ML20238A503

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Rev 3 to Solid Waste Process Control Program for Shoreham Nuclear Power Station Unit 1
ML20238A503
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 02/04/1987
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20238A498 List:
References
PROC-870204, NUDOCS 8708310102
Download: ML20238A503 (24)
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Text

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SOLID WASTE PROCESS cot

  • TROL PROGW4 FCV SHOF.U'M h"JCIIAF. PGTF STATICC - U::IT 1 RE','ISION 3 i

Ift;G ISLt27., LIGHIING CCtGAh*/

Docket Nc. 50-322 Januar,.' 19, 1967 Prepared by: I . c' ,

Date: . / /I > / .

l Nuclear Engineering Departnent / '

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Approved by:~ / ,' . .'-;, '.' r v. Date: '7.7/

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Approved by: M[/' 4.% _% Date: C-4 ~T[

Plant Manager 1'

UNCONTROLLED

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8708310102 870828 PDR ADOCK 05000322-R PDR I

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t TABLE OF CCNTDCS 1~ PAGE:

1 n l'. 0 ' PURPOSE 2.0 RTOIOACTAT WASTE SOURCES 2

'2, 2.1 . Evaporator Bottcrs

-2.2 Floor Drain Filter . 2

'2.3- Padwaste Filter 3 ii 2.4= Spent Pesin Te9. .

4 2.5- Cartridge FilterF 4 2.6 Trash Ccnpactor 4 3;0. . Radioactive Waste Streams 4 6

4.0 In-Heuse Solidification Syst(c 5.0 In-House Dewatering ,

6 L 6.0 Mobile Solidification and Dewatering Services 7 Solidification Process Control Parameter Determination 7 7.0 8.0: Solidification and Dew: tering Process Control 7 Sanpling arf. Analysis 7 S.1 f{'.1 E.2 Conhtiorin- 6 E.3 Batch Test Solidification 9 8.4 Waste Classification. 10 8.5 Container Control 10-II 8.6_ . Decontamination 8.7- Changes to the Process Control Progra:r 11 8.8 Records and Inventory Control- 11 Responsibilities- 11 9.0 10.0 References. 13 10.1. LIICO Operating Procedures '13 10.2 Mobile Services Contractor Documents 13 L 10.3 General References 14 Appendix A Solidification Record. Sheet 16 Appendix'B Dewatering Reccrd Sheet 21

-FIGURE 1 ' Solid Radwaste Syster,. 22 p

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Page 1 of 22 1.0 _ PURPOSE The Shoreham Muclear Power Station (Sh*PS) Process Control Program (PCF) descr2be the administrative and process controls wttich provide reasonabic assurance of a consistent cuality radioactive waste product which is acceptable for shipnent and burial. Implementation of this PCP will:

o Provide assurance that waste types produced at Sh'PS will be classified satisfactorily in accordance with the requirements of 10CE62.

o Provide assurance that the requirements of 10CFR61 and specific disposal site criteria for Class A unstable waste to be solidified ere met by the use of a ncbile solidification syster. supplied by a qualified contra-ter. Whcr edditional saq;1e solidificatic dat?

beccas available, this PCP will be modified to de~ce. strate the qualification of the in-house solidification system that ray be used ,

in addition to a nobile solidification syster, supplied by a qualified contractor, for processing of Class A unstable waste.

o Provide. assurance that the waste form stability requirements of 10mC2 for Class B and C wastes are met. This will be accceplished through the use of a mobile solidificatier. system supplied by a qualified contracter er use of approved High Integrity Containers (HICs) . Unti:

such time as thc contractor's Topical Report has been approved by the G hT<C, qualification will bc based on the contractor's past record of producing acceptat',e BU wastc packages for waste strea .s sirdle.r tc those prcduced at SSPS. h contractor's Process Centrol Procra.s arc.

referenced in the " Mobile Service Contracter Documents" Section of this docunent. Sh'PS nanageme .t shall enFure that the contractor's waste processing operations are performed in accordance with procedures.

o Provide assurance that dewatered Class A, B or C waste products neet the applicable burial site criteria for free stariing water when the in-house or ccatractor's dewetering equipnent and procedures are used.

o Provide assurance that the processing and packaging of solid radioactive wastes meet the requirements of federal and state regulations and disposal site criteria.

o Ensure that'the quality assurance requirements delineated in 10 CrF 71.101, 71.103 and 71.105 are net for both in-house and nobile contractor processing. ,

2.0 PAOICACTIVE Kt.STE SOURCES low-level radioactive wastes are prcduced as a result of routine plant cperaticr. and maintenance of pla*.t systems. Tbc rejer contributing sources cf radioactive waste are listed below:

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Page 2 of 22 2.1 EVAPORKIOR BCf"TCEF 2.1.1 Waste Evaporator The waste Evaporator receives hig'. conductivity waste prire.rily free the floor drains.

The design concentration of the Waste Evaporator is an le weight percent concentrate of dissolved and suspended solids.

2.1.2 Regenerant Evaporator The Regenerant Evaporator receives primarily liquid chenical wastes prodr. ' b:- the acid / caustic regeneration of the condensate demineralized resins.

The waste is collected, neutralized, and sampled in the Regenera"t Liquid and Evaporator Feed Tanks, and then purged

. to the Regenerant Evaporator for concentration to a 25 weight percent trixture of sodiurr. sulfate and other dissolved and suspended solids.

2.1.3 Bottms Transfer O

Lach evaperatcc is a forced circulation desic. with a reboiler providing process heat and an overhead entrainrent separator and rectifying coltrrn which minirrizes liquid droplets in the vapor. When the desired solid content has been reached, the concentrated evaporator bottccs are cooled and sent to the Evaporator Bottms Tank or directly to the Evaporatcr Bottens Metering Pump for solidification according to the centractor's procedure F458-P-002, "Oparating Procedures for Mobile In-Container Solidification of Sodium Sulfate Slurries."

In order to provide neximum flexibility, each evaporator can be used as a back-up for the other.

2.2 FLOORDPh1NFIL3 The filter is a horizontal traveling screen, precoat type, designed for air drying and air-aided discharge of the cake (withcot backflushing) into a shipping container for further dewatering. The waste ray contain filter nedia such as diatomaceous earth or a powdered resin / fiber blend type naterial.

The floor drain filter is used to process the follcwing cmbined.

1icuid radvaste streers:

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Page 3 of 22 o Reactor Bldg Floor Drains o Turbine Eldg. Flocr Drains i o Radwaste Bldg. Floor Drains'  !

o Machim Shop Flocr Drains o Sample Tank Area Floor Drains -

o Turbine Bldg. Deacon Area F1cor Drains o Condenscte Demin. System Waste Sump Pump Disch, and t.E Backwash.

o Cond. Storage and Transfer System overflow Sump PLrrps discharge.

o laundry Drains Tad.

Class A, B and C waste which is dewatered using in-house equipment is processed according to SF R3.710.02, " Dewatering of Spent Radwaste Madia".

Waste which is dewatered by the contractor's nobile equignent will be processed according to his procedurec, (see "REFERI: ICES" sectien) .

2.3 RDS.STI. FILTEF.

The Radwaste Filter is used to process the following certined liquid radwaste streams:

o loi conductivity equignent drains j o Reactor Bldg. Equip. Drains, drywell e-aip. drains, Radwaste Bldg '

equip drains, and Turbine Bldg equip. drains p o Solid Waste Syster dewatering tank decanted licuic' o RK filters displace.w / anG prefiltration liqui 6 o Decanted liquid frcr- the Phase Separater and the Spent Resin Tara o Blowdown frcr. the reactor water cleanup and residual heat remval systems o Blowdcrc. frcrr the Fuel Pool Cooling and Clean-up System o Ultrasonic Resin Cleaner Backvash The radwasto filter units are each ccrposed of stacked horizontal

, filter disc; assetlef en an axially located hollow shaft. After draining the filter vessel and air-drying the filter cake, the 1 filter assembly is spun to rencve the filter cake frcrr. the filter l discs and discharged directly into a waste shipping container for '

dewatering and disposal.

The waste resulting frcrn the filters nay contain diatomaceous earth, Ecodex or similar pcudered resin / fiber blend material. If Class A, B or C waste is being dewatered using in-house equipnent, it is processed according to SP R3.710.02, " Dewatering of Spent Ra:hraste Media". All classes of waste may also be dewatered by the contractor using procedures referencad in the "REFERDCES" Section.

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, a Page 4 of'.22 L .m 2.4 SPL'T RESIN TANE - (SRT) l

The Spent Resin Tank accepts resin / filter medic -(via the Phase Separctor Tanks) from the reactor water cleanup (RWCU) filter de .ineralizers, the' sludge frm the backwash storage tank of. the -

Fuel' Pool Cooling and Clean-up etched-disc type filter, in additier. "

to spent bead resin ,frm. the condensate demineralizers, .the fuel -;

. pool-demineralizers, and the radwaste'demineralizers. The resin is allcwed to settle befcre excess water is decanted to the waste callector tanks. ,

o .

l Mixed powdered and bead resin in.the SRI can be transferred directly ,.

into a HIC frcr the SRT for dewatering by the in-house equipwz.t or the contractors' Mobile unit using the procedures in the "RITEhCCEF" section of this PCP. '

2.5- CAPTRIDGE TILTERS ,,  ?

The laundry. Drain System and the Control Drive. System use $

cartridge type filter for processing. These cartridges Iray' be

-irrchilized. in .a' cement nixture which includes evaporator _ bottcrrs concentrates or spent resins. These may also be~ cmpacted as Dry

' 1 Active Waste . (DAW) usiny SF F3.075.01 (provided the filter cartridge is ' dry) . ' Liners that coctsin solid objects are specifically identified.

2.6 TRASH CTPICIDE The drut. cmpactor is used to conpress low level' dry waste such as rags, paper, shoe covers, floor sweepings, dry filters, HEPA filters, strainers and plastic gloves into 55 gallon steel dr ms fer shipment offsite . : Campaction force is rated at 18,000 lbs for an approximate 4:2 cornpaction ratio. t A box-cmpactor will be installed which ecrnpresses waste into 96 cu. .

ft. metal boxes. This is a self-contained unit with its own HEFA filtering system. The ca paction force is rated at 60,000 lbs.

3.0 PADICACTIVE WASTE STPIN'S < ,

3.1 EW@ORATOP BOITCFICONCB'TFATES ',

'o. :I 'l This may be a mixture of : .; 7 c q.,

c 3.1.1 Che-ical regeneration concentrates frcrr. the Regenerant t Evaporator process. '

j 3.1.2 Floor Drain concentrates frcrr. the Waste Evaporator process / ' i MA__--_------_------------__-_-__m._, --

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Page-5 of '22 3.2 ~ SPDC RESH; TAh7. WASTE This might be a mixture of the foIlowing:

1 3.2.1 Condensate Demineralized Pesins .

3.2.2 Radwaste Demineralized Resins 3.2.3- Fuel Pool De:-ineralizer Resins

.3.2.4 Phase Separater Resin'

3. 2. 5 - Veece Filter Bachesh Sludges

-3.3- FLT A FIL S GENrd r WASTE -

3.4 FICOP D: "i FILTEE GE;ETG.T US"E 3.5 DRY ATn'E WASTE (DM3 3.5.1 Cmpaetible 3.5.2 Unn-Capartible

3. 6 - FIL S C M r.!DGEF
3. 6. I' hrrA Filters 3.6.2 Laundry Drain Filter Cartridges 3.6.3 CRD Filter Cartridges 3.7 RADIOACTIVE 3 COCAMINATED LIQUIDS AND SOLIDS Due to val' jing buriel site regulations, each will be handled on a case by case basis in accordance with the burial site criteria and federal regulations.

3.7.1 Organics (including oils) 3.7.2 Charcoal (Filters, Charcoal Beds)

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4.0 IN-HOUSE SOLIDIFICATION SYSTm SNPS has a permanently installed Atcor radioactive waste solidification system which, when additional test data is available, may be used to package either radioactive evaporator bottans or resins / sludges for disposal as Class A waste. Until that time, all wastes for s:blidification will be transferred to the contractor's mobile equipment.

The frilowing is a description of the in-house system. Waste and cement fla.s are fixed by preset metering pugs using f1cn rates recomended by A cor cnd verified by full scale testing. F1 m s are also nonitored by techcneters installed on the control panel. The resin / sludge is processed fra the kaste Devatering Tank and evaporator bottms are processed frm the evaporctcr bottCDS syste: or directly frm. the evaporators.

Cement and evaporatcr bottms er resin / sludge are introduced into the mixer feeder unit for through mixing and discharge into a container. The arall-volux continuous mixer limits the surface contact of the wet cemnt and also linits the gaantity of wet cement in the system at any time. A manual handcrank is provided to pemit emptying the mixer / feeder by the operator in case of pcv.r loss or eqaipment malfunction.

Flush water connections are provided inside the mixer / feeder to renove cenent residuc.

Safety featurn inclu6+:

o An interlock to prevent filling unless the pipe is propcrly inserted into the container fill opening, o An ultrasonic level sensor, and a timer to nonitor waste level in thc container to prevent overflowing. Cement-bearing flush water cannot bc discharged unless.a receptacle is in place.

- o Failure to initiate a flush segaence within 20 minutes after fillire stops procpts an alarm.

When operational the syster,will be operated according to SP 23.713.01-

" Solid Padwaste System." A sinplified functional diagram appears in Figure 1. '

5.0 IN-HOUSE DD"nTEPING As an alternative to solidification, Class A, B, and C dewaterable waste ray be dewatered in High Integrity Containers (HIC) . Non high intecrity contziners can be used for Class A waste. All of these containers are egaipped with internal filters to which a pu"p may be attached. Pug:.ng

' continues until burial site criteria for free standing non corrosive ligaid are mot as describef ir SP P3.710.02.

Page 7 of 22 Dewatering is conducted in accordance with plant procedure SP R3.710.02, "Dewatenng of Spent Radwaste Fedia," to assure a consistently acceptable product.

6.0 MOBILE SOLIDIFICATION AND DB ATEFRJG SERVICES .

6.1 Wastes to be solidified nust be transferred to the mobile j solidification / dewatering equiprnent which is provided and operated by a cualified contractor. Class A, B or C dewatered wastes may be processed by the mobile sen' ices contractor or the in-house dewatering system at the discretion of the Radwaste Engineer.

Class A solidified wastes may be processed by the contractor or by ,

the in-house solidification system after : qualification is  !

conpleted.

6.2 The "Fobile Sen' ice Contractor Documents" in the "REFEPH;CES" Section lists these procedures which may be used by the mctile services contractor to ensure that waste products meet all requi: cements for shi; rent and burial offsite.

6.3 ' Provisions have been made for the mobile solidification equipraent to be installed on Elevation 19' of the Radwaste Bui",6ing which is a Seis-ic Category I Structure. This equipnent will be installed and utilized as required. Spill Q' arc contained by installing the equiprmnt in areas wherc sicping flocIs will carry lig.: ids te floor drain sunps. Thc building ventilation system provides for filtering of particulate airborne contamination and mcnitoring of radiation befCre it enters the station Ve.nt.

7.0 SOLIDIFICATION PROCESS CONTROL PARAMETER DETF E INATIOJ When additional saTles have been tested for solidification, this section will contain a se rnary of qualification test rusults for the in-house solidification syste:. During the interim, the in-house system will not be used to solidify waste for shiprnent offsite.

8.0 SOLIDIFICATION AND DDGTERING PRCDUCT CO. TROL 8.1 SAMPLING A'O ANALYSIS ,

8.1.1 Sanples shall be obtained and analyzed according to SP ,

72.002.18, "Eadwaste Sampling for Disposal," prior to each solidification or dewatering operation and SP R4.014.01, i "Radwaste Sanple Solidification Test," prior to solidification.

8.1.1.1 Sampling for Solidification

Pege 8 of 22

1. The waste tank to be sanpled shall be recirculated for a minim.2m of three tarA volu ce prior to sampling, unless the tank had been en recirculation continuously since it began filling. .
2. An exception to the above is the Waste Dewatering Tank which is equipped with an agitator rather than a recirculating pump.

Agitation is continued for et least 25 minutes prior to sampling.

3. The waste tank sampled shall remain isolated and in recirculation or agitation, as applicable, u.til the solidification process is started. If-it beccres necessary to add material to the tank being processed, e new batch number will be initiated and a new sanple will be taken after an appropriate mixing time.
4. Test solidification will be perforned acccrding to the schedule described in the " Batch Test Solidification" Section.
5. Solidification sampling requirements apply tc ell waste, W ether it is being processed by permanently installed equipre:4t or by the contractor's mobile equipment.

8.1.1.2 Sampling for Dewatering Funda, Spent Resin Tank and flat bed filter wastes mast be sa pled from the liner. These will not be p ,

mixed prior to sampling.

l 8.1.2 'Ihe following applies to both Dewatering and Solidification.

1. Sa ples will be analyzed for pH and gerara emitters.

Visual inspection will be made for oil.

2. The a*alysis nurber will be added to the Solidification or Dewatering Record Sheet which is prepared for each waste container (liner or HIC) .

B.2 CCtDITICEING l , 8.2.1 Waste conditioning for solidification is required when any of the following conditions exist:

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1. The pH is outside of the acceptable range according to i the contractor's PCP.
2. Liquid co. tent of the batch is above or below the ,

acceptable envelope for solidification as indicated in the Contractor's PCP in the "PEFERDCES" Section documents.

8.2.2 pH shall be determined on the decanted liquid frcrn each container which has been dewatered. If pH is less than 4 or greater than 11 it will. be determined on a case-by-case basic if any further action is ' required prior to shiprent.

E.3 BA2\'H TEST SO!IICTICATICN 8.3.1 Test solidification shall be performed according to tre following schedule:

1. One sate initially frcrn each type of wet waste, and then frcar. every tenth batch of each type of wet waste.

NOTE: Batch is defined as the total volume of waste contained in a waste mixing tank that has been prepared for solidification.

2. When sagle analyses fell outside the acceptable enveleg established by the rnobile services contractor, indicating a change in the. waste type.

8.3.2 If any test specinen fails to so'idify, the solidification of the batch under test shall be deferred until such tine as additional test specimens can be obtained, alternative

. sohdification parameters can be determined, and a subseguent test verifies solidification. Solidification of the batch may then be performed using the alternative solidification parameters determined.

Representative samples shall be cbtained and tested frcrn each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The process control program shall be nodified as required to assure solidification of >

subsequent batches of waste. The contractor shall nodify {

his own KP as necessary to acccrmodate unusual waste streams.

8.3.3 The test specimen shall be judged to have solidified successfully if, when its container has been re:rved, it

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Page 10 of 22 remains a free standing nonolith with no visible free liquid.

8.3.4 If a cement and water mixture (without waste) is used to solidify miscellaneous objects, this mixture will be tested for solidification prior to use.

8.4 KASTE CUSSIFICATIQ1 8.4.1 In ccrnpliance with 10 CFR 20.311, wastes are classified as.

Class A, B or C, or greater than Class C, based on the presence'of particular radionuclides and their activities as.

specified in 10 CFR 61.55. Plant procedureF SP P2.713.06,

" Calculations for Radwaste Curie Content," or SP R3.713.02 "PADE'; Corputer Program" provide the methodology for .this determination as used at SNPS.

8.4.2 Waste streams will be sampled based upon the Branch Technical Position requirements (or more frequently, if plant parameters indicate a change in waste characteristics) and analyzed for fission and activation products, including transuranic. Scaling factors developed frcn these ccrglete analyses will be used with gantra spectra frcrn each batch cf Q waste to infer the concentrations of non-gama snitting O radionuclides.t ,

8.4.3 During initial plant operation when the results of actual analyses are not yet available, radionuclides concentrations will be used in accordance with "RADE - Data Base Analysis Report".

8.4.4 The curie content of ..aste streams (such as trash) for wtdeh representative sanpling is difficult may be inferred based on game analysis of representative smears and external dose rate measurement (SP R2.713.06 or SP R3.713.02) .

8.5 COCAIhTR COUROL 8.5.1 A quality assurance program shall be established to inspect the container to be used for dewatering (and solidification) using SP R2.713.30, "Radwaste M tainer Control".

8.5.2 This program shall assure that prior to use, the containers to be used for dewatering are intact and free of any visual j damage that would prevent the dewatering of waste to required limits.

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Prior to shipnent, containers 411 be' swiped for removable conta:rination and examined for general condition. Decontamination will be conducted as necessary to meet shipping requirements.

E.7 CHANGES TO THE PROCESS CO,TRI PROGPAv. .

.Any changes to the Solid Waste Process Control Program for the Shoreha:r Nuclear Power Station shall be approved by the Revietof Operations Ccmittee and the Plant Manacer and reported to the NRC in the Semiannual Radioactive Effluent Release Feport.

8.6 RECORDS AND INVD,' TORY CQsTRI E.6.1 Solidification

1. A Solidification Pecord Shect (Appendi>: A) shall be ccepleted for each liner filled for solidification.
2. If nere than one liner results frar. a batch, then the

, initial liners will not be shipped until all liners for that batch have verified solidification. Those liners will be identified by a cerrcn analysis number.

O' 8.8.2 Dewatering U

Radiochemistry Analysis Sheet and Post Dewatering Survey Sheet (see Appsndix E and Appendicer 12.4 and 12.5 of SP R3.710.02) shall be corpleted for each container filled with dewatered waste.

8.8.3 Solidification and Dewatering

1. The Solidification or Dewatering Record Sheets and the attachcd isotopic analysis shall be forwarded to the Radwaste Engineer for retention until such tire as the liner identified on the Record Sheet is shipped for final disposition.
2. When the identified liner is shipped and then verified received, the Solidification or Dewatering Record Sheets and other documents concerning the shipnent shall be forwarded to SR2 for permanent record storage. ,

9.0 RESP 0;SIBILITIES The following outlines departmental responsibilities and interfaces to j L inplement and support all activities associated with the SNPS PCP.  !

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1 Page 12 of 22 NCrrE: . ' All service contractor procedures implementing the PCP which win be used-at SNPS, prier to their utilization and implementation, must be approved by the Review of Operations Cam.ittee as per SNPS Tech. Spec.

6.8.1.h. .

9.1 NOC Policy 25 (Management of im I4 vel Radioactive Waste) identifies the following departments as having direct responsibilities.for the

' implementation, maintenance, licensing and regulatory interface of the ShTS PCP.

9.1.1' Nuclear Engineering Department, as also described in hE 1.02.

9.1.2 Shorehan Operation Department, as alsc described in SP

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F1.0C1.01.

9.1.3 Nuclear Operations Support Department.

9.1.4 Quality Assurance Department - (CA) as described in the CA Manual, Section 1.

9.1.5 . Nuclear Review Board (NRB) as also described in the " Charter of the Shoreham Nuclear Power Review' Board".- i See NCC Policy 25 ' fcr nere details. -

. 9.2 Procedure hE 6.04, " Change Control",. in conjunction with the NOSL 6, " Control of License Docurents" shall.be used to review, approve, control and disposition proposed changes and revisions to the ShTS PCP". i 9.3 hE is responsible for preparing and maintaining the PCP current per h3 Procedu es 6.04 and E.01.

9.4 ' The Review of Operations Conmittee (ROC) is responsible for reviewing and approving any changes to this progran and the associated implementing procedures.

9.5 The Plant Manager's approval shall be obtained for every PCP revision.

9.6 ROC and Plant Manager approval signatures shall be indicated on the cover pege of the PCF.

9.7 PCP implementation is accomplished through station procedures and is the responsibility of the Radiological Controls and Operatione Divisions. ,

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Page 13-of .22 10.0 REFERLTES

~10.1 LIIfC OPEPATING PROCEDURES- 1 10.1.1 =SP 23.710.01, Icw Conductivity Liquid Radwaste 10.1.2 SP E3.710.02, Dewatering of Spent Radwaste Media 10.1.3 SP 23.711.01, High Conductivity Liquid Radwaste 10.1.4 SP 23.712.01, Regenerant Chmical ' Liquid Radwaste 10.1.5 SP 23.713.01,. Solid Radwaste System 10.1.6 SP 23.718.01, Liquid Radwaste Spent Resin 10.1.7 SP 23.719.01,- Liquid Radwaste Evaporator Bottens 10.1 8 DELETED 10.1.9 DELETED i 10.1.10 DL% '

1C.1.11 DELETII 10.1.12 SP R2.713.0f, Calculations of Radwaste Curie' Content 10.1.13 SP R2.713.24, Sampling, Treatment and Disposal of Radioactive Waste Oil 10.1.14 SP R2.714.30, Radwaste Container Control 10.1.15 SP R2.713.35, Storage of Packaged Radwaste Liners and DAW 10.1.16 SP R4.014.01,. Radwaste Sample Solidification Test 10.1.17 SP 72,002.16, Radwaste Sampling for Disposal 10.1.18 SP 76.030.30, Iab pH Meter Standardization and Use A

10.1.19 SP 73.033.30, Garra Spectrometer System Operation 10.1.20 SP R3.713.02, RA*0'AN.Ccnputer Program 30.1.21 SP Td 075.01, Corpaction of Contaminated Waste 10.1.22 SP R1.020.01, Liquid Radwaste Process Control 10.2 MOBILE SERVICES CONTPAC'IOR DOCUMC,75 10.2.1 STD-R-05-007, Topical Report, Cement Solidified Wastes to Meet the. Stability Requirements of 10CFR61, Westinghouse Hittma. Nuclear, Inc.

. Slurries 10.2.4 F458-P-002, Operating Procedure for Mobile Incontainer Solidification of Sodium Sulfate Slurries 10.2.5 F458-P-003, Process Control Program for Incontainer ,

Solidification of Bead Resin - Powered Resin Pix 10.2.6 F458-P-004, Dewatering Powdered Resin Slurries in Hittra-HN-100 Steel Liners with a Three Iayer Flexible Underdrain

, Astertly to less Tha .1/24 Drainable Liquid

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Page 14 of 22 10.2.7 F458-P-005, Dewatering Bead Pesins Mixed with Pcwered Resin

-in Hittman HN-100 Steel Liners with' a Three layer Flexible Underdrain Assembly to less Than 1/2% Drairable Liquid j 10.2.8 F458-PgG6, Dewatering Powdered Resin Slurries in Hittnan RADIE - 100 Container with a Three Layer Flexible Underdrain Assembly to less Than IS, Drainable Liquid 10.2.9 F458-P-007,Dewatg'ingBeadResinMixedwithPowderedResin in Hittrce PADILK - 100 Containers with a Three Layer Flexible Underdrain Assembly to less Than 1% Drairable-Liquid IC.2.10 F45E-P-002, Process Control Progra~ for Incontainer Solidificatic. of Powdered Fesin 10.2.11 F458-P-009, Process conta2 Program for the Incontainer Solidification of Radwaste Filter Cake. (50 weight percent powdered resin - 50 weight percent Diatcrnaceous Earth)  !

10.2;12 F458-P-010, Cperating Procedure for Mobile Incontainer Solidification of Mixed Bead Resin - Powdered Resin Slurry (Maximu- 2F weight percent powdered resin) i q

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~O IC.2.13 F45E-P-011, Operating Procedure for Mobile Incontainer Solidifict. tion cf Powdered Resin Slurry  ;

10.2.14 F458-P-012, Operating Procedure for Mobile Incontainer Solidification of 50% Powdered Resin /50% Diatcrnacious Earth  ;

Filter Sludge i 10.2.15 F458-P-014, Dewatering Filter Sludge Cakes in Hittman HN-100 Steel Liners with a Three Layer Flexible Underdrain Assembly to less Than 1/2% Drainable Liquid 10.3 GENERAL PEERENCES 10.3.1 NRC Standard Review Plan 11.4, " Solid Waste Management Systems" (NUREG-0800) 10.3.2 NRC Branch Technical Position HI'SB 11-3, " Design Guidance for Solid Waste L tagement Systems Installed in Light-Water-Cooled Nuclear Pcwer Reactor Plants", July 1981 10.3.3 Code of Federal Regulations, Title 10, Part 61, " Licensing j Requirements for Land Disposal for Radioactive Waste" l

10.3.4 Code of Federal Regulations, Title 49, " Transport 0tien" q

l l

4 L___ - _ - _ _ _ . J

Page 15 of 22 10.3.5: South Carolina Department of Health and Environmental Control, Radioactive Material Licena No. 097, as aneided.

10.2.6 hTC Special Nuclear Material License No. 12-13536-01, as-amended, for.Barnwell, SC ,

10.3?7 State of Washington Radioactive Materials License

  1. WN-IO19-2,,as amended, for Richland, Washington.

10.3.8 NRC Special Nuclear Material License No. 16-19204-01, as amended for Richland, Washington.

10.3.9 ANSI /ANS-55.1/1979, American National Standard for Solid Radioactive Waste Processing Systen, for Light Water Cooled Reactcr Plants.

10.3.10 AIF/IESP-027, Methodologies for Classification of Iow-level Radioactive Wastes fonn Nuclear Poaer Plants, Impe11 Corporation, January 1984.

~10.3.'11 IGC Low-Ievel Waste Licensing Branch, Final Waste Classification and Waste Fonr. Technical Position' Papers i May 11, 1983 )

(

1 10.3.12 RADEN-Data Base Analysis Report - Shoreha . Nucler.: Power Station - Waste Manege ~ent' Grcq, Inc. , August,19EE 10.3.13 @ Manual , App. E, " Packaging and Transport of Radioactive j Material". I l

6 I

Page 16 of 22 Appendix A Page 1 of 4 SOLIDIFICATION RECORD SHEET PART I Sampling and Pre-Solidification Analysis

1. Type of Waste ,
2. Vaste tank placed on recire.

Date/ Time

3. Waste Tank sampled analysis ID(/

Date/Itme

4. Waste Stream pH _
5. Oil Content Less than 1% (Visual Inspection) _

Initials

6. Isotopic Analysis Attached Check
7. Estimated Curie Code estimation 'i SP R2.713.06) Aci/cc h 8. Test Solidification Required Yes No
9. Acceptable Test Solidification performed (if rege red)

Initials

10. The above vaste tank has been analyzed and is aco ptable for solidification.

Radiochemistry ens ineer 1; ate or designee

Page 17 of 22 Appendix A Page 2 of 4 j SOLIDIFICATION REC 0FS SHEET j i

I PART II System Preparation and Processing (Use Part IIs. if vendor supplied system is used)

1. Container and (SP R2.753.30).

Type J Dfi

2. Container Properly Positioned Under Pill Pipe q Check j l
3. Till Plange Properly Meted to Container l Check
4. Sufficient Cement Available  :

Check .

1

5. Waste Dewatering Tank Level inches j Evap. Bottoms Tank Level inches l
6. Auth'orization to commence process I O ae te sePervi er o te
7. Time process started B. Time process stopped
9. Tachometer reading (Metering Pump) l
10. Waste Dewatering Tank Level inches ]
11. Evsp. Bottoms Tank Level inches ,

l

12. Process Completed Operator Date Time
13. Waste Class: A B C 14 Liner Check for free standing water Initials Date/ Time
15. Liner Capped Date Titne
16. Container Weight lbs.

. . . . . . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 9

i Page 18 of 22 I L

l i Appendix A.

Page 3 of I.

SOLIDIFICATION RECORD SHEET PART IIe Contractor System Preparation and Processing i

1. Container ID Number Type
2. Applicable connections made to liner for transferring waste and cement to liner Initials
3. Connections made to liner for mixing contents, if applicable Initials--
4. Process parameters Waste to be added to liner cf Cement to be added to liner cf Water to be added to liner cf

~

5. Authorization to com:r.ence processing 1

Radvaste Supervision' Date Time

6. Time processing started
7. Time processing stopped
8. Waste Class Class A Class B Class C
9. Container checked for free standing water Initials Time /Date
10. Liner capped Date Time
11. Liner Weight lbs.

Page 19 of 22 i

Appendix A l Page 4 of 4 i SOLIDIFICATION RECORD SHEET PART III Filled Liner Data

1. Filler Liner Radiation Levels .
a. Contact Dose Rate 1 Meter Dose Rate mR/hr mR/hr -

k

b. Smearable Activity 2 l

2 4 Quadrants 1 dpm/100cm/fI dpm/100 ce x9 (Use actual _dpm/100cm/f2 2

dpc/100emp number) 3 dpe/100 ce f3 dpm/100 cm3s 4 dpr./100 cm[/f 4 dpm/100 cm'.3

c. Liner decon performed Yes/No 2
d. Smearable activity after decon (if performed) dpm/100cm
e. . Liner ready for shipping or transfer to storage h Health Physics Supervision Date Tir7
2. Storage location Radwaste Supervision

\ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _- __

Page 20 of 22 Appendix B Page 1 of 2 DEWATERIt'G RECORD SHEET RADIOCHEMISTRY ANALYSIS SHEET

~

1. Type of Waste
2. ' Waste Tank (or Liner) Sampled Analysis ID#

Date/ Time

3. pH of Decant ,
4. Oil Content (Visual Inspection)

Verify Less than 1%

Initials (Radwaste Supervision)

5. Isotopic Analysis of filter media and or bead resin attached Check
6. The abeve waste tank / container has been sampled and found to contain the isotopes and properties as indicated on the attached data sheets.

O Radiochemistry Supervision Date

Page 21 of 22 l

Appendix B l Page 2 of 2  ;

DEVATERING RECORD SHEET POST DEWATERING SL'RVEY SHEET 1

1. Container and , l Type IDfi
2. Container Radiation Levels I
a. Contact Dose Rate mR/hr 1 Meter Dose Rate mR/hr
b. Smearable Activity 2 4 Quadrants I dpm/100 cm I dpm/100 cm p (Use actual 2 dpm/100 cm -

2 dpe/100 cm A nueber) 3 dpe/100 cm A'~ 3 dpm/100emp 4 dpc/100 cm f 4 dpm/100 cm z

c. Container Dese,on Performed Yes/No 2
d. Smearable activity after washdown/decon dep/100cm
c. Liner ready for shipping or transfer to storage Health Physics Supervision Date Time
3. Waste Class A B C Initials
4. Storage Location i

9 Radwaste Supervision l

l

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