ML20138R058

Rev 2 to Technical Evaluation Rept 15737-2-G03-107, TMI-2, Div Technical Evaluation Rept for Waste Handling & Packaging Facility

ML20138R058
Person / Time
Site:	Crane
Issue date:	10/11/1985
From:	Smith E GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20138R053	List: ML20138R051 ML20138R058
References
15737-2-G03-107, 15737-2-G03-107-R02, 15737-2-G3-107, 15737-2-G3-107-R2, NUDOCS 8511180409
Download: ML20138R058 (37)

Text

-

IduCICCr T E R is737-2-co3-to7 nay. 2 ISSUE DATE June 7, 1985 0 'ITS O NSR

[E NITS TNI-2 DIVISION TECHNICAL EVALUATION REPORT r

FOR l

Waste Handling and l

Packaging Facility COG ENG C # OJ DATE 6 / ~1 /*

4 NP/rs-RTR E. 7 b M1 DATE COG ENG MGR.

d' of. /2 V C R.L (2:1.DATE 0/1/~

)

2

$/," b Revised and l_ssued For Use 7iy T F cif.J Q l

Vl_0/M Revised and Innued For Une d

7M db Mm 0

%'i/;d Issued For Use lit -

W 3R L_gAf_.

no em nem.o.

F e, c icsso J",%

rfahtt';

W'...

N/#

0511100409 051112 PDR ADOCK 05000320 P

PDR DOCUMENT PAGE 1 OF 36 enm. u,..._ _ u.- : w :.:

s :

m.c = m u

15737-2-G03-107 4

h d.

Provide exhaust hoods or other devices for process equipment in order to limit exposure of personnel to airborne contamination.

e.

Maintain the concentrations within the process areas of the WHPF below maximum permissible limits as defined in 10CFR20, Appendix B, Table'1, Column 1.

f.

Limit releases of airborne radioactivity to the environment below the concentrations established by 10CFR20, Appendix B, Table II, Column 1 and the TM1-2 Environmental Technical Specifications.

g.

Supply filtered ventilation at a minimum rate of 5 air changes per hour.

2.3.1.2 System Description.

2.3.1.2.1 General Description The WHPF HVAC system will be divided into several areas which are described in section 2.3.1.2.2.

The administrative area, shipping and receiving area and the equipment room are clean areas and are each served by separate heating and ventilation systems which are not associated with the HVAC system for the potentially contaminated I

work' areas of the WHPF. All penetrations are sealed between clean areas, e.g. the administrative area, and the processing areas.

A radiation monitor is provided in each exhaust to the atmosphere from the potentially contaminated areas, downstream of the filter, to monitor radioactive releases to the environment. Excessive levels will automatically shut down the exhaust and supply systems. Supply E

units are not permitted to run unless the exhaust system is on.

7 Flow direction from relatively clean to more contaminated areas is maintained by appropriately arranging supply and exhaust quantities to each air space.

2.3.1.2.2 System Operation

?

Shipping and Receiving In winter time the temperature of this area is maintained at or above 600F. During the summer forced or natural ventilation will prevent the temperature from rising above a maximum temperature of 1040F.. Due to the location of the equipment access doors leading into the separation, segregation and survey area from the shipping and receiving area, the negative pressure in the potentially contaminated areas will cause air to flow from the shipping and receiving area into these areas during normal operation.

6 Equipment Room-During the winter the temperature of this area is maintained above 600F.

In. summer, forced or natural ventilation will prevent the temperature of this area from rising above 1040F. 0422Y Rev. 1

- _ -,.. -. -. _. - ~.

n.

.4.s.. -

. ~..-

~

15737-2-G03-107 1

I

~

Administrative Area This area will have an independent HVAC system to heat, cool and ventilate the area. The air, which may be recirculated within the i

administrative area, will not require filtering before recirculating or exhausting to the outside. Air from the toilet areas will not be j

recirculated. Air conditioning is provided by a heat pump system with mechanical cooling which will also provide supplementary electric heat as required. This system is controlled by a wall mounted programmable thermostat.

Potentially Contaminated Work Areas One or more HVAC units will be provided for these areas. Air will

.be supplied at a constant flow rate and temperature all year round.

Duct mounted temperature controls will be provided. A temperature switch, which senses the outdoor air temperature, determines whether the refrigeration system or the heating coil is required to be in operation. Electric reheat coils controlled by room thermostats may be used to maintain temperature in each zone.

Outside air will be supplied to the WHPF for cooling and heating the air, and for ventilation, as required. Air may also be taken from clean _ areas for makeup for this HVAC system. Recirculated air or induction units may be used to maintain the required supply air temperature. If recirculated air is used, it will be HEPA filtered. Air from the sectioning area, electro-polisher, rinse tank and paint digester will not be recirculated.

Exhaust hoods are installed at each equipment location where fumes or other contari.nants are generated, in order to reduce the exposure to operating parsonnel. Air flow through these hoods, except for the compactor exhaust, may be continuous. When the compactor is in operation its exhaust fan, which is an integral part of this piece of equipment, draws air from the compartment above the barrel through a HEPA filter and discharges it to the atmosphere or to the area exhaust. When the compactor is not in operation, an alternate exhaust system from the compactor room opens and the same room exhaust flow rate is maintained as when the compactor was operating. A differential pressure gauge, which is an integral part of the compactor, indicates when the filters must be changed. The inspection table hood will be provided with a HEPA filter.

Exhaust and supplied air quantities will be regulated to ensure a negative pressure of at least 0 20" w.g. is maintained in the potentially contaminated work areas relative to ambient condition.

Preferably some of the exhaust hoods will be in continuous operation

)

when the system is operated. As additional hoods are placed in use, the quantities exhausted and supplied will be adjusted to maintain a constant exhaust rate from the building.

(Exhaust steps up before.

supply and supply steps down before exhaust).

l I 0422Y Rev. 2

15737-2-G03-107 2.3.2 Other Major Systems 2.3.2.1 Compressed Air The conpressed air system consists of compressors and an air purification package. Compre'ssed air for the WHPF is provided by two 100 cfm, 125 psig, compressors located in the equipment room.

An air distribution system is provided throughout the facility. The compressed air furnished is primarily for tools used in the facility. The system is also capable of providing breathing quality air when used in conjunction with the air purification package and appropriate radiological control procedures. Breathing air may be required during certain sectioning processes. Condensate drained from the compressed air system will be routed to the sanitary drainage system.

2.3.2.2 Demineralized Water Demineralized water is provided for system make-up by processing domestic water within the WHPF. This processing equipment consists of replaceable / rechargeable de-ionizing resin tanks and associated piping and accessories. Water is routed through a distribution system to the decontamination area and battery charging area of the WHPF. Controls limit to 50 gallons the amount of water that can be supplied to the process area without resetting the controls. Resin regeneration will not be done in this facility.

i 2.3.2.3 Fire Protection A sprinkler system will cover the entire facility. The system shall conform to the applicable portions of National Fire Protection Association (NFPA) chapter 13.

The system will consist of 1650F fusible sprinkler heads, piping and fittings, isolation valve with tamper-proof switch, and an adjustable time-delay action deluge valve with abort switch. The deluge valve will be actuated by a signal from a heat or ionization detector, or manually. The sprinkler system shall be for ordinary hazard (group 1).

The building shall be zoned as required. Heat detectors set for 1650 F shall cover the disassembly and sectioning area. The rest of the facility shall be covered by appropriate ionization detectors. Audible fire alarms, which are activated by the detectors, shall annunciate simultaneously at the local panel, and in the plant main control room. Signals for trouble, alara, and system discharge shall be annunciated. All wiring shall be supervised. A signal from any detector shall initiate the alaras and the time-delay action to open the deluge valve. Auxiliary contacts shall be provided in the panel to shutdown the HVAC system.

!- 0422Y Rev. 2

_1_

15737-2-G03-107 Fire hose standpipes will be provided in conformance with the applicable portions of NFPA Codes and Standards. Fire hose racks with hose and fog nozzles will be provided as required by the NFPA Code.

In addition, portable fire extinguishers are provided throughout the facility in accordance with NFPA Codes and Standards.

2.3.2.4 Waste and Drain; Systems A sanitary drain system from the toilet area of the WHPF will be routed to the plant sanitary system. Clean, uncontaminated condensate from the HVAC system may also be discharged to this system.

Spills or leakage within the process area from processing equipment, the demineralized water system and from the sprinkler system will be contained in the individual areas and will not be discharged into this waste and drain system.

2.3.2.5 Domestic Water System Domestic hot and cold water will be provided to the toilet area.

Demineralized water will be processed from domestic water.

2.3.2.6 Electrical Electrical service is provided to supply power for lighting, receptacles and electrically operated equipment. All electrical equipment, structures and metal components are grounded.

2.3.2.7 Communications The WHPF communication system interfaces with the existing plant PA communication system.

2.3.2.8 Radiation Monitoring A portable airborne radioactivity monitor with local readout and alarm is provided for personnel protection. Each exhaust to the atmosphere is isokinetically sampled for particulate activity. Each exhaust monitor is provided with local alarm, readout and recorder, and remote alarm in the main control room. Portable monitors will be.used as required. Area radiation monitors will be provided as required by radiological control procedures.

Air samples from the building exhaust, which are used to assess radiological releases to the environment, will be analyzed for alpha activity. In the event any of these samples shows a significant increase in the frequency of alpha detection, the level of analytical scouting for the alpha emitters will be increased appropriately to address the situation. 0422Y

~

Rev. 2

gl:I I [:[f !y

'IgllIIlI l!! !!I!! "! d li I

ll I

illliiltl!l!II,lllllSIllI!III!

Alii'l'i Mi ilhI!.I@h.!!!!.!.!.!.l.l!.!.!!.!.!.!!.

_.~T,, )

~

i ih.!.!!.!.!ii.i.ii.li.!!!.........i.l.i..i.l.d..!.!.

,c.

s.

c. ys

.~

.I '

l.Y

_ :://

(..

e t

-- --==4y.C

,f p

.rlI H;

M:. '.

l r.

!n !

i..

g 1

0 I

i e

i i

)'.'.

J,.

?

/

I u

i k

]

i f

I

~

i

/

jl,!

l

?.-

a 3

r i

I l

j i

[Ih;:-

3 y

{

l r!

.ls.i Y, i

bs l

n..

ik:eddss=ms'# hi..-, Ne e

lf.

js===w =N P#O\\.:

aj

'i

i.

J;!

.[..;.f',tiEf.r

._a

'.'\\

!... ;- \\

0i it i

?.

t

?q s.

=

g I.l,5le),".# k i. 5_,<

... JJ

'b - - }d =

-}

e, n, / f,r"q=k'l' J k-il' . 2 i ' '. 9 6 jjlpl* r= ll{r - r.- ..b{ 5,c <-. p. t .t ^ ' ' . j if g g., Y s w b i-f;,&f.\\ ll, 3 J 7. d %.. Is ./ /jl o; i,r n,}-t.. W..- s.',1(1 ..-s ,b,, .O e h, =**$~E'h,.F."=i j .m o l.# / x ::a' yy [h - g .! Q 'l j' d g- - U;Q ,y 9 ,/ I l l l 1 O N ' 1 'Plc fi; i f I!! l l J 1 t t. 1

- V

~05 l./' ~ I J. J

== j < l liii,j lll! Ihf - 9 / 1 ( J t<

• h

/ J llm i!!l!ni!di 1 (i 'O - y ~ yyj~- 'b C']'. Jy,; i.. ) ofit!!! p 7 i ~......... .. ~

i 1 a s I u4 .t E; (sl .=_ r .%a - cu e.n o w w o z y e c!ssisivety e aoa r * ' c av : =c g b b, ns.r.asW ud[% !{ I cY A e r i { ,/ s:n

--]

k ] 4* /' I @ b I ////////////. 5 U s:=% 'a I NS,,.,.,,.._ L .re, g a

,":.t" 1

7. I =- - L*1 J = - '<> 1, g,.,..,,. w,, .a 3 t ar t m *: i CD I s v .s, u. m.. s _ m u. / / l l.- w% f mm 1 r a Q W g stia t.s.ca-s' 1 w. //// > I/ 4 %= a fp g ET r 7 2 y..... m J 1 5t -,A .C1 I g as3 S N' -1 b.a.,a6en s =c e

=

~ j .as L. ma g,ss,s 1, n g =O [( O 5 0,.. {, -. ~ m

• '"**.*.,"j'.'.."

8 I t. ' p.,,,i ;.,., ..........a ) _ P~ 4 l ce=atece 8 Q "UI "O 8 CD e. E 8O .se.ias g e u au.a or ] ~ -" 7 ,,r w.,.: -f:::.-. -

~ n,; ~_

iXI _t. e 6 - 0 g I k p"" M*'"" vtNetNG aats l r r "5 ! (;;.T:#'J':23. ,,, Q

• 1

== a's

• g enter j

o e i,, I / i ..... / EQ - o 6 1 '. 3.. g aa.. ..as .m - te e l l 1 ..r= o-8 CD 4- ) [-;; ' e o o O o y. l l (/ N _/ .u. m==. - I; 5 3 i i PLAN e EL. g 3 g, s 1 s a 9 em. ors..e EJ.4ae.6%e. a***

.b ' l d oi . 4. e H b' 32 ::"a'."..., W t igg I .[ j %l [o.4%T w.u a .m 4 m.a Ms as. - i i ... m w 4 yK. 4*% 'W o96%IQOOI.. KEY PLAN nL. f'.c, f '~J=1Y ='%. g ~ uma s g....u, >== e i ,. m.,s.n. c= m. G u.. .u, i g h [Tu,,g g. .u, -+ A s. ...u, ff "a^v g; 0 -=== im. -n..u, ,h - %,,. m. jp&l A gu. U,,... F =.;- CEccNu,*y*Tf"**ta g Eh Q.. g., , g., - - '==.: :re, w '- J. BDCD gyj

e..... ~,.

mo I I. race,. l 0 f , c..... -. su .u s

o...O.~.u, 11."1.. EQ{ (b

' ' = ' ' *

• 6'" *;u ",;,:.a'* **"***.*.=*"~*~. -

J y k ";:.~ A+1 0* cyg ;;ma l..,,=.,;. @ q,O f .wo. 3.gg = g.. po. ;;, y u/// ui///n n in /,4,o///////n n d 9 r rrn M U Chb [ $NM ,A' ".C,l" /,

=

>-mv. 3

• • • • k*-'8**'**'"
• 5*

./ 'U.'4.r e .s E1I. Neg-Ctwaacv' t sTa: sm as3. W j ...... e P act ac !.%. co .N-T

.4 e..M... g "%v.;i

% -'c-t u

• 'r L' "

w CD '

• q

"Q'p*

gIh' v.. := et ee..t m3 ute m.tt. Q L' ! / /, ' / >=m.=-. // / //////l1a mr . - ~ p.,p e s:3 cc -,t tt -{ { H =n;;; m.,., 9 ,.s.- eesva e artog Pim b4; g,,ygy.,, Mn enco y _,q-APERTURE = =::.4.... N' CARD n e. _,. N myy .. ~. Also Available On

1. "4'#' "*T"

'rm 3 8-twe ce,% oust-A erture Card P NcTE s, C te.n.ew<wv see. . u.':'.7.*#.C **l.S*."':"'c*'.'.**;*s5"i.m.u..'....... ...:. 4 F. s' r T ...,..C..,., l 'i' l 3 w' ia-. -+

.,=. r,:::: a<a.u,

• • !:*4:'t!!',t.*Q',1*. ".ws a n x t.=e e,A.P.M'.;.: g%

T 7"ia.* *.">!J.J A*Ji2* u.m ...,.=,..,,.,,me.,u.=.u..s,e ~ ......,.s... as 1 -. l/ u.m... PEF. DWG. r __ } .a ~ .4,.

m. m.

l b '""a= .' L.'.%. 3 Al'el III II H Al'el Iii i l (- -.-,c= <ye,.... ap% .... =:.. ; ,.m BECK 12L cat ra.nac.c.. ,t..e 5l//Q%/{ 6( pp d Gi-u NuCLLAA WETRCPCLITAN E3*1CN , yg THREE MILE l$LANO - Umtf 2 ,,,,,,,,ot,,,,,,co w,e,,c,t,,, 3 Figure 2 ARRANGEtaEh! CF ECUIPMENT AM3 SERV!CES Location of WHPF and Location of Equip 7ent e.... c...~.. l 15737 l 2-POA-9721l C . - - -w + u i 3 i 2 i=...,.. i

3.0 Technical Evaluation 3.1 General This section summarizes the safety issues which were considered in the design of the WHPF. These issues deal with the expected performance of the facility:during normal operations and various design basis events. The safety issues associated with the operation of the WHPF are: o Demonstrating compliance with 10CFR20 with respect to on-site dose limits, o Demonstrating compliance with 10CFR50, Appendix I, with respect l to offsite radiation doses due to releases of radioactivity to the environment from normal operations within the WHPF. o Assessing the consequences of potential accidents in the WHPF that could lead to radioactive releases to the environment. o Demonstrating compliance with the principles of ALARA. Each of these issues is addressed in the following sections. 3.2 Dose Assessment and Accident Analysis 3.2.1 On-Site Dose Assessment The WHPF exterior walls will be reinforced concrete or grout filled CMU blocks and will be 10 feet high. These walls will be thick enough to ensure that the direct dose rates from material in the building will not exceed the following-dose rates: Dose Limit Minimum l Wall Thickness -outside building 2.5 area /hr 12 inches -site boundary fence 0.6 area /hr 12 inches These wall thicknesses are based on the dose rates from 20 drums, each with a contact dose rate of 100 arem/hr in 2 rows, stacked 2 high, staged adjacent to the wall. The calculation of the dose rates was performed using an interactive computer program designed to solve gamma ray transport problems using the point kernel method. Any response function can be calculated by specifying appropriate conversion factors and Berger buildup factor parameters. The program library contains attenuation coefficients and buildup factor parameters for common shielding materials, and 0422Y Rev. 1

15737-2-G03-107 y dose equivalent and absorbed dose conversion factors. The problem geometry must be described by a set of up to 15 orthogonal slabs, right cylinders, and/or right parallelepipeds. These assumptions are also used in calculating the wall thicknesses required to ensure that the following dose rates within the facility are not exceeded: Dose Limit Minimum Wall Thickness -Personnel access area 1.0 mrea/hr 15 inches -Administrative area 0.5 area /hr 15 inches -Office 0.25 area /hr 15 inches -Equipment area 2.5 arem/hr 12 inches The wall for the personnel access area will be filled CMU block. The other walls will be formed or poured concrete. Since radiation field strengths are not precisely known for components that may be staged or processed in the WHPF, temporary shielding and/or administrative controls may be required to. limit the radiation field directly outside the WHPF. This may include limiting personnel access to particular areas outside of the WHPF to prevent unnecessary personnel exposure. Administrative controls will be in accordance with radiological control procedures. 3.2.2 Off-Site Dose Assessment j 3.2.2.1 Normal Operations 3.2.2.1.1 Airborne Dose TheheadlingofcontaminatedmaterialintheWHPFwasevaluatedto determine the resultant offsite doses from airborne activity released Trom the facility. The only source for airborne radioactivity in the WHPF will be the result of activities related to processing contaminated material from the reactor building and 1 AFHB. To assess this dose, the following assumptions were made-a. The material staged in the separation, segregation and survey area and in the non-compactible staging and packaging area of the WHPF is radiologically clean, that is, it will have a { smearable surface activity of less than 500 dpa/100 cm2 gf y 2 ) activity and less than 100 dpa/100 cm a activity. b. The total annual activity available for release from dry active waste and contaminated tools and equipment being processed in j the contaminated areas of the WHPF is equivalent to the - activity of: 3 120,000fj dry active waste (DAW) 141 Ci 12,000 ft contaminated tools and equipment 52 Ci (ref. 1) i This includes transuranic activity on the contaminated material. 0422Y Rev. 0 ~. -

Of this activity 10-6 is released due to material handling. c. -This release fraction is based on the airborne release fraction due to a drum containing compacted waste breaking open through impact (ref. 2) for all material handling except sectioning. The 10-6 release fraction from sectioning is based on the release fraction from'-shattered contaminated concrete (ref. 2) and,'further. considers the fact that only a fraction of the equipment and tools will be sectioned. d. The assumed isotopic distribution of radioactive waste is l listed in Table 3-1. The fission product distribution is based on historical data, and the distribution for transuranics is based on calculated predictions of core inventory. l l Table 3-2 lists the estimated annual airborne releases based on the above assumptions. l The dose to the public was calculated for these releases based on the following parameters. a. The nearest milk cow is located 1.1 miles east of the release 4 point. The corresponding meteorological dispersion and deposition parameters at this location are 6.91 x 10-6 sec/m3 and 2.05 x 10-8/m2 for X/Q and D/Q, respectively, at this location. b. The nearest residence and garden are 0.4 mile south-south-east of the release point. The corresponding meteorological parameters are 5.57 x 10-5,,e/m3 and 2.10 x 10-7/m2 for X/Q and D/Q, respectively, at this location. c. The nearest meat and milk goats are 1.2 miles north of the release point. The corresponding meteorological parameters are 7.83 x 10-6,,c/m3 and 1.71 x 10-8/m2 for X/Q and D/Q, respectively, at this location. d. The vegetable intake for the individual of interest is assumed tc be from the location of the nearest garden. e. The dose rate from the ground plane source was calculated based on the location of the nearest residence as described in b. above. The locations.were obtained from a table of receptor locations and the meteorological parameters were obtained from the TMI-Unit 1 Offsite Dose Calculation Manual (ODCM), and are applicable to Unit 4 2. The resulting annual dose to the maximally exposed individual is summarized in Table 3-3. r The most restrictive dose is to a child's bone. It is estimated l that this dose will be 1.4 x 10-2 ares /yr when the,vilk consumed

0422Y Rev. 2 x-

=

==

15737-2-G03-107 is f rom a cow and 1.9 x 10-2 mrem /yr when goat's milk is consumed. These doses are less than 0.5% of the 10CFR50 Appendix I limits for the site. 'If credit is taken for the HEPA filters in the WHPF ventilation exhaust these annual doses will be further reduced by a factor of 1000, The average' particulate release from the WHPF is 6.1 x 10-6 pCi/sec. _This is a very small percentage of the Technical ' Specification limit of 2.4 x 10-2 pCi/sec for particulates. 3.2.2.1.2 Skyshine and Direct Dose-Rate The whole body dose to a member of the public from all sources in .the fuel cycle is limited to 25 mrem / year by 40CFR190. An analysis was made to determine the contribution to this dose from operation of the WHPF. Both direct and air-scattered (skyshine) radiation were considered in this analysis. The following parameters were used: a. The WHPF is in the S and SSE sectors. The nearest residence for these sectors is in the SSE sector and is 0.4 miles from the facility; b. Credit was taken for 12 inch concrete outer walls of the WHPF, but no credit was taken for inner walls or roof; c. A total source of 2.51 x 1011 gamma /sec is used for the skyshine analysis. This source term includes the contribution from all sources within the WHPF that contribute to the skyshine dose (e.g. waste containers, equipment, etc.); d. The direct offsite dose is from drums staged in the WHPF with a contact dose rate of 100 arem/hr; e. These activities are conservatively considered to be 100% Cs-137. f. An occupancy factor of 0.7 at the residence was assumed. The skyshine dose calculation was performed utilizing a previous skyshine calculation done for the Interim Solid Waste Staging Facility (see Ref. 6). This calculation used a point-kernel theory computer code which accounts for the scattering in air. The degradation of the scattered photon's energy is determined from the incident energy and angle of scatter of the uncollided photons. The Klein-Nishina differential scattering cross section formulation is used to assess the probability of scattering from the differential scattering volume (air). Multiple scattering in air is also accounted for by applying a buildup factor. .. 0422Y Rev. O s.

The total annual doss to a member of the public was calculated to be 0.6 mrem. This annual dose is at a distance of 0.4 miles from the WHPF. However, the distance to the nearest residence from the site is measured from the mid-point between the TMI-1 and THI-2 reactor _ buildings. The WHPF is approximately 0.5 miles from this 1 residence. Therefore the dose contribution to the nearest residence to the site resulting from the operation of the WHPF will be a small fraction of the 40CFR190 limit of 25 mrem / year. 3.2.2.2 Contaminated Material Fire i For the purpose of evaluating the consequences of a potential fire in the WHPF the following assumptions were made: a. The total activity assumed available for release in a fire is the total activity of the staged material (from ref. 1), both awaiting processing and awaiting shipment, plus the expected activity (1/7 of staged waste awaiting processing) from waste and equipment being processed. The total activity available for release is 7.6 Ci, of which 2.8 Ci are from waste in sealed containers awaiting shipping, 4.4 Ci are from waste awaiting processing or being processed and 0.4 Ci are from the decontamination equipment. Of this activity 3.9 x 10-3 Ci l are from the transuranic contamination assumed in the DAW and l on the tools and equipment. The isotopic distribution of this waste is listed in Table 3-1. b. Release fractions of 10-3 for waste in sealed containers and 10-2 for decontamination equipment and contaminated tools, equipment and waste awaiting processing or being processed were used to estimate the airborne release (ref. 2). c. No credit was taken for HEPA filtration or the WHPF building. d. Accident breathing rates were used (ref. 3). The resulting inhalation dose was calculated using the 1-hour meteorological dispersion parameter (X/Q) of 6.1 x 10-4 sec/m3 for a ground-level release. This is discussed in Appendix 2D of the Three Mile Island Unit 2 Final Safety Analysis Report (FSAR). The resulting doses are tabulated in Table 3-4. i The maximum expected offsite dose in the event of a fire in the WHPF will be to a teenager's bone. This dose is 9.07 ares (including 1.84 mrem from transuranics), which is a small fraction of che dose limits set by 10CFR100 for a comparable limiting organ or whole body. l For the purpose of this TER, the acceptance criterion for the l-offsite dose due to a fire in the WHPF is 15 millires to any organ. The quantities of radioactive materials specified in this section are maximum expected activities based on conservative estimates of waste materials anticipated to be present in the WHPF at any time. However, any mix of radionuclide activities is considered acceptable to be present in the WHPF, provided that the maximum calculated offsite dose due to a fire does not exceed 15 millires to any organ, based on assumptions b., c. and d. provided above. I 0422Y ~ i l Rev. 2 .= = w -

: = C.2 :

= = : L - - - - - J L.-

15737-2-G03-107 3.2.2.3 Liquid Spill from Processing Equipment For the purposes cf evaluating the consequences of an airborne release from a potential spill, or leakage, from the processing equipment in the WHPF the following assumptions were made: a. It.is assumed that the total content of all tanks in the ~ process area is spilled. This results in a total of 0.34 ci available for release based on each tank and filter having a contact dose rate of 50 mrem /hr and a 100 mrem /hr contact dose rate for the ion exchangers. The isotopic distribution is assumed to be 90.6% cs-137, 4.6% cs-134 and 4.8% Sr-90. l Transuranic isotopes are not considered to be routinely present in the decontamination equipment liquids. b. The HEPA filter in the ventilation exhaust was not considered in estimating the doses from the airborne release from a liquid spill. A release fraction of 10-4 was used, based on the airborne c. release in a liquid spill (Table 7, ref. 4). d. Accident breathing rates were used (ref. 3) The resulting inhalation dose was calculated using the 1-hour meteorological dispersion parameter (X/Q) of 6.1 x 10-4 sec/m3 for a ground level release. This is discussed in Appendix 2D of the Three Mile Island Unit 2 Final Safety Analysis Report (FSAR). The resulting doses are tabulated in Table 3-5. The maximum expected offsite dose from an airborne release resulting from a liquid spill in the WHPF is 5.28 x 10-3 arem to a teenager's bone. The HEPA filter in the WHPF exhaust ventilation was not taken into consideration in determining the doses from a liquid spill. If credit is taken for the filter the dose will be reduced by a factor of 1000. Although transuranics are not normally expected to be in the decontamination liquids, the offsite doses due to transuranics in the liquids are bounded by the fire analysis. An evaluation was also made of the effects of liquid effluent from a potential spill or leakage. In this evaluation the following assumptions were made. a. Liquid in the decontamination equipment has a total activity of 0.34 ci, as explained for the airborne release from a liquid spill. It is all released in the liquid effluent. The volume of the liquid is estimated as approximately 2000 gallons. b. The isotopic distribution is assumed to be 90.6% co-137, 4.6% l cs-134, and 4.8% Sr-90. Transuranic isotopes are not considered to be routinely present in decontamination equipment liquids. j 0422Y Rev. 2 J

c. The entire liquid volume is released to the east channel, and l no dilution of the effluent occurs in the east channel. The river flow is 10,000 cfs at the dam elevation (ref. 5 Figure 2.4-6). A dilution factor is applied for mixing with the river beyond this point. This factor is 3.1 x 10-7 and is the ratio of the flow rate of contaminated liquid over the dam in the east channel aIid the flow rate of the river. This effluent will be diluted by mixing with the Susquehanna River s water. The resulting concentrations are listed in Table 3-5. Criteria are given in 10CFR20, Appendix B, based on the concentration of an isotope (C ) and its maximum permissible 1 concentration (MPC ), for which an isotope may be considered not 1 present in a mixture. These criteria are: CA MPCA 1 0.1 and CA + C3 +... < 0. 25 MPCA MPCs is 2.4 x 10-3, for Sr-90. Application The greatest C /MPCA A of the second criteria results in a sum of 3.0 x 10-3 As both of the criteria are met for a spill from the decontamination equipment in the WHPF, this release does not need to be considered in calculations of doses from liquid effluent releases. Although transuranics are not normally expected to be in the decontamination liquids, the above criteria are still met even assuming all transuranic activity evaluated in the fire analysis is present in the liquids. 3.3 Occupational Exposure ~ Minimization of personnel radiation exposures is a primary consideration in the design of the WHPF. The design and operational philosophies for the facility follow the guidelines set forth in NRC Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable," Revision 3, June 1978. This section describes the design features that are provided to ensure that exposures are ALARA. 3.3.1 Layout The WHPF general arrangement provides for separation of higher radiation areas from lower radiation areas. This separation is achieved through distance and through the use of physical barriers for shielding and minimizing the spread of contamination. For example, the compacting area is separated from the non-compactible staging and packaging area by a 12 inch grout filled CMU wall. Decontanication equipment is consolidated in the area reserved for decontamination equipment, and can be surrounded by temporary shielding, as necessary. This shielding will protect personnel in the contaminated work area from this potential source of direct radiation. 0422Y Rev. 2 . ~,.-, - :- .- -. z. a :....:.. -.. ... ~. -

15737-2-G@3-1@F Personnel access to and from the WHPF is provided through the office, in the administrative area, and chrough the receiving and shipping area. Access to the separatior., segreg.ition and survey area is from the administrative area an1 tre receiving and shipping area. Personnel access to the equipmert room is through the administrative area. These areas of the WHPF will have the lowest general area radiation levele 3.3.2 Shielding Shield walls inside the WHPF include the grout filled CMU walls around the compacting and decontamination areas. This shielding, coupled with appropriate health physics control of each area, provides assurance that occupational exposures will be minimized in these areas. The 15 inch thick concrete shield wall separating the administrative area and equipment room from the remainder of the facility will be a minimum of 10 feet high. This will ensure that dose rates of 0.5 arem/hr in the general administrative areas, 0.25 arem/hr in the office and a dose rate of 2.5 mrem /hr in the equipment room are not exceeded. The grout filled CMU block shield wall around the personnel access control area will be a minimum of 15 inches thick and 10 feet high. This will ensure a dose rate of 1.0 arem/hr is not exceeded in this area. Separate, shielded areas are provided for staging containers of waste that have a contact dose rate in excess of 100 mrea/hr, and for taking smears from and surveying containers. Exterior concrete walls will be 10 feet high to satisfy radiation shielding requirements for uncontrolled areas outside the WHPF. The requirement to design the facility so that the radiation field on the outside of the facility is maintained at no greater than 2.5 area /hr will ensure that the radiation field will not exceed the 0.6 arem/hr limit established for the site boundary fence. Since it is not known precisely what radiation sources will be introduced into the WHPF during the recovery, temporary shielding or restricted access both inside and outside the WHPF will be used as necessary to ensure compliance with the dose rate criteria. Figure 2, Layout of WHPF and Location of Equipment, provides additional details on the location of shield walls. 3.3.3 Airborne Contamination Control The WHPF ventilation system is designed to draw air from areas of low potential for contamination to areas of higher potential for contamination. Air from contaminated, or potentially contaminated areas will be filtered by HEPA filters prior to recirculation or discharge to the atmosphere. Radioactive waste and equipment entering the WHPF will be packaged or wiped down to ensure its 0422Y Rev. 2

15737-2-G03-107 o surface activity does not exceed 500 dpa/100 cm2 B/Y activity 6 or 100 dpa/100 cm2 m activity. All material staged in the staging areas will have a surface activity that does not exceed 500 dpe/100cm2 8/Y activity or 100 dpa/100 cm2 a activity. Separate hoods will be used as required for inspection, compaction, 4 sectioning and decontamination. Individual HEPA filters are incorporated into the design of the compactor and in the hood over the inspection table. 3.3.4 Radiation Monitoring The radiation monitoring system,' described in Section 2.3.2.8 will alert personnel to abnormally high airborne radiation levels. Steps can then be taken to minimize personnel occupancy in the affected areas or to reduce the airborne levels as appropriate. Additional radiation monitoring equipment will be provided in accordance with existing radiological controls procedures. 3.4 Design Conditions The design conditions which must be satisfied are specified in the TMI-2 GPDC. These fall into three categories: normal operation, incidents of moderate frequency, and infrequent incidents. Each of these categories is addressed below. 1 3.4.1~ Normal Operations J Normal operation conditions are discussed in the previous ' sections. These operations will be carried out without unplanned or uncontrolled releases of radioactive materials to the l [ environment. 3.4.2 Incidents of Moderate Frequency The WHPF and the equipment provided with the WHPF serve no nuclear I safety felated functions and since there is no interface with any 1 safety system, it will not interfere with the performance of any safety related feature, such as safe shutdown systems. The effects of loss of electrical power in the WHPF, inadvertent actuation of a component provided with the WHPF, single operator error associated with the operation of the WHPF, or a single failure of an active component in the WHPF, such as the HVAC, are enveloped by the analyses of infrequent incidents. They will not, therefore, i , endanger the health and safety of the public. Normal operations in the WHPF will involve the handling of contaminated. radioactive material. During the course of handling l the packages there is the possibility that a package could be broken open. This would not result in an uncontrolled release of radioactivity to the environment because of the design of the HVAC system, discussed in Section 2.3.1. Releases of radioactivity to the environment would be minimized by the filters in the filtered exhaust system provided with the WHPF. The result of a package breaking open is enveloped by the normal release calculation. 3.4.3 Infrequent Incidents 1 0422Y 4 Rev. 2 -.J

15737-2-G03-107 3.4.3.1 Tank Rupture or Pipe Break Tanks containing liquid are located in the decontamination room (decontamination equipment and rinse tank). Demineralized water will be connected by. pipes from the domestic water inlet, through the.lon exchanger and to equipment, as required. The decontamination area is surrounded by a concrete curb which prevents any spill in this area from flowing into other areas of the facility. Any spill from a pipe leakage in areas other than these will be manually cleaned. Potential offsite doses from a spill of contaminated liquid have been previously evaluated (see Section 3.2.2.3). 3.4.3.2 Fire An automatic water suppression system and portable fire extinguishers are provided to extinguish any fire within the WHPF. The radiological effects offsite from a fire in the WHPF are discussed in sections 3.2.2.2. 3.4.3.3 0he$a5ingBasisEarthquake(0.B.E.) In the event of an 0.B.E. it is postulated that containers of waste and the decontamination equipment will rupture. The effects of this are enveloped by the liquid spill and fire analyses. . 0422Y Rev. 0

s' 15737-2-G03-107 7 ( < Table 3-1 Isotopic' Distributions in the WHPF .5 TEansuradic Activities Isotope Percentage Pu-238' O.55 Pu-239 6.2 g: Pu-240 1.6 Pu-241 5 91. Am-241 0.65 Non-transuranic Activities Cs-134 4.6 Cs-137 90.6 Sr-90 4.8 s 's s x 'A i 6 0422Y Rev.' 0 s O _f.'* _ 1_

15737-2-G03-107-TABLE 3-2 CALCULATED ANNUAL AIRBORNE RELEASES FROM THE WHPF ~ 1Radionuclide-Annual Release (curies) ~ Cs-137 1.75 x 10-4 Cs-134 8.88 x 10-6 Sr-90 9.27 x 10-6 Pu-238 5.70 x 10-10 Pu-239 6.42 x 10-9 Pu-240-1.70 x 10-9 Pu-241 9.44 x 10-8 .Am-241 6.79 x 10-10 . 0422Y ~ Rev.-0

v.

, f i..,. - - ~

~~ ^ ^ ~ 15737-2-G03-157 TABLE 3-3 5' ESTIMATED ANNUAL DOSE TO THE MAXIMALLY EXPOSED INDIVIDUAL FROM RELEASES FROM THE WHPF 1. Annual., Dose:-from Inhalation, Vegetable Intake, Cow Milk, and Ground Plane ' Dose to Organ (mrem /yr) ' Age Group Bone Total Body 1 ggL Skin Liver. 3 Adult ~ 1.09E-2 4.70E-3 1.98E-3 1.76E-3 4.20E-3 Teen 1.04E-2 3.84E-3 2.25E-3 1.76E-3 4.86E-3 Child 1.44E-2 3.82E-3 .2.41E-3 1.76E-3 6.46E-3 Infant 7.55E-3 2.09E-3 2.32E-3 1.76E-3 7.09E-3 II. Annual Dose from Inhalation, Vegetable Intake, Goat Milk, and Ground Plane Dose to Organ (mrem /yr) Age Group-Bone Total Body 1 gyL Skin Liver 3 Adult-1.20E-2 5.64E-3 2.13E-3 1.76E-3 5.57E-3 Teen 1.24E-2 4.75E-3 2.57E-3 1.76E-3 7.26E-3 Child 1.90E-2 4.54E-3 2.90E-3 1.76E-3 1.06E-2 Infant 1.48E-2 2.78E-3 3.19E-3 1.76E-3 1.51E-2 . 0422Y Rev. 0 cs s.

I ~ 15737-2-G03-107 -TABLE 3-4 INHALATION DOSE ESTIMATE AT THE EXCLUSION AREA BOUNDARY FROM A FIRE IN THE WHPF Organ ~ s' Controlling Age Group Dose (mrem) Bone Teenager-9.07 Total Body. Adult 0.93 Lung Teenager 1.27 Liver Teenager 1.25 0422Y 'Rev. 0 m.

F-15737-2-G03-107 ~~~~~ TABLE 3-5 ESTIMATED DOSE TO MAXIMALLY EXPOSED INDIVIDUAL FROM A SPILL OF CONTAMI,NATED PROCESS LIQUIDS IN THE WHPF Organ Controlling Age Group Dose (mrem) Bone-Teenager 5.28E-3 Total. Body Adult 6.50E-4 Lung Teenager 8.25E-4 Liver Teenager 7.44E-4 I 0422Y Rev. 0 _s,

IE 15737-2-G03-107 TABLE 3-6 CONCENTRATIONS OF LIQUID EFFLUENTS FROM A . SPILL.0F CONTAMINATED PROCESS LIQUIDS IN THE WHPF . MAXIMUM

• CONCENTRATION PERMISSIBLE CONC.

ISOTOPE (pCi/cc) (uCi/cc) Cs-137 1.34E-8 2.0E-5 Cs-134 6.81E-10 9.0E-6 Sr-90 7.llE-10 3.0E-7

• from 10CFR20, App. B, Table.II, Column 2

. 0422Y Rev. O r,_ j

'ag7337-34@3)-A@y r 4.0 Safety Evaluation 10CFR50, paragraph 50.59, " Changes, Tests and Experiment", permits the holder of an operating license to make changes to the facility provided the change does n'et involve a modification of the TMI-2 Technica1 Specifications and the change is determined not to be an unreviewed safety question. As summarized below, the operation of the'WHPF does not require a modification to the TMI-2 Technical Specifications and is deemed not to be an unreviewed safety question as defined in 10CFR50. 4.1 Technical Specifications / Recovery Operations Plan Operation of the WHPF with respect to staging and decontaminating contaminated material will not require a change to the Technical Specifications. The Recovery Operations Plan will be revised to include the radiation monitor for each exhaust to the environment from potentially contaminated areas or from decontamination equipment. 4.2 Unreviewed Safety Questions The WHPF does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Final Safety Analysis Report. As demonstrated in Section 3, the consequences of various accidents are well within acceptable limits. The only interface between systems provided in the WHPF and any Important to Safety (ITS) systems is for fire' protection. Tie-ins between the WHPF and ITS systems will be done in accordance with procedures approved for TMI-2. Therefore, the WHPF will not impact existing ITS structures or systems and there will be no increase in the probability of an accident or malfunction of equipment important to safety. The possibility of an accident or malfunction of a different type than any'previously evaluated in the Final Safety Analysis Report is not created by the existence of the WHPF. Also, the operation of the WHPF does not result in a reduction in the margin of safety as defined in the.TMI-2 Technical Specifications since the WHPF does not impact any systems covered in the technical specifications and any release of radioactivity from the WHPF will be monitored for compliance with TMI-2 Environmental Technical Specifications. Based on the above, the WHPF is deemed not to be an unreviewed safety question as defined in 10CFR50.

0422Y Rev. 2

= =. + L =-

g -v V ~ 15737-3-@@3-A@W '5.0 Environmental Assessment The activities associated with the operation of the WHPF have been evaluated to ensure that these activities do not pose unacceptable risk to the health and safety of the public and to TMI workers. In addition, these activities have been evaluated to ensure that the environmental impact from th'e operation of the WHPF is acceptably low and does not.significantly differ from the impact postulated for similar activities in the TMI-2 PEIS (ref. 7). Proposed activities in the WHPF are similar in nature to those activities associated with solid waste packaging and handling as described in Reference 7. Postulated releases of radioactive materials to the environment from the normal operation of the WHPF are presented and discussed in Section 3.2.2.1 of this TER. 'These releases are similar to those estimates in Reference 7, that is, normal activities should result in a maximum organ and whole body dose of less than 1 millirem to the maximally exposed offsite individual. It is worthwhile to reiterate that the doses reported in this TER do not take credit for the ventilation and HEPA filtration systems which will be operated in the WHPF. HEPA filters normally provide greater than 99.9% efficiency for'the removal of airborne particulates. Accident scenarios evaluated in this TER are presented and discussed in Sections 3.2 and 3.4. Offsite radioactive releases were quantified for a fire involving all contaminated materials in the WHPF and a spill of all contaminated process liquids. The maximum calculated offsite doses were for a fire and were 9.07 millires to the bone and less than 1 millires to the whole body. This is well within the limits for offsite exposures from accidents presented in 10CFR100, which are 25 rem to the whole body and 300 rem to an organ (thyroid). Reference 7 includes an estimate of offsite doses due to a fire in contaminated dry waste storage areas. The maximum offsite doses were greater than those calculated for the WHPF, that is, a maximum whole body dose of 6.5 millirem and a maximum organ dose of 30 millires were reported in Reference 7 (p. 8-70). Specific collective occupational exposures for the operation of the WHPF have not been calculated. The exposures will be maintained as low as reasonably achievable as discussed in Section 3.3 of the TER. The availability of adequate facilities for waste handling, such as provided in the WHPF, is important in maintaining low r-occupational exposures for these activities. Reference 7 estimates L a range of exposures from 39 to 99 person-rem for all handling and packaging of solid wastes. Reference 8 estimates 97 to 485 person-ren for radioactive waste management and transportation.. Handling and packaging of radioactive waste in the WHPF should not adversely impact the total collective exposures for these activities. i-In conclusion, the activities associated with the operation of the WHPF will have negligible environmental impact and will have no l unacceptable consequences to the health and safety of the public or to TMI workers. ! 0422Y Rev. 2

?

. - = :: -: L w r =:

-==-u-s' 15737-2-G03-107 6.0 References 1. " Technical Plan, Solid Waste Handling and Packaging Facility", Rev. O, Jan. 1985. 2. " Environmental Survey of Transportation of Radioactive Materials to and from Nuclear Power Plants", Wash-1238, December 1972. 3. Reg. Guide 1.4, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactor," Rev. 2, June 1974. 4. NUREG/CR-2139, " Aerosols Generated by Free Fall Spills of Powders and Solutions in Static Air", December, 1971. 5. TMI-2 FSAR 6. Technical Evaluation Report for the Interim Solid Waste Staging Facility, 15737-2-G03-105, Rev. 6. 7. NUREG-0683 Final Programmatic Environmental Impact Statement Related to the Decontamination and Disposal of Radioactive Wastes Resulting from March 28, 1979, Accident Three Mile Island Nuclear Station, Unit 2, March 1981. 8. NUREG-0683, Supplement No. 1 to the Final Programmatic Environmental Impact Statement, Final Supplement Dealing with Occupational Dose, October, 1984. 0422Y Rev. 2 .}}