REVISIONS SSES SOLID PROCESS PROGRAMndap-ga-0646 revision 4 page 3 of 63 section 1.0 purpose 2;0 policy/discussion 3.0 references tab of conte s 4. 0 responsibilities 4. 1 effluents

APPENDIXB

REVISIONS TO SSES SOLID WASTE PROCESS CONTROL PROGRAM(NDAP-QA-0646)

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PROCKDURE CHANGE APPROVALFORMPCAFNO. ~~I 7

?PAGE I OF P

3. ROCEDURE NO. NDAPWA~ 4. FORM NO. . REV.

5. PROCEDURE TITLE

Sofid Radioactive Naste Pmcess Control

6. PROCEDURE TYPE:QA PROGRAM ~ YES .,~ NOPLANTPROC. YES ~ NO

7. REQUESTED CHANGE

DELETE PCAFs QQ NO ~ YES ¹

ADDStep 4.5.13

Ensure that radwaste tanks are prepared wftb Operations suppo

8. REASON FOR CHANGE

To prevent recurrence ofCR 9&0630.

Continued ~9. RECOMMENDED FOR TATUS2 UU YES

NO, EXPIRATIONDATE(60 DAYMAXIMUMFOR Y STATUS)

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PROCEDURE. COVER SHEET

NUCLEAR DEPARTMENT PROCEDURE

SOLID RADIOACTIVE WASTEPROCESS CONTROL PROGRAM

NDAP-gA-0646Revision 4Page 1 of 63

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EFFECTIVE DATE:

PERIODIC REVIEW FREQUENCY:

PERIODIC REVIEW DUE DATE:

REVISED PERIODIC REVIEW DUE DATE:

PROCEDURE TYPE: OA Program (Q} YES ( ) NO

Plant Procedure (j ) YES ( ) NO

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REVIEW METHOD:

( ) Alternate ( ) Expedited

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Prepared by

Reviewed by

Recommended

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Date 3 -zz-9'5

Approved by

PORC Committee Meeting No.

ERC Co tt Date

Date

FORM NDAP-gA-0002-1, Rev. 1, Page 1 of 1

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PRO DURE SION SUMMAR

SOLID RADIOACTIVE MASTE PROCESS CONTROL PROGRAM

The following changes will not reduce the overall conformance-ofthe solidified waste product to existing criteria for solidwastes.

1) Incorporated PCAF 1-94-1330 revising the PCP implementingprocedure matrix to reflect actual procedures in use andchanged the requirements for disposal of radioactive wastesamples after packaged radioactive waste has been in itsdesignated storage area.

2) Added SEG NRC approved Topical Report STD-P-05-011-P-A toContracted Vendor Services to reflect use of SEG for waste

'rocessingequipment, methods and verification of acceptablewaste forms for dewatering and solidification.

3) Added Activated Carbon as a new waste'type which isgenerated from processing of liquid wastes using vendorprovided demineralization services.

4) Added the Solidification/Dewatering/Services Vendor mayperform test solidification and determination of mixingratios for solidification performed offsite (vendorfacility)

5) Added Radlok (SEG) type containers to High IntegrityContainer approved for use list.

6)

7)

Added SNM inventory requirements during processing per SOOR

94-581 resolution.

Added NRC Technical Position on Concentration Averaging andEncapsulation to Radioactive Maste Analysis andClassification to ensure that radionuclide/concentrationsare adequately distributed over the volume or weight of thewaste.


SECTION

1.0 PURPOSE

2;0 POLICY/DISCUSSION

3.0 REFERENCES

TAB OF CONTE S

4. 0 RESPONSIBILITIES

4. 1 EFFLUENTS MANAGEMENT SUPERVISOR

4.2 SUPERVISOR - OPERATIONS TECHNOLOGY

4.3 POMER PRODUCTION ENGINEER — EFFLUENTS MANAGEMENT

4.4 HEALTH PHYSICIST - EFFLUENTS HANAGEHENT

4.5 RADMASTE SUPERVISOR

4. 6 CHEMISTRY SUPERVISOR

4.7 HP FOREMAN — EFFLUENTS MANAGEMENT

4.8 MANAGER-NUCLEAR ASSESSMENT SERVICES

'.9 AUXILIARYSYSTEHS OPERATOR

4.10 SOLIDIFICATION/DEMATERING/SERVICES VENDOR

4.11 MANAGER — NUCLEAR PROCUREMENT

4.12 MANAGER - NUCLEAR SYSTEMS ENGINEERING

4.13 MANAGER - NUCLEAR MAINTENANCE

4.14 LICENSING SUPERVISOR

4.15 MANAGER - NUCLEAR TRAINING

4.16 MANAGER - NUCLEAR SECURITY

5.0 DEFINITIONS


~SEC ION

6.0 PROCEDURE

AB E OF CONTENTS Co t'e

20

6.1 CONTRACTED VENDOR SERVICES

6.2 MASTE TYPES

6.3 RADIOACTIVE MASTE ANALYSIS AND CLASSIFICATION

6.4 TESTING/TREATHENT OF SOLIDIFIED RADWASTE FORCOMBUSTIBLE GASES

6.5 RADIOACTIVE WASTE SOLIDIFICATION

6.6 . RADIOACTIVE WASTE DEWATERING

6.7 HIGH INTEGRITY CONTAINERS (HIC)

6.8 IRRADIATED HARDMARE PROCESSING AND DEMATERINGII

6. 9 CONTAINER INSPECTIONS

6.10 WASTE CONTAINER SPACE UTILIZATION

6.11 STORAGE OF PACKAGED RADIOACTIVE WASTE

6.12 TRANSPORTATION, SHIPPING AND DISPOSAL REGULATIONS

6.13 SHIPPING OF RADIOACTIVE WASTE

6.14 SHIPHENT CONFIRMATION

6.15 CHANGES TO THE SOLID RADIOACTIVE WASTE PROCESSCONTROL PROGRAM

6.16 EVALUATION OF PROCESS OR. OPERATIONAL CHANGES

6.17 REPORTING OF HISHAPS INVOLVING LOW LEVELMASTE FORHS

6.18 PCP INPLEHENTING PROCEDURES

7.0 RECORDS

20

21

27

30

30

40

51 .

52

NOAP-gA-0646Revision 4Page 5 of 63

~](CHANT

A

D

ACHM NTS

Solidification Record Sheet

Dewatering Record Sheet

Susquehanna Guaranteed Solidified/Oewatered MasteVolume Record

PCP Implementing Procedure Matrix

Materials not Compatible with Polyethylene Containers

55

59.

60

63


1.0 f>URPOSE

Provide administrative control, guidance and records''r the processing,packaging, transportation, and disposal of radioactive waste. Thisprocedure is the Process Control Program required by SSES Technical,Specifications.

2.0 ~PL 0 0 0 000100

This procedure is applicable to Low Level Radwaste {LLRM) generated as aresult of the operation of the Susquehanna Steam Electric Station(SSES). The waste streams include solid and liquid waste as defined inthe FSAR, but do not include spent fuel or greater than Class C waste.

Efficient generation and processing of radioactive waste is veryimportant to the overall operation of SSES. An important objective withrespect to radioactive waste generation is to minimize'the volume ofwaste generated. The processing of large volumes of waste can result inthe inability to dispose of or store all waste packaged, the significantincreased costs associated with increased waste generation, and the-potential to over-burden the processing system and degrade its long termreliability. The Process Control Program describes the envelope withinwhich processing and packaging of radioactive waste is accomplished toprovide reasonable assurance of compliance with Low-Level Radwasteregulations and requirements. This procedure is applicable to SSESinstalled systems, temporary systems and equipment provided by vendorsfor processing, packaging, transportation, and disposal of applicablewaste forms.

3.0 ~RF R NCES

3.1

3.2

3.3

49CFR100 — 177, Transportation

10CFR20, Standards for Protection Against Radiation

10CFR61, Licensing Requirement for Land Oisposal of RadioactiveMaste

3.4

3.5

3.6

10CFR71, Packaging and Transportation of Radioactive Material

40CFR261, Identification and Listing of Hazardous Maste

SSES Technical Specifications Section 3/4.11.3, Solid RadwasteSystem

i 3.7 SSES Technical Specifications Section 6.13, Process ControlProgram (PCP)


3.8 NUREG 0800, Standard Review Plan 11.4 Solid Waste Management .

Systems

3.9 Technical Position on Waste Form Rev. 1, 1991

3.10 Technical Position on Radioactive Waste Classification, Rev; 0,~ 1983

3.11 Technical Position on Concentration Averaging and Encapsulation,Rev. 0, 1995

3.12 Regulatory Guide 1.21, Measuring, Evaluating and ReportingRadioactive Material in Solid Wastes and Release of RadioactiveMaterial in Liquid and Gaseous Effluents from Light Mater CooledNuclear Power Plants

3.13 Regulatory Guide 1.143, Design Guidance of Solid Waste ManagementSystems

,3.14

3.15

3.16

3.17

Regulatory Guide 7.1, Administrative Guide for Packaging andTransporting Radioactive Material

ANSI/ANS 40.35, Volume Reduction of Low Level Radioactive Waste

ANSI/ANS40.37, Mobile Radioactive Waste Processing Systems

ANSI/ANS 55.1, Solid Radioactive Waste Processing System for LightWater Cooled Reactor Plant

3.18. Pacific Nuclear Dewatering System Topical Report No. TP-02-P-A,Rev. 3

3.19 Pacific Nuclear Solidification Process Control Procedure No.PT-51-WS, Rev. 40-

3.20 Scientific Ecology Group Mobile Incontainer Dewatering andSolidification System (HOSS) Topical Report No. STD-R-05-011-P-'A,Rev. 2

3.21 Disposal Site Criteria for Barnwell, S.C.

3.22 DHEC-HIC-PL-001 South Carolina Certificate of Compliance for CNSIHigh Integrity Containers

3.23 DHEC-HIC-P0-006, South Carolina Certificate of Compliance for CNSIOverpack High Integrity Containers

3.24 DHEC-HIC-PL-012, South Carolina Certificate of Compliance forVectra'Technologies, Inc. High Integer ity Container

NOAP-QA-0646Revision 4Page 8 of 63

3.25 DHEC-HIC-PL-005, South Carolina Certificate of Compliance forScientific Ecology Group, Inc. High Integrity Containers

3.26 OHEC-HIC-PL-017, South Carolina Certificate of Compliance forScientific Ecology Group, Inc, High Integrity Containers

3.27 PLA-1237, Process Control Program, August 17, 1982

3.28 Review of Process Control Prog} am for Susquehanna, Unit 1,Youngblood to Curtis, September 30, 1982

3.29 Safety Evaluation NL-93-008, Solid Radwaste Waste ProcessingServices Utilizing Pacific Nuclear Processing System

3.30 IE Bulletin 79-19, Packaging of Low Level Radioactive Waste forTransportation and Burial

(') 3.31 NRC Information Notice No. 90-50, Minimization of Methane GasGeneration in Plant Systems and Radwaste Shipping Containers

(z) 3.32 Generic Letter 91-02, Reporting Hishaps Involving LLW FormsPrepared for Disposal

( ) 3.33 SOOR-1-90-148, Barnwell Received Container Pressurized withFlammable Gas

( ) 3.34 SOOR 1-90-172, Incorrect Sampling Method Used on Resin Liner

( ) 3.35 SOOR 1-91-322, Dose Rates on Container Higher Than Expected

( ) 3.36 SOOR 94-581, Spent TIP Found Unexpectedly in TIP Room.

4.0 EEENIB T H4.1 Effluents Management Supervisor responsibilities:

4.1.1

4.1.2

4.1.3

Developing and implementing programs and proceduresfor radioactive waste processing, packaging,transportation and disposal.

Haintaining the overall radwaste program to ensurecompliance with applicable radiological and shippingregulations.

Ensuring personnel who perform support activities suchas processing, packaging, and transportation of lowlevel radioactive waste are available and meet allqualifications and training required by SSESprocedures.


4.1.4 Collecting, maintaining, reviewing and submittingaccur ate data/information related to waste streamquantity and nuclide composition for inclusion intoAnnual Radioactive Effluent Release Report and StateDER-BRP quarterly Report.

4.2 Supervisor - Operations Technology responsibilities:

4.2.1

4.2.2

4.2.3

Providing technical assistance to Effluents Managementpersonnel. This includes interpretations of state,federal, and disposal facility regulations regardingnew, imminent, or proposed regulatory changesgoverning processing, packaging, transportation, anddisposal.

Naintaining a current copy of local, state, federaland disposal facility regulations pertaining todisposal and transportation of low level radioactivewaste.

Coordinating the submittal of the Annual RadioactiveEffluent Release Report as per the SSES TechnicalSpecifications.

4.3 Power Production Engineer — Effluents Management responsibilities:

4.3.1

4.3.2

4.3.3

4.3.4

4.3.5

Ensure procedures are adequate to provide for propersolidification and dewatering of waste.

Ensure test data or rationale is available to justifyapplicable solidification and dewatering functions ofeach waste type, or any combinations, to addressdisposal and regulatory agencies'equirements.

Evaluate services provided by various vendors toensure contracted solidification and dewateringoperations are performed in the most efficient andeconomical method, as required by the applicableregulatory agencies.

Perform the duties of Radwaste Supervisor as specifiedin this procedure in his absence.

Define waste streams based on generator, filtrationmedia and means of processing.

SOAP-gA-0646'evision

4page 10 of 63

4.3.6 Cqllecting, reviewing* ynd suhoitting data related to'hereporting of mishaps and results of PCP

surveillance specimen examinations to applicableregulatory agen'cies.

4;4

4.4.3

Health Physicist - Effluents Hanagement responsibilities:

4.4.1 Haintain a sampling and ana)ysis program to ensurelOCFR61 compliance.

4.4.2 Ensure procedures are adequate to provide for properpackaging and shipment of waste to ensure compaiancewith all applicable regulations.

Evaluate services provided by various vendors toensure contracted waste packaging, processing, and .

transportation services are performed in the mostefficient and economical method, as required byapplicable regulatory agencies.

4.4.4 Perform the duties of HP Foreman - EffluentsManagement as'pecified in this procedure in hisabsence.

4.4.5 Coordinate radioactive material evaluation of productacceptability for disposal at specific disposalfacilities.

4.5 Radwaste Super visor responsibilities:

4.5.1 Ensure Solidffication/Dewatering Equipment is operatedin accordance with approved operating procedure,including vendor supplied equipment.

4.5.2

4.5.3

4.5.4

Ensure appropriate waste solidification and dewateringrecords are generated.

Interface with station support groups to ensure properImplementation of process control programs.

Provide direction to contractor personnel involved insolid waste processing activities including:

a. Ensuring test data is available to 5ustifyspecific processing techniques.

b. Ensuring applicable vendor procedures andrevisions are incorporated .Into applicably plantprocedure and approved by PORC. ,

~97-DOCS

3 oF 2,I

NDAP-QA-0646Revision 4Page ll of 63

4.5.5

4.5.6

4.5.7

4.5.8

4.5.9

4.5.10

4.5.ll

4.5.12

4.5.13

c.. Coordinating pre-processing and post-processingtreatment activities.

.. d. Evaluating services provided to ensure efficientand economical methods are used..

Ensure Solidification and Dewatering operations arecarried out in an ALARA manner.

Interface with HP Foreman - Effluents Management forliner and cask selection for solid waste shippingactivities.

Ensure proper marking of containers prior to filling.Ensure solidification/dewatering personnel areadequately trained per NTP-gA-42.6..

Estimate classification of waste for containerselection and processing method.

Ensure that waste streams loaded into High IntegrityContainers are sanipled for radionuclide and evaluatedfor chemical, compatibility applicable to the use ofHigh Integrity Containers.

Ensure proper inspections and documentation arecomplete prior to use of a High Integrity Containerand ensure that conta1ner is properly used up to thepoint of transfer to HP Foreman - EffluentsManagement.

Complete and process High Integrity Container UserCertification Statement to ensure the container isused properly.

Ensure that radwaste tanks are prepared withOperations support.

4.6 Chemistry Supervisor respons1bili ties:

4.6.1

4.6.2

4.6.3

4.6.4

Perform required sample preparation and analysis inaccordance with approved chemistry procedures.

Perform test solidification if required. Store testsolidification billet 1f required.

Provide density of initial and final waste form.

Provide the isotopic mix and concentration of isotopesdetected in the material sampled for solidification ordewatering.


4.6.6

4.7.2

4.6.5 Complete Chemistry portion of the Solidification andDewatering Records.

Ensure personnel are adequately trained perNTP-(A-41.2.

4.6.7 Provide chemical analysis and/or treatment support asnecessary for use of High Integrity Containers andliners.

4.7 HP Foreman - Effluents Nanag'ement responsibilities:

4.7.1 Interface with Radwaste Supervisor for liner and caskselection and scheduling for solid waste shippingactivities.

Complete, process, and file radioactive waste shippingdocumentation.

4.7.3

4.7.4

4.7.5

4.7.6

4.7.7

4.7.8

4.7.9

4.7.10

4.7.11

Storage of packaged radioactive waste within theradwaste facilities.Determine waste classification and description ofsolidified, dewatered, and other packaged waste..

Final disposition of solidified, dewatered and otherpackaged waste.

Ensures SSES is a registered user of applicable HighIntegrity Containers at specific disposal facilities.

. Ensures HP personnel involved with radioactive wastehandling have received Radwaste Morker. training perNTP-gA-42.6.

Evaluate vendor services provided to ensure efficientand economical methods are used.

Complete and process Certification Statement forDisposal of High Integrity Containers as required byapplicable regulatory agencies.

Process and package Cartr'idge Filters, Dry ActiveHaste, solid sealed sources and other non processwastes.

Collection of DAM and non-process waste (10CFR61)samples.


4.8 Manager-Nuclear Assessment Services responsibilities:

4.8.1

~ 4.8.2

4.8.3

Perform periodic audit of implementation of this.program and review of radwaste service vendor's gAPrograms.

Inspection of Radwaste Containers as required byapplicable procedures.

Ensure process controls are adhered to by inspectionof test solidification, waste volumes, solidificationagent additions, product acceptability checks,dewatering process sequence/acceptance criteria andrecords review.

4.8.4 Inspection of packaging, storage, and shippingactivities, as required by applicable procedures.

4.9 Auxiliary Systems Operator is responsible for operating the plantsolid and liquid radwaste equipment in accordance with approvedoperating procedures as directed by the Radwaste Supervisor andAssistant Unit

Supervisor.'.10

Solidification/Dewatering/Services Vendor responsibilities:

4.10.1

4.10.2

4.10.3

4.10.4

4.10.5

Provide solidification, dewatering and/or volumereduction services in accordance with a valid contractfor said services.

Provide test data or make data available for PPLLreview during vendor audits to demonstrate that theirservices and equipment meet. the applicable regulatoryand disposal facility limitations for the service theyare providing.

Provide training documentation to demonstrate that thepersonnel being provided, to conduct the applicableservice, are in fact trained and knowledgeable in theapplicable services.

Provide procedures that are or can be placed into theSSES procedure format for the services being provided.

Ensure an approved guality Assurance Program existsthat covers the services being provided. The vendorshall work within the SSES guality Assurance Programwhen applicable.


4.10.6

4.10.7

4.10.8

4.10.9

Complete applicable sections of.Solidification and-Dewatering Records required for each containerprocessed.

Ensure pre-qualification test data for each waste formshall be submitted to the Nuclear RegulatoryCommission.

Provide a description of the equipment/process that isused in processing waste.

Obtain waste samples from processing equipment inaccordance with approved operating procedures.

4.10.10 Perform all pre and post treatment activities asdetermined by Radwaste Supervisor.

4.11 Nanager - Nuclear Procurement responsibilities:

4.11.1 Ensure High Integrity Containers are not exposed toultra violet light (sunlight).

4.11.2

4.11.3

Ensure proper material certification is complete priorto issuance of High Integrity Containers to plant foruse.

Receipt inspection of High Integrity Containers anddocument review to ensure conformance.

4.11.4 Ensure Certificate of Compliance (C of C) is receivedwith High Integrity Container.

4.12 Hanager — Nuclear Systems Engineering is responsible for providingengineering support as required for operation of assigned radwastesystems and equipment.

4.13 Manager - Nuclear Maintenance responsibilities:

4.13.1 Calibration and maintenance of applicable plantequipment in Radwaste Processing Systems.

4.13.2 Provide maintenance personnel to support processing,packaging and transportation of low level radioactivewaste.

4.14 Licensing Supervisor responsibilities:

4.14.1 Submitting transportation cask user registr'ationrequests to NRC per IOCFRTI.12.


4.14.2

4.14.3

Submitting to the NRC the Annual Radioactive EffluentRelease Report.

Coordinating and submitting to the NRC the reportsrequired as a result of Condition Report (CR) events,investigations, and resolutions.

4.15 Man'ager - NucTear Training responsibilities:

4.15.1

4.15.2

Providing training and re-training in applicableregulatory requit ements to personnel directly involvedin transfer, processing, packaging, storage, andtransport of radioactive waste.

Maintaining a record of training, attendees, andsubject material for all Low Level Radioactive 'Hastetraining.

4.16 Manager - Nuclear Security is responsible for notifyingappropriate law enforcement agencies in the event of lostradioactive material shipments.

T ONS3.0 KFFI

5.1

'.2

5.3

5.4

5.5

5.6

APPROYEO CONTAINERS: Approved means approval issued or recognizedby the NRC for use in shipment of radioactive material.

BATCH: The total volume of waste contained in a liner, isolated—waste mixing tank - spent resin tank - concentrates tank or-phase separator that has been sampled for

, solidification/dewatering.

BILLS OF LADING: Shipping papers or manifests serving a similarpurpose and containing the information required by 49 CFR 172.202,203, and 204.

CARRIER: Means a person engaged in the transportation ofpassengers or property. (10CFR71.4)

CERTIFICATE OF COMPLIANCE: License requirements established bythe Nuclear Regulatory Coamission for the use of approvedRadioactive Material Shipping Containers.

CHELATING AGENT: A chemical which combines with a metal so as toform a ring structure held by coordination bonds.


5.7

5.8

5.9

CHEMICAL FORM: The chemical content of the Radioactive Materialbeing shipped.

CLOSED TRANSPORT VEHICLE: A. vehicle equipped with a securelyattached exterior enclosure, which during normal transport,restricts the access of unauthorized persons to the cargo space.(49 CFR 173-403[C])

COMPOSITE SAMPLE: A mixture of samples collected representingconditions at time of sampling, from the same sampling point, atdifferent times.

5.10 CONSIGNEE: The individual or organization to whom the shipment isconsigned or intended.

5.11 CURING TIME: The time allowed for the solidified product to setprior to its evaluation for product acceptability.

5.12

5.13

5.14

DECAY HEAT: The heat produced by radioactive decay, usually'expressed in Matts or BTU/hr, but can be related to Curie Content.

DEMATERED: The removal of free liquid from solid material to apoint where less than 1'X for HIC's and less than 0.5X for steelliners by waste volume remains as required by the disposalfacility license.

EXCLUSIVE USE VEHICLE (a/k/a: Sole Use or Full Load): Shipmentfrom a single consignor having the exclusive use of a transportvehicle and for which all initial, intermediate, and final loadingand unloading is carried out by, or under the direction of theconsignor, consignee, or his designated agent. (49 CFA 173.403[i])

5.15. FREE LIQUID: Liquid which- is still visible after solidificationor dewatering is complete, or is drainable from the low point of apunctured container.

5.16 HAZARDOUS MATERIAL — A substance or material, including ahazardous substance which has been determined by the Secretary ofTransportation to be capable of posing a threat to health, safety,

'ndproperty when transported in commerce, and which has been sodesignated. The term includes hazardous substances, hazardous.wastes, marine pollutants, and elevated temperature materials asdefined in 49CFR171.8, materials designated as hazardous under 'theprovisions of 49CFR172.101 and 172.102, and materials that meetthe defining criteria for hazard classes and divisions in49CFR173.


I

HAZARDOUS WASTE: Waste which contains material listed in40 CFR 261, Subpart D and/or exhibits one or more of the four.characteristics cited in 40 CFR 261, Subpart C, and is notexcluded from regulation under 40 CFR 261, Subpart A.

Hazmat Employee means a person who is employed by a HazmatEmployer who during the course of employment:

5.18.1 Loads, unloads or handles hazardous materials.

5. 18.2 Prepares hazardous materials for transportation.

5.18.3

5.18.4

Modifies, marks, or otherwise represents containers,drums, or packagings as qualified. for use in transportof hazardous materials.

Is responsible for safety of transporting hazardousmateri al .

HIGH INTEGRITY CONTAINER (HIC): A disposal site approvedcontainer. that has an expected life of 300 years and provides thestructural stability to meet disposal requirements.

HIGHWAY ROUTE CONTROLLED QUANTITY: A quantity, the aggregateradioactivity of which exceeds that specified in(49 CFR 173.403[1]).

ISOTOPIC ANALYSIS: The identification of the isotopic elementsinvolved in a sample of Radioactive Material.

LABELING: Labels applied to a container denoting the contents ofthe container and degree of hazard associated with the containers.The labels are identified as the 'White I label, the Yellow II, andYellow III label. A label stating Radioactive - LSA can also beapplied to a container .when appropriate. (49 CFR 172, Subpart E)

LIHITED QUANTITY OF RADIOACTIVE MATERIAL: Means a quantity ofradioactive material not exceeding the material package limitsspecified in 49 CFR 172.423, and which conforms" with requirementsspecified in 49 CFR 173.421. (49 CFR 173.403[m])

LINER: Steel container in which dewatered or solidificationproduct is deposited.

LOW SPECIFIC ACTIVITY: Naterial in which the activity isessentially uniformly distributed and in which the estimatedaverage concentration per gram of contents does not exceed thespecification as stated in 49 CFR 173.403 (n).

NDAP-gA-0646 .

Revision 4Page 18 of 63 .

LOM LEVEL- RADIOACTIVE MASTE (LLRM): Radioactive waste generatedas a result of qperation of SSES, excluding spent fuel or byproduct material, is classified by the NRC as low-levelradioactive waste. LLRM does not include "greater than class C"waste.

jHIXING RATIO: The ratio of waste to cement and additives *

required for satisfactory solidification.

MIXING RECIPE: The amount of waste, cement and additives mixedto'olidifywaste.

MIXED MASTE: A mixture of low level radioactive and hazardouswaste.

NORHAL FORM RADIOACTIVE MATERIALS: Means radioactive materi al swhich do not meet the requirements of Special Form RadioactiveHaterials (49 CFR 173.403[s]).

PLACARDING: A label affixed to all four sides of the transportvehicle denoting the presence and level of Radioactive material onthe vehicle. (49 CFR 172, Subpart

F)'ROCESS

CONTROL PROGRAM (PCP): Program which contains thesampling, analysis, and formulation determination by whichsolidification of radioactive wastes from liquid systems isassured.

RADIOACTIVE HATERIAL: For purposes of transportation only,material in which the activity is essentially uniformlydistributed and the estimated specific activity exceeds 0.002microcuries, per gram of material. (49 CFR 173.403[y] and [aalu)

RAOWASTE MORKER: A Hazmat Employee involved with the collection,packaging, and transportation of radioactive waste.

SEALED SOURCES: Any by-product material that is encased in acapsule designed to prevent leakage or escape of by-productmaterial.

SOLIDIFICATION: A conversion of radioactive materials fromliquid'nd

solid systems to a homogeneous (uniformly distributed)monolithic, immobilized solid with definite volume and shape,bounded by a stable surface of distinct outline on all sides (freestanding).


5.37

5.38

5.39

5.40

5.41

5.42

5.43

5.44

5.45

5.46

5.47

SOLIDIFIED RADWASTE: Wet waste which is solid~fied (e.g.evaporator concentrates, sludge), meets the free liquid criteria,and satisfies applicable transportation and disposal siterequirements. Dewatered resins or filter sludge satisfying thetwo latter criteria shall also be defined as solidified radwaste.

SPECIAL FORM RADIOACTIVE MATERIALS: Radioactive material that iseither a single piece, or is contained in a sealed capsule, thatcan be opened only be destroying the capsule and meets theadditional requirements specified in 49 CFR Part 173.403(z).

STABLE AND UNSTABLE WASTE FORMS: Shall be defined as stated in10CFRPart 61 and other supporting regulatory documents.

TEST SOLIDIFICATION: The mixing of waste(s) and solidificationagents in the laboratory to support selection of mixing ratios andprovide insurance for final product acceptability.

TRANSPORT INDEX (TI): The dimensionless number placed on thelabel of a package to designate the degree of control, to beexercised by the carrier during transportation. The transportindex will be determined in accordance with 49 CFR 173.403(bb).

TYPE "A" PACKAGING: Packaging which is designed in accordancewith the general packaging requirements of 49 CFR 173.24, andwhich is adequate to prevent the loss or dispersal of theradioactive contents, and to retain the efficiency of itsradiation shielding properties if the package is subjected to thetest described in 49 CFR 173.465 or 173.466, as appropriate.{49 CFR 173.403[gg])

TYPE "A" QUANTITY RADIOACTIVE MATERIAL: That material which maybe transported in Type "A" packaging. {49CFR 173.431[a])

TYPE "B" PACKAGING: Packaging which meets the standards for Type"A" Packaging, and in addition, meets the standards for thehypothetical accident conditions set forth in 10CFR71.(49 CFR 173.403[hh])

TYPE "B" QUANTITY RADIOACTIVE MATERIAL: That material which maybe transported in Type 'B" packaging. (49CFR 173.431[b])

WASTE STREAM: A by-product of a process system or component withunique characteristics and maintained separate from other wastestreams.

I

WASTE TYPE: Specific contents of a liner or tank which maycontain one or multiple waste streams, the category of waste.suitable for a particular means of processing.

NDAP-qA-0646Revision 4page 20 of 63

5.48 MASTE PRE-CONDITIONING: The physical or chemical adjustment of'—the waste to bring it within an established envelope to assuresolidification.

6.0 JP Poc DURE

6.1 "CONTRACTED VENDOR SERVICES

6.1.1

6.1.2

6.1.3

6.1.4

6.1.5

6.1.6

Solidified radwaste processing services are providedby Vectra, Inc. for waste types included in thisProcess Control Program.

NRC approved Topical Report TP-02-P-A, describesVectra Inc. waste processing equipment, methods andverification of acceptable waste forms for dewatering.

/Vectra Inc. Solidification Process Control ProcedurePT-5I-MS, describes waste processing equipment,methods and verif'ication of acceptable waste forms forsolidification. This procedure does not providestability per the Branch Technical Position on MasteForm, Rev. 1.

Volume reduction, services are provided by ScientificEcology Group (SEG) for waste types included in theProcess Control Program.

NRC approved Topical Report STD-P-05-011-P-A,describes Scientific Ecoplogy Group (SEG) wasteprocessing equipment, methods and verification ofacceptable waste forms for dewatering andsolidification. Selected solidified waste forms havebeen approved to provide stability per the Bt anchTechnical Position on Maste Form, Rev. l.Other contracted vendor services which are requiredfor solidification, dewatering and volume reductionservices shall be evaluated to the requirements

stated'in

this Process Control Program on a case by casebasis

NDAP-gA-0646Revision 4Page 21 of "63

6.2 MASTE TYPES

The following waste types shall be processed in accordance withthis procedure or in combinations as defined. The waste should bedewatered whenever possible to minimize disposal volume.

6.2.1 Evaporator Concentrates

The following are concentrated with the RadwasteEvaporators and .are considered EvaporatorConcentrates waste stream:

(I) Condensate Demineral izer regenerati on

effluent'2)

Decon Shop drains

(3) Chemistry Laboratory sink drains

(4) Auxiliary Boiler blowdown effluent

b.

Ci

d.

The constituents of this waste stream mayinclude the following:

(1) Tr'i-Sodium Phosphate

~ (2) Sodium Sulfate

(3) Phosphoric Acid

(4) Sulfur ic Acid

(5) Sodium Hydroxide

(6) Decontamination solutions

(7) Negligible amounts of reagent chemicalsused for chemi..try analysis

Evaporator Concentrates in the range of 0-24weight percent sodium sulfate (equivalent) shallbe solidified for final disposal.

Evaporator Concentrates shall not be mixed withany other waste type in final processing.

gDAP-qA-0646Revision 4page 22 of 63

Mixed Solids

a o The following process waste streams arecollected either, in.Waste Mix Tanks, MasteSludge Phase Separator or transferred directlyto a liner/High Integrity Container and areconsidered Mixed Solids:

(I) LRM Filter Media and drain liquid

{2)

(3)

Sump Sludge

Ultrasonic Resin'Cleaner Maste (URC Maste)

b.

d.

The constituents of these waste streams may'ncludethe following:

{I) Diatomaceous Earth

(2) Powdered Resins

(3) Fibrous material

{4) Carbon material

(5) Corrosion products

(6) Various solids and dirt in smallconcentrations

Mixed Solids may be solidified or dewatered forfinal disposal.

Each waste stream should be processedseparately.

RWCU Filter Media

b.

The Reactor Mater Cleanup System and FuelPool'oolingand Cleanup System filter/demineralizer

waste are collected in the RWCU Phase Separatorand should be allowed to decay for 60

days.'his

waste stream is considered RWCU FilterMedia.

The constituents of this waste stream mayinclude anion and cation powdered resin,corrosion and contaminants removed from theprimary coolant.


C. RWCU Filter Media shall be dewatered in HighIntegrity Containers. If this waste must besolidified, Technical Specification 3/4.11.3action statement must be performed.

Condensate/Radwaste/Atmospheric Demineralizer BeadResin

a ~

b.

C.'I

Resins from the Condensate Oemineralizers,Liquid Radwaste Demineralizer and vendorprovided demineralization are collected in theSpent Resin Tank or transferred directly to aliner/High Integrity Container. This isconsidered to be. Condensate/Radwaste/AtmosphericOemineralizer Bead Resin.

The constituents of this waste stream mayinclude various types of anion, cation, mixedbead resin and corrosion and contaminatesremoved from liquid waste streams.

Bead Resin may be used to demineralize LiquidWaste in either steel liners or High IntegrityContainers.

d.

e.

Condensate Demineralizer bead resin should beultrasonically cleaned prior to collection inthe Spent Resin Tank.

Bead Resin may be solidified or dewatered forfinal disposal.

Bead Resin may also be processed by volumereduction methods which include drying,incineration, compaction, use as fillmaterialsor other evaluated method(s) on a case by casebasis.

Cartridge Filters

'a ~ Cartridge Filter waste type consists of thefollowing waste streams and constituents:

(I) CRD Filters - CRD or other filters andsmall un-irradiated primary systemequipment such as valves, CRD liftpumpfilters, Rinse Tank filters and othermetal components.

NOAP-gA-0646.. Revision 4

'Page 24 of 63

(2) RNCU Septa - Septa from RMCU Filte}Demineralizer including septa from FuelPool Cleanup Filter Demineralizer.

(3) Radwaste Filters - including degasifierfilters and other fiber or paper filtersother than primary system.

{4) Underwater Vacuum Filters - non-processfilters generated from wet cleaningactivities.

b. Cartridge Filters may be processed by thefollowing methods:

{1) Emplacement in a cement matrix in a steeldrum/liner or in a High IntegrityContainer.

(2) Dried to a point where no free liquid isvisible. Absorbent material may beincluded to absorb unintentional andincidental amounts of liquids.

{3) Oewatered if drying is impractical.

(4) Incineration or other volume reductionmethods.

c. Cartridge Filters to be solidified for finaldisposal shall not be mixed with any other wastetype.

d. Each cartridge filter waste stream should bepackaged separately unless analyzed prior topackaging in accordance with the requirements ofthis procedure.

Irradiated Hardware

a 0 Irradiated hardware is neutron acti'vated metalremoved from the internal area of the reactorpressure vessel. This waste stream isconsidered Irradiated Hardware.


The constituents of this waste stream mayinclude control rod blades, LPRHS's, IRK's,TIP's and components expended during hardwareprocessing and packaging activities. Startupsources may also be processed as part of thiswaste stream.

c. Irradiated hardware is packaged in steel linersfor disposal.

d. Liquid shall be drained to ensure free liquidAcceptance Criteria are met.

e. Irradiated hardware shall not be mixed with anyother waste type in final processing.

Dry Active Waste (DAM)

a. Dry Active Waste is a waste stream.

b. The constituents of thi's waste stream consist ofcontaminated paper, plastic, wood, metal andother discarded material.

C. Dry Active Maste,shall be processed by volumereduction methods which may includeincineration, compaction, decontamination andmetal melting.

d. At a minimum, DAM shall be packaged in strong-tight containers for disposal.

Liquid Oil Waste or Petroleum Based Materials

The constituents of this waste stream mayinclude turbine lubricating oil, EHC fluid andother petroleum based materials.

Contaminated Liquid Oil Waste generated at thefacility should be processed by adecontamination system, solidified for finaldisposal, volume reduced by incineration, orother acceptable methods.


Ci Liquid Oil Maste at concentrations 1X andgreater may be solidified provided the followingare adhered to:

k

(1) An emulsification agent is added atrequir ed concentrations.

(2) The Liner is NOT SHIPPED to a disposalfacility without prior disposal facilityapproval.

Solid Sealed Sources

ao

b.

co

Solid Sealed Sources requiring disposal shall bepackaged .for disposal as requested by HealthPhysics Supervision.

Method of disposal is dependent on waste classof the Solid Sealed Source and disposal facilityrequirements.

Acceptable methods of disposal include:

(1) Placement within a container consisting ofanother waste type provided:

(a) The source contains isotopicsalready in the waste.

(b) The source activity is significantlyless than the waste activity.

(2) Class B and C sources shall be stabilizedwithin an approved solidification orencapsulation media.

Activated Carbon

ao

b.

Activated Carbon from vendor provided liquidwaste demineralization is transferred directlyto a liner/High Integrity Container. This wastestream is considered Activated Carbon.

The constituents of this waste stream mayinclude various types of charcoal, ion specificcarbon filter media and corrosion and.contaminants from liquid waste streams.


C. Activated Carbon may be solidified, dewatet ed orprocessed by volume reduction methods whichinclude drying, incineration, compaction, use asfillmaterials or other evaluated methods on 'a

case by case basis.

6.2.11

6.2.12

6.2.13

. A Waste Type that is combined with a known amount ofhazardous waste'r "Mixed Waste" shall be processed .

for final disposal pending approval obtained from theprocessing and disposal facilities, EnvironmentalProtection Agency, U.S. Nuclear Regulatory Commissionand other regulatory agencies as required.

Waste types containing chelating agents within therange of 0.1 to 8.0 percent by weight shall beprocessed to a stable waste form in accordance withand authorized by disposal facility requirements and.approvals.

Various other materials not specifically identified aswaste types will be evaluated for solidification,dewatering volume reduction or other processing on acase by case basis.

(") 6.3 RADIOACTIVE WASTE ANALYSIS AND CLASSIFICATION

6.3.1 Radionuclide concentrations of radioactive waste areused to classify waste for shipping and disposal.Radionuclide concentrations should be determined basedupon isotopic analysis, volume and weight of finalwaste form.

6.3.2 The lOCFR61 Compliance Program establishes amethodology for characterizing radioactive wastethrough the use of correlation factors. This programshall require as a minimum that:

a ~ Samples representative of Susquehanna's wastestreams are collecte". and analyzed such thatresults are obtained ft om a designatedlaboratory at least every two years (Class A)for development of specific correlation factors.'Waste streams known or suspected to beclassified Class B or Class C should be analyzedon an annual basis.


b. Technical basis documentation and justificationof correlation factors are developed for each .

waste stream and are acceptable for use.Periodic evaluations and necessary adjustmentsto established ratios are performed in a timelymanner.

c. Correlation factors are re-evaluated followingsignificant changes {greater than a factor of10) in plant operations (such as significantchanges in fuel leakage, radwaste operations, orequipment).

Determination of waste classification shall be inaccordance with 10CFR61.55, Maste Classification, andits supplementary Branch Technical Position onRadioactive Maste Classification as follows:

b.

C.

Class A - Usually segregated from other wasteclasses at the disposal facility. Physical formand characteristics shall meet the minimumrequirements specified in 10CFR61.56(a). If thestability requirements in 10CFR61.56(b) are met,the waste does not have to be segregated fordisposal.

Class S - Physical form and characteristicsshall meet both the minimum and stabilityrequirements specified in 10CFR61.56.

Class C — Physical form and characteristicsshall meet both the minimum and stabilityrequirements specified in 10CFR61.56. Inaddition, measures shall be taken at thedisposal facility to protect against inadvertentintrusion.

Isotopic analysis may be performed by:

a. Gamma spectrometry of a sample and use ofcorrelation factors.

b.

C.

d.

Direct gamma spectrometry of waste and use ofcorrelation factors.

Complete radionuclide analysis of waste sample.

Dose to Curie calculations.

NDAP-QA-0646Revision 4Page 29 of 63

e. Activation analysis.

Volume and weight of final waste may be determined by:

a ~ Calculation using analytically derived sampledensities.

b.

C ~

d.

Calculation using standard waste densities.

Direct measurement of volume and weight.

Acceptable methods described in the TechnicalPosition on Concentration Averaging andEncapsulation.

If samples of waste are used for classification,sampling program shall include:

a ~

b.

Samples shall be obtained and analyzed for eachbatch of.wet waste if practical and ALARA.

Preferentially, samples should be taken foranalysis following processing into a final wasteform.

C. Samples taken prior to final processing should.enable results of sample analysis to be directlytranslated to final waste form.

d.

e.

Bead resin and Activated Carbon used forchemical demineralization shall be sampled afterhaving has been depleted in process.

Solidification/Dewatering Services Vendor oranother qualified individual shall obtainrequired samples.

Preparation of waste for sampling or analysis

a4

b.

Wet Waste Collection tanks shall be recirculatedin accordance with approved operating proceduresprior to sampling or analysis.

Waste processing in solidification liners/HighIntegrity Containers shall be mixed inaccordance with approved procedures prior tosampling or analysis.

NDAP-QA-O646Revision 4Page 30 of 63

6.3.81

c. Met waste to be processed may also be mixed,recirculated and sampled or analyzed from mobileprocessing equipment.

. Final waste form containing a mixture of waste typesor streams shall be individually analyzed to determineradionuclide concentrations. The summation of eachindividual radionuclide concentration shall be used tocharacterize the final waste form for shipping anddisposal. Waste types or streams of different wasteclasses (estimated by historical precedent orprojected analysis) shall not be mixed.

6.3.9 Deviations from sampling and analysis requirementsshall be approved by Chemistry Supervisor andEffluents Management Supervision.

6.4 TESTING/TREATMENT OF SOLIDIFIED RAOMASTE FOR COMBUSTIBLE GASES

6.4.1 Solidified waste shall be tested and/or treated toensure it is not capable of generating quantities offlammable or toxic gases, vapors or fumes which may beharmful to persons transporting, handling, storing ordisposing of the waste.

6. 5 RADIOACTIVE MASTE SOLIDIFICATION

6.5.1 General Requirements

a. Wet Maste Types which may be solidified in HighIntegrity Containers are EvaporatorConcentrates, Mixed Solids, Condensate/RadwasteDemineralizer Bead Resin, RMCU Filter Media andLiquid Oil Waste or Petroleum Based Material,Cartridge Filters, Solid Sealed Sources andActivated Carbon.

b.

c

d.

High Integrity Containers shall be used to meetthe stability criteria in accordance withfederal and disposal facility regulations.

Solidification processing shall be conducted byqualified SSES or Solidification/Dewatering/Services Vendor personnel.

The solidification process shall be operated inaccordance with approved procedures. Proceduresshall specify waste stream, amounts ofsolidification agent and additives or method fordetermination.


Maste Preconditioning

a ~

b.

Maste preconditioning requirements shall bedetermined by, chemistry analysis.

Preconditioning of waste shall be performed ifrequired prior to determining mixing ratios.

c. Maste preconditioning is required when any ofthe following conditions exist:

(I) A high or low pH condition, as determinedby chemical analysis.

(2)

(3)

Liquid content of the batch is out of theacceptable envelope for solidification.

Solids content of the batch is out of theacceptable envelope fo} solidification.

(4) Known potential problem chemicals andconstituents within waste that mayadversely affect setting and stability ofcement-solidified waste form.

d.

~ e.

Waste preconditioning shall be performed inaccordance with approved procedures to ensurewaste is within the acceptable envelope forsolidification.

Upon completion of waste preconditioning,additional samples, as required, shall beobtained in accordance with Radioactive MasteAnalysis and Classification section of thisprocedure.

Determination of Hixing Ratios

a. Determination of mixing ratios shall beperformed for each waste batch to be processed. "-

b. Deviation from the recommended mixing ratiosshall be reviewed by Plant Operations ReviewCommittee (PORC).

c. Chemistry Group determines:

(1) Density of the waste samples.

NDAP-gA-0646Revision 4page 32 of 63

d.

e.

(2) Specific gravity of Sodium SulfateSolution in Evaporator Concentrates.

Solidification/Dewater ing/Services Vendordetermines if the final mixing ratios are withinthe acceptable envelope for solidification.

For solidification performed on site:

(2)

Chemistry Group shall perform testsolidification of waste as required byTest Solidification section of thisprocedure.

Chemistry Group determines mixing ratiosto ensure pr'oper solidification.

For solidification performed offsite:

(1) Sol idification/Dewater ing/Services Vendorshall perform test solidification of wasteas required by Test Solidification sectionof this procedure.

{2) Solidification/Dewatering/Services Vendor, determines mixing ratios to ensure propersolidification.

Test Solidification

'a ~ Test solidification shall be performed tosupport waste mixing ratios as foll'ows:

(1) At least every tenth (10th) batch of thesame waste stream.

{2)

(3)

Mhen sample analysis fall outside theestablished range and criteria indicatinga change in waste characteristics.

Mhen it is believed that some unexpectedor abnormal contaminant may be present.

(4) Mhen'equested by Radwaste Supervisor.

NDAP-0A-0646Revision 4Page 33 of 63

(5) Mixing of materials shall be accomplishedin a manner that duplicates, to the extentpractical, mixing conditions that areobtained with full-scale mixing incontainer.

b.

c ~

d.

e.

(6) Curing shall be performed under. conditionssimilar to those used in laboratoryqualification test program.

Upon failure of a test solidification, an LCO isentered, additional samples shall be

obtained,'lternativesolidification parameters aredetermined and a subsequent test verifiessolidification. Test solidification shall beperformed on each subsequent batch of the samewaste 'stream until at least three (3)consecutive initial test solidificationdemonstrate acceptability in accordance withTechnical Specification 3/4.11.3.

guality Control shall verify test solidificationacceptability and indicate the acceptability onthe surveillance documentation. Theacceptability requirements are defined in thePCP Surveillance Specimen section of thisprocedure.

Extra sample volume for backup testing shall bedisposed of after acceptable container checksare completed.

High Integrity Container test solidificationbillets should be disposed after acceptablecontainer checks are completed.

Test solidification should be performed withsamples from waste obtained as follows:

(I) In accordance with Radioactive WasteAnalysis and Classification section ofthis procedure.

(2) 'ampling of the solids in the c'ontainerand the liquids used for hydration, thenmixed to the ratios that exist in thecontainer.

NDAP-gA"0646Revision 4Page 34 of 63

g. Test Solidification Procedures shall bedeveloped for each specific waste type asrequired.

h. Cement, water type and additives to be used inactual solidification shall be used inpreparation of test solidification.

PCP Surveillance Specimens

a. High Integrity Container test solidificationbillets shall be examined and tested foracceptability after the specified cure time for:

(1) Liquid on surface of solidified productless that 1.0X by waste volume.

(2) Visible defects, such as ct acking,spallin'g, or disintegration.

(3) Strength by physically poking the surfaceof solidified product with a rigidunyielding device. Nominal surfacedenting is acceptable.

b. If cement solidification in steel liners is NRCapproved to provide stability, PCP surveillancespecimen examination testing and reporting isrequired in accordance with the Branch TechnicalPosition on Waste Form, Rev. l.

Curing Time

A minimum of 30 hours shall be allowed for''cur ing prior to capping or transportingcontainer.

b.

c

The container may be moved during the first hour.after solidification but must remain undisturbedfor the remaining 29 hours.

Deviations from minimum required curing timeshall be approved by Radwaste Supervisor'andjustifications documented in remarks section ofSolidification Record.


Solidification Product equality

'a ~

b.

Solidification product quality is assured by useof predetermined mixing ratios of waste, cementand additive. Liquid to be used forsolidification should be demineralized water.

Pre-qualification mixing ratios are based onlaboratory testing using non-radioactive wastematerials.

c. Mixing ratios are re-enforced by the following:

(I) Test solidification performed periodicallyas stated in Test Solidification sectionof this procedure.

(2) Visually and physically checking at leastevery fifth (5th) container of the samewaste type.

d. Container checks shall consist of:

'(I) A visual check of solidified product forliquid on surface of product not to exceed1.0X by waste volume.

(2) Physically poking the surface ofsolidified product with a rigid unyieldingdevice prior to capping (Nominal surfacedenting may occur and is acceptable).

e. guality Control shall verify acceptability ofsolidified product when containers are checked.

f. Deviation from the container checkingrequirement shall be approved by the RadwasteSupervisor.

Handling of Unacceptable Solidified Maste Containers.

a0

b.

If a solidified waste container does not meetacceptability requirements, a Condition Report(CR) shall be issued.

If the reason for unacceptability is freeliquid:

(I) The free liquid will be removed; or


(2) Extra cement/additive will be added tosolidify free liquid.

If portions or all of the product did notsolidify after three days:

k

(I) The waste container will be capped aridplaced in a storage location andperiodically checked until'such a timeproduct is acceptable; or

(2) Additional solidification agents may beadded to achieve satisfactorysolidification, as determined by theRadwaste Supervisor.

If the product solidifies prematurely prior to .

completing the addition of required amount ofcement and additive, as calculated on thesolidification calculation sheet for thespecific procedure used, the following isrequired:

{I) A test solidification shall be performedusing the actual ratio of cement and wastein the container, provided sufficientsample volume remains to complete thisitem.

(2) gual ity Control shall check the productfor acceptability in accordance with .

Container Checks section of thisprocedure.

(3) The container is considered to meetacceptable waste form criteria forshipping provided the subsequent testsolidification and/or container checks are .

acceptable to guality Control andconcurrence of the Radwaste Supervisor is:obtained.

{4) The above apply only if the EffluentsManagement Supervisor determines that theproduct can be classified as "Class AUnstable" or is placed in a High IntegrityContainer or structure that providesstability in accordance with IOCFR61 and

~ the disposal facility criteria.

NDAP-QA-0646Revision 4Page 37 of 63

e. If the product does not solidify properly inaccordance with the specific solidificationprocedure, the following is required:

(I) An evaluation of the liner shall be madeby the following personnel:

(a) Effluents Management Supervision

(b) Solidification Vendor - Operations

(c) Solidification Vendor - Engineering

(3)

Disposal facilities shall be contacted andrequirements for receipt of the liner inquestion shall be defined.

Alternative packaging/processing shall beevaluated.

(4) Recommendations for 'final dispositionshall be made to the Power ProductionEngineer-Effluents Management.

(5) Final disposition shall be reviewed byPlant Operations Review Committee (PORC).

(6) Records shall be kept and documentationsupportive of final disposition attachedto the solidification record package.

'(7) The liner may be shipped after g.C. reviewof documentation is complete and disposalfacility concurrence is received in letterform.

9-

Specific instructions shall be established forhandling unacceptable solidified waste container'n

a case by case basis.

guality Control shall re-verify acceptability ofsolidified product by performance of ContainerChecks.

Capping of Solidified Waste Containers

a. The requirements of Solidification Productguality section of this procedure shall be metprior to capping the container.

NDAP-gA-0646Revision 4Page 38'of 63

b. If the container is not equipped with a passivevent and its contents are within the.requirements of Low Specific Activity (LSA)ensure one of the following:

(1) The container should be shipped within(10) ten days after. capping; or

(2) If a container has been capped for longerthan (10) days, it shall be opened,vented, and re-capped within (10) ten daysof shipment.

co If the container exceeds the limits for LowSpecific Activity and contains water and/ororganic substances which could radiolyticallygenerate combustible gases, determination mustbe made such that the following criteria are metover a period of time that is twice the expectedshipment time:

(1) The hydrogen generated shal.l be limited toa molar quantity that would be no morethan 5X by volume of the container gasvold; or

(2} The container and shipping cask cavitysha11 be inerted with a diluent to assurethat oxygen is limited to less than 5% byvolume. in those portions of the packagewhich could have hydrogen greater than 5X.

Solidification Agent Control

a ~

b.

Portland Cement —. ASTM C-150 Type I shall be

used for the mobile solidification process.

Other solidification agents may be used onlyafter acceptable testing of the agent has beencompleted that demonstrates acceptablesolidification and disposal facility approvalhas been obtained.


C. Documented Certification is not requiredfor'aterialsreceived in bags provided material

verification can be obtained as follows:

(1) Cement is acceptable provided the bagcontaining the cement indicates thatcement is Portland Type

I.'2)

Sodium Silicate is acceptable provided thebag containing the additive indicatesAnhydrous Sodium Hetasilicate.

(3) Other additives are acceptable providedthe container is clearly marked indicatingthe type of additive.

d. Other additives may be used for enhancement ofsolidification process as specified in thesolidification procedure and documented in thesolidification records.

Radioactive Maste Solidification Records

A Solidification Record Sheet (Form NOAP-gA-0646-1)shall be completed for each container filled withsolidification products.

Completion of the Solidification Record Sheet and therequired accompanying documentation shall be asfollows:

a ~ The Radwaste Supervisor is responsible forinitiating this form and completing Parts 1 and2.

b.

C.

Effluents Management Supervision, Chemistry andSolidification/Oewatering/Services Vendorpersonnel shall provide and check off therequired documentat~:~. specified in Part 3.

guality Control shall provide review as requiredfot the Solidification Records.


6.6 RADIOACTIVE WASTE DEMATERING

6.6.I General Requirements

Maste Streams which may be dewatered in eitherHigh Integrity Containers or steel liners areLRW Filter Media,. Ultrasonic Resin CleanerMaste, Sump Sludge, RWCU Filter acedia,Condensate/Radwaste Demineralizer Bead Resin,Cartridge Filters and Activated Carbon. Thetype of container used shall be based on thewaste classification and stability criteria inaccordance 'with federal and disposal facilityregulations.

b.

C.

d.

e.

Dewatering of Radioactive Maste shall beperformed by qualified SSES or Solidification/Dewatering Set vices Vendor personnel.

Dewatering of Radioactive Maste shall beperformed in accordance with approvedprocedures.

Dewatering procedures shall be based ondocumented test data that has demonstrated theability to achieve free liquid limits asspecified by disposal facilities and applicableregulatory agencies. Liquid volume and drainagecalculations and actual drainage verificationmay also be used to meet free liquid limits.

High Integrity Containers shall be used fordisposal when the concentration of radionuclideswith half-lives greater than 5 years exceeds IpCi/cc.

Each waste stream which may be dewatered shouldbe characterized by the Solidification/Dewatering Services Vendor to ensure theoperating parameters and effectiveness of 'thedewatering system are in accordance with theparameters established in the Topical Report.

I

4


Dewatered Product Control

a. The final dewatered product shall contain lessthan 1X non-corrosive free liquid for HighIntegrity Containers and 0.5X for steel liners.guality Control checks shall be performed onprocess steps..

b.

c

If a dewatered waste container does not meetacceptability requirements, a Condition Report(CR) shall be issued.

Specific instructions shall be established forhandling unacceptable dewatered waste containeron a case-by-case basis.

,

d. Deviation from the container checkingrequirement shall be approved by the PowerProduction Engineer-Effluents Hanagement.-

I

Radioactive Maste Oewatering Records

A Dewatet ing Record Sheet (Form NDAP-gA-0646-2) shallbe completed for each container filled with dewateredwaste streams. Parts of the form shall be completedby the following responsible individuals or groups:

a. The Radwaste Supervisor is responsible forinitiating this form and completing Parts 1 and2.

b. Chemistry Group shall complete Part 3 Samplingand Analysis.

c ~ Effluents Management Supervision, Chemistry andSolidification/Dewatering/Services Vendorpersonnel shall provide and check off therequired documentation specified in Part 4.

d. guality Control shall provide review as requiredfor the Oewatering Records.

NDAP-gA-0646Revision 4Page '42 of 63

6.7 HIGH INTEGRITY CONTAINERS (HIC)

6.7.1 Storage of High Integrity Containers

a ~ Yectra, Radlok and CNSI High IntegrityContainers (HIC) stored in direct sunlight or inareas where there is a strong source ofultraviolet radiation shaTl be filled anddisposed of within one year of manufacturingdate.

6.7.2

b.

c

Uses

a ~

Once filled a High Integrity Container may bestored for a period until a total of one (1)year of ultraviolet radiation is received.

Short exposures (i.e., several hours) tosunlight, such as 'occurring during shipment andon site transfer need not be counted whendetermining total ultraviolet exposure.

of High Integrity Containers

High Integrity Containers may be used to packagethe following waste materials for disposal:

(1) Oewatered bead resin, powdered resin anddiatomaceous earth.

(2) Compressible and non-compressible solidwastes.

(3) Filter elements and cartridges.

(4) Solidified resins, sludges, and liquidwastes.

(5) Incinerator ash, residuals, or equivalentwaste which has been rendered non-dispensable in a binding matrix.

(6) Other dewatered and dry materialprovided concurrence is received bycontainer vendor and disposal facility.


Prior to using a.High Integrity Container for aspecific waste material, procedures shall beestablished to define the specific requirementthat shall be met during use of the container.

The procedures shall contain:

Documentation requirements that specificconditions have been met such asinspection and exposure to degradingconditions.

Instructions as to how to handle andproperly close the container.

Instructions for on-site storage ofloaded containers for ultimate shipmentfor disposal.

The procedures shall provide a method fordocumenting required information relevant to thecontainer from initial receipt to shipping fordisposal.

Required information shall 'be based upon thecontainer certificate of compliance and disposalfacility requirements.

Retention and utilization of the documentationshall be defined in the procedures.

The procedures shall establish specific gualityControl inspection requirements.

Prior to the first shipment of a specific typeof High Integrity Container, authorization shallbe requested from the applicable regulatoryagency governing use of the container inquestion at the disposal facility of concern.


High Integrity Container Limitations

a. High Integrity Containers are approved for useprovided the following physical limitations ofthe waste are met:

(1) Vectra Payload density

(2) Loading temperature

Sl;47 gms/cc

g170 F

(3)

(4)

(5)

(6)

Vectra EL-50 N.S. loaded weight : 64200 lb

Vectra EL-142 N.S. loaded weight : <8250 lb

Vectra EL-142 S. loaded weight : 611250 lb

Vectra EL-190 N.S. loaded weight: gl1950 lb

(7) Vectra EL-190 S. loaded weight 514800 lb

(8) Vectra EL-210 N.S. loaded weight: g13000 lb

(9) Vectra EL-210 S loaded weight

{10) CNSI Small loaded weight

(ll) CNSI Hedium loaded weight

(12) CNSI Large loaded weight

(13) Radlok 179 loaded weight

(14) Radlok 195 loaded weight

(15) Enduropak 105 loaded weight

517300 1 b

52500 lb

g2500 lb

g2500 lb

gl8500 lb

gl8500 lb

gl700 lb

b.

(16) Enduropak 205 loaded weight : g1900 lb

{17) Enduropak 150 loaded weight : g2400 'lb

The maximum concentration of radionuclides withhalf lives greater than (5) five years that maybe disposed of in a High Integrity Container is350 pCi/[c. Other waste forms shall not exceed1.0 X 10 rads maximum integrated dose to thecontainer.


c. The polyethylene High Integrity Containers shallnot come into contact with materials listed inAttachment E.

d. A passive vent design shall be incorporated intothe container to relieve internal container,pressure.

Closure of High Integrity Containers

a. Closure of High Integrity Containers shall becompleted in accordance with approvedprocedures.

b.

C.

d.

If the container is not equipped with a passivevent and its contents are within the limits ofLow Specific Activity ensure one of thefollowing:

(I) The container is shipped within (10) tendays after closing;- or

(2) If the container has been closed forlonger than (10) ten days, it shall beopened, vented, and re-closed within ten

. (10) days of shipment.

If the container exceeds the limits for LowSpecific Activity or contains water and/ororganic substances which could radiolyticallygenerate combustible gases, determination mustbe made such that the following criteria are metover a period of time that is twice the expectedshipment time:

(I) The hydrogen generated shall be limited toa molar quantity that would be no morethan 5% by volume of the container gasvoid; or

(2) The container and shipping cask cavityshall be inerted with a diluent to assurethat oxygen is limited to gBX by volume, inthose portions of the package which couldhave hydrogen greater than 5X.

Step 6.7.4.b and 6.7.4.c shall also apply todewatered waste in steel liners.


P

6.8 IRRADIATED HARDMARE PROCESSING AND DEMATERING

6.8.1 General Requirements'. Processing an'd dewater'ing of Irradiated Hardware~ .. 'hall be performed by .qualified SSES or vendor

'ersonnel.

b. Processing and dewatering of Irradiated Hardwareshall be.performed in accordance with approvedprocedures.

Ci Irradiated Hardware consisting of non-fuelSpecial Nuclear Haterial shall be inventoriedduring processing in accordance withNDAP-QA-'0337.

6.8.2

6.8.3

d. Dewatering procedures shall be based onliquid'olume

and drainage calculations and actualdrainage verificatios'fo demonstrate the .ability '.

. to achieve free liquid limits as specified bydisposal. facilities and'applicable regulatoryagencies.

0

Dewatered Product Control '

a. The final dewatered product shall contain lessthan 0.5X free liquid for steel liners.

b. guality Control checks shall be performed onprocess steps.

Irradiated Hardware Processing and Dewatering Records'.

. All records generated shall be completed andfiled in accordance with approved implementingprocedures.

6.9

6.9.2

CONTAINER INSPECTIONS

6.9.1 guality Control shall inspect containers to be used:fear solidification, dewatering, and other packaging.for disposal.

This inspection shall assure that prior to use,the'ontainersto be used for solidification, dewater ing,

or other packaging are. intact and their internals arefree of. any visual damage that would prevent them from '.,

performing their intended function.

III

f

p~g J —f9', /d> 7' HDAP-qA-0646Revision 4

PQQg X~f N . 'age'47 of.63

6.9;3 Packages shall meet .the general criter'ia for normaltransport conditions in accordance with therequirements of 49'CFR. Type A packages shall meetthe additional design requirements specified in49 CFR.

'.10 MASTE CONTAINER SPACE UTILIZATION

6.10.1 Maste volume shall be maximized within theguidelines of specific procedures to minimize:

'otentialvoid space at the top of wastecontainer. after s'olidification or dewatering is '.complete.

6.10.2 ~

6.10.3

6.10.4 ~

AdcKtional radioactive material shoul'd beadded'nly after the initial waste volume isin final form and sampled and the added wastevolume is in final form and sampled.

\

b. The additional material may be drawn intocontainers able to withstand higher externalpressures without degredation by creating anarea of low pressure fnside the container,such as with steel liners.

c. tor all'ther containers, the additional~ material. shall be added via mechanital

~ processes or by other conveyance which doesnot exert higher exteznal pressures.

a

Maste volumes shall sect or exceed. disposal sitecriteria. Ifwaste volume 4s less than disposalfacility'criteria; requirement for disposal ofthe container in question shall be defined'bythe disposal facility.Specific waste volumes committed to by the .

Solidification/Dewatering/Services Vendor shallbe met or otherwise j'ustified as to why wastevolumes were not- achieved.

Susquehanna Guaranteed Sol idi fied/DewateredMaste Volume Record, Form NDAP-gA-0646-3; shallbe completed by the Solidification/Dewatering/Services vendor 'personnel, approved by. RadwasteSupervisor and shall be used to track..solidified/dewatered waste volumes'chieved, ineach individual container.

6.11 STORAGE OF PACKAGED RADIOACTIVE MASTE

6.11.1

6.11.2

Radwaste Supervisor shall provide Solidificationand/or Dewatering Record sheets that have beenreviewed by 'guality Control personnel stating thatprocessed waste has been solidified or de-watered 'inaccordance with=the Process Control Program and meetsthe applicable shipping and disposal criteria.

So'lidification and Dewatering Records shall 'includethe isotopic mix, isotopic concentration of the',wastethat was packaged, the total volume of the waste, andthe amount of water, cement or other solidificationagent used, as appropriate.

NDAP-gA-0646Revision 4

. Page 48 of 63

6.11.3

6.11.4

6.11.5

6.11.6

Solidification and Dewatering Records shall be pari ofthe permanent shipping records and adhere torequirements of the Process Control Program.

For materials packaged in a high integrity container,documentation shall be maintained on HIC,storage andpre-shipment checklist information.-

Packaged radioactive waste shall be stored in areasdesignated by HP Foreman Effluents Management.Storage of packaged radioactive waste in the Low LevelRadwaste Holding Facility (LLRWHF) shall be inaccordance with approved procedures.

An inventory of. stored, packaged waste shall bemaintained in accordance with approved procedures.

6.12 TRANSPORTATION, SHIPPING AND DISPOSAL REGULATIONS

6.12.1 Specific regulatory documents 'shall be maintained onsite in a status that is current. Specificregulations that shall be maintained include but arenot limited to the following:

a. 10CFR71 Packaging of Radioactive Material fortransport and transportation of radioactivematerial under certain conditions.

b.

c ~

d.

e.

9

49CFR100 - 199 Transportation.

Chem-Nuclear Systems Inc. Barnwell S.C. disposalsite operating license number 097 State of.SouthCarolina, as required.

Chem-Nuclear System Inc. NRC Material License12-13536-01, as required.

Chem-Nuclear System Inc. Barnwell- S.C. disposalsite operating procedures and site criteria, as .

required.

Scientific Ecology Group Licenses R-73008-E94,R-01052-A91.

Cask Manuals for casks of which PPKL is anauthorized user.

h. A copy of the license for each facility to whichRadioactive Material is sent:


6.12.2

6.12.3

i. 10CFR61 Licensing requirements for land disposalof Radioactive Waste.

Procedures applicable to transportation, shipping anddisposal shall be developed.

a. Procedures shall be established and maintainedto provide directions and assure

regulatory'ompliancefor manifesting, which includeapplicable federal, state, and disposal

facility'egulations,and NRC guidance.

b. Procedures shall contain check off listswhere'nd

when applicable to assure specific attentionis paid to the critical function beingcontrolled.

c. Procedures shall contain guality Controlnotifications or hold points.

II

Computer software used to implement applicableportions of the Process Control Program shall be inaccordance with NDAP-gA-0801.

6.13 SHIPPING OF RADIOACTIVE WASTE

6.13.1

6.13.2

6.13.3

6.13.4

All radioactive waste shall be shipped by EffluentsManagement.

All radioactive waste shipped from SSES shall only beto facilities licensed to receive the waste and inaccordance with 10CFR20, 10CFR71 and 49CFR100-199.

Dry Active Waste {DAW) should normally be shipped asType A quantities and therefore do not requirespecific licensed containers.

Waste containers shall be placed in a USNRC approved1'icensed shipping container if it:

Exceeds Type A quantities

b.

c

Exceeds 1000 mr/hr on contact

Exceeds 1000 dpm/100 cm loose surfacecontamination on the exterior of the container.

gmp-qA-0646Revision 4Page 50 of. 63

The specific conditions of the Certificate ofCompliance for each approved shipping cask shall bestrictly adhered to.

Packaged waste may be shipped unshielded if:a. - Contact dose rates are less than 200 mrem/hr .and

dose rates at 6 feet are less than 10mrem/hr.

b. Curie content of the package shall be a Type Aquantity.

c. Container shall be a minimum of a strong tightcontainer.

.Prior to the shipment of a package of radioactivewaste, the HP„Foreman Effluents Hanagement shallassure the container is surveyed for contact doserates and surface contamination. Decontamination, ifrequired, shall be done under the direction of the HP

'oreman Effluents management. Decontamination may bewaived based upon radiological conditions.

All vehicles used to transport radioactive wasterequiring the vehicle to be placarded shall be checkedfor adequate operation and safety conditions.

All Radwaste shipments from SSES shall normally be via"Exclusive Use" vehicles. Specific instructions givento the driver include:

a. Expected route of travel to his finaldestination.

b.

Ci

Maintaining "Exclusive Use" status.

Specific actions to be taken in the event of anaccident.

No vehicle carrying radioactive waste that isoverweight shall leave SSES without a Pennsylvaniaoverweight permit.

a. A DAW shipment or other shipment capable ofhaving its weight adjusted, shall not be allowedto leave SSES overloaded.

b. An overloaded condition for any vehicle is basedon total weight and weight per axle.

NOAP-gA-0646Revision 4 ,

Page 51 of 63

6.13.11 In'the event access is denied to SSES at all operatingdisposal facilities, PAL will provide carrier with aletter stating that SSES will meet all applicablefederal, state, and compact requirements for receiptback of the radioactive waste/material in carrier'spossession.

6.14 SHIPMENT CONFIRMATION

If disposal site shipment acknowledgement is not received within18 days from departure from SSES, Effluents Management Supervisionshall conduct a trace investigation for shipment location. If thedisposal facility shipment receipt can not be confirmed within 20days, a Condition Report (CR) shall be generated.

6.15 CHANGES TO THE SOLID RADIOACTIVE NSTE PROCESS CONTROL PROGRAM

6.15.1 Any changes as described in the TechnicalSpecifications, to the Solid Radioactive Maste ProcessControl Program shall be provided in the AnnualRadioactive Effluent Release Report filed with theNRC.

6.15.2 Any changes to the Solid Radioactive Haste ProcessControl Program shall be approved by Plant OperationsReview Committee (PORC) prior to implementation.

(") 6.16 EVALUATION OF PROCESS OR OPERATIONAL CHANGES

6.16.1

6.16.2

Changes in radioactive waste processing or operationalchanges shall be evaluated to determine any impacts onwaste characteristics and/or form.

Evaluation should include as a minimum:

a. Operational evaluation of processing impacts.

b. Chemistry evaluation of changes to sampling and.analysis methodology .-

Ci

d.

Effluents Management evaluation of packagingand/or shipping impacts.

Effluents Management evaluation for 10CFR61compliance.

8


e. Solidification/Dewatering Services Vendor wastestream characteristic evaluation of thedewatering/solidification system operatingparameters and effectiveness.

( ) 6.17 REPORTING OF NISHAPS INVOLVING LOW LEVEL MASTE FORMS

6.17.1 10CFR61 establishes the minimum and stabilityrequirements for Low Level Maste (LLM) forms. 10CFR20requi res certification that the processed wastesatisfies the requirements of 10CFR61. Mishaps whichmay impact the final waste form shall be reported tothe NRC.

6.17.2 Types of mishaps which should be reported include:

'a ~

b.

C.

Failure of high-integrity containers used toensure a stable waste form. Container failurecan be evidenced by changed containerdimensions, cracking, or damage resulting frommishand'ting (e.g., dropping or impacting againstanother object).

Misuse of high-integrity containers, evidencedby a quantity of free liquid greater than 1

percent of container volume, or by an excessive(>1M) void space within the container.

Production of a cement solidified Class B or C

waste form that has any of the -followingcharacteristics:

(1) Contains free liquid in quantitiesexceeding 0.5 percent of the volume of thewaste.

(2) Contains waste with radionuclides inconcentrations exceeding those consideredduring waste form qualification testingaccepted by the regulatory agency, whichcould lead to errors in assessment of-waste class.

(3) Contains a significantly different wasteloading than that used in qualificationtesting accepted by the regulatory agency.


d.

(4) Contains chemical ingredients not presentin qualification testing accepted by theregulatory agency, and.those quantitiesare sufficient to unacceptably degrade thewaste product.

(5) Shows instability evidenced bycrumbling, cracking, spalling,voids, softening, disintegration,non-homogeneity, or dimensionalchanges.

(6) Evidence of processing phenomena thatexceed the limiting processing conditionsidentified in applicable topical reportsor process control plans, e.g., foaming,temperature extremes, premature or slowhardening, and production of volatilematerial.

I

Failure to adhere to high integrity containerlimitations as required by container certificateof compliance.

6.17.3

6.17.4

e. Notification of violation by disposal facilityregulatory authorities at time of container.receipt for disposal.

'ailureof cement-solidified stable waste formlong term PCP surveillance specimens due toevidence of significant cracking, spalling, orbulk disintegration, compression or penetrometerstrength and i@version test results.

Requirements for reporting of mishaps shall apply onlyto processing liners and high integrity containerscontaining radioactive waste in its final productform.

A Condition Report (CR) shall be generated if one ofthe mishaps mentioned occurs.

6.18 PCP IHPLEHENTING PROCEDURES

Procedures required for implementation of the Process ControlProgram are shown in Attachment D. *

NDAP-gA-0646Revssion 4Page 54 of 63

7.0 ~RECO DS

7.1 The Solidification Records or Dewatering Records and the attacheddocuments shall be forwarded to fffluents Management Supervisionfor retention until such time as the container identified onRecord is shipped for final disposition.

7.2 When the identified container is shipped the SolidificationRecords or Dewatering Records and other documents concerning the .

Shipment shall be filed with the shipping documentation andforwarded to DCS for retention.

7.3 Documentation of Radioactive Waste Shipments shall be retained asrequired by SSES Technic'al Specifications.

7.4 Radioactive waste shipping documentation shall consist of, but notlimited to, the following records:

7.4;1

7.4.2

7.4.3

7.4.4

7.4.5

7.4.6

7.4.7

Radioactive Material Shipping Nanifest

Evaluation of isotopic mix and concentration

Radiological surveys of:

a. Vehicle upon arrival

b. Package to be shipped

c. Loaded vehicle prior to shipment

Vehicle Safety inspection

Check-off sheet for loading procedure

Documentation of adherence to Process Control Program(if applicable)

Special instructions to driver

SOLIDIFICATION RECORD SHEET

PART I: Container identification Information

d

Attachment ANDAP-gA-0646Revision

.4'age

55 of 63

1. PPSL Liner NumberNumber'. Container Vendor Serial

{RWCU Filter Media. cannot be entered)

(circle one)

3. Waste Stream

Test Solidification required7 YES NO

PART 2: Container Selection (Refer to MH-PS-100)

3. Expected Maste Classification/Stability

l. Estimated Liner Contact Dose Rates mR/hr

t. P 'dt / t t tt ~tt/d4. Container Type to be Used

6. Expected Cask Type to be Used

PART 3: Documentation Checklist

5. Empty Reight of Containet 'ha

l.2.

3 ~

Form NDAP-gA-0646-1 (original)Waste Form Documentation

WH-RP- Forms (original)SC-068-%2 Forms (copy)Maste Form: STABLE UNSTABLE {circle one)~85% Liner Volume Utilized: YES NO (circle one)

Qaste Activity DocumentationCH-RC- . Forms (copy)Isotop>c Analysis (copy)Compost added/Log entry made on CH-TP-055-1

4,

PART 4:

Health Physics DataLiner Radiological Survey (original)Actual Filled Container Weight

REMARKS:

lb. (If available ALARA}

FORM NDAP-(A-0646-1, Rev. 2, Page 1 of 1 (File R69-1)

T NG CO S

Attachment BNDAP-gA-0646Revision 4Page 56 .of 63

PART I: Container Identification Information

1. PPKL Liner Number 2. Container Vendor Serial Number

3. Maste'tream

PART 2: Container Selection (Refer to RR-PS-100)

1. Estimated Liner Contact Dose Rates 'R/hr'I

2. P tdC i C t t'li/g3. Expected Maste Classification/Stability

4. Liner Type to be Used

6. Expected Cask Type to be Used

5. Empty Meight of Container

a waste upervlsor ate >me

FORM NDAP-(A-0646-2, Rev. 3, (DUPLEX), Page 1 of 3 (File R69-1)

~PRT 3: Sampling and Analysis

1. Tank/Container sampl ed

2.. Sample Number

3. Waste Stream

4. Isotopic Analysis attached

AT ING CO D S

'ttachment BNDAP-gA-0646Revision 4Page 57 of 63

5. Specific activity of Dewatered Sample pCi/gm

6. a. Dewatered Volume

b. Dewatered Weight

c. Sample density

ml

gm

gm/cc x 62.43 lb/ft7. Composite added/Log entry made on CH-TP-055-1

The above tank/container containing solids has been analyzed in accordance withCH-RC-075 and found to contain the isotopes and specific activities as indicatedon the attached data sheets.

em>stry upervssson a e >me

FORM NDAP-(A-0646-2, Rev. 3, (DVPLEX) Page 2 of 3 (File R69-I)

ATER NG CO D S

+gT 4: Container Shipment Information Summary

Attachment 8NDAP-gA-0646Revision 4Page 58 of 63

3.

4.

PPEL Liner Number

Form NDAP-gA-0646-2 (original)

Maste Form Documentation

2. Maste Volume

MM-RP- Forms (original)t ~

Calculated Maste Meight lb/ft3 x ft lbPart~Actual Filled Container Weight lb. (if available ALARA)

)00 x (Dewatered Waste Volume) fts ~ fts

>85% Container Volume Utilized YES / NO (Circle one)

Waste Form: STABLE UNSTABLE (Circle one)

Maste Activity Documentation

CH-RC- Forms (Copy)

Isotopic Analysis (Copy)

PART 5: REMARKS:

a waste upv ate eview ~ate oreman I~ac

FORM NDAP-gA-0646-2, Rev. 3, (DUPLEX), Page 3 of 3 (File R69-I)

SU U HANNA GU 0 SO F EO EW T

Attachment C


ST Vo U 0 0

1. Date Liner number

2. . Waste Type

3.

4.

Container Type

Burial Volume

Useable Container Volume

7.

8.

Guaranteed Minimum Waste Volume

Waste Volume Attainedinches x

Waste Volume Container Usage

fts

ft> /inch

. 100 x (Waste Vol. ft> ~ Guaranteed Win. Waste Vol. ft3) -100

Dead band Assessment Volume

Guaranteed Min. Waste Vol. ft k {0.01 X Guaranteed Min. Waste Vol. ftMinimum{-) . ft to Maximum(+) ft

10. 'Performance Assessment Volume

Dead band Assessment Vol. ft Waste Vol. ft ft11. Remarks:

12. Signatureo s 1 >cation en or epresentatsve

13. Signaturea waste uperv~sor

FORM NDAP-(A-0646-3, Rev. 2, Page 1 of 1 (File R69-1)

M ST P OC SS NG

CP P M NG OC DUR

Attachment D

NDAP-qA-0646Revision 4Page 60 of 63

va orator Concentrates — Solidified

Pacific Nuclear PT-51-WS'acificNuclear OM-114-NS

Pacific Nuclear OM-104

Mixed Solids — Solidified

Pacific Nuclear PT-51-MSPacific Nuclear ON-104Pacific Nuclear OH-114-NS

LRW Filter Media URC Wast WCU F ter ed'a S S ud e - Dewatered

Pacific Nuclear OH-43-WSMM-RP-107

Condensate Radwaste Deminera 'r ead esi - So idified

Pacific Nuclear PT-51-MSPacific Nuclear ON-114Pacific Nuclear OH-104

Condensate Radwaste Demineral'r Bead Resin - Dewatered

Pacific Nuclear OH-43-MS

WM-RP-106

Cartrid e Filters

CNSI FO-OP-019 (Overpack)

WM-PS-230

Pacific Nuclear OH-16-NS

MM-RP-)05

SEG STD-P-22-002(Resin Express)

WH-RP-104

SEG STD-P-03-051

MH-RP-108

.Page 1 of 3

CP IMP M NG OC U

Attachment DNDAP-gA-0646Revision 4Page 61 of 63

r ad'ated Hardware — Dewatered Ste 'rNone

Dr ctive Waste DAW — Packa

WM-PS-210

'id Oil Waste — Solidif ed

None

'id Oil Waste - Decontamination

None

Solid Sealed Sources

None

WASTF ANALYSIS AND CLASSIFICATION — OCFR6

Pacific Nuclear OM-45 NSWM-RP-008

CH-RC-075CH-RC-076CH-TP-055

WM-PS-155WM-PS-160WM-PS-170

T STING TREATMENT COMBUSTIB GAS S

WM-RP-009 WM-RP-301

0 CT V WAST SO FIC T ON-

Pacific Nuclear OM-114-.NS

SC-068-002 (Test Solidification)

CMNT

Page 2 of 3

PCP I PL MENT NG PROC DU

Attachment DNDAP-qA-0646Revision 4,Page 62 of 63

RADIOAC IVE WASTE DEWATERING — GENERAL

Pacific Nuclear OH-60-MSWM-RP-010

HIGH IN GRITY CONTAIN RS

Pacific Nuclear OM-16-NSPacific Nuclear H-18-NSWH-RP-012

ISPOSA FACILITY RE UI EMENTS

MH-PS-180

~AC@GING

MH-RP-Ol1

WH-PS-401 (LLRMHF)

WN-PS-310WN-PS-311WH-PS-315MN-PS-345WH-PS-351WM-PS-352WH-PS-356

(HN-'142)(LN-142)(SEG 3-82)(CNSI 14-195)(CNSI 21.;300)(CNSI 8-120A)

MH-PS-354 (CNSI 14-215)WM-PS-316 (SEG 14-215)WH-PS-318 (Westinghouse TCT)

TRANSPORTATION - 49CF OCF 7

WN-PS-100WH-PS-120MH-PS-140WM-PS-180MH-PS-240WN-PS-250

Page 3 of 3

ATE I S NOT COMPA B E W PO

Attachment ENDAP-gA-0646Revision 4Page 63 of 63

Y N CO INERS

Aliphatic hydrocarbons (hexane, octahe,bexene, octane, etc.)AcetoneAmyl AcetateAmyl ChlorideAnilineAqua Regia

BenzeneBromine liquidButane

Camphor OilCarbon DisulphideCarbon TetrachlorideChlorine liquidChlorobenzeneChl or oformChlorosulfonic acidChromic/sulfuric acidCyclohexanone

DibutylphtalateDimethylamineDiesel fuel

Ethyl acetateEthyl butyrateEthyl chlorideEthyl etherEthylene chlorideEthylene chlorohydrinEthylene dichloride

FluorineFurfuralFurfuryl alcoholFuel Oil

Gasoline

Iodine

Methyl bromideMethyl ChlorideMethyl ethyl ketone (MEK)Nethylene ChlorideMoist Chlorine gas

Nitric Acid (50K weight concentration)

Organ PeroxidesOctyl cresolOleic acidOleum

PentanePetroleum etherPhenolPropanePropylene dichloride

Sulfric acid (60K weight concentration)

TetrahydrofuranceTitanium tetrachlorideTouleneTrichloroethyleneTurpentineTetralin

Xylene

Page I of I

't

'/

Documents

REVISIONS SSES SOLID PROCESS PROGRAMndap-ga-0646 revision 4 page 3 of 63 section 1.0 purpose 2;0 policy/discussion 3.0 references tab of conte s 4. 0 responsibilities 4. 1 effluents