ML20237K151

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Rev 3 to Solid Radwaste Sys Process Control Program
ML20237K151
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/11/1987
From: Cotton J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20237K112 List:
References
PBAPS-PCP, NUDOCS 8709040218
Download: ML20237K151 (14)
v • d • e


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PEACH BOTTOM ATOMIC POWER STATION

.. UNITS 2 AND 3 -

. PHILADELPHIA ELECTRIC COMPANY ,

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l' l l SOLID RADWASTE SYSTEM l l.. -

i PROCESS CONTROL PROGRAM' '

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1-PBAPS-PCP Rev. 3 Page 2 of 13 TABLE OF CONTENTS

' SECTION ,,

PAGE 1.0. PURPOSE .f-

. '3

~.2.0.. SCOPE .- .3

. c 3.0. REFERENCES 3 -

' 4.0 DEFINITIONS

. 4 5.0 OPERATING ORGANIZATION 6 6.0 PROCESSING 7 . ;,

' ~

. er .

S' 6.1 WASTE TYPES. 4 7 ,

.. 6.2 PROCESY DESCRIPTION 7

~ ~J, ;, . 6.3', PROCESS CONTROL ' . 9 5.4 PRODUCT CONTROL 10 6.5 TRAINING 11 6.6 PROCEDURE CONTROL 11 1

~

7.0 RECORDS 12

,8.0 QUALITY" ASSURANCE 12 ,

i*

'19.0.~ REVISIONS - 12 l

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PBAPS-PCP Rev. 3 Page 3 of 13 1.0 PURPOSE To provide guidance and boundary conditions for preparation ~

s 'V _ of'. specific procedures for processing, sampling, analyzing, .

J' f packaging and shipping solid radioactive waste in

~ accordance with State and Federal regulatory. requirements. '  ?> .

s 2.0 SCOPE - ,

This program is applicable to the Pench Bottom Atomic' Power

. Station solid radwaste processing system. Wastes -

considered in this scope are filter / demineralized and bead resins, sludge, oil, and aqueous liquids. Not included in this scope is dry active waste processing.

3.0 REFERENCES

.i.

3.1 49 CFR Parts 170 through 178 3.2 10 CFR Parts 20, 50, 61 and 71

. 3.3 Standard Review Plan 11.4, Rev. 2; including. Branch T Technical Position ETSB 11-3, Rev. 2 6-3.4 LcW Level; Waste Licensing Branch; Technical Position con Radioactive Waste Classification, Rev. 0 (5/83) 3.5 tow Level Waste Licensing Branch; Technical Position on -

Waste Form, Rev. 0 (5/83).

3.6 General Criteria for High Integrity Containers (SC0 HEC) dated 10/22/80.

3.7 South Carolina Department of Health and Environmental Control Radioactive Material License No. 097, Amendment No. 41. (Barnwell Facility) 3.8 Barnwell Site Disposal' Criteria, (Chen. Huclear

- Systems Inc.) November 1982. -

T 3.9 iState of Washington Radioactive Mater.ials License- 4

' No.5WN-IO19-2, Amendment; No.17 -(Richland Site).

s >

3.10 Transportable Modular AZTECH Plant Licensing" Topical. - ',

NEDE-30878 January 1985.

1 3.11 NUPAC Dewatering' Topical Report, No. TP-02-P-A, Rev. 1.

3.12 Bartlett Nuclear Inc. Modified Portland Cement (MPC-1)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ _ _ - - - _ _ _ _ _ _ - - _ _ __ _ _ _ _ - __ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - -

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p. *c PSAPS-PCP Rev. 3 :i Page 4 of 13 '!

L and Portable' Mixing Station Solidification -

(Topical Report). l

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L * '

t. A 3.13 Station Radwaste Procedures (RW). ,

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! Y e. 3.14 Statiori Chemistry Procedures (CO) . T .

- 9 '

3.15 Station Surveillance. Test.Procedores (ST). # ~ 1.-

I .,

3.16 Station Rautine Test. Procedures (RT). V- 'd '% > - -

+C w ,3.17 Corpora ~te Quality Assurance Plan,s Volume III', '

5 - .- '.,'

Operational Phase (HP&C).

3.18 Station Audit Section. Instructions (ASI-01),

Subsection Radioactive Waste Material Instruction For Audits of Radioactive Waste Material Activity. l 3.19 Bird Instruction Manual (EIM-30-1-0), Solid Bowl Centrifuge, Document Number M1JJ-9-1. -

.s . . 3.20 Beatty, NV Burial Site Criteria (future). 'O' -

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1 -

4.,,, ,p 0 DEFINITIONS - ,

.4.1 Batch * '

,Y, An isolated quantity of feed waste to be processed -

+

. .t(' having essentially constant physical and chemical  ; 5 4 characteristics. For the purposes of resin type waste, .

a batch'is defined as one full volume of phase separator.

4.2 Operable A system, subsystem, train, component or device shall '

i be operable or have operability when it is capable of

, performins its specified function (s), and when all

,. ,,. ' necessary attendant ~ instrumentation, controls, r8

, y,s electrical power, cooling or 'searwater, lubrication or ' ~ '

'I other auxiliary equipment that are required for.the M. A d' system, subsystem, train, component, or device-to * -

di N< perfora its function (s) are also capable 'of; performing , ,- ,

their related, support function (s). '* -

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.4.3 Processing' 566

~

. '5.Schanging,' modifying, and/or packaging. the courericial 5' -

l

.,- nuclear power ~ plant generated wet radioactive waste '

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+ +

into a form that is acceptable to a disposal facility.

4.4 Quality Assurance / Quality Control

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I; E PBAPS-PCP Rev. 3

, 'Page 5 of 13 As used in this document, " quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a structure, system,

- ***u,..

. or component will perform. satisfactorily in service.

1. n Quality assurance includes quality controll which '

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. >' comprises those quality assurance actions related to .

the physical characteristics of a material, structure, ,:

l

't component, or system which provide a means to control /

Jtthe quality of the material, structure, component, or M

W system to predetermined requirements. .

4.5 Sampling Plan

) l A sampling program implemented to ensure that representative samples from the feed waste and the final waste form are obtained and tested for conformance with parameters stated in the PCP and waste form acceptance criteria.

4.6 Low-Level Radioactive Waste (LLWi .

Wrm

  • Those low-level radioactive wastes containing source.

special nuclear, or by-product material that are

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.. . acceptable.for disposal in a land disposal f acility.

For the purposes of this definition, low-level

' , radioactive waste has the same meaning as in the Low-Level Waste Policy Act, that is radioactive waste not

  • P' ' classified as high-level radioactive waste, transuranic -

, waste, spent nuclear fuel, or.by-product material as .

e. / defined in section.11e.(2) of.the Atomic Energy Act '

c(uranium or; thorium tailings:and waste).  %

% (4.'7 Waste Container - C 1

A vessel of any shape, size, and composition used to contain the final processed waste.

4.8 Waste Form Waste in a waste container acceptable for disposal at

t. -

a licensed disposal facility.

,4.9 Sludge . .e

, Contaminated liquid wnich may contain water, oil, and  ; P

, t ' suspended solids. .. i l

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. i PBAPS-PCP Rev. 3 Page 6 of 13 5.0 OPERATING ORGANIZATION The operating structure of the solid radwaste processing system is outlined in Section 13.2 of the FSAP. . . -

5.1 Responsibilities 2'  : .

5.1.1 The Corpor. ate Nuclear Operations Quality Assurance +.

Division 1s responsible for. establishment af a . 9

. '. Quality Assurance Program.- The Audit Section of -

.i d N 4 ."

^ this division performs audits to ensure comoliance * <- M

- i with the Quality.-Assurance Plan, Nuclear *

  • 's.

Operations and contracted personnel are responsible ,

.f for implementation of procedures and good practices so as to provide Quality Assurance.

5.1.2 In-house training is the responsibility of the 4- . Corporate Nuclear Training Section.

5.1.3 . Record keeping and document control of shipping and -

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iprocessing data are the:responsibi.11ty of the station Engineer-Radwaste. _ ,

5.1.4 Compliance with this PCP is'the responsibility of . i .

the station Engineer-Radwaste. .

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-v 5.1.5 The maintenance 'and verification of procedure .i>1

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. training to operate: appropriate radwaste systems-is . m i

the~ responsibility of the station Engineer- -

Radwaste. The Engineer-0perations is responsible +

. . for providing trained personnel to operate -

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v.; appropriate radwaste process equipment.

. 5.1.5' " Development"and-implementation of a training

, o program for personnel having. responsibilities related to waste processing operations to ensure that waste processing shall be performed within the requirements of this Process Control Program shall 1 be the responsibility of the station Engineer- {

- Radwaste. This training shall be updated

- s ' , periodically to ensure continued compliance. .

5.1.7 Huclear Operations and contracted personnel are z ~

responsible for' implementation of' procedures and n -

" .. good, practices so.as to maintain ALARA. -

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PBAPS-PCP Res. 3 l- Page 7 of 13 1 I

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6.0 PROCESSING L 6.1 Waste Types I

i ' ef>.'1.1 ~ Condensate F i l te r/ Demi ne ra l i zer :Was'te <F i

, . .a . The contaminated waste product generated by the e A l' . f , backwash of.the condensate, filter.demineralizers. *W b.' Waste consists'offcontaminated powdered ion ,- + 1. - -

i 2 exchange resins'at varying degrees of exhaustion, ^ -

.% N fibrous filter, media, and small concentrations of '

a various solids, activated and non-activated i corrosion products and fission products. ,

I l 6.1.2 Radwaste Demineralized Waste

.a . The contaminated waste product generated by the f

s t mbackwash of the liquid radwaste filters and demineralizers, collected in the waste sludge tank. .

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b. Waste consists of contaminated powdered' ion "

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exchange resins and bead resins at varying degrees-

- of exhaustion, fibrous filter media, carbon overlay l material along with small concentrations of various

{ solids, activation products, fission products, and .

i ae both contaminated and non-contaminated corrosion 7es products. .

W - 6.1. 3 Reactor, Water Cleanup' Filter / Demineralized Waste + -

L

,wi *n. (A contaminated waste product generated by the l

b Tbackwash'of the Reactor Water Cleanup filter @y~

demineralizers. '

b. Waste consistsvof contaminated powered ion exchange resins at varying degrees of exhaustion, fibrous filter media. and small concentrations of various solids, corrosion products, activation products, and f'ission products.

m

" 6. r. 4 'Dils/ Sludges-Wet' Radioactive Wastes i

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.0ils consist' of non-reclaimable contaminated oils - h.

. , m and grease.of various grades both synthetic and , 7' l

.4' - 's natural, in free form or containing various amounts o .

h - v. of-solid material. Sludge consists of sump wastes, .4

'+hfilterxsolids,strainersolidsandotherwetsolids.- '

? ,not handled by conventional dewatering techniques. .

4 6.2 PROCESS DESCRIPTION ,

a44 6.2.1 Condensate Filter Demineralized Waste

. ~, l PBAPS-PCP Rev. 3

'Page 8 of 13 a .- A condensate filter-demineralized backwash consists of approximately 9,000 gallons of slurry with an average of 350 lbs. (dry wt.) spent resins and crud.

b.* Backwashes are collected and" settled in a '

4 i : condensate phase separator. Clarified liquid is . ~ * '

t. c decanted until sufficient volume.of settied sludge'

. ,_is obtained for: processing. -

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Phase separator contents are mixed before - 4 14:

, ' c processing.

d. The solids slurry feed to a centrifuge for dewatering is controlled at approximately 20 GPM.

6.2.2 Radwaste Demineralized p' , .,

..AWA"backwashifrom a'.radwasteif titer consists of approximately 1,925 gallons of slurry, with an bn.c w "taveragemf 160 lbs. (dry wt.)*. spent : resins tand crud. , g

. n ., u ,_ Filters may contain charcoal overlay for oil ' ".

i removal.

T, , b. A backwash from the radwaste deep bed dem.ineralizer ,

consists..of approximately 1,'500 gallons of slurry,~ . . 1 with.an< average of 3,200. lbs.< (dry wt.) spent l : . m. .Q .* : . - . .

resins.

n le, c.. Backwashes from radwaste filter demineralizers.

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'a .- .

. radwaste deep bed demineralizers, and fuel pool -

+'

F. - *,. <b filter-demineralizers are collected in the Waste .' % '

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" Sludge iTank until approx.imately13,500 gallons of '"*

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  • liquid'is accumulated.

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  • ~ ' -" d. Waste Sludge Tank contents are mixed before processing.

During normal operation the waste sludge tank

, 2 ., contains only the radwaste and fuel pool filter

, demineralized backwashes. . -

. e. The solids slurry feed to'n centrifuge.for

. dewatering is controlled at approximately 20 GPM D

~

for Jewatering. '

n'-

i L .f. s%ste sludge tank. contents.ciay also be sent :to a .4' H c -

. condensate phase separator for. processing .in ~ ' 6 '-

accordance with' Section 6.2.1.

1

p.  :

PBAPS-PCP Rev. 3 Page 9 of 13 I 6.2.3 Reactor Water Cleanup Waste L

a. A RWCU filter-demineralized backwash consists of

'S approximately 1,100 gallons of slurry with an v .

average of 35 lb. (dry wt.) spent' resins. < w.2 L .b. 'Back' washes are collected and' settled in a phase M separator. Clarified liquid is decanted until u . a sufficientavolume<of_ settled. sludge is obtained for V '

.. F l processing.

l i.

. c.. Phase-separator' contents are mixed.before .

processing.

d. The solids slurry feed to the centrifuge for dewatering is controlled at approximately 20 GPH.

l , a s.t..u 6.2.4 # Jils/ Sludges L a. Sludges and oils generated during operation and b w. nnaintenance are collected in containers in h appropriate approved areas throughout the' plant. ' '

~

2. The filled and labeled containers are sealed and -

, 7 moved to available areas for temporary storage, i

) 5. 6.2.5 Miscellaneous Waste ,

1-

i. # c i .. a. Certain wet wastes may be . allowed to dry and be -

7 .- treated as ~ dry active waste. '

~ 6.3 ' PROCESS CONTROL s. . t ..

, A. Resin O. 6J3.1 ; Resin processing (dewatering) performed via centrifuge is accomplished by delivering resin from a phase separator or waste sludge tank. See figure 1 for details.

6.3.2 The slurries discussed in Sections 6.2.1 to 6.2.3 shall be fed to a centrifuge at about.20 GPM.

6.3.3 . Proper centrifuge operation shall: be observed. A System operability shall be demonstrated by -

successful processing of waste' for disposal. - .

' Abnormal'. observations shall be documented. .

20344~ The design ofliigh Integrity Containers which are v'# ,

used to package dewatered resin are accepted by the

~, state of South Carolina. Applicable station procedures describe techniques for verifying that less than 1% of the volume in the HIC is free standing liquid when shipped.

P..

L.

L- PBAPS-PCP Rev. 3  ;

Page 10 of 13 c 6.3.5 Vendor supplied radwaste systems used for j processing resin type waste shall be operated in i accordance with the vendor. Process Control Program

. .. . +

(PCP). General Electric Modular Aztech and NUPAC ,

V# . u Dewatering Systems are planned. . .

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BF-Oils / Sludges q

A ,6.3.6. . Solidification,ofsoily,wastetissaccomplished in ,a m l L. > '+ .

accordance with station' radwaste procedures and the; af-

'.# ' ' Bartlett Nuclear Inc. solidification process '

  • 0 .

eN ~. procedure.and Process Control Program. -- 2 * * '

l 6.4 PRODUCT CONTROL

! 6.4.1 A sample from each batch is analyzed quantitatively for activity and isotopic identity. If

, w -radionuclides distributions are shown to be  ;

i i W : reasonably consistent between<.similar batches, I" consideration may be given to decreasing the b e frequency of routine measurements. This constitutes routine sampling.

, *L 7M6 6.4.2 Scaling factors for nuclides which are hard to N -

identify are established for waste by analysis -

} c~b through an off-site vendor. Frequency of sampling  ;

is normally on an annual basis. This frequency '

7 should be raised or lowered based upon '

'< '- ' consideration of, waste' stream or radionuclides ' -

i '

characteristics. Factors which would influence '.. ,

e this consideration include the frequency of process W d i

+ -vessel change out or waste shipment, the difficulty * *

, ~,:

?(e.g..,30sts.- occupational; exposures) .in obtaining 9

'A ma representat.ive sample.of.a particular waste stream, the variability of the radionuclides distribution within the waste stream over time, and the availability of analytical capability for  ;

particular radionuclides. '

t l'

If radionuclides distributions are shown to be 1  ; reasonably consistent between similcr batches, s ':' consideration may be given to decreasing the -

. frequency of routine measurements.

)

6.4.3 7 Radionuclides concentrations'and classification of . ,.

' - future waste shipments are expected to be similar  :- -4."

% to those of previous shipments for each specific - . f; S W, waste stream. Values are available from. shipment "

4 manifest forms.

6.'4.4 ~ Administrative Controls for preventing

  • unsatisf actory waste forms from being released for 4 shipment are described in. applicable station l

procedures.

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i PBAPS-PCP Rev. 3 Page 11 of 13 )

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L s 6.4.5 Solidified or absorbed radioactive wastes shall have no detectable free standing liquids. No detectible free standing liquid shall be defined as j not more than 0.5% or one gallon per container, 4 whichever is less. This is verified using ..

.,(.g

~ appropriate station procedures.

Processed resin shall be sampled in accordance with.

6.4.6

. regulatorysguidance and applicable station' . 7 T. c' - .

s r

procedures to verify that~ the free liquitiit:ostent, 2

f. - 2 q. . .

of the, packaged product is within limits

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established by applicable regulatory agencies.s c 4 :, ,s ,,".

, u Sampling and measurement of free liquid content r

shall be' performed whenever process changes occur that may significantly alter system performance, i.' until compliance with moisture content limits under these conditions can be demonstrated.

I Each waste shipment shall be accompanied by a 6.4.8 f shipping manifest giving a physica1' description of ,s , , ,.;

y

' ' the waste, the volume,.the radionuclides identity ,

9 and quantity, the total radioactivity, the .

~

~

principal chemical form and waste' class, based one.

" 10CFR61. 55.-

4 '

", 6,4.9 Radwaste Solidification Systems which provide -

k' stabilization'shall be operated within parameters

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e. ')^" ident.ified in prequalified testing to ensure

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y acceptable waste form. _

  • 6.5' ' _ Training 9

a 6.5.1 Processing of solid radioactive waste shall be lj performed by qualified and trained operating .

3 4 personnel; Records of training shall be maintained , ,;f for operators of mobile vendor processing units.

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$ 6.6 Procedure Control 6.6.1 On-sfte ' processing of radioactive waste shall be '

M; performed in accordance with approved station  %,.9 g; 4' p  ; ,. a.;,

procedures. 4 h,  %

M cy4 i ..M5.6'2[iProcessing of radioactive waste by off-site vendors

,, > 'S- : shall be perfomed in accordance with applicable ,

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Process Contror Programs, procedures ..and e S

A'" g@.

% . applicable NRC guidance.

W 6.6.3 Procedures'for processing, containerization, and

[d3

  • transport of wastes shall ensure that specific DDT, .o

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10-CFR and burial site requirements are satisfied.

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7.0 RECdRDS, u j t + 7.1Wasteclassificationrecords,4asteformrecords,and j

  • other records required for Che preparation of the i, semiannuah Radioactive Effluent Release Report shall be

( . # 0 s. N ~1 prepared aitd rstained in accordance with the .-

O x v*<

M

" requirements or't0CfR20, 11CFR71, 49CFR170-178, and Pr.nch Bottom Tedhnical.. Spec?fications. *.

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[ , 4 .c - 7.2 Recordtof proccsting data, test and analysis results,- u _' ~t '

1 v. and rn M ts.cf training,/ inspection, and. audits are n. w ,

L~ -

g retained in acccrdani:e 41t' the Corporate Quality -

q ,g:+ Assurance Plan'and applicabla Station Quality Assurance S't

-J 1 'l

( and Administrative procedures.

L .( 5 j- 7.3Sufficientdocumentatdnsna11bemaintainedto lg, c dem nstrate compliance >of dolid radwaste processing g 4, - , with this Pr3 cess Cost,rc1 Program, i

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8.0 ' QUALITY ASSURANCE y i 8.1 Quality' Assurance shall be maintained as defined by the l' 'l Staiion Quality Assurance Plan, Volume III, Operational

" Phass, (lip &C) . The QA Plan shall ensure compliance with i

A t1RC and.bdrial site criteria for waste classification , ,

1 .and wate ford. Audits. are conducted in accordance ,

[v a 'with stetion Audit Section instructions (ASI)-01), .

1 i subsection Radioactive iW te Material Activity '

h:tnuction far Audits of 4tadicactive. Waste Material T- .x:2 2 l . N Activity. j 3

l g' i 8.2 The Topical Reports of vendor supplied radwaste l

. processing systems shall undergo management review.

3 8.3 Audits of a sandling of implementing procedures shall

{s . be performed at least once every 24 months. Any change; to procedures shall be reviewed to ensure

'i(- contir/uaF compliance with the requirements and process

. parameters of this Process Control Program.

b^> -

- Radioactive wastes not described within this document '1

@ 31 , a or wastes that do not fall withiw previous; waste -

R n , xprocessing experience mustnbe evaluated and approved 7

@if Toriinclusion in',this. Process Control Program prior to g%

C i- processing, j

i l . 9.0 ' REV:SIMS p 's . '

l 9.1 Any changas to tiel Solid Radwaste Process Control

~s Progrim shall be approved b.y the Plant Operations l Review Committee (PORC) and submitted to the Corporate s

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PBAPS-PCP Rev. 3 Page 13 of.13 L Engineer-In-Charge of Licensing for input to the Semi-p Annual Radioactive Effluent Release Report.

I:

'1 ,". .

. C ...S.2 PORC approval shall be indicated by the signature of 4; l'  : ethe PORC Chairman or designated alternate. This 2-l ,

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'd ; signature shall be in the upper right hand corner of k ? "

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the document along with the meeting number at Wch the V

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program was approved. > " _

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