ML20114B741

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Rev 5 to Procedure RWS-0304, Radwaste Handling & Control
ML20114B741
Person / Time
Site: River Bend Entergy icon.png
Issue date: 03/08/1989
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20114B582 List:
References
FOIA-91-440 RWS-0304, RWS-304, NUDOCS 9208310179
Download: ML20114B741 (11)
v • d • e


Text

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C RIVER BEND STATION APPROV/.L SHEET STATION Ol'E::ATING PROCEDURES NO. RW5-0304 TITLE RADIOACTIVE WASTE HANDLING AND CONTROL SAFETY REIATED YES ,

' N08 V,0 TECHNICAL REVIEW REQUIRED YES NO

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! iES!.;ED SEP 111989 ST 'l C: L'l.*Ei.~ , C::TF C,L RECIIVED MoR 0 51989 soc l

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SOM-003 , r t208310179 911223 q REY 2 C PDR FOIA SHINKLE91 -440 PDR i

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l RADI0 ACTIVE WASTE ttANDLING AND CONT. 0L i I i l .

I I I I ,

l TABLE OF CONTENTS I I l I sECTION PAGE NO. l l l l 1.0 PURPOSE / SCOPE / APPLICABILITY 2 l l l l

2.0 REFERENCES

2 l -

l l l 3.0 DEFINITIONS 2 l 1 l l 4.0 REQUIRED EQUIPMENT 2 l l 1 l 5.0 PRECALTIONS 3 l l l l 6.0 LIMITATIONS 3 l 1 l l 7.0 PREREQUISITES / INITIAL CONDITIONS 3 l l l l S.O P ROCEDUR E / I NSTRUCTI ON S / REQUI REMESTS 3 l l l l 8.1 Dry Active Waste (DAV) 3 l l 1 l 8.2 Processed Waste 4 l 1 l l 8.3 Storage and Identification 6 I I I l 9.0 RESTORATION 7 l l 1 l 10.0 DATA REQUIREMENTS 8 l 1 I

, l 11.0 ACCEPTANCE CRITERIA 8 l l I I I I I I I I l ATTACIDIENTS l l 1 l Attachment 1 - Example of a Radioactive Waste l l Inventory / Storage Form 9 l l 1 l Attachment 2 - Guide to the Storage Location l l Grid Numbering System 10 l 1 I I I I I I I I I 11 1 1 I I I ll 1 1 l l l ll RWS - 0304 l REV - 5 l par;E 1 0F 10 l 1 I ll I I I

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1.0 PURPOSE / SCOPE / APPLICABILITY 1.1 This procedure establishes the methodology for handling, control and storage of radioactive waste. i 1.2 RADWASTE is an unwanted by product in the form of radioactive trash, f resin and liquids produced by the operation of a nuclear reactor. The  ;

disposal of radioactive waste is regulated by the NRC.

2.0 REFERENCES

2.1 ADM-0006, Control of Plant Records l

2.2 RWS-0207, Radwaste Shipping Criteria 2.3 RWS-0209, Conduct of Radwaste Vendor Services 2.4 RWS-0307, Radioactive Waste Segregation 2.5 RWS-0305, Use of the Dry Active Waste Storage Facility (DAWST) 2.6 RWS-0313, Receipt Inspection. Storage and Inventory of Radioactive Material Shipping Packages 2.7 RWS-0327, Shipping Low Specific Activity (LSA) Radioactive Material 2.8 RSP-0006, Radiatfor. Protection Task scheduling 2.9 RSP-0200, Radiation Work Permits 2.10 RSP-0213, Control and Handling of Radioactive Material l

! 2.11 RPP-0005, Posting of Radiologically Controlled Areas 2.12 RPP-0006, Radiological Surveys 3.0 DEFINITIONS 3.1 DAWSF - Dry Active Vaste Storage Facility 1

1 4.0 REQUIRED EQUIPMENT NOTE Part or all of the following may be needed to perform this procedure.

4.1 USDOT approved shipping containers (or equivalent) 4.2 Absorbent material /dessicant 4.3 Polyethylene liner for 55 gallon drums (4 mil. thick minimum) 4 .4 Radwaste and Radiation Protection consummables RWS-0304 REV - 5 PAGE 2 0F 10

- . - - , . . - . . . ~ . . _.- . . - - . . . .

l i .-

4.5 Radwaste Collection Cart.

. 5.0 PRECAUTIONS ,

5.1 Minimize the volume of materials placed in radioactive waste containers by decontaminating and releasing items whenaver practical.

5.2 Segregate contaminated oily or greasy waste for appropriate packaging.

5.3 Transport and Handle Radioactive Material in accordance with Reference 2.10.

S.4 Dry all wet Radwaste. The drying area shall be utilized to prevent compacting of materials which contain free standing or absorbed water.

5.5 Drum weight and pallet restrictions may apply based upon burial site criteria. The Radwacte Foreman is responsible for assigning package weight limits and pallet instructions.

5.6 Corrosive materials are to be placed in inner containers (liners) such that the corrosive material does not come into contact with a drum.

5.7 Follow the access requirements cf the appropriate RVP when performing work in a Radiologically Controlled Area (RCA) to maintain exposures ALARA.

5.8 All handling and loading of material shall be performed in accordance with applicable plant saftty procedures.

6.0 LIMITATIONS

  • 6.1 Strong Tight Containers (as a minimum) will be used for packaging and storing Dry Active Wastes 7.0 PREREQUISITES / INITIAL CONDITIONS 7.1 Inspect Radwaste shipping containers in accordance witn section 11.0 of Refexence 2.6, for manuf acturing defects and damage prior to use.

8.0 PROCEDURE / INSTRUCTIONS / REQUIREMENTS 8.1 Drv Active Vaste (DAV) 8.1.1 Container Requirements

, 1. Color coded containers used for the collection of l Radwaste shall be convienently located through-out the RCA,

a. Yellow painted containers lined with yellow bags should be used to identify contaminated trash and laundry.

l RVS-0304 REV - 5 PAGE 3 0F 10 i

  • , , - - , - - - - - , . , - . - , - - ~, . . - - - . . - . , . . , . . - ..-,,,--,.--.,n-.n.
b. Green painted containers lined with red bags should be used to identify potentially contaminated wastes.

f c. Seperate containers will be provided for i

noncompactable material, 8.1.2 Collection

1. Radwaste material should be picked up daily or as necessary, based on general area work load.
2. The Radwaste Supervisor or the Radwaste Foreman shall

) spot check material ingress and egress throughout the

RCA during peak work load periods. This inspection j should be documented in the Radwaste Volume Reduction 7 Discrepency Log.

l 3. Individuals handling or transporting bags of waste i shall be cognizant of radiation levels to maintain

personnel exposures ALARA.

1

e. Transport of Radiaselve Material through-out the plant

, shall be in accordance with reference 2.10.

8.1.3 Segregation 1 Segregate Radioactive Wastes in accordance with 4

Reference 2.4.

8.1.4 Trancorting of Radioactive Waste on Plant Site i
1. Transport waste material using flatbed vehicle or other appropriate means. Load the vehicle in the loading area designated by the Radwaste Foreman.

]

2. Radioactivo Waste should be contained in closed strong j tight packages, or transported in an enclosed vehicle.

Transport Radioactive Material onsite in accordance

! with Reference 2.10.

j

4. The transport vehicle should travel unimpeded and by the shortest route to its destination. The vehicle should not make unauthorized stops. Emergency stops (mecnanical failure, flat tire, etc.) requires the immediate notification of the Radwaste Foreman and Radiation Protection.

8.2 Processed Waste 8.2.1 Container Requirements

1. Solidified waste shall be stored in strong tight packages which are commercially manufactured.

1

] RWS-0304 REV - 5 PAGE 4 0F 10 i

2. All radioactive waste slurries should be dewatered or solidified before short term storage / shipment.

Radwaste slurries and concentrates are solidified in concrete or other acceptable medium, in the Radwaste Building solidification area. In addition to operating procedures, the Radwaste Process Control Program (RPCP) verifies that proper solidification takes place.

3. Complete Attachment 1 for each container of solidified radwaste.

8.2.2 Spent Filter Handling NOTE When using the RAD. M AIL computer program, Attachment 1 is not required. Information will be maintained in the computer.

1. The selection of the proper storage / shipping container and storage area for spent filters will be made by the Radwaste Foreman.
2. Add absorbent to the drum to absorb any free standing liquid from the filters, before placing filters in the drum.

1 a) Filters with a dose rate of less than 1000 mR/hr may be placed in unshielded drums, b) Filters with a dose rate of greater- than 1000 l mR/hr will be dispositioned by the Radwaste Foreman for storage and disposal.

3. Shore or otherwise stabilize filters to prevent shif ting during shipment. If required, solidify l filters'in_ cement prior to shipment, j 4 Determine container activity in accordance with
Reference 2.7.
5. Complete Attachment 1- for each container of spent f filters. (If Required)

RWS-0,J4 REV - 5 PAGE 5 0F 10 e

) 8.3 Storage and Identification 8.3.1 Temocrary and Interim _ Storage

1. The Radwaste Building may be used to temporarily store radioactive wastes while they are awaiting transfer to the DAWSF, futher processing or shipping for offsite burial.
a. Dry Active Wastes (DAW) and oily trash in plastic bags, drums and metal or wooden strong tight containers, solidified drums of oil and drums of contaminated filters may be temporarily stored in the Radwaste Building in areas designated by the Radwaste Foreman,
b. Solidified liners may be stored in the high bay of the Radwaste Building in the sheilded storage area for liners while they are awaiting shipment for offsite burial.
c. Other wastes such as Special Nuclear Material, '

transuranics, > type A quantities, etc. may also be stored in areas designated by the Radwaste Foreman.

2. The Dry Active Waste Storage Facility may be used for 4 storage of packaged wastes while awaiting further vi processing or shipment for offsite burial in b{ accordance with Reference 2.5. Radioactive Material q; f

, may be stored in the DAWSF as approved by the Radwaste l N Foreman.

a. Dry Active Wastes (DAW) and oily trash in USDOT strong tight containers, solidified drums of oil and drums of contaminated filters may be stored in areas of the DAWSF, authorized by the Radwaste Foreman while awaiting shipment.
b. Up to 1 inch of cement in dry powder form (or a suitable type and quantity of absorbant or dessicant) should be added, before packaging, to the bottom of the inside of the packages to ensure compacted and/or non-compacted waste packages do not contain free standing liquid and to minimize the ef fects of temperature changes that may cause condensation resulting in free standing liquid inside the shipping packages.
3. Raiioactive Waste in RW 106' High Rad Bay, and DAWSF awaiting shipment should be stored using a grid f

I sto. age system (Attachment 2) to p ovide X,Y, and Z axes for information only. (Example: Storage Locaticn: 49-AC-2)

RWS-0304 REV - 5 PAGE 6 0F 10

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4. The Radwaste Foreman is responsible for tracking radioactive waste package location. A tracking board depicting the grid layout of the storage area, using a q

i color coded system to identify unusual packages or contents, is used for tracking package information and i location.

8.3.2 Container Identification and Numbering

1. Each packaged storage and shipping container shall be f i assigned a unique number by the Radwaste Foreman using f
the RADMAIL computer program. The package number
identifies the year packaged and the sequence number i

of the package. Containers being reused such as j j laundry boxes may be assigned a permanent number.

l 8.3.3 Radiological Surveys 1

i Radiological surveys of all' waste shall be performed in accordance with Reference 2.12.

8.3.4 Posting a

' Radioactive waste storage areas shall be posted in accordance with Reference 2.11.

q 8.3.5 Stored Container Inspection Stored containers shall be inspected quarterly for signs of container deterioration or leakage. Repack contents in another container or place damaged container in an overpack -

j container if damaged containers are found NOTE To keep personnel exposure ALARA, containers stored in High Radiation and Very High Radiation Areas i

, will be inspected for damage prior to shipment.

f 8.3.6 Package Preparation for Shipment I

) 1. Prepare package for shipment in accordance with

Reference 2.2.
9.0 RESTORATION N/A RWS-0304 REV - 5 PAGE 7 0F 10

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1 10.0 DATA REQUIREMENTS l

l, _ 10.1 Attachments referenced'in this procedure are provided as an example. They eay be replaced by ce=puter generated forms, or  !

f other format, i.e., phone, telelog, etc., as required by the i Radwaste Foreman.

11,0 ACCEPTANCE CRITERIA I

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s RIVER BEND STATION APPROVAL SHEET STATION OPERATING PROCEDURES ,

yo, RWS-0204 TITI.E 1 !

RADWASTE PROCESSING CONTROL PROGRAM SAFETY HLATED TES [

TECHNICAL HVIEW HQUI RD TES C yo )

uv. PACES INDEP.

NO.

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ISSUED REVIEW REVIEW APPROVED BY SICMATURE/DATE EFFECT SICMATURE/DATE SICMATURE/DATE DATE O 1 Thru 11 dh/&u/r/ey Tw&I QQg,I'b, 12/28184 a/>#/SY 1 1 THRU 11 , Ity>v'C/ . -Tdh 7,/.R 5/1/86

$ 11/10/87 2 1 Thru 17 'fN/77 7

INFORMATiON CE LY t ISSUED _ -

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'. SEP 111989 simon cacunni c7 im 1

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l RADUASTE PROCESSING CONTROL PROGRAM l l

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l TABLE 07 CONTEhTS l 1

1 I

I l SECTION PAGE NO. 1 I

I l 1.0 PURPOSE / APPLICABILITY / SCOPE 2 l 1

l l

2.0 REFERENCES

2 l I

l I 3.0 RESPONSIBILITIES 3 l l

l l 4.0 DEFINITIONS 4 l l

I l 5.0 PROCEDURE 5 l 1

l l 5.1 General Requirement 5 l l 5.2 Solidification Process Control Program 6 l l 5.3 Dewatering Process Control Program 8 l l 5.4 Encapsulation Process Control Program 9 l l 5.5 Dry Active Waste Process Cuntrol Program 10 l 1

I l 6.0 ACCEPTABLE CRITERIA 10 l 1

I l 7.0 DOCLMhTATION 11 l I

i l ATTACHMENTS l

1 I

I ATTACHMENT 1 - EXAMPLE OF A VASTE SOLIDIFICATION DATA SHEET 12 l I

i 1 ATTACHMENT 2 - EXAMPLE OF A DEWATERED DATA SHEET 15 I I

I I ATTACHMENT 3 - BASIC FLOW PATH AND DESCRIPTIONS 16 l 1

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_ _ - - _ - _ _ - - - - - _ - - _ _ J

,2 1.0 PURPOSE / APPLICABILITY / SCOPE 1.1 The purpose of the Radwaste Processing Control Program (RPCP) is to provide reasonable assurance and documentation that the processing and packaging of wet and dry radioactive waste will be accomplished in accordance with specifications set forth by the disposal facility, as well as state and federal regulations.

1.2 The Radwaste Processing Control Program (RPCP) contains the sampling and testing methodology, analyses and formulation determination by which dewatering, solidification at.d packaging of wet and dry radioactive waste is assured.

1.3 Changes to the Radwaste Processing Control Program (RPCP) will be done in accordance with Reference 2.8.

2.0 REFERENCES

2.1 ASTM Standard Part 13 2.2 ASTM Standard Part C39 2.3 BTP Final Waste Classification and Waste Form Technical Position :q Paper 1 2.4 10 CFR 20, Standards for Protection against Radiation 2.5 10 CFR 61, Licensing requirements for Land Disposal of Radiative Material 2.6 RBS FSAR 11.4, Radioactive Solid Waste System 2.7 RBS Technical Specification 3/4.11.3 2.8 RBS Technical Specification 6.13 2.9 ADM-0006, Control of Plant Records 2.10 ADM-0038, Radioactive Waste Management Program 2.11 COP-0019, Sampling of Liquid Radwaste Sludge and Resin Holding Tanks 2.12 SOP-0108, Liquid Radwaste Processing 2.13 RSP-0009, ALARA Program Implementation 2.14 RSP-0200, Radiation Work Permits 2.15 RWS-0209, Conduct of Radwaste Vendor Services 2.16 RWS-0304, Radioactive W'aste Handling and Control RWS-0204 REV - 2 PAGE 2 0F 17

l 2.17 RWS-0307, Radioactive Waste Segregation i

2.18 RWS-0327, Shipping of Low Specific Activity (LSA) Radioactive Material l 2.19 SD-OP-003, Chem Nuclear System Incorporated (CNSI) Process 1 Control Program 4

2.20 SD-0P-003-518, Process Control Program for CNSI Cement Solidification Units i

2.21 SD-0P-026, Process Control Prograe for Cement /011 Solidification

, 2.22 DM-0P-022, Process Control Program for CNSI Demineralization System 2.23 SD-OP-020, Operating Procedute for CNSI Portable Cement Solidification Unit Number 21 (PUS-C-21).

4 2.24 FO-OP-011, Dewatering Procedure for the 24-inch Diameter Pressure Demineralizer Vessel Containing Activated Carbon 0.5% Free Standing Water.

2.25 FO-OP-009, Dewatering Procedure for CNSI 76-inch Diameter Pressure Demineralizers Containing Ion Exchange Resin.

2.26 F0-0P-023, Dewatering Procedure for CNSI 14-195 or Smaller Liners j 2.27 FO-OP-025, Dewatering Procedure for CNSI 24-inch Diameter Pressure Vessel 2.28 Chem Nuclear System Inc. Topical Report CNSI-2 (4313-01354-01P-A) 2.29 RWS-0207, Radwaste Shipping Criteria 2.30 RWS-0211, General Performance Control for Radwaste 2.31 RWS-0203, Personnel Qualification for Radwaste Section

, 2.32 RWS-0206, Radwaste Scaling Factor Program

( 2.33 RWS-0310, Operation of the Nuclear Packaging Model WC-18000 waste compactor i 3.0 RESPONSIBILITIES t

! 3.1 The Radwaste Supervisor / designee, is responsible for the

, implementation of the Radwaste Processing Control Program in

! accordance with Reference 2.10, ensuring the Vendors PCP meets l

the requirements set forth by the NRC and is incorporated into the Radwaste Processing Control Program prior to use.

3.2 The Radwaste Specialist / Foreman is responsible for interfacing with the Vendor and preparing a weekly work plan in accordance with Reference 2.10.

RWS-0204 REV - 2 PAGE 3 0F 17

3.3 All personnel working under this procedure shall know their

, responsibilities to the ALARA Program in accordance with Reference 2.13. -

3.4 The Vendor is to ensure the general design of the solidification equipment is in accordance with Reference 2.28 and this equipment is installed, and tested in accordance with Reference 2.15.

Operability shall be demonstrated prior to initital startup of the vendors equipment. Vendor's equipment shall oc operated and inspected in accordance with Reference 2.23.

3.5 The Vendor is to ensure that the chemicals and/or material composition being used for solidification is equal to or better than required by the vendors PCP.

3.6 Vendor and plant personnel performing work for the Radwaste Department shall be qualified in accordance with Reference 2.15 and 2.31 respectively. (As required) 4.0 DEFINITIONS 4.1 Batch - An isolated quantity of feed waste to be processed having essentielly constr.nt physical and chemical characteristics (i.e.

the amount of waste contained within a tank). If new waste-is added to the waste being processed then a new batch is created and further sampling is required.

4.2 Dry Activated Waste (DAV) - Any dry radioactive material (i.e.

contaminated tools, equipment, clothing, etc.)

4.3 Dewatering - The process of removing liquids from wet radioactive waste so that the form of waste is suitable for disposal.

4.4 Encapsulation - The process of encapsulating solid radioactive waste which is non-uniform in size and cannot normally be homogeneously mixed (i.e. filters, sources ect.).

, 4.5 Free Standing Liquid - Liquid which is still visible after I

processing, or liquid drainable from the low point of a punctured container.

l 4.6 High Integrity Container (HIC) - A polyethylene container which l has been approved for the type of waste being processed.

I l 4.7 Prequalification Test Sample - Test conducted un laboratory

samples to demonstrate the ability to produce an acceptable waste i

form using the type of wet waste and solidification agent expected.

, 4.8 Production Test Sample - A sample used to demonstrate the ability l

i of the on site solidification agent and waste batch to produce u '

acceptable waste form u' sing the parameters identtfied in the PCP.

4.9 Solidification - The conversion of wet radioactive w rte anto a form which is suitable for disposal.

RWS-0204 REV - 2 PAGE 4 0F 17

4.10 System Description - A brief description and flow path diagram of process flow path can be fo"td on Attachment 3.

4.11 Waste Classification - The determination of waste class as outlined in Reference 2.5 by radionuclide isotopic analysis and/or correlation with hard to measure radionuclides.

4.12 Vet Radioactive Waste - Any radioactive liquid or liquid / solid slurry which does not meet the burial site requirements for free standing tiquids (i.e. sludge, resin, evaporator bottoms, contaminated oils etc.)

5.0 PROCEDURE 5.1 General Requirements 5.1.1 All processing of wet radioactive waste performed by a vendor shall be done under an approved process control program for the type of waste being processed.

5.1.2 All solidification, dewatering and sampling activities performed inside the RCA till have an R'JP in accordance with Reference 2.14 b

5.1.3 For high activity waste being solidified, where handling of the production test sample could result in personnel radiation exposure that is inconsistent with the ALARA principles, a non-radioactive test sample having essentially the same chysical and chemical characteristics may be solidified.

5.1.4 As required by Reference 2.7, a Production Test Sample shall be solidified from at Isase one (1) out of every ten (10) batches of wet radioactive waste solidified.

5.1.5 As a minimum the vendor's PCP for Solidification Process shall require annually.

1. A Production Test Sample selected from the most recent production level solidification batch will be subjected to a:

i

a. Standard 14 day immersion test in water and thsn
b. Compression test in accordance with Reference l 2.2.
2. The vendor must demonstrate that the Prcduction Test Sample parameters are the same as the Prequalification Test sample.

RVS-0204 REV - 2 PAGE 5 0F 17

5.1.6 As a minimum the Vendors PCP for dewatering process shall include and/or reference documentation necessary to ensure the dewatering process and equipment being used will produce a waste form that will meet the disposal facilities requirement for free standing liquids. This documentation should be made available to RBS.

5.1.7 As a minimum the vendors PCP for Encapsulation Process shall include and/or reference documentation necessary to ensure the following:

1. The Encapsulation Media satisfies the stability requirements of Section B and C of Reference 2.3.
2. Should be capable of maintaining at least a 50 PSI compression strength (giving credit for the structural strength of the waste material, i.e.

filter cartidges).

3. Demonstrate that the container or the Encapsulation-Media will not degrade within the prescribed time requirement.

5.1.8 All documents shall be maintained in accordance with Reference 2.9 and/or Reference 2.29.

5.1.9 The Radwaste Department Quality Control Functions are performed in accordance with Reference 2.30. The RBS QA Department performs annual audits on the Radwaste Process Control Program and Procedures in accordance the GSU Quality System Internal Audit Schedule.

5.1.10 All HIC used at RBS for disposal of radioactive waste will be approved for the type of waste being processed.

This approval will be based on the chemical and physical limitation of the container and each HIC will be certified that it meets the acceptance criteria set by the disposal site being used.

5.1.11 Reference 2.32 provides instructions for developina scaling f actors necessary for ensuring compliance w.th 10CFR61.

5.1.12 Preparation of manifest and shipping paperwork shall be performed in accordance with Reference 2.29.

5.2 Solidification Process Control Program 5.2.1 Sampling

1. Obtain a representative sample of the waste batch.

This sample will be used by the Vendor to determine the actual process formulation for solidification.

Record this information on Attachment 1.

RWS-0204 REV - 2 .PAGE 6 0F 17 i

l l

NOTI To keep personal radiation exposure ALARA, the sample taken may be used for both vendors test solidification and chemistry isotopic analyses.

2. Chemistry shall obtain a representative sample of the waste 'oatch in accordance with Reference 2.11.

This sample will be used for radiochemics1 analysis and to determine the quantity of oil in the batch of waste. Record this information on Attachment 1.

5.2.2 Vaste Classification

1. Prior to Solidification a Waste Classification will be performed, as outlined in Reference 2.18, on the waste batch. Record this information on Attachment 1.

NOTE The Waste Classification and Vendor Production Test solidification may be performed at the same time.

5.2.3 Test Production Solidification

1. The Vendor will perform a test solidificacian of the waste batch in accordance with the Vendors PCP, Prior to the rese solidification the Vendor will obtain the pH of the waste and adjust as necessary.

Record this information on Attachment 1.

2. If pretreatment of the batet of waste is necessary, the test sample shall have the required pretreatment
prior to test sample solidification.
3. If the oil content of the waste batch is greater l than 1% by volume, secure solidification operation and nctify the Radwaste Supervi ar.

l NOTE i

! If the oil content of the waste batch is greater then 8% by volume then the solidification must be done using an approved PCP for wet radioactive waste with oil content. greater than 8% by volume.

RVS-0204 REV - 2 PAGE 7 0F 17

. - - . - - _ ~ . . . - . . . . - . - . - .. . - . . . = .

1 4 If any Production Test Sample fails to verify solidification, the solidification of the batch under test shall be suspended until such time as additional Production Test Samples c an be obtained, alternative solidification parameters can be determined in accordance with the Radwaste Processing Control Program, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined by the Radwaste Processing Control Program.

5. If the initial Production Test Sample from a batch of waste f ails to verify EOLIDIFICATION. Obtain representative samples from each consecutive batch .

of the same type of wst waste until at . east 3 5 consecutive initial Prod _. tion Test Samples demonstrate SOLIDIFICATION. -

6. Vith the provisions of the RADWASTE PROCESSING CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the sits. Notify the Shift Supervisor in accordance with Reference 2.7.
7. If any free standing liquid is observed on top of the test sample, decant tne liquid into a volumetric beaker and record the amount of liquid. Calculate the percent of itee standing liquid. Record this information on Attachment 1.

5.3 Dewatering Process Control Program (Portable disposal Pressure Vessels / Liners / HIC's) 5.3.1 Sampling

1. Chemistry shall obtain a representative sample of the waste batch in accordance with Reference 2.11.

This sample will be used for radiochemical analysis and to determine the quantity of oil in the batch of waste. Record this information on Attachment 2.

5.3.2 Waste Classification

1. A waste classification should be performed prior to transferring the waste batch to the container (if possible). As a minimum a waste classification s shall be performed prior to sealing the container for shipment. The waste classification vill be performed as outlined in Reference 2.18. Record

, this information on Attachment 2.

RVS-0204 REV - 2 PAGE 8 0F 17

2. If the waste classification and/or the container ecntent activity requires the waste batch to be classified as a stable waste form, then the waste shall be packaged in a High Integrity Container (HIC). (Reference 2.5)
3. The Vendor will supply the information needed to complete Section II of Attachment 2.

5.4 Encapsulation Process Control Program - High activity filters, Irradiated Components and other materials which may require encapsulation i.e. lead 5.4.1 Sampling

1. Chemistry shall obtain a sample of the waste to be encapsulated. This sample will be either a qualitative or a quantitative sample. This sample will be used for radiochemical analysis and to determine the quantity of oil in the waste.

5.4.2 Waste Classification

1. Prior to encapsulatici a waste classification will be performed, as outlined in Reference 2.18, on the waste.
2. If the wasce classi'ication and/or item specific

! activity requires the final package to be a stable l waste form then an approved encapsulation PCP for stable waste form will be used. If an approved PCP

is not available then the item may be encapsulated l inside a high integrity container (HIC). (Reference l 2.5) l l
3. Once the waste classification is completed the Radwaste Specialist / Foreman will calculate the amount of encapsulation material needed. The calculation will be based on the dose rate of the

, item beirg encapsulated and the type of containec j being used.

l -NOTE Ensure adequate encapsulating material surrounds the item being encapsulated, l

I 1

l RWS-0204 REV - 2  ? AGE 9 0F 17

9 5.5 Dry Active Vaste Process Control Program 5.5.1 Sampling

1. Chemistry will analyze a sample of the waste to be packaged (if possible). If a sample of the waste is unobtainable then the nuclide distribution for the DAV Vaste Stream will be used for the identity and percent abundance.

5.5.2 Waste Classification

1. A waste classification should be performed prior to transfering the waste batch to the container. As a minimum a waste classification shall be performed prior to shipment. The waste classification will be performed, as outlined in Reference 2.18.

5.5.3 Packaging / Handling

1. DAW will be segregated and stored in accordance with Reference 2.16 and 2.17.
2. Compactable and noncompactable DAW should be packaged in accordance with Reference 2.33 and 2.17.

6.0 ACCEPTANCE CRITERIA

, 6.1 Solidification Process Control Program 6.1.1 The test sample will be considered acceptable if it meets the free standing ligdid requirements for the disposal facility and stability requirements if it is evident from the physical appearance that the test sample maintains its shape if removed from the centainer.

6.1.2 Once the test sample demonstrates an acceptable waste form and the waste classification is acceptable for near surface burial, solidification may be performed as per formulas stated in the Vendor's PCP and operating sequences spe_.fied in Reference 2.23, 6.1.3 Once solidification is completed the container will be stored in accordance with Reference 2.16 and prepaired for shipment in accordance with Reference 2.29.

6.2 ' Dewatering Process Control Program 6.2.1 The container shall be considered acceptable if it meets the dewatering limitation set forth in the Vendors PCP and the disposal site requirements for free standing liquids.

6.2.2 The limit (s) and sample results shall be recorded on Attachment 2.

RWS-0204 REV - 2 PAGE 10 0F 17

6.2.3 Once dewatering is completed the container will be stored in accordance with Reference 2.16 and prepaired for shipment in accordance with Reference 2.29.

6.3 Encapsulation Process Control Program 6.3.1 The waste form will be considered acceptable if it meets the test requirements as outlined in the Vendors FCP and the free standing liquid requirement for the dispcsal site.

6.4 Dry Active Waste Process Control Program 6.4.1 The waste form will be considered acceptable if it meets the free standing liquid requirement for the disposal site and the waste classification for near surface burial.

7.0 DOCUMENTATION 7.1 Data sheets will be included in the file copy of the shipping package.

,,END" l

l l

l RWS-0204 REV - 2 PAGE 11 0F 17

. I I l l 1 l EXAMPLE OF l ATTACHMEhT - 1 l i l WASTE SOLIDIFICATION DATA SHEET

' l I

I I

_ i

,. I

I I

l

, I j I

WASTE SOLIDIFICATION DATA SHEET l I

i 3 I l

l Batch No. -

[

, 1 Date: I l Prepared By: l l' 1 I. A. Prior Batch Sample Solidification l

l l

l Verify prior batch sample solidification performed. Check one below and i j l show date and batch number of sample. l l 1 l

l Evaporator Bottoms Dat.e : Batch No: l l l Chemical Vastes Date: Batch No: I

. I Resins Date: Batch No:

1 1 l Other i

l I

l B. Initial Batch Sample Solidification l

l 1

, l If sample is from an initial batch of waste, describe waste stream below: l

) l I

II. Batch Sample Analysis l

4 l l A. Lab Results 1 l

l l Sample Volume I

l I

i pH of Waste

I I

I If greater than 1*. refer to 1 I Waste Oil Content Section 5.2.2.3 0F RPCP. I I

l i Radionuclide Content l

! I l

I waste Classification I l

l I B. Vaste Pretreatment l l l l

\

pH - Identify agent used and quantity to adjust pH of the waste-in l l the sample.

i I l

l l Agent /Qur.ntity Adjusted pH value_ l I

I l Performed by: Date: l 3

I I

I I

I I

! I I

i i I I I I 1 AW ACHMENT - 1 l PAGE 1 0F 3 RWS-0204 1

1 l l REV - 2 l PAGE 12 0F 17 1 I I I I l

_ , J

_ _ _ . , . - . - - - . -~-s

l i l l l

[ EXAMPLE OF l ATFACHMENT - 1 l 1

WASTE SOLIDIFICATION DATA SHEET l

. I i

i I

i i

I III. Production Test Solidification (Required on at least every tenth l l

batch of each type of wat radioactive l l

vaste.) l I

I l A Test Solidification Formula: '

l I

I l Volume of Vaste:

l 1

l Volume of Binder: l l

l Volume of other ingredients: 1 l

Waste / Binder Ratio:

Binder / Ingredient Ratio:

I Total Volume: I I

I l B. Free-Standing Vater Analysis:

l l

l l Volume of Decanted Vater l l

I l Volume of Sample:

' l

  • . Free-Standing Vater: l j

j C. Solidification Acceptability I

I

1. Percent of free-standing water calculated in Section III.B I

( (above) must be less than disposal facility criteria. I I

l I

2. Visual physical appearance: Verify that the solidified waste l would mairtain its shape if removed from the e.ontainer. I I

i l 3. The above Acceptance Criteria satisfies RBS Technical Specification l I 3/4.11.3. l 1

4. I l Other (state additional results here) ]

I I

I l

I l Performed By: Date: i g

g IV. Batch Solidification

  • I A. Formula (Per Drum Basis)  !

I I

I Waste to be solidified (gallons) l I

Binder added (pounds) _ l l

1 Other ingredient (added) l I

I i

) ATTACHMEST - 1 l DAGE 2 0F 3 l RWS-0204 l

l REV - 2 i

l PAGE 13 0F 17 I

l i 1 .I I I I s

i

1 I l I l EXAMPLE OF l ATTACHMENT - 1 l l

  • WASTE SOLIDIFICATION DATA SHEET l

' l l

I i _I I l i l I I I i l I VASTE SOLIDIFICATION ACCEPTABLE / UNACCEPTABLE

{

l (circle one) I l

i I l B. l Remarks I I I I I I I I I I I I I I I I I I l I Performed By: Date:

I 1 l I Reviewed By: Date:

1 1 I I I

I a l l l l l l I 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

I i I i i i l A M CHMENT - 1 i

! l PAGE 3 0F 3 l RWS-C204 l REV - 2 l PAGE 14 0F 17 I l I I I I I i

. _ _ _ _ _ _ ___._._____.__.________.._____._._._.U

4 l l EXAMPLE OF l l A1TACHMENT - 2 l RESIN DEWATERING DATA SHEET l 1 _l i I I I l RESIN DEVATERING DATA SHEET l l Batch No.: l l Date: l l Prepared By: l 1 I i l

' l l I. Sample Analysis l

I I l Sample Volume l

, I I l Laste Oil Content I

I l l Radionuclide Content l I I l Waste Classification l i I I I lII. Vessel Information i l

l l Type oZ Vessel being Dewatered l 1

1 I Vessel Serial Number i i l l

l Number of pumping cycles l l

l 1 Volume of water collected during final pumping cycle l l

l l Limit of remaining liquids for this type of vessel l I

l l

l l l Remarks:

l l

l 1 '

I I

I I

I I

i 1

I l Completed By: Date: l l

l l

1 l Reviewed By: Date: 1 I

l l

1 I

I I

l i_

I I

I I

I I I ll 1 I I l ATTACHMENT l PAGE 1 ll l l- l l

2 1 0F 1 ll RWS-0204 l REV - 2 i PAGE 15 0F 17 l l ll 1 I I

. . -. . . . - . -. .~. .- . . . - . .- - - .- - - . . . -

i' l l

' l I I 1

l A'ITACHMENT - 3 l. BASIC FLOW PATH AND DESCRIPTIONS l l

l L .

l a

i

! ASIC T'.CV PITH FCR SOLIDITICATION PROCESS - 1 I

. .>. WA, . .

NER ,.>.>.>.>.,. . I l

I .) l' <-< < CHEMICAL SUPFLY-< <-l l

I

.<.<.<.1  ; <-c OEVATERING LINE l ll l l

l I i l iI I l I

4 I l _l l_ f _ _ l l l l l  ! VENDORS l l l

, l l l 1 FILLMEAD l l l

....l............l.... l g l l l VENDORS LINER l l

l ....!.... l ............. I

]

I l l DEWA ER l l l l CHEMICAL j l I l< l PCMP l 1 l l BULX l l l l l SKID j i l 1 TRAILER j.

l l  ;

l l g Wet radioactive waste are notmally transferred to the vendor from the phase l separator tanks, backwash tank and/or waste sludge tank. This radioactive  !

waste is dewatered using the vendors dewatering skid which discharges liquid l l to the floor drain system. Once the vendors liner is full, the wet radioactive l

, ) waste is mixed vath chemicals form the vendors bulk trailer and sol-idified j l in accordance with the vendors PCP.

l 1

i

,- 1

' I l BASIC TI.0V PATM FOR DEVATERING PROCESS l I

l' , ->.>- WASTE LINE TO LINER >->->->.> >->-l l

l 3 i

! -< <-<-l l<-< DEVATERING i.iNE i i  !

! I

, I I i I i l l _I I I

, I I l l VENDORS l l l l l l FILLMEAD ] g

l [ ....l............l....

l l l LINER / HIC ]  !

l l ....l.... l l l

! l I DEVATER l l l l l l< l PCMP _l l l l l l l SKID l- l l

[

l

l. l I

River Bend does not normally dowater. resin but has the capability to do so. I I To perform dewatering, wat radioactive waste are transferred to a liner .l l f rom the phase separator tanks, backwash tank and/or waste sludge tank. -l l This wet radioactive waste may be dowatered using the vendors dewatering skid

, j or similar type equipment which dischargee liquids to the floor drain systee. l 4

- Portable disposal Pressure Vessels are normally dowatered in accordance with. .g g

the Vendors Process Control Progras. 'I I

I I

I I- 1 il . I I I l A"ITACHMENT l PAGE 1 l[ [ [ [

0F 2 ll 8

3 R'4S-0204 REV - 2 1 l l PAGE 16 0F 17- 1 I il I f I P

1

.w-.- .7' . -.

, , .w,.u....,._m, ym.m ,......,wm... y

I l I I I I

l ATTAC10d.ENT - 3 I l

' BASIC FLOW PATH AND DESCRIPTIONS l

. I 1

- 1 l I l l I

i l

i I

l w - r. o m T , t e n e r n n: a s l

I I

l  ??!OR *O *AU RIAl, PLACE 3 i IN0AP$t ATl0% l I lNTO CONTAINER

....... ....... FIN!5".IO

. ..... P400CC*

i I

I i** "*I **l

.- .,i l**

l ***"** I I t- - ...>.,...,.>.>.>.

i .e.

,-...e i - ,,  ;

l l.>.>.........>...>.i ....,q

.~ q gp g e.,.... g l

l  ! * ***l l*******l l*******I

....... ....... \

i

  • ENCAPSULAT!ON "A*IRIAL I l

u a ; TEN SE!NO ENCAPSCLATED l I

i l ?tter to encapsulatton the contatner will be prepared by insta11teg a sold / footer to support the stes cetag encapsulated. Once this mold / f ooter l is tn place the stem being encapsulated as than placed tate the contatner g l and the rematador of the encapsulation aatettal placed on top of the g stem complettng the env apsulation. I l

1 l

l BASIC TLOW PATN TOR OAW PROCESS l

l I 1 I i l

i  !

I P t.A.NT I I

i i l l I I l

I i 1 l ............. i ..............

1 j

l l l l 1 I hTT/ORY g I. i 1 SEOR10ATION i l l<=>.....< D.l SE013ATION j l

l l l TACILITY l i FACILITT l 1 1 j

I I I

l i I I g.........>.>...<.

.<.<.<.<.l I g

I l, . .............

l i ............. l' I l l I WN y l l l COMPACTA3II l l l COMPACTASIZ l l l l VASTE l<.<.<...>.>.>l WASTE l

! I I l l I g

i l

I "he waste which is generated by the plant will be sent to the <2 *0t/16t l' l

segeretton factlity or placed in the wet / dry segetation facility. Once l l the waste as dried, separated, and identified as radioactive estettal Lt as either processed as compactable or nos compactable waste. l I

I I

I I

I I I II I I I l ATTACIC".ENT l PAGE 2 ll l l l 1 3 l OF 2 ll RWS-0204 l REV - 2 l PAGE 17 0F 17 l 1 11 1 I I

-. - ~ _ - . - - . . , - - . . . . . . . .- - .

b

[@ MQ ~f o UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION y 7, p WASHING TON, D. C. 20656 k...../ JAN 2 41991 ATTENTION: Commission Licensees f

L

SUBJECT:

Waste Form Technical Position, Revision 1 t

The regulation, " Licensing Requirements for Land Disposal of Radioactive Waste," 10 CFR Part 61, establishes a waste classification system based on the radionuclide concentrations in the wastes.- Class B and C waste are rec,uired to-be stabilized. Class A wastes have lower concentrations and may be

! segregated without stabilization. Class A wastes may also be stabilized and i- disposed of with stabilized Class B and C wastes. All Class A liquid wastes, i however, require solidification or absorption to meet the free liquid.

} requirements. Structural stability is intended to ensure that the waste -

does not degrade and (a) promote slumping, collapse, or other failure of the l cap or cover over a near-surface disposai unit and thereby lead to water infiltration, or (b) impart a substantial increase in surface area of-the waste form that could lead to an increase in leach rate. Stability 's also a '

{ factor in limiting exposure to an inadvertent intruder since it provides

greater assurance that the waste form will be recognizable and nondispersable F during its hazardous lifetime. Structural stability of a waste form can be

- provided by the waste form itself (as with u.tivated stainless steel components), by processing the waste to a stable form (e.g., solidification),

or by emplacing the waste in a container or structure that provides stability

! (e.g.,highintegrity'containerorengineered, structure).

1

[ This technical position on waste form was initially developed-in-1983 to 4 provide guidance _to both fuel-cycle and non-fuel-cycle waste generators.on

! waste form test methods and results acceptable to the NRC staff for implementing l

the 10 CFR Part 61' waste form requirements. It has been used as an acceptable

approach for demonstrating compliance with the 10 CFR P_ art 61 waste stability j criteria.--This position includes guidance on (1).the processing of wastes into

!- an-acceptable,) stable waste form, (2) the design of acceptable high' integrity.

containers,(3 the.packagingof_filtercartridges,and(4)minimizationof radiation effects on organic ion-exchange. resins. The regulation,-10 CFR 20.311-(d)(1), requires waste generators;and processors to prepare wastes-that meet.the waste characteristics requirements of Part 61_(including the

! requirements for. structural stability)._ The recommendations and_ guidance

provided in this technical position are an acceptable method to demonstrate
waste stability. -0ne way of demonstrating conformance with_the-general-

. recommendations contained in this technical position.is to reference an approved Topical Report, because such reports-are reviewed and approved in -

accordance with the acceptance criteria contained in this technical position. ,

However, additional actions (e.g., plant-specific process control procedures) j by waste generators will be needed to demonstrate that a stabilized i plant-specific waste stream satisfies Part 61 waste form requirements.

i

? <

'9 h*

~ - , , . - . . - - - .-m. ,_.,,-.;.,. , , _ , . . . - = _ . - . ,,,,-,.,,,-.~.-%..,,,...,, ..m#,.--.e,ww..,-

- - . _ - - . _ _ - - - _ - . - - - - - - . - - - - ~ - - - - - _ - - _ _ _

N t i i-

~.

j Since the initial issuance of the Technical Position, it has been the intent of the NRC staff to provide additional guidance on waste form as it became necessary to address other pertinent waste form issues. One such issue involves the use of' cement to stabilize-low-level wastes. Field experience and laboratory testing of cement-solidified' low-level radioactive waste has indicated that some unique chemical and physical interactions can occur between l the cement constituents and the chemicals and compounds that can exist in the waste materials. Therefore, an appendix (Appendix "A") dealing with the qualification testing, performance confirmation and reporting of mishaps 4 involving cement-stabilized waste forms has been included in this revision to the Technical Position.

To provide more comprehensive guidance on cement stabilization of low-level radioactive waste, Appendix A addressed several areas of concern that were not considered in the May 1983, Revision 0, version of this Technical Position.

Thus, information and guidance on cement waste form specimen preparation, statistical sampling and analysis, waste characterization, process control program (PCP) specimen preparation and examination,' surveillance speciraens and reporting of mishaps are provided in Appendix A. The guidance provided in' Appendix A is the culmination of an extended period of study and information gathering and exchange between the NRC staff and representatives of various organizations, including government laboratories, the Advisory . Committee on Nuclear Waste (ACNW), cement processing vendors, other war.te form vendors, nuclear utilities, and state regulatory agencies. Especially useful in the development of the guidance in Appendix A was the information exchanged in a Workshop on Cement Stabilization of low-Level Radioactive Waste held in-June 1989. The Workshop proceedings have been published as an NRC report, NUREG/CP-0103, which is available from the following sources:

Superintendent of' Documents U.S. Government Printing Office l P.O. Box 37082

' Washington, DC 20013-7082 l

and National Technical Information Service l- Springfield,'VA 22161 The waste form technical position is attached to this-letter. Questions on the technical position paper may be referred to Dr. M. Tokar (301-492-0590), or to Hs, M. T. Adams (301-492-0505) of my~ staff. The information collections l

contained in the technical position have been approved under 0MB number 3150-0014.

  • d.

L Paul H. Lohaus, Chief e

Low-Level Waste Management Branch-Division of Low-Le' vel Waste Management and Decomissioning, NMSS

Enclosure:

As stated' a .-.---._a-. . _ - _ a . - ., - - - - ._.-.-.-a.._.

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