner solidification.
7.3 The CNSI/SCE Solidification Worksheet and related instruction sheets are considered as proprietary information and not to be distributed outside of Chem-Nuclear Systems Inc. or required SCE personnel.
Each CNSI operator shall maintain a controlled file of these documents. This file is subject to audit by CNSI or SCE Quality Assurance.
Reust:02756
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
.UNIT 1 REVISION 0 PAGE 12 OF 61 ATTACHMENT 1 EQUIPMENT RECOMMENDED FOR TESTING SAMPLE 250 ML Plastic Beakers with Lids (12) 600-1000 ML Containers (12)
Wide Blade Spatulas (2) 0-212OF Thermometer (3) pH Paper:
Wide Range (0. to 9.0)
Narrow Range (9.0 to 13.0)
Hydrometers, Range 1.000 -
1.200 and 1.200 -
1.400, or equivalent 0-600 or 0-1000 gm Triple Beam Balance Hot Plate, variable temperature control Pyrex Beakers, 600 ml capacity (12)
Marking Pen Sample Heating Oven, Thermostatically Controlled from 1000 to 180*F.
(See Note 2)
Graduated Cylinders, 250 ml (2)
NOTE 1:
Chemicals to be used should be taken from the full scale soli'dification chemicals. These should be stored in capped containers.
NOTE 2:
Waste Solidified with cement on a small scale at ambient temperature will set much more slowly due to removal of exothermic heat. Sample conditioning in a temperature-controlled oven permits more meaningful evaluation of solidification results in 6-24 hours as specified for the waste form, or as established by experience at a particular utility.
0275e ATTACHMENT 1 PAGE 1 OF 1
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 13 OF 61 ATTACHMENT 2 PCP SOLIDIFICATION OF BORIC ACID CONCENTRATES (N-24, CEMENT, LIME SEQUENCE) 1.0 SAMPLE VERIFICATION NOTE:
The chemical additives used for PCP preparation should be those actually used in full scale solidification and should be stored in capped containers. The sequence for chemical addition for PCP preparation and full scale solidification shall be the same.
1.1 From past experience and the analysis supplied by the utility, determine the appropriate PCP solidification formula using the amounts below.
Note that boric acid waste that has been partly neutralized unintentionally or to reduce storage temperature may require additional solidification agents and result in less efficient waste handling.
Waste temperature must also be considered in determining the preferred PCP formula and full scale material requirements. The sample volumes are listed below:
Amounts Boron Content Boric Acid Waste
- WT. of CNSI *WT. of CNSI Weight of Weight of (ppm)
Equivalent Volume Agent N-24 Agent P-14 Cement Lime 0- 6,900 0-4%
200-210 ML 5 GM 0-20 GM 170-210 GM 60-80 GM 7,000-21,000 4-12%
210-240-ML 10 GM 0-20 GM 130-180 GM 60-80 GM Above 21,000 Above 12%
220-250 ML 15 GM 0-20 GM 120-170 BM 60-80 GM
- Typical Amount or As Required by Test Results 1.2 Notify Radwaste Health Physics personnel that preparations for verification testing are complete and that a sample is required.
HP 1.3 If waste sample has crystallized and is non-uniform, the entire sample must be heated to 140 0F or above until crystals have re-dissolved. Then measure out waste volume required in 250 ml graduate and immediately transfer to a 600 ml pyrex beaker.
HP 1.4 If sample is less than 160oF, heat sample to 160 0 F on the hot plate using a glass rod to occasionally stir contents. Then remove beaker from the hot plate and, when temperature is just 160 0F, immediately add required weight of CNSI Agent N-24. Stir vigorously to disperse powder in hot liquid, and to determine if foaming may occur in the full scale solidification. Note maximum temperature reached during the 30 seconds of stirring after addition.
Record temperature on CNSI Solidification Worksheet I, Item (b).
ATTACHMENT 2 PAGE 1 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 14 OF 61 ATTACHMENT 2 1.0 SAMPLE VERIFICATION (Continued)
NOTE:
If any foam is created due to the agitation of the waste, then small quantities of a CNSI chemist-approved anti-foam shall be added (less than or equal to 1 ML) while agitating the sample. The total amount of anti-foam added to subside the foam shall not exceed 2% of the total waste volume without prior approval from the SCE Radwaste Supervisor or CNSI Manager of solidification services.
QHP 1.6 Proceed directly with lime addition and using minimum weight for first lime addition, or if experience with the particular waste form indicates that the required pH will be achieved with a quantity of lime different than the minimum indicated on the table, that quantity may be used for the first lime addition. Mix with spatula and check pH with litmus paper to confirm a value of 11 or above. Add more lime if pH is low or if mix is too watery.
QHP 1.7 Transfer entire sample to a 250 ml container using spatula. Attach lid firmly and place sample in oven at 165 + 50F.
HP 1.8 Maintain sealed sample in oven for 6-24 hours according to past experience at that particular utility. Then remove sample from oven and allow to cool for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before unsealing and evaluating solidification results according to guidelines of paragraph 6.3.
NOTE:
The 2-hour cooling period can be deleted if experience with this particular waste stream indicates that no water is standing on the sample and it meets the requirements of paragraph 6.3.
2.0 FULL SCALE CALCULATIONS 2.1 Determine the volume (cubic feet) of waste to be received by completing SCE/CNSI Solidification Worksheet II or according to past experience at the particular utility.
2.2 Be sure that total solidificaton weight and waste radiation level is consistent with allowable transportation regulations and requirements.
ATTACHMENT 2 PAGE 2 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 15 OF 61 ATTACHMENT 2 SCE/CNSI SOLIDIFICATION WORKSHEET I (SW-I)
(PCP SOLIDIFICATION OF BORIC ACID CONCENTRATES)
N-24, CEMENT, LIME SEQUENCE Waste Identification Date:
Operator:
Unit:
Boron Content
__ppm or Boric Acid Content Specific Gravity pH:
Temperature oF (In Waste Tank)
Physical Appearance (color, clarity, sediment)
Sample Preparation Shipment No.
(a)
Volume Of Waste:
ml (b)
Weight of N-24:
gm ( _F)
(c)
Antifoam Agent Required:
Yes No (d) Weight of P-14:
gm (e)
Weight of Cement:
gm (f)
Weight of Lime:
gm pH After Mixing in Lime (g)
Additional Lime Added, If Any:
gm pH After Mixing in Lime (h)
Total Lime Added (f&g) gm Oven Temperature at Start of Test OF Time Sample in Over (Sealed) hrs Oven Temperature When Sample Removed OF Time Outside Oven Before Unsealing hrs ATTACHMENT 2 PAGE 3 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 16 OF 61 ATTACHMENT 2 Solidification Results Free Liquid, If Any ml (Approximate)
Relative Set (Very Hard, Firm, Soft)
Unusual Appearance (Color, Foam, Stratif"ication):
PREPARED BY:
/
Date REVIEW/APPROVED BY:
/
Radwaste Foreman Date ATTACHMENT 2 PAGE 4 OF 9
.NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
..UNIT 1 REVISION 0 PAGE 17 OF 61 ATTACHMENT 2 SCE/CNSI SOLIDIFICATION WORKSHEET II (SW-II)
(Full-Scale solidification of boric acid concentrate)
N-24, Cement, Lime Sequence)
Volume Information Waste Identification Tank:
Date:
Operator:
(a) Usable Liner Volume (Attachment 7)
Ft' (b) Liner Ft3 Inch of Height (Attachment 7) _____Ft'/Inch (c) Waste Volume to be Solidified
_____Ft' (See Note)
NOTE:
MAXIMUM WASTE VOL. (FT 3 =
+ 200 (Round off to next PCP Waste Vol.
lowest 5 Ft' Level) SW-I, Item (a) x (a) x.632 =
Ft 3 Usable Vol.
Waste Calculations (To Nearest Pound)
(d)
Weight of N-24 =
x
+
(Waste Vol.)
PCP Wt. of Add.
PCP Waste Vol.
SW-I, Item (b)
SW-I, Item (a) x 62.4 =
Lbs + 10%
lbs (e)
Weight of P-14 =
x
+
(Waste Vol.)
PCP Wt. of Add.
PCP Waste Vol.
SW-I, Item (b)
SW-I, Item (a) x 62.4 =
Lbs + 10%
lbs (f)
Weight of Cement =
x
+
(Waste Vol.)
PCP Wt. of Add.
PCP Waste Vol.
SW-I, Item (b)
SW-I, Item (a) x 62.4 =
Lbs + 10%
lbs (g)
Weight of Lime =
x (Waste Vol.)
PCP Lime Wt.
PCP Waste Vol.
SW-I, Item (h)
SW-I, Item (a) x 62.4 =
Lbs + 10%
lbs ATTACHMENT 2 PAGE 5 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
.UNIT 1 REVISION 0 PAGE 18 OF 61 ATTACHMENT 2 Weight Calculations (To Nearest Pound)
(h) Weight of Waste =
(c) x 62.4 x 1.02*
=
Lbs.
(Waste Vol.)
- Average Waste Specific for Calculation Purpose.
(i) Estimated Total Wt to be Added = (d)+(e)+(f)+(g)+(h) =
Lbs.
Level Heights (To The Nearest 0.1 Inch)
(j) Waste Alarm Height =
((b)
=
Inches (Waste Vol.)
(V/H Ratio)
(k) Cement Height =
(f)+
173**
(b)
(Cement Wt)
(V/H Ratio)
=
Inches
- Typical True Cement Density, Lbs/Ft3 (1) Cement Alarm Level = (j)
+ (k)
=
Inches (m)
Lime Height =
(
+ 137*** -
(b)
(Lime Wt.)
(V/H Ratio)
=
Inches O (n) Lime Level (Estimated = (1) + (m)
=
Inches
- Typical True Lime Density, Lbs/Ft3 (o) High Level Alarm = (n) + 2 Inches
=
- Inches
- Round Up to Next Nearest Inch.
PREPARED BY:
/
Date REVIEW/APPROVED BY:
/
Radwaste Foreman Date ATTACHMENT 2 PAGE 6 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
.UNIT 1 REVISION 0 PAGE 19 OF 61 ATTACHMENT 2 FIGURE 1 - TYPICAL SAMPLE CALCULATIONS FOR WORKSHEET II (PWR WASTES) 140 cubic feet of waste at 170*F containing 12% un-neutralized boric acid is to be solidified in a 14-195 liner. A satisfactory PCP test was completed using 240 ml of hot waste, 10 gm of N-24, 10 gm of P-14, 130 gm of cement and 70 gm of lime.
(a) Usable Liner Volume (Attachment 7)
= 190 Ft3 (b) Liner Volume/Height Ratio (Attachment 7)
= 2.62 Ft'/Inch (c) Volume of Waste to be Received
= 140 Ft3 NOTE:
Maximum Waste Volume = 240 + 200 x 190 x.632
= 144.1 Ft3 (Round off to 140 Ft3 (d) Weight of Additive N-24 = 140 x 10 + 240 x 62.4
= 364 Lbs (e) Weight of Additive P-14 = 140 x 10 + 240 x 62.4
= 364 Lbs (f) Weight of Cement = 140 x 130 + 240 x 62.4
= 4,732 Lbs (g) Weight of Lime = 140 x 70 + 240 x 62.4
= 2,548 Lbs (h) Weight of Waste = 140 x 62.4 x 1.02
= 8,911 Lbs (i) Estimated Total Weight To Be Added
= 16,891 Lbs (j)
Waste Height = 140 + 2.62
= 53.4 Inches (k) Cement Height = 4332 + 173 + 2.62
= 10.4 Inches (1) Cement Level'= 53.4 + 10.4
= 63.8 Inches (m)
Lime Height = 2548 + 137 - 2.62
= 7.1 Inches (n) Lime Level (Estimated) = 63.8 + 7.1
= 70.9 Inches (o) High Level Alarm = 70.9 + 2
=73 Inches**
- Round up-to next inch NOTE:
Weight (Item i) plus14-195 liner weight (Attachment 8.5) would exceed cask payload weight for a 14-195 cask and shipment utilizing a cask would require a 21-300 cask. Consideration must also be given for, allowable radiation levels in cask selection.
ATTA:HMENT 2 PAGE 7 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
.UNIT 1 REVISION 0 PAGE 20 OF 61 ATTACHMENT 2 FIGURE 1 - CNSI SOLIDIFICATON.WORKSHEET III (SW-III)
(Process Summary - Boric Acid Concentrates)
Unit Operator Waste Tank
- 1. Waste Added:
Start Time Date Estimated Finish Time Date Weight Lbs.
From WS-II, Item (h)
- 2.
Temperature After Waste Added:
OF
- 3.
Agent N-24 Added:
Time Date Weight
+ 10%
lbs
- 4.
Temperature After N-24 Added:
OF
- 5.
Agent P-14 Added:
Time Date Weight
+ 10%
lbs
- 6.
Antifoam Agent Added (If Required) Time Date Vol.
- 7. Cement Added:
Start Time Date Finish Time _____
Date Weight
+ 10%
lbs
- 8.
Temperature after Mixing in Cement:
OF
- 9. Lime Added:
Start Time ______
Date Hydraulic Pressure _psi Finish Time ______
Date Hydraulic Pressure ___psi Weight __Lbs
- 10.
Temperature After All Lime Added:
OF
- 11.
Agitation Stopped:
Time Date Hydraulic Pressure _psi ATTACHMENT 2 PAGE 8 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT I REVISION 0 PAGE 21 OF 61 ATTACHMENT 2 FIGURE 1 - CNSI SOLIDIFICATON WORKSHEET III (SW-III)
(Process Summary -
Boric Acid Concentrates)
(Continued)
- 12.
Initial Temperature After Agitation Stopped OF 6 Hours Later (From Chart Recorder)
OF 12 Hours Later (From Chart Recorder)
OF 24 Hours Later (From Chart Recorder)
OF
- 13.
Peak Temp.:
Time Date
- 14.
Temp. Under 160 0 F:
Time Date
- 15.
Fillhead Removed:
Time _
Date
- 16.
Liner Capped:
Time Date
- 17.
Observations, Additional Comments:
PREPARED BY:
/
Date REVIEWED/APPROVED BY:
/
Radwaste Foreman Date 0275e ATTACHMENT 2 PAGE 9 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 22 OF 61 ATTACHMENT 3 PCP SOLIDIFICATION OF PARTICULATE WASTES (RESIN BEADS, POWOEX, DIATOMACEOUS EARTH SLURRIES, AND OTHER PARTICULATE SLURRIES 1.0 Sample Verification NOTE:
The chemical additives used for PCP preparation should be those actually used in full scale solidification and should be stored in capped containers. The cement and Agent M-5 should be blended together for PCP preparation with a ratio of 2 parts cement to one part Agent M-5 by weight.
1.1 Arrange with the Radwaste Health Physics personnel to assign a special test area which contains adequate protection from the anticipated high radiation levels of bead resins.
1.2 Notify Radwaste Health Physics that the preparations for verification testing have been completed and a waste sample is required.
QHP 1.3 Transfer 100 ml of resin from the sample container to a 250 ml graduated cylinder and allow solids to settle. Control resin bead level at 75-80 ml with 20-25 ml of water on top for the 100 ml sample. Pour the sample into 250 ml disposable beaker.
NOTE 2:
When radiation levels are excessive in accordance with Health Physics Guidelines, the sample amount may be reduced to as little as 25 ml.
Be sure to reduce other additives by the same ratio.
QHP 1.4 Measure and record on SCE/CNSI Solidification Worksheet the waste pH, using the wide range pH paper.
NOTE 3:
If pH of waste is above 10.5, it will not be necessary to use alkaline agents (i.e., lime).
However, if the pH is less than 10.5, add lime in accordance with paragraph 1.4.1 until pH is about 11.0 prior to adding cement and Agent M-5 in accordance with paragraph 1.5.
1.4.1 Add lime (CA(0H) 2) in 0.5 gm increments until a pH of approximately 11.0 is reached. The pH should be evaluated using a narrow range (9-13) pH paper. Stir thoroughly after each addition of lime. Record the total amount of lime added on SCE/CNSI Solidification Worksheet I for particulate wastes.
ATTACHMENT 3 PAGE 1 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 23 OF 61 ATTACHMENT 3 1.0 Sample Verification (Continued)
QHP 1.5 Add cement/agent M-5 blend (ration of 2 parts cement to one part Agent M-5 by weight) slowly (e.g., increments of <10 gms) while stirring until a smooth homogeneous mix is obtained. The amount added for a 100 ml waste sample may be 95 to 110 gms depending on resin type, and amount of water in the slurry. Record amount of cement/agent M-5 blend added on the SCE/CNSI Solidification Worksheet.
NOTE 4:
Do not exceed 110 grams of cement/agent M-5 blend without authorization of the SCE Radwaste Supervisor or CNSI Manager of Solidification Services. If mixture becomes too thick before 95 grams of cement/agent M-5 blend has been added, add additional water as necessary to allow a maximum of 95 grams of binder (cement/agent M-5 blend) to be mixed to a smooth homogeneous mix.
Full scale waste volume calculations must include the water as part of waste volume.
HP 1.6 Place the lid over the beaker and store the sealed mix in an oven controlled at 120-130 0 F for 18-24 hours. Then allow to cool for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before removing lid and evaluating solidification.
1.7 Evaluate the sample using the guidelines of paragraph 6.3. If the sample does not meet the acceptance criteria, contact the CNSI Supervisor, Solidification Services, and SCE Radwaste Supervisor, for possible formula modifications.
2.0 Full Scale Calculations (Bead-type of particulate wastes) 2.1 Determine the volume of waste material to be received and the amounts of cement and lime required by completing the SCE/CNSI Solidification Worksheet for bead-type of particulate wastes. Reduce the calculated amounts as necessary to comply with weight and radiation limitations imposed by waste activity and shielding requirements.
ATTACHMENT 3 PAGE 2 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 24 OF 61 ATTACHMENT 3 SCE/CNSI SOLIDIFICATION WORKSHEET I (SW-I)
(PCP Solidification of Particulate Wastes) aste Identification Date:
Operator:
Unit:
Type of Waste:
(Resin Beads, Powdex, Sludge)
Waste Activity: (Reported Curie Content) pH:
(Reported by Utility)
==
Description:==
(Color, Uniformity, Free Liquid)
Sample Preparation (a)
Volume of Waste (In 250 ml Container):
ml resin; ml total water + resin (Notes 1 and 2)
NOTE 1:
The volume of fluidized waste must be controlled as nearly as possible to the 100 ml mark in the graduated cylinder and contain 75-80 ml of resin beads with 20-25 ml of water on top of beads.
Remove water from or add water to the waste sample received as necessary to acquire the right level.
NOTE 2:
If the radiation level of the waste prevents using a 100 ml sample, the test may run with less waste material, but the CNSI Solidification Supervisor must be contacted for verification of the full-scale formula.
(b) pH of sample:
(Tested By CNSI)
NOTE 3:
If pH of waste is above 10.5, it will not be necessary to use alkaline agents. However, if the PCP sample fails to solidify in the required time, notify CNSI Solidifi.cation Supervisor or Manager and add lime until pH is about 11.0 prior to adding cement/agent M-5 blend.
Without previous history, use lime as the preferred alkaline agent.
(c) pH Adjustment (If Necessary) (Add lime in 0.5 gm increments):
Total Lime Added gm; Final pH NOTE 4:
Add cement/agent M-5 slowly (e.g., increments of < 10 gms).
DO NOT EXCEED 110 grams of cement/agent M-5 blend per 100 ml of waste without authorization of SCE Radwaste Supervisor of CNSI Manager of Solidification Services. If mixture becomes too thick before 95 grams of cement/agent M-5 blend has been added, add additional water as necessary in 1 ml increments to allow a maximum of 95 grams of binder (cement/agent M-5 blend) to be mixed to a smooth homogenous mix.
ATTACHMENT 3 PAGE 3 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 25 OF 61 ATTACHMENT 3 Sample Preparation (Continued)
- d)
Cement/Agent M-5 Blend Added to Obtain Smooth, Uniform Mix NOTE 5:
Add up to 95 gms; then continue to add cement/agent M-5 blend in approximately 2 gm increments (if possible) until one of the following occurs:
(1) The sample becomes too thick to mix (at which point, stop addition of binder (cement/agent M-5 blend) and record the total binder added; or (2) The total weight of cement/agent M-5 blend added reaches 105-110 gms (do not exceed 110 gms).
Record total binder added.
gms (e)
Total Additional Water Added (If Necessary) (Add in 1 ml increments):
ml Oven Temperature at Start of Test-OF Time Sample in Oven (Sealed):
hrs; Date:
Oven Temperature When Sample Removed:
OF Time Outside Oven Before Unsealing:
hrs; Date:
NOTE 6:
Allowable oven temperature range is 120 0-130 0 F.
.olidification Results Free Liquid, If any:
ml (Approximate)
Relative Set (Very Hard, Firm, Soft):
Unusual Appearance (Color, Foam, Stratification):
(f) Repeat the PCP for a second sample using only 95gms of the Cement/Agent M-5 Blend.
Cement/Agent M-5 Blend:
gm Additional Water Added (If Required):
ml Lime Added (If Necessary):
ml Oven Temperature at Start of Test:
__OF Time Sample in Oven (Sealed):
hrs; Date:
Oven Temperature When Sample Removed:
OF Time Outside Oven Before Unsealing:
hrs; Date:
ATTACHMENT 3 PAGE 4 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 26 OF 61 ATTACHMENT 3 olidification Results Free Liquid, If any:
ml (Approximate)
Relative Set (Very Hard, Firm, Soft):
Unusual Appearance (Color, Foam, Stratification):
PREPARED BY:
/
Date REVIEWED/APPROVED BY:
/
Radwaste Foreman, or Designee Date ATTACHMENT 3 PAGE 5 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 27 OF 61 ATTACHMENT 3
.SCE/CNSI SOLIDIFICATION WORKSHEET II (SW-II)
(Full-Scale Solidification of Particulate Wastes)
NOTE 1:
This worksheet is intended to provide a solidification formula consistent with the waste liner selected. The amounts of additives required are for calculation purposes only, and do not restrict the quantities actually added to achieve an acceptable solidification product.
NOTE 2: A line-by-line explanation of this worksheet is provided at the end of the worksheet.
Date:
Operator:
Unit:
a) Useable Liner Volume (LV) (Attachment 7):
LV =
ft3 b) Volume to Height (V/H) ratio (Attachment 7):
V/H =
ft3 /in c)
Waste Volume to Binder (WV/B) ratio (Attachment 7): WV/B =
d) Waste Volume (WV) =.a x c WV=
x WV =
ft3 e)
Waste Alarm Height (WAH) = d b
WAH =
+
WAH =
in.
Water Volume Factor (WtVF) (Attachment 7):
WtVF =
g) Water Volume (WtV) = a x f WtV=
x WTV =
ft3 h) Process Volume (PV) d + g PV=
+
PV =
ft3 i) Additional Water volume (AWV) added to PCP sample (from Worksheet I (SW-I), item e):
AWV =
ml j) Additional Water Volume-Liner (AWV-L) = i x h x 0.01 AWV-L =
x x 0.01 AWV-L =
ft3 k) Line Weight (LW) added to PCP sample (from Worksheet I (SW-I), item c):
LW =
gms ATTACHMENT 3 PAGE 6 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT. 1 REVISION 0 PAGE 28 OF 61 ATTACHMENT 3 Lime Weight - Liner (LW-L) = h x k x 0.623 LW-L =
x _
x 0.623 LW-L =
lbs (allowable deviation = + 10% =
lbs) m)
Lime Height (LH)
= [1 + b] + 137 LH = [
]
137 LH =
in.
n) Cement/Agent M-5 weight (CMW) added to PCP sample (from Worksheet I (SW-I), item d):
CMW =
gms o) Agent M-5 Weight-Liner (MW-L) = n x h x 0.208 MW-L =
x x 0.208 MW-L =
1_bs (Allowable deviation = + 10% =
1bs) p)
Agent M-5 Weight (MH) = o + 6 + 173 MH=
+
+ 173 MH =
in.
q) Water Height above waste level in liner (WtH-L):
WtH-L =
[g + j] + b WtH-L = [
+
]
+
WtH-L =
in.
r) Water Height in mix tank (WtH-T):
WtH-T
[g + j]
z 1.53 WtH-T
[
+
]
+ 1.53 WtH-T =
in.
s) Total Mix Tank Height (MTH) = r + [o + 264.7]
MTH =
in.
+
[
+
264.7]
t)
Cement Weight -
Liner (CW-L) = 2 x o CW-L = 2 x CW-L =
lbs (Allowable deviation = + 10% =
lbs) u) Cememt Height (CH = 2 x p CH = 2 x CH =
in.
v)
Cement Alarm Height (CAH) = e + m + p + q + u CAH=
+
+
+
+
CAH =
in.
w)
Liner High Alarm Level (HAL) = v + 2 HAL = ____
+ 2 (round to the next highest inch)
HAL =
in.
0 ATTACHMENT 3 PAGE 7 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNI-T 1 REVISION 0 PAGE 29 OF 61 ATTACHMENT 3 x) Solidification Process
- 1)
Fill mix tank to r inches (
inches) with water.
- 2)
Energize mixer.
- 3)
Slowly add o lbs (
lbs +
lbs) of agent M-5 to mix tank. Do not exceed total mix Tank Height (item s above).
- 4)
Slowly add t lbs (
lbs +
lbs) of cement to liner along with agent M-5 and water slurry.
DO NOT EXCEED
/
Liner High Alarm Level (item w above).
y) Approximate Weight Calculation of Solidification Liner Sum the following:
- 1)
Liner Weight (Attachment 7):
W =
lbs
- 2)
Water Weight (WtW) = [g + j] x 62.4 WtW =
[
+
]
x 62.4 WtW =
lbs
- 3)
Agent M-5 Weight Liner (item o)
MW-L =
lbs
- 4)
Cement Weight-Liner (item t)
CW-L =
lbs
- 5)
Lime Weight-Liner (item 1)
LW-L =
lbs
- 6) Resin Weight (RW) = d x 70 RW_=
x 70 RW =
lbs
- 7)
Total Weight (TW) = sum of 1-6 above TW =
lbs PREPARED BY:
/
Solidification Operator /
Date VERIFIED BY:
/
Radwaste Foreman, or
/
Date Designee APPROVED BY:
/
Radwaste Foreman
/
Date ATTACHMENT 3 PAGE 8 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 30 OF 61 ATTACHMENT 3 Explanation of Worksheet II (SW-II) a) Useable Liner Volume (LV):
From Attachment 7 b) Volume Height (V/H) ratio:
From Attachment 7 c) Waste Volume to Binder (WV/B) ratio:
From Attachment 7 d) Waste Volume (WV) = Liner Volume x Waste Volume to Binder Ratio e) Waste Alarm Height (WAH) = Waste Volume + Volume to Height Ratio f) Water Volume Factor (WtVF): From Attachment 7 g) Water Volume (WTV) = Liner Volume X Waste Volume Factor h) Process Volume (PV) = Waste Volume + Water Volume i) Additional Water Volume (AWV) added to PCP (from Worksheet I [SW-I], item e) j) Additional Water Volume in Liner (AWV-L) = Additional Water Volume (AWV) x Process Volume x 0.623 (Note A) + 62.4 (Note B)
NOTE A:
A factor converting gms PCP additive weight per 100 ml waste sample to pounds required per ft' of waste.
NOTE B:
A factor to convert pounds to ft3.
k)
Lime Weight (LW) added to PCP sample (from Worksheet I [SW-I], item c)
- 1)
Lime Weight in Liner (LW-L) = Process Volume x Lime Weight m)
Lime Height (LH) = Lime Weight in Liner (LW-L) + Volume to Height ratio (V/H) + 137 (Note C)
NOTE C:
Approximate fluid lime density, lbs/ft' n) Cement/Agent M-5 Weight (CMW) added to PCP sample (from Worksheet I [SW-I],
item d) o) Agent M-5 Weight in Liner (MW-L) = Cement/Agent M-5 Weight (CMW) x Process Volume x 1/3 (Note D) x 0.623 NOTE D:
1/3 is the M-5 component of the 2 to 1 cement/M-5 ratio.
p)
Agent M-5 Height (MH) - Agent M-5 Weight in Liner (MW-L) + Volume to Height ratio (V/H) + 173 (Note E)
NOTE E:
Typical true agent M-5 Density, lbs/ft'.
ATTACHMENT 3 PAGE 9 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 31 OF 61 ATTACHMENT 3
)
Water height above waste level in liner (WtH-L) =
[Water volume + Additional Water Volume in Liner (AWV-L]: +
Volume to Height ratio (V/H) r) Water Height in Mix Tank (WtH-T) = [Water Volume + Additional Water.Volume in Liner (AWV-L)] + 1.53 (Note F)
NOTE F:
Volume to Height ratio in Mix Tank.
s) Total Mix Tank Height (MTH) = Water Height in Mix Tank (WtH-T) +
[Agent M-5 Weight in Liner (MW-L)] + 173 + 1.53 t) Cement Weight in Liner (CW-L) = twice the Agent M-5 Weight in Liner (MW-L) based on the 2 to 1 cement to M-5 ratio u) Cement Height (CH).= twice the Agent M-5 Height based on the 2 to 1 cement to M-5 ratio v) Cement Alarm Height (CAH) = the combined heights of waste alarm height, lime height, Agent M-5 height, water height above waste level, and cement height w)
Liner High Alarm Level (HAL) = 2 inches higher than cement alarm height ATTACHMENT 3 PAGE 10 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 32 OF 61 ATTACHMENT 3 SCE/CNSI SOLIDIFICAITON WORKSHEET III (SW-III)
(PROCESS
SUMMARY
PARTICULATE WASTES Unit:
Operator:
Waste Tank:
- 1. Waste Slurry Addition No. 1:
Start Time Date Finish Time Date
- 2. Dewatering No. 1, If Necessary:
Start Time Date Finish Time Date
- 3. Waste Slurry Addition No. 2, If Necessary:
Start Time Date Finish Time Date
- 4. Dewatering No. 2, If Necessary:
Start Time Date Finish Time Date IS TE 1:
Waste Slurry to be at the waste volume Item C of Solidification Worksheet II and water level initially even with top of resin.
- 5.
Waste Temperature After Mixing:
OF
- 6. Actual Amount of Lime Added (if necessary):
Start Time Date Finish Time Date Weight lbs NOTE 2:
Lime addition must be within + 10% of solidification worksheet II item (L).
Net excess of lime and M-5/cement slurry should not exceed volume of container.
- 7.
Temperature After Mixing in Lime (if necessary):
OF
- 8.
Time and Date Agent M-5 Slurry Prepared:
Time Date
- 9.
Weight of Agent M-5 in Slurry:
lbs ATTACHMENT 3 PAGE 11 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT.1 REVISION 0 PAGE 33 OF 61 ATTACHMENT 3
- 0. Time and Date Agent M-5 Slurry Actually Added:
Start Time Date Finish Time Date NOTE 3:
When visual (TV camera) observation shows a fluid mix, cement addition may begin while adding agent M-5 slurry.
- 11.
Cement added:
Start Time Date Finish Time Date Weight lbs NOTE 4:
M-5/cement addition must be within + 10% of solidification worksheet II item (o) and (t).
Net excess of lime and M-5/cement slurry should not exceed volume of container.
- 12.
Additional Cement Added, If Necessary:
lbs
- 13.
Temperature After All Cement Added:
OF
- 14.
Agitation Stopped:
Time Date
- 15.
Initial Temperature After Agitation Stopped OF 6 Hours Later (From Chart Recorder)
OF 12 Hours Later (From Chart Recorder)
OF 24 Hours Later (From Chart Recorder)
OF
- 16.
Peak Temperature Time Date
- 17.
Fillhead Removed Time Date
- 18.
Liner Capped Time Date
- 19. Observations and Additional Comments:
PREPARED BY:
/
Solidification Operator
/
Date REVIEWED BY:
/
Radwaste Foreman
/
Date 0275e AT~:A:HMFNT 3 PAGE 12 OF 12
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 34 OF 61 ATTACHMENT 4 PCP FOR PREPARATION OF FLUID MIXTURE FOR IN-SITU SOLIDIFICATIONS 1.0 Sample Verification NOTE:
The chemical additives for PCP preparation should be those actually used in full-scale solidifications and should be stored in capped containers. The sequence for chemical addition for PCP and full scale solidification shall be the same.
1.1 Secure representative samples of all components to be used in the actual solidification.
QHP 1.2 To a 600-1000 ml plastic beaker, weigh in the dry materials listed and record values on SCE/CNSI Solidification Worksheet (for In-Situ Solidifications).
Portland Cement 200 gm CNSI Agent M-5 100 gm QHP 1.3 Add water to the dry ingredients and mix well with spatula.
Control the flow characteristics of the mix to a smooth, fluid consistency, record the weight of water added. Normally 125-150 gm of water will be required.
NOTE:
The requirement for IN-SITU solidification is a cement composition that can be pumped as a fluid, but will set hard with little or no bleed liquid after placement. The proper consistency is best described as a "heavy cream to a soft ice cream" texture. Adjust water added as necessary to obtain desired texture.
1.4 After confirming the proper weight of M-5/cement needed to control the flow characteristics of the mix, note this value on the SCE/CNSI Solidification Worksheet (for In-Situ Solidifications.)
1.5 Transfer fluid cement mixture to a 250 ml container to about 1/4 inch of the top, and then attach lid firmly.
HP 1.6 Place sealed container in an oven controlled at about 130-1400 F for 18-24 hours.
Then remove the container and allow to cool before unsealing. Examine product and record approximate volume of free liquid, if any, and the apparent relative hardness.
ATTACHMENT 4 PAGE 1 OF 4
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
'UNIT I REVISION 0 PAGE 35 OF 61 ATTACHMENT 4 1.0 Sample Verification (Continued)
NOTE: If an oven is not available, the test solidification may be completed at warm room temperature (75-850 F), but-will not necessarily give the same results over the same time period.
Small samples do not retain the normal exothermic heat of cement hydration that accelerates hardening of bulk mixtures.
2.0 Determine the volume of waste material to be received and the amounts of cement, lime, sodium sulfate, and boric acid required by completing SCE/CNSI Solidification Worksheet for In-SitU.Solidifications. Chemical amounts may be changed with supervisor approval as necessary to comply with weight and radiation limitations imposed by waste activity and shielding requirements.
NOTE:
The cement encapsulation mixture employed by CNSI represents a controlled formula that has been tested for strength and resistance to water degradation. The test results for simular mixtures containing waste products demonstrate that all requirements to 10 CFR 61 are satisfied.
ATTLCHMENT 4 PAGE 2 OF 4
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT-.1 REVISION 0 PAGE 36 OF 61 ATTACHMENT 4 SCE/CNSI SOLIDIFICATION WORKSHEET I (SW-I)
FULL-SCALE IN-SITU SOLIDIFICATION OF SUSPENDED OBJECTS Shipment No.
Volume and Weight Constants L6-80 L8-120 L14-170 L14-195 (a) Internal Liner Height 54" 71.5" 69.3" 75.5" (b) Total Liner Volume (FT) 82 174 174 196 (c) Volume Of Expanded Metal Cage (FT')
38.2 59.7 98.5 110 (d) Liner V/H Ratio (Ft'/In) 1.53 1.69 2.52 2.62 NOTE:
The waste volume added to the cage will vary with object size, type, and number loaded. The technician must estimate waste volume. Typically this will be 40-70% of cage volume. The estimated waste volume is a critical number and should be conservative to the low side volume.
- 1. Calculate the volume of wet cement mixture required.
(
Ft)
) -
) =
Ft3 Tot. Liner Vol.
2 x V/H Ratio Est. Waste Vol.
Mix Vol.
- 2.
Weight of Water Added to PCP =
gm
.PCP Volume:
+
2.77) + (
+2.77) =
ml PCP gm H2 0 PCP gm cement PCP gm M-5
- 4. Water Volume:
(+)x
_______x 7.48 =
gal. water PCP gm H20 PCP volume mix volume (Item 3)
(Item 1)
- 5. Water Height for M-5 Mix Tank for Slurry:
x 2/3 + 7.48 + 1.53 =
inches + 1/2 inch Water volume gal/ft3 V/H ratio (Item,4)
Mix tank
- 6. Agent M-5 Weight:
+ 2.77 +
x x 173 =
lbs M-5 +
10%
Mix Vol.
(Item 3)
(Item 1)
ATTACHMENT 4 P/GE 3 OF 4
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT.1 REVISION 0 PAGE 37 OF 61 ATTACHMENT 4
- 7. Additional Water Height for Addition to M-5 mix tank:
ater Volume x 1/3 + 7.48 + 1.53 =
inches + 1/2 inch (Item 4)
- 8. Cement Weight:
+ 2.77 +
x x 173 =
lbs cement lb PCP gm cement PCP Vol.
Mix Vol.
+ 10%
(Item 3)
(Item 1)
Add water (Item 5) to Agent M-5 slurry tank, start mixer and add Agent M-5 (Item 6) to make slurry. Pump slurry into in-situ mix tank. Add (Item 7) additional water volume as water to flush Agent M-5 slurry tank into in-situ mix tank. The total water used (Item 4) in the in-situ mix must be added as either Agent M-5 slurry or flush water.
PREPARED BY:
/
Date REVIEWED/APPROVED BY:
/
Radwaste Foreman Date
- 275e ATTACHMENT 4 PAGE 4 OF 4
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 38 OF 61 ATTACHMENT 5 PCP Solidification of Particulate Wastes (Class A Unstable Waste Form Only)
(Resin Beads, Powdex, Diatomaceous Earth Slurries), and Other Particulate Wastes 1.0 Sample Verification NOTE:
The chemical additives used for PCP preparation should be those actually used in full scale solidification and should be stored in capped containers. The sequence for chemical addition for PCP preparation and full scale solidification shall be the same.
1.1 Arrange with Radwaste Health Physics personnel to assign a special test area which contains adequate protection from the anticipated higher radiation levels of bead resins.
1.2 Notify Radwaste Health Physics personnel that the preparations for verification testing have been completed and that a waste sample is required.
QHP 1.3 Transfer 100 ml of resin from the sample container to a 250 ml disposable beaker and allow solids to settle. Typically, there will be a layer of water on top of the resin beads. Centrifuged powdex will show no separation of liquid.
NOTE:
When radiation levels are excessive in accordance with the utility guidelines, the sample amount may be reduced to as little as 25 ML. Be sure to reduce other additives by the same ratio.
QHP 1.4 Measure and record on CNSI Solidification Worksheet the waste pH using the wide range pH paper. Add lime (Ca(OH)2) in 0.5 gm increments until pH of 10.5 to 11.5 is reached by narrow (9-13) range pH paper. Stir thoroughly after each addition of lime and add 3 more grams after the desired pH range is reached. Record the total amount of lime added on SCE/CNSI Solidification Worksheet I for particulate wastes.
QHP 1.5 Add cement slowly (e.g., increments of < 10 gms) while stirring until a smooth homogeneous mix is obtained. The amount added for a 100 ml waste sample may be 80 to 150 gms depending on resin type, quantity of lime added and amount of water in the slurry.
Record amount of cement added on the CNSI Solidification Worksheet.
HP 1.6 Place the lid over the beaker and store the sealed mix in an oven controlled at 1200 - 130 0 F for 18-24 hours. Then allow sample to cool for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before removing lid and evaluating solidification.
ATTACHMENT 5 PAGE 1 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 39 OF 61 ATTACHMENT 5 1.0 Sample Verification (Continued) 1.7 Evaluate the sample using the guidelines of Paragraph 6.3. If the sample does not meet the acceptance criteria, contact Supervisor, Solidification Services for possible formuTa modifications.
2.0 Full Scale Calculations (Bead-Type or Particulate Wastes) 2.1 Determine the volume of waste material to be received and the amounts of cement and lime required by completing the CNSI Solidification Worksheet for bead-type or particulate wastes.
Reduce the calculated amounts as necessary to comply with weight and radiation limitations imposed by waste activity and shielding requirements.
ATTACHMENT 5 PAGE 2 OF 9
.NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 40 OF 61 ATTACHMENT 5 SCE/CNSI SOLIDIFICATION WORKSHEET I (PCP Solidification of Particulate Wastes)
Class A Unstable Waste Form Only Waste Identification Date:
Operator:
Unit:
Type of Waste:
(Resin Beads, Powdex, Sludge)
Waste Activity: (Reported Curie Content) pH (Reported by Utility)
==
Description:==
(Color, Uniformity, Free Liquid)
Sample Preparation Shipment No.
(a) Volume of Waste (In 250 ml Container):
ml (Notes 1 and 2)
NOTE 1:
The volume of fluidized waste must be controlled as nearly as possible to the 100 ml mark in the 250 ml test beaker, since full-scale calculations are normally figured on this amount. Remove water from, or add water to, the waste sample received as necessary so that a fluid material is formed.
No more than about 1/16-1/8-inch of liquid should separate quickly from the 100 ml test sample.
NOTE 2:
If the radiation level of the waste prevents using a 100 ml sample, the test may be run with less waste material, but the solidification supervisor must be contacted for verification of the full-scale formula.'
(b) pH of Sample:
(Tested by CNSI)
(c) pH Adjustment Summary Increment Amount pH After Mixing 1
2 3
4 (d) Total Lime Added gm (e) Cement Added gm NOTE 3:
Do not exceed 100 grams of cement per 100 ml of waste unless an earlier test using the same waste sample indicated that more cement was required. Add cement slowly (e.g., increments of <l0gms).
Oven Temerature at Start of Test OF Time Sample in Oven (Sealed) hrs.
Oven Temperature When Sample Removed OF Time Outside Before Unsealing nrs.
ATTACHMENT 5 PkG: 3 O' 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
-UNIT 1 REVISION 0 PAGE 41 OF 61 ATTACHMENT 5 SCE/CNSI SOLIDIFICATION WORKSHEET I (PCP Solidification of Particulate Wastes) (Continued)
Class A Unstable Waste Form Only (f) Repeat the PCP using 90% of the lime (Item d) and 90% of the cement (Item e).
- Lime Added gm (90% of Item d)
- Cement Added gm (90% of Item e)
Oven Temerature at Start of Test OF Time Sample in Oven (Sealed) hrs.
Oven Temperature When Sample Removed OF Time Outside Before Unsealing hrs.
Solidification Results Free Liquid, if any ml (approximate)
Relative Set (Very Hard, Firm, Soft)
Unusual Apperance (Color, Foam, Stratification)
PREPARED BY:
/
Date REVIEWED/APPROVED BY:
/
Radwaste Foreman Date ATTACHMENT 5 PAGE 4 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 42 OF 61 ATTACHMENT 5 SCE/CNSI SOLIDIFICATION WORKSHEET II (Full-Scale Solidification of Particulate Wastes)
Class A Unstable Waste Form Only NOTE:
This worksheet is intended to provide a solidification formula consistent with the waste liner selected. The amounts of additives required are for calculation purposes only, and do not restrict the quantities actually added to achieve an acceptable solidification product.
Volume Information Date:
Operator:
Unit:
Shipment No.
(a) Usable Liner Volume (Attachment 7)
Ft' (b) Liner Ft'/Inch of Height (Attachment 7)
Ft'/Inch Waste Alarm Height (To the nearest 0.1 inch).
(c) Waste Volume =
(a) x 0.643* =
_ Ft2 (Liner Vol.)
- A factor providing for 2.5 to 1.0 waste volume to binder ratio, and a 10% volume allowance for additional cement, if required, to assure a satisfactory mix.
Express results to the nearest cubic foot.
NOTE:
For particulate waste slurries where the water content is consistently controlled (such as by centrifugation), it may be possible to increase waste volume as long as the PCP product is clearly satisfactory as concerns hardness and absence of free-standing liquid. Any such increase must be approved by the manager, solidificaiton services prior to implementation.
(d) Waste Alarm Height =
(c
+
(b) =Inches Waste Vol.) -
(V/H Ratio)
Lime Weight and Height (Nearest Lb. and 0.1 Inch)
(If lime is not to be used, this section is N/A.)
(e) Lime WT. =gm x 0.623** x (c) =
Lbs. + 10%
Lbs.)
SW I, (f) Lime (Waste Vol.)
(f) Lime Height =
(e) 137*** +-
(b)
=
Inches (Lime WT.)
(V/H Ratio)
- Approximate fluid lime density, Lbs./Ft' ATTACHMENT 5 PAGE 5 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 43 OF 61 ATTACHMENT 5 NOTE:
This is to verify that an acceptable product will be produced even with significant unanticipated reduction of chemical addition. An excess of chemicals within acceptable liner volume will not hinder the solidification process.
Cement Weight and Alarm Height (Nearest Lb. and 0.1 inch)
(g) Cement WT. =gm x 0.623** x (c)=
Lbs. +10% (
Lbs)
SW I, (g)
(Waste Vol.)
- A factor converting grams PCP additive weight per 100 ml waste sample to pounds required per Ft3 waste.
(h) Cement Height =
(g)+
173****(
=
__(b) Inches
- Typical true cement density, Lbs/Ft3 (i) Cement Alarm Height -
(d)+(f)+(h)
=
Inches
- When using a cyclonaire transfer system, the estimated number of transfers
=
lbs. of cement required + ____ lbs./transfer =
transfers.
PREPARED BY:
/
Date VERIFIED BY:
/
Date APPROVED BY:
/
Radwaste Foreman Date ATTACHMENT 5 PAGE 6 CF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 44 OF 61 ATTACHMENT 5 TYPICAL SAMPLE CALCULATIONS FOR WORKSHEET II (Particulate Wates)
Class A Unstable Waste Form Only A slurry of radioactive mixed bed resin beads is to be dewatered and solidified in a L6-80 liner. After adjusting a laboratory sample so that 100 ml of fluidized material was measured for testing, it was found that four (4) portions of lime (2 grams each) raised the pH to about 11.
Addition of three more grams of lime and 90 grams of cement formed a smooth mix, which set firm and dry in the sealed container after 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> in an oven controlled at about 125 0 F.
(a) Usable Liner Volume (Fig. 4)
= 79 Ft3 (b) Liner Volume/Height Ratio (Fig. 4)
= 1.53 Ft'/Inch (c) Waste Volume -
79 x 0.643
= 51 Ft' (d) Waste Alarm Height = 51 + 1.53
= 33.3 Inches (e) Lime Weight = 11 x 0.623 x 51
= 350 Lbs.
(f) Lime Height = 350 - 137 + 1.53
= 1.7 Inches (g) Cement Weight 90 x 0.623 x 51
= 2860 Lbs.
(h) Cement Height = 2860 + 173 + 1.53
= 10.8 Inches (i) Cement Alarm Height = 33.3 + 1.7 + 10.8
= 45.8 Inches ATTACHMENT 5 PAGE 7 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 45 OF 61 ATTACHMENT 5 SCE/CNSI SOLIDIFICATION WORKSHEET III (Process Summary -
Particulate Wastes)
Class A Unstable Waste Form Only Unit:
Operator:
Waste Tank:
- 1.
Wate Slurry Addition No. 1:
Shipment No.:
Start Time Date Finish Time Date
- 2. Dewatering No. 1, If Necessary:
Start Time Date Finish Time Date
- 3. Waste Slurry Addition No. 2, If Necessary:
Start Time Date Finish Time Date
- 4. Dewatering No. 2, If Necessary:
Start Time Date Finish Time Date
- 5. Water Added to Refluidize, If Necessary:
Estimated Volume Time Date Added Gal.
NOTE:
Waste height must be within + 1 inch of solidification worksheet II Item (d).
- 6. Waste Temperature After Mixing:
_____OF
- 7. Lime Added:
NOTE:
Lime addition must be within + 10% of solidification Worksheet II Item (e).
Net excess of lime and cement should not exceed volume of container.
Start Time Date Finish Time Date Weight Lbs.
ATTACHMENT 5 PAGE 8 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 46 OF 61 ATTACHMENT 5
- 8. Temperature After Mixing In Lime:
OF NOTE:
Cement addition must be within + 10% of solidification Worksheet II Item (g).
Net excess of lime and cement should not exceed volume of container.
- 9.
Cement Added:
Start Time Date Finish Time _Date Weight Lbs.
- 10. Additional Cement Added, If Necessary:
Lbs.
- 11.
Temperature After All Cement Added:
OF
- 12.
Agitation Stopped:
Time Date
- 13.
Initial Temperature After Agitation Stopped _OF 6 Hours Later (From Chart Recorder)
OF 12 Hours Later (From Chart Recorder)
OF 24 Hours Later (From Chart Recorder)
OF
- 14.
Peak Temperature Time Date
- 15.
Fillhead Removed Time Date
- 16.
Liner Capped Time Date
- 17.
Observations, Additional Comments:
PREPARED BY:
/
Date REVIEWED/APPROVED BY:
/
Radwaste Foreman Date 0275e ATTACHMENT 5 PAGE 9 OF 9
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
- UNIT 1 REVISION 0 PAGE 47 OF 61 ATTACHMENT 6 PCP SOLIDIFICATION OF MISCELLANEOUS AQUEOUS WASTES NOT REPRESENTING TYPICAL CONCENTRATES)
Class A Unstable Waste Form Only 1.0 SAMPLE VERIFICATION NOTE:
The chemical additives used for PCP testing should be those actually used in full scale solidification and should be stored in capped containers.
1.1 Notify the Radwaste Health Physics personnel that preparations for verification testing have been completed and that a sample is required.
QHP 1.2 Measure out 200 ml of radwaste sample in a 600-1000 ml disposable container. Then vigorously agitate to determine if foaming may occur in the full scale solidification.
NOTE:
If any foam is created due to the agitation of the waste, then small quantities of a commercially available antifoam shall be added (less than or equal to 1 ml) while agitating the sample.
The total amount of antifoam added to subside the foam shall not exceed 2% of the total waste volume without prior approval from the supervisor or manager of solidification II services and the SCE radwaste supervisor.
QHP 1.3 Add 120 to 140 grams of Portland Cement and mix well with spatula.
QHP 1.4 Add 80 to 100 grams of lime and mix well with spatula.
NOTE:
On a new waste sample, start with minimum quantities of cement and lime to form a smooth mix not producing excessive bleed liquid.
1.5 Transfer (pour) sample mixture into 250 ml plastic beaker, filling to within 1/4 inch of the top.
HP 1.6 Press lid tightly over sample container and store in an approved constant-temperature oven. The sealed sample should be held at 120-130 0 F for 18-24 hours.
NOTE:
It is necessary to hold sample mixtures at elevated temperatures to simulate solidification conditions of full scale operations.
ATTACHMENT 6 PAGE 1 OF 7
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
,UNIT 1 REVISION 0 PAGE 48 OF 61 ATTACHMENT 6 1.0 SAMPLE VERIFICATION (Continued)
HP 1.7 Remove sample from oven and allow to cool for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before unsealing. Evaluate solidification using guidelines of paragraph 6.3.
1.8 Contact the CNSI Supervisor, Solidification Services, and the SCE Radwaste Supervisor, if the test sample containing maximum amounts of cement and lime still fails to meet solidification requirements. A significant change in typical cement to lime ratio or reformulation with an approved additive may be necessary.
2.0 FULL SCALE CALCULATIONS 2.1 Determine the volume (cubic feet) of waste to be received, referring to the table in Attachment 7 for usable liner volumes.
2.2 Complete the SCE/CNSI Solidification Worksheet II for Miscellaneous Aqueous wastes to determine actual chemical requirements and level control settings.
ATTACHMENT 6 PAGE 2 OF 7
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 49 OF 61 ATTACHMENT 6 SCE/CNSI SOLIDIFICATION WORKSHEET I (PCP Solidification of Miscellaneous Aqueous Wastes)
(Not Representing Typical PWR Concentrates)
(Class A Unstable Waste Form Only)
Waste Identification Date:
Operator: __
Shipment #
Solids Content (If Known) ppm or Weight%
Principal Mineral Ions (If Known)
(Such as Calcium, Sodium, Sulfate Chloride, etc.)
Specific Gravity pH Temperature oF (In Waste Tank)
Physical Appearance (color, clarity, sediment)
Sample Preparation (a)
Volume of Waste:
ml (b)
Weight of Cement:
gms (c)
Weight of Lime gs
)
Weight of Other Additive, if used gs I*
Additive Name or Code #
Oven Temperature at Start of Test OF Hours Sample In Oven (Sealed)
Oven Temperature When Sample Removed OF Hours Outside Oven Before Unsealing Solidification Results Free Liquid, If Any:
ml (Approximate)
Relative Set (Very Hard, Firm, Soft)
Unusual Appearance (color, foam, stratification)_________________
PREPARED BY:/
Date REVIEWED/APPROVED BY:/
Radwaste Foreman Date ATTACHMENT 6 PAGE 3 OF 7
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT.1 REVISION 0 PAGE 50 OF 61 ATTACHMENT 6 SCE/CNSI SOLIDIFICATION WORKSHEET II (Full Scale Solidification Of Miscellaneous SI rAqueous Wastes Class A unstable Waste Form Only)
- lume Information (a)
Usable Liner Volume (Fig. 5)
____Ft2 Date:
(b)
Liner Ft'/Inch of Height (Fig. 5)
_____Ft'/Inch Operator:
(c)
Waste Volume to be Solidified
__Ft' Utility:
Shipment No.:
NOTE:
Be sure that volume (c) is less than 68% of volume (a).
Weight Calculations (To The Nearest Pound)
(d)
Weight of Cement =(c) x x.312 =
Lbs. + 10%
(Waste Vol.)
SW-I, Item (b)
(e)
Weight of Lime
(c) x x.312
Lbs. + 10%
(Waste Vol.)
SW-I, Item (c)
(f)
Weight of Other =
(c) x x.312 =
Lbs. + 10%
Additive, If Used (Waste Vol.)
SW-I, Item (d)
(_)
Additive Name Or #
(g)
Weight Of Waste =
(c) x 62.4 x 1.02*
=
Lbs.
(Waste Vol.)
- Use 1.02 or Actual Waste Specific Gravity, If Known.
(h)
Total WT. Of Waste And Additives = (d)+(e)+(f)+(g)
=
Lbs.
Level Heights (To The Nearest 0.1 Inch)
(i)
Waste Level
=
(c)+
(b)_=_Inches (Waste Vol.)
(V/H Ratio)
(j)
Volume Height
=(d)
+ 173** +
(b)
=
Inches Occupied By Cement (Cement WT.)
(V/H Ratio)
- Typical True Cement Density, Lbs./Ft' (k)
Cement Level
= (i) + (j)
=
Inches S
ATTACHMENT 6 PAGE 4 OF 7
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNI-T 1 REVISION 0 PAGE 51 OF 61 ATTACHMENT 6 SCE/CNSI SOLIDIFICATION WORKSHEET II (Full Scale Solidification Of Miscellaneous Aqueous Wastes)
(Continued) 0
- 1)
Volume Height
=
e) + 137***
b =
Inches Occupied By Cement (Lime WT.)
(V/H Ratio)
- Typical True Lime Density, Lbs./Ft' (m)
Lime Level = (k) + (1)
=
Inches PREPARED BY:
/
Date VERIFIED BY:
/
Date APPROVED BY:
/
Radwaste Foreman Date ATTACHMENT 6 PAGE 5 OF 7
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIJ 1 REVISION 0 PAGE 52 OF 61 ATTACHMENT 6 TYPICAL SAMPLE CALCULATIONS FOR WORKSHEET II (Miscellaneous Aqueous Wastes) 120 cubic feet of reverse osmosis waste liquid containing about 2% sodium chloride is to be solidified in a L14-195 liner. Test results indicate 130 grams of cement and 100 grams of lime were required to solidify 200 ml of waste liquid. No other additive was used.
(a) Usable Liner Volume (Attachment 7)
=
190 Ft' (b) Liner Volume/Height Ratio (Attachment 7)
=
2.62 Ft3/In (c) Volume of Waste to be Received
=
120 Ft3 NOTE:
(c)/(a) x 100 = 63% (Less than 68%)
(d) Weight of Cement = 120 x 130 x 0.312
=
4,867 Lbs.
(e) Weight of Lime = 120 x 100 x 0.312
= 3,744 Lbs.
(f) (Not Applicable)
(g) WT. of Waste = 120 x 62.4 x 1.02
= 7,638 Lbs.
(h) Total WT. Of Waste And Additives
= 16,249 Lbs.
(i) Waste Level = 120 + 2.62
= 45.8 Inches (j) Vol. HT. Occupied By Cement = 4,867 + 173 + 2.62
= 10.7 Inches (k)
Cement Level = 45.8 + 10.7
= 56.5 Inches (1) Vol. HT. Occupied By Lime = 3,744 + 137 2.62
= 10.4 Inches (m) Lime Level = 56.5 + 10.4
= 66.9 Inches ATTACHMENT 6 PAGE 6 OF 7
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 53 OF 61 ATTACHMENT 6 SCE/CNSI SOLIDIFICATION WORKSHEET III (Process Summary - Miscellaneous Aqueous Wastes)
Class A Unstable Waste Form Only Unit Operator Waste Tank No.
Shipment No.
- 1. Receive Waste:
S t a r t T i m e D a t e E s t i m a t e Estimated Finish Time _
Date Weight Lbs.
- 2. Add Cement:
Time Date Time Date Weight _Lbs.
- 3. Add Lime:
Start Time Date Finish Time Date Weight Lbs.
- 4.
Other Additive Time Date Weight Lbs.
(Code # ____)
- 5. Temperature After All Ingredients Added:
OF Agitation Stopped:
Time Date
- 7.
Initial Temperature After Agitation Stopped OF 6 Hours Later (From Chart Recorder)
OF 12 Hours Later (From Chart Recorder)
OF 24 Hours Later (From Chart Recorder)
OF
- 8.
Peak Temp:
Time Date OF
- 9.
Temp. Under 160'F Time Date
- 10.
Fillhead Removed: - Time Date
- 11.
Liner Capped:
Time Date
- 12.
Observations, Additional Comments:
PREPARED BY:
/
Date REVIEWED/APPROVED BY:
D Radwaste Foreman Date 0275e ATTACHMENT 6 PAGE 7 OF 7
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
.UNIT 1 REVISION 0 PAGE 54 OF 61 ATTACHMENT 7 LINER AND CASK CALCULATIONS Liner L21-300 L21-235 L14-195-L14-170 L8-120 L7-100 L6-80 Diameter 82" 82" 76" 74" 61" 74.5" 58" Height 104.5" 79" 75.5" 69.37" 71.5" 37" 54" Total Volume, 3
Ft 317 241 196 174 120 93 82 Usable Liner Volume, (LV),
Ft (2" Safety Factor) 311 235 190 169 116 88 79 Volume/Height (V/H)
Ratio FT'/Inst 3.05 3.05 2.62 2.52 1.69 2.52 1.53 Weight (W), Lbs.
2400 1800 1650 1550 1100 1250 950 Cask Payload, Lbs. (Including 27250 27250 17700 14000 20000 13000 7500 Liner Weight)
Waste Volume to Binder Ratio (WV/B) for Resin Beads 0.54 0.54 0.54 0.54 0.54 0.54 0.50 NOTE 1:
A factor.providing for proper waste volume to binder ratio (WV/B), and an allowance for additional binder, if required, to assure a satisfactory mix.
For resin beads, based on liner weight and height limits for liner L6-80, use factor 0.50.
For other liners, use a factor of 0.54. Waste volume for sludge will vary depending upon sludge characteristics. The CNSI Solidification Supervisor or Manager must be contacted to verify waste volume and correct factor for use based on sludge characteristics.
These ratios apply only to Attachment 3.
Water Volume Factor (WtVF) 0.13 0.13 0.13 0.13 0.13 0.13 0.10 NOTE 2:
A factor to provide correct water volume (WtVF) for Agent M-5 slurry.
Based on liner weight and height limits for liner L6-80, use factor 0.10.
For other liners, use a factor of 0.13.
0275e ATTACFMENT 7 PAGE 1 OF 1
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIf 1 REVISION 0 PAGE 55 OF 61 ATTACHMENT 8 DATA RECORD FORM PROCESS CONTROL PROGRAM FOR SAN ONOFRE UNIT 1 CDM File No.
M.O. NO.
Prerequisites Met
/
Signature Date Cask No./Shipment No.
/
Acceptance PERFORMED BY Step No.
Description Data Criteria Signature/Date 3.9 Scale Accuracy SAT Accuracy verified
/
Verification UNSAT last 6 months over scale range in 50 gm increments (i.e.,
50 gm, 100 gm, 150 gm
... to upper range)
HP VERIFIED BY:
/
.2.2 Waste SAT Chemical Analysis
/
Identification UNSAT Waste provides proper information QHP VERIFIED BY:
/
6.2.3 Equipment SAT All necessary
/
UNSAT ____
equipment avail able or approved substitutes HP VERIFIED BY:
/
6.3.1.1 Sample SAT Uniform, dry,
/
6.3.1.2 Acceptance Freestanding UNSAT resists penetration QHP VERIFIED BY:
/
ATTA:HMENr 3 PAGE 1 OF 5
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT 1 REVISION 0 PAGE 56 OF 61 ATTACHMENT 8 Acceptance PERFORMED BY Step No.
Description Data Criteria Signature/Date Test Equipment SAT All Equipment on
/
Available UNSAT is available HP VERIFIED BY:
/
6.4.3.4 Form SO(123)
SAT ____
Form completed
/
159 UNSAT satisfactorily VERIFIED BY:
/
6.5.1 Test SAT SCE/CNSI Worksheets
/
Documentation UNSAT have been completed QHP VERIFIED BY:
/
1.3 Crystallized SAT Sample Heated
/
Sample UNSAT to 140'F or above N/A and completely dissolved HP VERIFIED BY:
/
1.4 Sample SAT Amount of N-24
/
Preparation UNSAT recorded Temp.
N/A _____
160 0 F Temp.
after addition recorded HP VERIFIED BY:
/
1.6 Solidification SAT _____
Proper amount of
/
Agent Addition UNSAT lime added, pH 11 N/A or above QHP VERIFIED BY:
/
ATTACHMENT 8 PAGE 2 OF 5
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT.1 REVISION 0 PAGE 57 OF 61 ATTACHMENT 8 Acceptance PERFORMED BY Cep No.
Description Data Criteria Signature/Date 7
Oven Setting SAT Oven Temp 165 +/-oF
/
1.8 Sample Cure UNSAT Maintained sealed in Time N/A sample oven for 6-24 hours QHP VERIFIED BY:
/
1.3 Sample SAT _____
Sample volume at
/
Preparation UNSAT least 100 ml, less ml if Rad levels high QHP VERIFIED BY:
/
1.4 pH Adjustment SAT ____
pH recorded on
/
with Lime UNSAT worksheet QHP VERIFIED BY:
/
1.5 Solidification SAT Sample mixed
/
Agent Addition UNSAT ____
thoroughly cement and M-5 weight used in grams recorded QHP VERIFIED BY:
/
1.6 Oven Setting SAT Oven Temp 120-130'F
/
Sample Cure UNSAT ____
Maintained sealed in Time N/A sample oven for 18-24 hours HP VERIFIED BY:
/
1.2 Material Dry SAT Dry weight of
/
Weight UNSAT materials recorded QHP VERIFIED BY:
/
ATTACHMENT 8 PAGE 3 OF 5
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNIT, 1 REVISION 0 PAGE 58 OF 61 ATTACHMENT 8 Acceptance PERFORMED BY ep No.
Description Data Criteria Signature/Date
.3 M-5/Cement SAT ___
300 gms added
/
Addition UNSAT _____
mixed thoroughly QHP VERIFIED BY:
/
1.6 Oven Setting SAT Oven Temp 130-1400 F
/
Sample Cure UNSAT Maintained sealed in Time N/A sample oven for 18-24 hours HP VERIFIED BY:
/
1.3 Sample SAT _____
Sample volume at
/
Preparation UNSAT least 100 ml less if ml Rad levels high QHP VERIFIED BY:
/
1.4 pH Adjustment SAT Lime added in
/
with Lime UNSAT ____
0.5 gm increments N/A ____
until pH of 10.5 to 11.5 is reached.
QHP VERIFIED BY:
/
1.5 Solidification SAT Sample mixed
/
Agent Addition UNSAT thoroughly, cement weight used in grams recorded QHP VERIFIED BY:
/
1.6 Oven Setting SAT _____
Oven Temp 120-130 0 F
/
Sample Cure Time UNSAT Maintained sealed in N/A sample oven for 18-24 hours HP VERIFIED BY:
/
ATTACHMENT 8 PAGE 4 OF 5
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1
- UNIT-1 REVISION 0 PAGE 59 OF 61 ATTACHMENT 8 Acceptance PERFORMED BY p No.
Description Data Criteria Signature/Date achment 6 1.2 Sample SAT 200 ml waste sample
/
Preparation UNSAT transferred to disposable beaker QHP VERIFIED BY:
/
1.3 Cement SAT _____
120 to 140 gms added
/
Addition UNSAT _____
mixed thoroughly QHP VERIFIED BY:
/
1.4 Lime SAT _____
80 to 100 gms added
/
Addition UNSAT _____
mixed thoroughly QHP VERIFIED BY:
/
1.6 Oven Setting SAT _____
Oven Temp 120-1300 F
/
Sample Cure Time UNSAT Maintained sealed in N/A ____
sample oven for 18-24 hours HP VERIFIED BY:
/
1.7 Sample SAT
>2 hours after
/
Cooling UNSAT removal from oven HP VERIFIED BY:
/
0275e ATTACHMENT 8 PAGE 5 OF 5
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE S01-VII-8.5.1 UNIT 1 REVISION 0 PAGE 60 OF 61 ATTACHMENT 9 DEVELOPMENTAL RESOURCES A.
Procedures
- 1.
SO124-VII-3.5, ALARA Program
- 2.
S0123-VII-3.0, ALARA Job Review
- 3.
S0123-VII-8.2, Shipment of Radioactive Material
- 4.
SO123-VII-8.15, "10 CFR 61 Waste Sampling Program"
- 5.
S0123-VII-8.4, "Transfer of Radioactive/Waste Materials Between Units 2/3 and Unit 1"
- 6.
CNSI Procedure QA-AD-001, CNS Quality Assurance Program
- 7.
S023-VII-8.5.1, CNSI Procedure SD-OP-003, Rev. N, Process Control Program for CNSI Cement Solidification Units
- 8.
S0123-SD-OP-630, CNSI "Assembly and Disassembly Procedure for the Portable Cement Soldification Unit No. 125 (PSV-C-125)"
ATTACHMENT 9 PAGE 1 OF 2
NUCLEAR GENERATION SITE HEALTH PHYSICS PROCEDURE SO1-VII-8.5.1 UNJI 1 REVISION 0 PAGE 61 OF 61 ATTACHMENT 9 DEVELOPMENTAL RESOURCES (Continued)
B. Other
- 1.
NRC Regulatory Guide 1.143, Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants
- 2.
Standard Review Plan 11.4, Revision 2, July 1981, Solid Waste Management Systems
- 3.
California Adminitrative Code, Title 17, Public Health Chapter 5, Subchapter 4, Radiation
- 4.
Design and Control of Concrete Mixtures, 12th Edition, Portland Cement Association
- 5.
CNSI Topical Report, CNI-2, 4313-01354-OIP, January 1983, Revision 2
- 6.
Letter from K. P Baskin to F. Miraglia of USNRC, providing responses to METB questions on PCP for San Onofre, Unit 2 and Unit 3, dated June 3, 1982
- 7.
Additional Guidance on the Implementation of 10 CFR 61, USNRC, February 1984
- 8.
State of Nevada license to U. S. Ecology, No.,13-11-0043-02, with amendments
- 9.
State of Washington license to U. S. Ecology, No. WN-1019-2. with amendments
- 10.
Hanford Special Nuclear Material License issued to U. S. Ecology, License No. 16-19204-01
- 11.
USNRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, Rev. 0, May 1983
- 12.
USNRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Form, Rev. 0, May 1983
- 13.
49-CFR, Transportation
- 14.
10 CFR Part, 71, Packaging of Radioactive Waste
- 15.
10 CFR Part, 61, Licensing Requirements for Land Disposal of Radioactive Waste 0275e ATTACHMENT 9 PAGE 2 OF 2