ML20039D648

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Forwards marked-up FSAR Pages Re Open SER Item 1.7.17, Solid Radwaste Handling & Disposal. Encl Proprietary Process Control Program:Packaging of Low Level Radwastes Withheld (Ref 10CFR2.790)
ML20039D648
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 12/28/1981
From: Nichols T
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19297F173 List:
References
NUDOCS 8201050311
Download: ML20039D648 (48)
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Text

{{#Wiki_filter:- _ _ _ _ _ _ _ _ - - _ _ _ - _ _ _ _ _ _ - _ _ _ SOUTH CAROLINA ELECTRIC a GAS COMPANY POST OFFICE SOX 784 COLUMBIA, SOUTH CAROUNA 29218 g T. C. NicHoLs,J a. \\\\ wa r.o .v... o. ocev'= December 28, 1981 s g6.t) unu. onne. 97e 5 c, Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation 4 to U. S. Nuclear Regulatory Cmmission W Washington, DC 20555

Subject:

Virgil C. Sumer Nuclear Station Docket No. 50/395 Solid Radwaste Handling and Disposal Open SER Item 1.7.17

Dear Mr. Denton:

In a letter dated November 4,1981, South Carolina Electric & Cas (bmpany (SCE&G) transmitted five attachments which reflected the changes implemented as part of our new Solid Ladwaste Handling and Dispsal System. As follow-up to that transmittal, we are subnitting the following documents: a. ISAR Chapter 11.5, " Solid Waste Systen," marked to reflect changes (Attachment I). b. ESAR page 10.4-19b marked to reflect changes in the (bndensate Polishing System (Attachment II). c. ESAR Figure 10.4-7a, " Condensate Polishing," marked to reflect changes (Attachment III). d. " Virgil C. Sununer Nuclear Station - Process (bntrol Program - Packaging of Iow-Level Radioactim Wastes," (Attachment IV). e. ESAR Figure 1.2-25, "Drtuning Station and Hot Machine Shop Plan at Elevation 436'-0" and Elevation 447'-0"," (Attachment V). Attachments I and IV of this subnittal supersede and replace the same attachments subnitted in the November 4,1981, letter. Attachment III and V are Ireliminary and for information only. %ese figures represent the general flow path for the condensate polisher dewatering systen and the general area for the low level storage pad. The figures will be issued along with Amendment 29 of the ESAR. Please note that Attachment IV is proprietary. Se attached affidavit is in supprt of the document being withheld fran public disclosure and is the same as that subnittal in the November 4,1981, letter (A ta VI). \\ Q (19he.PoA 1Q fjd d s,g up t 90K M \\ M nms @ ef ( b,e pJp 82010s0311 81122e gge eM PDR ADOCK 05000 j t E _]

. Mr. Harold R. Denton December 28, 1981 Page Two Based on the above, we feel that sufficient information has been Irovided to emplete your review. However if you require further information, please advise us. Very truly yo A T. C. Nichols, Jr. GD(:'ICN:glb Attachments cc: H. R. Denton 25 copies (15 proprietary,10 non-proprietary) V. C. Sinner w/o atts. T. C. Nichols, Jr. w/o atts. G. H. Fischer w/o atts. H. N. Cyrus H. T. Babb D. A. Natrnan M. B. Mtitaker, Jr. W. A. Williams, Jr. O. S. Bradham R. B. Clary M. N. Browne A. R. Koon G. J. Braddick J. L. Skolds J. B. Knotts, Jr. B. A. Bursey w/o attachment IV J. C. Ruoff w/o attachment IV NPCF File A

1 Attachment I. Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 b 11.5 SOLID UASTE SYSTEM s 11.5.1 DESIGN OBJECTIVES aaJ/or 2Y The solid waste syste= is designed to package.ad-solidify radioactive wastes for shipment to an approved offsite burial f acility in accordance with applicable Department of Transportation (DOT), NRC and State regu-lations. The system conforms to 10 CFR 20 and 10 CFR 50 requirements by providing shielding so that radiation exposure of operating personnel an'd the public is within acceptable limits. Solid waste packaging is Ioo 01 li- % d :::1s area located on the ground floor J "/ accomplished in : (elevation 436') of the auxiliary building, a Seismic Category I struc- -Sir're ' i=:I=*rdf"~ ^2 5" " -9: 2' 211127/ 'cuilding 'i ture. - r m*: chield 2112, ::.::;t fer emceening-into,the trucP ::cce z7 w ider. *

  • 9 3Mhrough=this-opening =ie-conuol.144 -4 hare ir 21 c.

. -- n incarr; dict: ca; et: chi:1d 5 w a this ep H ng 2nd the fill rece2 Design, f abrication and test of solid waste system components and piping f"t' is in accordance with ANSI B31.1 and other accepted standards referenced D by ANSI B31.1. Additional onsite system tests will be performed using nonradioactive materials prior to commercial operation. The shipping containe: s are DOT Type A. Overpacks for highly radioactive materials satisfy DOT regulations. Packaging and shipping conform to 49 CFR 171 through 49 CFR 178. and casks Individual container shields be cin;; nrrind 3 1/2 ::d ^ inch thichn::::: N .-of lead are used, when required, to maintain radiation levels within 200 mR/hr at surf ace contact and 10 mR/hr at 3 feet. 11.5.2 SYSTEM INPUTS I Radioactive waste packaged includes: 11.5-1 AMENDMENT )?' su I =, "m L J

Attachment I Mr. Ilarold R. Denton Docket No. 50/395 December 28, 1981 1. Evaporator bottoms. 2. Onemical taooratory samples. P(.. \\ 3. Spent resins. 4 Used filter cartridges. 5. Radioactive hardware. 6. Compacted waste such as. rags, paper, clothing, etc. IN. SERT /)A (~ [ iners holding high level solidified radioactive materials are stored their individual shields, within a concrete cubic c grade. Contal holding low level wastes are stored ~ their individual shields, ' quired, on a mezzanine or 11 feet above this area. They are lifte 10 ton, r driven trolley and crane which locates containers in this The filling, flush" solidification proce erformed auto-k )( matically o e manually from a control panel in a ded room. e Figur -1 is a flow diagram of the system. A layout of th rea is n by Figure 1.2-25. i- 'j Design quantities and activity levels of the various wastes are listed in Tables 11.5-1 through 11.5-4. 19-11.5.3 EQUIPMENT DESCRIPTION 11.5.3.1 Processing 24 The input to the solid waste system consists of the contents of fo'ir radioactive waste storage tanks containing waste evaporator concen-S trates, chemical laboratory samples, primary spent resins and nuclear blowdown spent resins and the associated valves, piping and pumps. These co=ponents are located at elevation 412' in the auxiliary building I 14 except for the chemical drain tank which contains spent chemical labo-Af ratory samples and is located at elevation L ' of the auxiliary build-ing. l TasERT Secen dary side condensde polishey resin may also AA l be handled by de sop d was te system GeVec to 10.4.6), m\\ 19 l 11.5-2 AMENDMENT # ~ga

g, L

}

Attachment I IiVSE~R7 A Mr. narold Denton Docket No. 50/395 December 28, 198 chemical processing area is located on the auxiliary building mez-za ine floor at elevation 447' to locate as much t wipment as possibl in a onradioactive area for service and maintenance purposes. The follow g equipment is located in this area: 'l. The ur formaldehyde concentrates (UFC) storage tank whi 6 contains a-urea fo idehyde, water and a small amount of a proprietary additive. is mixture comprises the solidification a ent (SA). 2. The urea catal t storage tank which contains ammo um sulfate, prilled urea, wat r and a small amount of a propriretary additive. This mixture compri es the catalyst. 3. The sulfuric acid stora e tank contains the e Ifuric acid which can / be used to lower the pH o liquid waste bel w 6.9, if required, prior to packaging. 4. The chemical process module whi h contains'the catalyst pump, UFC ,. / pump, valves and piping to direct th SA and catalyst to the waste 3. container. v t 5. The sodium hydroxide storage tan con ns sodium hydroxide which is used to raise the pH of the liqu/id waste bove 6.0, if required, prior to packaging. M Liquid waste is routed to a. waste blending tank ( T) prior to packag-X / ing, where the liquid is recirculated through a pH eter by a recircu- / lating/radwaste pump. Sul.furic acid and/or sodium by roxide is added to / the WBT as necessary to/ adjust the pH of the tank liqui to within 6.0 to 7.0. By appropriate valving, a sample of the WBT cons ituents can be / obtained to demonstr' te solidification capability as requi d by NRC a / regulations. The'WBT is equipped with a mechanical mixer to naure a f homogenious mixture for sampling and for greater assurance of lidifi-ThelWBT is also heated to permit close temperature contr 1. cation. Therecir[ulatingpumpislocatedinashieldedcubiclebelowthe / and adjacent to the fill area at elevation 436'. The WBT is located n \\ the' floor above the pump within the same cubicle at elevation 445'. II.5-2a AMENDMENT g 7.9 m_ ._b

Attachment I Mr. Harold R. Denton [/Vj { /{ { j} Docket No. 50/395 December 28, 1981 And waste so li d;T,' e n t;c, is a ccompits4 ed osty n po r table ceme, t scl;d:V;en t,'on pro cess scyp l,'e d Li uid tvaste b Chem A/vc lea e S sle ms In c. 7 ( y y con fatu e d

e ibe C h e mic al benin 5k and (Naste Evapo<a to r C on c e n h a fe.s in 8 k is eee
c c s la te d usin3 ffeic ve sp ec t;ve p u-ys

( 7%;s sam is Asyn ~ple sayle is taken and a to use d in 14 e hvocess Cont <c/ 28 de tc< min e ah a djustm e n f, waste /1;nder tai to ( a n d, %,th e,o rpose u o? fest solidi c ic a fion, L;7u;d wasfe is frans F'e7e d' io fhe ??// h ee d an d

nto f4e

/in er /ccate d' ( tfe so/id;Fic a five area. Con-eef p H ro y e m accomp/uded 14e fe s f so /;di Pie a fib > is based on by addiq calcium ly droxide boug h 1Ae 7,w heg d to the I:ne r. A v ik cem e,t an d en /cium b d<cx;de a< e s / ore d in a bulk feailew y ou 15 d e fle A uxiliary Building fruek access. I 6 +4 e c c.sn d i fic 8 ;9 ehe m ic e f s may be aHe d iT n ecessq<y 2<0~ f4e c on difto nig c he micg/ tw k ed fems D ( er,ou~p. l [1,5 - 4 6 hrM ~ ^

Attachment I Mr. Harold R. Denton Docket Ne. 50/395 --December' 28, 1981 e WBT provides a means to accomplish the following: } k' l. Tho ghly mix and homogenize the waste. 2. Add chemica for pH adjustment. 3. Control radwaste tem rature. Based upon solidification data plied by the process manufacturer for various chemical solutions, the c'or et band of ratios of waste SA and catalyst is selected. .k9 The control of waste material content before dition of SA provides the means for assuring mo/re consistent results. Whe the radioactive waste solidification fil operation is terminated, the ma rial within the / containerisaflowedtosolidifyandthenonlySAand talyst are added to seal thef op surface of the solidified waste, t t[ The dedatering module is located in a shielded cubicle on the a iliary , building operating floor (elevation 436'). It-consists of a resin k(urrydevateringpumpandtheassociatedpipingandvalves. Primakc fran s Fe{ red and S econ der sp en t resin s are e; r res,0cetve hold up iknks to eilber q Team a;5posable linee in k solid) Pication aren er et line r whic h i.s q/ read in a cash re ady for fransporf y r^ny then be eifher M d. in ih e fruc A by. The resin s solid; Vied or dewa te:re d for shyrnent. Bewa ter re tven is threqh the - b d r ': pip;ng process shid h the de watec c onn e c tio n in fhe .so7) di Fiu tion area <md (. From. the re to aiMec +h e Exce ss Lqu;d Waste the Spen t Resin S fo<a3 e Ta n K. lleid sp Ta n k or Eac h wasfe t<msVee is bn n e dlale/y q'ol/ owe d by Dush opera fim, o7 the waste transfer p pn3 and ( a fAe. inferno /s o? Ybe. W// heo d. AMENDMENT [28 11.5-3

e { Attachment I ~' Mr. Harold R. Denton Docket No. 50.395 'cemb er 28, 1981 Labyrinth shteld wa)tue1s separate the drumming station contro room, the pmcess snd cos l _ pir,$rr! y -iul:- and tbe container fill area from one another. l g7 19 Equipment is described in more detail in Section 11.5.3.2. 11.5.3.2 Equipment The equipment comprising the solid waste system is described in Sections 11.5.3.2.1 through 11.5.3.2.7. Table 11.5-5 provides equipment design Refer lo CIV S.E Op e m t;,5 P. ece do, e : decom en t parameters. SD-oP-020 and 9/od diayam 313 - 210 / - E01 11.5.3.2.1 Waste Storage Tanks and Pumps 19 l Tanks containing radioactive waste and wetted parts of pumps are fabricated from stainless steel, type 304, except as noted. The chemical drain and the primary spent resin storage tanks and pumps are described in Section 11.2. Other radwaste tanks and pumps are the waste evaporator concentrates pump, nuclear blowdown spent resin storage tank,gnd r nuclear blowdown spent resin storage tank pump, r f th_ "'?. P.: ""T 1. 2,7 l f: brie:ted fn i.yr 210 t R. lese etccL b 11.5.3.2.2 Chemical Storage and Process Equipment SA, catalyst, sulfuric acid and sodium hydroxide are stored i anks DEEAT in a che al storage area on the auxiliary building mez - e floor at b elevation 447, bove the drumming control room and ill area. A chemical process modu s also located i area, with appropriate valving and pumps for directin to,th'e waste container, or sulfuric W l acid and/or sodium hydroxide to t(e Containers of dry chemicals .for addition to the SA or cat yst tanks are o stored in this area. ( The SA (UPC) and cataly tanks are of coated carbo teel construction, / whereas the sulfuite acid tank is constructed of 316 stai ss steel and the sodium hy oxide is fabricated from polyethylene. ( The chemical process module consists of the following skid mounted / l _.e 9.u t pme n t - l 11.5-4 AMENDMENT)( .-JUNE ;--l-980-

ttenel[4 #sers=

  1. 9

( N U*w.er. N.f*/19f ? U**H hsr 53, s 9 s(t 1/VSER T 8 fTo P~r d.r-b LIk cemen t an d en(crum b dwxi o e are s fece d - 'l y in a bulk +ra ile c loc a fe d outs (de f4e Aun %'esy Buriding. hoe k a c' cess. A p n eu~a fic. fpe y cemen f con vey or loca te of in fbis same aren, +v nsfers 14e cement fArough a fruc k a wall pene fee fron to a portable access are a hose lea dinJ to f4 e F;// head. TAe Pm A Ul U so/ia iVicefro8 head nceina fl lace fe d in ibe l y a lony w;f t ffe bydcauIic. unif. i area ro skid con fain s fAe?wYsfe The bspin3 hve, cess fran s ?e r va radmonitor, air an d wa ter con tro l Valve s, an d dewa+eeing pu,.,p. The pip;y process skid is locafe'd inside fhe shieIde d cubicle of il>e solid;Picafhn area. A wall penefra fion In this shielde d cubicle is loca te d 40 reduce exposure in the fruek access an d to allow Tor connecfin3 e7vipment in fbe truck access \\ wiIb eyuipmen f in the solid; F;ca + ion area. The con dii108183 chemical.stora3 e and process l area is locafe d within a curbed area in fde +,oc k ac ces s. Liner ven tilo fion eyu/p meu f is bocafe d in curbe d areq in Ibe fruck a access, The di.s c h ar3 e 3' rom th e lin e r-Veni) laf10n e.yvipm e n t 1.s d1recte d to the p ku t ven t. NmwbtnEivr 2.<1

Attachment I Mr. Ilarold R Denton 1 SA pumo., Docket No. 50/395, December 28, 1981f / 2. Ca alyst pump. / 3. Flow d ectors to indicate solidification agent and catalyst flow. j 4. Pressure sw ches in pump discharge lines. ,W 5. Electrical termi al box. 6. Associated piping. , [(. 11.5.3.2.3 Radwaste Module The radwaste module consists of t e following skid m'ounted equipment: 1. Liquid radwaste pump._ 2. Preserve switch in pump discharge lin 3. Flow detector for radwaste flow. 4. Three motor operated valves: one to admit th WBT effluent; another to recirculate the WBT contents; and the last t discharge the WBT y effluent to the disposable container. / 5. Electrical terminal box. / (~ 6. Associated pipin ,/ 11.5.3.2.3.1 Dewatering Module The dewatering module consists of the following skid mounted equipme t: 1. Dewatering pump 2. Flow detector for dewatering flow. [ AMENDMENT)( 11;~5 -4ct;z, 1980~ Mr. HaroldWDentor} 1 DocketNo.,50/p95 Preocura twitch in pump suction line. Decembe A 8, 1981 4. A motor ope d three-way vals~ to admit water f the WBT or the (- disposable containe 2i 5. A manual valve to isolate the-pump. / 6. Electrical terarnal box. Associated piping. l %j 11.5.3.2.4 Instrumentation and Controls 'Ihe system uses temperature, flow, pressure, and level instruments to monitor and/or control the process located throughout the system. 7"l1e in 4n-edditionr-therefloh f is-a control panel, power panel and radiation monitor gre located in the drumming station control room..A-descr4ption of Gese-D last-itcm: ie as-follows?. 77/)e C /VH C0h'[ec / 0 om e / J'5 -a/.c0 / lcc<tfc d In 5N Sam e G re 9. .( In pki -1. /1 Control Panel inpknh The # control panel is a standard enclosure of NEVA 12 construction. - A fouctien:1 fic; chart chcuing velue pecitione, - pumps,--eterr-is- -presented-on-its-face. 'Ihi-s-provid e e a-vi sual-pr4sena r i nn--of- _sysram par f ar= mace and-gives-the-operator _ful-1-unde rs t anding-o f- -current-sys tem-s ta tus. The control panel is designed to provide a av of operational controls and safety limits. All -ths/ required ~ for manipulation of the-sy / solid-state cir stem is located ( / within the panel. Manual ov is ded to allow for system / mal function corrections or' 1 operat of the process. Z1 ( The control panel provides proof circuits which indicate t the various valves are properly positioned before the reg'iired pump / f[l >ystart t and that the pumps are operating. 'The inplet conk / pan el pov; des ?vil opeca b m/ cc hel q uakc to l h e~l " k W# . % resm and lipd waste knsYec ment. It is nise vsed Io I'lY$fa't WiIh " *"3 'S u W me t ecc s e w a te, r.c n c n a, a e c c - ~ =. Im-i'Ivahiy operaticus.

Attachment I ~ ~ Mr. Harold R. D:nton 2. Power Panel Docket No. 50/395 De'cember 28, 1981 The power panel provides power for the operation of the various pump r( 19 motors and valve motors in the system. oof of Flow Systems Proof of flow uiery and solid-state thermally actuated r w switches for the dewat g, waste, solidifiestion ent, and g catalyst lines are iurnished. nals fr e flow switches interface with the solid-state co = nel to provide a method of M (.- pr.eventing either operati of the pumps with liquids present so that the pumps ar ot damaged by being run " dry" or ssion of one of the th components required to make a solidified mass o y oactive material in the disposable liner.

s. A v tona tie in tecloc ks, alarm.s,

an d con mis ex?st to peven+ improper opera fron of the eyu;omenf. The.sc. include : . i Confrol bower j . 7;tl head pressure alarm Wil head position a larm \\ h:3 h leve.l alarm i cemen f level q larm wasfe /evel alarm hig h - 6 4 /cvel alarm 3 lin er level in dica tion L waste valve con frol e in bea tion mixer speed in dlea tion /ow S/eed a/qrm l( h:3 h an d low oil fe npera tore glae n,.s -?;il head tempeca tore a la e m. los oil lesel alaem [ e m erg en cf S fo/) (

2. Y 11.5-6 AMENDMENT.1 7

~ A 980 ' l

Attachment I Mr. Harold R. Drnton Docket No. 50/395 De^cember 28, 1981 4, Offac co ois ani indications inclod'e : 4;11 head light a Ttt ea,meno. cyclon gice panel wei.h t sen te. cemo,1 3 hy dca uItc maton con frois con h tton in3 che>8;calpoing counfer ecomirols main air controls Wa S $e Veh f l3loweh coh fra Is cain e ca ? lush con tro ls ae ra fro n blowe c 2 ce>,en f blower cos, fro ls liner fe~perafure re cor der liner si2.e selee for s witc h mixer mafor co>, tra is d e w fe e po1~p con trols a main aie peessore in d:ca froi, vesse I p ces sur e indieation supp ly pressure in dice t ion vent it/fer bFerenfte/ pressure vane alc pressure re3 ala foe sin dibo fios,. de wa te-c pomp air pressure regulator e indication Con difichiH3 poinp air fressure regulator e indicolhs Galnera alr indica fion an d confrols (ill l1eq d coo ling Gir indic 9 tion & Coh lro/S i l. 5 - (c n.

Attachment I Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 4. Radiation Monitoring lDv.5ER T C ( ( radiation monitoring is loca.ed on the wall of the control cubic ~le' to ert the oparator in the event of excessive radiation. In Jf' additi two radiation sensors, one measuring the radiationdevel- ~~~ at the con iner or shield surface, the other measuring' / radiation / six feet away, re located in the container f rea. These are connected to a ra

  • tion monitor located on op of the control panel.

There is also radiation senso located near the WBT to measure radiation level in he WB cubicle. The radiation monitor is located on the control pa If excess radiation levels exist, an alarm.is sounded and e fill op ation is automatically gf terminated. If this ccurs, a decision n be made to either dilute, ship a s Ier volume and/or provide dditional shielding. The radia on sensors in the container fill area als serve to l segre te filled containers by radiation level. This pe 'ts some 1 specific activity (LSA) shipments to be made. ,o ."x The radiation monitors are in addition to those discussed in 14 Sections 11.4, 12.1.4 and 12.2.4. 11.5.3.2.5 Waste containers and Shielding Compacted wastes are packaged in standard 55 gallen drums. Other wastes are packaged in 50 ft3 containers having dimensions of 4 feet in diameter and 4 feet high or other DOT Type A containers. -Thc-conteiner-g l -t^p h:: previsica tc conocet c = ster-t+-an-internal,-disposable-mixer.- g i i Tillhea d j Quick disconnect fittings are located in the centn M top for the 1 following:

  • ENSER T D 1

enting from the container through a filter to the plant exhaust' system. 2. Admissi n of liquid waste to t'..e container. X r n z7 11.5-7 AMENDMENT,1f 4UN E,-4980--

L Attachm:nt 1 Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 g T/VSER T C to pa e it. 5-7) s Raella tre n montfe,-;,3 is prevede d by 14e vendor s eyv;pmen t _ -Pc / lowing are a.s : in ft, e Y I. was te. i.sc /q fra n v'q/ve of ff e p,p;n3 preces s skrd 2. line r -Trll he a d. B. Con tro I room. Radmen tfor-R M-766 2 is porfable -Por use in either %e solidificafton area or + ruck hay. Ylis nadmonitoe wEll larn an d ferrninafe a Pill opera fion by closin3 vaIves Alo v-2 2.IMOV-5 if iis setpoint Es excee ded. a TivsER T b l. bewa ter fl,covy h c< filfen haek fo L Excess L;yu:d % s te Held qJ Ta n k or Ta n k. Spen t Res;,n s tes ay e Jy ecxide Pill connec ften d_ z. cemen t Calc;u.n 3 ccnd:fioning che>~,ica/ s99 yl 4. t/en f to WIfers etn d p /5 t Ve n i ?lus h. S. Eadwa.ste sq)ly kP!EADP1EtJT 27 vwws .;, w w,n n

3. missior of SA to tha ce nr. Docket No. 50/395 4. Admission o ata st. M ~ 5. Admissio of air for s ging. 6. watering of resin slugy. T/VSER T 2 l T/1e. pro ce.s sin 3 09 mesY OT lbe h/Qsle Volume will be in tXe solid;* ice from area. This area is enalose d on he e. s; des b i y shieldti9 ~lls s d ' includes a-walls ' for con tain spi A movable shield curb to be brou hf ih iT " add; fioneI shieldig may reyvire d.3 Hig y acfivify wa.s te.s - piu is ~ p racesse d with % lin e e airer dy in fbe be. irahsport cask located in the 'fruck access area. A double lid ens k top will be used fo Iim;f ex 00sure in th1s areg. The main pac t,o? tbe lid shieMs the edire i fop o: tbe cask excepf k imme dig te rey viced f' r f4e F/// hee d. M/e r o a re q process is. complefe, the N/I head )S re mode. N Qhk $b t .SYCondary ORS k l lid is insfalle d. b remde Final closure oV all ra dweste liners i.s y handlins e7uipent. Caebon sfceI linecs ave seale d, t by a %y raulic barrel te,0 crimper, iltyi, integ,gfy d are sea le d by q dev;ce which screwg con fairlers the. c.lo sore cap info the lin e r. II.6-7e ArnENp/hENT 2'l

Attachm:nt I Mr. Harold R. Denton Docket No. 50/395 December 28,.1981 i 19 T e expected container design for packaging radioactive filters and hard 3 ware a 50 f t container having a removable lid and a centrally located basket in which the filter or hardware is lowered. The lid is'/then re- / placed and lig d waste is packaged and solidified in and around the / .m

basket, ggg y When the radiation level of t waste requires shi ding, the container gf E-is completely enciosed in leed sh ds havin 1/2 inch or 4 inch nominal thicknesses. A centrally located shi plug, approximately two feet in diameter, on the top of the shie,1 plac in position after filling by a pendant controlled overh b crane.

When the Curie ntent of radioisotopes packaged within container ex- \\ ^ ( ceeds D0 rescribed limits, the container and its shield a ackaged (

wi in a DOT approved overpack for transport to the burial site, 11.5.3.2.6 Contamination Control Facilities An adjacent decontamination area is provided for cleanup of contaminated containers. Exposed surfaces of filled containers or casks are surveyed by the health physics group to identify the presence of removable radio-active contamination prior to transfer to storage or shipment.

Containers m are decontaminated in the adjacent decontamination area, if required. I 11.5.3.2.7 Handling Equipment han dlin e q Vip'"'" l m ( Equipment used forympor41 g-the-waste containers and shield within 2-Y the radwaste area.and for truck loading includes the following: m ( 27 11.5-8 AMENDMENT. W _ JUIC, 1900--

Attachment I Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 -1. Lead pullet. z7 2. Load-pa14et-and-pe rs onnel-s hieltir -1V -3. --Lif t truck.- 4. One ton jib crane. 5. Ihree ton jib crane. 6. Ten ton bridge crane. 7. Wenty ton hoist and menorail. 8. Three ton bridge crane. 9. Ten ton bridge crane. ,\\ 'q^The wastAcontainer and individual shield, if needed, are placed on-a j 7-pallet by the ten'ronJtrid e crane in the hot machine, shop'~or by the k \\ / overhead twenty ton hoist. If radiatio o level of waste to be pack-additional 3 inch thick aged is expected to be high, a palle stainless steel shield, -11 or additional p on 4f the operator. The waste c tainer, shield and pallet are transported withi Tadwaste 14 elevation 4 36' by the lif t truck. area'a l' (. The one ton jib crane is located on a wall above the truck access floor at toi elevation 435'. It is used for hoisting chemicals and equipment.f-rom the truck access areagto-the-mezzanine floore It has a lift of 23 feet at a . ' '19' N speed of 22 ft/ min. solid;Vica t% The three ton jib crane is located on a wall above the container-fill- ~ M area.] I't 'is usedTo~femove ~atid replace tE[ lead shield from the topf M n ont= % r. It is also used to support the filter transfer-leiid cask l 9 while transferring a spent rtrid e from'th to the con- -~n5ERT The flexible rubber hoses /, used when fill hg-a-container, are T tainer. /~ N F also connected-to this crane for removal of the hoses from the container.,, etion of the filling operation. l It has a 23 foot lif t at a uport w- ,( speed of 11 f t/ min. I/$ERT H is vsc <] fc })a n c}lc j],' V'"gd'S l'dI heac/ i n F a*g oflier eppmen t. p e 11.5-9 AMENDMENT # -JUNE, - 1980-

Attachment I Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 compact;ble e run-compnet;ble The ten ton bridge crane is used for transporting m2 t: conceinew h/457c -cithcr with ar--whhcut : 1-1/2-inch-1ead-shieldrin the low radiation j l level s torage area at floor elevation 447'. It has a lift of 14 feet at a speed of 11' f t/ min and a' trolley speed of 65 ft/ min. W k 1he twenty con hoist and monorail is used 2: h ackup -Jor-the-1-14t-t-ruck- ~ to load the containerSanAsh-ield, if required, en either-a pal-let--or--

2. 7 on a truck for transport to a burial site.

It has a lift of feet at a m. speed of 10 f t/ min. ( The three ton bridge crane is located over the radioactive filter area at floor elevation 463'. It is used in conjunction with a 3-1/2 inch thick lead filter transfer cask to remove spent radioactive filter 14 cartridged from the filter housings located in concrete cubicles on the floor below at elevation 452'-6". The trolley has a transfer mechanism which permits the hoist and the cask to engage a monorail which extends over the radwaste fill area. A hatch at floor elevation 463' is removed and the hoist lowers the cask to the radwaste area at floor elevation 436'. It has a lif t of 47 feet at a speed of 22 ft/nin and a trolley speed of 65 ft/ min. Another ten ton bridge crane is located in the hot machine shop. It is 14 chiefly used to service the machine shop. However, a portion of the floor area in the machine shop is partitioned from the rest of the shop for storage of unused containers and 55 gallon drums, pallets, e fC. I j y/ .shielde md the eve m @. The storage area is also serviced by this crane. f The hoist has a lif t of 24 feet at either 7 or 20 f t/ min. The trolley has a speed of either 32-1/2 or 65 f t/ min. e( 11.5.3.2.8 Waste Compactor An electromechanical compactor, with a compressive force capacity of four tons, is used to compact dry wastes into 55 gallon drums. During compaction the drum is completely enclosed. A self-contained HEPA filter e\\ z7 11.5-10 AMENDMENT -# --3uu, a n

Attachment I bk. Harold R. Denton Docket No. 50/395 December 28, 1981 and blower system filters the air released in the compaction process before it "is discharged to the auxiliary building atmosphere. An elec-trical interlock prevents operations of the compactor if the door, which encloses the drum, is not completely closed. This prevents injury to the operator and unfiltered air from escaping to the auxiliary building atmosphere. This compactor satisfies Occupational Safety and Health Act (OSHA) requirements. 11.5.3.2.9 Truck Loading Features A wall penetration is provided between the. fill and truck access areas to fill directly to containers on a truckpxcess wasa osu ulates. Was l yf chem d vent lines are provided with qui com cts on both sides of the wall. e wall is stepped to 7_7 = ir.a eie ie a +ihua+, permit two,..u. f stee =:n e ' tion is ie ' - t Th;s Pene tia loca te a in th e s8;elded cubiele or thi solid;fY-- cation area such fnat exposere in }he truck acce.ss is limite d. 11.5.4 EXPECTED VOLUMES Y ( The expected a.nual volu=e of solid radioactive wastes together with the associated Curie content of principal nuclides to be processed are des-cribed in Sections 11.5.4.1 through 11.5.4.4. 11.5.4.1 Activity Levels The activity level of the vastes generated directly from operation of the nuclear steam supply system is based upon reactor plant operation H at a base load f actor of 80 percent power with reactor coolant activity levels determined on the basis of fission product diffusion through cladding defects in 0.12 percent of the fuel rods. The system is con-servatively designed to accommodate solid wastes generated by plant op-p erations with up to 1 percent fuel defects. Source term data used for system design are presented in Section 11.1. m ( '27 11.5-11 AMENDMENT.-W - = = ~

Attachment I Mr. Harold Ro Denton Dockee No. 50/395 December 28, 1981 every six full power months of cperation and that one of the three nuclear blowdown system filters will require cartridge renewal, normally for high AP, weekly. All other filterc are assumed to be renewed annually. These replacem'ent rates are approximations only since suf-ficient specific operational data is not yet obtainable (see Table 11.5-4). The maximum expected activity of expended filter cartridges shipped from the site is conservatively based upon a shielding criteria of a maximum contact dose rate. 11.5.4.4 Miscellaneous Solid Wastes The annual volume of miscellaneous solid wastes processed by the solid waste hydraulic baler is assumed to amount to 350, 55 gallon drums of l3 compacted refuse. The wastes consist of rags, coveralls, ventilation filter cartridges and various other potentially contaminated refuse. The activity of this refuse is low level and does not present a radia-L.i', tion hazard (less than 1.0 Ci/yr). e 11.5.5 PACKAGING 11.5.5.1 Evaporator Bottoms and Chemical Samples Evaporator bottoms, concentrated to 12 percent, or less, boric acid in 14 the boron recycle or waste evaporator, are stored in the heat traced 5000 gallon vaste evaporator concen at tank. Lines from this tank discMme s aste cratmi valu me h 1> v a (- to the M T P 4 eleo-heat-trace p ~nemical samples are stored in a 600 -M. o gallonchemicaldraintank,jWhenasufficientquantityhasarr.umulate-d' m IT5r pa7,urgingga unnte is transferred tghe_WBT-in'b of 700 gallons or less. This.vaste 6 5Ae~w111 fill h tainers ,14' f when solidification and catalyst chemicals are added in the normal ~ INS ER T mportions. / G I \\ 27 11.5-12a AMENDMENT R Jr :,Po J

Attachm:nt I Mr. Harold R. Dinton December 28$3[ Docket no _ #M F G (t. f.y 11, S-it ) idhen a soTTte;e8 t c) van 1 sty has a ccov>, ula fe d ih si/ hie waste ' tan k ifs coasten fs are recirculafed -{'cr 41 least hvc Vo /um e c b a y e s cr n d a sample is Yahen. The sample is use d by The P<ccess con troI broya m Tor tes t se/MSich. h A yfer sampling, the was te volum e s are then frans?ere el to the Ven dot s 69UEP"en f for p ro cess 13 / e d a

Attachment I Mr. Harold R. Denton Docket No. 50/395 liquid waste is recirculated by the recirculating /radwaste p@nh**dile 28, M 81 started to thoroughly homogenize the waste ! the echanical mixer is This p ocedure also emulsifies or holds in suspension small quan ies of other astes, such as oil and anti-foam agents. Sulfuric d and/or sodium hydr xide can be added from their respective tanks,

required,

'~ until a pH me er in the recirculation line indicates a s dy reading of 6.0 to 7.0. A mple can be withdrawn for analysis if equired. Based upon solidific tion data provided by the proc ss manufacturer for various chemical analy es, the desired waste temp rature is maintained by the WBT heater and th correct band of ratio of waste, catalyst and SA is selected. In additi , small samples a e periodically solidified using the selected proportio to assure complete solidification. A radiation sensor located in the WBT cubicle is used to determine the size of the lead shield required fo t 50 ft3 container. It is Lf anticipated that the 1-1/2 inch thick ead shield will be more than adequate and that in many cases no s/ hie ing will be rep ired. The container (withorwithoutshield,!asrequred)onapallet is located / in the fill area by a lift truci. Five conn tions are made to the N f container with flexible wire an/d fiber braid r 'nforced hoses designed for 1500 psig (6000 psig min / mum burst pressure). These hoses have quick disconnects and are enclosed within a fill s " eld assembly. An electrical connection is also made to a disposable 1 vel probe and temp-erature probe within thd container. The hoses are conne ted as follows: ( l. Vent to the auxiliary building exhaust system. 2. Waste f om the WBT.

(

3. Sol'dification agent. 4. atalyst. I p. Station air for sparging of the mixture. AMENDMENTJ9' M 11.5-13 t JNP, 1950 ~ g

Attachment I Mr. Harold R. Denton Docket No. 50/395 [ De c_emh_o r ?R 1981 I e control panel is placed in the fill and solidify mode and fill flush nd termination of flow are done automatically under con ol of a level prob in the container. Provisions are al.so made fo automatic flushing of lin from the radwaste module to t'ae WBT d to the N container.* Radiati mohitors located at the con iner (or sh'icid) surface and 6 feet away cuate an alsrm if e radiation level exceeds that anticipated..Should an larm be a ated, the operation is automatically terminated. A de 'si is then made concerning dilution, [f shipping of a lower-volume or vi *on of additional shielding. f r The air sparger is.sta ed and waste is pum d by the radwaste module from the WBT to th disposable container. Flow s stopped when the container leve probe indicates the container is 50 60 percent full. M Equal propo mions of catalyst and SA are added to fill t container and the air parger stopped when solidification reactions increase e Normal proportions of waste to SA to catalyst are 2.5 bac ressure. o l to 1. ( r ( t 27 11.5-14 AMENDMENT 8 m i

Attachment I ~ Mr. Harold R. Dentori Docket No. 50/395 g Deseh r 28. 1981 y Th

  1. ~ve flexible hoses and one electrical lead are disconnecte chains attac to the overhead jib crane wh snaps the g

quick disconnects free. fill shiel a m ly is removed and the lid shield is installed on the onen n hield cask by use of the pendant N controlled jib ne. The container is auto 'cally sealed when the 1 C disconnect are freed. The filled container is store storage area un ti-puent. / 11.5.5.2 Spent Resin Resin in a demineralizer is considered spent when its decontamination factor falls below a permissible level or the demineralizer surface dose rate exceeds its limit. The spent resin, from demineralizers in the 3 primary system is stored in a 350 ft storage tank. The spent resin 3 from demineralizers in the secondary system is stored in a 600 ft nuclear blowdown system storage tank. The resin stored in the primary system is allowed to decay for a period of up to several months but not less than 30 days. The resin stored in the nuclear blowdown system f storage tank is surveyed to determine the minimum decay period required. This period is expected to be less than 30 days. When a sufficient quantity cf resin has accumulated and decayed, the resin is saepled for radiation level and packaged. Prior to packaging, resin sluice water is recirculated in the tank to form a slurry which is Iin e.r f transfctred to the jWby nitrogen cover gas pressure. Devatering of the resinjsfTer-f-a.Q the WT is accomplished _through_a-filteinn W3T4 -OthMid radwaste may be added to M T. ( is a ccomplish e y using tf e ven da,1, ep;p m en t with f4e wa h,~ bety re tun e d 29 eilbec to 'fb e 2 x cess L,yu;d was te Mc Mup 1/> e Spent Re sin S ferq3 e To n K, Tank or q-Syn + resin may also be so l,'dG,'e. d, 'Lf 11.5-15 AMENDMENT 8 ._, JUNE, 1980 - g

Attachment I Mr. Harold R. Denton Docket h sn /'195 December 28 19 / W illing the container with resin slurry, an additional flex *, ' n must be made to the container for dewat g the resin { hose conne t slurry. With this nection, six hoses are no onnected to the con-tainer. Filling of the co ner with r n slurry and dewatering are performed simultaneously. When t ntainer is approximately.50 per-N cent filled with dewatered in, the fill y ration is terminated. The resin is then solidi ~ by the addition of SA and alyst as described in Section 11 .l. The air sparger is operated continuo -during 19, r th e f. operation. The radiation level of the primary resin is expected to require use of St-ht 4 inch lead shield on some occasions. The radiation level of the 27 nuclear blowdown system resin is expected to require not more than eht O 1-1/2 inch lead shield. The primary spent resin storage tank has a two inch dischcrge line. located along the tank center line, protruding from its top and extend-ing to within 3 inches above the dished head bottom. In preparation for packaging, the discharge valve is opened and the center discharge tube cleared by backflush with a burst of flush water from the reactor makeup water system. Pressure to 100 psig is available, if required. Plush water may continue to be added'if needed to obtain a reasonable slurry. -The discharge valve is then closed. Loosening of the resin is achieved l by introducing nitrogen through seven spargers at the tank bottom. Resin sluice water can be recirculated through the spargers to loosen the resin if desired. When the nitrogen pressure increases to that required'for ~ resin transfer, the resin discharge valve is opened,- ' " - -- 2 " -- -fer to'the "T hr h eel ed-jus tees as acccr eeryr Nitrogen continues { to bubble through the re, sin bed to maintain a gas pressure for transfer M l.ner of the resin until the SBT' reaches the full level.. tac //<1er Ved d.%$ flis operatien is derec te d -h> h plan t Ven t. l l l The nuclear blowdown system spent resin st'orage tank is discharged by use of a procedure similar to that used for the primary spent resin l ( 27 11.5-16 AMENDMENT,1( 1 l ..-mVM--

Attachment I Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 storage tank. The resin slurry is discharged through a 2 inch nozzle located at the tank bottom. Prior to discharge, this line is flushed k-with resin sluice water or demineralized water. The resin sluice pump 19 is started to loosen and fluff the resin. When a resin and water slurry is established within the tahk, nitrogen gas is bubbled into the tank bottom pump suction connection to loosen and mix the resin and pressurize the tank. When the tank gas pressure increases to that required for resin trar.sfer, the resin slurry discharge valve-ta A m. f is opened. Operation of both tanks from this point is similar. ( vpn com mMcath from +he vendor hi 1h h-ensFec is compete JInon vacaipt ef : :;ig.:1 fre-the level-probe-in-the-WBT, the resin 2.7 discharge and nitrogen supply valve Aclose and a tank vent valvedpenec/ d to discharge the nitrogen cover gas from the storage tank. In addition, the flush water supply valve 4openir& IS to backflush and forward flush and decontaminate the resin transport line. A flow diagram of the primary resin system is provided by Figure 11.2-2, Sheet 3. Figure 10.4-15 describes the nuclear blowdov, resin storage tank. A flow of approximately 40 gpm is required to transfer the resin slurry 27 liner

vy-to the SBT~in the radwaste area.

It is anticipated that approximately 3 3 1300 sto ft and 2200 std ft of nitrogen gas will be the maximum 3 required for each resin transfer operation from the 350 ft primary 3 resin storage tank and 600 ft nuclear blowdown resin storage tank, respective 1'y. . Actual gas pressure required, as well as system operation will be verified using nonradioactive resins during preoperational testing.. (- The nitrogen system is set to supply nitrogen to the resin storage tanks at a pressure of 100 psig, if needed. The resin storage tanks are designed for 150 psig. Relief valves on the primary and nuclear blowdown af 11.5-17 AMENDMENT. W _ p &;-1980 )

Attachment I Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 resin storage tanks are set to relieve at 110 psig and 140 psig, res-pectively. The primary resin storage tank relieves to the waste holdup tank. The n'uclear blowdokn resin storage tank relieves to the nuclear blowdown sys_ tem reservoir by way of an onen dra_in. E 11.5.5.3 Filter Disposal Filters are of the disposable cartridge type contained in housings having hinged tops. They are replaced when surface dose rate or pres-b

  • sure drop exceeds established levels.

Filters which are potentially radioactive are. located in individual cubicles in an area close to the . drumming station. area. If the radiation level of the cartridge requires a concrete. plug in he floor above the housing shielding during removal'JagJ w i n a t w l,e ir, i es-ofdced i Me s ed cDcnl,)' g? is is removed and a+.,f_nen~ p 1o ta-ih-eada ncased 1:cr cc , eith F1,2 in tamless. steel is placed cier lead e., cased in $ocat-ed-in-the-stepped-opening.the Juje A. 7;i}e(p<m s k lyith 3 %.",e ttcia ca r eruoved ;--is-e t e e _ -and-i-ta v The filter housing is opened and the cartridge is drawn into the cask Pi by the use of special tools having extension rod l. 9_ha,cq"ise - t te< is The e tej s ~ ia,stgjled ia, pincg fe cafk bertem is slid cine and th o cask-is lifte

01...- e l e e _,o-less-viewiw-t-in-t-he-to p.

.equ w em ne - The cask is then trans-c h'e$e a d'nd-i tS-bo t-to m-is--a ttached,- J' * -er hem _ cmne by Ar) portedAto a hatch at floor elevation 463' of the auxiliary building. This hatch is located above the drumming station area on the floor be-low. The cask is lowered into the drumming station area.-i_~-....._} / removed and the cask is raised above a shipping container by a 3Aon jib er Filters with high radiation levels are placebin a con-tainer of specia inn which has a centrally ed, perforated basket into which the filter idge owered. The filter cartridge .[NSERl 1s detached from the grapple after 1 within the cask. Filters [ with low radiation e s are randomly dropped into c t4 ners used for liquid wa The space around filters with either high or low r c. 1s. mis ir fillcd ith-- liyuld,.mc,sh44h-4c salidifiede { 3 g,ig pr 27 - 11.5-18 3 l

Attachment I Mr. Harold R. Denton Docket No. 50/395 December 28, 1981 rivsea r t (+. e.,<

11. 5 - Is <.)

.skry e a n d dr.sposal oV all P;Ifers is wiffin eifber h;gh inteyity containers or DOT approve d 55 3allon drums depending on 1 heir curie con fen f. For D /fers reyuiriny i shieldin3, the con +aine r is store d in a shielde d cask, TAe 2 lfer + cans?er cask i is postfion e d ove r sme// c)ening in a 1he shield cask, h bottom slide is polle d open, an d fbe F// fee ? alls down info the shielde d' con ta ner. In this r ma nn e r, fbe han dlin3 o F hyhly contamin a fe d F;Hees is kep+ fo ca minimum. ,e AinvbmBvi 29

Attachment I Mr. Harold R. Danton Docket No. 50/395 December 28, 1981 11.5.5.4 Radioactive Hardware Radioactive hardware can consist of damaged or used equipment or instru-ments, which due to geometry or materials of fabrication, cannot be readily decontaminated. Such material is disposed of in much the same way as are filter cartridges or as compacted waste, depending upon radiation levels. 11.5.5.5 Compacted Waste An electromechanical compactor provides four tons of compressive force for the compaction of compressible waste into 55 gallon drums. During compaction the drum and compacting mechanism are enclosed and the en-closure is vented to the auxiliary building atmosphere through a HEPA filter by a blower. The blower and filter are contained within the co=pactor. The compactor conforms to current OSHA requirements. The compactor will not operate unless the door is closed, preventing the operator from injury and preventing escape of unfiltered air to the atmosphere. g rA. 11.5.6 STORAGE F1 d containers are stored either on the radwaste operating floor a, grade or mezzanine floor 11 feet above the operating pend-ing upon contain activity. Filled 50 ft containers quiring 1-1/2 or 4 inch thick indi al lead shields a ed on the operating floor which has storage capacity at 1 ontainers. These shielded gg containers are located between co te walls and 3 inch thick steel k plates for additional shieldi g. Containers requiring no shielding are stored on t upper floor. This floor has suff ent load capacity to permit storage o iners having 1-1/2 inch thick lead shields, if required. Sto e capacity lindividua / 3 i for'20, 50 ft containers is provided. These containers are a located / / ehind concrete walls for additional shielding. / Yb x / 11.5-19 (t lE/VDAENT 27 h

r Aresa r I ne oe..:t) R De.r.- o -.c,.n LvSER T H _ (10 f*1s I/* S ~I1* b ~~'v,,, Cornpaefable

waste, Pilled confainers ovcon,pacfed was te,

and s,oent Pilfee carfrid es are sfored g in the shielded areas oV the ra dwasfe

area, Contar,inate d hard wace an d tools may q/so be stored in fl,ese room.s.

Solid; Pie.d waste, aVier solidiPientien is coinf ete, l an d dewa+ered resins, once dewateri* 3 si cos,plete, will be shyped off? site For in,me dfale borraI a f q licensed Pacilif. A/o cre dif is y fa kei, For decay aP slwet liveJ radionueRdes will hve of s,oenf resin, krj>~ary s,0ent resins at lens f a one monf4 decey peciod while bein3 held in /Ae spen t resin sferage kh. Evapara for In ttom an d secondacy h/ovdown c/ecayperiod. resins da n oi normally reyvire 9 IF sol;J;rie d waste an J/or dewafered resing reyv;re s torage Vor any reason, 14ey will be store d in f4e ra d in tion con tre / a rea cut-f4 e storagepad side flie truc k access on (see Ffare 1, z -25). Tbe sfor.y e j a d is 40 Peet wide by /20 Teet ap,oecxi>nafe17 long an d is slofe d }owae d a hoH-o,o ~ /)/nEniDrieltr 27

A++.a..,i ~ n..i> a n., Posn a r p,, o,py D'u ~ n n, irr, 1NSER T H_ ( con ti>,sied) t. II r - ><t 4 henci), Wasfe ^.sfor e d in fl1e s foraye aceq reyvire d by f or fa b /e will be shie lde d as shields and/or cas ks use d For slupmed. Vas te whos e radla tran leve/ con fa c f on exc e e ds lR/hc a store d on h porfios, o f the storage pa d whase access is con fesled adhtton n / kc ked chain link Pen ce. b an Ins kcke d access is approximafen 30 feef w;de b 40 feet /ong. y a eens for solid 7Fied wasle, Sfontge dewa tered resins, an d compac te d was te 30 fic len Y, based on }b e eslimales Qre preses, te d in see fion II,5' 4, to a c c on,mo da fe y enfer 30 days waste genem tion. i m ,e AmwDnwivr 27 a

Atmkn~- l reemesJ5pa.rw Mae r No S0/J22 b ee-w is,srs I credit is taken for decay in storage since spent resins will have had / f atJ t a one month decay period in either of the spent resin storage (., / tanks bef solidification, when required. Evaporator bottoms do not r normally requi a decay period. The area adjacent to the c ctor ha e e capacity of approxi-2 [ mately 10 drums. Additional onst 4torage is provided to accomanodate one full offsite shipment of cred te. C Storage areas p solidified wastes, based on estima presented in j Section M4, are thus capable of accommodating greater than 30 days) / N / wp fe generation. V 11.5.7 SHIPMENT Shipment, in accordance with applicable regulations, is made as necessary dependent upon operational considerations and storage area availability. 11.5.8 POTENTIAL FOR RELEASES 11.5.8.1 Potential for Release during Container Filling I Th illing opet. tion is automatically terminated under any of the f le lowing co tions: l i T e vaste is still within 1. Overfill, indica by the level pr/obe. 2, the container. The cont er at-the normal stop, or full, condi-( i tion is actually only about'95 cent full. l 2. Loss of electr cal r to the level p e. 3. Overpr stire in the waste pump discharge line. l 4. erpressure in the vent line fran the container. ( i L-resn T K l 4 ( 11.5-20 AMENDMENT )( f -IU"E, 923

== L

w.24,yr / . n < m n/ e o.-c.- on.,s. o/nr Ossemb*e 16, /9y) T/VSERT K (to Pays II, s L 0,, ) The Vility operation is autornafica//y ferminefed if fbe preselecfe d sefpoinf of radmortifor %%R is exceeded. This avfoi,a f;c fecminaf;on is a ccomplishe d by closing valves thov-2 an d /hotl-5 $1anua/ ferming f to n of a Vi/I operation can be acenmplis he d by c. losing eliher /Ylo V - 2. a /ho v-5 o r h waste frerPee f4e pip;ng,6rocess skid. As vaIve on. discossed in see tron ll,5, t 2 6 the % Ilo wl y is use d by fle op e <a tor to Vill ope <a fisn manually te rmina te a by closing the waste }rans er v'a lve : B ra d:a fion mon tfs es Piil her d p ressore alaem h;3 h leve I

gIncn, cemen/ /evel alacm was fe le ve I a la rin hi h-hiyh level alaem 3

11n er level in dica tion TLl ca m era fill her d +e mp era for e a larm. A91EivbME/VT 2'l L

Ahkatar i Mr thra./ R ik re Po u ar m rop:-r 4" A** 2 Q, itvs A D 1' cation flow in any of the feed _ lines.' 5. (' 7 6. Excessive radiation, indica by eitherJ he radiation monitor at 2 g Ja_contatner surface or 6 feet away. ~ a;rbNne. There is noArelease to the atmosphere in the fill areas, Air in the container and gas, if any, from the waste entering the container are vented to the building exhaust through a local filter. Only one line feeds waste to the container. This is flushed with water as the final phase of the fill cycle. Eh= 1 liue= m E : sc.;cicu, se wich ,4 a ssanec u = tc=c e - n y :21scthct a alppas ac e Except Vor the corb in the solid;Picatten area,areos d There are no physical barriers in the immediate fill eree-to contain 27 spills, since the radiation sensors automatically stop the fill opera d ion if rKdiat-ico, ahqve a safe operating level, is_ detect [ The in-corporation of a concrete cu o ' N t use of the lift truck. W / Floor drains in the area'wduld be plugged as a res i f solidification of the urea-fo'rmaldehyde solidific_ation agent in the unlikely en Q L a -significant _ spill. Inadditionf8pillsfromtheshippingcontainer r (_ would need to be drained to a special container since spilled material could not be mixed with the contents of any other tank. The floor surfaces have a special nonporous finish to permit decontam-ination of the surface, if required. N 11.5.8.2 Potential for Release from 3torage Tanks 11.5.8.2.1 Waste Evaporator Concentrates Tank Essentially all radioactive gases are stripped from the concentrates in the waste evaporator. A normally closed vent is ducted to the auxiliary building exhaust system. A water seal, set for 2 feet of water, vents 3 to the waste evaporator concentrates tank cubicle which is serviced by the auxiliary building exhaust system. 29 11.5-21 AMENDMENT,I _RNE;-1W9 ~

h[tssin.s*T $ ne amt/ R pa-rw pesAst Hs C:/Hf 0.mou a s, nas normal plant operating conditions. Overflow protection is provided by a ,k high level alarm at the solid waste system control panel. Excess water can either be pumped or drained to the waste holdup tank. Overflow, if it occurs, is to the waste holdup tank through a relief valve. The tank is enclosed within a concrete cubicle with entrance from an overhead shield slab. Any leakage is directed to the floor drain tank through a floor drain. F 11.5.8.2.4 Nuclear Blowdown Spent Resin Storage Tank This tank contains only trace amounts of radioactive gas. The gas is normally contained in the tank by a closed vent valve. The tank is vented to the cubicle, which is serviced by the building exhaust sys-tem, only during transfer of resin from the demineralizers or at the conclusion of resin transfer from this tank to the radwaste packaging area. n( Overflow is not anticipated since the nuclear blowdown spent resin storage tank capacity is sufficient to accommodate at least 30 days waste generation under normal plant operating conditions. Overflow protection is provided by a high level alarm at the solid waste system control panel. Excess water can either be pumped or drained to the nuclear blowdown system reservoir. Overflow, if it occurs, is to the nuclear blowdown system reservoir through a relief valve. r k The tank is enclosed within a concrete cubicle with entrance from an overhead shield slab. Any leakage is directed to the nuclear blowdown system reservoir through a floor drain. ( ~ 11.5.8.2.5 wast *JQe_nding Tank n The '4BT is used to on radioactive liqu e and resin o o packaging. Waste will not be stored in this 11.5-22a g AMENDMENT M ' -JUNE r-44SIL__.

htt & o<r I m reuou t De-ro# De casr *> rs/sti (s pseuue is,19so tan except for the quantity prepared for immediate packaging and solidy A in / \\ ny radioactive gases that may have been present ificatt evaporatorconcentratesorchemicaldrains'wouldhavebeenpea./ e sed s either in the respe tive storage tanks or during ti'ons prior to storage. However, the is vented to the ur ding exhaust system ( through a filter and water tra. ented point is located at the top of the tank. The WBT is u ppe Nith normal and high level probes. N Overflow is not a tpated since fill'ing of the WBT is closely meni- ~ tored p

  • r o the solidification operatio The cubicle housing is d i o contain the WBT contents in the event tank rupture.

( 4g x x c N. t i ( t 17 11.5-23 AMENDMENT d _-2.=,

a; -

A+f. A s-1 1 - Me nest) R Deeres. Duursynr ) ><sskt te,ipsj

11..

Radwaste Module Cubicle a [ priate valving are located The radwaste/ recirculation p / um within a, concrete cubici neath the WBT cu A 6 inch high 1h f concrete curb ains any leakage which may occur in thi. ea. The I ts serviced by the building exhaust system. C C i ( 1 ( ( 27 11.5-24 AMENDMENT [ JUNE, 1980

ht % Lrs-r j n e asMJ R 9 -r** Ni TABLE 11.5-5 (Continued) w (' S,OLID WASTE SYSTEM-EQUIPMENT DESIGN PARAMETERS Urea Catalyst Tank Quantity 1 Volume, gal 5000 Type Horizontal Design Pressure Atmospheric Design Temperature, F 150 Urea Formaldyhyde Concentrates (UFC) Storage Tank Quantity 1 Volume, gal 5000 Type Horizontal Design Pressure Atmospheric { Design Temperature, F 150 Urea Formaldehyde Concentrates (UFC) Day Tank Quantity 1 Y Volume, gal 750 l Type 'ertical Design Pressure At spheric / Design T perature, F ,O Sodium Hydroxide Addition Tank / Qua ty 1 VoJume, gal 200 / Vertical ype Design Pressure Atmospheric Design Temperature, F 150 (- 27 11.5-30 AMENDMENT 49 ~ .__ JUNE,-1980-

F AN<4a$ r I .W "' HeMJ t %re-TABLE 11.5-5 (Continued) peu.'y a rope l AcknW :s,syfi (~ SOLID WASTE SYSTEM EQUIPMENT DESIGN PARAMETERS Sulfuric Acid Additio Tank-Quantity I g ') Volume, gal 100 Type Vertical Design Pressure Atmospheric Design Temperature, 'F 150 Waste Blending Tank Quantity 1 Volume, gli 800 Type Vertical Design Pressure A mospheric Design Temperature, F 1 ( A_ = s. k. 27 ll.5-30a AMENDMENT # J"NE, 1080

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Attachment II, Mr. Harold R. Drnton Docket No. 50/395 - December 28,1981 On unit startup, the polishers will be on line until the plant attains approximately 50% full load capacity. Then, due to condensate pump charac teristics and system pressure drop, the CPS will be by-passed. During shutdown of the unit, the CPS could be placed in service when the plant load is approximately 50% if system chemistry indicates a need for cleanup. If the condenser develops a leak, which will be detected by the con-denser leak detection system, the leak location will be determined and ,39 ' that ha1f of the condenser will be taken out of service for repairs. At this time, the unit will be at a load of about 50% and the condensate polishers can be placed in service to assist in removing chemical impurities introduced by the detected leak. If a primary to secondary leak occurs, it will be detected by the steam It is not generator leak detection system and the CPS will be isolated. intended to operate the CPS if a SG leak occurs. In the event that the condensate polishers are used in the presence of a steam generator tube leak, all applicable Health Physics measures and precautions will , JET' ' be observed. Depleted resins are backflushed to a Backwash Receiving Tank from which The results of samples will be taken and analyzed prior to release. isotopic analyses are then utilized via established station pro-gamma determine if a release is '*S~~ cedures and administrative controls to,he normally a;secuee ted spoolf,rece is m. fallk s t und If a release is acceptable / the depleted resins are dis-possible. ikrev$ RML~il, h

capli;hed uri-g mone'aariate charged to the settling pond A Th ' a 2 N

norm W - t e s t ive--pr oc c d e c c 3 wh ici. ncludes-the install =H an af a >2: discennecteLepo 4 iec: to-the pond d i "h a r ga-4ine-. -I f s cis..e is w bie, N depictcd io ms will be diepeeed-cf in = accegaMe 2T _The-anticipcted-eperatienci inforr.ction is as fc11 sus: -enaar-1. Flow rate each vessel: condensate flow rate = 4411 gpm backwash flow = 200 gpm 25' _ 3 backwashes per 24 hr startup 2. Backwash frequency: 3. Backwash holdup tank: 12,000 gallon capacity O 10.4-19b AMENDMENT 27" samst_Stanst

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bI d 11 Mr. Harold R. Denton j NE Docket No. 50/395 g December 28, 1901 p y 2 i g; j g -c r .= "OR x NFORWA TION =

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f Attachment V 9 Mr. Harold R. Denton Docket No. 50/395 - December 28,1981 j.[l ih. 1 I i-i. 4- !.::.ei.g e h! h !I o !E + .m,;r . %nin=se rre- + l o; i i }-i;e. ]a e s. u;i e a, a;3 ,g es g g, m ig

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ATTAGIMENT VI Do k b/ 12/28/81 TO: U.S. Nuclear Regulatory Commission Washington, D.C. Attention: Frank Miraglia Re: Chem-Nuclear Systems, Inc.(CNSI) Document SD-OP-003, Rev. D " Process Control Program for CNSI Cement Solidification Units", CNSI Operating Procedure for Portable Cement Solidification Unit ho. 21(PSU-C-21), CNSI Dewatering Procedure for Conical Bottom High Integrity Containers 1% Free-standing Water, CNSI Drawing No. 313-2101-E01 Rev.- AFFIDAVIT SUBMITTED IN SUPPORT OF REQUEST THAT THE ABOVE DOCUMENTS BE WITHHELD FROM PUBLIC DISCLOSURE PURSUANT TO 10 C.F.R. S 2.790 STATE OF SOUTH CAROLINA ) COUNTY OF RICHLAND ) GERALD P. MOTL states as follows on behalf of Chem-Nuclear Systems, Inc.: 1. I am the Director of Field Operations of Chem-Nuclear Systems, Inc. ("CNSI"). 2. I have reviewed and am familiar with the contents of the above referenced documents and submit this affidavit in support of the request by South Carolina Electric and Gas Company that portions of these documents be withheld from public disclosure. 3. The information contained in the documents provided, as described hereinabove, has been held in confidence by CNSI as follows: CNSI has always maintained confidentiality with regard to the design and operation of its mobile solidification units. The proprietary information contained in the above documents is not available from public scarces. 4. The information contained in the above documents is of a type customarily held in confidence by CNSI, and there is a rational basis for such confidentiality as follows: CNSI has devoted extensive resources to the development and improvement of its radioactive waste disposal services. It is customary for CNSI to maintain confidentiality concerning services maintained for particular customers and originators of radioactive waste both for the protection of such originating' entities and also to protect the competitive position of CNSI

ATTACHMENT VI Mr. Harold R. Denton Docket No. 50/395 12/28/81 5. The information described hereinabove was transmitted to the Commission and received by it in confidence as f o llows.: The documents were forwarded to the Commission along with South Carolina Electric & Gas. Company's license application. 6. The information contained in the above documents is not available in public sources as follows: The documents contain a complete description of the CNSI mobile solidification unit, including hardware, chemical usages, and adjustment date, and formulas, all of which are set forth as proprietary information. 7. Public disclosure of the documents requested to be withheld from such disclosure is likely to cause substantial harm to the competitive position of CNSI as follows: CNSI has devoted extensive resources to the development and improvement of its radioactive waste disposal services. Release of the above document to the public would afford competitors of CNSI an unfair advantage and would cause substantial harm to the Company and loss of the benefit of past investment of financial resources including engineering costs. Company employees agree, as a condition of employment, to maintain and keep company proprietary information confidential. The information contained in the documents is not available through public sources. 8. For the reasons set forth in the affidavit, CNSI respectfully requests that the Nuclear Regulatory Commission withhold the above documents from public disclosure as permitted under 10.C.F.R. S 2.790(b)4. GERALD P. MOTL DIRECTOR, FIELD OPERATIONS 1 STATE OF SOUTH CAROLINA ) COUNTY OF RICHLAND ) On this 30th day of October, 1981, before me personally appeared Gerald P. Motl, to me known to be the Director of Field Operations of Chem-Nuclear Systems, Inc., the corporation that executed the foregoing instrument, and acknowledged said instrument to be the free and voluntary act and deed of said corporation, for the uses and purposes therein mentioned, and on oath stated that he is authorized to execute said instrument. i -. ~..

ATTACHMENT VI Mr. Harold R. Denton Docket No. 50/395 12/28/81 IN WITNESS WHEREOF, I have set my hand and affixed my official seal the day and year first above written. I .h h I infand NOTARY PUBLIC for the State of South Carolin resid* g at s Pohnw &~ 'D- ~ r l$ I ( 1 L}}

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