RBG-26274, Forwards Rev 2 to RWS-0204, Radwaste Processing Control Program, Per NUREG-0989.Requests NRC Approval by 871015 So That Revised Program Can Be Implemented Prior to Startup After First Refueling Outage

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Forwards Rev 2 to RWS-0204, Radwaste Processing Control Program, Per NUREG-0989.Requests NRC Approval by 871015 So That Revised Program Can Be Implemented Prior to Startup After First Refueling Outage
ML20235Z157
Person / Time
Site: River Bend Entergy icon.png
Issue date: 07/16/1987
From: Booker J
GULF STATES UTILITIES CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20235Y062 List:
References
RTR-NUREG-0989, RTR-NUREG-989 RBG-26274, NUDOCS 8707270202
Download: ML20235Z157 (1)
v • d • e


Text

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~l 1-l- RADVASTE PROCESSING CONTROL PROGRAM l l l l 1 1 I I I l TABLE OF CONTENTS l l l l 1 l SECTION PAGE NO. I I I i 1.0. PURPOSE / APPLICABILITY / SCOPE 2 l l l l

2.0 REFERENCES

2 I r I I l 3.0 RESPOCIBILITIES 3 l l l l 4.0 DEFINITIC M 4 I I I I 5.0 ' PROCEDURE 5' l l l l 5.1 ' General Requirement .5 l l 5.2 Solidification Process Control Program 6 l l 5.3 Dewatering Process Centrol Program 8 l l 5.4 Encapsulation Process' Control Program 9 ,l l 5.5 Dry Active Waste Process' Control ~ Program 9 l.

I I I 6.0 ACCEPTABLE CRITERIA 10 l l l l l l ATTACHMENTS l

l 'l l ATTACHMENT 1 - EXAMPLE OF A WASTE SOLIDIFICATION DATA SHEET 12 l l 1-l ATTACHMENT 2 - EXAMPLE OF A DEWATERED DATA SHEET 15 l-1 I l- ATTACHMENT 3 - BASIC FLOW PATH AND DESCRIPTIONS 16 I .j i l-  !

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1.0 PURPOSE / APPLICABILITY / SCOPE 1.1 The purpose of the Radwaste Processing Control Program (RPCP) is to provide reasonable assurance and documentation 1. hat 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 regu.'ations.

1.2 The Radwaste Processing Control Program (RPCP) containt the sampling and testing methodology, analyses and formulati n determination by which dewatering, solidification and pacraging 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

j 2.1 ASTM Standard Part 13 2.2 ASTM Standard Part C39 2.3 BTP Final Waste Classification and Waste Form Technical Position Paper 2.4 10 CFR 20, Standards for Protection against Radiation i 2.5 10 CFR 61, Licensing requirements for Land Di'posallof Radiative Material  !

i 2.6 RBS FSAR 11.4, Radioactive Solid Waste System j 2.7 RBS Technical Specification 3/4.11.3 I

2.8 RBS Technical Specification 6.13 -l 2.9 ADM-0006, Control of Plant Records 2.10 ADM-0038, Radioactive Waste Management Program j i

2.11 COP-0019,. Sampling of Liquid Radwaste Sludge and Resin Holding I 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 RWS-0204 REV - 2 PAGE 2 0F 17

1 2.17 RWS-0307, Radioactive Waste Segregation 2.18 RWS-0327, Shipping of I;ow Specific Activity (LSA) Radioactive Material 2.19 SD-0P-003, Chem Nuclear System Incorporated (CNSI) Process j Control Program 2.20 SD-0P-003-518, Process Control Program for CNSI Cement Solidification Units 2.21 SD-0P-026, Process Control Program for Cement /011 Solidification 2.22 DM-0P-022, Process Control Program for CNSI Demineralization System ,

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2.23 SD-0P-020, Operating Procedure for CNSI Portable Cement {

! Solidification Unit Number 21 (PUS-C-21).

2.24 FO-0P-011, Dewatering Procedure for the 24-inch Diameter Pressure Demineralized Vessel Containing Activated Carbon 0.5% Free Standing Water. (

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

2.26 FO-0P-023, Dewatering Procedure for CNSI 14-195 or Smaller Liners 2.27 FO-OP-025, Dewatering Procedure for CNSI 24-inch Diameter Pressure Vessel 2.28 Chem Nuclear System Inc. Topicel 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 l

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

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l RWS-0204 REV - 2 PAGE 3 0F 17

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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 be operated and inspected in accordance wi+h Reference 2.23.

3.5 The Vendor is to ensure that the chemicals and/or material composition being used fcr 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 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.)

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

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

4.5 Free Standing Liquid - Liquid which is still visible after l processing, or liquid drainable from the lov point of a punctured ]

container. J 4.6 High Integrity Container (HIC) - A polyethylene container which l has been approved for the type of taste 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 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 the PCP, 4.9 Solidification - The conversion of wet' radioactive waste into a form which is suitable for disposal.

RWS-0204 REV - 2 .PAGE 4 0F 17

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

i 4.11 Waste Classification - The determination of waste class as outlined in Reference 2.5 by radionuclides 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 standing liquids (i.e. sludge, resin, evaporator bottoms, contaminated oils etc.)

5.0 PROCEDURE I

5.1 General Requirements 5.1.1 All processing of wet radioactive waste perforened by a ,

vendor shall be done under an approved process control l program for the type of waste being processed.

5.1.2 All solidification, dewatering and sampling activities performed inside the RCA will have an RWP in accordance with Reference 2.14.

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 essentia13y the same physical and chemical characteristics may be solidified.

i 5.1.4 As required by Reference 2.7, a Production Test Sample  !

shall be solidified from at lease 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 Prequalification Test Sample to be subjected to a compression test in accordance with Reference 2.2. 3 l
2. A standard 14 day immersion test in water. '
3. The vendor must demonstrate that the production test sample parameters are the same as the Prequalification Test Sample, j l

5.1.6 As a minimum the Vendors PCP for dewatering process shall {

include and/or reference documentation necessary to j ensure the dewatering process and equipment being used  !

will produce a waste form that will' meet the disposal )

fac111 tics requirement for free standing liquids. This documentation should be made available to RBS.

RWS-0204 REV - 2 PAGE 5 0F 17

l 5.1.7 As a minimum the vendors PCP for Encapsulation Proce.ss 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 ']

r.tructural strength of the_ waste material, i.e. ,

filter cartidges). )

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3. Demonstrate that the container or the Encapsulation ~ j Media will not degrade within the prescribed time d requirement. 1 l

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

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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 i 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.

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This approval will be based on the chemical and physical l 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 I scaling factors necessary for ensuring compliance with j 10CFR61.

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

J 5.2 Solidification Process Control Program l I

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 i

To keep personal radiation exposure ALARA,  !

the sample taken may be used for both vendors test solidification and chemistry isotopic analyses.

RWS-0204 REV - 2 PAGE 6 0F 17 l

2. 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 1, 5.2.2 Waste Classification

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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 solidification of the waste batch in accordance with the Vendors PCP. )

Prior to the test solidification the Vendor will obtain th~e pH of the waste and adjust as necessary. {

lt Record this information on Attachment 1.

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2. If retreatment of the batch of waste is necessary, {'

the test sample shall have the required retreatment prior to test sample solidification, j

3. If the oil content of the waste batch is greater '

than 1% by volume, secure solidification operation and notify the Radwaste Supervisor.

3 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.

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 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 b; the Radwaste  :

Processing Control Program.

RWS-0204 REV - 2 PAGE 7 OF 17

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5. If the initia! Production Test Sample from a batch  !

of waste fai2e to veriff SOLIDI.FinATION. Obtain representative samples frota sach consecutive batch of the saee type of ret waste until at leant 3 l onsecutive initial Production Test Samples demonstrate SOLIDIFICATIDs. {

6. With the provisions of tha hADWASTE PROCESSING CONTROL PROGRAM not sBtisfied, suspend shipments of defectively processed or defectively packagad solid radioacti"e wastes from the site. Notify tra Shift Supervisor in accordance with Reference 2.7.
7. If any free standing liquid is observed on top of.

the .tcet sample, decent the Iiquid into a voluaetric t beaker and record the amount of Ilquid. Calculate the percent of free a tar. ding ligold. Eccord this informaticu on Attachment 1.

5.3 Dewatering Process Control Program _

5.3.1 Sampling

1. Chemistry shall obtafr 6 representative sample of the waste b,ttch in accorc'anct wiCa 2eference 2.11.

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l This sampic will be used for radiochemical analysic and to determins the quantity of oil in the batch of )

waste. Record this information on Attachment 2.

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l 5.3.2 Warte Cla;sification 1

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 shipasnt. The waste classification wil? be performed as outlined in Reference 2.18. Record this information on Attachment 2.
2. If the waste classification and/or the container conte.nt 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) l l 3. The Vendor will supply the information needed to i complete Section II of Attachment 2.

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RWS-0204 REV - 2 PAGE 8 0F 17

5.4 Encapsulation Process Control Program 5.4.1 Ssapling >

). Chemistry shall obtain a saepic of the waste to be encapsulated. This sample will be either e qualitative or a quantitative sample. This sample will be used for radiochemical anaiysis cnd to i determine the quantity of oil in the war.te.

5.4.2' Waste C.! assificatter.

1. Prior to encapsulation a waste clesritication will be perfonted, as oc. Lined in Referense 2'.18, on the j waste. j
2. If the waste classification and/o r item specific actkvity requires the final package to to a stabic .

weste form then an approved encapsulation PCP for I stable waste form will be uged. YF an approved PCP is ncn available then the item may tu cncapsula'ced inside s high integzaty container (HICL. (Reference 2.5)

3. Once the waste classification is completed tha-Rsdwaste Specialist / Foreman will calculate the amount of encapsulation material needed. Tan calculation vill ne based on the dose rate of tke- 1 ityp being encapsulated and the type tof container being used.

NOTE' Ensure adequate encapsulating material surrounds 'the item being Encapsulated, j q

i 5.5 Dry Active Wast.e Process Control Program j 5.5.1 Sampling

1. Chnmistry will analyze a s>sple of' the weste tu be packagad (if possible). If a sample'of the waste is. (

unobtainable thea the nus:lide distribution -fer the l daw Waste Stream wil) Ln used for the identity and i percent abundance.

l 5.5.2 Waste Classification

1. a waste classification should be periotaed prior to j trapsfering the waste batch to' tite container. As a minimum a waste cl. ossification shall be performed  ;

prior t'o shipment. Th9 waste classification will be performed, as outlined in Reference. 2.18.

RWS-0264 REV - 2 PAGE90F1h

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5.3.3' ?nckaging/ Handling

1. DAW will be segregeted ar/. stored in accordance with Reference 2.16 and 3.17.
2. compactable and noncompactable DAW should be packaged in accordence with Reference 2.33 and 2.17.

6,0 ACCEPTANCE CRITERIA 6.1 Solidification Process Control Program 6.1.1 T.c test samole will be considered acccptable if it meets 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 frce the container.

6.1<2 Once the test sample demonstrates an acceptable waste l J

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 i i

sequances specified in Reference 2.23.

6.1.3 Once solidificatico is completed the container will be stored in accordance with Reference 2.16 end prepaired 1 for ahipment in accordanca with Reference 2.29.

6.2 Dewatering Process Control Program 0 2.1 Tns container shall oc considered acceptable if it meets the dewatering limitation set forth in tha Vendors PCP and the disposal sita requirements for fras standing liquids.

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

6.2.3 Once dewatering is completed the container will be stored in accordance with Reference 2.16 and prepaired for shipment in accordanco nith Reference 2,29, 3 6.3 EncapsuiatiCa Process Cantrol 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 acquirement for the disposal site.

6.4 Dry Active Waste Process Ceutrol Program 6.4.1 The waste form will be considered acceptable if it meets the free standing liquid requfremen2 for the disposal- 4 site and the waste classifiestion for near surface buriel.

RWS-0204 REV - 2 PAGE 10 0F 17 .

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.. j 7.0 DOCUMENTATI0??

Data stieets will be included in the file copy of the shipping

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! -1 RWS-0204 REV .2 PAGE 11.0F 17

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l l EXAMPLE OF l  ;

I ATTACHMENT - 1 l VASTE SOLIDIFICATION DATA SKEET l  !

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-l i 1 WASTE SOLIDIFICATION DATA SHEET 1

l I l I Batch No. - I g  !

l Date: '

g l Prepared By:

) I. A. Prior Batch sample Solidification __

Verify prior batch sample solidification performed. Check one below and I show date at1d batch number of sesple. l ]

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I Evaporator Bottoms l Date: Batch No:

I C;winical Wastes i Date: Batch No:

i Resins Date: Batch No: l )

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l l l B. Indtial Batch Sample solidification If sample is from an initial batch of waste, describe wastn stream below:

II. Baten Samplo Analysis l

t l A. Lab hsults I I l

\ Sample Volume I I l l pH of Waste l l If greater than l'; refer to I j Waste Oil Content _ _ _ Section 5.2.2.3 01 RPCP. I I

Radionuclides Content _ l

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Waste. Classification ,. _

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l B. Vaste Retreatment l I l pH - Identify agent used and quantity to adjust pH of the kaste in  !

l the sample. I l l g Agent / Quantity Adjusted pH value l

! I Perfermed.by:m Date.

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

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Ill. Production Test Solidification (Required on at least every tenth batch of each type of wet radioactive waste.)  !

l l l j, A Tes,t e Solidification Formula.:_

l Volume of Waste: .

I-l I l Volume of Binder: l l I g Volume of other ingredients: .

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Waste / Binder Ratic: ,_

l Binder / Ingredient Ratio:  ! l l 1  !

l Total Volume: _ . l l l l

B. iree-Standing Water Analysis:

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l Volume of Decanted Water l

Volume of Samplu: ,

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  • Free-Standing Water:

I I l C. Solidification Acceptability l l l l l 1

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

(above) must be less than disposal facility criteria. l 'l j j

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

g l 3. The above Acceptance Criteria satisfies RBS Technical Specification  ! j l 3/4.11.3. I '

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

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Performed.By: Date: l g

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! IV. Batch Solidification  !

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l A. Formula (Per Drum Basis) I 1

l l Waste to be solidified (gallons) l l

l l Binder added (pounds) l l

Other ingredient (added)__ l g

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a l 1 l l l EXAMPLE OF l {

l ATTACHMElTr - 1 l WASTE SOLIDIFICATION DATA SHEET l l l 1 l L i I I 2

I I I I I i l l I l WASTE SOLIDIFICATION ACCEPTABLE / UNACCEPTABLE l l (circle one) l I i i  !

B. Remarks J

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l l l Performed By: Date: l  ;

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"l l EXAMPLE OF l l A'ITACHMENT - 2 l RESIN DEWATERING DATA SHEET 1 1 I I l- 1 I l RESIN DEWATERING DATA SHEET l l Batch No.: l-l Date: l l Prepared By: 1 I I I I l I. Semple Analysis l I I l Sample Vclume l I I l Waste Oil Content l I I l Radionuclides Content l I I l Waste Classification l l l 1 l lII. Vessel Information l ,

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l Type of Vessel being Dewatered l l l l Vessel Serial Number , l l 1 l Number of pumping cycles l 1

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

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

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l Remarks:

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l. A*ITACHMENT - 3 l BASIC FLOW PATH AND DESCRIPTIONS l l l . . _ _ - 1 I i g . BASIC FLOW PATH FOR SOLIDIFICATION PROCESS l

.>->- FASTE LINE TO LINER >->->~>->->->-l I  !

l l--<-<-< CHEMICAL SUPPLY-<-<-l I -<-<-<-l l<-< DEWATERING LINE-l ll I l

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j l l FILLHEAD l l l l l .o..l............l.... l [

g l l l VENDORS LINER l l l l ....l.... l l g l l DEWATER l l l l CHEMICAL j g l<-l PUMP l l l l BULK l l l l l SKID l l l l TRAIL 2R l l l l l l l l Wet radioactive waste are normally transferred to the vendor from the phase .l l separator tanks, backwash tank and/or waste sludge tank. This radioactive l waste is dewatered using the vendors dowatering skid which discharges liquid.

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to the ficar drain system. Once the vendors liner is full, the wet radioactive [. j i waste is mixed with chemicals form the vendors bulk trailer and solidified l; j in t.cccrdance with the vendors PCP.

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} BASIC FLOW PATH FOR DEWATERING PROCESS  !

I I l ->->- VASTE LINE TO LINER >->->->->->->- l l J l l l l l l -<-<-<-l l<-< DEWATERING LINE-l l l

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l l l l LINER / HIC l l l l ....l.... l l l l l l DEWATER l l l l l l<-l PUMP l l l l l l l SKT.D l l l l

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River Bond does not norms 11y dowater resin but has the capability to do so.

l To perform dewatering, wet radioactive waste are transferred to a liner  !-

l from the phase seRarator tanks, backwash tank and/or waste sludge tank.  !

l This wet radioactive waste may bw dowatered using the vendors dowatering skid I l cr similar type equipment which discharges liquids to the floor drain system. l' l l.'

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BASIC FLOV PATH FOR ENCAPSULATION PROCESS  !

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Prior to encapsulation the conteiner will be prepared by installing a mold / footer to support the item being encapsulated. Once this mold / footer I l 1s in place the item being encapsulated is than olaced into the container l l and the remainder of the encapsulation material placed on top *f the item completing the encarrulation, l g

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l SEGREGATION {<.>.....<.>.l SEGERATION ( j j l

l FACILITY l l FACILITY l i l g l l l l

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

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

l I i ............. I  !

l l l l l NON l l l l COMPACTABLE l l l COMPACTABLE l l l VASTE l<-<.<...>->->l WASTE i 1 i. ,

i I i l

l i

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

I j the waste is dried, separated, and identified as radioactive material i l it is either processed as compertable or nan compactahlo waste.

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l "I ll l l I l ATTACHMENT l PAGE 2 ll l l l l 3 l OF 2 ll RWS-0204 l REV - 2 l PAGE 17 0F 17 l l l _ l ._ _ iI i l I t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ .

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