ML20236B006

Rev 2 to Process Control Program Manual

ML20236B006
Person / Time
Site:	Hope Creek
Issue date:	10/31/1988
From:	Public Service Enterprise Group
To:
Shared Package
ML20236B001	List: ML20236A999 ML20236B003 ML20236B006
References
PROC-881031, NUDOCS 8903200276
Download: ML20236B006 (46)

Text

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f t 2 P'J isLI C SE RVI C4 EL ECTRI C & G AS ' CO MP ANY i

PROCESS . CONTROL PROG RAM HOPE CREEK GENERATItG STATION

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Revision'2 ~l October 1988 I

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SECTION TITLE -

PAGE(S)

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1.0 Purpose.....................................' 1 2.0' System Description.........'................. l 5

q 3.0 Waste Sources............................... 14-

-4.0 Process Control.............................' 19 l

5.0 Sampling....................................: 24 1

6.0 Waste Classification...................'.....- 25 l 7.0 Temporary Radwaste Processing (Contracted.

• Vendor)..................................... 25

]

8.0 Administrative Controls..................... 27' ..

8.1 Quality Assurance...................... 28 8.2 Training .............................. 29

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8.3 Doc ume n t a t ion Co n t ro l . . . . . . . . . . . . . . . . . . . 33 9.0 Revisions To The PCP........................

~

33 ATTACHMENTS

1. CIGURES l Figure 1,' Solid Radweste System Block; Diagram '

Figure 2, Radwaste Supply and Exhaust Ventilation Block Diagram Figure 3, Waste Processing, Sequence of Events 'l Figure 4, Operational Responsibility Chart k Figure 5, Vks Process Data Sheet l

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TABLE OF CONTEN'ST (Cont.) -

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Figure ~ 6, ASTM D-312-71, Type EIII Specific'at:l'on Requirements di Figure 7, Werner &)Pfleiderer Test Equipmentii l lill 'i j

Arrangement , H l

Figure 8, : General Arrangement, Temporary. o 1 Radwaste' Processing Facilities  ! .[  !

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2. APPENDICES L i i L  ! -f

, Appendix A )

- System Operating Procedure t

- Alarm Response Procedures l

- StationLAdministrative' Procedures

- Chemistry. Procedures ---

- Rad ~iation Protection Procedure

-1 Bypass System Operating Procedure 7

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Appendix B 'j DN / -

) - Process Control Nomographs o 4 Appendix C 1

- Attachments 19, 20, and 21 from RP-RW.22-004(O) ,

. Appendix D

- Waste Stream Composition 5

s Appendix E fi

- BTP Testing Methodology 11 Rev. 1

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l' 1 l- - . Waste Form Performance

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l- - 55 Gallon Product' Test Appendix H e,. , o

- Compressive Strength Test Data

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' Appendix I "

l l 81 . Irradiation / Test Data- ,

I Appendix :J - .. {

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- - Bartha Pramer Test Data ^-

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Appendix K-  !

" il . . ,. '- S-R' Analytical Laboratory Leachant. Analysis

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1.0 PURPOSE. -

I The purpose of - the Hope Creek Generating; Station' (HCGS) d

. Process Control' Program (PCP) isito describe the '

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, y envelope within which processing and packaging: of - l Low-Lovel radioactive waste is accomplished and .a:s such '  !

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provide: assurance of. complete solidification of various y -radioactive" wet wastes" -in accordance with the

.c applicable portions of NRC regulations and general

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industry guidance 'which includes the following

L documentus.  ?{

' 10CFR61 " Licensing Requirements-for Land Disposal'of- ,

> Radioactive, Waste" <

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10CFR20 " Standards for Protection Against Radiation" 4 H

- :10CFR71 " Packaging of Radioactive Material for- l'

' Transport -and Transportation of Radioactive Material under certain Conditions" a 49CFR, " Transportation" NUREG-0000;-Standard Review Plan Section 11.2,

" Liquid Waste Management System

- I NUREG-0800; Standard Review Plan Section 11.4, " Solid <

Waste Management System"

' Branch Technical Position (ETSB).11-3." Design '

' Guidance .for Solid Radioactive Waste Management Systems' Installed in Light Water Coeled Nuclear Power Reactor Plants"

' Branch Technical Position Papers pertaining to' Waste Classification and' Waste Form as transmitted to Commission Licensees in letter from Leo B.

c_ Higgonbotham, Chief Low-Level Waste. Licensing Branch dated May l'1, 1983. ,

Werner & Pfleiderer Volume Reduction System Technical Manual; 10855-M137A-463.

1 . .

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,  ! ;--- Merner & s Pfleiderer. Volume Red'uction System Topical - "

, IReport WPC-VRS-001; Revision'1, dated'May.1978 '

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. . 'I n<' 1-' iRegulatory GuideL 1.143 Rev./ 0,1 Design-Guidance for- JJ l Radioactive Waste Management System, Structures,Jand l Components; Installed /in Light-Water-Cooled Nuclear' 1 o Power Plants.. f p ' I 1

- : iProperties of Radioactive ~ Wastes and' Waste' '

1 1 1 _ Containers,aBNL-NUREG-50957,~ Nuclear Waste Management l

Research1 Group," Department of Nuclea'r Energy, L Brookhaven National Laboratory, Augustil979.- E NUREG ' 01231- " Standard . Radiological Ef fluent . .

j Technical Specifications for Rolling Water Reactors. il .-

i South LCarolina Department' of Health and. Environmental

.l Control, Radioactive Meterial License No. 097,. as '

amended..

NRC Special Nuclear' Material License No.; 12-13536-02,.

, as' amended, for Garnwell, SC.  :;

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State aof Washington Radioactive Materials License j #WN-I013-2, as amended, c for Richland, Washington.

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

- ANSI /ANS-55.1/1979,' American National Standard for t)

Solid Radioactive Waste Grocessing System for! Light L Water ~ Cooled Reactor Plants. - 15!

s

. Waste Chem Topi cal Report ent itled "10CFR61 Was te Form Conformance Program for Solidfied . Process Waste Produced By a Waste Chem Corporation Volume Reduction and' Solidification (VRS)' System" as transmitted ' to Mr. .Malcolm R. Knapp, Chief Low-Level .

' Waste.and Uranium Recovery Project Branch, Division of" Waste Management, NRC, in a letter dated May 30, )

1986.

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. S0pplement.11, "Biodegradat. ion Test 'Results; to the'

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Waste Chem: Topical Report ' entitled '"10CFR6 l' Waste . .

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,jyj F Form Conformance Prografa for Solidified kaste ,-

?fc' Producta. Produced lby.La Waste Chem CorpordtionjVolume' Reduction and' Solidification (VRS)ySystem"tas.L, .

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,H transmitted . to Mr. Malcolm. R. , Knapp, Chief Low-Levd ' " - . Wl c

LWaete.and Uranium Recovery Projects (Branch,; Division < W j; 4 'O ^

of Wast ( Management, NRC,.in asiletterldated; August 15,}

' L // .1986. 3

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,a The . results . described herein demonstrate 3 thh compliance ?

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, of the' generic 1 waste forms-- tested with the applicable 4 i i.1 ]a

.N I waste form criteria of 10CFR61. JThe; provisions 1of"'E .

10CFR61.56.(b)' require ' assurance,. that s '

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l  : the- was to "does not structurally degradeE through W sismping, ; collapse , or other failure 'of ' the '

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disposal unit -and; thereby 1. lead; to ' water . '

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'i'f11tration;

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the. waste . is ' in a recognizable and nondispersible ,

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/ f orm; to 111mit ' exposure to an inadvertent'-intruder c  ;

3 110CFR61 requires that these ovorall objectivesibe xmet by-providing-assurance thatt u

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( 1 )i the:lw'aste has structural stability:and wil'1

• m generally 'naintain- its phys ical' dimensions L and- form :

under ,the . expected ' distaosal condition,s r ..

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(2) liqisid was te, ior- liquid contained in waste,'in no l' j]

case exceeds 0.5% of~the volume'of! the ' was te J.

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-(3)- void , spaces ; within tho' waste and between the Iwaste '

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and 'its package are ' reduced : to the ' extent - ,

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. practicable. - c3, j

The' waste forms evaluated have been shown to mse't ' <

paragraph (1)' above by subjecting .them to all-'of the . l tests described in'the NRC's Technical Position on Waste j

Form. 1

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,l' Ai summary of these'M t es.ts and their L res'ults ~1s as follows ::

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. Recoutmended 4 W j i 0* Te fit Acceptance Criterion fTest-Results. j d g'- ' 1 Cornpressive; Strength - > 50 p.si at 10% >50. psi:at 10% '* -

, . deformation def ormation'. for: >

H a,t alltwaste forms =

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'%, Radiation Stability- > S0 psi at'10% >50 psi at'104 1

' i deformation af ter deformation 1 for '

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, 10% rad exposure 1 .all waste. forms.  !

, after 10%; rad i

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/# s Leach Resistance Leach fndex 6 Leach ind,ex 8 f for all waste

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' forms'for Co,  :

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.? . Sr, Cs-s 1

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,;, TImmersion ) .50 psi'at'10% '

>50 psi.at.10% ~*

H IIeformation after

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deformation for l

, 90-day water. all waste I immersion y forms, after 90

'_...# . day. water i A,

• immersion ' '

N f. except evaporator

. concentrated a neutralization'  !

waste.

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>50. psi at 10%'

Ther. mal stability > 50-psi.at'10% .

- deformation after .30 deformation thermal cycles after 30 j U '

' thermal cycles ,

, for all waste-forms

.Biodegrad.ation for Less than 10 weight Less than 5.49 all we,ste forms' in percent degradation- weight percent Hanford soil in 300 years degradation in s 300 years for

[. all waste forms

. Biodegradation for Less than JO weight Less than 4.57 ,

y, all waste forms in percent degradation weight pe rce n t 1 ', 'Barnwell soil in 300 years degradation in 300 years for all waste forms-O Page 4 of 34 Rev. 1

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i-P ragraph (2) of.10CFR61.56(b) regarding liquidfwaste has .

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. 'been met for all waste forms. tested.- There was noJfree liquid present in any of1thefsamples produced under this-program.

Paragraph-(3)-of;10CFR61.56(b) regarding void . space is met in severa1' manners. Hope Creek's waslte filling l- ~ stations are " turntable" style. Each' waste container can i

be rotated thru more than one ' time toiallow cooling of j

. partially filled containers. Additionally, the U

! temperature profile shown in- Paragraph- 4.4 can be adjusted (last bstrel) to prevent the " dishing" effect from occurring. . The experience .with the VRS System

, installations .in radioactive service, demonstrates that fill ef ficiencies arengreater than _85% for all wastes processed. This experience includes wastes. which have been tes ted under this qualification program as 1 well as , ' ,

additional generic waste types and the preoperational-system testing prior to release to Operations , here at ,

Hope Creek.

~'

In summary, all waste forms meet the requirements of 10CFR61,-for structural. stability, free liquids and void a space.-

(N In a'ddition, all' waste forms are in strict compliance

.\-

) with the recommended test criteria of the NRC's Technical

. Position on Waste Form, with the single exception of the immersion test results for evaporator concentrates- i' neutralization waste.. Since- this' waste form meets all other criteria, including leach resistance, it too is '! '

seen to satisfy the overa11' stability requirements of 10CFR61.

This PCP will also ensure that solidification will be

~

performed to maintain any potential radiation exposure to 3 plant pe rso.nnel' "as low as reasonably achievable" ( ALARA)  ?

in accordance with Hope Creek ALARA program procedures. 1

'2.0 SYSTEM DESCRIPTION The Solid ~ Waste Management System (SWMS) collects,  ;

reduces the volume of, solidifies, and packages wet .

and dry types of radioactive waste in preparation for shipment of fsite to a licensed burial site. The SWMS is l desig ned to operate on a batch process basis. A block diagram of the Hope Creek SWMS is presented as Figure 1.

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The, SWMS ; accepts '. dry solid trash, evaporator' bottoms from- '~

qE' i Lthe concentrated waste tanks, _and : powdered and bead resin.

and - filter m'e dia slurries from the. waste sludge phase  ;

separator, . clleanup phase separator, a nd the-spent resin.

1

-tank.- -j

,' The Eresin ~andi filter media slurries and concentrates are processed - for preliminary . volume ' reduction by removing; .

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4 the free water. Final volume reduction is accomplished in each of two (2) oxtruder-evaporators.- The initial

]

i volume reduction process varies for each waste type, .

e.g., a centrifuge for resin slurries, and a l crystal 11zer for evaporator concentrates.- These radioctive . waste products are further reduced in volume and mixed with asphalt in-the~ extruder-evaporators. ,

j Extruder-evaporator "A" receives dry cake discharge from )

the ' centrifuge or. slurry feed f rom the centrifuge feed .

~

J tank or. concentrates f rom the crys tallizer bottoms tank.. 3 Extruder-evaporator "B" receives, slurry feed from the '

centrifuge feed s tank, and concentrates from the crystallizer bottoms: tank. .

The extruder-evaporators mix the waste-streams with j

. asphalt at approximately 1 gpm in a range- of 325. to 350*F  !

e- (supply temperature). At this temperature, all remaining kg,Y). water is evaporated. The extruder-evaporators through- ,j their kneeding'and. mixing action also compact the. waste i and asphalt, producing a denser, product. The waste and- ,

asphalt mixture is deposited into a 55 gallon drum.

The solid radwaste monorail hoist places empty drums on the. turntables , which position the drums for filling under the extruder-evaporator discharge = ports.- The same monorail' hoist removes filled drums from the turntables.

The filled drums are placed on. a conveyor and guided to a capping-swipe station. At th is location, the drums.are ,

capped, swiped, and labeled. Radiation readings are also -

. taken. The drums are then conveyed to the truck bay i

/: where they are placed in the temporary storage area  !

loca ted in the north part of the auxiliary building by the storage area bridge crane. This facility provides for over 30 days of storage space, prior to shipment off-site.

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'V TThe radwaste area 1( Auxil'iary ' Building ) 'ventila tion .-*

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. systems f (Figure 2) A are arranged as :follows:

-~ L outside' air" supply to the balance of the radwaste'

- arcas Lin the Auxiliary' Ruilding, consisting of two . 1 .,1 "one-half capacity trains with low . ef ficiency land high ' 1 ef ficiency filters. j I

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1 .

. ventilation offall tanks in the radwaste! system.

N p This ' consists of two trains of low efficiency.. ,

1 profilters, HEPA-filters, charcoal absorbe rs , ' fire ,

protection nozzles, and high efficiency-after- -)- i

, . filters. >

. ventilation of the - ex trude r-evapora tor ' discharge . , .

consis ting of : one train - of . pre-filter, cha'rcoalD and '

HEPA filters Efor each.

' ventilation'of the'radwaste' trash compactor through.a

, HEPA: filter.- 4 The solid radwaste-areaEexhaust,' compactor exhaust and . 3 exhaust from' the . extruder-evaporators are . directed to the - j

' filter trains..dedicatec to this area. This train .

1

= consists ofl two one-half capacity , low ef ficiency and HEPA^

.E ~ . filters af ter1 which is then directed . to the north plant vent.

The tank exhaust -is directed to the . exhaust - filter trains-for the balance of radwaste. These consist.of;three one-third capacity units with' low ef ficiency and HEPA' j' filters. This flow is directedito the couth plant vent.

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- _s/ 2.1 Radioactive Waste Characteristics '

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In addition to fulfilling the'eight minimum. l requirements of .10CFR61.56(a), Class B and' Class C i waste must fulfill' the stability requirements of  ;

10CFR61.56(b). Stability 'of the waste ' form is- 1

ensured through a process of .encapsula tion.- i j

Encapsulation of waste entails surrounding' or containing the waste' in a ' solidification agent, in j this case an asphalt binder. A description'of the' ) '

was te solf.difica tion - method - used is presented in Section 2.0 of the PCP. , Process parameters are '

identified in Section 4.0 of the = PCP. Compliance  ; o with these operating process parametersiprovides j .f

' boundary conditions for processing;the waste and j reasonable assurance that the final waste form q

. meets . s tacili. ty requirements.

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The asphalt encapsulating media satisfies-the  !

stability guidelinee of Sections B and C of the DTP on Was te Form. Specifically, the final waste --

' form (waste and encapsulation media) is capable'of maintaining at least a .50 psi compressive strength' 1

.as demonstrated through actual generic. j prequalification testing of waste forms. .j

,-~ . .

I, ,J . 2.2 Prequalifica,, tion Testino 2.2.1 Wasto Forms to be Tested Waste Chem has' performed prequalification ,

testing on test specimens of the gnneric 1 '

waste forms in order to demons trate stability' compliance to the criteria of l Section B and C of the BTP on Wa,s t e Fo rm .  !

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-A[ Th'ej Waste Chem prequalification L tes t

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program 'is . designed to > produce and Ltes t Volume Reduction Sys tem l(VRS) . waste forms .

~j j .which simulate those' whichf are - produced ! at.

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commercial light water reactors.' ;While both the chemical : and radiochemical.

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composition'. of j liquid : radioact ivef wastes

,(and waste process: system,by products) . ,

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. varies from plant _ to plant. and from c times . to

- time - withinf a given plant,"thore ;is a '

sufficient similarity in the ' various L "

11

. process ' wastes produced by a-; given reactorf '

- type , /1. e , ' PWR : or BWR, to enable these

@"3 " L* ' "wastes . to be characterized by?a1 few *

- generic" waste chemistries. . ' This' l m '

similarity? was recognized ' by Broo'khaven :

Na tional Laboratory -- ( BNL) La nd was 'used as E a basis f ors t.he generic wasto compositio'ns -

~

i examined inDtheir NRC-sponsored report- [

"Propertiestof Radioactive Wastes and Waste

~

C Containers"1 .: The generic liquid waste . . .

types-of interest to. Waste Chem program are4 a-

-as follows:

Bead' Resins (BWR/PWR)

A -

Precoat Filter . Cake- with Powdered Resin -

3 ' ') ' (BWR) 1 17 -

Precoat Filter Cake with Diatomaceous Earth (BWR).

Evaporator Concentrates - Neutralization Waste: (BWR)

' Evaporator Concentrates.- Floor Drain Wastef(BWR)

Evaporator-Concentrates (PWR) 1 1

Decontamination. Waste'.(RWR/PWR) .

' Mixed Resin and Filter Cake-Waste (BWR) t

,T

. The specific waste . types of interest, i to Hope Creek 1are; i

'. Bead Resins i

~ Precoat Filter Cake with Powdered Resins Evaporator Conc'entrates - Neutralization Wastes

- Evaporatur Concentrates - Floor Drain Waste Decontaminate. ion Was te j'

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\_ / These waste types are virtually identical to those ~

q examined by BNL with' the' following exceptions: )

a) A generic waste stream not identified by l BNL' has been added.

~

This is an evaporator concentrates waste straam for 'BWR's which l process floor drain wastes by concentration i rathe.r than by l filtration and ion exchange.

Hope Creek's floof drain radwaste is filtered and subjected E to ion exchange.

However, this waste form was sponsored in ,

the event that plant configuration changes  !

are implemented to include this f acility.

b) A mixed ~ resin and fi.lter cake waste has been added for BWR's w:.ich do not segregate and solidify independently the various 1 precoat and ion exchange materials used in  !

liquid waste process system. This waste form contains diatomaceous earth which is --

not used at Hope Creek. This waste form  !

was therefore not sponsored.

l The actual composition of the foregoing waste 1

.gsg streams are described in Appendix D.

2.2.2 Conduct of Testino A. Scale of Testino/ Test Facility Simulated waste forms were prep'ared on an electrically heated 53mm extruder-evaporator. Although this extruder is a small scale version of the standard 1 120mm commercial radwaste extruder, it  !

.will produce waste products which'are equivalent in all respects to those 1 produced by a 120mm machine. [

1 Testing has been performed at Werner &  !

Pfleiderer Corporation's pilot test i facility in Ramsey, New Jorsey. The  ;

test equipment was set up in l accordance with Drawing No.- 940201-293 ,

and simulates the VRS process as it is 4 installed at commercial nuclear power plants. (Figure 7).

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B. Simulated- Waste Feeds '

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Waste' feed -streams simulating! the fies - ,

(5) Hope. Creek'related' liquid wasteL  :

)

types identified :in Section 2.2.1 were  !

. prepared and servedias feedstock'for

' production of Lwaste forms. . The actua11 compositions 1 of .these ' feed' streams 'is -

. identified:in' Appendix D.

The two (2) Evaporator. concentrates feed streams and . the Decontamination-waste-feed stream are fed : to ' the -

system . ( extrude r-evapora tor )1 as ' liqu id wastes. While 1 the - extrude r-evapora to r is capable . of. accepting the balance of

. waste feeds as eitherf slurried or

-dewatered material,:Wastechem

, processed these feeds . in a' dewatered state. Since the volume reduced-product from this process is a' --

dehydrated waste residuo dispersed in

-asphalt, the state of the feed material, whether slurried or dewatered, has no effect on the

-/ .

properties of the' product, i.e., the 1

=

~

products from both feed types are equivalent in all respects.

The Werner & Pfisideror pilot test

, f acili ty ' is . not licensed to handle radioactive materials,' therefore,: for leach test purposes, j the simulated waste feed streams were '" doped" with non-radioactive tracers; salts of-cesium, strontium, and cobal t. These are the pri.ncipal fission'and ,

activation products present in solidified process. wastes produced by

. light water reactors. A discussion of-the analytical technique to be used to detect tracers present 'in leachant solutions is contained in Appendix K.

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.C.- ' Asphalt Feed -

The asphalt to be used : for .this -

program is:an oxidized, petroleum q based asphalt' ' conf orming to - ASTM DJ l 312-71, TypeEIII: specifications. This

.is the. same - binder material used by all commercial VRS installations ~.

The: asphalt conformance requirements-are presented :in Figure 6.

D. Sample ' Prepara tion

.The .various asphalt encapsulated waste forms were' encased ;in cylindrical,,

thin-wall aluminum sample molds nominally two l inches in diameter byi: ,;

five and.one half inches long.- This type of mold has been used because it can be stripped f rom the waste -forms without the use of. lubricants-or . . .

. parting compoundsfwhich could interfere with ' leach rate ; testing. -

Test specim' ens of ' each . waste : type were

, produced at' multiple waste solid. I loadin'gs starting at'10%' waste' solids

]i ~ -

(and 90% asphalt). and increasing by

.,' 10% increments to a 40% waste solids-

' loading. Beyond-40%, the increment was 5%,to a. maximum achievable-loading. .The maximum achievable l loading is characterized by an '

increase in. product viscosity to the ,

point where the molten product becomes d grainy 1and is no longer fluid when i discharged ~ f rom the extruder. Where  ; '

necessary, . the cas t was te forms are -

cut to a length compatible with the tes t specimen geometries -( length to diameter ratio). {

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In addition to'the small scale waste I forms, a full size 55 gallon drum waste. form was generated from one-r '

generic waste feed stream. This waste 5

form has been produced from a bead resin' feed and has a nominal waste loading of 50%. This waste sample is made - for destructive examination as i

.a. discussed in ~ Item E of this section to I demonstrate that the properties of a j typical waste form are independent of size.

on.two different occassions, engineering personnel from Hope Creek.

witnessed the sample preparation.

i E. Analytical Test Duplicate specimens of small scale ,

~~

generic waste forms-(2 inch diameter) produced at or near the maximum waste-loading. have been' subjected to the y following tests prescribed by the BTP:- j

(i 1) Compressive Strength i

\,_,/ 2) Radiation Stability .

)

,N,' <

3) Biodegradation - Bartha-Prame r 1

4) Thermal Degradation y

5) Leach Resistance R

6) Immersion  !

7) Free Liquids I

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, \' ,/1 Test specimens produced at lower j Lloadings were held inJreserve in the' <

eventaa " highly loaded" sample does :I "u not Lperform satisf actorily. . Samples of pure , asphalt.were subjected'to.  ;

~

compressive-strength, radiation stability, thermal degradation and . i '

full range. of biodegradation tests :to :

establish waste form performance at the-lower. waste. loading limit,.i.e.,

pn ze ro pe rcent solids. - By testing samples at both the maximum and minimum waste loadings, the complete range'of loadings will be characterized (bracketed),-thereby.

eliminating the need ' to test products '

at intermediate loadings. A I

, , description of the BTP required y testing methodology employed c is L presented.in Appendix E. The results ,;

r '~

of the BTP ' required testing l pertaining to the five Hope Creek related - generic waste streams are presented. in j Appendix F. The 55 gallon product

)

sample has been examined for the i

^ presence of free standing water. Two l inch diameter core. samples of the 55 gallon drum have been extracted and +a

' have been' sub'jected to compressive strength testing to demonstrate' that waste . form properties are independent

, .of scale (2 inch diameter vs 55 gallon drum). The results of'these tests are presented in Appendix G.

3.0 WASTES SOURCES 3.1 Equipment Drains Filter and Demineralized I

This subsystem processes high purity waste from piping and equipment'containing high quality water in the Reactor Recirculation System, Condensate System, Feedwater System, low conductivity rinse water from regeneration, etc. The waste is processed through a filter, coated with a powdered resin product and a deep-bed domineralizer.  !

H/as:

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' \ /.' Af tsr' aybatch of processed water is . collected in f1 a : sample tank, -a sample is taken 'and- analyzed. :If:

it meetsswater> quality requirements, the water is -

transferred 1to the condensate' storage' tank. If

,. the batch does not. meet water. quality or j l radiological concentration specifications (10CFR20

-limits); fit is reprocessed. Water not' meeting condensate'stGrage ' quality will tm diluted and u

Lreleasedrin a controlled and monitored manner.into the station cooling . tower . blowdown line.

3.2: Floor Drains Filter &nd Domineralizer This . subsystem processes waste the 'same' as the: i

, equipmentLdrain subsystem, except that the waste  !

to be -[cocessed. is ' of ' lower purity. This waste-is 1 from floor drains, drains from.the fuel pool-cooling system and the'RHR system flush. .,

4 Af ter- a:. batch of ~ processed water is collected in a sample tank, 'a sampleJis taken - and analyzed. If it meets water quality requirements,. the water is --

transferred ' to the condensate storage; tank. :If thei batch does not meet water. quality or-

. radiological concentration s. specifications (10CFR20 limits), it . is reprocessed. .

I)!

water not meetingEcondensate storage. quality will be' diluted and released 'in a controlled and:

monitored manner into the station cooling' tower  !

'bl wdown line.

3.3 Decontamination solution Evaporator The Decontamination Solution Evaporator receiv'es

' laboratory waste, decontamination' solutions and sample. drain waste which is collected in the chemical waste tank. These wastes are neutralized a nd if' required, buf fered with sodium phosphate, th'an processed by the Decontamination Solution Evaporator. The, Decontamination Solution ,

Evaporator is designed to concentrate to a 10% by j weight solld. concentration. The bottoms are then discharged to the decontamination solution concentrates' waste tank. The bottoms are later discharged to the regenerative waste concentrates tanks for processing th ru a crystallizer evaporator.

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5 s E - 3. 4 Recenerant WasteLEvaporator ~

The Regenerant Waste-Evaporator receives regeneration solutions from the condensate deminera'lizer.and.radwaste domineralizer resin regeneration as well ~as inputs from the high :

conductivity sumps in the. Turbine and Auxiliary' l Buildings. These wastes are neutralized and. then.

'I

. processed by the regenerant waste evaporator.. 1

-ThefRegenerative Waste Evaporator is designed to concentrate wastes . te ~a 25% by weight. solid concentration of sodium sulfate. The bottoms

.are then discharged . to. the regenerative' waste concentrates tank, where it is processed thru-

a. crystallizer evaporator.

3.5 Detercent' waste

.The Detergent Waste Spstem. receives waste f rom.

laundry drains, personnel decontamination and.the --

chemistry laboratory. These wastes which are normally-low in radioactivity, are' processed by-filtration and then discharged .to the ' cooling tower blowdown line for dilution. If unsuitable

- r~%. for discharge (10CFR20 limits), the waste is (j. ~

processed through the decontamination solution 1

.i evapora tor.

3.6 Crystallizer Evaporator The Crystallizer Evaporator processes the sodium sulfate wasta in the waste evaporator concentrates tank. This waste is concentrated to a 50 % tar o weight concentration and is discharged to the 3 crystallizer bottoms tank. This tank is cne of i two of the final waste streams that are isolated, sampled and finally introduced for solidification into the asphalt extruder-evaporator.

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(_/I ~3.7. Spent Resin Storace Tank -

Exhausted resin' from the seven ccndensate deep-bed-demineralizers and the two radwaste demineralizers are. stored in this tank...once sufficient ~ resin.is in thectank it will be transferred to the centrifuge feed tank. This is the second of the

-two final waste streams that is isolated, sampled,-

and _ fina11yLintroduced for solidification into l.

asphalt extruder-evaporator'"A".

3.8 Waste Sludoe Phase Separator j

This , separator receives . exhausted powdered filter.

coating from the fuel ' pool and radwaste filters, along with crud discharged from the ult ~rasonic resin cleaner.-

The sludge', separated from the water, is transf erred ; to the ce'ntrifuge. feed tank.

3.9 -Cleanup Phase Separators

- These' separators receive exhausted and fouled l powdered resin from the Reactor Water Cleanup  !

L ,f System.- The sludge separated f rom the water 'is J ]j '_

transferred to the centrifuge feed tank.

3.10 Centrifuce Feed Tank and Centrifuge

- S pe nt resin, fouled and exhausted powdered resin and crud from the spent resin storage tank and i sludge separators are fed to this tank to be processed through the centrifuge. The feed tank recirculates the slurry to produce a homogeneous mixture. Once in a homogeneous form, a sample is taken to determine the pH and the solids concentration of-the slurry. The concentration measurement is used to set the metering pump flow rate for feeding to the centrifuge and on to the extruder-evaporator.

The centrifuge separates the carrier water f rom the resin / sludge phase separator. The remaining waste solids are discharged as a moist solid to extruder-evaporator "A" via a vertical chute. The .;

centrif uge can be bypassed, if inope rable , to feed  !

the extruder-evaporators directly.

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Extruder Evaporator A and B receive concentrates f rom the crystallizer bottoms tank and slurries from the centrifuge feed tank. Extruder Evaporator A is the only one to receive resin from the centrif uge.

The extruder-evaporators encapsulate a waste f stream with asphalt at a temperature range of '

approximately 325'F to 350*F (supply). At this temperature' the remaining water is evaporated resulting in a reduction in. volume. The end product drips in a 55-gallon drum, where cooling 1 and solidification occurs. The drums are then '

capped, swiped, labeled, and stored for shipment offsite.

3.12 Contaminated oils Contaminated oils will be collected and stored in ~~

55 gallon drums. With a large enough volume on hand to economically justify, a contracted vendor may be brought in for disposal in a suitable p_ manner.

N/ m Filtering of oil to return it to as received

s. properities is an Alternative. I 3.13 Filter Cartridges and Miscellaneous Items j

Filters and miscellaneous ' items will be handled on '

a case by case basis, and disposed of by methods acceptable to the burial site. This may include encapsulation of the articles within a 55 gallon

' drum with aspha'lt.

3.14 Trash Compactor Compactable low level trash will be processed and compacted in a hydraulic-operated box compactor.

A 100 ft3 metal container with anti-springback devices is used for storing and shipping. The box compactor is equipped with an external HEPA filtration system.

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b ,l g 4 ^. 0 PROCESS CONTROL .

j py !The process variables having a. directIbearing on the 'd

' properties'of the finalt product which' relate onlyi to .the 4

' ability 'to form a free _ standing . monolith with less .than

O.5% water bysvolumeiare described below. Additional-

< process variables sUch as pH, must be contro11ed ' to minimize; corrosion within.the system > however,isince "

these variables do not affect the ability of'the waste <

. product to form a ' monolithic solid upon cooling, they-

). -will not be discussed herein.

In accordance with the foregoing limitations, the following ' variables influence the properties and

,3 consistency of the final solid products

- Asphalt typer

- Waste chemical _. species being incorporated' into - the- 'l asphalt matrixt j '

- Ratio of waste-to-asphaltr,and

- Process temperature profile. ,

4.1

. Asphalt Type

. . i Hope Creek will use an oxidized petroleum-based  !

ff

?d'

)- asphalt, _ conforming to ASTM-D-312-71,. Type III requirements. This grade of asphalt has.a low

'l[

a. - residual volatile content, and a high molecular weight. At room : temperature and at all normal' l ambient conditions,- this material is a. free standing monolith. At Hope Creek, delivery of this asphalt will be sampled for product-conf o rmance .

4.2 Waste Chemical Species The type and-. relative quantity (waste-to-asphalt ratio) of waste chemicals being incorporated in the asphalt matrix has a direct influence on the properties of the final product. Encapsulation of inorganic salts and solids typically "stif fen" and harden . the waste. product s whereas organic j liquids' have the opposite ef fect. When the  ;

proper ratio of . waste-to-asphalt .i s ma intained ,-

final product properties relative to j solidification. are independent of the waste j '

type.

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. cA limit of 1 percent oil and organic contaminants -

. in. the . waste f eed stream is . imposed -for : process control. Mos t oils _ found !in 'a ; power i pla nt ' was te stream are low ' viscosity Lfluids,Lwhich-'are liquid 3# at room temperature. Based on) calculations- for L a .!

typical; waste' stream with 20 percent. solids by

' weight ' and> l percent oili the total' concentration' R of oil in the._end product:would'be approximately:

i g 2.5 pe rcent. ,This'would'lowerLthe end product o

sof tening point by Approximately 5' F; a -

negligible change.' ,

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'I' 4.3 Waste-to-Asphalt Ratio ~in the Product The rati'o of.was'te-to-asphalt contained in'the w end product has -theimost bearing en the viscosity P , ,

and physical consistency of ? that ! product during . ,  ;

processing.. The maximum ratio of waste-to-asphalt-

)

.for each. waste feed 'which has . been demonstrated to '

meet.10CFR61 stability requirements is as follows: q

' l Maximum Evaluated 4 j

' Ratio of Waste-to-Asphalt 1

Feed in the End Product (by Weight) d

/ Yi ~ 1.' Bead' Resin' 50/50 fL/3 e

. 2. Precoat Filter Cake W/ Powdered Resin 25/75

3. Evsporator Concentrates . 60/40-

- Neutralization Waste

- 4. . Evaporator Concentrates 45/S5 "

1

- Floor Drain

5. Decontamination Waste 30/70

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Optimum value depends on type and ' quan,tity of contaminants present. For resins, the presence I

of ' fibrous additives may also influence. product flow characteristics, and, the re f o rt:, waste l loadi ng s . Should the ratio of waste-to-asphalt be increased above the range specified in the-foregoing table,the end product viscosity will increase and may exhlbit a grainy texture. .This ,

could . lead ' to " pyramiding" of the product in the container, thereby decreasing the container.

filling efficiency. In all cases, the product will cool to: form a f freestanding monolir.h. If.

lower than specified waste loadings are realized,

. the end product preperties will approach, that of pure asphalt.

Prope r was te-to-asphalt ratios in the product are automatically maintained by a coordinated i

proportioning feed system to the extruder-evaporator. Operator involvement is limited to ..

setting the extruder-evaporator and . the initial

. proportion of.. waste-to . asphalt f l'ow . To do-this, he. must determine , by sampling, the solids ,

contents of the waste feed. With the sample  !

if~') analysis, he need _ only consult the nomographs j'

.(_/- shown in Appendix B for proper feed control settings.

4.4 Procesr Temperature A proper temperature profile along the length of the extruder-evaporator is required to provide i adequate evaporative (process) capacity, and to assure that free water is not discharged from the  ;

machine. Typical process temperature profiles for all Hope Creek waste types are as follows:

e i

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Jaky WASTE TYPE ' PROCESS TEMPERATU RE (

• F ).*

7' BARREL: =1 2- 3 4 5 6/7 8 ,

I BEAD RESI N. **85 200 280- 320- 350 300 190 I PRECOAT ' FILTER 85 200 280 320 350 300 190 j CAKE ' W/ POWDERED u l RESIN ,

..* 1 EVAPORATOR 85 200 280' 320 ~350 350 280 ,

CONCENTRATES  !

DECONTAMINATION 85 200 280 320 350 350 280 '

WASTE >

I MIXED RESIN AND 85 200 280 320 350 300 190 FILTER AND FILTER I CAKE-

• Temperatures lare approximate. Field setpoint  ;

changes may he required to optimize process.- These. --

4 changes can be made at the temperature indicating controllers.

, **This barrel temperature is not steam heated and as  ;

s r~'s such may flu'ctuate with subsequent barrel -

-(,,) temperature settings. 85* is shown to represent ~a

' typical ambients condition. i l ..

Low temperature alarms are provided to alert the operator to a. low temperature of f-spec. condition p which could potentially lead to the discharge of i

free water. These alarms are based on a percent deviation from set point, typically 1/2-l%.

The percent deviation permitted can be . adjusted in the field up to 10% of set peint. While' deviations i of 10% will not result in free water in the product, l this condition is the maximum deviation that should I be tolerated since f ailure to hold this range  !

indicates a problem with the equipment.

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> f _,I' :If ? an fof f-spec. condition ' persists . for: twos (2). ~

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minutes, the- extruder-evaporator _ and feed ' pumps. are i

' automatically. tripped to prevent : free - water f rom-being discharged !into?the 6ontainer. .' Free water cannot ;be discharged 11n the. interim, since the -

"* residual heat: of L the extruder-evaporator itself is sufficient 3 to effect' evaporation. . The foregoing controls / interlocks are provided to prevent the 4

-discharge:of f ree; water ; to the container. 'The temperature profiles specified above have been- <

proven by experiment. to yield residual total .

moisture content in theLproduct of 14 by weight'for ,

bead res ins. . This margin provides assurance that ;j '

free water cannot be discharge under normal' c i rcumG ta nce s . ' Under upser -- off-spec. conditions, discharge of"f ree water; is s.evented by the low ,

temperatures, process. interlocks. <

1 4.5 Minimum Functional Components In support of maintaining the! four major' process -- -i parameters;. l

' Process Temperature "

Asphalt Type  ;.

.. ;l t $, s. . -

Mixture-Ratio e: c' 01'l Content l

~!

and to assure a stable waste , form coneistent with-l the guidance of the PCP, operators ' will insure the. 1 following . list of equipment is,available,Las a e minimum, prior . to beginning processing.

C1csed circuit television system.at'the asphalt' loading stations.

All tempe.ratura profile monitoring instrumentation.

Th's asphalt and slurry metering equipment (pumps, valves, etc.). J 4

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Crystallizer bottoms anc centrif uge feec tank'

• recirculation and agitation equipment. j q

All sampling capabilities.

Batches will not be processed through the af fected-extruder-evaporator, when any of the above.

equipment is tagged out of service.. ,

, l 5.0 S AMPLING 1 i

From all the various sources of wastes, two final iso).able tanks receive input. The crystallizer bottoms tank and the centrifuge. feed tank are each recirculated- 3 and agitated to insure a homogeneous mixture. Once-isolated nothing further is added.

]

A sample of each batch is obtained in accordanci with epe rating procedures OP-SO-HC-004 and - OP-SO-HC-005. The.

samples are analyzed and the sample data form ( F!.g u re

5) is .comple ted . . Chemistry personnel will determine the ..

chemical and radionuclides content. of each seeple in accordance with the pro'cedures listed in Appendix A. ,.

Hope Creek is a licensed user of the " RAD MAN " computer sof tware of Waste Management Group, Inc. On a yearly q f g) basis the waste forms at Hope Creek will be analyzed and i

' (V ' characterized and included -in the RADMAN data base.

This assures the: accurate assessment of radionuclides present (chemistry-does not analyze for transuranic) in the daily sampled was teL streams. Inis software may be used to classify . waste for burial using the data base of Hope Creek's characterized waste streams. j The system operators, utilizing the da ta f o rm (Figure 5) ,

and the-nomoQraph (Appandix.B) select'appropt3 ate feed rates for introduction into the extrudar-evaporators.

The system will be operated until the entire batch is l processed.

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I Should. circumstances result in inter r~ uption of a batch, l the source tank will be isolated and remain so until processing can resume.

6.0 WASTE CLASSIFICATION ,

The eight. minimum waste characteristic requirements  !

identified in 10CFR61.56(a) shal1~be eatisfied. The Hope Creek PCP assures that wastes, determined .acceptacle  ;

i for naar surface disposal are properly classified for the purpose of segregation at the dispogal site.- Waste classification is performed consistent with .the guidance  ;

6 provided in the Branch Technical Position pertainingLto Waste Classification and is based upon the concentration  ;

of certain radionuclides in the waste form as given in 10CFR parts 61.55 and 61.56.

The methods utilized by Hope Creek, and the frequency i for determining the radi~ onuclide ' concentration of the i final waste form is conducted in accordance with Hope ,

Creek Procedures RP-RW-22-004 " Shipment of Radioactive .. l Materials * ' arid CN.TI .22-012 " Chemistry Sampling '

, Frequencies, specifications, and Surveillance . i Classification will be performed in accordence with these procedures, ,

9.0 I TEl1@RARY RADWASTE PItOCESSING (CONTRACTED VENDORI class A waste may be processed by an of f-sita vendor, ,

.provided a satisf actory technical review of processing I

. and Quality Assurance programs has been coppleted.

The technical review shall ensure compliance with applicable Regulatory requirements.

In the event Hope Creek requires the services of 4 contracted vendor to temporarily process and package radwaste on site, PSE6G will obtain the services of a vendor with an NRC approved topical report.  ;

An engineering review of the subject topical report will be performed to assure vendor operational requirements are compatible with Hope Creek systes opacations responsibility.

All dewatering or solidification processes will receive the same OA and station support coverage to assure 10CFR61 waste form requirements are wet.

In all caJes, safety will not be compromised and I assurance that ALARA concerns are addressed will be the primary goal for any temporary radwaste system interface.

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4 Y - l p). (j' < Perman'ent llanged' connections are provided on the south -

wall of the SWMS truck bay to enable processing lof l '

concentrates, filter media, waste sludge and/or resin slutries by a portatle dewatering / solidification i tystem. This provides maximum sys tem . flexibility and  ;

i i niinimizes radiation exposure in the event that key portions of the SWMS become unavailable for any reason.

-The following SWMS flanged connections are provideo in the truck bay: .

a. Concentrates feed j

b. Resin / sludge feed I c. Decant return

d. , Condensate supply  !

e. Service. air supply '

f. Vent filter connection i Space'f i s provided outside the truck bay (if required), l

( to the wes t)' f or the temporary control panel with an  ;

adjacent 480 Vac power supply connection. Check valves 7 ,\' are' supplied in all feed / supply lines.  ;

' (d ~

The area for the teaporary vendor's equipment is snown in Figure 8.

In addition to the service connections, shielding of the vendor liner or HIC, Station Health Physics coverage, communications and operations support are to be supplied as required. Station Procedure GP-TE-HC-001( R) governs the operation of the bypass system piping utilized to supply the waste streams and services. A s teel platf orm

-)

is available to protect the conveyor shown in Figure 8. 1 '

The tempora ry vendor's dewatering / solidification equipment can be located upon this platform to ensure sufficient floor area for the liner or HIC. Due to the lifting limit of the solid radwaste bridge crane (7.5 tons), various systems are used to move loaded waste I packages out of the truck bay. Hope Creek can utilize a rail and cart sys tem which can accommodate large was te 1 containers or a special short flat bed truck for smaller multiple containers.

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']. All_ vendor proceduros Will be reviewed by engineering:. ,

and approved by . SORC 'in .accordance with SA-AP.ZZ-001(O) .

A saf ety.. evaluation'.will be perf ormed to ' analyze the-- '

tl ef fects of. t.he vendors presence in the truck bay, ,

postulating spills and fire scenarios.

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Technical Specification 3.11.1.4 liinits will be  ;

o bs e rve d .

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, 8. 0 - ADMINISTRATIVE CONTROLS This section of' the . Hope Creek PCP describes ,

administrative' coritrols as they relate to ' quality assurance,, training, documentation, and record keeping i programs implemented by the PCP.

.. 1 Administrative controls are utilized to ensure that all processing is pc-formed 'in accordance with the guidelines. set 1 orth in' the Hope Creek. PCP. Public

< Service Electric and Gas is ultimately responsible for performing this function through the Hope. Creek 's Operational Ouality Assurance program. The i

c. . responsibility of the operational. Quality Assurance f '

program include the followings

./'N d

- -measures to assure contro.1 of activities af fecting the function of structures, systems and 'componeats planned monitoring and audit program to assure that specified requirements of the operational OA program j a re me t  :

coordinated and centralized quality assurance, s direction, control and documentation as required by -

the applicable portions of 10CFR50 Appendix B are

' complied with ,

{

management controls are established for the safe .

operation of Hope Croek l

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Page 27 of 34 Rev. 1 j l

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[8 1. .Oual'ity As s'urEncei '

'The administrative controls designedito prevent , d l

solidified waste forms f rom: being released for i shipment prior to test sample verification of acceptability require QA ' to verify; that a1 sample _

l- ' record sheet hae been properly executed for each j l wasta batch prior to processing.

'l q Figure 3 illustrates the sequence of: events in

~

O flow chart fobm, for the Hope' Creek solidification ,

lm i process. In addition, this figure presents'the applicable Hope Creek procedures. employed for each  ;

step of the solidification process. '

)

+

[k n Figure 4 is the Operational . Responsibility Chart j.

for all radwastes systems. )

Implementation of the Operational OA program is 1o assured by. ongoing review, monitoring and audit -

functions which fall under the direction of the . ..

General Manager - Nuclear Qua.lity Assurance, who -

reports to the Vice President - Nuclear.  !

The authority vested in the General ' ManagerJ- 1 l

Nuclear QA is as follows:

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independence to interpret quality _ requirements l i

7g -

identify quality- problems and trends l provide recommendations or solutions to Quality '

problems The General manager --Nuclear QA has the authority I to stop work when significant conditions adverse to quality require action. f

.l 1

1 Page 28 of 34 Rev. 1 I l

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' .(_/ j The: Nuclear'OA. program assures compliance with'the S;E waste'classificationLand characterization  !

'4 requirements of 10CPR61.55-'and 10CFR'61.56; .With respect to ! waste classification, this is achieved H by Nuclear - OA verifying proper adherence to  !

waste classification procedures and review' and -

t' verification of waste classification' data sheets.

3 A Nuclear - OA repr'esentative 'shall on a '

SP . '

surveillance basis, verify or observe , waste f classification procedure adherence for a minimum

, 1 single batch waste processing operation. -

n. With respect to was te chcracterizatier, the

~f

requirements of 10CPR 51.56 are ' intended to provide stab.ility of the waste., stabilit<y is -' '

y, intsnded t? : ensure that waste does not j i

structurally degrade and' affect overall, stability.. f of1the wastecdisposal' site. -The auditing functionL o* . the. Nuclear - Ok program assures stability requirements care achieved in accordance with 10CFR61. ' ' ~~

i In the event a ' vendor is contracted to pe rf orm temporary radwaste services, the Nuclear - OA

program, requires management review of th6 v.endor .

gg topical report. . The purpose cf this review is tp, i

j  ; assure that vendor operation and requirements are q l , compatible with responsibilities and operation ;f i Hope Creek. The contracted vendor shall comply with all OA described in this document. j 8.2 'Traininc A training program is being implemented for  !

personnel having responsibilities related to waste '

processing operations. The results of this '

training program shall ensure that waste processing is performed within ene specific requirements of the PCP. To accomplish this objective and to provide, the necessary control of the SWMS, the following general training programs 1

L will be implemented.

L I

Page 29 of 34 Rev. 1 s,

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'( ~. 8 . 2.1 - Initial Plant StaffITrainino' Program -

p A/ t r.

.These programs , are designed ' to : provide' ,  !

U,. competent,' trained personnel 'in all . I

., disciplines and-at all levels of plant! l organization. The programs are designed to allow ' personnel 1 to be placed at various- '3 points,.according to their training,- 1 experience and intended' position.

I

- Subsequent to class room instruction,

- each Radwaste Operator must'qualifyEon each piece of Radwaste Equipmentsby completion Lof 'a Qualif f. cation Card.' .g

- On-the-job training will. ensure that each' a SWHS operator. maintains an. acceptable i lcvel of skill:and familiarity. associated j with SWMG, controls and operational j procedures-. ,1

- The training procedures are ldetailvi in the Nucle'ar Department Training Manual.' j s This training includes ' familiarity .with the

< following SWMS coqponents: i f-6  !

1(,) '

' Liquid - Drains, Filters, Collection' Tanks j and'Sub-Systems  !

Solid - Extruder-Evaporators, Crystall'izer l cud Sub-Systeme l Radiation Protection personnel receive training commensurate with their ,

.l rssponsibtAities as Supervisor, Technician, j Technical Assistant or Worker. This j training is in the form of formal classroom lessons and on*the-job training culminating.

by completion of a Qualification Card.

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<,-~l h Lk,, , 8.2.2 Continuing Training' Program - A continuing E

p 4 training cprogram f or SWMS personnel, is  ;

P s, developed and . provides: continuous training i l11 and upgrading of . plant _ personnel. '

d WJ Continuing training 'inL specific areas is s ,

provided. to the -extent necessary,for i

personnel to saf ely; and of ficiently1 carry:

out' their assigned responsibilities in' accordance with established policies 'and procedures. . The continuing training 1

, program shall.run on an annual' basis with J all- program requirements completed during <f nu. i the two year training cycle. The.

continuing training program will consist of , o L tw9 areas; lectures which may consist of vendor presentations., technical training  ;

sessions, on-the-job work experience or j programmed instruction, and continuing i training examinations .,

'i) The continuin'g training program will' -.

cover fundamental review and j operational proficiency. ' Fundamental' review training will' be in system modifications , revision to procedures

. l and incidents encountered during p(>, g _ 4 operations. Operational proficiency

'/ training will involve lectures that will' focus on essential plant operational guidelines and changes or~

experiences in the nuclear industry. j 1

)(, (2) Continuing training examinations will be given tp determine the SWMS  ;

I operator's knowledge of the meterial .

covered,-areas'where additional training may be required and operational proficiency.- These  ;

examinations should-consist of

{

written examination and/or or&1 i examination. j i

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p-5-c Personr:el' are evaluated on an annual . "-[b g i ' J[ '

1 ' bas is whe re 'indivi dual ' n'eeds' f or. '

(

av 1 0 . retrainingiwill be . identified. _ _ ,;-

P, ' :y

Personn,el .fdemonstra ting a . significant :'

N deficiency in a : given area of knowledge -

s l iW 4 '

i  : and proficiency may ' be placed !into . a remedial training program. This 1

" m  ; program -is specifically > s tructured ; to . . , .

"., , upgrade knowledge and iskills identified ' N 4,

as. deficiencies.t. Successful ~ completion 'l of the accelerated training programpis .J y .

evaluated by.sa' written and/or. oral' examination.

7 ,

L The' combinatiori of formal training, ' '

{'

on-the-job, experience'.and SORC ,

approved garacedures. which ;. include o ccautions and corrective actions'should-i a malf unction or an .out of L bounc'.ary : >'

' condition occur,will give: assurance

s thatf.controlfparameters.within this'PCP us I are maintained. 3

. > g 1 8.2.3- Replacemen't traininc - These programs:are designed : to - provide. qualified personnel Jfor the. station organization;; The General:

, >- Manager - Hope. Creek . operations, or the : .

g

, - , designated . representative, may waive 'q-portions of the training program.for 1

, individuals. based on their previous

o experience and/or qualifications. . ]

The SWMS training records shall be a . maintained f or" audit; and ' inspection 1 purposes.- These records are considered ,

nonpermanent records.and shall' meet the applicable requirements of~ ANSI /ASME j'l N4 5.2.9-1979 " Requirements ~ for . Collection j S to rag e ,, and .Mainter,ance of Quality Adsurance' Records. for Nuclear Power

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Page 30 of 34 Rev. l' l 1

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L\_,/ . 8.3 Documentation Control and Record Retention-i Nuclear - OA program audits of waste classifi-cation records are performed on a periodic basis.

Management evaluation of such audits shall be performed and as such satisfy the requirements of.

10CFR20,311(d)(3).

Audits of the SWMS operating procedures shall be.

performed by .the Nuclear - QA organization at a I minimum of once per 24 months. Changes to operating procedures shall be reviewed on an as 'l required basis by Nuclear - QA in parallel with ]

the Hope Creek Station Operation Review Committee '

(SORC) in order. to ensure continued compliance with the requirements and established -process parameters of the PCP. These changes may be-promulgated as a result of proposed plant

' operations and betterment initiatives, system design changes, maintenance requirements, ALARA )

concerns or temporary vendor interface. -

l

.\

Hope Creek shall utilize the PSE&G Radioactive' l Shipment Record Form as presented in Attachment 19 and 20 to Procedure RP-RW.22-004(0)- for manif <2st  ;

3- preparation (Appendix C). The-information' )

t l contained in the form * . include s the required

\- 4 'information of 10CFR 20.311.

The tracking System for manifest preparat' ion shall be in accordance with Procedures RP-RW.22-004(0) " Shipment of Radioactive (

Materials" and RP-AP.22-Oll(O) " Records Management and RetentionProgram". The retention period for j these records is the life of the company. j J

9.0 REVISIONS TO THE PCP Public Service Electric & Gas Company proposed revisions .

to the. Hope Creek PCP will receive SORC approval. l These revisions may be initiated as a result of proposed )

plant operacions and betterment initiatives, system  :

design changes, maintenance requirements, ALARA conce rns or temporary vendor interface.  !

I l

r Page 33 of 34 Rev. 1 liQ) f'N 1

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$, Thel. PCP , if' revised, shall~be submitted to the NRC .

.'with the semi' annual': Radioactive Effluent Release

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-Report. ,

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FIGLME 1 HOPE CREEK SOLID RADWASTE BLOCK DIAGRAM d

SPENT - RES!N VE FROMICPS RES!N RACWASTE RESIN fl " "

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WASTE SLUDOE EXTRUDER - EVAPORATOR PWhSE SEPARATOR. " CENTh!FUGE A 3AMPLINO

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FROM: vARIOUS HICH a CENTRIFUGE' SOLIOS ORAINS WASTE PREC0ATS FEED TANK f .

/

CLEAN-UP IC00 LINO BACKWASH TANK =* --

ASPHALT RWCU WASTE STORAGE  :

PRECCAT TANK ELECTRIC B0!LER

. ,C' ' . (STEAM)

V DECONTAMINATION

. TO VEN00R SOLUTION EVAPORATOR  :

FROM: DETER 0ENT WASTE o LAS WASTE ,

DECON WASTE " "

l RECENERATE v EV P RATORS " " " "

FROM: CPS & RA0 WASTE EXTRUDER EVAPORATOR CEMINERALIZER 3 REG"NERATIONS CRYSTALLIZER BOTTOMS TANK t o CAPPER / SEAMER SWIPE STATION CONVEYOR i

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PC's TRASH ONSITE OFFSITE RA0 WASTE COMPACTOR STORACE ShRk j TRASH (OAW) er

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START I OP-SO.HC-001(R)-

OP-SO.HC-004(R)

CH-RC.ZZ-007(0) OP-SO.HC-004(R)

CH-CA.ZZ-021(0) - ISOLATE AND MIX. - OP-50.HC-005(R)

CH-CA.ZZ-020(0) SAMPLE' WASTE FORM. METH00S FOR DETERMINING l CH-C A.ZZ-018(0) CHEMICAL A00lTION FEED SYSTEM FLOW RATES i 1

CH-CA.ZZ-002(0) (WPC-VRS)

OP-SO.HC-002(R) ,

OP-SO.HC-003(R)'

PROCESS OP-SO.HC-004(R)

WASTE FORM- OP-SO.HC-005(R) '

OP-SO.HC-006(R)

OP-SO.HC-007(R)

CLASSIFY. L'ABEL AND STORE WASTE FORM 0.

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g4 4p,'ZZ-029(0)-

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MANIFEST - RP-ST.ZZ-001(0) 1 NOTIF T NS p p g RP-RW.ZZ-004(0)

I SHIP . RP-RW.ZZ-004(0)

WASTE FORM RP-ST.ZZ-601(0)

RP-RW.ZZ-004(0) CLOSE RP-AP.ZZ-111(0) NO WASTE FORMS YES RECEIVEO AT FILE ON [RP-RW.ZZ-004(0 SA-AP.ZZ-006(0) l INVESTIGATE WASTE RP- AP.ZZ-011(0) -

SA- AP.Z Z-035(0) OISPOSAL SITE FORM 0

RP-RW.ZZ-004(0) FILE ON' RP-RW.ZZ-000, RP-AP.ZZ-011(0) WASTE O,, _ FORM l

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FIGURE 4 3(myH .

i OPERATIONS RESPONSIBILITY CHART w OPERATIONS MANAGER v 1 ir ir .

RESPONSIBLE FOR:

SENIOR SHIFT ~ SENIOR - OVERALL IMPLEMENTATION OF SUPERVISOR . t OPERATING LIQUIO AND SOLIO RA0 WASTE SUPPOPT . MANAGEMENT PR00 RAM SUPERVISOR . CO-ORDINATE EFFORTS BETWEEN i SUPPORTING DEPARTMENTS

. - SUPERVISES' SHIFT SUPP. SUPV. -

(RA0 WASTE SUPV.) ,

. (BACK SHIFTS)

RESPONSIBLE FOR:

SHIFT - ASSU' RING COMPLIANCE OF DAILY-SUPPORT OPERATIONS TO THE OVERALL SUPERVISOR LIQUID AND SOLIO RA0 WASTE MANAGEMENT PROGRAM

- SUPERVISING EQUIPMENT OPERATORS RA0 WASTE i

- CO-ORDINATING DAY TO DAY EFFORTS BETWEEN DEPARTMENTS l ,,

l RESPONSIBLE FOR:

l EQUIPMENT - ALL DUTIES DESCRIBE 0 IN JOB OPERATOR SPEC INCLUDING:

RA0 WASTE - OPERATION OF LIQUID RA0 WASTE SYSTEM l

- OPERATION OF SOLIO RA0 WASTE SYSTEM

- ORUM HAN0 LING

- ASPHALT SYSTEM OPERATION

- AUX. 8 OILER OPERATION l

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MIN MAX

' SOFTENING POINT ( RING 'AND Bt.LL - METH00 ). 0EG. F 180 200 .

I 437 FLASH POINT- ( CLEVELAND OPEN CUP ). OEG. F ...

PENETRATING:

32 F (O C) 200g. 60s ,

77 F (25 C)100g. 5s 15 35 115. F (46 C) 50g. Su . 90 ~!

O QUCTILITY AT--77 F (25 C)(Sem/ min). em 3 ...

V. LOSS ON' HEATING AT 325 F (163 C) 50g. Sh. PERCENT ... 1 ]?

PENETRATION OF RESIOUE, PERCENT OF ORIGINAL 60 ...

-TOTAL BITUMEN (SOLUBLE IN CS,). PERCENT:

MINERAL STABILIZE 0 ASPHALT 65 ...

ASPHALT' WITHOUT MINERAL STABILIZER 99 ...

PORTION OF BITUMEN SOLUBLE IN CCl. PERCENT- 99.5 ...

ASH, PERCENT:

MINERAL STABILIZED ASPHALT 10 35 ASPHALT WITHOUT' MINEML . STABILIZER ...

1 j COARSE PARTICLES RETAINED ON 200-MESH  :

SIEVE AS PERCENTAGE OF MATTER INSOLUBLE IN ... 12 }

CS . PERCENT e

'THIS LIMIT APPLIES ONLY ON MINERAL-S TABILIZER OR NATIVE ASPHALT.

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