ML20082M273
| ML20082M273 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/10/1987 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20082M216 | List: |
| References | |
| RW-1-210, NUDOCS 9109050116 | |
| Download: ML20082M273 (33) | |
Text
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Pott SECT 103 E2Y1510N 2 i
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-A 3 ADMINISTRATIVE PROCEDURE 3 N g PROCESS CONTROL PROGRAM
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M C Chaicuas LATE Approved Flaat nanageb iuclear W- / 7"MbDATE W
- c. Effecstve Date
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WT 1-002 Revision 10 , ,.
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REVIEU COVEA SEET RIVIEV OT: RW-1-210 - (Change 1) Process Control Program (Rev. 2)
PORC RIVIEW The PORC has retteved this ites and deterstaed that a safety reslaatton vse performed (as spplicable), that an uarevirvvd anfety questioc does act e:Ist (se applicable), that a change to the Technical Specifications is not required, and that outlest safety)a7was not adversely affecte6. l OITER RICtZtfLEDC)
OT PORC HDfBER PORC MDO.IR FOR APPROVAL DATI KEVIEW SIGAATURE - g g Maintenance - .
N Mr. hl};ff) l Wan -
N Operations \
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Radiation Protection ,
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Superistendent 1 lf) [Q g "
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Nuclear Operattons ; Iy /
N Support and Assessnest ,5
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(g g Manager (Quality Review) 7 h /
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g, , Plant Engir.eering " -), N j Superintendant %vp [/ p d y j,g i O Assistant Plast Manager PORC Choismas b(l[$a ,, . r ,., V f e .* f f_)
PORC Heating Wo. M MI tem # cN Date: M.2N'M This itaa to recommeaded f or approval? TIS o 15 0..
This stes requires $1C/XRC review prior to implementattoof C TIS If yes, ensure documentation supporttag review is attached.
fpo This ites requires QA review prior to Fn N sppterst? O TES [po ;
PhAirT MANAGE 1 ItUCT. EAR APPROVAL (RIIIR TO 5.4.12.1) i Cosaments : / N 1
Approved by M-(( Adm.. Date /C -/.-8 2 Plant Manager-muclear !
UNT-1 004 Revision 7 Attactament 6.1 (1 of 1) 18
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WATERTORD 3 SES Check Block Below PLANT OPERATING fiA3 RIAL CHANGE /REVISICN/DEIITION REQQL3T ($Poti ([lPORC-S/C poc,% do gho{ ppy, p, y Procedure No, M -1. 2to ytt},
I (if dif ferent f roa spproval date)
Effective Date Cosolete A. B,_ aod C Espirstloo Date u/A A. Change No. I @lPersaneut 1[lDevastion Revision No. 7-B.
C. Deletica l[lTES ffjNO DESCRIPTION OF CHANGE OR REVISION
\c 14 a ufh: k wasd adb h tfe-w t weiut kt- ih A du.dic 0 r kd ie 3. c s . Ad[el \! t o tu ft 9rD ( ed u rr _ ndb keIe_rew ed O m N ha Aun- 'n BcAu d b e h re.
i FJ.ASON FOR CRANGE, REVid!ON, OR DEIITION (1 se n k b2 uns cT RQ kra $ rd vw e du s (S _r it3 k r D e.
[5 C- sit d i N icrdm3 REQUIRED SIGNATi$f( DATE /d 13 N nh-co J ~ I '
ORIGINATO ~
p SATETT/COttilitENT RIVIEV Does this change, revision, or delettun:
O 1. Change the design, description. function and/or operation of a system structure or coeponent described
! TIS N0 1 i in the TSAR 7 NO )(.
TIS
- 2. hange the procedures as described in the FSART No X
~; TI3_
Conduct tests /expertsents not described in the FSARf 3
Require a change to the Technical Spectiteetionst YE5 _ N0 1 j w.
Alter the Laplementation of any comattaents?
YT5 NO [
5 f complete and attaca a If the answer to any of the above is Ye f
10CTR50.59 Safety Evalu on, g t o } t 3 kK ~/
anAc,sn ( im DATE S ATETY/ Co*titITMT.NT WI
_DATE M/M/b7 TICHNICAL REVIEW hMNd M/(M2tO DATI N/A1// 7
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l CROUP HEAD REVIEW [OtMM 2 h fT DATE TEMPORARY APPROVAE* (SRO) DATE TEMPORARY APPROVAL *
- Ten:porary approval must be followed by Plant Manager / Aptt-N - Nuclear ap 14 days.
Attachment 6.7 (1 of 1) 5 UNT-1-003 Reviston 10 30 f,
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$5 M EW cts Vi FMC ffTITV I gn l i 9a7 na tuRC has rerteved this itse sad deterziavd that a se(fty erslaattes vos l l
Wl ,vesere.d (u epplicale), tast en rarevuved ufear vest.w een set utet (ce opplittele), IAst a casaca to tt.s fetts4 sal Desifis441 sed to set fM i required, 464 that sus tear sa f ety J<f t** est swwwssaly safested. I
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. . 2 WATERTORD 3 SIS PLANT OPERATING MANUAL Check Block Selow CRANGI/ REVISION / DELETION REQUEST @POM l'_lPORC S/C Procedure No._fgtM LlO Title froem (bleat . Pwn m A/A (if dif ferent f ree a,m revel data)
Effective Data Complete A. B. and C l[IDeviation T.1,..s.lon Date A. Change No. NA l[lPermanent
- 8. Revision No." 7 C. Deletion l',l TIS ((lNO DESCRIPTION OF CRANCE OR RIVIS10R Ch?!A r iMM .4 &?nk NJP h4 ditad AiWMw w a i:
1 9 in N RIASOT FOR CRANGE, REVIS10W y 00 DEIITION
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(Nikh t Mlrhnt$ 1107?f flin ifX!n b fi n _ 1MtD b a,revhsyh it-:n n A <t{ q REQUIRED SICKi.TURES ORIGINATOR fg d _ hfM MU Y >h7 ei SAIITT/COMMITttINT EVITW Does this chatige, revision, or delt: tion: m Change tt.= desig escriptico, f unction and/or operetton J . r a structure or casponent described i in the TSAR 7 YES N0 1 TES NO \/ 2 Change the procenutes as described in the TSAR?
! 3 Conduct tests /erpertser.ta out described to tLs TSAR? TIS Mo d
- 4. Requtre a change to the Techotcal Spectftcatiot..? TES N0 1 TES NO N
- 5. Alter the implea ntation of any comettaentet j
If the answer to any of the above is Yes, complete and attach a 10CTR50.59 Safety Evaluation, SATETY/CorfilTMDiT RIVIEW h11)M $ / O/Md DATE 27!N TICENICAL n. IEW / _g [ DATE #///f 3 M urNf b [,, U T L DATE /,/[/F 7 GROUP KEAD REVIEW TE.TORARY APPROVAL * (SRO) [ DATE
.DATE TEMPORARY APPROVAL *
- Temporary approval must be followed by Plant Manager /APM-H - Nuclear approval within 14 days.
l Attachment 6.7 (1 of 1) , j UNT-1-003 Revision 10 30 WPaFmgigtaifRp5
F 1 210 Adetnist e o Procebre ' Farision 2 Procsss Control Progras TAILE OF CairIIETS 1.0 FURPost 2.0 RITERD CES 3.0 DU IRITIONS 4.0 RISPON81BILITIES
.c 5.0 PROCIDUEZ N 5.1 Psogres Description
" 5.2 Solidification Process Parumeters
-- 5.3 Administrative controls 5.4 Wast 4 Chatectorization and Classification 5.5 Qaslity Assurance 3
N 6.0 ATTACL M ::
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M C : ' I O LIST CT IJTECTIVE FAC15 Title Eerision 2 1-11 Revistos 2 c,4y 8,H,Y ?lh i i
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k"J 210 Administrative Procedure Process Control Progras kevision 2 8 1.0 FURPOSE 1.1 The purpost- of Vaterford Steam Electric Station - Unit Number 3 (Vaterford 9' F'scess Ccatrol Program (PCP) is to describe the program wh d provides reasonable assurance of the cceplete solidift-attou of various radioactive " vet vastes" including resin slurries and evaporator bottoms are accordance with applitable Department of Transportation (DOT), Nuclear Regulatory Coossission (NRC), State and 1/. censed burial facilities acceptance crateria for pach ging and i N shipment to en approved burial site. Compliance with these criteria N will be achieved through implementation of the PCP and related Vaterford 3 and vendor supplied procedures. (
2.0 REFERENCES
N 2.1 Vaterford 3 Documents
! N N 2.1.1 Technical Specifiution 3/4 11.1 M
2.1.2 Technical Specification 6.13.2 2.1.3 FSAR Chapter 11.4. Solid kaste Management System i U- 2.1.4 FSAR Chapter 13.4, Revtew and Audat
- i 2.1.5 FSAR Chapter 13.2. Training JJ a
1 2.1.6 FSAR Chapter 13,5, Plant Procedures 2.1.7 Nuclear Operations Management Manual, Section VI, Chapter 5
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y Administrative Procedure RV*l-210 Process Control Progres Revision 2 l 2.2 Vendor Controlled Documents
! 2.2.1 TR002, LW Technologies Corporation, Topical Report on 10CTR61 Qualified Radioactive Weste Forms, nay 1984 i .
2.2.2 4313 01354-OlP Chem-Nuclear Systres Inc. , Topical Report on Mobile Cement Sslidificatism Systes
=
2.2.3 CNSI-VF-C-01-NP, 10Cf761, Waste Form Certification-Creent, i: e Ches-Nuclear System Inc. , November 30, 1983 ) 3 PV J CWSI-DN-11118-01-P, Chee Wuclear Systes, Inc., Devatering j , 2.2.4 i Topical, December 23, 1983
- 1 2.2.5 STD-R-05-005, Westinghouse Mittaan Nuclear, Inc. , Topical
~3 N Report on Cement Solidified Wastes to heet the Stability
=
--l N Requirceents of 10CI161 si N N 2.2.6 STD-R-03-008, Westinghouse hittaan Nucteer, Inc., Topical m
y Report on Hittasa RADLOX 111gb Integrity Coctaincre cd 2.2.7 F1-013 Process Control Program for Do eterans Liner with
-i LN Technologies Corporatton laternels, LN Technolostes A
Co rpo r a t t on _7 i 2.2.8 STD-P-05-003, Mittaan buclear Developoet,t Corp., Process j Control Progras for Incontainer Solidification of 10 of 14 3
-j Veight Percent Boric Acid 2.2. STD-P-05-004, litttman Nuclear Development Corp. , Process 2 Control Program f or locontainer Solidification of ficad Resan
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V W l=310 Administrative trecedure Frecess Costrol Fregree Revision 2. 2.J.10 1tittsaa Wecisar Developeest Corp., STD-f4 3-905 Rittmas paclear Develoyeest Corp., Devotertog Eittama Estlock Containere with F1tztble Uaderdrets.e to tese Thaa 11 Drainable 1.iquid 2.2.11 8'TV P 04-002, Westisth ouse Eittman Nuclear, 1st. Dewstering ten 1* change Resia and Activated Charcoal T11tet tiedle to 0.5% 2.2.12 12 Techselogias Corporatica, 88-00$, Operettag Frecedure for
' 12 Technologies Corporation Radenste Se11dificattoa 3retea
^' Wueber 1908.
m / 2.2.13 !J Technologies Corporation, 88 001, Frecess Control Program for Redvaste 8o11dtitration Service N A Computer 2.2.14 WW 102*KP A, Waste tiaragement Group, SAIM&B N ede ttata Topical Erpert c' M , 2.2.15 MW ,1027, Waste tianair est Gresp BRmA2 - A campster Code o j'opical Report - Apisadieee ;gi khb.m Si *il 7 0(e41 , O ret A i Ioei r a ci.oOS fo r- M 2.2.tk DeMen. At ud (/ Paw. s e,T hheiC,uudShm 2.3 Other Dechmente . 2.3.1 10CTR61,1.tcenatog Raoutremente for 1.asm Disposet of Radio-active Weste 2.3.2 10CTT20.311, Tracefer for disposet and saufeste 2.3 3 10CIR71.91, Recorde 3.0 DET!NITICN8 NONE 4 4- -* * ' - 57 -
ItW+1 210 Administrative Procedure Process Control l'togram 4.0 kt SPoW51 BILITif.S 4,1 rient Manager. Nuclear 4.1.1 The riant Manager hoclest has overall adelnistrative control responsitsilittas for the Process Control Program at Vaterford-3, He is re*ronsible f or ensuring the following 4.1.1.1 The preparation, review and approval of the Process O Control Progran procedures pertaining to the process
- nrag and pe(beg 6ng, of radioactive seterials, and for m the operation and maintenarne of redweste systems; 4,1.1.2 that plant personnel adhere to the procedural require
- sients of this protras; N
N 4.1.1.) That plant interdepartmental respons 6blitties af f ect-tr g the Faccess control Program are clearly estattlished fq and acc onflished; O 4.1.1.4 1 hat personnel receive appropriate tr atutos and are qualtlied for their respective duties. 4.1.1.5 Proc ur ement of materials and supplies required f or toplev.entatiori and maintenance of the Process (ont rol Progree; 6,1.1 0 Operation and saintenance of radveste sHte**i 4,},1,7 lospection of Radweste activities; and 4.1.1.8 Adequate stafitog and sufficient resources for efficient and economic operation of the Process Control prograa. 3 h , 4,
103 1 210 Administrative Procedure wenn 2 Process Cont'0I I8' 4.2 Radiation Protection Buperintendent 4.2.1 he Radiation Protection Superintrodent is responsible for the overall effective manegreent of the plant Proteas Control The Radiation Protection Superintendent *
- res ,
Progras.
/rogran that theriges are initiated to the Process Contro Ith Physics proce dures when tietessary and that appropriate H, support to provided.
4.3 Plant Redweste Engineer *Wucleat _ M
- 4.3.1 The llant Radweste 1.ngineer who reports to the Radiation Protection Superintendent holds key responsibilities for implementation of the Process Control Progros such as:
N 4,3.1.1 Data collection, trend analysis, long tere planning, and probles solving for the plant Process Control c' Program; M g 4,3,1,2 Managing redweste solidilltation, dewstering and packaging; 4.3.1.3 Preper tog procedures for sclidtlication, devstering and portaging; 4.3.1,4 Intesfating wit 5 other groups as necesesty to analyse and resolve problems relating to tt.e Process Control progras) such as the design of Radwaste Systems and Equipment; 4,3,1,5 Prepa ring periodne s epor ts summar tr ang the Pro ("s s Cont ol Progras. P C 6 I i
l@ l 210 Administrative I8utedute 2 process Control progtem 4.4 Ope r et tons Superit. tender t - 5 The Cterations Superintendent is responsible for the effective m 4.4.1 redraste systres and will l operet toos of permanent plant C toordinate redweste activitica with the redveste departseent -. i 4.5 Clietr.i s t ry [ng inee r-liur le a r i 4.5.1 The Cbeststry I.r.gtneer kuclear is responsible for saterfectng 1
- ] #9 with the hadwsste ingineer on ttees et ptobless relating to M t odwe st e ps otes se s and <!.es a s t ry c ont role or c htet r al re ac t ions analyses of samples
- and p* forming (t, cat <al and radiochesits) ci r a dicot t ive wa s t e or u.at e t t a t s -
4 . t. Opetatione Quello Assurance Nanager - q N 4.6.1 The Operations Quality Assuran(e fianager is responsible f or 4 it.e review of platit Frotess Control Progres procedures. .
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O k.7 hurleet Servites Menaker as responstl>le for providin$ IIe 4.7.1 The hurlear ben.(es Manager j follow 6ng serviers. r 4.7.l.) S t a t e - t,l - t l.e - a r t t e t hnt( 41 adV e se . Support, and - g alsaltanic 46 tcQuired,
.,\=M y 4.7.1.2 llEchsing and legulatory Meplishfe support, and g y
fe[ y Appre u n.g the wat er f ord-3 Process Cont r ol t r ogree h 47.1.3 1
'DU. ana ren menan.g i.pnve.rt.t..
y E- _.V " 5 q' U 4.7.2 lt.e buc le a r Se rvic es i.t a f f interfaces directly with the hN Fj
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RV-1 210 Administrative Procedure Rettston 2 Process Control Progras - 4.4 Corprete Qus11ty issurance tianager 4.8,1 The Corporate Quality Assntsace tianager is responsible for assessing the imple=2ntation ar.d ef fettiveness of the quality asestance arpects of the Process Control Progree through regular audits and selective sonitoring of setiettlee. 5.0 170CfDUEL m
*a $.1 Program Description 511 Se11difiestico Brites
Description:
Waterford 3 utt11:ss vendor supplied portable solidificatico < e References egalpoent for radiosgeg3ss4e solidification. 2.2.1 through 2.2.134provide e general description of respec- g,g W htlf'/ N tive vender solidification procespo and process control a' features; fieferences 2.2.16 sad 2.1.t3 descrites the method which vill be utilised ta classify westes is accordance with m Sad Reference 2.1.1 through 1.1.7 are Veterford 3 g , (OCTJtd1 documents which either implement er describe activities which provide reasonable assurance that vastas are solidified or devotered in accordance with all applicable regulations sad c rit s ris . - 6.$t -
$e 5.1.2 Sourc.es se ear of Vaterford 3 Solidification Peeds: d6 fl.e, solidification systas will be used to process resins, rp6fD During resia evaporator bottoms and boric acid concentrates.
solidification, vendor equipment vill be connected to both the Resta Vaste Management System outlet and dewaterieg inlet to allow for the transfer of resta and the devotering of the 1Lner. Vendor equipment vill be connacted to the $olid waste tianagement System outlet when evaporator bottoes free the radweste evaporstor and boric acid concestrates freci the Boron Management System evaporator are to be solidified. d 4c, 0a St1 % twt seedia, 411 bt use
- Sc h:1 d'uAico remo re s . a s, , *> 9;l, %rafv hetta u b ber.<.
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K Wel*210 Administrative procedure f(evision 2 prpctes Control Prolta8 M
).2 Solidification Process Persett u s: _
5.2.1 Solidification formulas and solidification process parameters h ' are incorporated into the applicable vendor piecess control
- program. No esceptions or deviations from vendor supplied procedures or Lupical reports are enticipated for stabilised _ _
waste. The formales are used to calculate the ratio of waste,
<ement, water and other reagents required to achieve en acceptable solldtfied product. Coerpatibility requirements of n'
the waste stream with respect to the solidification media are described in the vendor process controls progree. Veste
> stream parameters are adjusted as necessary to ocet these , requirements.
7 5,2,2 Test solidifications are performed on vaste stress sawples to q verify vendor calculated solidification formulas. Plant N procedures describe the f requency f or perf ormatig test soll-difications and estabitsh the ecceptance criteria for the _ M test solidifications in accordance with Technical Specification _ a 3/4 11.3. 9
W 1 210 Adstristrative Procedurr Revision 2 Pretess Control Progros i S.) Administrative Controls S.3.1 Administ rative cont rols utilised to insure coerplisoce with applicable state and f ederal reguistions and Liuriel site criteris are detailed in the radioactive vaste solldtlication surveillance procedure (s). These loplemet ting doc umynt(s) f or radioac tive waste solidification and devote ritig dese rtt.es the r e yut r ement s whic h aius t t e me t prior to processtos radio-active waste, as well as the condition of the solidified or devotered waste. Test solidifications, full scale calcule-
" ticris and opera tion of tbc solidtittation equitecot age
- perforr.ed by venJor gersonnel. Llevaterleg ope r ations will be staff.
g er f orvied by vendor perscnoel or try qualified Plant Plant staf f provides ficolth Pbistc o and Qualit'i Assurante coverage, operates plent vedtpactive waste systems, collecte y weste st ress sosples and per forms isotopit analyses. Copies of all tef erenced docuents are avstleble on site f or use try
~- perscnnel cogeged in solidt t tration activities.
rn O S.3.2 Cttsta6es to tbt s Prot ess Control Prett aa shall te described in tt e armi annual hedicett ne 1.t fluent Aeleast Report for the per sed it, whtch the t han6e t o ese ie , in cctordan(e with Tethnt-L l col 5pectittation 6,13.2 b 1 5.6 Leste Cherectestistico end (lessifttatico h t S.6.1 Weste Classtittatico h.q Solidified wastes are classif ted to a(cordan(e witt b.4.1.1 tt.e requites. cuts of 100 kt.l .55, a s typicewated t>y t e f e r ent e s 2.2.14 acd i . 2. a5 and plant wa s te cla ss i t u at ich and chars (tertratton procedure (s). ( s 10 m La 77a:7qL ^:, ' y m .y #y,7w,, m w ym%w,w, 9g yo, " agggggg p? -
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RV-1 210 Administrative Procedure Revision 2 Process Control Progres ,
$,4,1,2 Annus) analysis will t>e performed on the waste streams to determine the isotopic abundance of gamma esseitting isotopes f a the stresos, Scaling factors for the nro ganna esunttting and transurenic consti-tuents will be developed f rom this annual analysis.
The activity of each radionutlide in the solidified waste will be deterstned by a catrulational method a employing the percent abundance and scaling factors ' with a dose to curie conversion factor as described
# in reference 2.2.14.
M m 5.4.2 Vaste Characteristics
$,4,2.) Solidified westes will meet the characteristirs of _
10Cn61.5t>(a) st.J (b) . Vaste containers will be N labelled to identify the weste class. _ N N 5.4.2.2 The manifesting sequirewnts of IDCIR20.311 are i M implemented and recosds are maintained in accordance with 10CI'R71,91 a
$.S Quality Assurance 5.5.1 Quality Assurante related activatles f or (tie Radioactive -
Weste Program are teptemented se described in the Nuclear These Operations Quality Assurauce flanuel (Reference 2.1.7). acitvntie6 provide verification that the solidtfied wastes sieet applicable state and federal regulations and burial site criterna, i I t, . 0 ATT ACletLNT S sm i i
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, UCl: DICA!. REVIItf CEECKLIST NO. bd } IID M $10X NO. 2- CEDGE Wo. l p7oCEDL'F{Per, Titu e e u & M re tI c tmn 4
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1 AssicrtD nCatcAx. uviEw.a bc_ u u ; s Skee u, TICEXICAL REVIEV SU8Com!!TTU FOD1D l~1 TES Q N0 1.187 $UBC0ttKITTEE NEMEERS/DEFARTMEKTS r I
- 1. Is this procedur , revision, change, or deletion ~
g N technically and administratively correct? @ TLS l,1 NO m 2. Is this procedure, revision, or change capable of , batag performedt [,q US I,) No f 3. Is this procedure, rettston, change or deletion i - compatible with other plant procedures? }{lTES l"1 NO
- 6. Does this procedure, rev4ston, or change reference and adequately implement (or to the case of a deletion, i adequately coerpensate for) coszattaents (CMS Report)
N ~ l
..i; sade in the TSAL, SEE, and other licensing documents? @ n5 ll No g
j 5. Is this procedure, revision, chsoge or deletion correctly a ce numbered, formatted and prepared to accordance with i approved procedurest f3 H5 l-l No-
- M
_j 6. Does this procedure, rettston, change, or deletion o adequately address and/or reference Technical Specifications and other estters that eLay affect nuclear , , safety? fr{ TES 1,1 No 7 Vere the Safety Review questtons on the New Procedure Request or Change /Feviston/Deletton Request properly , , answered? ($ US 1,1 NO
- 8. Does the Safety Evoluetton, if appiscable, provide adequate bases and justification as to whether or not ~
an u revneved safety question entstst @ H5 l l No g 7. Does the procedure meantain the level of Fire Protection , , g as outlined to the approved Ftre Protection Procedure? )<1 YES 1,1 No s;l gll I have revteved this procedure and all items chectec "NO" above have been
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i _ s TECEDICAL M VIEU CEICKLIST FROCEDU11 50. Riv. / - 2 /0 MYl810N po. 2 CRAsGE pa, ^/M TITLE /hr e a C c ,. /, c / ! O, m e,,,.i d AlsICKED TECENICAL MVIEVER Il 2. . ) / Cede ,
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, TECXXICAL REVIEV St3CormlTTLE FORKED l l TLS @ E0 LIST $14 Cot-t11TTEI ttIMELR3/DTtAn'n3JT5 M1
- 1. Is this procedure, revision, change, or deletion m technically and administratively correct? Q YES l[lNO l 2. Is this procedure, revision, or change capable of M being performedt
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l,1 ko lK Yt3 f?' 3. le thte procedure, revision, change or delettoo compatible with other plant procedurest IK Yts ([l50 6, Does this procedure, revision, or change reference and adequately (seplement (or in the case of a delettoo, adequately compeasste 1:,r) comunitaects (CMS Report) N made in the TSAR, SER, and other licensing doctae.cotet kgTLS l l[lNO N 5 le this procedure, rettston, change or delettos correctly numbered, formatted and prepared in accardance vit.h N approved procedurest l'g TIS l[IWO M 6. Does this procedure, rettston, change, or deletion adequately address sad /or reference Techottel O Specifiestions and other setters that may ef fect nuclear safetyt
? Vere the Safety Revtev questions en the New Procedure kits l[INO -
Request or Change /keviston/ Deletion kequest properly eneveredt h RS ((] 40 8 Does the Safety Evaluation, if appitcable, ptr, vide adequate bases and justification as to vbether or not en unrevtewed safety queetton esists? H5 ((lNO
- 9. Does the procedure setotato the level of Ftre Protection as outlined in tie approved fire Protectten Proceduret $ TIS l[1NO -
! have revneved this procedure and all items ct.ected "WO" above have been resolved vtth the Author (or responsible Group Head) and documented on Document Review Coseent sheets.
ASSIGNED TICKNICAL REVIEVER_ 9 DATE 87
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UNT 1-003 Revisten 10 AttacLaent 6.10 (1 of 1) h.
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EVIIV COVLR $KLIT gyggy cy, RW-1-210 - (Change 1) Process Control Program (Rev. 2) PORC RVifV Tbs PORC has rettered this ites e.ad deterutned that a safety evaluatten vse perferwed (as appitceble), that sa unterteved safety queettes does not estet les orplicable), that a change to ttie Techotcol $pectiteettens to set required, and that nuclear esfety Je7was not adversely ef fected. OELR ECatt11XIED OT PORC IGXBIR PORf HDDEER Tts AFPRWAL DATI RIVIEW $1GEAT181 TIS M
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!! yes, assure documentation supporties rettaw to attached.
Ttts ttee requires QA rettev prior to PH W epprove11 O T13 90 PLANT nAXACER.FUCLEAR APPROVAL (MIER TO 5.6.12.1) Comments : M - Approved by M Y Ad.4 m Date /d '/-- N Plants nana ge r-Nucle a r l L'WT 1-006 Reetaton 7 Attachment 6.1 (1 of 1) Il f .
,y VATLFJORD 3 SE5 Chect Block F,elow FLAYT OFEMTING PJXUAL CEAllGE/REV1510W/DLLETIos RI%TST l@ PON l[lPCSC 5/C Procedure No. M
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(if dif ferent f rom approval date) Effective case qparlete A, B and_C ~ Erpiration Date 4/A Change No. I T2irermanent l,,lDeviation A. B. Revision No. E C. Deletton ([lTES @NO ptsCRIPTICW 2 OF CHANCE CR RIVI$iONM ufd aan IArrosv & rn*L ko hA $md c0 7 lat wik re ty d u rv . ndh hek e_(tuAcI Od kt k i e . f i rA - bd c3 M t Ob? CL
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5 If the answer to any of the above u Ye c wplete and attaca a 10CTF30.59SafetyEvalupon. *g SATETY/C0FMIT:E.NT , IRT utw t k IA DAH , W I 4 3 k8 ~7 DATE AYbH37 i TEOLNICAL REVIEV _ $ M-tW1 Md6M DATE /C/lM 7
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TEMPCRARY APPROVAL * ($RO)_ ) _ CATI Nuclear approval witain TEMPORARY APPROVAL *
**erporary approval cust be followed by Plant Manager /APM-N 14 days. ! AttacLaent 6.7 (1 of 1)
UNT 1 003 Reviston 10 f ' 30 T - r y
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Adetyistretteo Procodnro EW"I*810 Frecess Control Fregre Revisico 3
?ABT1 of CairTINTi 1.0 FULPOSE 2.0 RUIKUCL8 3.0 DU DIT1038 6.0 KL5P085181LITI15 S.0 FROCIDURI
" 5.1 Program Description
- 5.2 Solidification Process Parameters S.3 Adataistrative Controle S.6 Vests Charactertsstion and classificatios 5.5 Qualit) Assurance N
6.0 ATTAC!2%NT4 , c' :- m =.. i a LIST OT UTICTIVE PAGZ3 Title Eartston 2 1 11 Rettston 2 [cy I,Y lh 1 Y
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M 1+110 Adataistrative Procedura Lavision 2 Frecess Control Program ih . 2,2.10 Rittaan Nuclear Dervelepasmet Corp. , FTD-P-03-003, Eittaas 7 Nuclear Development Corp., Dewatettag Rittman Radloct 1~ F Containers with nasible Underdretas to Less Than 1% Drsimabis Liquid 1.2.11 5&P-04-002, Vestinghouse Eittmas Nuctur, lac. Dcratertag lon tachange Resta and Activated Charcoal Tilter Media to 0.5%
;I 9 2.2.12 12 Tectaologies Corporation, 83-005, oprating Procedure f or h
12 Technologies Corporation Radvsets Solidification System v d Number 8904. 3. 2.2.13 IJ Technologies Corporation, 55 001, Process Control Progras ,j
- for Radvsste Solidification Service N
N 2.2.16 um 102 EP A, Weste tias.asement Group, RAIrtAN - A Congwter code Main Topical Esport c' l M 2.1.15 WM )C27, Vsste tianassasut Group, RADhAN
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active Wests 2.3.2 10CTR20.311, Trsnator for dispossi sad e6entfests y t 2.3,3 10CTRM.91, Racords [ A i 3.0 CETINITIONS. NOKI
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- EV-1 210 g Ada.tnistrative Procedurs Process Control Program Revision 2 M '3B .
6.8 Corporate Quality Assuran e tianage3 k 6.s.t the corporate qu11ty Assurance tianger u respoutbie for d assessta; the invie.ent4 tion ud offmpwo .i tre quiity sesurance +ereen of tre Process cwmt Ngo arougn
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ter31er audita and selecti's waiteu 4 4 .cuvoies. 5.0 09EW.2. m 1 - 5.1 program Desertption k
- 5 1.1 Solidification systas Descriptions h .
Waterford 3 utilizes vendor supplieJ port 4ble solidificatico h equipmentforradiosgeg3angesolidificatios. References e
-h 2.2.1 throu eh 2.2.134provide a general description of respec- g j N tive esador solidification processes and process control e htlT/
k ^' f asturee n Rafersaces 2.2.16 sa4 2.L LS describes the estAod which will be utilis-ed to classity wastes La accordance with M
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documents vtLich either isplenwat er descathe activities vttich W provide ressouble assurance that wastes are solidified or Wg devotered in accordance vita all applicable regulations and 5 c rite ria .
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$e 5.1.2 Sourc.e.s wr of Waterf ord 3 Solidtiteetion Teods:
s T!.es solidification tystes vill be ued to process resins, d.h8 w i h qisp? t evaporator bottoms and boric acid concentrates. During re s ta solidificatica, vendor equipenant will be connected to bota the Resta Weste tianagement System out.let and desatoring talet to allow f or the transf er of resta and the devatoring of the
=:4 liner. Vendor equiguent vill be connected to the Solid wasts y8 tianagement System outlet vtten ervaporator bottosa f rom the W1 y radwasta evaporator and boric acid concentrates free the Boron Management Systes evaporator are to be solidified.
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Adstnistrative Procedure itV 1-210 Process Control Frogram Revision 2 TABLE Of CONTEXTS 1.0 l'URPOSE 2.0 REllRI NCES 3,0 DEFINifl0NS 6.0 RESPON3!BILITIES if 5.0 l'ROCEDL'RE
, 5.1 Progree Description 5.1 Solidification Process Panameters
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5.3 Administrative Controlo 5.4 Veste Charactertration and Classification N 5.5 Quality Assurance N et 6.0 ATTACHMENTS M O LIST of F.IITCTi\T PAGES Title Revision 2 1-11 Revision 2 m a 5 1 m wr T .
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W 1 210 Adoinistrative Procedure _i itevision 2
= frocess Control Prestso i
2.2.10 Hittaan Nuclear Develogeent Corp. , STD-F-03 005, Hittaan j Nuclear Development Corp., tyvatering Hittman Radlock Centainers with Fleitble Underdrains to less Then 11 Drainable i j Liquid
'l f3 2.2.11 STT)-P 04 002, Wes t toghouse Hit taan Nucle a r , Inc . Ivvat e r ing 3
2 Ion Lachange hesin and Activated Charcoal litter Media to 0.$1 2.2.12 1.h lechnologies Corporet ton, SS 005, Ope r ating Procedure f or N LN Techriologtes Corporation Radweste Solidatication System a 16 Nun.ber 6908. 2.2.13 1.N Technolegtes Corporation, SS 001, Frecess Control Pregras 4 for hadwaste bolldtlication Service N' 2.2.14 kN 3 102 N P A , h a s t e Ma na geme nt G r oup , AAletAh - A Computer 4-N Code Main Tcpical F.eport g p. 2.2.15 WHO 102P, We st e Mana g ement Grot.p RAlriAN - A C(epute r Code M Topical heport - Appendices g
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-J active kaste 2.3.2 10;t R20. 311, T r ans f e r for disposal and sanifests 3
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RW 1 210 Administrative Procedure Revision 2 Process Control Progras 4.8 Corporate Quality Assurance Manager 4.8.1 The Corporate Quality Assurance fianager is responsible for assessing the inrplesentation and ef f ectiveness of the quality atsurance espects of the process Control progree through regular audits and selective monitoring of activities. b.0 ffgCfM
$.1 program Description in
- 5.1.1 Solidification System
Description:
Vaterford 3 utiltres vendor supplied portable solidification equipme nt for radioactive waste solidificatin. Referernes 2.2.1 through 2.2.13 p* ovide a general description of respet
- g tive vendor solidifstation procesaca and process control f eatures; Ref erenc es 2.2.14 and 2.2.15 describes the method which vill be uttitred to classify vastes in accordance vnth M 10CIMl; and llef erence 2.1.1 through 2.1.1 are Waterf ord 3 O
docuriente yhtch either implencot or describe activities which provide ressunable assurance that vastes are solidified or dewatered in accordance with 411 applicable regulations and c61terta. 5.1.2 Sources cf Waterf ord 3 Solidt fication f eeds: The solidification systra vill be used to process resins, During resan evaporator bottons and borne acid concentrates. 6cindif tration, vendor equipwnt will be connected to both and dewatering inlet the liestn Vaste Managreent Systes outlet to allow for the transfer of resin and the dewatering of the liner. Vendor equipment will be connected to the Solid waste Management System outlet when evaporator bottoms from the radweste ev:poratos and boric acid concentrates f rom the Boron Management Systes evaporator are to be solidified. 8 4 -
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Nrw onutANs punuc sinvict INc. PCM VOLUME aw.1.-210 PCM SECTION - REVISICN 3 ADMINISTRATIVE PROCI'DUHE PROCESS CONTROL PROGRAM LP&L W -3 RECORDS MANiGEMENT n vun y;T,o is ps_i m_ -n. COPY -
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P olt C llI:V I E W COVI:ll 1;lll!!:T ItEVIEW OP Il W - 1 1 0 - Procenn Corit t o l l'rog ram (iteV. 3)
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\ pellC REVIEV The FORC bas reviewed this ite:n and dete rmine I t h,t a safety evaluntten -as performed (as applicable), that an unrevic'ed safety question does not exist - (an a p p l i c a t' l e ) , that a chnuse to the Technical Specifications is not required, andthatnuclearsafetyysfwasnot adversely affected. Wl'ER _ _ . _ Uf RECCt!!!E!iDED FOllC 11E!! DER I CPC !!E!1PER ( l'EVIEW Folt ATI POVAI. DA!!: n l cl4 A I URE gg flaintenance - . Superinteudent _-% _h * - . . . . _ _ . . Operations
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lhls i t e ra is r e c em:::e n d e d f o r a p p r o v a l 7 11 iES U NU Ibis i t e ra requires SRC/NRC review prior to t plementatlon? O YES 0 MO If yes, ensure documentation supporting, review is attached. f!.A!!T ?!AM ACER-!!UCI. EAR Af f DOVAL (REFER 10 c.4.12.1) Com:ne n t s : Approved by h\b ._ 153te i ,\p f1 ant flan a r a r -N ir 1" T r U N I' O U 4 Prvision 3 Attach;" nt *i . ) (1 >f 1)
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CHANGE / REVISION /DEIITION RIQUEST l,9 PCM i lPCRC-5/C i Procedure No. /NO-/* 2/0 Title [/w.'.f M d+>1/70 / [e or 1'h ) a Effective Datrl (if different from approval date) { Complete A, 3, and C l A. Change No. A/A l[l Pe r:nanent l[lDeviation Expiration Date ! t B. Revision No. 3 i C. Deletion l[ LYES lj{NO l DESCRIPTION OF CHANGE CR REVISION 1 0/b'!C m'4N!cf . 3!6 0,rkt:0 NMl (l tf Mtn' fM!Wdh /A n u n;rth
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' I SATETY/CC."MITMENT REVIEW
! Does this change, revision, or dele; ion: f ' t
- l. Change the design, descriptten, function and/or !
operation of a system structure or component. descr, bed j
- n the FSAR? YES NO 'l !
- 2. Change the procedures as described in the FSAR? YES N0 /
- 3. Conduct tests / experiments not described in the 13AR? YES -
NO / J. , Require a change to the Technical Specifications? YEd. NO 6 I
- 5. Alter the implementat:en of any coc:mitments? YES No 4-- !
If the answer to any of the above is Yes, co=plete and attach a j 10CTR50.59 Safety Evaluation. i r SAFETi/CCMMI*'iENTREVIEWhn)!)/t,
/fN D DA TE ?k7 b9 !
p .-. TECHNICAL PIV!EW de a /L Nm, t 3 DATE d - ? 4' Ff l GROUP EEAD REVIEW Grte %? ///7d/k ~r6 DATE 4/Ze/W TEMPORARY APPROVAL * (SRO) DATE . TEMPORARY APPROVAE* DATE ! I Memporary approval *ust be followed by Plant Manager /APM-N - Nuclear approval within j 11 Jays. t i i I
"'NT 00 3 Revision 10 Attachment o.' ' af 1 ;
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_ _ _ = - ', Administrative Procedure RW-1-210 Process Cont rol Program Revision 3 t 4 r
- TABLE OF CONTENTS 1.0 PURPOSE i
) ' 2,0 REFERENCES l 3.0 DEFI.NITIONS i 40 RESPONSIBILITIES f i ! f 5.0 PROCEDURE 5.1 Program Description f j 5.2 Solidification Process Parameters ; 5.3 Administrative Controls '
- 5.4 Waste Characterization and Classification !
i 5.5 Quality Assurance . o.0 ATTACHMENTS 1 LIST OF EFFECTIVE PAGES 3 Title Revision 3 f 1-10 Revision 3
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- Administrative Procedure RW-1-210 j Process Control Program Revision 3 i
1 1.0 PURPOSE a
- 1.1 The purpose of Waterford Steam Electric Station - Unit Numtier 3 (Waterford 3) Pcucess Control Program (PCP) is to describe the program which provides reasonable assurance of the complete solidifi- !
[ ation of various radioactive " wet wastes" including resin slurries t I and evaporator bottoms are accordance with applicable Department of { Transportation (DOT), Nuclear Regulatory Commission (NRC), St. ate and ) licensed burial facilities acceptance criteria for packaging and l shipment to an approved burial site. Compliance with these criteria will be achieved through implementation of the PCP and related Waterford 3 ar;d vendor supplied procedures. I i
2.0 REFERENCES
4 2.1 Waterford 3 Documents I6 2.1.1 Technical Specification 3/4 11.3 i 2.1.2 Technical Specification 6.13.2 i i ! 2.1.3 FSAR Chapter 11.4, Solid Waste Management System l r i l 2.1.4 FSAR Chapter 13.4, Review and Audit i 2.1.5 ESAR Chapter 13.2, Training } j 2.1.6 FSAR Chapter 13.5, Plant Procedures i I 2.1.7 Nuclear Operations Management Manual, Section VI, j
- Chapter 5 I 4
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l Administrative Procedure RW-t-210 ! Process Control Program Revision 3 P i 2.2 Vendor Controlled Documents ! t 2.2.1 LN Technologies Corporation. TR002, Topical Report on t i 10CFR61 Qualified Radioactive Waste Forms, ?!ay 1984 j t 2.2.2 LN Technologies Corporation FI-013, Process Cont rol Program i l \ for Dewatering Liner with LN Technologies Corporation Internals, i s LN Technologies Corporation j t i 2.2.3 I.N Technologies Corporation, DW-002, Process Control Program for Dewatering Bead or Powdered Resin with Qutek-Dry j r Dewatering Syster No 8814. 2.2.4 LN Technologies Corporation, SS-005. Operating Procedure for j i LN Technolo.r.es Corporation Radwaste Solidification System ! u Number 890F. [ 2.2.5 LN Technologies Corporation, SS-001, Process Control Program ! for Radwaste Soliditication Service ! 6 2.2.6 WMG, Inc., 102-NP-A, RAD.' TAN - A Computer Code Blain Topical Report . l l 1 6 :
- 2.2.7 i Inc., 102P, RAD"AN - A Computer Code Topical heport - {
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2.3 Other Documents ! 2.3.1 10CFR61 Licensing Requirements for Land Disposal at Radio- ! i active Waste j l t' 2.3.2 10CFR20.311, Transfer tor disposal and manifests { l I i J.3.3 10CFR71.91, Records ' I t h j f i
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Administrative Procedure RW-l+210 l Process Control Program Revision 3 I
.! . 0 del I_N_i_l I ONE 4
4.0 RESPONS 1 B I L I T II'S
!. 1 Plant 'ta n a cc r -Nu c l e a r 4.'.1 The Plant Manager-Nuclear has overall ailministrative tontrol responsibilitiet t' o r the Proce:s Control Program at Waterford-3.
He is r e s pon:. t b l e for ensuring the f o l. l ow i n g 4.1.1.1 The preparation, review and approval of the P ro c c e, s Control Program procedures pertaining to the p r o c e r, e. - Ing and p. irk 1ging, of tadioactive materials, l'id for the opetation and maintenance o t' tadwaste :; y s t enui ; - 4.1.1.2 'I h a t plant pernunne1 adhere to the p+otedural require-ments of this program; 4 l.I4 3 Ihat p l a lli. i nt e rilepa r tmelit a l r e 5 ptin h a h i l l t. l e h .i t f e r l
- ing tne Proce , con rol Program are i l ea r l y c:.t abl i shed ind accompi t shed ;
4 1.1.4 That pertonnel r ec e ive approptlate training mu are
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4.i.1 h Pro ( urement 't i materlal8 .s tri ;upplie: t e-{u t red !or implement at ion and m t int en inre ot the P roc e :, < Lontrol program;
+.1.1.O ipe r .l! ' i;t t .l fl. ] m i l o t t'fi llle e ett E .t i j w 15 t. P ' '; ( e m ';
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_._...____.._._.____.__._m. _ _ . . . . _ . _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ . . _ . _ _ . _ . . _ i t Administrative Procedure RW-1-210 Process Control Program Revision j ; t F t 4.1.1.8 Adequate staffing and sufficient resources for ! t efficient and economic operation of the Process [ t f Control Program. I 4.2 Radiation Protection Superintendent l I ! 4,2.1 The Radiation Protection Superintendent is responsible for I the overall effective management of the plant Process Control I ! Program. The Radiation Protection Superintendent ensures l that changes are inittated to the Process Control Program ,
' i procedures when necessary and that appropriate Health Physics !
support is provided. 4.3 Plant Radwaste Engineer-Nuclear 4.3.1 Tht Plant Radwaste Engineer who reports to the Radiation Protection Superintendent holds key responstbalities for implementation of the Process Control Program such as: , 4.3.1.1 Data collection, trend analysis, long-term planning, and problem solving for the plant Process Control __ Irogram; 4.3.1.2 Managing radwaste solidification, dewatering and packaging; 4.3.1.3 Preparing procedures for solidificatton, dewatering and packaging; a.3.1,4 intertacing with other groups as necessary to analyze l and resolve problems relating to the Process Cont. col ! c progra,m such as the destan of Radwaste Systems and ' l i Equipment; 4.3.1., Preparing periodte reports summar utng the Process Control Program. J
Process Control Program Revision 3 4.4 operations Superintendent 4.4.1 The ope ra tions Supe r i:it endetit is t es potis i bl e for the ettecttve operations of permanent plant radwaste systems and will C OO rd i n a t e- radWaSte act1Vltir 'llh t he radhaSte d e pii r t me n t . 4.5 Chemi st ry Eng tnee r-Nuc lea r 4.5.1 The Chemistry Engineer-Nuclear .s responsible for intertacing with the Radwaste Engineer on items or problems relating to radwaste procesnes and chemistry controls or c hemical reactions afid peri 0rming Chem 1 Cal Jud radiol $1 emit ~al aftalyseE Of sample: of radioactive waste or materials. 4.6 Operations Quality Assurance Manac,er 4.b.1 The Operations quality Assurance Manager is r e r. pons t b l e for prOVidinR the t u (((rwing sery1Ces 4.o.l.1 Revt. wing plant Process Control Program Procedur e: 4.b.1.2 35SeSning the i mp [ eme n t a t t o n ;g nd e t t' p c t 31, pnggg ,,g the quaILLi ,l S S il r a n c e 15pecL5 i! t he p ro c e s c, Cunt 70[ Program t hf ullgh reRul al audit 5 and selective ma n i t o r t 'ig c; t act1.itics 4.' Nur1 ear Se rv i C e: lanager
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4..1 The Nuclear Se rv i c e: Manager . , r"sponsible for providing the 101IOW1UR SerY1Cet 4.7 1 Stat" a!-the-irt t e( hnt( al advi: , ;ppo rt , a n r1 is ! ii s t ance is rmju ; re't ;
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Administrative Procedure IN 210 Process Control Program Revision i l J..'.1.2 !actnt.ine and : e c u ! i t ; r:, < mpl:ance -; uppo r t , and 4.' l.3 Appraising the Watertotd-A Procesc Jant: al Prceram and recommending improvement: 4.>.2 l'h e Nuclear Services statt interfaces directly 5- 5 the plant statt in providing these services 5.0 P RO C E D_ L_'R_E d 4 m
~.1.1 SolidtfLCat10n '\Gl.em IeSC.lplion.
Waterford 3 ut11tzes vendar suppliel portable s o l i d t i t. t a t l a n equipment tor radioactive waste ,altditication. References 2.2.1, 2.2.- and 2.2 5 provide a general description ;>t respec-ttve vendor .olidi icattan processe: and proces< cuntrol teatures. Reterences _.2.0 and 2.2.' describes the methcnt wilich will be utilized to classifs wante' 'n accordance with 10CFRul; and heterence J .4 t h r o u e tt _.1.' are 'w a t e r t a r i documents which either ;mplement or describe actietttei which provide reasonable assurance that waste
- _t re ol.idit;'d 0:
,!t*Wa t e r ed i tl a C C u ril-'i n c e wlth al[ .ipp [ 5 c a h [ t_' PQu}atIanS an}
criterta.
Administrative Procedure RW-l 210 Process control Program Revision 3 5.1.2 Sources of Waterford 3 Stabilization / Solidification Feeds: ne Cement solidification will be used to stabili;e resins, l evaporator bottems and boric acid cencentrates. During resin stabilization, vendor equipment will be connected to the Resin Waste Management System outlet to allow for the transfer of resin. Vendor equipment wi 1 be connected to the Solid waste Manacement System outlet when evaporator bottoms from the rad-waste evaporator and boric acid concentrates from the Boron Management System evaporator are to be stabilized. Solidi-feation using Aquaset /Pe t rose t media will be used to process resins, oil, water / acid, evaporator bottoms and boric acid i t concentrates. This process will not be connected to any plant l waste systems and will be processed on a batch basis, i i l , i 5.2 Solidi fication l'rocess Parameters: ( i 5.2.1 Solidification formulas and solidification process parameters 8 are incorporated into the applicable vendor process control program. No er.ceptions or deviations from vendor supplied ; procedures or topical reports are anticipated for stabtlized fr waste. The formulas are used to calculate the ratio af waste, ' cement, water and other reatents required to achieve an acceptable solidified product. Compatibility requirements of l the waste stream with respect to the solidification media are t i described in the vendor process controls procram. Waste l l stream parameters are adjusted as necessarv to meet these ! i requirements. !, I r 5 . .' . 2 Test solidifications are perf ormed on waste stream samples to ! verify vendor cal.culated solidifiention formulas. Plant ! procedures describe the frequene;. for performing test -; n i ! - l dificatiens and establish the acceptance criteria 'or the ; , test solidifications in accordance with Technical Serification ; 6 -- a ;/ 4 t. .? a. ! i l 8 ! I
Administrative Procedure RW-1-210 Process Control Program Revision 3 5.3 Administrative Controls t 5.3.1 Administrative controls util t; ed to insure compliance with applicable state and teferal regulations and burial site criteria are detailed in the radioactive waste solidification surveillance procedure (s). These implementing document ( for radioactive waste solidification and dewatering describes the requiremen s which must be met prior to processing radio-active waste, as well as the condition of the solidified or Jewatered wast.e, rest solidifications, full scale calcula-tions and operation of the solidtfication equipment are pertormed by vendor personnel. Dewatering operations wtll be performed by vendor personnel or by qualified Plant staff. Plant statt provides Health Physics and Quality Assurance coverage, operates plant radioactive waste systems, collects waste stream samples and perf orms isotopic analyse: ,:opies of all referenced documents are available on alte for use by . personnel engaged in solidtfacation activities 5.3.2 Changes to this Process Control Program shall t'e descrited in the semi innual Radioactive Efiluent Release Report ter the per: id n which the chance ti made. ta accordance with Techni-C a l. S p e t 1i!calIDn h,13...
- Waste 'haracterifatton .inti 1" [ a s i fleattun i ,.1 Waste Cla55 i f I ca t 1,n
~.4.' ! loliditled Waste tre classifled n accordance with the requt:ements *
' J C I'h t2 l 55, as tmplemented by ret"rence< _.2.b and 2. ,' and plant waste
- lass t ! cati n uni <haracterizat: .n pr;cedure(t 1 4
p ' Administrative l'r ocedur e RW-1-210 P r o c e 'i s Control Program Revision 3 1 .4. 1 . Aunuai : n a l , s i :, wtll he performed on the waste
.; t r e t m > t:)
dt'l e rm i ne the t !.o t O p 1 C a h ulld a ltl e it g aluma emit t ing ..otopes in the n t. r e a m s . :ic a l i n g tactort
!or the non gamma emttting and tIansutanit ionSt1-
- 1. u e n l S wt11 he developed Irom th1S annual JnalyS15.
The activit, 't each radionuclide in t he nolidtiled waste will be determined by a core sample or a cal-culational method employing the percent abundance and scaling tactors with a lose to curie conversion tactar as d e s c ri tie d in reference 2.2.0. 4.J Wa $. t.c C h a r a i, t e r t ti-, 1 5.4.. 1 Solidi!ted wastes wt11 meet the cha r.n t c ri s t t c:. ot 10CFRnl.50(a) and (b). Waste containers will be labelled 'a identity the waste claua E 4.2.2 The mantiesting requirements ot 10CFR20.ill are implemented arui records are maintained .n accordance wtth ! a&R 7 I 91.
'ual1ti Assurance 4 . ') .i 'lU a l i ' A S ^, u r a ll t. P r#' lated lettVitleS !at !he R,ld ] O a i t I Ve Wahle {'rcRIam ars' mp l eme n t. e r l a f., ile G( r } }it=(i .n the Slitlear Operations %nagement .bnual (Reference 2.1 71. These activitte, provide verl!tcatton that the .otidt! tea wastes meet ippii t a ti l < tal+ and !Pdetal regulatt ,nn and hartal .ite c r t L
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