RBG-26673, Forwards Rev 2 to Radwaste Processing Control Program, for Review & Approval,Per NUREG-0989

Forwards Rev 2 to Radwaste Processing Control Program, for Review & Approval,Per NUREG-0989

ML20235J215
Person / Time
Site:	River Bend
Issue date:	09/21/1987
From:	Booker J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0989, RTR-NUREG-989 RBG-26673, NUDOCS 8710010354
Download: ML20235J215 (1)

Text

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et GULF STATES UTILITIES COMI'ANY IUVf R tlF ND ST AhDN POST Of flCE BOX 220 ST FRANClbVILLE. LOUISIANA '/0775 ARE A CODE 504 635 60 % 346 8651 September 21, 1987 RBG-26673 e h

File No. G9.5 9 to

$ C U.S. Nuclear legulatory Commission

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Document Control Desk Washington, D.C. 20555 r$

i Gentlemen: j River Bend Station - Unit 1 i Docket No. 50-458 1 On July 16, 1987, Gulf States Utilities Company (GSU) submitted for i your review and requested your approval of a revised Process Control Program (PCP) in accordance with Section 11.4 of the Safety Evaluation Report for River Bend Station (NUREG-0989).

As a result of recent discussions with the NRC Staff, the enclosed PCP has been further revised and is resubmitted for your review and approval.

Any questiers or comments should be directed to our Mr. James Cook at 4 (504) 381-4151. -

1 Sincerely, l l

8710010354 870921 ,

[ hrgdA,/

PDR ADOCK050g8 P J. E. Booker l Manager, River Bend Oversight l River Bend Nuclear Group  !

JEB/E C/ch Enclosure cc: Robert D. Martin, Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611RyanPlazaDrive, Suite 100p Arlington, TX 76011

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NRC Senior Resident Inspector Post Office Box 1051 kp ,'I St. Francisville LA 70775 .

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.- l- 1 l RADWASTE PROCESSING CONTROL PROGRAM l l l i l l-l /

l 2 I I l TABLE OF CONTENTS l l l l l l SECTION PAGE NO. l .

I I I l 1.0 PURPOSE / APPLICABILITY / SCOPE 2 l j l I l

2.0 REFERENCES

2 l 1 I I I l 3.0 RESPONSIBILITIES 3 l )

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l 1 l 4.0 DEFINITIONS 4 I I I l 5.0 PROCEDURE 5 l 1 l l 5.1 General Requirement 5 l 4

l 5.2 Solidification Process Control Program 6 l l 5.3 Dewatering Process Control Program 8 I l 5.4 Encapsulation Process Control Program 9 l l 5.5 Dry Active Waste Process Control Program 10 l 1 l l 6.0 ACCEPTABLE CRITERIA 10 l 1 l l 7.0 DOCUMENTATION 11 l l l l ATTACHMENTS l

1 l l ATTACHMENT 1 - EXAMPLE OF A WASTE SOLIDIFICATION DATA SHEET 12 l l

1 l ATTACHMENT 2 - FXAMPLE OF A DEWATERED DATA SHEET 15 l l l l ATTACHMENT 3 - BASIC FLOW PATH AND DESCRIPTIONS 16 l 1

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1 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 '

I processing and packaging of wet and dry radioactive waste will be I accomplished in accordance with specifications set forth by the f disposal facility, as well as state and federal regulations. i

.i 1.2 The Radwaste Processing Control Program (RPCP) contains the {

sampling and testing methodology, analyses and formulation  !

determination by which dewatering, solidification and 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

l 2.1 ASTM Standard Part 13

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i 2.2 ASTM Standard Part C39

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2.3 BTP Final Waste Classification and Waste Form Technical Position Paper j i

2.4 10 CFR 20, Standards for Protection against Radiation  !

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2.5 10 CFR 61, Licensing requirements for Land Disposal of Radiative 1

Material 1

2.6 RBS FSAR 11.4, Radioactive Solid Waste System

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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 Waste Handling and Control f

RWS-0204 REV - 2 PAGE 2 0F 17

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-2.17 RWS-0307, Radioactive Waste Segregation  !

2.18 RC -0327, Shipping of Low Specific' Activity..(LSA) Radioactive' ,

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Material i 1

2.19 SD-0P-003,. Chem Nuclear System Incorporated (CNSI) Process Control Program

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2.20 SD-OP-003-518,-Process Control Program for.CNSI Cement .

Solidification Units i

2.21 SD-0P-026, Process Control Program for Cement /011 So11dification' 2.22 DM-0P-022, Process Control Program for CNSI Demineralization System

.1 2.23 SD-0P-020, Operating Procedure for CNSI Portable Cement Solidification Unit Number 21'(PUS-C-21). )

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

2.25 FO-OP-009, Dewatering Procedure for CNSI 76-inch Diameter 4 Pressure Demineralizers Containing Ion Exchange Resin. I 2.26 F0-OP-023, Dewatering Procedure for CNSI 14-195 or Smaller Liners 2.27 FO-OP-025, Dewatering Procedure for CNSI 24-ir.ch Diameter Pressure Vessel l

t 2.28 Chem Nuclear System Inc. Topical Report CNSI-2 (4313-01354-01P-A) 1 2.29 RWS-0207, Radwaste Shipping Criteria 2.30 RWS-0211, General Performance Control for P.adwaste.

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 3.0 RESPONSIBILITIES 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-the requirements set forth by the NRC and is incorporated into  ;

the Radwaste Processing Control Program prior to use. '

3.2 ine 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 l

l. _ _ - _ - _ _ _ _ _ _ _ _ _ - _ _ - _

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i All personnel working under this procedure shall know their.

3.3 responsibilities to the ALARA Program in accordance with i Reference 2.13. /

l 3.4 The Vendor is to ensure the general design of the solidification i equipment is in accordance with Reference 2.28 and this equipment {

is installed, and tested in accordance with Referer.ce 2.15. J Operability shall be demonstrated prior to initital startup of the vendors equipment. Vendor's equipment shall be operated and inspected in accordance with Reference 2.23.

3.5 The Vendor is to ensure that the chemicals and/or material j l composition being used for solidification is equal to or better 1 l than required by the vendors PCP.

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3.6 Vendor and plant personnel performing work for the Radwaste Department shall be qualified in accordance with Reference 2.15 l 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 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 (DAW) - Any dry radioactive material (i.e.

contaminated tools, equipment, clothing, etc.)

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

l 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 ect.).

4.5 Free Standing Liquid - Liquid which is still visible after.

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

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

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has been approved for the type of waste being processed.

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

4.8 Production Test Sample - A sample used to demonstrate the ability I of the on site solidification agent and waste batch to produce an ]

acceptable waste form using the parameters identified in the PCP.

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

RVS-0204 REV - 2 PAGE 4 0F 17 j

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J 4.10 System Description - A brief description and flow path diagram of f process flow path can be found on Attachment 3. ,

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

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

5.0 PROCEDURE i

5.1 General Requirements 1

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

l 5.1.2 All solidification, dewatering and sampling activities performed inside the RCA will have an RWP in accordance with Reference 2.14. j 5.1.3 For high activity waste being solidified, where handling  ;

of the production test sample could result in personnel j radiation exposure that is inconsistent with the ALARA J principles, a non-radioactive test sample having )

i essentially the same physical and chemical )

l characteristics may be solidified.

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

1 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: l

a. Standard 14 day immersion test in water and then

b. Compression test in accordance with Reference 2.2.

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

4 RWS-0204 PEV - 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.

i 5.1.7 As a minimum the vendors PCP for Encapsulation Process j 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 i 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.

I 5.1.8 All documents shall be maintained in accordance with i 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 l 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 weste 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 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, 5.2 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.

Recor,d thi: information on Attachment 1.

RWS-0204 REV 2 PAGE 6 0F 17 E-___________

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NOTE ]

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

2. Chemistry shall obtain a representative sample of I 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 'I waste. Record this information on Attachment 1. i l S.2.2 Waste Classification j

1. Prior to Solidification a Waste Classification will be performed, as outlined in Reference 2.18,'on.the- :l 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 solidification of the waste batch in accordance with the Vendors PCP.

Prior to the test solidification the Vendor will

• obtain the pH of the waste and adjust as necessary.

Record this information on Attachment 1.

2. If retreatment of the batch of waste is necessary, the test sample shall have the required retreatment prior to test sample solidification.

3. If the oil content of the waste batch is greater than 1% by volume, secure solidification operation and notify the Radwaste Supervisor.

NOTE 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 I with oil content greater than 8% by volume.

RWS-0204 REV - 2 PAGE 7 0F 17 w_____- _ . _ _ _ - _ _ _ _ _ - - - - _ _ . . _ _ _ _ _ _ . _ _ -

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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 can be obtained,-

. alternative solidification parameters.canfbe 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 fails to verify SOLIDIFICATION. Obtain representative samples from each consecutive batch' of the same type of wet waste until at least 3 consecutive initial Production Test-Samples 1 l demonstrate SOLIDIFICATION.

' 6. 'With the provisions of the'RADWASTE PROCESSING' CONTROL PROGRAM 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 standing 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 l information on Attachment 1.

5.3 Dewatering Process Control Program-(Portable disposal Pressure Vessels / Liners / HIC's) l- 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 i; 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 shall be performed prior to sealing the container for ihlpment. Tne waste classification will be performed'as outlined in Reference 2.18. Record this information on Attachment 2.  :

RWS-0204 REV - 2 PAGE 8 0F 17

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2. If~the waste' classification and/or the container T

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' content activity requiresjthe waste; batch to.be d classified as a / stable waste form, then th'e' waste I shall be packaged in a High Integrity container .{

'(HIC). (Reference-2.5) ij l

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 J 1

5 . 4 ~.1 Sampling '

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! 1. -Chemistry shall obtain a sample of the waste to be I l encapsulated. This sample will be either a qualitative'or a quantitative sample. .'This sample- 3 will-be used for radiochemical analysis and to

determine the quantity of oil in the' waste.

5.4.2 Waste Classification t

1. Prior to encapsulation a waste classification will be performed..as outlined in Reference 2.18, on the. I waste. l b

2. If the waste classification and/or item specific i activity requires the final package to be a stable :j waste form then an' approved encapsulation PCP for

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j stable waste form will be used. If an approved PCP is not available then the item may-be encapsulated:

inside a high integrity. container'(HIC). (Reference 2.5)

3. Once the waste classification is; completed the Radwaste Specialist / Foreman will calculate the cmount of encapsulation material needed. The calculation will be based on the dose rate of the item being encapsulated and the type of container being used.

.J NOTE Ensure adequate encapsulating material surrounds the item being encapsulated.

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5.5 Dry Active Waste Process Control Program j 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 DAW Waste Stream will be used for the identity and j percent abundance. '

5.5.2 Waste Classification

1. A waste classification should be performed prior to  ;

transferring the waste' batch to the container. As a

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minimum a waste classification shall be performed prior to shipment. The waste classification will be j

performed, as outlined in Reference 2.18.

5.5.3 Packaging / Handling

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1. DAW will be segregated and stored in accordance with j

! Reference 2.16 and 2.17.

2. Compactable and noncompactable DAW should be packaged in accordance with Reference 2.33 and 2.17.

l 6.0 ACCEPTANCE CRITERIA l l

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 stability requirements if it is evident from the physical appearance that the test sample maintains its shape if removed from the container.

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 specified 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 ?. 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 1 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 PCP and.

the free standing liquid requirement for the disposal 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.

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[. l EXAMPLE OF l l

l' ATTACHMENT.- 1 l WASTE SOLIDIFICATION DATA SHEET i l l l I I

.l-I WASTE SOLIDIFICATION DATA SHEET -

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.I I .j 1 Batch No. : i!

l Date:

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.} /repared By: '

l-I. A. Prior Batch Sample Solidification . .

-Verify prior. batch sample solidification performed. Check one below and l.

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,I show date and batch number of sample. I I' Evaporator Bottoms Date: Batch No:

I I' Chemical Vastes Date: Batch No:

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l' Resins Date: Batch No: }L 1

Other l J l

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l B. Initial Batch Sample Solidification j

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

! II, Batch Sample Analysis- '

l I . Lab Results 'I l l l n

l .1 Sample Volume i

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I l pH of Waste l I I If greater than' 1*; refer to r l I g Waste Oil Content Section 5.2.2.3 CF RPCP. I i

l Radionuclides Cont.ent Waste Classification l B. Weste Retreatment i I l pH - Identify agent used and quantity to adjust pH of the waste in I

[ the sample. I I I g Agent / Quantity Adjusted pH value l Performed by: Date:

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l l-1 I I I I I I I I I I I I I I I I I I I I I I l I 1 l ATTACHMENT - 1 l PAGE 1 0F .3 l RWS-0204 l REV-- 2 l PAGE 12 0F 17 l t_ i i 1 -I i

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EXAMPLE OF l

j. ATTACHMENT - 1 l WASTE SOLIDIFICATION DATA SHEET l I I I l' l I l l-1 III. Production Test Solidification (Required on at=least every tenth I

batch of each type of wet radioactive waste.)-

l A Test Solidification Formula; I' I l l '

l Volume of Waste: I I I l

Volume of, Binder:

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!< l -I g Volume of other ingredients:_

l Waste / Binder Ratic:

I Binc!er/ Ingredient Ratio: I I  !

l Total. Volume: l I l  !.

' l B. Free-Standing Water Analysis:

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l l l g Volume of Decanted Water l

Volume of Sample:

l *. Free-Standing Water:  !

I I l C. Solidification Acceptability I i l i I l

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

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

l l 2. Visual physical appearance: Verify that the solidified waste l would maintain its shape if removed from the container.

I 3. The above Acceptance Criteria satisfies RBS Technical Specification I I

l 3/4.11.3. I l l l 4 Other (sr.t.e n'ditional results here) _ l 1 I I I  ;

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Performed By: Date: I '

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! IV. Batch Solidification I I I l A. Formula (Per Drum Basis) l I I l Waste to be solidified (gallons) l l

l l Binder added (pounds) l l

g Other ingredient (added) l g

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l 1 I I 1 I I I I I Performed By: Date: l l

l l Reviewed By: Date: l.

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l l EXAMPLE OF l l ATTACHMENT - 2 l RESIN DEWATERING DATA SHEET l

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I I I I RESIN DEWATERING DATA SHEET I ,

l Batch No.: I-l Date: l l Prepared By: l l l l l l I. Sample Analysis l l l  !

l Sample Volume 1 1 I  ;

I Waste Oil Content l I I l Radionuclides Content 1  !

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I Waste Classification l .l I I l i I lII. Vessel Information l l l l Type of Vesnel being Dewatered l-1 I l Vessel Serial Number i .

I I l Number of pumping cycles l 1 l 1 l Volume of water collected during final pumping cycle l l l l l Limit of remaining liquids for this type of vessel l l l l l l  !

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l Remarks: I l I I I I I I I I I I I l

l Completed By: Date: l 1 l I I I Reviewed By: Date: I I I I I I I 1 I I l i I I I I I I ll l l l l l ATTACHMENT l PAGE 1 ll l l l l

l 2 l OF 1 II RWS-0204 I REV - 2 l PAGE 15 0F 17 l l l ll ,

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.l. ATTAClefENT' '.3 l BASIC FLOW PATH AND DESCRIPTIONS l' 4 l l l if

' 'lu I BASIC TLOW PATH TOR SOLIDIFICATION PROCESS - _j.

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

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l. ] l--<-<-< CHEMICAL SUPPLY-<-<-l l y l~ -<-<4<-l !l<-< DEWATERING LINE-l: l"l '

'l' l l l l' l. ll l- l l .l l _l' l_1 _ l- I

g. l' - l VENDORS l '

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l FILLMEAD l l~ 'g 3 . .... ............l.... l

-l' l l l- VENDORS LINER ' l l y ,

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q l f .li l DEWATER l l l l CHEMICAL' l .l )

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TRAILER l-l "l l

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Wet radioactive waste are normally transferred to the vendor from the phase - -

l separator tanks, backwash tank and/or waste sludge tank. This radioactive ,

g!  !

l. waste is dewatered using the vendors dewatering skid which discharges' liquid j

.l to the' floor drain system. Once the vendors liner.is full, the wet radioactive I-'

l waste-is mixed with chemicals form the vendors bulk trailer and solidified, l In accordance with the vendors PCP.

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BASIC TLOW PATH TOR DEWATERING PROCESS o i i 1 l ->->- WASTE LINE TO LINER >->->->.> >->-l l ~

l 'I I i l l 1: i l -<-<-<-l l<-< DEWATERING LINE-l l l l l i .

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! l 1 l l l VENDORS- l  !

l l l l l TILLHEAD 1 i l l l ....l............l.... l J l l l LINER / HIC l. I

i ....l.... i l l l l DEWATER l l l l 1; l

l<-l PUMP { -l l l  !

l l SKID .........

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l l l u l River Bend does not normally dewater resin but has the capability to do so.  !.

l To perform dewatering, wet radioactive waste'are transferred to a liner 'l l l from the phase separator tanks, backwash tank and/or waste sludge tank. I i g This wet radioactive waste may be dewatered using the vendors dewatering skid l j

.g or similar type equipment which discharges liquids to the floor drain system. l l Portable disposal Pressure Vessels are normally dewatered in accordance with  !

the Vendors Process Control Program, g g j

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'l ATTAC10fENT l PAGE 1 ll l ,

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l g I f The waste which is generated by the plant will be sent to the <2 MR/HR l segeration facility or placed in the wet / dry segeration facility. Once }

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