ML20053C650

Forwards marked-up FSAR Pages Showing Changes to Be Incorporated Into Chapter 11 of Amend 32 Re Radwaste Sys

ML20053C650
Person / Time
Site:	Summer
Issue date:	05/24/1982
From:	Nichols T SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8206020427
Download: ML20053C650 (15)

Text

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k SOUTH CAROLINA ELECTRIC Sc GNh, opWPA NY Post omer sox 7s4 COLUMBI A. S. C. 29218 May 24,1982

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Ccmnission Washington,' D.C.

20555

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Subject:

Virgil C. Sunner Nuclear Station Docket No. 50/395 Radwaste Syst s FSAT Changes

Dear Mr. Denton:

South Carolina Electric and ' Gas Ccrpany (SCE&G) fiereby provides ma'rked-up FSAR pages showing ctianges that will be Incorpo' rated into Chapter 11 in Amendment 32. The majority of thase changes do not inpact previcus ccmnitments and result from our utilization of the Chm-Nuclear Cement Solidification System as opposed to our previous urea-formaldeh de systs or frm printing l

errors. Ho wver, there are two changes which warrant further discussion to preclude any confusion.

f' First, the PSAR previously stated that liquid ralwastes would be allowed to decay in storage' tanks on site for at least 31 days prior to shipping.

s Because we om find no basis, either regulatory or technical to delay shipnent of wastes that may meet acceptable radicactivitiy%11mits, we will modify this ccmnitment. SCE&G will store liquid radwastes oil, sits as required prior to shipping. This storage period may be len,s than or greater. than 30 days. The capability exists to acumudate stored wastes for at least 30 day waste generation in accor6hice with Standard Eevicw Plan Section 11.4.

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Another chanta involves the sealing of radwate linersa SCE&G had '

previously stated'in the FSAR that the final closure ol' Ml'rahaste liners would be done by rmote handling equipnent. Although this equipuent is available, it will not be n'tilized when radiation levels permit hand installation of a barrel top for sealing.i The re: note handlin94;uipment will be used for closure of radwaste liners Af required by radiation'ldvels.

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As menticned earlier, the other changes shown in the attached pages do not represent changes to prior ccraaitments. 'Powver, if you have any questions, please let us know.

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e Very truly yours, 7

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T. C. Nichols, Jr.

Senior Vice President

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Power Operations g-T g

8206020427 820324 PDR ADOCK 05000395 i

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PDR i g.

e Mr. Harold Denton May 24, 1982 Page 2 NEC:'KN:lkb cc:

V. C. Sumer (w/o attach.)

G. H. Fischer (w/o attach.)

H. N. Cyrus T. C. Nichols, Jr.

(w/o attach.)

M. B. Whitaker, Jr.

J. P. O'Reilly H. T. Babb D. A. Nauman C. L. Ligon (NSRC)

W. A. Williams, Jr.

R. B. Clary O. S. Bradham A. R. Koon M. N. Brome G. J. Braddick J. L. Skolds J. B. Knotts B. A. Bursey G. D. Moffatt T. N. Effinger NPCF File s

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11.5 SOLIO ASTE SYSTEM 11.5.1 DESICN OBJECTIVES l

The solid waste system is designed to package and/or solidify rad-29 ioactive wastes for shipment to an approved offsite burial facility in

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accordance with applicable Department of Transportation (DOT), NRC and State regulations.

The system conforms to 10 CFR 20 and 10 CFR 50 req-uirements by providing shielding so that radiation exposure of operating

• personnel and the public is within acceptable limits. Solid waste pac-kaging is accomplished in an area located on the ground floor (ele-vation 436') and in the upper mezzanine area (elevation 447') of the auxiliary building, a Seismic Category I structure.

29 Design, f abrication and test of solid waste system components and piping 15 is in accordance with ANSI B31.1 and other accepted standards referenced by ANSI B31.1.

Additional onsite system tests will be performed using I

nonradioactive materials prior to commercial operation. [1m s pp ig ta'..crs ar T ay, A/Ov a[s[r[ihy r[i[c

've ma ri s sa t s f-DO* re als onstl Packaging and shipping conform to 49 CFR 171 through 49 CFR 178.

used re uired to main-32 ioactde,whe$triaft Individualcontainershieldsandcasbsadr en_puhfions.

y re mn apphca er 10 rE/hr tain radiation levels within 200 n/h; ;; ;;;f;;; ;; :::t

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11.5.2 SYSTEM INPl'TS i

Radicactive waste packaged includes:

i 11.5-1 AMENDMENT JA::L'ARY, 1982 T1~u rie.

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11.5.3.2.4 Instrheentation and Controls The system uses temperature, flow, pressure, and level instruments t o*

monitor and/or control the process located throughout the system.

The inplant control panel, power panel and radiation-monitor are located in the drumming station control room.

The CNSI control panel is also located.in this same area.

1.

Inplant Control Panel The inplant control panel is a standard enclosure of NEMA 12 con-struction. The inplant control panel provides full operational control for resin and liquid waste transfer operations to the ven-dor's equipment.

It is also used tr, interface with vendor equipment 29 f r dewater return and for flushing operations. This panel contains switches and lights for valves and pumps which facilitate these

sg7, operations.

Thi: p ::1 ::nt in: := che :nd light; f or va l. ;

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k 11.5-Sa 32, AMENDMENT E9 J*Me999, 1982 600e.

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4.

Radiation Monitoring Radi.ition monitoring is provided by the vendor's equipmetit in the following areas:

Vaste isolation vabe of the piping process skid 1.

2.

Liner fill head 3.

Drumming station control room

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4 Radmonitor RM-7662 is portable for use in either the solidification area 29 or truck bay. This rasmonitor will alarm and terminate a fill operation t

by closing valves HOV 2 and MOV-5 if its setpoint is exceeded.

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The radiation monitors are in addition to those discussed in Sections 14 11.4, 12.1.4 and 12.2.4.

Ad'8/dq.5,,ewasggogtal"*f30YMMMi"6Meners. W wrdcunus wd for ced 2

reado deurdering anoTodd A SU SOf P N @ db-SctidiGeab'm ao

%.te an ard/55,/ga/loy[4 ud./Ot/ierj6aff 4

t wa n e s a re pa d n 3L a

p ka d iD T pe s e nt ne s./

Quick disconnect fittings are located in f*M 4.eed top for the following:

Sillhead 1.

Dewater through a tilter, provided in the container, back to the Excess Liquid Waste Holdup Tank or Spent Resin Storage Tank.

2.

Cement - Calcium hydroxide fil'1 connectf on 3.

Conditioning chemical supply 29 4.

Vent to filters and plant vent 5.

Radwaste supply flush AMENDMENT 31 11.5-7 m. 1982

19 h*qpd ~

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31 The processing os most of thEAwast'e volthe wi11 be in the solidification I

area. This area is enclosed on three sides by walls for shielding and

.e includes a curb to contain spills. A movable shield may be brought in

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if additional shielding is required.

Higher activity wastes will be processed with the liner already in the transport cask located in the truck access area. A double lid cask top will be used to limit exposure in this area. The main part of the lid shields the entire top of the cask except the immediate area required for the fill head. After the 29 process is complete, the fill head is removed and the secondary cask lid is installed.

can be cuempH.hecl by 4 rgoired.

n Final closure of all radwaste liners ie-by remot'e handling equipment A f

remotely Carbon steel liners are4 sealed by a hydraulic bagrel top crimper.

High 3j7 remedelv Mna manipula4e integrity containers areAsealed by a device which screws the closure cap n

into the liner.

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i 11.5.3.2.6 Contamination Control Facilities An adjacent decontamination area is provided for cleanup of contaminated containers.

Exposed surf aces of filled containers or casks are surveyed by *the health physics group to identify the pres,ence of removable radio-active contamination prior to transfer to storage or shipment.

Containers 4

are decontaminated in the adjacent decontamination area, if required.

11.5.3.2.7 Handling Equipment Equipment used for handling waste containers and equipment within the radwaste area and for truck loading includes the follouing:

29 32L 11.5-8 AMENDMENT 29 Ja:,UART, 1982 Sune

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[

I One ton jib crane.

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1, Three ton jib crane.

2.

Ten ton bridge crane.

3.

Twenty ton hoist and monorail.

4.

4 Three ton bridge crane.

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5 6.

Ten ton bridge crane.

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The one ton jib crane is located on a wall above the truck access floor at

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from the l39 is used for hoisting chemicals and equipment It 30t l elevationjj/,.

It has a lift of 23-feet at a truck access area to the mezzanine floor.

speed of 22 ft/ min.

The three ton jib crane is located on a wall.above the solidificat' ion is used to handle the vendor's fill head and other equipment.

area.

It a speed of 11 ft/ min.

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It has a 23 foot lift at l

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i 31 AMENDMENT 4MI 11.5-9

%g4 J x:;n' 't, 1982

The ten ton bridg2 crena is ussd for trcnsporting compcctible end non-(

compactible waste, in the low radiation level storage area at floor elevation 447'.

It has a lift of 14 feet at a speed of 11 ft/ min and a troll'ey speed of 65 ft/ min.

y 7' ~ ~'

The twenty ton hoist and monoh is used to load the containers on a p

truck for transport to a burial site.

It has a life of 17 feet at a speed of 10 ft/ 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 cartri,dges from the filter housings located in concrete cubicles on the 14 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 I

436'.

It has a ;ift of 47 feet at a speed of 22 ft/ min and a trolley speed of 65 ft/ min.

Anothertent[nbridgecraneis 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, 55 gallon drums, pallets, etc.

The The hoist has a lift of 24 29 storage area is also serviced by this crane.

feet'at either 7 or 20 ft/ min.

The trolley has a speed of either 32-1/2 or 65 ft/ min.

11.5.3.2.8 Waste Compactor An electromechanical compactor, with a compressive force capacity of is used to compact dry wastes into 55 gallon ' drums.

During 32 l N tons, A self-contained HEPA filter compartion the drum is cor::pletely enclosed.

32 11.5-10 AMENDMENT 29" ygye

/1;; r, 1982

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and blower system filters the air released in the compaction process befo're it is discharged to the auxiliary building atmosphere.

An elec-trical interlock prevents operations of the compactor-if the door, which 2

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 to fill directly to containers on a truck.

This penetration is located;,,f

.f3/1 29 in the shielded cubicle of the solidification area such that exposure in the truck access is limited.

11.5.4 EXPECTED VOLUMES The expected annual volume 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.

o 11.5.4.1 Activity Levels The activity level of the wastes generated directly from operation of the nuclear steam supply system is based upon reactor plant operation 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-erations with up to 1 percent fuel defects.

Source term data used for system design are presented in Section 11.1.

3-11.5-11 AMENDMENT 26

,W:t3xRT, 1982 Gune

Table 11.5-1 lists the demineralizer resin volumes and expected volur.es replaced on an average yearly basis.

Table 11.562 presents a summary f

cf the anticipated total solid radioactive waste generated per year.

The expected activity of the solid vsste at time of shipment is depen-dent upon the decay storage time.

An isotopic breakdown of spent resin and waste concentrates activities is presented in Table 11.5-3.

The raximum activity of expended filter cartridges is'piven in Table 11.5-4

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The associated Curie content and volume of waste shipped from a number of Westinghouse designed operating reactors is given in Table 11.5-6 for each year from 1971 through 1974.

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11.5.4.2 Processed Wastes The maximun Curie content of the evaporator concentrates is approximately 40 eCi/ce.

^^ 9' "" cf 35 ft c: pur- ^- run:cntriter per cc -

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ctivity ic 25 Curiec Fowever, the average activity t,4~-

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content is expected to be on the order of 4 pCi/cc.

The Curie content of the chemical drain tank effluents totals approxi-

') l-mately 2.0 Ci/yr, uc 0.5 Cu iua wuu to inu., In the case of primary gu.

spent resins, the Curie content totals approximately 1390 Ci/yr, p4' 7

g.0-2 P^ '- H F-th-Nuclear blowdown system spent resins are esticated, for design purposes, to account for approximately

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2-11.5.4.3 Filter Cartridres o'

1he volume of expended filter cartridges processed for disposal by the solid waste system is based upon the expected filter cartridge change fiequency for potentially radioactive filters.

The assumption is made that itirers processing reactor coolant will require cartridge renewal i

due to excessive radiation 1cvels high AP at minimum intervals of G

g h )p(){ Q 11.5-12 nne.

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every six full power months of operation and that one of the three

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nuclear blowdown system filters will require cartridge renewal, normally for high AP, weekly. All other filters are assumed to be renewed annu-

'a11y. These replacement rates are approximations only since suf ficient specific operational data is not yet obtainable (see Table 11.5-4). -

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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 vaste hydpdcs beler is assumed to amount to -3M, 55 gallon drums of l

32 com 1000 i

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compacted refuse. The vastes consist of rags, coveralls, ventilation filter cartridges and various other potentially contaminated refuse. W cetivity cf thi: : fu : i 1 r level and de : :t present : :: diction I

W 1.0 Ci/yr'. M #6 U D N M:::d (12 : th2:

GC.fldig 11.5.5 PACKAGING 11.5.5.1 Evaporator Bottoms and Chemical Samples Evaporator bottoms, concentrat'ed to 12 percent, or less, boric acid in l

14 the boron recycle or waste evaporator, are stored in the heat trace'd 5000 gallon waste evaporator concentrates tank. Lines from this tank to the vaste line connection in the piping process skid cubicle are also heat trace [i. Chemical samples are stored in a 600 gallon chemical drain tank. When a sufficient quantity has accumulated in either waste tank, its contents are recirculated for at least two volume changes and a sample is taken. The sample is used by the Process Control Program for test solidification. Af ter sampling, the waste volumes are then trans-ferred to the vendor's equipment 'or processing.

37 11.5-12a AMENDMENT E Jf rJ32Y, 1982 June

y flexible hoses end cna electricci leed are disconnte The

~c snaps the the overheed jib crsne which lift chains attach ly is removed and the lid fill shield a 3I quick disconnects free.

ic1d cask by use of the pendant 2$

shield is installed on the conta' ally sealed when the container is autom controlled jib crane.

storage area filled container is stored reed.

The disconnects shipment.

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.u 11.5.5.2 Spent Resin _

i ation Resin in a demineralizer is considered spent when its decontam n dose factor falls below a permissible level or the demineralizer surface 5

from demineralizers in the I

rate exceeds its limit. The spent resin, 3 storage tank.

The spent resin primary system is sected in a 350 ft 29 d

from n'uclear blowdown demineralizers in the secondary system is store The resin stored 3 nuclear blowdown system storage tank.

norrmity i d of up to several in a 600 ft in the primary system isAallowed to decay for a per o months.but net le:: tF - 20 drye; The :::Ir ::: ::' ir th; nuclccr bl:'"

N Ada=i"a *a "i "i "" d * "" ? -

d ta der eyere

-tecage t 9 ir a"~a"e This period i: np :::d tc b 100; th;; 30 J:7r.

paried required.

l19 has accumulated and decayed, the When a' sufficient quantity of reeiar vg e %wertes and omvmes; ior to packaging, N

annt p d fo 1 and packaged. Pr resin is sampled f e edisfi M form a slurry which is ll 3

resin sluice water is recirculated in the tank to Dewatering of ssure.

transferred to the liner by nitrogen cover gas pre i

t with the water the resin is accomplished using the vendor's equ pmen 29 k or the be ng returned either to the Excess Liquid Waste" Holdup Tan resin may also be solidified.

Spent Resin Storage Tank. Spent o

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37 AMENDMENT 29 11,5-15

M, 1982 6V06 A.1

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resin storage t.?nks are set to relieve at 110 psig and 140 psig, res-pectively.

The primary resin storage tank relieves to the' waste holdup tank.

The nuclear blowdown resin storage tank relieves to the nuclear blowdown system reservoir by way of an open drain.

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11.5.5.3 Filter Disnosal Filters are of the disposable cartridge type contained in housings y

having hinged tops.

They are replaced when surf ace dose rate or pres-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 shiciding during removal, a concrete plug in the floor above the housing is removed and another plug with a hole in it is placed in the stepped opening. A filter cask with 31/2" lead encased in stainless steel is placed over the hole. The filter housing is opened and the cartridge is drawn into the cask by the use of special tools having extension rods.

Once the filter is in place, the cask bottom is slid closed and the tops installed. The cask is then transported by an overhead crane to a hatch at floor elevation 463' of the auxiliary building. This hatch is located above the drumming station area on the floor below. The cask is lowered into the drumming station area.

Storage and disposal of all filters is within either high integrity containe or DOT approved

+he pcKic ctclavsfy cf e 4illtr>-

55-gallon drums depending on thc.: c ur k w.G.a For filters requiring shielding, the container is stored in a shielded cask. The filter y

transf er cask is positioned over a small opening in the shield cask, the as owered bottom slide is pulled open, and the filter falla d;ua into the shielded

],3 container.

In this manner, the handling of highly contaminated filters is kept to a minimum.

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(:1 sz 11.5-18 AMENDMENT 24 W 1982 qu ne.

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11.5.5.4 R+dio+ctivi usedw*re Radioactive hardware can consist of damaged or used equipment or instru-rents, which due to geometry or materials of f abrication, cannot be readily

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decontaminated. Such material is disposed of in much the same way as are filter cartridges or as compacted waste, depe'nding upon radiation levels.

11.5.5.5 Compacted Waste s

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An electromechanical compactor provides Seer tons of compressive force

'.2-s-.

for the compaction of compressible vaste 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 compactor. The compactor conforms to current OSRA requirements. The compactor will act operate unless the door is closed, preventing the operator from injury and preventing escape of unfiltered air to the atmosphere.

11.5.6 STORACE Compactable vaste, filled containers of compacted waste, and spent fil-ter cartridges are stored in the shielded areas of the radvaste area.

Contaminated hardware and tools may also be stored in these rooms.

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Solidified waste, af ter solidification is complete, and dewatered

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re sins, once dewatering is complete, will be shipped off-site for imme-diate burial at a licensed facility. No credit is taken for decay of short lived radionuclides of spent resin. Primary spent resins v111 ADifM40j f3(

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have at leas t a one month decay period while being held n the spent resin storage tank. Evaporator bottoms and secondary blowdown resins do not normally require a decay period.

29 If solidified waste and/or dewatered resins requir's storage for any

$ hey will be stored in the radiation control area outside the

reason, truck access on the storage pad (see Figure 1.2-25). The s torage pad is approximately 40 feet wide by 120 feet long and is sloped toward a hold-up trench. Waste stored in the storage area vill be shielded as Waste required by portable shields and/or casks used for shipment.

whose radiation level on contact exceeds 1 R/hr is stored on the portion of the storage pad whose access is controlled by an additional locked chain link f ence. This locked access is approximately 30 feet vide by r

40 feet long.

I Storage areas for solidified waste, dewatered resins snd compacted

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waste are sufficient, based on the estimates presented in Section l

11.5.4, to accomodate greater than 30 days vaste generation.

11.5-19.

AMENDMENT JANTERT, 1982 TUAC t

There is no airborne release to the atmosphere in the fill areas. Air in the container and gas, if any, from the waste entering the container e

i 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.

29 Except for the curb in the solidification area, there are no physical barriers in the itmediate fill areas to contain spills.

Spills from the specihc locahon er shipping container would need to be drained to a ep_cici cen:2iner cince "s,.-__ T_ _R_._ N_ N...f M O_ _ N_ N.l.. D.N..f. b 8__. Y. M..f. N_,. 3_. M_ _b. N_ _I. _.,..,.. -

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The floor surfaces have a special nonporous finish to permit decontam-ination of the surface, if required.

11.5.8.2 Potential for Release from Storage Tanks 11.5.8.2.1 Waste Evaporator Concentrates Tank 1

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 4

to the waste evaporator concentrates tank cubicle which is serviced by the auxiliary building exhaust system.

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11.5-21 ANENDMEN"I 29 JnncARY, 1982 ITVn e,