ML20082M006

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Rev 4 to RWS-0204, Radwaste Processing Control Program
ML20082M006
Person / Time
Site: River Bend Entergy icon.png
Issue date: 08/09/1991
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20082L993 List:
References
RWS-0204, RWS-204, NUDOCS 9109040505
Download: ML20082M006 (21)
v • d • e


Text

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RIVER BEND STATION APPROVAL SKEET STATION OPERATING PROCEDURES 30, RVS-0204 TITLE RADWASTE PROCESSING CONTROL PROGRAM ,

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SATETY LELATED YES NO TECENICAL REVIEW REQUIRED YES N0l X l Pgy. PAGES lNDEP. TECH. '

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I l l RADwAr .' PROCESSING CONTROL PROGRAM i ,

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-l l l l TABLE OF CONTENTS i l l l l l SECTION PAGE NO. l l l l l 1.0 PURPOSE / APPLICABILITY / SCOPE 2 I l l l l

2.0 REFERENCES

2 l  ;

I 3.0 RESPONSIBILITIES li  ;

l 4 l l l 1 I I 4.0 DEFINITIONS 4 l l l l  !

l 5.0 PROCEDURE 5 l I

I I ,

l 5.. General Requirement 5 l l 5.2 Solidification Process Control Program 7 l l 5.3 Dewatering Process Control Program 9 l l 5.4 Encapsulation Process Control Program 10 l  !

l 5.5 Dry Active Weste Process Control Program to l l l 1 6.0 ACCE.7ANCE CRITERIA 11 1 I I I 7.0 DOCIA TION 13 l ,

I l l  !

A_TTACHMENTS l I I r l ATTACHMENT 1 - EXAMPLE OF A WASTE SOLIDIFICATION DATA SHEET 14 l I I I l ATTACIDfENT 2 - EXAMPLE OF A DEVATERED DATA SHEET 17 l l l l ATTACIUiENT 2 - BASIC FIM PATH AND DESCRIPTIONS 19 l  !

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1.0 PURPOSE / APPLICABILITY / SCOPE 1.1 1he 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 wastes will l be accceplished in accordance with specifications set forth by the disposal facility, as well as state and federal regulations.

(Reference 2.34) 1.2 ite Radwaste Processing Control Program (RPCP) contains the sampling and testing methodology, analyses and formulation determination by which dewatering, solidification and packag a of wet and dry radioactive vaste is assured.

1.3 Changes to the Radwaste Processing Control Program (RPCP) will be done in accordancs with Reference 2.8. (Reference 2.41)

2.0 REFERENCES

2.1 ASTN Standard Part 13 2.2 ASTM Standard Part C39 2.3 BTP Final Vaste Classification and Vaste form Technical Position Paper 2.4 10 CFR 20, Standards for Protection against Radiation 2.5 10 CFR 61, Licensing r";uirements for Land Disposal of Radiative Material 2.6 RBS USAR 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 .sDM-0038, Rac active Waste Management Program l

2.11 COP-0019, Sarpling of Liquid Radwaste Sludge and Resin Holding l Tanks l

2.12 SOP-0108, Liquid Radwaste Processing 2.13 RSP-0009, ALARA Program Implementation 2.14 RSP-0200, Radiation Work Permits 2.15 RVS-0209, Conduct of Radwaste Vendor Services l

2.16 RWS-0304, Radioactive Waste Handling and Control RWS-0204 REV - 4 PAGE 2 0F 20

f 2.17 RVS 0307. Radioactive Vaste Segregation 2.18 RWS-0327 Shipping of Low Specific Activity (LSA) Radioactivo Material 2.19 SD OP-003, Chem Nuclear System Incorporated (CNSI) Process Control Program 2.20 SD 0P 003 518, Process Control Program for CNSI Cement Solidification Units 2.21 SD OP 026, Process Control Program for Cement /011 Solidification 2.22 DM OP-022, Process Control Program for CNSI Demineralization System 2.23 SD-0P-020, Operating Prccedure for CNSI Portable Cement Soliditication Unit Number 21 (PUS-C-21).

1 2.24 FO-0P-011 Dewatering Procedure for the 24-inch Diameter Pressure Deminera,12er Vessel Containing Activated Carbon 0.5% free Standing Vater.

2.25 F0-0P-009 Dewatering Procedure for CNSI 76-inch Diameter Pressure Demineralizers Containing Ion Exchange Resin.

2.26 FO-0P 032-51802, Setup and Oparating Procedure for the RDS-1000 Unit at River Bend Station 2.27 T0-0P 025, Dewatering Procedure for CMSI 24-inch Diameter Pressure Vessel 2.28 Chem Nuclear System Inc. Topical Report CNSI 2 (4313 01354-01P A) 2.29 RWS-0207, Radwasta Shipping Criteria 2.30 RVS-0211, General Performance Control for Radwaste 2.31 RWS-0203, Personnel Qualification for Radwaste Section 2.32 RVS-0206, Radwaste Scaling Factor Program 2.33 RVS-0310, Operation of the Nuclear Packaging Model VC-18000 waste compactor 2.34 Commitment Number C0736 2.3L Commitment Number 00721 2.36 Commitment Number 00740 2.57 Topical Report CNSI (DV-11118-D1-P-A? k 2.38 Topical Report CNSI (RDS 25506-01-P-A) l RVS-0204 REV - 4 PAGE 3 0F 20

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

r 2.39 USNRC Generic Letter 91-02  !

l 2.40 RBNP 004. Reporting Requirements 2.41 Commitment Number 03020 i f

2.42 Commitment 03090 l

2.43 Commitme.-t 08199 ,

3.0 gESPONSIBILITIES l 3.1 The Radwaste Supervisor /dowignee, is responsible for the implementa". ion of the Radwaste Processing Control Program in i accordance with Reference 2.10 enettring the Vendors Process Control Program (PCP) meets the requirements set forth by the NRC and is incorporated into the Radwaste Processing Control Program '

i prior to use.

3.2 The Radwaste Foreman is responsible for interfacing with I' contracted vendors and for preparina a weekly work plan (Reference 2.10). The purpose of this interface is to ensure the I timely and efficient processing of waste forms generated at River  ;

Bond Station. (Reference 2.43) i 3,3 All personnel working under this procedure shall know their  !

responsibilities to the ALARA Program in accordance with r Reference 2.13.

l 3.4 The Vendor is to ensure that the general design of the processing l equipment is in accordance with The Vendors Topical Report 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 be operated and inspected in accordanc< with the Vendors i Cperating Procedures.

3.5 The Vendor is to ensure that the chemicals and/or materials used in a particular waste processing method are equal to or better than that which is required by the Vendor's approved Process Control Program (PCP),

t 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 essentially constant physical and chemical characteristics (i.e.

the amount of vaste contained within a tank). If new waste is  ;

added to the waste being processed then a new batch !s created and further sampling is required.

RWS-0204 REV - 4 PAGE 4 0F 20  ;

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4.2 Dry Activated Vaste (DAV) - Any dry radioactive material (i.e. j contaminated tools, equipment, clothing, etc.) i 4.3 Dewatering - The process of removing liquids from wet radioactive 1 waste so that the form of waste is suitable for disposal. 1 4.4 Encapsulation The process of encapsulating solid radioactive l waste which is non uniform in size and cannot normally be  !

homogeneously mixed (i.e. filters, sources, etc.), j 4.5 Free Standing Liquid - Liquid which is still visible after f processing, or liquid drainable from the low point of a punctured i container. I

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4.6 High Integrity Container (HIC) - A polyethylene container which  !

has been approved for the type of waste being processed.  :

4.7 Prequalification Test Sample - Test conducted on laboratory l samples to demonstrate the ability to produce an acceptable waste form using the type of wet waste and solidification agent ,

expected. [

}

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

of the on site solidification agent and waste batch to produce an acceptable waste form using the parameters identified in tne PCP.

4.9 Solidification - The conversion of wet radioactive waste into a form which is suitable tor disposal. f t

4.10 System Description - A brief description and flow path diagram of ,

the process flow path can be found on Attachment 3.  !

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

4.12 Wet Radioactive Waste - Any radioactive liquid or liquid / solid i slurry which does not meet the burial site requirements for free t standing liquids (i.e. sludge, resin, evaporator bottoms.

  • contaminated oils etc ) r 5.0 PROCEDURE >

5.1 General Requirements f i

5.1.1 All processing of wet radioactive waste performed by a j vendor shall be done under an approved process control  !

program for the type of waste beine, processed. '

(Reference 2.35) 5.1.2 All solidification, dewatering and sampling activities i performed inside the RCA shall have an RWP in accordance ,

with Reference 2.14. '

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l RWS-0204 REV - 4 PAGE 5 0F 20  !

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5.t.3 For high activity waste being solidified. where nandling ,

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 physical and chemical

  • characteristics may be solidified. 3 5.1.4 As required by Reference 2.7, a Production Test Sample I shall be solidified from at lease -ne (1) out of every ten (10) batches of wet radioact- 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 r production level solidification batch will be subjected to: i
a. Standard 14 day immersion test in water and then
b. Compression test in accordance with Reference [

2.2. *

2. The vendor must demonstrate that the Production Test Sample parameters are essentially the same as the Prequalification Test Sample.  ;

5.1.6 As a minimum the Vendors PCP for dewatering procus shall ,

include and/or reference documentation necessary to ensure the dewatering process and equipment being used will i produce a waste form that will meet the disposal facilities I requirement for free standing liquids. This documentation [

shall be made available to RBS, as necessary.  !

5.1.7 As a minimum the Vendors PCP for Encapsulation Process j shall include and/or reference documentation necessary to '

ensure t'.. followingt  :

1. The Encapsulation Media satisfies the stability  !

requirements of Section B and C of Reference 2.3. j

2. The capability of maintaining at least a 500 PSI l" compression strength (giving credit for the structural strength of the waste material, i.e. filter i cartidges), j
3. The container or the Encapsulation Madia will not degrade within the prescribed time requirement. L 5.1. 8 - All documents shall be maintained in accordance with Reference 2.9 and/or Reference 2.29, as required. l l I

r RWS-0204 REV - 4 PAGE 6 0F 20 i

5.1.9 The Radwaste Department Quality Control Functions are performed in accordance with Reference 2.30. The RBS QA Dep'artment 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's used at RDS for disposal of radioactive waste l will be approved for the type of waste being processed.

This approval will be based on the chemical are physical limitations of the container and each HIC w'.11 be certified that it meets the acceptance criteria set . ' t..e disposal site being used.

5.1.11 Reference 2.32 provides instructions for developing scaling factors necessary for ensuring compliance with 10CFR61.

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

5.1.13 RBNP-040 controls the purchase of chemicals and provi es guidance for their use. All site personnel are trained to appropriately use chemicals. However, it should be cautioned that strong oxidizing agents in bulk amounts can cause exothermic reactions with ion exchange resins.

Therefore, if for any reason oxidizing agents are suspected of being introduced to a resin steam, then the Radwaste Supervisor / Designee shall be notified immediatel . j Chemistry shall be notified and an analysis performed to determine if a hazardous condition exista. (Reference 2.42) 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.

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

2. Chemistry shall obtain a representative sample of the waste batch fa accordance with Reference 2.11. This sample will be ussd for radiochemical analysis and to determine the quantity of oil in the batch of wasto.

Record this information on Attachment 1.

I RVS-0204 REV - 4 PAGE 7 0F 20 l

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5.2.2 Waste Classification *

1. ?rior to Solidification a Waste Classification will be [

performed, as outlined in Reference 2.18, on the waste batch. Record this information on Attachment 1.

(Reference 2.36) i NOTE i

The Waste classification and Vendor Production ,

Test solidification may be performed et the l same time.

l 5.2.3 Test Production Solidification i L

1. The Vendor will perform a test solidification of the '

I waste batch '.n accordance with the Vendors PCP. Prior  !

to the test solidification, the Vendor will obtain the l pH of the waste. Tiin pH of the waste will be l adjuntad, as necessary, to ensure it is within the i desired range for the PCP to be performed. The pH will be adjusted using the guidelines specified in the ,

Vendor's PCP. ,

, 2. If protreatment of the batch of waste is necessary, the test sample chall have the required pretreatment  !

prior to test sampie solidification, i

3. If the oil co->;teLi of the waste batch is greater than 1% by volume, secure solidification operations and
  • notify the Radwaste Supervisor. 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.

4 If any Production Test Sample fails to verify I solidification, the solidification of the batch under test shall be suspended until such time as additional Production Test Samples can be obtainea. Alternative  !

solidification parameters can be determined in accordance wi+.h the Radwaste Processing Control Program, and a subsequent test verifies l solidification. Solidification of the batch may then l- be resumed using the alternative solidification i

parameters determined by the Radwaste Processing

, Control Program. .

. 5. If the initial Production Test Sample from -2 batch of waste fails to verify solidification, obtain .

representative samples from each consecutive batch of i the same type of wet waste until at least 3 consecutive initial Production Test Sarples  !

demonstrate solidification.

k RWS-0204 REV - 4 PAGE 8 0F 20 r

6. If the provisions of the Radwaste Processing Control Program are not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site. Notify the Shift Supervisor in accordance with Reference 2.7.
7. If any free scanding liquid is observed on top of the test sample, decant the liquid into a volumetric beaker and record the amount of liquid. Calculate the percent of free standing liquid. Record this information on Attachment 1.

5,3 Dewstering 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.

5.3.2 Waste Classification

1. Vaste classification should be performed prior to transferring the waste batch to the container (if possible). .As a minimum, a waste classification shall be performed prior to sealing the container for shipment. The waste classification will be performed as outlined in Reference 2.18. (Reference 2.36)
2. If the vaste classification and/or the container content 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)

NOTE Vendor supplied dowatering records may be uned in place of Attachment 2.

i i

3. Use Attachment 2 to record thn resin dewatering information.

l RWS 0204 REV - 4 PAGE 9 0F 20 i

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S.4 Encapsulation Process Control Program - liigh activity filters,  !

Ir:adiated Components and other .terials which may require  !

encapsulation, i.e. lead; '

5.4.1 Sampling j

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 radiochemict! analysis and to determine the quantity of oil in the waste. t 5.4.2 Waste Classification  ;

1. Prior to encapsulation a waste classification will be performed, as outlined in Reference 2.18, on the wasta. (Reference 2.36) ,
2. If the waste classificatirn and/or item specific activity requires the final package to be a stable ,

waste form then an approved encapsulation PCP for i stable waste form will be used. If an approved PCP is '

not available then the item may be placed inside a k -

high integrity container (!!IC). (Reference 2.5) ,

NOTE Ensure adequate encapsulating material surrounds  !

the item being encapsulated.

3. Once the waste classification is completed the Radwaste Poreman will calculate the amount of '

encapsulation material needed. The calculation will '

be bar.ed on the dose rate of the item being encapsulated and the type of container being used.

5.5 Dry Active Waste 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 l

unobtainable then the nuclide distribution for the DAV Vaste Stream will be used for the identity and percent

! abundanca, l-5.5.2 Waste Classification

1. Vaste 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. (Reference 2.36)

RWS-0204 PlV - 4 PAGE 10 0F 20

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$,5.3 Packaging / Handling

1. DAW will be segregated and stored in accordance with Reference 2.16 and 2.17.
2. Compactable and noncompactable DAV 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:

1. The free standing liquid requirements for the disposal facility and
2. Stability requirements if it is evident from the physical appearance that the test sample will maintain its shape if removed froa the container.

6.1.2 Onco the test sample demonstrates an acceptable waste form and the waste classification is acceptable for near surface burial, solidification may be performed as per formulus stated in the Vendor's PCP and operating sequences specified in Reference 2.23.

6.1.3 Once solidification is completed the container will be stored in accordance with Reference 2.16 and prepared 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.

6.2.3 Once dowatering is completed the container will be stored in accordance with Reference 2.16 and prepared for shipment in accerdance 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 PCP and the free standing liquid requirement for the disposal site, 6.4 Dry Ac4 've Waste Process Control Program 6.4.1 The unste 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.

RWS-0204 REV - 4 PAGE 11 0F 20

6.5 Reporting of Conditions of Non Acceptance 6.5.1 Documentation of the following will be required in accordance with Reference 2.40 to be reported within 30 days of the incident to the NRC's Director of the Division of Low-Level Vaste Management and Decommissioning and to the designated State disposal-site regulatory authority as per Reference 2.39:

1. The failure of high-integrity containers used to ensure a stable waste fctm. Container failure can be evidenced by changed container dimensions, cracking, or damage resulting from mishandling (e.g., dropping or impacting against another object).
2. The misuse of high-integrity containers, evidenced by a quantity of free liquid greater than 1 percent of container volume or other misuse as prohibited by 10CFF61.56.
3. The production of a solidified Class B or C waste foru that has any of the following characteristics:
a. Conta. ins free liquid in quantities exceeding 0.5 percent of the volume of the waste,
b. Contains waste with radionuclides in concentrations exceeding those considered during waste form qualification testing accepted by the r1gulatory agency, which could lead to errors in-assessment of waste class.
c. Contains a significe.ntly different waste 1cading than that used in qualification testing accepted by the regulatory agency.
d. Contains chemical ingredients not present in qualification testing accepted by the regulatory agency, and those quantities are sufficient to unacceptably degrade the waste product.
e. Shows instability as evidenced by crumbling, cracking, spalling, voids, softening,.

l disintegration, nonhomogeneity, or dimensional -

changes .

f. Evidence of processing phenomena that exceeded l the limiting processing conditions identified in applicable topical reports on process control plans, e.g , foaming, temperature extremes ,

premature or slow hardening, and production of a i

volacile material.

l l

RVS-0204 REV - 4 PAGE 12 OT 20

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/ 7.0 DOCUMENTATION 7.1 Data sheets will be included in the file copy of the shipping 1 package, as required by the applicable shipping procedure. l 1D

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RWS-0204 REV - 4 PAGE 13 0F 20 l

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Batch No. r I l Dates

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-l 1. A. Prior Batch Sample Solidification -

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

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Evaporator Bottoms Date: I l _ Batch Not Chemical Wastes Datet Batch Not g l Resins Dates. Datch No  !

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l g l If sample is from an initial batch of waite, de.cribe waste stream below: .

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!!. Batch Samplej nM ysis A. Lab Results Sample Volume I

l pH of Wasta I  :

Ensure pH is within the desired I I l

range for the PCP being used. l i l

g l If greater than 1* refer to g Vasto 011 Content Section 5.2.3.3 0F RPCP. l l l Radionuclide Content i l

Waste Classification I i

l B. y W t_e,_Prattnatment I l l g pH l Identify agent used and quantity to adjust pH of the waste in the sample, g l )

j Agent / Quantity Adjusted pH value l

Performed by: Date:

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I III. Produttton Test Solidification (Required on at least every tenth I ,

I batch of each type of wet radioactive l l l wasta.) l l l

1 l A Test Solidification Tormula l  :

I Volume of Vaste: l I l ___

l l Volume of Binder: _,,,

I Volume of other ingredients:  !  !

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g B. Free Standina Water Analysis l g j Volume of Decanted Water _

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C. I l Solidificat ion Acceptabill_t,y l j l '

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1. Percent of free standing water calculated in Section Ill.B (above) must be less than disposal facility criteria.

l 2. Visual physical appearance: Ver!fy that the solidified waste 1 l sample would maintain its shape when removed from the container. l l

l l 3. 'Ihe above Acceptance Criteria satisfies RBS Technical Specification l l 3/4.11.3.

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4 I g Other (state additional results here) _

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A. 1 i l Formula (Per Drum Basis) l l Wast to be solidified (gallons) l .i

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I I I l

I I I l l I .

I I I I l l 1 i l l I I I '

I I I I ATTACHMENT' - 1 l PAGE 3 0F 3 i RWS-0204 { REV - 4 l PAGE 16 0F 20 l ,

I I _l- l __, I . _ , I 1

I

l l EXAMPLE OF l ATTACHMENT 2 l RESIN DEWATERING DATA SHEET l H I I L_ _ l 1 -

l RESIN DEWATERING DATA SHEET l I I i l Batch Number Vaste Prepared by: l 6 I I .

l lIIC / Liner Number: l i l 1. Sample Analysis l  :

l l '

l Sample Volume l ,

l l  !

l Vaste Oil Content  :

l l l

l l Radionuclide Content : l I I  !

l Vaste Classification : _ _ , , . l 1 l l l II. Additional Information l  :

1 I r l Type of Vessel Dewatered  : l  !

I  :

I l Type of Media being Dewatered  : l [

! l l Vessel Veight Empty  : , _ l l l l l Date Dewatering Accepted  :

_ l t i I  ;

lIII. Dewatering Acceptance Criteria l I I t l A. Bead Resin l l l l Length of time dewatering pump l l ran after final waste transfers hour (s) - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> minimum l l l t l Length of time RDS-1000 Unit j i l was operated: hour (s) - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> minimum l l l- I r 1 Maximum change in the moisture l l separator sight glass during '

l final 30 minute operation: '

l inches - 1/2 inch maximum j i 1 I Dewatered: [ } Satisfactory [ ] Unsatisfactory I i l I  ;

l Remarks:. l- i i l i l I  :

I I  !

-l l I I t i i I

l i I I ll l l 1 l ATTACHMENT l PAGE 1 ll l l l I I 2 ] 0F 2 ll RVS-0204 l REV - 4 l PAGE 17 0F 20 1 I_ I ll I I I

.L

e j

i l I l l EXAMPLE OF l l ATTACHMENT - 2 l RESIN DEWATERING DATA SHEET l 1 l- l l l l 1 l B. Precoat Media l l I i Length of time dewatering pump l re.n after final wsste transfer:

l hour (s) - I hout minimum l 1 I l Vith all lateral suction valves l l open, dewater rump suction (as Vacuum [ ] SAT [ ] UNSAT l l indicated on PI 4 or PI 8) is l l less than or equal to lo inches PI-4 / PI-8 (circle one) l l of mercury, after dewater pump l l is run for a minimum of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Value: inches Hg. l l l l Length of time RDS-1000 Unit l l was operated: hour (s) - 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> minimum j i l l Maximum change in the moisture l l separator sight glass during l I finst 30 minute operation: inches - 1 inch maximum l l l l Dewatered:

[ ] Satisfactory [ ] Unsatisfactory l 1 I I I I I l Remarks: l 1 I I I I I I ___ i l l 1 -

l I I i I i l l I l I I I I I I l l l Completed By: Date: l l l-1 I l Reviewed By: Date: l l 1 1 I i

l l-I I I I I I l l l 1 I I I ll 1 I i l ATTACILMT l PAGE 2 ll l l 1 l 2 l OF 2 ll RWS 0204 l REV - 4 l PAGE 18 0F 20 l l I ll l 1 I i

eo

  • l t

l I I l l l l ATTACRMENT 3 BASIC FLOV PATil AND DESCRIPTIONS i l l 1 I I  !

l l l  !

I I  :

l E83,JtCV P ATH FOR $0f,IDIFIC ATION PROCESS j l l .e.>. VASTt LIST TO LINTR n " n n n n '1 I  !

i l i I )

l t 1**<**** OMIM! CAL SUPPLY <*c-l l '

  • l .<.< < l jc.< DEVATERING LINEAL i l l ( j l l. .1 l i I J l l

l l 1 l.__.l f _ l i I l l VENDCR$ l .

l l FILI.HIAD l I l l i i_ l l l ....j.......... 4l.... l-l [

! _l l l. l %T.NDCRS LINER l l l l l l= ....l.... g_ l .............  ?

l l l l DEVATER l 1 l CHEM! CAL l l l l l<*l PLHP l l l 8U12 l i

l l SK!D l 1 l l TRA! LEA l

)

'I I I  ;

l l Vet radioactive waste are normally trat.sterred to the vendor from the phase l ,

l separator tatiks, backwash tank and/or waste sludge taak. This todioactive l t l weste in dowatered using the vendors dowaterstig skid which discharget, liquid l f g to the floor drain systes. Once the vendors liner 12 full the wet radioactive g  ;

I-waste is sized with chemicals f ec>e the vendors bulk trailer and solidified  !

in accordance with the vendors PCP. I i i l i l I  !

BASIC FLOV PATH TOR OtVATERINO PRott$8 l

.bn VASTE t!NE TO LINER nunnunul I -

1 I I

1. - 1 I
l. <.4.<=l j< < DEVATERING LINT . )-

l l 1 1 I I l l  ;

l 1 i j

.I i j  ;

,' l l VENDOR 5 l

.l l l l FILLHIAD l I 5 l

l l ....j. ..........l.... l i L jy ,

l L!hTR/ HIC l .

_g ....l.... l l j g l - DEVATER l l' l [

l<- PtmP l -

l  !

l $K!D l l  !' I I I .

I I l- I +

l :l Vet radieestive waste are transferred to a liner lf l L

g from the phase sepet ator tanka, backwash-tank and/or weste aludge tank. g t This wet radioactive weste may be dowatered using the vendors dowatering skid i l or stallar type equipe nl which discharges liquide to the floor drain systee. 1

[

l Portable disposal fre~asura Vessels are notes 11y dowatered la accordance with l  ;

l the Vendors Prc<ess Control Program. l -i l I I I I- 1 II I I I

-l ATTAC10ff.NT l PAGE 1 ll . l l l 1

-l 3 l OF 2 ll RVS-0204 l REV - 4 l PAGE 19 0F 20 l l _l lI I I .I i i

I' I

L _

i: -[

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

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- - - - 1 l l [

l l I l ArrACllMENT

  • 3 l BASIC F1,0W PATH AND DESCRIPTIONS l i

t l l l i l I  !

I I l l IA$1C FWV PA*Hl0# twCAP$l"JT!0N P90CW l t i l i l PR!!R TO *AITRIAL PLA0tD I

l t s:APstuT::n.  : m = m :stR rtN!sato rR0euCT  !

....... .... .. l l  :.. --; .. l l

..i J.... .; i i  ! +, i wu -. : I.. I

. .t l } r. auj.n.p.m.p.s....... 4,s u d 9 5 A.8.A.D.P.D.).).).f..g$gh l p ,. ... l ,.."..~...l i.......; j

mn,....g .......,

,..... l l ....... .......  ;

l....***j l ....... I I I l *

  • ENCAP$tLAT!0N 9AitR!AL
  1. . gTts ggtso gNc4PstLATgp l  ;

i g i

l Prior to encapsulatsen the :entainer .sli :e prepared by tr.stallica a I l Sold /lcoter to support tre stes tears encaptalated. Once this mold / footer l l ts in place the stem betrg encatt44tes is then placed into the contanner .

and the reesinder of the encapsi.tetten +4tertal placed on top of the l I tie. coepieting the encapsulat.on g -

l I  :

l l t 9& E FLOW PATW r*R Dav Pf40Ct$$ L l

l ..... ..... I j l l l t i l I l PLANT l I I l I '

I '

i i I I I 1

l ............. I j ..............  ;

I I I I I I j i

) t i  ! wtT/0RY I l l l $tCRtGATION le >a=*=*****1 5tGREGAT10N l l l FACIL!iY I

I l rACILITY l l i 1 I I I l l I I l.s.n. .>.>. ...c.e.e.e.e.<.Il l s

f I i I i ............. .............

i i ,

l l l l l NON l l ,

g i COMPACTAl!.E l 1 l COMPACTABLE l  :

Vasti, l<*< <* l l >a***l VASTE l

!' I I l l g

l ............. l-1 I  !

! The weste which tr generated by the plant stil be sent to the <2 MRb0t I segregation facility or placed to the wet / cry segregation festlity. Once  !

l the waste is dried, separated, and tdentafted as radioactive esterial l g it is either processed se coep(stable or non compactable waste.

l l . I I I 11 I I I  ;

l A'ITACILMENT l PAGE 2 ll l l I '

3 l OF 2 ll RWS-0204 l REV - 4 l PAGE 'O OF 20 l  ;

i I iI .j l I i 9

t

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