Text

Proposed Tech Specs,Consisting of Change Requests 235 & 109, Incorporating Editorial Changes & Implementing Requirements of GL 95-05 for voltage-based SG Tube Repair Criteria
	ML20113B337
Person / Time
Site:	Beaver Valley
Issue date:	06/18/1996
From:	; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20113B333	List: ML20113B330; ML20113B337;
References
	GL-95-05, GL-95-5, NUDOCS 9606270055
	Download: ML20113B337 (200)
	v • d • e

_ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

ATTACHMENT A-1 l

Beaver Valley Power Station, Unit No. 1 Proposed Technical Specification Change No. 235 l

The following is a list of the affected pages:

Affected Pages: XIX 3/4 4-10 3/4 4-10a 3/4 4-10b 3/4 4-10c 3/4 4-10d 3/4 4-10g 3/4 4-10h B 3/4 4-2b B 3/4 4-3f B 3/4 4-3g l

9606270055 960618 (Proposed Wc~ ding)

PDR ADOCK 05000334 P PDR

DPR-66 Table Ind3x (cont.)

l TABLE TITLE PAGE 3.3-11 Accident Monitoring Instrumentation 3/4 3-51 4.3-7 Accident Monitoring Instrumentation 3/4 3-52 Surveillance Requirements 3.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-55 4.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-57 Surveillance Requirenents 4.4-1 Minimum Number of Steam Generators to be 3/4 4-10 l Inspected During Inservice Inspection 4.4-2 Steam Generator Tube Inspection 3/4 4-10/b l 4.4-3 Reactor Coolant System Pressure Isolation 3/4 4-14b Valves I

3.4-1 Reactor Coolant System Chemistry Limits 3/4 4-16 4.4-10 Reactor Coolant System Chemistry Limits 3/4 4-17 i surveillance Requirements 4.4-12 Primary Coolant Specific Activity Sample 3/4 4-20 and Analysis Program SMce 3.7-1 Maximum Allowable Power Range Neutron Flux 3/4 7-2 .

High Satpoint With Inoperable Steadline I

{

Safety Valves During 3 Loop Operation ,

! 3.7-2 Maximum Allowable Power Rahge Neutron Flux 3/4 7-3 l High Setpoint with Inoperable Steam Line .

l Safety Valves During 2 Loop Operation l l

3.7-3 Steam Line Safety Valves Per Loop 3/4 7-4 l 4.7-1 Snubber Visual Inspection Interval 3/4 7-31 4.7-2 Secondary Coolant System Specific Activity 3/4 7-9 l

Sample and Analysis Program t

3.8-1 Battery Surveillance Requirements 3/4 8-9a 3.9-1 Besver Valley Fuel Assembly Minimum Burnup 3/4 9-15 vs. Initial U235 Enrichment For Storage in Region 2 Spent Fuel Racks :

l l l 4

BEAVER VALLEY - UNIT 1 XIX Amendment No.

(PrcpssJ Wecd,j)

l DPR-66 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) ..

Catecorv Insoection Results l l C-1 Less than 5 percent of the total l

tubes inspected are degraded tubes and none of the inspected tubes are l

l defective.

C-2 One or more tubes, but not more than 1 percent of the total tubes inspected are defective, or between 5 percent and 10 percent of the total tubes inspected are degraded tubes.

C-3 More than 10 percent of the total tubes inspected are degraded tubes or more than 1 percent of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes or sleeves must exhibit significant -

(greater than 10 percent) further wall penetrations to be included in the above i percentage calculations.

4.4.5.3 Insoection Frecuencies - The above required inservice inspections of steam generator tubes shall be performed at the _

following frequencies: ggg (

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections ;

shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.

If two consecutive inspections following service under conditions, not including the preservice inspection, result j in all inspection results falling into the C-1 category or l if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

i

b. If the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 requires a third sample inspection whose results fall in Category C-3, the inspection frequency shall be r-duc-^ to at least once per 7

l hncreased -

l BEAVER VALLEY - UNIT 1 3/4 4-10 Amendment No. -144-(Propo3cd Wor

l DPR-66 l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) fjwgQ 20 months. The\ - M 4^r in inspection frequency shall

L J apply until a subsequent inspection demonstrates that a third sample inspection is not required.

c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

1. Primary-to-secondary tube leaks (not including leaks i originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2,

2. A seismic occurrence greater than the Operating Basis Earthquake,

3. A loss-of-coolant accident requiring actuation of the engineered safeguards, or 1 v

4. A main steamOline or feedwater line break.

4.4.$.4 Acceotance Criteria

a. As used in this Specification:

1. Imperfection means an exception to the dimensions, l finish or contour of a tube or sleeve from that l required by fabrication drawings or specifications.

l Eddy-current testing indications below 20 percent of I the nominal tube wall thickness, if detectable, may be considered as imperfections.

2. Decradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.

3. Decraded Tube means a tube or sleeve containing i

imperfections greater than or equal to 20 percent of t the nominal wall thickness caused by degradation.

l l 4. Percent Decradation means the percentage of the tube

' or sleeve wall thickness affected or removed by degradation.

5. Defect means an imperfection of such severity that it exceeds the plugging or repair limit. A tube

containing a defect is defective. Any tube which does

not permit the passage of the eddy-current inspection

probe shall be deemed a defective tube.

BEAVER VALLEY - UNIT 1 3/4 4-10a Amendment No. 4S4-(9toposed W o d m

DPR-66 l

[ REACTOR COOLANT SYSTEM '

SURVEILLANCE REQUIREMENTS (Continued)

6. Pluacina or Renair Limit means the imperfection i

depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving in the affected area because it may become '

unserviceable prior to the next inspection. The plugging or repair limit imperfection depths are !

specified in percentaga of nominal wall thickness as l follows: !

i original tube wall 40% ;

i This definition does not apply to tube support plate intersections for which the voltage-based l repair criteria are being applied. Refer to 4.4.5.4.a.10 for the repair limit applicable to these intersections.

} Babcock & Wilcox kinetic welded sleeve wall 40%

Westinghouse laser welded sleeve wall 25%

7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an i operating Basis Earthquake, a loss-of-coolant l accident, or a steamline or feedwater line break as

specified in 4.4.5.3.c, above. l

8. Tuba Insoection means an inspection of the steam generator tube from the point of entry (hot-leg side) completely around the- U-band to the top support to the cold-leg.

9. Tube Renair refers to slesving which is used to maintain a tube in-service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure. The following sleeve designs have been ,

found acceptable: ]

1 Babcock & Wilcox kinetic welded sleeves, BAW-2094P, Revision 1 including kinetic sleeve

" tooling" and installation process parameter

) changes.

4 l

l Westinghouse laser welded sleeves, WCAP-13483, !

Revision 1.

\

l l

BEAVER VALLEY - UNIT 1 3/4 4-10b Amendment No.He (fcopath M

DPR-66 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

10. Tube Suoport Plate Pluacina Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the plugging (repair) limit is based on maintaining steam generator tube serviceability as described below:

Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to 2.0 volts will be allowed to remain in service.

Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts will be repaired or plugged, except as noted in 4.4.5.4.a.10.c below.

) Steam generator tubes, with indications of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltagegreaterthan2.0voltsbutlesstp"anor equal to the upper voltage repair limit may remain in service if a rotating pancake coil or acceptable alternative inspection does not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion cracking degradation with a bobbin voltage greater than the upper voltage repair 3

limit will be plugged or repaired.

If an unscheduled mid-cycle inspection is performed, the following mid-cycle repair limits apply instead of the limits identified in 4.4.5.4 p10.a, 4.4.5.4 g10.b, and 4.4.5.4 10.c.

.d.

(1) The upper voltage repair limit is calculated according to the methodology in Generic Letter 95-05 as supplemented.

BEAVER VALLEY - UNIT 1 3/4 4-10c Amendment No.MG (Fr.pese h ADer

DPR-66 REACTOR COOLANT SYSTEM l

l l

SURVEILLANCE REQUIREMENTS (Continued)

The mid-cycle repair limits are determined from the l'ollowing equations:

V.z Vuun = -

- ' CL - A t*

1.0 + NDE + Gr s CL >

CL- At' han = Vutn-(Vcu-Vm) l < CL i l where:

)

Vme = upper voltage repair limit Vuc = lower voltage repair limit vast = mid-cycle upper voltage I

l repair limit based on time into cycle Vm23 = mid-cycle lower voltage i repair limit based on l Vams and time into cycle !

At = length of time since ;

last scheduled i inspection during which !

Vme and Vue were

, implemented l CL = cycle length (the time between two scheduled steam generator l inspections) l V,t = structural limit voltage t Gr' = average growth rate per i cycle length NDE = 95-percent cumulative probability allowance for nondestructive l -

examination uncertainty l (i.e., a value of 20- .

~

i percent has been approved by NRC) "3 Implementation of these mid-cycle repair limits should follow the same approach as in TS

! 4.4.5.43 10.a, 4.4.5.4g 10.b, and 4.4.5.43 10.c.

4 (2) The NDE is the value provided by the NRC in GL 95-05 as 4

supplemented.

BEAVER VALLEY - UNIT 1 3/4 4-10d Amendment No.44B (Propes5 UJoe

DPR-66 TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION OELETE ..

Preservice Inspection .

No a s f Yes s-f r

m f)

No. of Steam Generators per Unit 4we- J Three \_ JourJ - -@we Three .Ecur First Inservice Inspection All One Two -9we-t Second & Subsequent Inservice Inspections One (1) n"a f i-! )One (2). One '2]

. -DELETE Table Notation:

(1) The inservice inspection may be limited q to one steam generator on a rotating schedule encompassing 8-N percent of the tubes (*ecre " ir the number cf ctca- gencrcterc ir the p1=nt) if the results of the first or previous inspections indicate that all steam generators are performing in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

(2) The other steam generator not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in (1) above. ,

) Fach of the ether t':?e ctea= genercterc net incpected during the first inscryicc inspections chcIl Sc inapested during the cccend cnd third incpectienc. Thc fourth and subscqucnt incpectienc shall felle" the ine& m e&inne dac ~ihad in (1) nhnva-DEETEJ BEAVER VALLEY - UNIT 1 3/4 4-10g Amendment No.pyg.

(N(bpub Web

DPR-66 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION,,

Simple Size Result Action Required Result Action Required Result Action Required A nimum of C-1 None N/A N/A N/A N/A S es per S.G C-2 Plug or repair C-1 None N/A N/A defective tubes and inspect additional C-2 Plug or repair defective C-1 None 2S tubes in this S.G. tubes and inspect additional 4S tubes in C-2 Plug or repair this S.G. defective tubes C-3 Perform action for C-3 result of first sample C-3 Perform action for C-3 N/A N/A result of first sample C-3 Inspect all tubes in All other None N/A N/A this S.G., plug or S.G.s are repair defective C-1 tubes and inspect 2S tubes in each other S.G. Some S.G.s Perform action for N/A N/A C-2 but no C-2 result of second Notification to NRC additional sample pursuant to S.G.s are Specification 6.6 C-3 ,

Additional Inspect all tubes in S.G. is each S.G. and plug or N/A N/A C-3 repair defective tubes.

O Notification to NRC 3 pursuant to Specifi-cation 6.6.

= Where k ' - ' " - - - " - ' - ' - - - - - - - - - " - ' - ' " " ' ' -

n is the number of steam generators inspected n during an inspection.

~

OELETE BEAVER VALLEY - UNIT 1 3/4 4-10h Amendment No:f96-(fropq1NW '*j)b

DPR-66 REACTOR COOLANT SYSTEM BASES i

3/4,4.5 STEAM GENERATORS (Continued) ,

correlation and then the subsequent derivation of the voltage repair limit from the structural limit (which is then implemented by this surveillance).

The voltage structural limit is the voltage from the burst pressure / bobbin voltage correlation, at the 95-percent prediction' interval curve reduced to account for the lower 95/95-percent tolerance bound for tubing material properties at 650*F (i.e., the 95-percent LTL curve). The voltage structural limit must be adjusted downward to account for potential degradation growth during an operating interval and to account for NDE uncertainty.

The upper voltage repair limit; Vunn, is determined from the structural voltage limit by applying the following equation:

VURL " VsL - Vor - VNDE where vor represents the allowance for degradation growth between inspections and Vuos represents the allowance for potential sources of error in the measurement of the bobbin coil voltage. Further discussion of the assumptions necessary to determine the voltage repair limit are discussed in GL 95-05.

4 The mid-cycle equation in SR 4.4.5.4 10.d-should only be used j during unplanned inspections in which addy current data is acquired i for indications at the tube support plates.

i SR 4.4.5.5 implements several reporting requirements recommended by GL 95-05 for situations which the NRC wants to be notified prior to returning the SGs to service. For the purposes of this reporting requirement, leakage and conditional burst probability can be calculated based on - the as-found voltage distribution rather than the projected end-of-cycle (EOC) voltage I

distribution (refer to GL 95-05 for more information) when it is not practical to complete these calculations using the projected EOC voltage distributions prior to returning the SGs to service.

Note that if leakage and conditional burst probability were calculated using the measured EOC voltage distribution for the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, then the results of the projected EOC voltage distribution should be provided per the GL section 6.b (c) criteria.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to Specification 6.6 prior to

. resumption of plant operation. Such cases will be considered by i the Commission on a case-by-case basis and may result in a

! requirement for analysis, laboratory examinations, tests, l additional eddy-current inspection, and revision of the Technical l Specifications, if ne*cessary.

BEAVER VALLEY - UNIT 1 B 3/4 4-2b Amendment No.

(fryosd Web

i DPR-66 y,f & g g el ,& he.SC l10 lNlcaJ REACTOR COOLANT SYSTEM '

k 5u ek f Wllp e ~l?ase) slkmjed/h BASES i

3/4.4.6.2 OPERATIONAL LEAKAGE (Continued)

I APPLICABLE SAFETY ANALYSES (Continued) i affect the probability of such an event. The sa ty analysis for an event resulting in steam discharge to the atmo here conservatively j assumes a 10 gpa primar h @ econdary LEAKAGE.

] Primary 6,tchecondary LEAKAGE is a f r in the dose releases outside i containment resulting from a steamOline break (SLB) accident. To a i lesser extent, other accidents or transients involve secondary steam i j

' release to the atmosphere, such as a steam generator tube rupture l (SGTR). The leakage contaminates the secondary fluid. I ebb is more limiting ror sita[radi n releases. he safety, I

analysis for the%EsB accident assumes a && gpm primaryW I to O scondary LEAKAGE. a The d;;; ;;;;;;;;;;;; re;;1 ting fre; the OLO eCelcent ;;; ;;11 within th; li;it; defined in 10 OT 100 or the ;teff

ppr:v;d lic:::in; 52:10 (i.:., : 22:11 fr :ti n Of th;;; li;it:).

I 'A EFL ACE W iTH go (INsertT "A A"

. RCS operational LEAKAGE shall be limited to:

1 l

j a. Pressure _ Boundary J.ZAKAG.E l 1 i No pressure boundary LEAKAGE is allowed, being indicative of l

[ material deterioration. LEAKAGE of this type is unacceptable as the leak itself could cause further dricerioration, resulting in higher LEAKAGE. Violation of this LCO could

result in continued degradation of the RCPB. LEAKAGE past j seals and gaskets is not pressure boundary LEAKAGE. Should pressure boundary LEAKAGE occur through a component which can be isolated from the balance of the Reactor Coolant System,

plant operation may continue provided the leaking component is promptly isolated from the Reactor Coolant System since 4 isolation removes the source of potential failure.

l 5

4 d

i l 1 j I BEAVER VALLEY - UNIT 1 Amendment No.1:3 B 3/4 4-3f (brope.5=d d o

INSERT AA The radiological consequences of a MSLB outside of containment was reanalyzed in support of the tube support plate voltage-based repair criteria stated in SR 4.4.5.4.a.10. For this analysis, the thyroid dose was maximized at 10% of the 10 CFR Part 100 guideline of 300 rom. RCS leakage was based on projection rather than on technical specification leakage limits. The analysis indicated that offsite doses would remain within regulatory criteria with an increase in primary-to-secondary leakage to 4.5 gpm should steam generator tubes fail due to the depressurization associated with a MSLB.

A similar analysis was performed using a control room thyroid dose of 30 rem as the criterion. The control room was assumed to be manually isolated and pressurized at T=30 minutes for a period of one. hour, at which time filtered emergency intake would be automatically started. The control room would be purged with fresh air at T=8 hours following release cessation. The analysis ;

indicated that control room doses would remain within regulatory criteria with an increase in primary-to-secondary leakage to 4.5 gpm should steam generator tubes fail due to the depressurization associated with a MSLB.

(Proposed Wording)

DPR-66 REACTOR COOLANT SYSTEM BASES 3/4.4.E.2 OPERATIONAL LEAKAGE (Continued)

LCO (Continued)

b. Unidentified LEAKAGE One gallon per minute (gpm) of unidentified LEAKAGE is allowed as a reasonable minimum detectable amount that the containment air monitoring and containment sump level monitoring equipment can detect within a reasonable time period. Violation of this LCO could result in continued degradation of the RCPB, if the LEAXAGE is from the pressure boundary.

c. Primarv-to-Secondary LEAKAGE throuah Any one SG Maintaining an operating LEAKAGE limit of 150 gpd per steam generator will minimize the. potential for a large LEAKAGE event during a main steamline break. Based on the non-destructive examination uncertainties, bobbin coil voltage distribution, and crack growth rate from the previous inspection, the expected leak rate following a 5 steamline rupture is limited to %:1:r 4.5 gpm in the hessko of faulted loop. Maintaining LEAKAGE @ the 4.5 gpm g4 limit will ensure that postulatea offsite doses will

'76 remain within the 10 CFR 100 requirements and that control room habitability continues to meet GDC-19.

LEAKAGE in the intact loops will be limited to the operating limit of 150 gpd. If the projected end-of-cycle distribution of crack indications results in primary-to-secondary LEAKAGE greater than 4.5 gpm in the faulted loop during a postulated steamline break event, additional tubes must be removed from service or repaired in order to reduce the postulated steamline break LEAKAGE to ,be&ow 4.5 gym.

Also, the 150 gallons per day leakage limit incorporated ,

into this specification is more restrictive than the ;

standard operating leakage limit and is intended to !

provide an additional margin to accommodate a crack which

~

might grow at a greater than expected rate or i unexpectedly extend outside the thickness of the tube support plate. Hence, the reduced leakage limit, when combined with an effective leak rate monitoring program, provides additional assurance that should a significant leak be experienced in service, it will be detected, and the plant shut down in a timely manner.

)

BEAVER VALLEY - UNIT 1 B 3/4 4-3g Amendment No.Me

ATTACHMENT A-2 Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Change No. 109 yr The following is a list of the affected pages:

Affected Pages: 3/4 4-12 3/4 4-14 3/4 4-14a 3/4 4-14b 3/4 4-16 3/4 4-19 B 3/4 4-3 B 3/4 4-3a B 3/4 4-4e B 3/4 4-4f B 3/4 4-4g

MPF-73 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

1. All nonplugged tubes that previously had detectable wall penetrations greater than 20 percent, and

2. Tubes in those areas where experience has indicated potential problems, and

3. At least 3 percent of the total number of sleeved tubes in all three steam generators. A sample size less than 3 percent is acceptable provided all the sleeved tubes in the steam generator (s) examined during the refueling outage are inspected. These inspections will include both the tube and the sleeve, and

4. A tube inspection pursuant to Specification 4.4.5.4.a.8. If any selected tube does not permit the Aoo , i, passage of the eddy current probe for a tube or s1eeye WSEC inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c. The tubes selected as the second and third samples -(if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and psEn "6 2. The inspections include those portions of the tubes c where imperfections were previously found.

The results of each sarple inspection shall be classified into one of the following three categories:

Catecorv Insoection Results C-1 Less than 5 percent of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1 percent of the total tubes inspected are defective, or between 5 percent and 10 percent of the total tubes inspected are degraded tubes.

BEAVER VALLEY - UNIT 2 3/4 4-12 Amendment N o . Te--

repo M W e d l

- . - . .. - . . - .- ._ . = _ _. .-

INSERT A l

S. Indications left in service as a result of application of the tube support plate voltage-based repair criteria (4.4.5.4.a.10) shall be inspected by bobbin coil probe during all future refueling outages.

INSERT B

d. Implementation of the steam generator tube-to-tube

support plate repair criteria requires a 100-percent j bobbin coil inspection for hot-leg and cold-leg tube 4

support plate intersections down to the lowest cold-leg tube support plate with known outside diameter stress 1

corrosion cracking (ODSCC) indications. The l determination of the lowest cold-leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20-percent random sampling

, of tubes inspected over their full length, i

I i

l

)

4 l

t 1

1 l

f i

i l

4 I

1 i

i i

i 4

(Proposed Wording)

I

NPF-73 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

3. A loss-of-coolant accident requiring actuation of the engineered safeguards, or Y

4. A main steam 0line or feedwater line break.

s 4.4.5.4 Acceotance Criteria

a. As used in this Specification:

1. Imoerfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications. I Eddy-current testing indications below 20 percent of !

the nominal tube wall thickness, if detectable, may be .

considered as imperfections.

2.

Dearadation means a service-induced cracking,

wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve. ,

3. Dearaded Tube means a tiube or sleeve containing I imperfections greater than or equal to 20 percent of !

the nominal wall thickness caused by degradation.

4. Percent Dearadation means the percentage of the tube or sleeve wall thickness affected or removed by degradation. I

5. Defect means an imperfection of such severity that it exceeds the' plugging or repair limit. A tube containing a defect is defective. Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defective tube.

6. Pluacina or Reoair Limit mecns the imperfection depth !

at or beyond which the tube shall be removed from ;

service by plugging or repaired by sleeving in the af fected area because it may become unserviceable prior to the next inspection. The plugging or repair limit gg .) imperfection depths are specified in percentage of nominal wall thickness as follows:

sE(<T 'p\ a4 Original tube wail 40s by Babcock & Wilcox kinetic welded sleeve wall 40%

25%

ch' Westinghouse laser welded sleeve wall BEAVER VALLEY - UNIT 2 3/4 4-14 Amendment No. 4t.-

1 INSERT C This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.5.4.a.10 for the repair limit applicable to these intersections.

i I

l l

l j

I (Proposed Wording)

MPF-73 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating B sis Earthquake, a loss-of-coolant accident, or a steam ine or feedwater line break as specified in 4.4.5.3.c, above.

8. Tube Insoection means an inspection of the steam generator tube from the point of entry (ho eg side) completely around the U-bend to the top suppor to the coldgleg. Q

9. Tube Repair refers to sleeving which is used to maintain a tube in-service or return a tube to service.

This includes the removal of plugs that were installed as a corrective or preventive measure. The following sleeve designs have been found acceptable:

a) Babcock & Wilcox kinetic welded sleeves, BAW-2094P, Revision 1 including kinetic sleeve A00 756

)

"O" l b)

" tooling" hanges.

and installation process parameter Westinghouse laser welded sleeves, WCAP-13483,

( Revision 1.

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit) required by Table 4.4-2.

4.4.5.5 Reports

a. Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2.

b. The complete results of the steam generator tube and sleeve inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:

1. Number and extent of tubes and sleeves inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or repaired.

BEAVER VALLEY - UNIT 2 3/4 4-14a Amendment No. E' (fry seb WorcN*.

INSERT D

10. Tube Suonort Plate Pluaaina Limit is unad for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the plugging (repair) limit is based on maintaining steam generator tube serviceability as described below:

a) Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to 2.0 volts will be allowed to remain in service, b) Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts will be repaired or plugged, except as noted in 4.4.5.4.a.10.c below.

c) Steam generator tubes, with indications of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts but less than or equal to the upper. voltage repair limit

may remain in service if a rotating pancake coil or acceptable alternative - inspection does not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion cracking degradation with a bobbin voltag limit greater than the upper voltage repair will be plugged or repaired.

d) If an unscheduled mid-cycle inspection is performed, the following mid-cycle repair limits apply instead of the limits identified in 4.4.5.4.a.10.a, 4.4.5.4.a.10.b, and 4.4.5.4.a.10.c.

(1) The upper voltage repair limit is calculated according to the methodology in Generic Letter 95-05 as supplemented.

(Proposed Wording)

. . . . - .-.- _ _ - . - . - _ _ - = - . . - . . . - - - . . .-. . ..

INSERT D (continued)

The mid-cycle repair limits are determined from l the following equations:

Vst Y"""

' CL - A t' l 1.0 + NDE + Gr

< CL s

' CL - ht' Van = Vw.:st -(Vunt - Visti) -

< CL s where:

Vunt. = upper voltage repair limit Vm = lower voltage repair l limit Vm = mid-cycle upper voltage repair limit based on time into cycle Vm = mid-cycle lower voltage repair li'mit based on Vm and time into cycle At = length of time since last scheduled inspection during which

! vun and Vm were t,

implemented CL = cycle length (the time i i

between two scheduled steam generator inspections) i V,x, = structural limit voltage Gr = average growth rate per cycle length NDE = 95-percent cumulative probability allowance for nondestructive examination uncertainty (i.e., a value of 20-percent has been approved by NRC)

Implementatior, of these mid-cycle repair limits should follow the same approach as in TS 4.4.5.4.a.10.a, 4.4.5.4.a.10.b, and 4.4.5.4.a.10.c.

(2) The NDE is the value provided by the NRC in GL 95-05 as supplemented.

(Proposed Wording)

t i NPF-73 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) i ...

4

c. Results of steam generator tube inspections which fall into 4 Category C-3 shall be reported to the Commission pursuant to l Specification 6.6 prior to resumption of plant operation.

i The written report shall provide a description of

. investigations conducted to determine the cause of the tube

] degradation and corrective measures taken to prevent j recurrence.

h0D,)

I E,,+

Y NSEAT J l

l BEAVER VALLEY - UNIT 2 3/4 4-14b Amendment No. 4 (hhp 3cb U'

INSERT E

d. For implementation of the voltage-based repair criteria to tube support plate intersections, notify the Commission prior to returning - the steam generators to service (MODE 4) should any of the following conditions arise:

1. If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds the leak limit (determined from the licensing basis dose calculation for the postulated main steamline break) for the next operating cycle. j

2. If circumferential crack-like indications are detected at the tube support plate intersections.

3. If indications are identified that extend beyond the confines of the tube support plate.

4. If indications are identified at the tube support .

plate elevations that are attributable to primary l water stress corrosion cracking. '

5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual measured -2end-of-cycle) voltage distribution exceeds 1 X 10 , notify the Commission and provide an assessment of the safety 1 significance of the occurrence.

l l

(Proposed Wording)

NPF-73 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION IST SAMPLE INSPECTION. 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N/A N/A N/A N/A S [ bes per S.G. C-2 Plug or repair C-1 None N/A N/A defective tubes and ,

inspect additional C-2 Plug or repair defective C-1 None 2S tubes in this S.G. tubes apd inspect additional 4S tubes in

C-2 Plug or repair i

this S.G. defective tubes C-3 Perform action 7

for C-3 result I of first sample C-3 Perform action for C-3 N/A N/A result of first sample C-3 Inspect all tubes in All other None N/A N/A this S.G., plug or S.G.s are repair defective C-1 tubes and inspect 25 tubes in each other S.G. Some S.G.s Perform action for N/A N/A C-2 but no C-2 result of second Notification to NRC additional sample pursuant to Ser49 e S.G.s are (h;;2; cf 10 07.". C-3 Peet-64 Additional , Inspect all tubes in r S.G. is each S.G. and plug or N/A N/A l [p i og 8.8 C-3 repair defective tubes.

k Notification to NRC pursuant to p.72 (b)

(2; cf 10 05' ?::t 50 9

n* Where n is the number of steam generators inspected during an inspection.

S BEAVER VALLEY - UNIT 2 3/4 4-I6 Amendment No.-44 (fropJtd Wcr

NPT-73 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE,

b. 1 gpm unidentified LEAKAGE, I

gg c. 1 gpr total pristry t: ::::.dary 1".'I'.C" thr: ugh 11 :te:

C, K p gallons per day primar econdary LEAKAGE through any I

o n steam generator, and i

Qiso b i

% 10 gpm identified LEAKAGE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With any pressure boundary LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With any Reactor Coolant System LEAKAGE greater than any cme of the above limits, excluding pressure boundary LEAKAGL, reduce the LEAKAGE rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at Isamt HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System LEAKAGES shall be demonstrated to be within each of the above limits by:

a.

Monitoring the following " leakage detection instrumentation at least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s:(

j

1. Containment atmosphere gaseous radioactivity monitor.

l 1

(1) Only on leakage detection instrumentation required by LCO j 3.4.6.1. :

BEAVER VALLEY - UNIT 2 3/4 4-19 Amendment No. "

(brop3t WD ^

l 4

b t 4

4

! NPF-73 j REACTOR COOLANT SYSTEM i .

J BASES 3/4.4.5 STEAM GENERATORS (Continued) j decay heat removal capabilities for RCS temperatures greater than j

350*F if one steam generator becomes inoperable due to single failure considerations. Below 350*F, decay heat is removed by the RHR system. l The Surveillance Requirements for inspection of the steam l t

generator tubes ensure that the structural integrity of this portion j of the RCS will be maintained. The program for inservice inspection of steam generator Guide 1.83, Revision 1.

tubes is based on a modification of Regulatory j

tubing is Inservice inspection of steam generator l essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation i

due to design, J

manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a means )

of characterizing the nature and cause of any tube degradation so that q corrective measures can be taken.

1 The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those parameter limits

, found to result in negligible corrosion of the steam generator tubes.

If the secondary coolant chemis"ry is not maintained within these parameter limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation

would be lin: ted by }he limitation of steam generator tube leakage between the dimary cbolant @ stem and the fecondary 8oolant lystem m

EO (primaryetoes.condary LEAKAGE - * *

gallons per day per steam generator) . ggracks having a primary 9tossecondary LEAKAGE less than this limit during operation will nave an acequate margin or sarety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that primaryGtoG secondary LEAKAGE of W gallons per day per steam generator can readily be detected. M recistic: 22 it Leakage in excess of this limit will require Ofplant tr : shutdown;:::::t:r bland rd:Ungan unscheduled inspection, during which the leaking tubes will be located 3 and plugged.

gg.

Wastage-type defects are unlikely with the all volatile treatment (AVT) of secondary coolant. However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam generator tube examingtions. Plugging or repair will be required of all tubes with imperfections exceeding the plugging or i repair limit. Degraded steam generator tubes may be t

i BEAVER VALLEY - UNIT 2 B 3/4 4-3 Amendment No ?

(Propc M WS

l l

I NPF-73 I REACTOR COOLANT SYSTEM l BASES 3/4.4.5 STEAM GENERATORS (Continueril l I

repaired by the installation of sleeves which span the degraded tube ;

section. A steam generator tube with a sleeve installed meets the !

structural requirements of tubes which are not degraded, therefore, )

the sleeve is considered a part of the tube. The surveillance requirements identify those sleeving methodologies approved for use.

If an installed sleeve is found to have through wall penetration greater than or equal to the plugging limit, the tube must be plugged. The plugging limit for the sleeve ' is derived from R.G.

1.121 analysis which utilizes a 20 percent allowance for eddy current uncertainty in determining the depth of tube wall penetration and additional degradation growth. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20 percent of the original tube wall thickness. I Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to Specification 6.6 prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.

tl pse U I

BEAVER VALLEY - UNIT 2 B 3/4 4-3a Amendment No. :::

Ytofo.ltb Uorh

INSERT F Tha voltaga-based repair limits of these surveillance requirements (SR) implement the guidance in GL 95-05 and are applicable only to Westinghouse-designed steam generators (SGs) with outside diameter stress corrosion cracking (ODSCC) located at the tube-to-tube support plate intersections. The guidance in GL 95-05 will not be applied to the tube-to-flow distribution baffle plate intersections. The voltage-based repair limits are not applicable to other forms of SG tube degradation nor are they applicable to ODSCC that occurs at other locations within the SG. Additionally, the repair criteria apply only to indications where the degradation mechanism is dominantly axial ODSCC with no NDE detectable cracks extending outside the thickness of the support plate. Refer to GL 95-05 for additional description of the degradation morphology.

Implementation of these SRs requires a derivation of the voltage structural limit from the burst versus voltage empirical correlation and then the subsequent derivation of the voltage repair limit from the structural limit (which is then implemented by this surveillance).

The voltage structural limit is the voltage from the burst pressure / bobbin voltage correlation, at the 95-percent prediction interval curve reduced to account for the lower 95/95-percent tolerance bound for tubing material properties at 650'F (i.e., the 95-percent LTL curve). The voltage structural limit must be adjusted downward to account for potential degradation growth during an operating interval and to account for NDE uncertainty.

The upper voltage repair limit; Vun, is determined from the structural voltage limit by applying the following equation:

Von = VsL - Vor - Vuog where Vor represents the allowance for degradation growth between inspections and Vuos represents the allowance for potential sources of error in the measurement of the bobbin coil voltage. Further discussion of the assumptions necessary to determine the voltage repair limit are discussed in GL 95-05. i The mid-cycle equation in SR 4.4.5.4.a.10.d should only be used during unplanned inspections in which eddy current data is acquired i for indications at the tube support plates. !

l SR 4.4.5.5 implements several reporting requirements recommended by GL 95-05 for situations which the NRC wants to be notified prior to returning the SGs to service. For the purposes of this reporting requirement, leakage and conditional burst probability can be calculated based on the as-found voltage distribution rather than

'the projected end-of-cycle (EOC) voltage distribution (refer to GL 95-05 for more information) when it is not practical to complete these calculations using the projected EOC voltage distributions prior to returning the SGs to service. Note that if leakage and conditional burst probability were calculated using the measured EOC voltage distribution for the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, then the results of the projected EOC voltage distribution should be provided per the GL section 6.b (c) criteria.

I (Proposed Wording)

NPF-73 REACTOR COOLANT SYSTEM BASES 3/4.4.6.2 OPERATIONAL LEAKAGE (Centinued)

BACKGROUND (Continued)

During plant life, the joint and valve interfaces can produce varying amounts of reactor coolant LEAKAGE, through either normal operational wear or mechanical deterioration. The purpose of the RCS Operational LEAKAGE LCO is to limit system operation in the presence of LEAKAGE from these sources to amounts that do not compromise safety. This LCO specifies the types and amounts of LEAKAGE.

10 CFR 50, Appendix A,' GDC 30, requires means for detecting and,

to the extent practical, identifying the source of reactor coolant LEAKAGE. Regulatory Guide 1.45 describes acceptable methods for selecting leakage detection systems.

The safety significance of RCS LEAKAGE varies widely depending on its source, rate, and duration. Therefore, detecting and monitoring reactor coolant LEAKAGE into the containment area is necessary.

Quickly separating the identified LEAKAGE from the unidentified LEAKAGE is necessary to provide quantitative information to the operators, allowing them to take corrective action should a leak occur that is detrimental to the safety of the facility and the public.

A limited amount of leakage inside containment is expected from auxiliary systems that cannot be made 100 percent leaktight. Leakage from these systems should be detected, located, and isolated from the containment atmosphere, if possible, to not interfere with RCS leakage detection.

This LCO deals with protection of the reactor coolant pressure boundary (RCPB) from degradation and the core from inadequate cooling, in addition to preventing the accident analyses radiation release assumptions.from being exceeded. The consequences of violating this LCO include the possibility of a loss of coolant accident (LOCA).

APPLICABLE SAFETY ANALYSES Except for primary to secondary LEAKAGE, the safety analyses do not address operational LEAKAGE. However, other operational LEAKAGE is related to the safety analyses for LOCA; the amount of leakage can affect the probability of such an event. The safety analysis for an event resulting in steam discharge to the atmosphere assumes a 1 gpm primar 6 econdary LEAKAGE as the initial condition. We3 84 G$CG id1 ckSCAbdbel04 St 7lt2 Klat.s s}%m lide bre d O fS4 8) ana u sed' na. A sypd d m%y -6ad'skywde 74,vpv BEA ER VALLEY - UNIT 2 B 3/4 4- e Amendment No. ~

ffejt' Of )

l NPF-73 REACTOR COOLANT SYSTEM l

1 BASES l

i 3/4.4.6.2 OPERATIONAL LEAKAGE (Continued) '

APPLICABLE SAFETY ANALYSES (Continued)

Primarho@econdary LEAKAGE is a fact.or in the dose releases outside containment resulting from a stean d ine break (SLB) accident.

To a lesser extent, other accidents or transients involve secondary steam release to the atmosphere, such as a steam generator tube rupture (SGTR), The leakace contaminates the secondary fluid.

5 /7i 19D Th h is moge limiting for site radiationireleases. The safety analysis LEAKAGE.

gor the GbB accident assumes E gpm primary @to@ secondary ,

l .h: de:0 00n00;20n000 r Culting fr;; th: CL" ;;;ident are I rell vithir the lirite defined in 10 CT" 100 er the staff approved licerring barir (i.e , a crall fractier cf th--- 14=4*s): l g f@EPLAC$ WITH )NSERT " W' j !

RCS operational LEAKAGE shall be limited to:

a. Pressure Boundarv LEAKAGE No pressure boundary LEAKAGE is allowed, being indicative of i material deterioration. LEAKAGE of this type is 1 unacceptable as the leak itself could cause further deterioration, resulting in higher LEAKAGE. Violation of this LCO could result in continued degradation of the RCPB. '

LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE. Should pressure boundary LEAKAGE occur through a component which can be isolated from the balance of the Reactor Coolant System, plant operation may continue provided the leaking component is promptly isolated from the Reactor Coolant System since isolation removes the source of potential failure.

b. Unidentified LEAKAGE One gallon per minute (gpm) of unidentified LEAKAGE is allowed as a reasonable minimum detectable amount that the containment air monitoring and containment sump level monitoring equipment can detect within a reasonable time period. Violation of this LCO could result in continued degradation of the RCPB, if the LEAKAGE is from the pressure boundary.

l l

BEAVER VALLEY - UNIT 2 B 3/4 4-4f Amendment No. &

Otopstc\ Worch u

INSERT H Ths radiological consequeness of a MSLB outside of containment was reanalyzed in support of the tube support i plate voltage-based repair criteria stated in SR 4.4.5.4.a.10. For this analysis, the thyroid dose was l maximized at 10% of the 10 CFR Part 100 guideline of 300 !

ram. RCS leakage was based on projection rather than on !

technical specification leakage limits. The ' analysis .

indicated that offsite doses would . remain within !

regulatory criteria with an increase in primary-to- !

secondary leakage to 2.95 gpm should steam generator tubes e fail due to the depressurization associated with a MSLB.

1 A similar analysis was performed using a control room '

thyroid dose of 30 rem as the criterion. The control room was assumed to be manually isolated and pressurized at ;

T=30 minutes for a period of one hour, at which time !

filtered emergency intake would be automatically started.

The control room would be purged with fresh air at T=8 hours following release cessation. The analysis indicated i that control room doses would' remain within regulatory I criteria with an increase in primary-to-secondary leakage to 2.95 gpm should steam generator tubes fail due to the l depressurization associated with a MSLB.

]

i I

i i

(Proposed Wording) t

NPF-73 REACTOR COOLANT SYSTEM BASES 3/4.4.6.2 OPERATIONAL LEAKAGE (Continued)

LCO (Centinued) fc Pr d -- Y t Ferer' ry '"'**c" thrruch

_'_11 Ste== cc.cr ter_

h OBEEd T t:1 127 t ^"f'~r '"'"'c" 'r^""tir; t^

hra"Oh ell 9C5 prad'2cer ecc ; table effrit: d:::: in th: 1OLO ==

ident 2n:17:ic. '!ielitien ef *21: LC^ : uld ::::d th:

effeite da e 14=ite fer this tecident. Prir ry t: ::::..dcry E"'"'.0" runt 5 id:nt i f ied ' "'_"_'.C" included

. in the tet:1 0110 251: li=itf;r)

K PrimarvGter-Mecondary LEAKAGE throuch Any One SG (Th: 500 ; 11:50 per d 7 lirit On : : SC 10 b ::d en the REPLACE t "-" r'i^2 '"t s cin:12 crsch ic Mir; tMie --^"nt'eeuld not g A pr";2;st" t0 SCTP. "-der the Strie: ::nditirn: Of LCC'. Or W6o e =ein et er line yn7tu e_ If 1 eMed

wren;h 2:7 ::::h ,

H nsstT st6 the___...t1....

gen crect: tre very crell, 2nd th: 15 1: :::::pti:n isJ Identified T.FAKAGE Up to lo gym of identified LEAKAGE is considered allowable because LEAKAGE is from known sources that do not interfere with detection of identified LEAKAGE and is well within the capability of the RCS Makeup System. Identified LEAKAGE includes LEAKAGE to the containment from specifically known and located sources, but does not include pressure boundary LEAKAGE or controlled reactor coolant pump (RCP) seal leakoff (a normal function not considered LEAKAGE) .

Violation of this LCO could result in continued degradation of a component or system. i APPLICABILITY In MODES 1, 2, 3, and 4, the potential for RCPB LEAKAGE is greatest when the RCS is pressurized.

In MODES 5 and 6, LEAKAGE limits are not required because the reactor coolant pressure is far lower, resulting in lower stresses and reduced potentials for LEAKAGE.

4 BEAVER VALLEY - UNIT 2 B 3/4 4-4g Amendment No. &

[bego5th U

_ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ _ . s

INSERT G Maintaining an operating LEAKAGE limit of 150 gpd per steam generator will minimize the potential for a large LEAKAGE event during a main steamline break. Based on the non-destructive. examination uncertainties, bobbin coil voltage distribution, and crack growth rate from the i previous inspection, the expected leak rate following a I steamline rupture is limited to less than or equal to l 2.95 gpm in the faulted loop. Maintaining LEAKAGE less l than or equal to the 2.95 gpm limit will ensure that postulated offsite doses will remain within the 10 CFR 100 requirements and that control room habitability continues to meet GDC-19. . LEAKAGE in the intact loops ,

will be limited to the operating limit of 150 gpd. If~ l the ' projected end-of-cycle distribution of crack indications results in primary-to-secondary LEAKAGE greater than 2.95 gpm in the faulted loop during a postulated steamline break event, additional ; tubes must be removed from service or repaired in order to reduce the postulated steamline break LEAKAGE to less than or equal to 2.95 gpm.

Also, the 150 gallons per day leakage limit incorporated into this specification is more restrictive than the standard operating leakage limit and is intended to provide an additional margin to accommodate a crack which might grow at a greater than expected rate or j unexpectedly extend outside the thickness of the tube support plate. Hence, the reduced leakage limit, when combined with an effective leak rate monitoring program, provides additional assurance that should a significant leak be experienced in service, it will be detected, and the plant shut down in a timely manner.

j (Proposed Wording)

ATTACHMENT B Beaver Valley Power Station, Unit Nos. 1 and 2 Proposed Technical Specification Change Nos. 235 and 109 1 7OLTAGE-BASED TUBE REPAIR CRITERIA l v

A. DESCRIPTION OF AMENDMENT REQUEST For the Beaver Valley Power Station Unit No. 1 (BVPS-1) only, ;

Specification 3.4.5 and associated Bases Section would be '

revised. The Bases Section for Specification 3.4.6.2 would also be revised. The proposed changes are editorial in nature and are intended to add consistency to the Specification and associated Bases. Index Page XIX would be revised to reflect the revision l to Tables 4.4-1 and 4.4-2 page numbers due to shifting of text. I For the Beaver Valley Power Station Unit No. 2 (BVPS-2) only, the proposed amendment would revise Specifications 3.4.5 and 3.4.6.2, and Bases 3/4.4.5 and 3/4.4.6.2 to implement voltage-based steam generator tube repair criteria for the tube support plate elevations. Table 4.4.2 would be revised to reference Specification 6.6 for reporting requirements. j 1

B. BACKGROUND l i

The proposed change for BVPS-2 would implement a voltage-based '

repair criteria similar to the changes implemented for Unit 1 by Amendment No. 198 (TAC No. M94202) (Reference 2) to reflect the guidance provided in NRC Generic Letter (GL) 95-05, " Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking." l C. JUSTIFICATION The voltage-based repair criteria detailed in the proposed ;

technical specifications reflects a conservative approach for the BVPS-2, recognizing that a voltage-based repair criteria has been demonstrated to provide adequate margins in accordance with GL 95-05. The proposed tube repair criteria is provided in accordance with the following:

1. A bobbin coil inspection of 100 percent of the hot-leg and cold-leg tube support plate intersections down to the lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) will be performed.

Determination of the lowest cold-leg tube support plate intersections having ODSCC indications are based on performing a 20-percent random sampling of tubes inspected over their full length.

2. Degradation signals confined within the thickness of the tube support plate with bobbin voltages less than or equal to 2.0 volts will be allowed to remain in service.

ATTACHMENT B, continund Proposed Technical Specification Change Nos. 235 and 109 Page 2

3. Degradation signals confined within . the thickness of the tube support plate with a bobbin voltage of greater than 2.0 volts will be plugged or repaired except as noted in Item 4.

4. Degradation signals confined within the thickness of the tube support plate with a bobbin voltage greater than 2.0 volts but less than or equal to the upper voltage repair limit may remain in service if a rotating pancake coil (RPC) or acceptable alternative probe inspection does not confirm degradation. An acceptable alternative means a nondestructive examination technique that is qualified using similar criteria as that used for qualifying rotating pancake coil probes. Degradation indications with a bobbin voltage greater than the upper voltage repair limit will be

~

plugged or repaired.

5. An end-of-cycle (EOC) voltage distribution will be established for each cycle based upon the most recent EOC eddy current data. Based upon this distribution, postulated main steamline break (MSLB) leakage will be determined based on the guidance of GL 95-05. Projected leakage must remain at or below a level which results in postulated offsite doses remaining within 10 CFR 100 requirements and postulated control' room doses remaining within GDC-19. This level.has been determined to be 2.95 gpm (see Attachment D).

Should this estimation' exceed 2.95 gpm, the steam generator tube (s) with the highest voltage indications will be successively repaired until the leakage estimation drops to less than or equal to 2.95 gpm.

6. An overall tube burst probability during a postulated MSLB event~2 will be calculated and if found to be greater than 1.0 X 10 ,'the Commission will be notified.

The - proposed change modifies the steam generator surveillance requirements, the reactor coolant system operational leakage limiting condition for operation, and related technical specification Bases. These proposed changes closely follow the-model technical specificatiwni contained in Attachment 2 of Generic Letter 95-05. Specification 3.4.6.2 has been modified by deleting item "c", which limits total primary-to-secondary leakage to 1 gpm. Item "d", which limits primary-to-secondary leakage in any one steam generator to 500 gpd, has been modified by changing this limit to 150 gpd. Accordingly, items "d" and "e" have been renamed to items "c" and "d", respectively.

For BVPS-1 only, the proposed change to SR 4.4.5.3.a is necessary to define the term "AVT." The proposed change to SR 4.4.5.3.b will better define that the inspection is to be performed on a more periodic basis. This change is consistent with BVPS-2 SR 4.4.5.3.b wording and the wording contained in NUREG-0452, Revision 4, titled " Standard Technical Specifications for Westinghouse Pressurized Water Reactors." The proposed change to B-2

ATTACHMENT B, continusd !

Proposed Technical Specification Change Nos. 235 and 109 l Page 3 SR 4.4.5.4.a.6 and 4.4.5.4.a.9 is necessary to make the letter designation. unique in these surveillance requirements. The proposed change to SR 4.4.5.4.a.10 is also necessary to make the letter designation unique in this surveillance requirement. In addition, the letter "a" will be added to the current references to SR 4.4.5.4.10.a, 4. 4. 5. 4.10. b and 4.4.5.4.10.c. This change is necessary to reflect the correct reference number to these surveillance requirements. The Bases Section will also be revised to reflect the correct surveillance reference number.

The proposed change to Tables 4.4-1 and 4.4-2 will remove information pertaining to plants with two or four steam generators per unit. This information is not applicable to BVPS-1 and.therefore can be deleted. The proposed change-to the Bases Section for Specification 3.4.6.2 will update the Bases to reflect the reanalysis that was performed to support voltage-l based repair criteria implemented by Technical Specification l Amendment Number 198 (Reference 2). In addition, the wording L pertaining to the 4.5 gpm leakage rate will be revised to clarify that the limit is less than or equal to 4.5 gpm. This change is consistent with the radiological analysis which reflects that a 4.5 gpm leakage rate is acceptable.

For BVPS-2 only, the proposed change to Table 4.4-2, pertaining to notification to the NRC, will make the table notification requirements consistent with the current SR 4.4.5.5.c.

Specification 6.6 contains a reference to notify the NRC in accordance with 50.72. This proposed change to Table 4.4-2 it, not directly related to implementation of GL 95-05, but is necessary to add consistency between the reporting requirements contained in SR 4.4.5.5.c and Table 4.4-2.

D. SAFETY ANALYSIS The voltage-based repair criteria involves a correlation between eddy current bobbin probe signal amplitude (voltage) and indicated depth (phase angle) versus tube burst pressure and leak rate. The principal parameter is voltage amplitude which is correlated with tube burst capability and leakage potential.

Indicated depth is a secondary paramaicr utilized as a threshold value below which added margins incorporated in the repair criteria to minimize excessive MSLB leakage are not necessary.

The repair . criteria are developed from testing of laboratory induced ODSCC specimens, extensive examination of pulled tubes from operating steam generators, and field experience from leakage due to-indications at the tube support plates.

A technical evaluation of the voltage-based repair criteria is i provided in Attachment C. Due to the enhanced and expanded i inspection program and methodology required by the voltage-based l_ repair criteria, the overall safety level of the BVPS-2 steam.

generator tubing will be increased.

B-3

ATTACHMENT B, continund Proposed Technical Specification Change Nos. 235 and 109 Page 4 The voltage-based repair criteria remains commensurate with Regulatory Guide (RG) 1.121 and RG 1.83 criteria, and, hence, meets General Design Criteria 14, 15, 30, 31, and 32. As stated in GL 95-05, the voltage-based repair criteria ensures structural and leakage integrity for all postulated design basis events.

The structural criteria are intended to ensure that indications subjected to the voltage repair limits will be able to withstand pressure loadings consistent with the criteria of Regulatory Guide 1.121, " Bases for Plugging Degraded PWR Steam Generator Tubes." Also, General Design Criteria 2 and 4 continue to be met as it is expected that the BVPS-2 steam generators can continue to perform their intended safety function.

From a tube leakage perspective, the potential for adverse ,

radiological consequences due to primary-to-secondary leakage I during postulated accident condition loadings is addressed. The most limiting accident affected by the implementation of the voltage-based repair criteria with regard to the potential for radiological consequences evaluated in the Updated Final Safety i Analysis Report (UFSAR) is a postulated MSLB event. The potential for excessive leakage during a MSLB is minimized by verifying that the expected distribution of crack indications at the end of each cycle would result in a level of leakage for j which the radiological consequences remain within the licensing i basis. Calculated tube leakage is limited to assure that the assessment of doses resulting from a MSLB (outside of containment and upstream of the main st samline isolation valve) will be less than the 10 CFR 100 require;aents and GDC-19.

In accordance with the. guidance provided in GL 95-05, radiological dose calculations (Attachment D) were performed at the Exclusion Area Boundary (EAB), for the Low Population Zone (LPZ) and the Control Room (CR). Based on these analyses, the EAB was more limiting, the leak rate associated with the 30 Rem thyroid limit was 2.95 gpm. This evaluation was performed in accordance with Standard Review Plan $15.1.5 methodologies and assumptions, with one exception. In lieu of dose conversion factors based on Regulatory Guide 1.4 and TID 14844, this evaluation used dose conversion factors based on ICRP-26/ICRP-30.

Application of the voltage-based repair criteria requires that the primary-to-secondary leakage rate be limited to 150 gpd in any one steam generator. Axial cracks having leakage less than this limit will have an adequate margin of safety to withstand normal operating and accident loadings.

The above criteria represent the conservative limits which support structural integrity of the potentially degraded tube bundle, commensurate with the applicable NRC Regulatory Guides, during normal operation and postulated accident conditions.

In establishing the voltage-based repair criteria, the general approach is to establish the existence of acceptable margins to B-4

l ATTACHMENT B, continutd Proposed Technical Specification Change Nos. 235 and 109 Page 5 l

tube burst and excessive steam generator tube leakage during all ]

plant conditions. l l NRC Generic Letter 95-05 (Reference 1) has established the l

framework for utilities to follow who desire to implement the i voltage-based criteria. A voltage-based steam generator tube l repair criteria which includes the following items has been developed for BVPS-2: !

l

1. Standardized inspection requirements and data analysis guidelines,

2. Determination of an end-of-cycle voltage distribution using an approved methodology, 1

3. Primary-to-secondary steam generator tube leakage prediction for a postulated MSLB event; the recommended MSLB leakage calculation will be performed using the most recent EPRI l voltage-leakrate correlation (if applicable),

1

4. Calculation of a MSLB primary-to-secondary allowable leakage limit using NUREG-0800 guidance for comparison,

5. The use of a reduced normal operating primary-to-secondary leakage limit, and

6. Calculation of an overall end-of-cycle tube burst probability during a postulated MSLB, In general, the degradation morphology occurring at the tube support plate (TSP) intersections at plants in the U.S. can be I described as axially oriented ODSCC. Axially oriented I macrocracks can occur at one or more azimuthal locations around i the circumference of the tube. The macrocracks nP comprised of short, nearly colinear microcracks separated 1> ligaments of nondegraded material. Typical microcrack length is less than 0.2 inch. The corresponding macrocrack can be as long as the support plate thickness. Minor to moderate intergranular attack (IGA) can occur in addition to the axial ODSCC. The corrosion morphology of the degradation at the tube support plate intersections in the BVPS-2 steam generators will be demonstrated to be consistent with that attributable to ODSCC via tube pulls and destructive analysis. The number and frequency of subsequent tube pulls will be consistent with GL 95-05 requirements, or BVPS-2 will participate in an NRC endorsed industry program per Section 4.a of GL 95-05.

Pulled tube examination results from other plants indicate that through-wall cracks can potentially occur below 10 volts but that I

the associated crack lengths are short with no measurable leakage at operating conditions. Leakage at operating conditions has not been identified for bobbin coil voltages less than 7.7 volts in a B-5 l

i ATTACHMENT B, continued j Proposed Technical Specification Change Nos. 235 and 109

!~ Page 6 i

i i 3/4" tube in the field. Operating leakage due to ODSCC at the TSPs has not been identified in a plant with 7/8" tubing.

The criterion of RG 1.121 to maintain a factor of 3 times normal i operating pressure differential on tube burst is inherently

[ satisfied during normal operating conditions due to proximity of the tube support plates to the degradation area. Steam generator tube denting (due . to TSP corrosion) and cracking potentially initiate and progress at high temperature within the TSP. Since the tubes and support plates are in an equilibrium situation j auring normal operation, and since the causes of the cracking i occur at the tube-to-tube support plate intersections, it is i

clear that the cracking would be situated within the plates

i. during normal operating conditions . and that tube burst cannot

! occur due to degradation within the TSP. Therefore, the most

appropriate manner to assess degraded tube operability and burst

potential with regard to RG 1.121 is to examine the tube

! integrity at faulted (MSLB) conditions, since the tube support plates have the potential to deflect during the rapid blowdown ,

j phase of a postulated double-ended guillotine break of the main !

} -steamline, thereby uncovering the degradation area.

l In accordance with GL 95-05, in establishing the acceptability of 1 the voltage-based repair criteria and in determining the upper voltage repair limit (Vun) , the supporting data set must contain 1 all applicable data consistent with the latest revision of the

! industry data base as approved by the Commission. Based upon the

[ latest industry approved voltage-burst correlation.(currently 8.6

volts), the end-of-cycle indication would satisfy the steamline

!- break tube burst margin requirement of RG 1.121 with a 1.43

safety factor applied to the MSLB pressure differential. MSLB I pressure differential will be limited to approximately 2560 psi,

{ which is the approximate pressurizer safety valve liftoff setting s plus 3 percent for valve accumulation. The upper voltage repair

limit (Vun) will be determined prior to each outage using the most recently approved NRC database to determine the tube 1 structural limit (VsL). The structural limit is reduced by j allowances for nondestructive examination (NDE) uncertainty j (Vuog) and growth (Vog) to establish Vun. As an example, the NDF l uncertainty component of 20% and a voltage growth allowance of l 30% per full power year can ba utilized to establish a Vun of i 5.7 volts. The 20% NDE uncertainty represents a square-root-sum-i of-the-squares (SRSS) combination of probe wear uncertainty and

! analyst variability. The degradation growth-allowance should be

an average growth rate or 30% per effective full power year, j whichever is larger.

I j Duquesne Light Company (DLC) has undertaken several steps to help i mitigate steam generator tube corrosion. These include boric

! acid addition beginning in December of 1991, removal of copper j moisture separator tubes, all volatile treatment (AVT) secondary

chemistry and molar ratio control according to EPRI i recommendations.

1 B-6

I ATTACHMENT B, continund i

Proposed Technical Specification Change Nos. 235 and 109 Page 7 I

I MSLB leakage as a function of EOC voltage distribution will be determined in accordance with GL 95-05, Section 2.b, " Total Leak Rate During MSLB."

l The maximum allowable MSLB leakage from steam generator tubing I has been determined to be 2.95 gpm in the faulted loop. This ,

value is established based on NUREG-0800 guidelines as suggested I by GL 95-05 and assessed both offsite dose and control room dose. l The technical specification reactor coolant and secondary coolant dose equivalent Iodine-131 activity limits of 1.0 microcuries per gram and 0.1 microcuries per gram, respectively, are used in the analysis for establishment of initial radioactivity conditions.

The normal operating primary-to-secondary leakrate limit defined in the technical specifications will be revised to 150 gpd per steam generator, 450 gpd total, as part of the voltage-based i license amendment. Postulated leakage at 150 gpd from a tree span single crack would imply a throughwall crack length of approximately 0.41 inch at nominal leak rates and a single throughwall crack of approximately 0.62 inch at the lower 95 percent confidence level leak rates at a primary-to-secondary pressure differential considered bounding for BVPS-2. A crack of this extent would exhibit a bobbin indication far in excess of any end-of-cycle predicted voltage. If primary-to-secondary ,

leakage occurs during operation, it is reasonable to assume that I more than 1 crack would contribute to the leakage value. The throughwall crack lengths that would represent a potential for tube burst at 1.43 times the MSLB pressure differential and the MSLB pressure differential are approximately 0.57 and approximately 0.84 inch, respectively.

Upon implementation of the voltage-based repair criteria, projected voltage distributions for the following cycle will be established using current EOC eddy current data. The overall tube burst probability for the next cycle will be establishpd at that time and compared to the acceptance criteria of 1 X 10~ .

The steam generator tube repair or plugging criteria for the tube ;

support plate elevation degradation observed in the steam generators is summarized in Table 1.0. The recommended tube repair or plugging criteria is based upon bobbin coil inspection voltage signal amplitude, which is correlated with tube burst capability. The criteria is developed to preclude free span tube burst if it is postulated that TSP displacement would occur under accident condition loadings. The repair or plugging criteria provides RG 1.121 tube burst margin. The repair or plugging criteria (which is much more conservative than the structural repair or plugging limit) is expected to result in the majority of the EOC voltages existing below the MSLB leakage threshold.

The upper voltage repair limit (Vunt) for tube support plate intersections will be established as previously discussed.

B-7

ATTACHMENT B, continued Proposed Technical Specification Change Nos. 235 and 109 Page 8 TABLE 1.0 STEAM GENERATOR TUBE REPAIR OR PLUGGING CRITERIA FOR TUBE SUPPORT PLA'fL ELEVATION ODSCC BOBBIN SIGNAL ACTION VOLTAGE S 2.0 LIMITED *

> 2.0 but less than or equal to Vun ROTATING PROBE TECHNOLOGY **

r

> Vun PLUG OR REPAIR

If it is found that the potential for MSLB leakage at end-of-cycle conditions exceeds 2.95 gpm in any steam generator, then additional tubes will be plugged or repaired to reduce MSLB leakage ratt potential in that steam generator to below 2.95 gpm. If additional tubes are to be plugged in order to show compliance with the 2.95 gpm leakage rate limit, the largest bobbin coil voltage degradation indications would be plugged or repaired.

- Plug or repair if indications of ODSCC are detected.

Implementation of the voltage-based plugging criteria involves a 100% inspection of all hot-leg tubes down to the lowest cold-leg intersection with identified ODSCC in order to provide a conservative inspcction philosophy and to monitor the progression of ODSCC. Probe wear will be monitored to ensure compliance with the NRC approved Industry procedure (NRC letter from Brian Sheron (NRR) to Alex Marion (NEI) dated February 9, 1996 and NEI letter from Alex Marion to Brian Sheron dated February 23, 1996]. The NEI letter identifies the following exception to the referenced NRC letter regarding probe wear. Reinspections of all intersections in low row tubes (rows 1-9) where entry from both the cold leg as well as the hot leg would be required will not be performed. All tubes with indications above 75% of the repair limit will be reinspected with an acceptable probe when the probe fails the wear check. Non affected intersections in those subject tubes will be reinspected as permitted by access from the hot-leg side unless cold-leg entry is required to reinspect indications on the cold-leg side that are above 75% of the repair limit. This exception will be applicable to BVPS-2.

Additionally, the industry methodology will be utilized for new probe variability as approved by the NRC and further acknowledged in NEI letter dated February 23, 1996.

B-8

ATTACHMENT B, continued Proposed Technical Specification Change Nos. 235 and 109 Page 9 An RPC inspection will be conducted for all degradation indications exceeding a signal amplitude of 2.0 volts but less than or equal to a floating upper voltage repair limit (VURL=V3t-VNDE*YGR). Generic Letter 95-05 permits the use of alternatives i to rotating pancake coil for RPC inspections. The RPC results are to be evaluated to establish that the principal indications can be characterized as ODSCC. If indications other than ODSCC are identified, these indications will be evaluated against a (bobbin coll) 40% depth requirement for tube plugging as applicable. The RPC inspection recommendation is consistent with a threshold value below which MSLB leakage is expected to be negligible and other types of degradation (wear, cold-leg thinning, etc.) are not expected to have a significant effect on steam generator tube integrity. The standardized inspection plan provided by the voltage-based repair criteria uses an ASME calibration standard I cross-calibrated to the laboratory standard and the use of a i probe wear standard. j Previous evaluations have indicated a potential for tube deformation and collapse during a postulated loss-of-coolant-accident (LOCA) + safe-shutdown-earthquake (SSE) event. The tube i collapse potential arises from TSP deformation at the support wedges. Analysis results provided in Attachment E demonstrate that no tubes were subject to deformation or collapse.

Therefore, no tubes are excluded from application of the criteria due to tube deformation or collapse concerns.

The proposed amendment may preclude occupational radiation exposure that would otherwise be incurred by plant workers involved in tube plugging or repair operations. It would minimize the loss of margin in the reactor coolant flow through the steam generators in LOCA analyses. The proposed amendment would, therefore, assist in demonstrating that minimum flow rates are 'i maintained in excess of that required for operation at full .

power. Reduction in the amount of tube repair or plugging l required can reduce the length of plant outages and reduce the time that the steam generator is open to the containment environment during an outage. DLC has determined that this methodology is applicable to our steam generators and provides a safe and effective alternative to repair or plugging.

The proposed changes to the BVPS-1 Index, Specifications and associated Bases and the proposed changes to BVPS-2 Table 4.4-2 are editorial in nature and do not affect plant safety. These changes do not reduce the margin of safety because they have no impact on any safety analysis assumptions.

Therefore, based on the above discussion, it can be concluded that the proposed change does not involve a significant reduction in a margin of safety.

B-9

ATTACHMENT B, continund Proposed Technical Specification Change Nos. 235 and 109 Page 10 E. NO SIGNIFICANT HAZARDS EVALUATION The no significant hazard considerations involved with the proposed amendment have been evaluated, focusing on the three standards set forth in 10 CFR 50.92(c) as quoted below:

The Commission _ may make a final determination, pursuant to the procedures in paragraph 50.91, that a proposed amendment to an operating license for a facility licensed under paragraph 50.21(b) or paragraph 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a cargin of safety.

The following evaluation is provided for the no significant hazards consideration standards.

1. Does the change involve a significant increase in the !

probability or consequences of an accident previously evaluated?

Tube burst criteria are inherently satisfied during normal operating conditions due to the proximity of the tube support plate (TSP). Test data indicates that tube burst cannot occur within the TSP, even for tubes which have 100%

throughwall electric discharge machining notches, 0.75 inch long, provided that the TSP is adjacent to the' notched area.

Since tube-to-TSP proximity precludes tube burst during normal operating conditions, use of the criteria must retain tube integrity characteristics which maintain a margin of safety of 1.43 times the bounding faulted condition, main steamline break (MSLB) pressure differential. The Regulatory Guide (RG) 1.121 criterion requiring maintenance of a safety factor of 1.43 times the MSLB pressure differential on tube burst is satisfied by 7/8" diameter tubing with bobbin coil indications with signal ~ amplitudes less than 8.6 volts, regardless of the indicated depth measurement.

The upper voltage repair limit (VURL) will be determined prior to each outage using the most recently approved NRC database to determine the tube structural limit (VsL). The structural limit is reduced by allowances for nondestructive examination (NDE) uncertainty (Vuog) and growth (Van) to establish _Vugt. Using the Generic Letter (GL) 95-05 NDE and growth allowances for an example, the NDE uncertainty B-10

ATTACHMENT B, continund

-Proposed Technical Specification Change Nos. 235 and 109 Page 11 component of 20% and a voltage growth allowance of 30% per full power _ year can be utilized to establish _ a VURL of 5.7 volts. The 20% NDE uncertainty represents a square-root-sum-

'of-the-squares (SRSS) combination of probe wear uncertainty and analyst variability. The degradation growth allowance should be an average growth rate or 30% per effective full power year, whichever is larger.

Relative to the expected leakage during accident condition loadings, it has been previously established that a postulated MSLB outside of containment but upstream of the main steam isolation valve (MSIV) represents the most limiting radiological condition relative to the' plugging criteria. In' support of ~ implementation of the revised plugging limit, analyses will be performed to determine whether the distribution of cracking indications at the tube support plate intersections during future cycles are projected to be such that primary-to-secondary leakage would result in postulated site boundary and control room doses exceeding 10 CFR 100, 10 CFR 50 Appendix A, and GDC-19 requirements, respectively. A separate calculation has determined the maximum allowable MSLB leakage limit in a faulted loop. This limit was calculated using the technical specification reactor coolant system (RCS) Iodine-131 activity level of 1.0 microcuries per gram dose equivalent Iodine-131 and the recommended Iodine-131 transient spiking values -consistent with NUREG-0800. The projected MSLB leakage rate calculation methodology prescribed in Section 2.b of GL 95-05 will be used to calculate the end-of-cycle (EOC) leakage. Projected EOC voltage distribution will be developed using the most recent EOC eddy current results and considering an appropriate - voltage measurement uncertainty.

The log-logistic probability of leakage correlation will be

.used to establish the MSLB leakrate used for comparison with the faulted loop allowable limit. Therefore, as implementation of the' voltage-based repair criteria does not adversely affect steam generator tube integrity and implementation will be shown to result in acceptable dose consequences, the proposed amendment does not result in any increase in the probability or consequences of an accident previously evaluated in the Updated Final Safety Analysis Report (UFSAR). ;

The proposed changes to the BVPS-1 Index, Specifications and l associated Bases and the proposed change to BVPS-2 Table 4.4-2 are editorial in nature. Therefore, these changes'do i not involve an increase in the probability or consequences of :

an accident previously evaluated.

2. Does.the chenge create the possibility of a new or different kind of accident from any accident previously evaluated?

B-11

_ . . _ . __ _ . . . _ _ _ , = . - - - -

l ATTACHMENT B, continued Proposed Technical Specification Change Nos. 235 and 109 Page 12 l

Implementation of the proposed steam generator tube voltage- !

based repair criteria does not introduce any significant f changes to the plant design basis. Use of the voltage-based j repair criteria does not provide a mechanism which could result in an accident outside of the region of the tube support plate elevations as no outside diameter stress corrosion cracking (ODSCC) is occurring outside the thickness 4 of the tube support plates. Neither a single or multiple l tube rupture event would be expected in a steam generator in which the plugging limit has been applied (during all plant i conditions).

Duquesne Light Company will implement a maximum primary-to-secondary leakage rate limit of 150 gpd per steam generator to help preclude the potential for excessive leakage during all plant conditions. The RG 1.121 criterion for establishing operational leakage rate limits that require I plant shutdown are based upon leak-before-break considerations to detect a free span crack before potential tube rupture during faulted plant conditions. The 150 gpd limit provides for leakage detection and plant shutdown in the event of the occurrence of an unexpected single crack resulting in leakage that is associated with the longest permissible crack length. RG 1.121 acceptance criteria for establishing operating leakage limits are based on leak-before-break considerations such that plant shutdown is initiated if the leakage associated with the longest permissible crack is exceeded.

The single through-wall crack lengths that result in tube burst at 1.43 times the MSLB pressure differential and the MSLB pressure differential alone are approximately 0.57 inch and approximately 0.84 inch, respectively. A leak rate of 150 gpd will provide for detection of approximately 0.41 inch long cracks at nominal leak rates and approximately 0.62 inch long cracks at the lower 95% confidence level leak rates.

Since tube burst is precluded during normal operation due to the proximity of the TSP to the tube and the potential exists for the crevice to become uncovered during MSLB conditions, the leakage from the maximum permissible crack must preclude tube burst at MSLB conditions. Thus, the 150 gpd limit provides for plant shutdown prior to reaching critical crack lengths for MSLB conditions using the lower 95% leakrate data. Additionally, this leak-before-break evaluation assumes that the entire crevice area is uncovered during blowdown. Partial uncovery will provide benefit to the burst capacity of the intersection. Analyses have shown that only a small percentage of the TSPs are deflected greater than the TSP thickness during a postulated MSLB.

As steam generator tube integrity upon implementation of the voltage-based repair criteria continues to be maintained through inservice inspection and primary-to-secondary leakage B-12

_ _ . _ _ _ _ _ _ . . _ _ . _ _ . _ . _ _ ~

ATTACHMENT B, continusd Proposed Technical Specification Change Nos. 235 and 109 Page 13 l

monitoring, the possibility of a new or different kind of i accident from any accident previously evaluated is not

. created.

The proposed change to BVPS-1 Index, Specifications and associated Bases and.the proposed change to BVPS-2 Table 4.4-2 are editorial in nature. These changes do not change the performance of plant-systems, plant configuration or method of operating the plant.

o Therefore, the proposed change does not create the l possibility of a new or different kind of accident from any l

accident previously evaluated.

l

3. Does the change involve a significant reduction in a margin t of safety?

The use of the voltage-based repair criteria at BVPS-2 maintains steam generator tube integrity commensurate with the criteria of RG 1.121. This guide describes a' method acceptable to the Commission for meeting GDCs 14, 15, 30, 31, and 32 by reducing the probability or the consequences . of l

steam generator tube rupture. This is accomplished by L determining the limiting conditions of degradation of steam

! generator tubing, as established by inservice inspection,-for j which tubes with unacceptable cracking should be repaired or o removed from service. Upon implementation of the proposed criteria, even under the worst case conditions, the occurrence of ODSCC at the tube support plate elevations is not expected to lead to a steam generator tube rupture event l during normal or faulted plant conditions. The EOC distribution of-. crack indications at the tube support plate elevations will be confirned to result in acceptable primary-to-secondary leakage during all plant conditions and that l

radiological consequences remain within the licensing basis.

In addressing the combined effects of loss-of-coolant-l accident (LOCA) + safe shutdown earthquake (SSE) on the steam l generator component (as required by GDC 2), it has been determined that tube collapse may occur in the steam generators at some plants. This is .the case as the tube support plates may become deformed as a result of lateral loads at the wedge supports at the-periphery of the plate _due to the combined effects of the LOCA rarefaction wave and SSE loadings. Then, the resulting pressure differential on the deformed tubes may cause some of the tubes to collapse.

There are two issues associated with steam generator tube l collapse. First, the collapse .of steam generator tubing l reduces the RCS flow area through the tubes. The reduction

in. flow area increases the resistance to flow of steam from the core during a LOCA which, in turn, may potentially

increase peak clad temperature. Second, there is a potential that partial through-wall cracks in tubes could progress to B-13

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

_ .. _ _ . _ _ __ .. ~ . _ - . _ - - _ _ _ _ . . _ _ . _ _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _

ATTACHMENT B, continusd Proposed Technical Specification Change Nos. 235 and 109 Page 14 complete through-wall cracks during tube deformation or I collapse.

The results of an analysis using the larger break inputs show that the LOCA loads were found to bc of insufficient l magnitude to result in steam generrator tube collapse or '

significant deformation. Since the leak-before-break methodology is applicable to the reactor coolant loop piping, the probability of breaks in the primary loop piping is sufficiently ~ low that they need not be considered .in the structural design of the plant. The limiting LOCA event ,

becomes the pressurizer spray line break. Analysis results !

have demonstrated that no tubes were subject to deformation or collapse. No tubes have been excluded from application of the subject voltage-based steam generator tube repair criteria.

Addressing RG 1.83 considerations, implementation of the voltage-based repair criteria is supplemented by: . enhanced eddy current inspection. guidelines to provide consistency in voltage normalization,. the bobbin coil inspection will include 100% of the hot-leg TSP intersections and cold-leg intersections down to the lowest cold-leg TSP. with known ODSCC, the determination of the TSPs having ODSCC will be based on the performance of at least 20% random sampling of tubes inspected over their full length, and rotating pancake coil inspection requirements for the larger indications left inservice to characterize the principal degradation as ODSCC.

As noted previously, implementation of the tube support plate intersection voltage-based repair criteria will decrease the number of tubes which must be repaired. The installation of steam generator tube plugs reduces the RCS flow margin.

Thus, implementation of the voltage-based repair criteria will maintain the margin of flow that would otherwise be reduced in the event of increased tube plugging.

The proposed change to the BVPS-1 Index, Specifications.and associated Bases and the proposed change to BVPS-2 Table 4.4-2 are editorial in nature. These changes will not' reduce the margin of safety because they have no impact on any i safety analysis assumptions.

Based on the above, it is concluded that the proposed license amendment request does not result in a significant reduction I in margin with respect to plant safety as defined in the UFSAR or any BASES of the plant technical specifications.

F. NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Based on the considerations expressed above, it is concluded that ,

the activities associated with this license amendment request B-14

ATTACHMENT B, continuzd Proposed Technical Specification Change Nos. 235 and 109 Page 15 satisfies the no significant hazards consideration standards of 10 CFR 50.92(c) and, accordingly, a no significant hazards J

consideration finding is justified, t

l 1

\

l B-15

ATTACHMENT B, continund Proposed Technical Specification Change Nos. 235 and 109 Page 16 REFERENCES

1. NRC Generic Letter 95-05, " Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking," August 3, 1995.

2. US NRC Letter, " Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 198 to Facility Operating License No. DPR-66, Duquesne Light Company, BVPS-1, Docket No. 50-334," April 1, 1996.

B-16

ATTACHMENT C Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Change No. 109 TECHNICAL EVALUATION OF VOLTAGE-BASED REPAIR CRITERIA INTRODUCTION The purpose of this Attachment is to provide the technical basis for a request for license amendment to change the Beaver Valley Power Station Unit 2 (BVPS-2) technical specifications (TS) for the implementation of the voltage-based repair criteria for steam generator tubes affected by outside diameter stress corrosion cracking (ODSCC), according to the i guidance of NRC Generic Letter (GL) 95-05 (Reference 1) on this subject.

l This attachment describes the BVPS-2 plan for implementation of the voltage-based repair criteria and the requirements of GL 95-05.

Sections 1 to 6 of Attachment 1 to GL 95-05 are addressed herein to l summarize the BVPS-2 plan, which complies with the requirements of GL 95-05. Clarifications to the Section 3 Inspecticn Criteria are identified in the corresponding section of this attachment. These clarifications relate to implementation of the bobbin probe variability requirements (Section 3.c.2), the probe wear requirements (Section 3.c.3) and the use of alternate probes to the rotating pancake coil (RPC) probe.

BVPS-C DESIGN FEATURES I BVPS-2 is a Westinghouse 3-loop pressurized water reactor plant with Sert.es 51M steam generators (SG) featuring drilled hole tube support i pla:es and 7/8 inch diameter Alloy 600 tubing. These SGs have a flow distribution baffle plate.

Section 1: APPLICABILITY The repair criteria will be applied to predominantly axial ODSCC indications at tube-to-tube support plate (TSP) intersections (within the TSP thickness) of the steam generator tube bundle. Any other type of tube degradation or any other location in the tube bundle shall continue to be evaluated in accordance with existing BVPS-2 technical specifications. The observation of circumferential cracks, or primary water stress corrosion cracking associated with TSP indications, or ODSCC beyond the TSP thickness will be reported to the NRC prior to returning the steam generators to service (Mode 4).

The voltage-based repair criteria will not be applied at the following atypical tube-to-TSP intersections of the steam generator tube bundle:

BEAVER VALLEY - UNIT 2 Page 1 of 5

I ATTACHMENT C, continund Proposed Technical Specification Change No. 109 Page 2

1. At locations where tubes with degradation would substantially deform or collapse during postulated loss-of-coolant-accident (LOCA) and safe-shutdown-earthquake (SSE) loading. Analysis )

results provided in Attachment E demonstrate that such locations 1 do not occur at BVPS-2 and no tube locations need to be excluded I from application of the voltage-based repair criteria. )

I

2. At tube-to-TSP intersections with dent signals exceeding 5.0 l (bobbin) volts. Any indications confirmed by RPC will be l repaired. l l

3. At tube-to-TSP intersections where mixed residuals could mask a l 1.0 volt bobbin coil ODSCC indication. Any indications confirmed !

by RPC will be repaired.

4. At tube-to-TSP intersections where copper deposits interfere with bobbin coil signals. Any indications confirmed by RPC will be repaired.

l l 5. Tube-to-flow distribution baffle plate intersections.

Section 2: TUBE INTEGRITY EVALUATION There are three principal engineering analyses that shall be performed during each voltage-based repair process at BVPS-2:

a. Prediction of SG bobbin voltage population distribution.

b. Calculation of SG tube leakage during a postulated main steamline break (MSLB).

i c. Calculation of SG tube burst probability during a postulated MSLB.

The latest approved EPRI database (7/8 inch diameter tubing) utilizing NRC approved data exclusion criteria will be applied in the voltage correlations (burst, probability of leakage, MSLB leak rate) used for the leak rate, burst probability and upper voltage repair limit calculations.

The methodology for the performance of these analyses, including correlations which relate bobbin voltage amplitudos, free span burst pressure, probability of leakage and associated leak rates will be consistent with the methodology of Attachment 1, Section 2 of GL 95-05.

In addition, the upper voltage repair limit used to repair bobbin indications independent of RPC confirmation will be determined at each outage based on the guidance of Section 2.a.2 of GL 95-05.

MSLB Tube Leak Rate The calculated maximum allowable tube leak rate for BVPS-2 during a hypothetical MSLB event shall not exceed 2.95 gpm in the faulted loop.

The 2.95 gpm leak rate is calculated consistent with currently accepted BEAVER VALLEY - UNIT 2 Page 2 of 5

ATTACHMENT C, continued Proposed Technical Specification Change No. 109 Page 3 licensing basis assumptions as specified in Paragraph 2.b.4 of GL 95-

05. The analyses do NOT take credit for reduced reactor coolant system iodine activity, as allowed by this paragraph. The analyses of offsite doses and control room doses utilized dose conversion factors based on ICRP-30 as substitutes for the factors specified in the Standard Review Plan. The 2.95 gpm leak rate value is based on Attachment D. The 2.95 gpm leak rate value in the faulted loop (with leakage in the intact loops equal to the technical specification normal operation leakage limit of 150 gpd) will not result in offsite doses exceeding 10% of 10 CFR 100 requirements or control room doses exceeding 10 CFR 50, Appendix A, GDC-19, and therefore, is consistent with the BVPS-2 licensing basis. If it is determined during the operating cycle that this leakage limit might be exceeded, the reporting requirements of Paragraph 6.a.1 will be followed.

Consistent with the guidance of Section 2.c, the BVPS-2 MSLB leak rate analysis performed prior to returning the SGs to service may be performed based on the projected next end-of-cycle (EOC) voltage distribution or the actual measured distribution at a given outage.

The method selected at a given outage will be based on outage schedule constraints, particularly the ability to complete the growth rate analysis prior to restart.

Distribution of Bobbin Indications as a Function of Voltage at BOC The frequency distribution of bobbin indications found during inspection will be determined in accordance with paragraph 2.b.1 of GL 95-05.

Eddy Current Voltage Measurement Uncertainty The eddy current voltage measurement uncertainty will be determined in accordance with paragraph 2.b.2(1) of GL 95-05.

Voltage Growth Due to Defect Progression Voltage growth rate will be determined in accordance with paragraph 2.b.2(2) of GL 95-05. Steam generator chemical cleaning has not been performed; however, if chemical cleaning is scheduled in the future, the impact on voltage growth rates will be evaluated.

Section 3: INSPECTION CRITERIA All SG tubes will be inspected with a bobbin coil during each normally scheduled refueling outage. The inspection will include all hot-leg side tube-to-TSP intersections and all cold-leg side tube-to-TSP intersections to the extent of any known ODSCC. Data acquisition and analysis will be performed consistent with the methodology of GL 95-05.

Data analysts will be trained and qualified in accordance with the same program used for BVPS-1. The supplementary guidance of Section 3 of GL 95-05 will be applied with the clarifications noted below. Any indication with bobbin voltage exceeding 2.0 volts shall be inspected BEAVER VALLEY - UNIT 2 Page 3 of 5

ATTACHMENT C, continued Proposed Technical Specification Change No. 109 Page 4 with a rotating pancake coil and shall be repaired if the bobbin indication is confirmed by (PC . Any indication will be plugged or repaired regardless of any RPC inspection results, if the bobbin voltage exceeds the upper voltage repair limit as obtained per section 2.a.2 of GL 95-05.

Clarifications to Section 3, Inspection Criteria Probe wear will be monitored to ensure compliance with the NRC approved industry procedure (Reference 3). The NEI letter identifies the following exception to the referenced NRC letter regarding probe wear.

Reinspections of all intersections in low row tubes (rows 1-9) where entry from both the cold-leg as well as the hot-leg would be required will not be performed. All tubes with indications above 75% of the repair limit will be reinspected with an acceptable probe when the probe fails the wear check. Non affected intersections in those subject tubes will be reinspected as permitted by access from the hot-leg side unlesu cold-leg entry is required to reinspect indications on the cold-leg side that are above 75% of the repair limit. This exception will be applicable to BVPS-2.

Additionally, the industry methodology will be utilized for new probe variability as approved by the NRC and further acknowledged in NEI letter dated February 23, 1996.

Section 4: TUBE REMOVAL AND EXAMINATION / TESTING The BVPS-2 program for tube removal and examination will comply with the guidance of Section 4 of GL 95-05. The corrosion morphology of the degradation at the tube support plate intersections in the BVPS-2 steam generators will be demonstrated to be consistent with that attributable to ODSCC via tube pulls and destructive analysis. The number and frequency of subsequent tube pulls will be consistent with GL 95-05 requirements, or BVPS-2 will participate in an NRC endorsed industry program per Section 4.a of GL 95-05.

Section 5: LEAKAGE The operational leakage limit will be revised to 150 gpd through each SG. SG tubes with known leaks will be repaired prior to returning to service. Leakage monitoring measures will follow the guidance of the industry /EPRI report of Reference 2.

Section 6: REPORTING REQUIREMENTS BVPS-1 will comply with the reporting requirements of Section 6 of GL 95-05.

BEAVER VALLEY - UNIT 2 Page 4 of 5

1 l

ATTACHMENT C, continued l Proposed Technical Specification Change No. 109 !

Page 5 j REFERENCES

]

1. NRC Generic Letter 95-05, " Voltage-Based Criteria for Westinghouse ;

Steam Generator Tubes Affected by Outside Diameter Stress j Corrosion Cracking," August 3, 1995.

2. EPRI TR-104788, "PWR Primary-to-Secondary Leak Guidelines,"

Research Project S550, Final Report, May 1995.

3. NRC letter from Brian Sheron (NRR) to Alex Marion (NEI) dated l

February 9, 1996 and NEI letter from Alex Marion to Brian Sheron l dated February 23, 1996.

, I i

r l l I

i l

l l

i l

EEAVER VALLEY - UNIT 2 Page 5 of 5

ATTACHMENT D Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Change No. 109 MAIN STEAMLINE BREAK DOSE ANALYSIS FOR VOLTAGE-BASED TUBE INSPECTION CRITERIA I

i

RTL: A9.621 A Form: RE 1.103-1

$ y 1W '

Health Physics Department REVISION O 1 2 3-Subject Safety Anaiysis of the EAB, LPZ, and Control Room Doses PAGE 1 Or from a Main Steam Une Break Outside of CNMT at U2 with ERS-SFL-96-010 Increased Primary-to-Secondary Leakage (SG APC) N#

Reference RCM RP EPP T/S EM DCP RIP Review Category 10 CFR 50.59 E RSC Reg'd RSC Not Reg'd Required 1 Purpose The purpose of this calculation package is to assess the maximum primary-to-secondary leakage that could occur and postulated EAB, LPZ, and CR doses still remain within applicable limits. This analysis performed in support of a license amendment to institute alternate plugging criteria (APC) at Unit 2.

NOTE:This calculation package documents the evaluation described above. This package DOES NOT,in ofitself, provide autority for any revision in a structure, system, or component; nor changes in procedures, tests, and experiments described in the plant licensing basis. The data and/or conclusions of this package shall not be extended to other purposes without explicit concurrence from Radiological Engineering.

by date chk date WP date by date

^*

3 date 49 date by date 2 ch*

date app date by date 1 chu date RPP f date Y 5/19/96 Checklist Attachments 0 E Purpose E Input Data E Data Sheets

', [ da f M Assumptions E Results E Illustrations

,p E Methodology E References N Printouts For RSC /O-gc, O Code Listings E BV RECORDS CENTER O DIR, RadOps-1 E Author: S.F. LaVie E CALCULATION FILE D DIR, Radops-2 E G.A. Kammerdeiner O MGR, Health Physics O DIR, Safety & Env Sves E R.N. Ireland E DIR, RadEng & Health O Trng Dept.. O AC961002.PM5 l

RTL: n/a Form: RE1.103-3 9/92 DNM Health Physics Department ERS-SFL-96-010 Page 2 DISCUSSION

1. General in 1996, Unit 1 submitted a license amendment request (IA2N)' for steam generator alternate plugging criteria (APC) in accordance with the provisions of USNP.C Generic Letter 95-052 ,

Ucense amendment 198 was issued.. For that proceeding, the assest, ment of the offsite dose consequences was prepared by Westinghouse3 . The control room dose assessment was per-formed in-house'.

For the Unit 2 licensing, SWEC evaluated the radiological consequences of a main steam line break assuming technical specification RCS activity and primary-to-secondary leakage. The 5

analysis was performed in accordance with the Standard Review Plan Chapter 15.1.5 and addressed both concurrent and pre-incident lodine spiking. This analysis was documented in 12241 UR(B)-3548 and in 915.1.5 of the Unit 2 UFSAR7 The work herein will be Ivgely based on that analysis.

SWEC also performed calculations of the potential control room doses from DBAs at Unit 28.e and at Unit 1.1 " These calculations became part of the licensing basis for BVPS-1 and -2 and have been documented in the UFSARs 2 7. Since 1987, there have been various re-analyses made of the control room habitability.4.13 '4 5 817.18.18.2o The referenced analyses modified one or more design basis aspect (s) of the original SWEC calculations (References 8-11). There have been additional re-analyses performed as part of various incident reports. These !ater analyses address specific situations and are not part of the design basis.

The purpose of this calculation is to determine a maximum allowable accident leakago re'.a in j support of alternate plugging criteria for Unit 2. This leakage rate will be the more restrictive of rates based on (1) offsite dose, or (2) contro! room dose.

2. Main Steam Line Break l

l The acceptability of the plant design to withstand steam generator leakage and not cause unac-ceptable offsite radiological consequences is assessed during plant licensing by the required analyses of a complete rupture of a single steam generator tube, i.e., the design basis Steam Generator Tube Rupture (SGTR), and by the inclusion of technical specification primary to-secondary leakage rates (and technical specification reactor coolant radioactivity) as input parameters to other design basis accidents, such as loss of AC power auxiliaries, CRDM ejec-tion, and, of specific interest here, main steam line breaks.

Main steam line breaks are of interest to the issue of degraded steam generator tubes because (1) the secondary depressurization event results in the most rapid differential pressure transient on the steam generator tubes thus increasing the probability of tube failure, and (2) should the tubes fall, the event would constitute a failure of two of the three fission product barriers and result in a release of radioactivity to the environment. j in typical design basis calculations, there is a single initiating event, in this case, a failure of the main steam piping outside containment. The analyses address this initiating event, and any failures that are a direct consecance of the initiating event. Leakage of the steam generator tubes greater than technical specifications was not postulated in the original analyses of record ;

AC9610o1.PM5

l RTL: n/a Form: RE 1.103 3 297 1 Duquesm @ ERS-SFL-96-010 h HealthPhysicsDepartment page 3 since the steam generator tubes were assumed to have sufficient structural integrity to withstand the expected differential pressure by a very large margin. Since this analysis is being performed to support a licensing amendment allowing continued operation with steam generator tubes that have known indications of degradation, it is appropriate that the consequential tube leakage be considered. !

l METHODOLOGY l

1. Overall Methodology The analyses in this package uses version 2.0 of the TRAILS (for Transport of Radioactive ,

material in Linear Systems) code documented in ERS-SFL-89-0202' This code is comparable l to the DRAGON code used by SWEC in the References 8 - 11 analyses, i.e., the original analy-ses of record. There are some differences between DRAGON and TRAILS that warrant discus-sion. The differences and the justification thereof are described below:

I 1.1 DRAGON assesses the buildup of daughter radioactivity due to the decay of a parent radionuclide. TRA!LS does not assess this contribution. The decay of the iodine radioiso-topes produces xenon radioisotopes. Thus, TRAILS tends to underestimate the xenon i concentrations. This is not a significant concern in the current analysis in that noble gas l exposure is not limiting. This is a conservative situation with regard to the onset of the radiation monitor alarm and the actuation of control room isolation, since the TRAILS gamma dose rate results will be slightly underestimated, thus delaying isolation. I 1.2 The DRAGON and TRAILS codes differ in dose calculational methods:

1.2.1 The DRAGON code used in the original licensing analyses of record determined whole body-photon, whole body-beta, and thyroid dose as defined in TID 1484422 4 and Regulatory Guides 1.4 23 and 1.2524, 1.2.2 Version 1.0 of the TRAILS code determined the same dose quantities as did DRAGON, using the same data sources for the thyroid dose, and the formulae of )

Reference 23 for the whole body doses. The energy per disintegration values used ;

in the whole body dose formulae were taken from the BVPS Radionuclide Data l Basees rather than the reference stated in Reference 23 (which is no longer in l print). TRAILS implements the infinite-to-finite cloud correction algorithm of Murphy and Campe.28 In previous test calculations performed in Reference 27, close correlations were demonstrated with the previous DRAGON results.

1.2.3 Version 2.0 of the TRAILS code uses the same dose calculational methodology of version 1.0 and adds the capability for assessing the dose quantities: effective dose equivalent (external) (EDE), skin dose equivalent (DE), arid thyroid committed dose equivalent (CDE). In accordance with licensing positions taken in REAP-1.106, Dose Calculation Methodoloav in DBA Analyses 28, these dose quantities may be utilized in license proceedings as substitutes for the outdated corresponding dose I quantities of Reference 23 provided the initial application is reviewed by the NRC l staff. The analysis herein is being performed in support of a license amendment.

Thus, this stipulation will be satisfied.

AC961001.PM5

l RTl; n/a Form: RE 1.103-3 292 Ducpese M ERS-SFL-96-010 Health Physics Department I 1.2.4 Version 2.0 of TRAILS also assesses the committed effective dose equivalent i (CEDE) and the total effective dose equivalent (TEDE). These dose quantities may l not be used for showing compliance with 10 CFR Part 100.11, since that guideline l specifically references the whole body and thyroid dose quantities. ,(See assump-tion 1.11 for applicability to control room habitability analyses showing compliance to GDC19.)

)

1.3 The DRAGON code does not provide a direct means to handle concurrent iodine spiking.

The method used by SWEC as a work-around involves averaging. The TRAILS code can isotopically model initial activity and a constant introduction rate, and, therefore can exp!ic-itly model concurrent spiking. Thus, there may be slight differences between the DRAGON

! and TRAILS cases and results.

2. Control Room Modeling The modeling of the control room intake and exhaust is described in Appendix 1 to this calcula-tion package. With specific regard to yfQ, the turbine building value is the more limiting of the possible break locations.

Note that previous analyses of the consequences of a main steam line break accident (assuming

! 1 gpm primary-to-secondary leakage) on the control room habitability have shown that automatic l Isolation and pressurization of the control room does not occur. The control room radiation l

monitor reading did not exceed the monitor setpoint. Instead, previous analyses have conserva- l l tively assumed that the control room operators would manually initiate control room isolation and l pressurization at T=30 minutes. See Assumption 1.7. l l

l The monitor setpoint was developed by SWEC during Unit 2 licensing and was based on the dose rate at the monitor submerged in a cloud of gas having a concentration that would result in J l a 30-day inhalation dose less than 30 rem (thyroid dose limiting). When the analysis was per- 1 l formed, the small line break (outside CNMT) was the limiting accident. The intake concentration for the main steam line break did not result in a early radiation monitor alarm, but would be j l sufficient to result in doses exceeding GDC1929. With the increased primary-to-secondary leakage assumed in this analysis, the control room radiation monitor reading may exceed its setpoint and isolation may occur prior to 30 minutes post-accident. The analysis herein will I

assess the timing of control room isolation actuation via the radiation monitor for differing leakrates. The dependency of the postulated dose on the timing of control room isolation, as weil as the primary-to-secondary leak rate, makes it impossible to calculate a " rem per gpm" value valid for all leak rates.

l 3. Main Steam Line Break Modeling i iI The radioactivity releases from this accident are addressed in a series of cases. The results from applicable cases are summed to obtain the total postulated dose. In order to determine the timing of control room isolation, limiting cases may be run twice for each leakage - once for dose rate with no isolation assumed, and once for dose, with the isolation credited. The cases are (see Attachment 1):

FRP: Release from Eaulted S/G, aupture leakage P_re-incident RCS iodine spike activity. Re-lease rate from steam generator equal to release rate from RCS. No hold-up or iodine AC961001.PM5 l

RTU n/a Form: RE 1.103-3 R92 OWN M Ak HealthPhysicsDepartrnent ERS-SFL-96-010 page 5 decontamination credited. Eight hour release. Noble gases and lodines considered.

Replaces model #1 of References 6 and 8 FRC: Release from Eaulted S/G, Hupture leakage, Concurrent RCS iodine spike activity plus T/S equilibrium activity. Release rate from steam generator equal to release rate from RCS. No hold-tp or iodine decontamination credited. Eight hour release. Noble gases and lodines consicered. Replaces model #Cl-1 of Reference 6 and model #1C of Reference 8.

ITN: Release from Intact S/Gs,I/S leakage, RCS Hoble gas activity. Release rate from steam generator equal to release rate from RCS. No hold-up credited. Eight hour release. Noble gases considered. Replaces model #2 NG of References 6 and 8 ITP: Release from Intact S/G, I/S leakage, Ere-incident iodine spike RCS activity. Release rate from steam generator equal to release rate from RCS. Eight hour release. No hold-up credited. However, release rate reduced by factor of 100 to reflect lodine partitioning after ;

one hour. Replaces model #2 I of References 6 and 8.

Note: Partitioning credit is appropriate whenever the steam generator levelis such that the l tube leak location is submerged. In this event, the levelin the intact steam generators will initially drop, but is assumed to be restored within one hour. See assumption 1.10 below.

ITC: Release from Intact S/G, I/S leakage, Concurrent iodine spike plus T/S equilibrium RCS activity. Release rate from steam generator equal to release rate from RCS. Eight hour release. No hold-up credited. However, release rate reduced by factor of 100 to reflect iodine partitioning after one hour. Replaces model #2 I of References 6 and 8.

See note above under ITP FLI: Release from Eaulted S/G, Liquid lodine activity initially present in S/G. Release rate based on release of 99.999999% of pre-accident activity in the liquid phase in 30 minutes. Re-places model #3 of References 6 and 8.

Note: The 30 minute assumption is based on the assumption used in the original analyses in Reference 6. The exponential transfer lambda associated with the stated release and duration is such that 99.3% of the activity is released in the first second. Thus, the assump-tion will be retained as it is sufficiently conservative.

ILl: Release from Intact S/Gs, Liquid lodine activity initially present in S/G. Release rate based on steaming rate of steam generator. Hold-up is modeled. Release rate reduced by a factor of 100 to reflect iodine partitioning. Replaces model #4 of References 6 and 8.

Note: This partitioning not affected by S/G Ievel since the activity was dispersed in the liquidprior to the event. Case ITP /ITC/ITN address leakage after the start of the event.

ASA: Release from All S/Gs, _S_ team space activity initially present in S/G, pre-incident S/G activity, All nuclides. Instantaneous puff release (99.999999% in 1 second.) Replaces model #5 of References 6 and 8.

AC961o01.PM5

RTL: n/a Form: RE 1.103-3 292 M

Heahh Physics Department ERS-SFL-96-010 Page 6 For the pre-incident iodine spike cases FTP and ITP, the dose equivalent iodine-131 technical specification activity of 60 Cl/gm will be used to obtain the pre-incident activities for the five lodine nuclides. These will be added to the lodine and noble gas equilibrium concentrations associated with the 1.0 Cl/gm dose equivalent lodine-131 technical specification.

For the co-incident iodine spike cases FTC and ITC, the iodine appearance rates equal to 500 times the lodine appearance rate that yields the 1.0 Ci/gm dose equivalent lodine-131 technical specification concentrations will be added to the lodine and noble gas equilibrium concentra-tions. At four hours post accident, the concurrent spike ceases (modeled by dividing lodine appearance rates by 500).

For the ITN case, the noble gas concentrations associated with the 1.0 pCi/gm dose equivalent lodine-131 technical specification concentration are used.

For the FLI and ILI cases, the iodine activities in the steam generator liquid phase associated with the 0.1 pCl/gm equilibrium concentration dose equivalent iodine-131 technical specification are used. Noble gases are assumed to enter the steam phase immediately.

For the ASA case, the activities in the steam phase associated with the 0.1 Cl/gm equilibrium ;

concentration dose equivalent lodine-131 technical specification are used.

It is important to note that only the FRP and FRC cases vary as a function of accident primary-to-secondary leakage. Thus, the other models can be calculated once and added to the sequence of FRP and FRC cases.

INPUT DATA AND ASSUMPTIONS This section documents input data that are applicable to this analysis. Appendix 1 provides additional input data associated with the control room modeling.

1. Assumptions 1.1 The analysis of the main steam line break (MSLB) is based on the guidance provided in Chapter 15.1.5 of Reference 5 and Reference 2.

1.2 There is no failed fuel for the MSLB The Unit 2 UFSAR shows that DNB is not exceeded for a MSLB. In accordance with Reference 5, no fuel damage need be assumed if DNB is not exceeded.

1.3 The MSLB occurs outside of containment releasing activity from the faulted and the intact steam generators.

1.4 The transport of radioactivity from the point of release from the CNMT or a system to the control room intake is assumed to be instantaneous.

This is a conservative assumption in that the activity intake during damper movement and diesel start-up and sequencing is maximized.

AC961oo1.PM5

I RTL: n/a Form: RE 1.103-3 292 D"N M Health Physics Department ERS-SFL-96-010 page 7 i 1.5 incoming air is uniformly distributed throughout the control room volume. !

1 This is a conservative assumption in that the radiation monitors will alarm when the dose from l l' the cloud of gases adjacent to the monitor exceeds the setpoint. Assuming complete mixing l reduces the concentration and dose, thereby delaying the isolation actuation.

1.6 The control room process safety limit of 30 rem thyroid is represented by the process safety limit (PSL) of 1 mR/hr on the control room area monitors.

The PSL was established as part of the Unit 2 licensing process. Analyses performed at that time indicated that for the most restrictive accident, the 30 day thyroid dose critedon would not s

be exceeded if a certain airbome concentration was not exceeded. The postulated extemal dose l l rate from this airbome concentration was shown to equal 1.0 mrem gamma. Because ofinstru-ment uncertainties, the actual trip setpoint (TSP) of the monitor is established at 0.47 mR/hr.

Thus, the actualisolation may occur as early as 0.47 mR/hr, but no later than 1 mR/hr, depend-

, ing on the actual summation of uncertainties. l 1.7 Because the radiation monitor will not reach its setpoint for a protracted period, this analysis assumed that the Control Room Emergency Bottled Air Pressurization System (CREBAPS) will be actuated by manual operator action at 30 minutes following event initiation.

1 The Unit 2 Emergency operating procedure (EOP) E-2, Faulted Steam Generator Isolation has, as its very first step, the requirement that the operator verify Control Room Emergency Bottled Air Pressurization System (CREBAPS) actuation. The procedure step " response not obtained" requires manual actuation. The operators have several rapidindications of a MSLB. The break k assumed here will result in steam line isolation, safety injection, and a reactor trip. Entry into the EOPs (E-0) occurs on a reactor trip or safety injection. The transition from procedure E-0 to E 2 l occurs within minutes after the status of the trip, safety injection, electricalpower, and other l safety equipment operability is veriRed. Thus, this assumption is deemed appropriate. l 1.8 Loss of power is assumed coincident with the accident initiation.

4 This assnption meets the requirements of 93.1.1.3 of the FSAR that states that a loss of offsite power is assumed if the postulated event orits effects results in a reactor or turbine trip. This requirement implies a coincident loss of power. This assumption does not impact the results in that control room isolation by radiation monitor was not assumed.

j 1.9 Unfiltered inteakage of 10 cfm is assumed during control room pressurization.

This assumption is consistent with Reference 5, Chapter 6.4. Note that this inleakage is intended to address the air inleakage associated with access air lock door openings while the control room is pressurized. Reference 5 does not specifically require this assumed inleakage for the BVPS type of control room design. It is required for zone recirculation type of control rooms and is included herein for consistency with the originallicensing basis.

1.10 The level in the unaffected, intact steam generators is restored to greater than 5% narrow range within one hour, in response to the rapid pressur!zation of the main steam line, main steam line isolation (<500 psigt) will occur, pressurizer level will drop to below the SI actuation setpoint (1845 psig$).

AC961ool.PM5

l RTL: n/a Form: RE 1.103-3 292 )

Dugsesm M ERS-SFL-96-010 Page 8 k Hea2PhysicsDepartment l When Si occurs, all three auxiliary feedwater pumps will receive a start signal and willinject water into the steam generators. The EOPs will have the operatorisolate feedwater to the faulted steam generator. However, these EOPs direct the operator to ensure that (1) the dis-charge MOVs for the intact generators are fully open, and (2) once levelis restored, that the levelis controlled between 5% and 50%. It is significant to note, that if the levelis less than 5%

in allintact S/Gs and feedwater flow is less than 350 gpm, a heat sink red path critical safety function terminus is declared and function restoration procedure FR-H.1 is entered. As long as the heat sink is in a red path, all operator attention is directed to restoring the heat sink. Simula-tot training scenarios responses indicate that the levelis restored to greater than 5% within 30 minutes from completion of blowdown of the faulted generator. It is therefore reasonable to assume that partitioning be credited after one hour from the start of the event. The doubling of the expected time to cover the tubes was done to provide additional margin for this qualitative conclusion.

1.11 The EDE result provided by TRAILS is assumed to correspond to the whole body photon guide-line in SRP 6.4, the skin DE to whole body beta, and the thyroid CDE to thyroid. ;

I See REAP 1.106 for justification.

NOTE: Assumption 1.11 is valid only in the context of a license amendment request that is to be reviewed by the NRC staff. The assumption is considered to be unreviewed safety question since the methodologies and assumptions of the original reviewed analyses j are modified by this assumption. Once the license proceeding is approved by the NRC, '

this assumption may be considered part of the design basis for this particular postu-lated accident.

1.12 The conversion of water volume to mass (e.g., gpm to Ibm / hour, gm/sec, etc.) will assume a density of 1.0 g/cm3.

The density of the RCS at operating pressure and temperature is approximately 0.7 gm/cm'.

Thus, this assumption is conservative in that it results in a larger assumed mass for a unit vol-ume. However, as the event progresses, the trend in RCS density is towards 1.0 gm/cm*. A density gradiant exists in the steam generator between a density of about 1.0 for the incoming auxilary feedwater to a lower density associated with the steam properties. Assuming a density i of 1.0 g/cm' eliminates the need to assess the changes in state as the incident progresses. Per the UFSAR, RCS pressure and temperature decrease to <1000 psia and 400*F within 200 seconds following a MSLB. At these parameters, the density Is about 0.88 gm/cc. l

2. Input Data 2.1 Technical Specification Concentrations *, pCi/gm [7,30]

those concentrations that equate to 1.0 pCi/gm DE I-131 in RCS; 0.1 pCi/gm DE I-131 in S/G based on TID 14844 DCFs. (See T/S definition of dose equivalent I-131.)

AC961001.PM5

RTL: n/a Fcrm: RE1.103-3 A92 DS"N M Ak HealthPhydesDepartment ERS-SFL-96-010 p,g, 9 S/G S/G Huclide BC1 !!g steam Kr-83m 1.13E-1 -

4.87E-6 Kr-85m 5.51 E-1 -

2.37E-5 Kr-85 2.91 E+0 -

1.25E-4 Kr-87 3.15E-1 -

1.36E-5 Kr-88 8.40E-1 -

3.62E-5 Kr-89 2.65E-2 -

1.14E-6 Xe-131m 2.83E-2 -

1.22E-6 Xe-133m 8.09E-1 -

3.49E-5 Xe-133 6.89E+0 -

2.97E-4 Xe-135m 2.86E-1 -

1.23E-5 Xe-135 8.45E-1 -

3.64E-5 Xe-137 4.29E-2 -

1.85E-6 Xe-138 1.77E-1 -

7.63E-6 l-131 6.60E-1 6.87E-2 6.87E-4 l-132 2.30E-1 2.03E-2 2.03E-4 l-133 1.03E+0 9.84E-2 9.84E-4 l-134 1.44E-1 4.53E-4 4.53E-6 l-135 5.54E-1 4.40E-2 4.40E-4 2.2 Pre-incident lodine Spike Concentrations, Ci/gm (6,7]

Nuclide BCS l-131 39.9 l-132 13.9 l-133 62.2 1-134 8.7 l-135 33.4 I

2.3 Concurrent lodine Spike Rate, Ci/sec [6,7] l Nuclide hcl 1-131 1.36E+6 l-132 2.52E+6 l-133 3.08E+6 l-134 3.68E+6 l-135 2.81 E+ 6 2.4 Concurrent lodine Spike Duration = 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months [6,7,31 )

This is a licensing basis assumption used in the original analyses. See UFSAR Table 15.1-3. ,

AC961001.PM5

RTL: n/a Ferm: RE 1.103-3 M2 DMN M Health Physics Department ERS-SFL-96-010 page 10 2.5 Technical Specification Primary-to-Secondary Leakage [*]

150 gpd any one generator,450 gpd tota!

These values will replace the 500 GPD,1 gpm T/S currently in place as part of this license amendment. ;

i 2.6 Primary Coolant Mass = 4.2E5 lbm,1.91 E+8 gm [6]

2.7 Secondary Side Mass [6]

Liquid: 99300 lbm = 4.50E+7 gm @ generator Vapor: 8700 lbm = 3.95E+6 gm @ganerator 2.8 lodine Partition Factors [5,6]

Steam release from faulted S/G = 1.0 l Initial steam release from non-faulted S/Gs = 1.0 [5,6]

Steam release from non-faulted S/Gs after 1.0 hour0 days 0 hours 0 weeks 0 months = 0.01 [ Assumption] j i

2.9 Time to isolate Faulted S/G = 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months [6]

2.10 Steam Release from Intact S/Gs [6]

0-2 hrs: 366,776 lbm 2-8 hrs: 705,393 lbm 2.11 Breathing Rate = 3.47E-4 m8 /s [23]

2.12 Atmospheric dispersion (yjQ) values, sec/m 3 [6,7]

EAB 0-2 hours = 1.44E-3 l LPZ 0-8 hours = 7.07E-5 CALCULATION i i

1. Activities Datum 2.1 provides the technical specification concentrations, in pCi/gm, in the RCS and in the ,

S/Gs. For use in TRAILS, these values must be expressed in terms of activity, in Cl. The l

conversions are:

RCS: ARCS = CRCS. Ci/gm x 1.91E8 gm SG Liquid: ASG = Cse, Cl/gm x 4.50E7 gm (each S/G)

SG Vapor: Age = Cse, Ci/gm x 3.95E6 gm (each S/G)

AC961o01.PM5 4

RTL: nh Ferm: RE1.103-3 A92 DuqueSN M ERS-SFL-96-010 page 11 Ak HealthPhysicsDepartment Table 1 Technical Specification Equivalent Activities, uCl

@SG @SG NucIlde ILQR llq Vapor Kr 83m 2.16E+07 0.0 1.92E+01 Kr-85m 1.05E+08 0.0 9.34E+01 Kr-85 5.56E+08 0.0 4.93E+02 Kr-87 6.02E+07 0.0 5.36E+01 Kr-88 1.60E+08 0.0 1.43E+02 Kr-89 5.06E+06 0.0 4.49E+00 Xe-131m 5.41 E+06 0.0 4.81 E+00 Xe-133m 1.55E+08 0.0 1.38E+02 Xe-133 1.32E+09 0.0 1.17E+03 Xe-135m 5.46 E+07 0.0 4.85E+01 Xe-135 1.61 E+08 0.0 1.43E+02 Xe-137 8.19E+06 0.0 7.29E+00 Xe-138 3.38E+07 0.0 3.01 E+01 1-131 1.26E+08 3.09E+06 2.71 E+03 1-132 4.39E+07 9.14E+05 8.02E+02 1-133 1.97E+08 4.43E+06 3.89E+03 1-134 2.75E+07 2.04E+04 1.79E+01 1-135 1.06E+08 1.98E+06 1.74E+03 For the pre-incident iodine spike cases, the datum 2.2 values were added** to the datum 2.1 RCS values and corrected to activity.

Table 2 RCS Pre-incident fodine Spike Nuclide RQ.1 Kr-83m 2.16E+07 Kr-85m 1.05E+08 Kr-85 5.56E+08 Kr-87 6.02E+07 .,

Kr-88 1.60E+08 i Kr-89 5.06E+06 Xe-131m 5.41 E+06 Xe-133m 1.55E+08 Xe-133 1.32E+09 Xe-135m 5.46E+07 Xe-135 1.61 E+08 Xe-137 8.19E+06 Xe-138 3.38E+07 l-131 7.73E+09 l-132 2.70E+09 l-133 1.21 E+10 l l-134 1.69E+09 l-135 6.49E+09

- NOTE: This is conservative. The pre-incident values are based on T/S. Thus, the 1-131 thru l.

135 datum 2.2 values already include the equilibrium iodine values. The difference is 1-2%

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RTL: nh Form: RE 1.103-3 9N2 DNM Ak HeahhPhysicsDepartment ERS-SFL-96-OiO page 12

2. Transfer Coefficients initial transfer coefficients for the model cases are determined in this section. Density based on assumption of 1.0 gm/cc (see Assumption 1.12):

8.345 1=

gal 453.599m gal 2.1 FRP, FRC

)

Base the release rate on a primary-to-secondary leakrate = 1,3,5,7 gpm. For one gpm: l 1.0 gpm = 1.6666E-2 gal /sec = (1.6666E-2 gal /sec)(8.345 lb/ gal) / (4.2E5 lbm) = 3.3114E-7 sec-1 3.0 gpm = 3.3114E-7 x 3 = 9.9341E-7 sec-1 5.0 gpm = 3.3114E-7 x 5 = 1.6557E 6 sec' 7.0 gpm = 3.3114E-7 x 7 = 2.3180E-6 sec 1 Intermediate results indicated that a leak rate of 2.95 gpm would be acceptable. The release rate is then:

2.95 gpm = 3.3114E-7 x 2.95 = 9.7686E-7 sec-1 2.2 ITN Base the release rate on a primary to secondary leakrate = 300 gal /d (3.4722E-3 gal /sec) [2 x datum 2.5]:

release rate g, = (3.4722E-3 gal /sec)(8.345 lb/ gal) / (4.2E5 lbm) = 6.8990E-8 sec 1 l

(Since the release rate represents two S/Gs, the Table 1 RCS activities need not be multiplied.) l 2.3 ITP, ITC Same as ITN for first hc.ur. After the first hour, the release rate is reduced by a factor of 100 to account for partitioning:

release rate,., = 6.8990E-8 sec-1/100 = 6.8990E-10 sec-1 The 0-1 hour value will be entered as the base value. The XREM multiplier after one hour is 0.01 (Since the release rate represents two S/Gs, the Table 1 RCS activities need not be multiplied.)

2.4 FLI Release from faulted S/G of liquid activity initially in S/G. Hold-up credited.

In order to model the release of 100% of the initial activity in 30 minutes, it will be assumed that AC961001.PM5

RTL: n/a Ferm: RE 1.103-3 C92 DNM k HeahhPhysics0epartment ERS-SFL-96-010 page 13 a reduction of 1.0E-6 represents 100% of the activity. The release rate (A) can be found:

0.000001= e-Ax1soo

A = 7.675E-3 seca l

2.5 lLI Release from intact S/Gs of liquid activity initially in S/G. Hold-up and partitioning credited.

Datum 2.11 provides a release of 366,766 lbm in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and a release of 705,393 lbm in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Both of these values represent the release from both intact S/Gs. Thus, in order to determine the release rate from bath S/G, we divide by the mass of one generator (99,300 lbm)

Partitioning applies since the activity is already in the water and break flow above the water is thus not a concern. The release rate is multiplied by 0.01.

release ratea2 = (366,776 lbm / 7200 sec) / (99,300) x 0.01 = 5.1300E-6 seed release rate,. = (705,393 lbm / 21600 sec) / (99,300) x 0.01 = 3.2887E-6 seed 1

The 0 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months value will be entered as the base value. The XREM multiplier after two hours is l 3.2887/5.1300 = 0.64. Since the release rate represents the mass of two SG, the Table 1 activi- 1 ties need not be multiplied.

2.6 ASA l Release from all S/Gs equal to release fraction of 1E-6 in 1 second of activity initially in S/G steam space, all nuclides.

0.000001= e-A*1 A = 13.82 sec-1 The steam activity (per SG) needs to be multiplied by 3.

3.0 Control Room Dose Rates The Unit 2 control room isolation is activated by either CNMT isolation phase B (CIB) or high radiation alarm on the control room area monitors. For this particular sequence, CIB will not occur since the steam line break is postulated to occur outside of the CNMT. Experience has indicated that the control room monitor will not alarm for a MSLB break early enough to provide mitigation. For this l reason, this analysis assumes that the control room isolation occurs at T=30 minutes by manual actuation, that emergency pressurization fans start at 90 minutes, and that the control room is purged at t=8 hours for 30 minutes. See Assumption 1.7 and Appendix 1.

In order to confirm the above conclusion, two TRA!LS runs were made. One was done for the cocurrent lodine spiking case for the faulted S/G (FRC), the other for the pre-incident lodine spiking case for the faulted S/G (FRP) Both were done assuming a primary-to-secondary leakage of 7 gpm AC961001.PM5

1 l

RTL: n/a Form: RE 1.103-3 A92 Duquesm @ ERS-SFL-96-010 page 14 k HealthPhysicsDepartment and a continuous unfiltered 500 cfm intake to the control room. The TRAILS printouts are in Attach-ment 2. A graph of the dose rate versus time is provided in Attachment 3. The monitor alarm setpoint is not reached prior to 30 minutes. The other release cases (e.g., ASA, ITN, etc.) would be negligible contributors to the dose rate.

Note: Computer runs were made on the ARERAS VAX and saved to text files. These tiles were down-loaded via KERMIT to Word 6.0 on a PC. The files were edited on the PC to remove repetitive mate-rialin the interest of saving paper.

4.0 Offsite and Control Room Dose Parameter input files were built using the assumptions and parameters discussed above. TRAILS was re-run to obtain the postulated offsite and control room doses. The LPZ and CR cases were pro-cessed in the same run with a separate run used to assess the EAP, dose. The FRP and FRC cases are the only cases directly dependent on the magnitude of the i:reak flow. For this reason, these two cases were re-run several times to obtain the results for the various flow rates. Only excerpts of these ;

runs are provided since they represent intermediate results. From these results, it was determined that j the maximum leak rate would be 2.95 gpm. The FRP and FRC cases were edited and re-run for 2.95 gpm. The results are tabulated in the RESULTS section. Attachment 4 provides excerpts from the code run printouts.

5.0 Release Activity ;

The isotopic activity released during a MSLB with 2.95 gpm primary-to-secondary leakage from 0-2 l hours and from 0-8 hours (duration) are tabulated in Attachment 5. ,

l RESULTS The results showed that the maximum allowable leak rate would be 2.95 gpm. The dose results for the analyzed cases are tabulated below.

Postulated EAB Dose (0-2 hr)

MSLB - Concurrent lodine Spike EDE Skin DE Thyroid CDE mrem miem mrem ASA 6.04E-03 3.30E-03 5.53E+00 ILI 7.00E-02 3.69E-02 7.53E+01 FLI 2.14E+00 1.09E+00 2.10E+03 ITC 2.15E+00 8.08E-01 5.09E+02 1 ITN 4.93E-02 6.03E-02 0 l FRC - 2.95 gpm 1.06E+02 4.08E+01 2.72E+04 SUM 1.10E+02 4.28E+01 2.99E+04 +--Limiting Value Criterion 2.50E+03 2.50E+03 3.00E+ 04 AC961001.PM5

I RTL: nh Fum: RE1.103-3 9M M

A> HealthPhysicsDepartment ERS-SFL-96-010 Page 15 i Postulated LPZ Dose (0-8 hr)

MSLB - Concurrent lodine Spike l

l EDE Skin DE Thyrold CDE l mrem miem mrem ASA 2.97E-04 1.62E-04 2.73E-01 ILI 7.89E-03 4.42E-03 1.02E+01 l FL1 1.05E-01 5.37E-02 1.03E+02 )

! iTC 1.27E-01 4.89E-02 3.48E+01 ITN 5.90E-03 9.45E-03 0 FRC - 2.95 aom 3.58E+01 1.51 E+01 1.51 E+04

)

~~

l SUM 3.60E+01 1.52E+01 1.52E+04 l

Crlterion 2.50E+03 2.50E+03 3.00E+04 i

Postulated CR Dose (30 day)

MSLB - Concurrent lodine Spike )

EDE Skin DE Thyroid CDE miem mrem miem ASA 2.76E-05 3.23E-04 6.43E-01 ILI 1.22E-04 1.37E-03 3.21E+00 l FLl 9.78E-03 1.07E-01 2.38E+02 l ITC 1.93E-03 1.61 E-02 1.65E+01 ITN 3.79E-04 1.48E-02 0 FRC - 2.95 gpm 1.83E-01 1.78E+00 1.89E+03 SUM 1.95E-01 1.92E+00 2.15E+03 Criterion 5.00E+03 3.00E+04 3.00E+04 Postulated EAB Dose (0-2 hr) ;

MSLB - Pre-incident lodine Spike l

EDE Skin DE Thyrold CDE miem mrem mrem l ASA 6.04E-03 3.30E-03 5.53E+00 ILI 7.00E-02 3.69E-02 7.53E+01 FLI 2.14E+00 1.09E+00 2.10E+03 ITP 1.67E+00 8.09E-01 1.34E+03 ITN 4.93E-02 6.03E-02 0 FRP - 2.95 gpm 4.40E+01 2.22E+01 3.72E+04 SUM 4.79E+01 2.42E+01 4.07E+04 Criterion 2.50E+04 2.50E+04 3.00E+05 l AC961001.PM5 l

~= _ _ __ ._ .

! RTL: n/2 Fum: RE1.103-3 GC2 NA ERS-SFL-96-010 7A@ Opsswme Lis. fits..JPhysics Department page 16 Postulated LPZ Dose (0-8 hr)

MSLB - Pre-incident lodine Spike l

EDE Skin DE Thyroid CDE miem mrem mrem ASA 2.97E-04 1.62E-04 2.73E-01 l lLI 7.89E-03 4.42E-03 1.02E+01 l FLI 1.05E-01 5.37E-02 1.03E+02 ITP 8.52E-02 4.14E-02 6.95E+01 ITN 5.90E-03 9.45E 03 0 f

FRP - 2.95 apm 6.29E+00 3.48E+00 7.00E+03 SUM 6.49E+00 3.59E400 7.18E+03 l Criterion 2.50E+04 2.50E+04 3.00E+05 l

l Postulated CR Dose (0-30d)

MSLB Pre-incident todine Spike l

EDE Skin DE Thyrold CDE miem mrem mrem ASA 2.76E-05 3.23E-04 6.43E-01 l lLI 1.22E-04 1.37E-03 3.21 E+00 FLI 9.78E-03 1.07E-01 2.38E+02 ITP 3.73E-03 3.90E-02 7.73E+01 ITN 3.79E-04 1.48E-02 0 FRP - 2.95 gpm 8.47E-02 1.06E-00 1.80E+03 ,

SUM 9.87E-02 1.22E+00 2.12E+03 !

Criterion 5.00E+03 5.00E+03 3.00E+04 CONCLUSION l

The analysis documented herein has established that the maximum primary-to-secondary leak rate i that could be tolerated during a main steam line break outside of CNMT is 2.95 gpm.

This value differs from that determined for Unit 1 in that: (1) differences in the control room yjQ for both uni +s made the Unit 1 control room dose controlling. A more restrictive EAB yjQ at Unit 2 made j t the offsite cases more limiting.

l REFERENCES

1. DLC, Prooosed Ooeratina Licensing Change Reauest No. 229. did 12/7/95 l 2. USNRC, Voltage-Based Reoair Criteria for Westinghouse Steam Generator Tubes Affected by l Outside Diameter Stress Corrosion Cracking. Generic Letter 95-05

3. Westinghouse, Beaver Valley Power Station-1 Steam Generator Tube Plugging Criteria for Indications at Tube Sucoort Plates. WCAP-14122, dtd 7/94

4. DLC, Safety Analvsis of the Common Control Room Doses from A Main Steam Line Break Outside of CNMT at U1 with increased Primarv-to-Secondarv Leakage. ERS-SFL-95-008

5. USRNC, Standard Review Plan for the Review of Safety Analysis Reoorts for Nuclear Power Plants. NUREG-0800 l

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Duquesm @ ERS-SFL-96-010 Page 17 Health Physics Der artme.M

6. SWEC, FSAR see 15.1.5 Main Steam Line Break Accident with Preaccident or Concurrent lodine Soikina (no Failed Fuel) Releases and Offsite Doses.12241-UR(B)-354 ;

7. DLC, Uodated Final Safety Analvsis Reoort Unit 2.

8. SWEC, Control Room Habitability Due to Desian Basis Accident (exceot LOCA) at BVPS-2.

12241-UR(B)-445,1987 9 SWEC, FSAR Section 15.6.5 - LOCA Releases and Doses - Site and Control Rp_91n.

12241-UR(B)-190,1987 10 SWEC, Doses to the Combined Control Room due to LOCA at BVPS-1.12241-UR(B)-450,1987

11. SWEC, Combined BV1-BV2 Control Room Habitability Due to Design Basis Accidents (exceot LOCA) at BV1.12241-UR(B)-456,1987

12. DLC, Uodated Final Safety Analvsis Reoort Unit 1.

13. DLC, Unit 2 FHA Doses at EAB. LPZ. and Common Control Room. ERS-SFL-89-019

14. DLC, Safety Analvsis of the Dose Conseauences of a Locked Rotor Accident at BVPS-1. ERS-SFL-89-021

15. DLC, BVPS Common CR Rad Habitability Durina a DBA SGTR atU2 (based on WCAP-12738.

ERS-SFL 90-030

16. DLC, Assessment of the Doses in the U2 CR Due to LRA at U2 - 18% F.F.. ERS MPD-91-035

17. DLC, Safety Analvsis of the Dose Conseauences of a FHA at BVPS-CR. ERS-SFL-92-025

18. DLC, Combined Control Room Doses due to SGTR at Unit 1. ERS-SFL-92-033 Analvsis of FHA in RBC at Unit 1. ERS-SFL-92-034 19 DLC, Analvsis of FHA in RBC at Unit 1. ERS-SFL-92-034

20. DLC, Combined Control Room Doses fom DBAs at Unit 1. ERS-SFL-93-005,1993

21. DLC, TRAILS: Transoort of Radioactive Material in Linear Systems. ERS-SFL-89-020, Revision 0;1989

22. DiNunno, J.J., etal, Calculation of Distance Factors for Power and Test Reactor Sites. USAEC TID-14844,1962

23. USNRC, Assumotions Used for Evaluating the Potential Radiological Consecuences of a Loss of Coolant Accident for Pressurized Water Reactors. Regulatory Guide 1.4, Revision 2; 1974

24. USNRC, Assumotions Used for Evaluating the Potential Radiological Consecuences of a Fuel Handlina Accident in the Fuel Handling and Storaae Facility for Boilina and Pressurized Water Reactors. Regulatory Guide 1.25, Revision 0; 1972

25. DLC, Beaver Vallev Power Station Radionuclide Database and RADFILE. ERS-SFL-84-004, !

Revision 0; 1984 j

26. Murphy, KG. and Campe, K.W., Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19. published in proceedings of 13th AEC Air Cleaning Conference

27. DLC, Combined Control Room Doses Due to DBA's at Unit 2 with Delaved Isolation. '

ERS-SFL-89-007, Revision 1; 1989

28. DLC, Dose Calculation Methodology in DBA Analvses. Radiological Engineering Administrative Procedure 1.106.

1 AC961o01.PMS

R" : n/a Form: RE 1.103-3 942 N4Druswane Ah HeaEPhysicsDepartment

@ ERS-SFL-96-010 page 18 i

29. USNRC, Criterlon 19. Title 10 Code of Federal Regulations Part 50, Appendix A

30. SWEC, BV2 Tech Soec Primary Coolant and Secondarv Side Concentrations - Usina TID 14844 lodine Dose Conversion Factors.12241-UR(B) 233, Revision 1 31 Westinghouse ltr DMW-D-2880 dtd 5/28/82 H.Judkis to P. RaySircar (see 12241-UR(B)-354)

ATTACHMENTS

1. Main Steam Line Break Model

2. Control Room Dose Rate Printouts

3. Control Room Dose Rate vs Time

4. Offsite and Control Room Dose Printouts

5. Release Activities

5. Appendix 1, Control Room Model I

AC961001.PM5

RTL: n/3 Form RE 1.103-3 Mr2 Attachment 1 gW4Duquesne 7g Lkjit ERS-SFL-96-010 4 HeanhPhysicsDepartment pa9e {g l

0-8 hrs Main Steam Line Break n

0-4 hrs; / I spike r 1 4-8 hrs; FRP i spike /5 FRC,lTC

- _ FRC Faulted, Rupture Flow, OUgYs \ Pre-incident Faulted, Rupture Flow, Co-incident I

>> N i

/ l O-8 hrs RCS 4.2E5 lbm

\ //

ITP ITC Intact, T/S, Pre-incident MC950802.DS4 s Intact, T/S, Co-incident j

RTL: n/a Form RE 1.103-3 f42 Attachm:nt 1 g@gDam @ ERS-SFL-96-010 a

v g Health Physics Department page: 2Q N ,

/ !

\

Main Steam Line Break o.a n,,

l l

l l b N # l I

ITN !

Intact, T/S, Noble Gases ;

_ _ 1 RCS _

4.2E5 lbm i

MC950802.DS4 I

RTL: nh Fomi RE 1.103-3 9S2 Attachm:nt 1 M Vg,, D n m @ ERS-SFL-96-010 a

v g HealthPhysicsDerartment page: 21 Main Steam Line Break o-2 hrs 2-8 hrs 8

\ //

1 ILI

- - Intact, Liquid Phase, Initial i

i 1-second 0-0.5 hrs

, ~

\ /// \ /

ASA - -

FLI All, Steam Phase, All Faufted, Liquid Phase, initial MC950802.DS4

ERS-SFL-96-010 Att chm:nt 1 Pcgs 22 l

l Intentionally Blank l

(Provided for copying double-sided) l l

l l

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l

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose rate for 7 gpat [TC961036.DAT]

COMP: not used COMP: faulted S/G COMP: Control Roost VOLUME: 1.730E+05 Cu.Ft.

____ -- -----==_____ _ _ _ _ _ _ _ - _ _

INITIAL: 0.000E+00 Kr-83m 2.160E+07 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 1.050E+08 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 5.560E+08 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 6.020E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.600E+08 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 5.060E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Ze-131m 5.410E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.550E+08 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.320E+09 Xe-133 0.000E+00 Xe-133

0.000E+00 Xe-135m 5.460E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 1.610E+08 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 8.190E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 3.380E+07 Xe-138 0.000E+00 Xe-138

0.000E+00 I-131 1.260E+08 I-131 0.000E+00 I-131 0.000E+00 I-132 4.390E+07 I-132 0.000E+00 I-132 0.000E+00 I-133 1.970E+08 I-133 0.000E+00 I-133 0.000E+00 I-134 2.750E+07 I-134 0.000E+00 I-134 0.000E+00 I-135 1.060E+0B I-135 0.000E+00 I-135 ACT MULT (to uC1) : 1.000E+00 1.000E+00 1.000E+00

_ =_ _------------------------------ ____-- ------------------------

PRODUCTION,uci/s: 0.000E+00 I-131 1.360E+06 I-131 INTAKE: 1.000E+01 CEM 0.000E+00 I-132 2.520E+06 I-132 0.000E+00 I-133 3.080E+06 I-133 0.000E+00 I-134 3.680E+06 I-134 0.000E+00 I-135 2.810E+06 I-135 t

ERS-SFL-96-010 CR Dose Rate FRC / FRP 7 gpm cases Attachment 2 Page 23

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TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose rate for 7 gpa [TC961036.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

PHOTON-SUBMG BETA-SUBMG THYROID-INHAL PHOTON-SUBMG BETA-SUBMG THYROID-INHAL !

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ERS-SFL-96-010 CR Dose Rate FRC / FRP 7 gpm cases Attachment 2 Page 25

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 FRP Case for dose rate 7 gpea [TC961037.DAT]

COMP: not used COMP: faulted S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

= - . . - =_

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TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 IRP Case for dose rate 7 gym [TC961037.DAT] *

ENYIRONMENT--------- -------CONTROL ROOM-------

PHOTotf-SUBMG BETA-SUBMG TNYROID-INHAL PHOTON-SUBMG BETA-SUBMG THYROID-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE t arem aren/hr aren aren/hr urem arem/hr arem aren/hr arem arem/hr area aren/hr ALL NUCLIDES :

0.0167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.17E-05 2.60E-03 1.48E-04 1.77E-02 3.27E-01 3.92E+01 l 0.0833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.12E-04 1.27E-02 3.50E-03 8.70E-02 7.81E+00 1.95E+02 0.1667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.57E-03 2.48E-02 1.08E-02 1.71E-01 2.42E+01 3.86E+02 i 0.2500 h 0.00E+00 0.00E+0G 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.55E-03 3.63E-02 1.7 6E-02 2.51E-01 4.00E+01 5.74E+02 '

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ERS-SFL-96-010 CR Dose Rate FRC / FRP 7 gpm cases Attachment 2 Page ?O

MSLB C.R. Dose Rate vs Time,7 gpm P-to-S Based on Faulted SG Break Flow (FRC, FRP) 1.2 Process Safety Limit = 1 mR/hr

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ERS-SFL-96-010 Attachmsnt 3 Paga 30 Intentionaily Blank (Provided for copying double-sided)

TRAILS -- Transport of Radioactive Material in Linear systems, v2.0 ASA Case for EAB dose [TC961022.DAT]

COMP: not used COMP: all S/Gs COMP: Control Roost VOLUME: 1.730E+05 Cu.Ft.

- - - . --- . - - - ====--___ - - - - - - -

-- -=-- - - -

INITIAL: 0.000E+00 Kr-83m 1.920E+01 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 9.340E+01 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 4.930E+02 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 5.360E+01 Kr-87 0.000E+00 Kr-87 0.000Et00 Kr-88 1.430E+02 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 4.490E+00 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 4.810E+00 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.380E+02 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.170E+03 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 4.850E+01 Xe-135m 0.000E+00 Xe-135m 0.000E400 Xe-135 1.430E+02 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 7.290E+00 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 3.010E+01 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 2.710E+03 I-131 0.000E+00 I-131 0.000E+00 I-132 8.020E+02 I-132 0.000E+00 I-132 0.000E+00 I-133 3.890E+03 I-133 0.000E+00 I-133 0.000E+00 I-134 1.790E+01 I-134- 0.000E+00 I-134 0.000E+00 I-135 1.740E+03 I-135 0.000E+00 I-135 ACT MULT (to uci) : 1.000E+00 3.000E+00 1.000E+00

__ ..... --. =--------.-- -= __

-- ==-----------------------------__- =_ _

ERS-SFL-96-010 ASA Case for EAB Dose Attcahment 4 Page 31

i r

l TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 ASA Case for EAB dose [TC961022.DAT]

, = _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = = _ _ - - -

=_- - -----

REMOVAL: 0.000E+00 1/sec 1.382E+01 1/sec 1.000E+01 cfm NUC Grp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL ER: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 '

NUC Gzp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

_ _ _ _ . . - - - - - = - - . -- ___ . - _ _ _ _ _ - ---

- - - ==== _ _ _ . . _ _ _ _ _ _ _

MULTIPLIERS >

STEP TIME XPR XREN XRF XPR XREM XRF XPR XREM XRF 1 6.000E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 70.0 70.0 1.00 CONTROL ROOM -- ---- ENVIRONMENT ---

X/Q Breathing occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 MULTIPLIERS >

ETEP TIME,s 1 6.000E+01 2.72 1.00 1.00 1.44 1.00 2 1.800E+03 2.72 1.00 1.00 1.44 1.00 3 5.400E+03 2.72 1.00 1.00 1.44 1.00 4 7.200E+03 2.72 1.00 1.00 1.44 1.00 ERS-SFL-96-010 ASA Case for EAB Dose Attcahment 4 Page 32

{

i l TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 l ASA Case for EAB doce [TC961022.DAT]

j not used all S/Gs AVERAGE ---- -

CONTROL ROOM- -

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD l LTEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 5.760E+01 0.000E+00 '

Kr-03m TOTALS 0.000E+00 4.168E+00 5.760E+01 0.000E+00 Kr-85m INITIAL 0.000E+00 2.802E+02 0.000E+00 Kr-85m TOTALS 0.000E+00 2.027E+01 2.802E+02 0.000E+00 Kr-C5 INITIAL 0.000E+00 1.479E+03 0.000E+00-Kr-85 TOTALS 0.000E+00 1.070E+02 1.479E+03 0.000E+00 Kr-87 INITIAL 0.000E+00 1.608E+02 0.000E+00 Kr-87 TOTALS 0.000E+00 1.164E+01 1.608E+02 0.000E+00 Kr-88 INITIAL 0.000E+00 4.290E+02 0.000E+00 Kr-88 TOTALS 0.000E+00 3.104E+01 4.290E+02 0.000E+00 Kr-89 INITIAL 0.000E+00 1.347E+01 0.000E+00 Kr-89 TOTALS 0.000E+00 9.744E-01 1.347E+01 0.000E+00 X2-131m INITIAL 0.000E+00 1.443E+01 0.000E+00 Xe-131m TOTALS 0.000E+00 1.044E+00 1.443E+01 0.000E+00 Xe-133m INITIAL 0.000E+00 4.140E+02 0.000E+00 X2-133m TOTALS 0.000E+00 2.996E+01 4.140E+02 0.000E+00 Xa-133 INITIAL 0.000E+00 3.510E+03 0.000E+00 Xe-133 TOTALS 0.000E+00 2.540E+02 3.510E+03 0.000E+00 Xe-135m INITIAL 0.000E+00 1.455E+02 0.000E+00 Xe-135m TOTALS 0.000E+00 1.053E+01 1.455E+02 0.000E+00 Ka-135 INITIAL 0.000E+00 4.290E+02 0.000E+00 Xa-135 TOTALS 0.000E+00 3.104E+01 4.290E+02 0.000E+00 X9-137 INITIAL 0.000E+00 2.187E+01 0.000E+00 Xe-137 TOTALS 0.000E+00 1.582E+00 2.187E+01 0.OCOE+00 Za-138 INITIAL 0.000E+00 9.030E+01 0.000E+00 Xe-138 TOTALS 0.000E+00 6.534E+00 9.029E+01 0.000E+00 I-131 INITIAL 0.000E+00 8.130E+03 0.000E+00 I-131 TOTALS 0.000E+00 5.883E+02 8.130E+03 0.000E+00 ERS-SFL-96-010 ASA Case for EAB Dose Attcahment 4 Page 3 3

l I-132 INITIAL 0.000E+00 2.406E+03 0.000E+00 I-132 TOTALS 0.000E+00 1.741E+02 2.406E+03 0.000E+00 t

I-133 INITIAL 0.000E+00 1.167E+04 0.000E+00 I-133 TOTALS 0.000E+00 B.444E+02 1.167E+04 0.000E+00 I-134 INITIAL O.000E+00 5.370E+01 0.000E+00 I-134 TOTALS 0.000E+00 3.886E+00 5.370E+01 0.000E+00 I-135 INITIAL 0.000E+00 5.220E+03 0.000E+00 r I-135 TOTALS 0.000E+00 3.777E+02 5.220E+03 0.000E+00 i

i ERS-SFL-96-010 ASA Case for EAB Dose Attcahment 4 Page 3 4

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ASA Case for EAB dose [TC961022.DAT]

ENYIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE. DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem aren/hr arem arem/hr arem aren/hr arem aren/hr arem aren/hr arem aresa/hr Kr-83m TOTALS 1.23E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m TOTALS 1.04E-05 2.06E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 TOTALS 7.57E-07 1.06E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 TOTALS 3.28E-05 7.78E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 TOTALS 2.21E-04 4.87E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 TOTALS 6.25E-06 6.79E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

XO-131m TOTALS 2.82E-08 3.13E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m TOTALS 2.82E-06 1.87E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 TOTALS 2.82E-05 5.34E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XQ-135m TOTALS 1.43E-05 4.53E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00

, Xe-135 TOTALS 2.45E-05 4.00E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 TOTALS 9.53E-07 1.44E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 .

TOTALS 2.58E-05 1.92E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 TOTALS 7.09E-04 3.74E-04 4.39E+00 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 ASA Case for EAB Dose Attcahment 4 Page 3 5

__ _ _ _ _ . _ _ _ _ _ - _ . . . - - - _ ~ _ - - . .- . . . - - _ _ .

1 i

I-132' TOTALS 1.31E-03 3.87E-04 7.74E-03 0.00E+00 0.00E+00 0.00E+00 I-133 TOTALS 1.63E-03 1.52E-03 1.05E+00 0.00E+00 0.00E+00 0.00E+00 I-134 :

TOTALS 3.37E-05 1.11E-05 2.87E-05 0.00E+00 0.00E+00 0.00E+00 TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 ASA Case for EAB dose [TC961022.DAT] l

ENYIRONMENT--------- -------CONTROL ROOM------- 1 External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL ,

DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE '

arem arem/hr arena mrem /hr mresa nresa/hr arena arem/hr arem aren/hr arem arem/hr I-135 TOTALS 1.99E-03 6.01E-04 8.16E-02 0.00E+00 0.00E+00 0.00E+00 ,

t ALL NUCLIDES l 0.0167 h 6.04E-03 3.62E-01 3.30E-03 1.98E-01 5.53E+00 3.32E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i TOTALS 6.04E-03 3.30E-03 5.53E+00 0.00E+00 0.00E+00 0.00E+00 t

t l

t 1

ERS-SFL-96-010 ASA Case for EAB Dose Attcahment 4 Page 3G

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ILI Case for EAB dose [TC961023.DAT]

COMP: not used COMP: intact S/Gs COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

INITIAL: 0.000E+00 I-131 3.090E+06 I-131 uci 0.000E+00 I-131 0.000E+00 I-132 9.140E+05 I-132 0.000E+00 I-132 0.000E+00 I-133 4.430E+06 I-133 0.000E+00 I-133 0.000E+00 I-134 2.040E+04 I-134 0.000E+00 I-134 0.000E+00 I-135 1.980E+06 I-135 0.000E+00 I-135 ACT MULT (to uci) : 1.000E+00 1.000E+00 1.000E+00

_-___ .- .... _ _ - - .--- .....------. _=- ----- _. --

TRAILS -- Transport of Radioactive Material in Linear Systents, v2.0 ILI Case for EAB dose [TC961023.DAT]

--_ ..-- --- _ _ _ _ - - - _ _ - _ - _ - - - - - - - - - - - - = = - - - _ - - _ _ _ _ _ _ - - - - - -

REMOVAL: 0.000E+00 1/sec 5.130E-06 1/sec 1.000E+01 cfm NUC Grp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

__ - ------------------------- ==------- _ ----------...-----------. .==-----

MULTIPLIERS ====>

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00

===-

CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 MULTIPLIERS - >

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 1.44 1.00 2 5.400E+03 2.72 1.00 1.00 1.44 1.00 3 7.200E+03 2.72 1.00 1.00 1.44 1.00 ERS-SFL-96-010 ILI Case for EAB Dose Attcahment 4 Page 3 7

TRAILS -- Transport of Radioactive Material in Linear systems, v2.0 ILI Case for EAB dose [TC961023.DAT]

not used intact S/Gs AVERAGE - - - -

CONTROL ROOM --

CURRENT INTEGRD CURRENT INTEGRD BRTRASED RELEASE CUPRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I-131 INITIAL 0.000E+00 3.090E+06 0.000E+00 I-131 TOTALS 0.000E+00 2.176E+10 1.117E+05 0.000E+00 I-132 INITIAL 0.000E+00 9.140E+05 0.000E+00 I-132 TOTALS 0.000E+00 4.861E+09 2.494E+04 0.000E+00 I-133 INITIAL 0.000E+00 4.430E+06 0.000E+00 I-133 TOTALS 0.000E+00 3.030E+10 1.554E+05 0.000EF00 I-134 INITIAL 0.000E+00 2.040E+04 0.000E+00 I-134 TOTALS 0.000E+00 7.277E+07 3.733E+02 0.000E+00 I-135 INITIAL 0.000E+00 1.980E+06 0.000E+00 I-135 TOTALS 0.000E+00 1.263E+10 6.481E+04 0.000E+00 ALL NUCLIDES 0.000E+00 8.984E+06 0.000E+00 0.000E+00 6 STEP 3

'1 RAILS -- Transport of Radioactive Material in Linear Systems, v2.0 I7cI Case for EAB dose [TC961023.DAT]

ENVIRONMENT------- -

CONTROL ROOM-------

E: sternal EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem mren/hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem arem/hr mrem mrem /hr I-131 TOTALS 9.74E-03 5.14E-03 6.03E+01 0.00E+00 0.00E+00 0.00E+00 I-132 TOTALS 1.36E-02 4.01E-03 8.03E-02 0.00E+00 0.00E+00 0.00E+00 I-133 TOTALS 2.18E-02 2.02E-02 1.40E+01 0.00E+00 0.00E+00 0.00E+00 I-134 TOTALS 2.34E-04 7.71E-05 2.00E-04 0.00E+00 0.00E+00 0.00E+00 I-135 TOTALS 2.47E-02 7.47E-03 1.01E+00 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 ILI Case for EAB Dose Attcahment 4 Page 38

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ILI Case for EAB dose [TC961023.DAT]

not used intact.S/Gs AVERAGE - - - - - - - - - -

-CCNTROL ROOM CURRENT INTEGRD CUR *AENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec uCL uCi-sec uCi uCi/sec uCi uti/cc uCi-sec ALL NUCLIDES 0.5000 h 1.92E-02 3.84E-02 9.88E-03 1.98E-32 1.92E+01 3.85E+01 0.00E+00 0.00E+00 0.00E+00 0.00E'00 0.00E+00 0.00E+00 1.5000 h 3.49E-02 3.49E-02 1.84E-02 1.84E-92 3.77E+01 3.77E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.59E-02 3.18E-02 8.60E-03 1.72E-02 1.84E+01 3.68E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 7.00E-02 3.69E-02 7.53E+01 0.00E+00 0.00E+00 0.00E+00 l

ERS-SFL-96-010 ILI Case for EAB Dose Attcahment 4 Page 3 9

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FLI Case for EAB dose [TC961024.DAT]

COMP: not used COMP: faulted S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

_____- - - - - - ___ ___=--- ----------

INITIAL: 0.000E+00 I-131 3.090E+06 I-131 uci 0.000E+00 I-131 ;

0.000E+00 I-132 9.140E+05 I-132 0.000E+00 I-132 l 0.000E+00 I-133 4.430E+06 I-133 0.000E+00 I-133 0.000E+00 I-134 2.040E+04 I-134 0.000E+00 I-134 0.000E+00 I-135 1.980E+06 I-135 0.000E+00 I-135 >

ACT MULT (to uci) : 1.000E+00 1.000E+00 1.000E+00

= - - - = - -___________ _ --- _ _ - - - - _ - - - . _ - - = - - - - - = _ _ = ==-

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FLI Case for EAB dose [TC961024.DAT]

=-- - _ = _ _ - = _ --- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ _ _ _

REMOVAL: 0.000E+00 1/sec 7.675E-03 1/see 1.000E+01 cfm NUC Grp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE RELUCT: 9.360E-01 5 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 ,

________________ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - = - - - - _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

MULTIPLIERS->

I STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 ;

-- CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathing ,

s/M3 M3/s s/M3 M3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 i HULTIPLIERS->

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 1.44 1.00 2 5.400E+03 2.72 1.00 1.00 1.44 1.00 3 7.200E+03 2.72 1.00 1.00 1.44 1.00 ERS-SFL-96-010 FLI Case for EAB Dose Attcahment 4 Page 4 0

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FLI Case for EAB dose [TC961024.DAT) not used faulted S/G AVERAGE = ---

-CONTROL ROOM-- -

CURRENT INTEGRD CURRENT INTEGRD RELEASED RKY.R3LSE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uC1/cc uCi-sec I-131 INITIAL 0.000E+00 3.090E+06 0.000E+00 I-131 TOTALS 0.000E+00 4.026E+08 3.090E+06 0.000E+00 r

I-132 INITIAL 0.000E+00 9.140E+05 0.000E+00 I-132 TOTALS 0.000E+00 1.178E+08 9.041E+05 0.000E+00 I-133 INITIAL 0.000E+00 4.430E+06 0.000E+00 I-133 TOTALS 0.000E+00 5.765E+08 4.425E+06 0.000E+00 I-134 INITIAL 0.000E+00 2.04GE+04 0.000E+00 I-134 TOTALS 0.000E+00 2.584E+06 . "~~iE+04 0.000E+00 I-135 INITIAL 0.000E+00 1.980E+06 0.000E+00 !

I-135 TOTALS 0.000E+00 2.570E+C8 1.973E+06 0.000E+00 ALL NUCLIDES 0.000E+00 9.341E-18 0.000E+00 0.000E+00 0 ETEP 3 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FLI Case for EAB dose [TC961024.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE- DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE atrem arem/hr mrem arem/hr arem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr I-131 TOTALS 2.69E-01 1.42E-01 1.67E+03 0.00E+00 0.00E+00 0.00E+00 I-132 TOTALS 4.92E-01 1.45E-01 2.91E+00 0.00E+00 0.00E+00 0.00E+00 I-133 TOTALS 6.20E-01 5.75E-01 3.98E+02 0.00E+00 0.00E+00 0.00E+00 I-134 TOTALS 1.25E-02 4.09E-03 1.06E-02 0.00E+00 0.00E+00 0.00E+00 I-135 TOTALS 7.51E-01 2.27E-01 3.09E+01 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 FLI Case for EAB Dose Attcahment 4 Page d 1

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FLI Case for EAB dose [TC961024.DAT]

not used faulted S/G AVERAGE - - - - --

-CONTROL ROOM CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec ALL NUCLIDES 0.5000 h 2.14E+00 4.29E+00 1.09E+00 2.19E+00 2.10E+03 4.20E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 2.02E-06 2.02E-06 1.05E-06 1.05E-06 2.09E-03 2.09E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.82E-18 3.64E-18 9.78E-19 1.96E-18 2.07E-15 4.14E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 2.14E+00 1.09E+00 2.10E+03 0.00E+00 0.00E+00 0.00E+00 i

ERS-SFL-96-010 FLI Case for EAB Dose Attcahment 4 Page /j 2

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITC Case for EAB dose [TC961025.DAT]

COMP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

-- -_____===

INITIAL: 0.000E+00 I-131 1.260E+08 I-131 uci 0.000E+00 I-131 0.000E+00 I-132 4.390E+07 I-132 0.000E+00 I-132 0.000E+00 I-133 1.970E+08 I-133 0.000E+00 I-133 0.000E+00 I-134 2.750E+07 I-134 0.000E+00 I-134 0.000E+00 I-135 1.060E+08 I-135 0.000E+00 I-135 ACT MULT (to uC1) : 1.000E+00 1.000E+00 1.000E+00

- ----________--- ______________=- -------

PRODUCTION,uci/s: 0.000E+00 I-131 1.360E+06 I-131 INTAKE: 1.000E+01 Cnf 0.000E+00 I-132 2.520E+06 I-132 0.000E+00 I-133 3.080E+06 I-133 0.000E+00 I-134 3.680E+06 I-134 0.000E+00 I-135 2.810E+06 I-135 ERS-SFL-96-010 ITC Case for EAB Dose Attcahment 4 Page d 3 l

TRAILS -- Transport of Radioactive Material in Linear systems, v2.0 ITC Case for EAB dose [TC961025.DAT]

- .-- -_ ==_ _ _ - - - - _

REMOVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfm NUC Grp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01

- NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

==- . - - _ = - - _ _ _ - - - = = = - - _ _=- -- _____________.._______________ =---------

MULTIPLIERS->

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.000E-02 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.000E-02 0.000E+00 70.0 70.0 1.00 CONTROL ROOM --------- ---- ENVIRONMENT ---

X/Q Breathing occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 MULTIPLIERS->

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 1.44 1.00 2 3.600E+03 2.72 1.00 1.00 1.44 1.00 3 S.400E+03 2.72 1.00 1.00 1.44 1.00 4 7.200E+03 2.72 1.00 1.00 1.44 1.00

?

4 ERS-SFL-96-010 ITC Case for EAB Dose Attcabment 4 Page gj d

i TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITC Case for EAB dose [TC961025.DAT]

not used intact S/G AVERAGE -

-CONTROL ROOH-- - - - -

CURRENT INTEGRD CURRENT INTEGRD PRTJt4 SED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I-131 INITIAL 0.000E+00 1.260E+08 0.000E+00 I-131 TOTALS 0.000E+00 3.607E+13 6.570E+05 0.000E+00 I-132 INITIAL 0.000E+00 4.390E+07 0.000E+00 I-132 TOTALS 0.0GOE+00 5.419E+13 1.058E+06 0.000E+00 I-133 INITIAL 0.000E+00 1.970E+08 0.000E+00 t I-133 TOTALS 0.000E+00 7.945E+13 1.450E+06 0.000E+00 I-134 INITIAL 0.000E+00 2.750E+07 0.000E+00 l I-134 TOTALS 0.000E+00 6.014E+13 1.319E+06 0.000E+00 I-135 INITIAL 0.000E+00 1.060E+08 0.000E+00 I-135 TOTALS 0.000E+00 6.868E+13 1. 273E+ 06 0.000E+00 ALL NUCLIDES 0.000E+00 7.682E+10 0.000E+00 0.000E+00 ,

8 STEP 4 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITC Case for EAB dose [TC961025.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE TRY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE PATE mrem mren/hr mrem aren/hr mrem arem/hr arem arem/hr mrem mren/hr mrem mrem /hr [

I-131 TOTALS 5.73E-02 3.02E-02 3.55E+02 0.00E+00 0.00E+00 0.00E+00 j i

I-132 TOTALS 5.76E-01 1.70E-01 3.40E+00 0.00E+00 0.00E+00 0.00E+00 j I-133 TOTALS 2.03E-01 1.89E-01 1.30E+02 0.00E+00 0.00E+00 0.00E+00 I-134 TOTALS 8.28E-01 2.72E-01 7.05E-01 0.00E+00 0.00E+00 0.00E+00 I-135 TOTALS 4.85E-01 1.47E-01 1.99E+01 0.00E+00 0.00E+00 0.00E+00 '

ERS-SFL-96-010 ITC Case for EAB Dose Attcahment 4 Page 4 5

TEN -- Transport of Radioactive Material in Linear Systeams, v2.0 ITC Case for EAB dose [TC961025.DAT)

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE TRY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem uren/hr nrem aren/hr arem mren/hr arem arem/hr arem aren/hr aren aren/hr ALL NUCLIDES 0.5000 h 5.66E-01 1.13E+00 2.12E-01 4.23E-01 1.29E+02 2.59E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 1.53E+00 3.06E+00 5.76E-01 1.15E+00 3.65E+02 7.30E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 2.33E-02 4.66E-02 8.86E-03 1.77E-02 5.99E+00 1.20E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 3.01E-02 6.01E-02 1.16E-02 2.31E-02 S.31E+00 1.66E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 2.15E+00 8.08E-01 5.09E+02 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 ITC Case for EAB Dose Attcahment 4 Page d 6

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for EAB dose (TC961026.DAT]

COMP: not used COMP: intact S/G COMP: Control Room YOLUME: 1.730E+05 Cu.Ft.

== _ _ _ - - _ . _ _ = = - - - _ _ - - - - _ _ _ _ =-- -.------------------

INITIAL: 0.000E+00 Kr-83m 2.160E+07 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 1.050E+0B Kr-85m 0.000E+00 Kr-85m i 0.000E+00 Kr-85 5.560E+08 Kr-85 0.000F+00 Kr-85 ,

0.000E+00 Kr-87 6.020E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.600E+08 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 5.060E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 5.410E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.550E+08 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.320E+09 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 5.460E+07 Xe-135m 0.000E+00 Xe-135m i 0.000E+00 Xe-135 1.610E+08 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 8.190E+06 Xe-137 0.000E+00 Xe-137 !

0.000E+00 Xe-138 3.380E+07 Xe-138 0.000E+00 Xe-138 ACT HULT (to uCi) : 1.000E+00 1.000E+00 1.000E+00

_=-----=____=_

_ _ - _ ----- ._ __----------------------------- j TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for EAB dose [TC961026.DAT]

--- .----==-- _ - - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = -

REMOVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfm NUC Grp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

. ==. __=------ == ==------------ __ _ ----------------- --

MULTIPLIERS - >

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00

= = -- CONTROL ROOM = -- - -

ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 MULTIPLIERS->

ETEP TIME,s 1 1.800E+03 2.72 1.00 1.00 1.44 1.00 2 3.600E+03 2.72 1.00 1.00 1.44 1.00 3 5.400E+03 2.72 1.00 1.00 1.44 1.00 4 7.200E+03 2.72 1.00 1.00 1.44 1.00 ERS-SFL-96-010 ITN Case for EAB Dose Attcahment 4 Page d 7

TRAILS -- Transport of Radioactive Mat.erial in Linear Systems, v2.0 ITN Case for EAB dose [TC961026.DAT]

not used intact S/G AVERAGE ----------CONTROL ROOM- = ==

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/see uci uci/cc uci-sec Kr-83m INITIAL 0.000E+00 2.160E+07 0.000E+00 Kr-83m TOTALS 0.000E+00 1.090E+11 7.522E+03 0.000E+00 Kr-85m INITIAL 0.000E+00 1.050E+08 0.000E+00 Kr-85m TOTALS 0.000E+00 6.501E+11 4.485E+04 0.000E+00 Kr-85 INITIAL 0.000E+00 5.560E+08 0.000E+00 Kr-85 TOTALS 0.000E+00 4.002E+12 2.761E+05 0.000E+00 Kr-87 INITIAL 0.000E+00 6.020E+07 0.000E+00 Kr-37 TOTALS 0.000E+00 2.639E+11 1.821E+04 0.000E+00 Kr-88 INITIAL 0.000E+00 1.600E+08 0.000E+00 Kr-C8 TOTALS 0.000E+00 9.113E+11 6.287E+04 0.000E+00 Kr-89 INITIAL 0.000E+00 5.060E+06 0.000E+00 Kr-89 TOTALS 0.000E+00 1.384E+09 9.549E+01 0.000E+00 Xe-131m INITIAL 0.000E+00 5.410E+06 0.000E+00 Xe-131m TOTALS 0.000E+00 3.885E+10 2.680E+03 0.000E+00 Xe-133m INIIAL 0.000E+00 1.550E+08 0.000E+00 Xa-133m TOTALS 0.000E+00 1.101E+12 7.597E+04 0.000E+00 Xe-133 INITIAL 0.000E+00 1.320E+09 0.000E+00 Xe-133 TOTALS 0.000E+00 9.450E+12 6.519E+05 0.000E+00 Xe-135m INITIAL 0.000E+00 5.460E+07 0.000E+00 X2-135m TOTALS 0.000E+00 7.227E+10 4.986E+03 0.000E+00 Xe-135 INITIAL 0.000E+00 1.610E+08 0.000E+00 Xa-135 TOTALS 0.000E+00 1.075E+12 7.417E+04 0.000E+00 Xa-137 INITIAL 0.000E+00 8.190E+06 0.000E+00 X2-137 TOTALS 0.000E+00 2.715E+09 1.873E+02 0.000E+00 Xe-138 INITIAL 0.000E+00 3.380E+07 0.000E+00 Xe-138 TOTALS 0.000E+00 4.122E+10 2.844E+03 0.000E+00 ALL NUCLIDES 0.000E+00 2.361E+09 0.000E+00 0.000E+00 6 STEP 4 ERS-SFL-96-010 ITN Case for EAB Dose Attcahment 4 Page fl,o,

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for EAB dose [ TOR 61026.DAT]

r

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem area /hr arem aress/hr mrem aren/hr arem arem/hr arem arem/hr arem arem/hr Kr-83m TOTALS 1.61E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Kr-85m TOTALS 1.67E-03 3.30E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85

TOTALS 1.41E-04 1.98E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 TOTALS 3.71E-03 8.81E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 TOTALS 3.24E-02 7.14E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 TOTALS 4.43E-05 4.81E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m TOTALS 5.24E-06 5.81E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m TOTALS 5.17E-04 3.43E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XO-133 TOTALS 5.24E-03 9.91E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XD-135m TOTALS 4.89E-04 1.55E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xo-135 TOTALS 4.24E-03 6.91E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xa-137 TOTALS 8.17E-06 1.24E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XD-138 TOTALS 8.13E-04 6.05E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96 ITN Case for EAB Dose Attcahment 4 Page g0

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TRAILS -- Transport cf Raditactive Material in Linear Sy,:tems, v2.0 31tc Case for dose for EAB 2.95 gpea [TC961017.DAT]

COMP: not used COMP: faulted S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

_ _ _ - - -- = -_ -- _ __ _ . _ _ _

INITIAL: 0.000E+00 Kr-83m 2.160E+07 Kr-83m uCi 0.000E+00 Kr-83m j 0.000E+00 Kr-85m 1.050E+08 Kr-85m 0.000E+00 Kr-85m J 0.000E+00 Kr-85 5.560E+08 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 6.020E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.600E+08 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 5.060E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 5.410E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.550E+08 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.320E+09 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 5.460E+07 Xe-135m 0.000E+00 Xe-135m i 0.000E+00 Xe-135 1.610E+08 Xe-135 0.000E+00 Xe-135 i 0.000E+00 Xe-137 8.190E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 3.380E+07 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 1.260E+08 I-131 0.000E+00 I-131 0.000E+00 I-132 4.390E+07 I-132 0.000E+00 I-132 0.000E+00 I-133 1.970E+08 I-133 0.000E+00 I-133 0.000E+00 I-134 2.750E+07 I-134 0.000E+00 I-134 0.000E+00 I-135 1.060E+08 I-135 0.000E+00-I-135 ACT MULT (to uCi) : 1.000E+00 1.000E+00 1.000E+00

______- - - _ - - _ - - - - - - - - - - - ----- -.=________ ___________=

PRODUCTION,uci/s: 0.000E+00 I-131 1.360E+06 I-131 INTAKE: 1.000E+01 CEM 0.000E+00 I-132 2.520E+06 I-132 0.000E+00 I-133 3.080E+06 I-133 l 0.000E+00 I-134 3.680E+06 I-134 j 0.000E+00 I-135 2.810E+06 I-135 l l

ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 51

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for EAB 2.95 gpm [TC961017.DAT]

_________________=- _- .______________________- - ----

REMOVAL: 0.000E+00 1/sec 9.769E-07 1/sec 1.000E+01 cfm NUC Grp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 MULTIPLIERS->

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 70.0 70.0 , 1.00

CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 MULTIPLIERS->

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 1.44 1.00 2 3.600E+03 2.72 1.00 1.00 1.44 1.00 3 S.400E+03 2.72 1.00 1.00 1.44 1.00 4 7.200E+03 2.72 1.00 1.00 1.44 1.00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 5 2

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ERC Case for dose for EAB 2.95 gpat [TC961017.DAT) i not used faulted S/G AVERAGE ==

-CONTROL ROOM-

, CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD LTEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc 1Ci-sec

Kr-83m INITIAL 0.000E+00 2.160E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.784E+07 3.539E+10 3.457E+04 1.921E+01 0.000E+00 0.000E+00 0.000E+00 l l 2 1.0000 h 0.000E+00 0.000E+00 1.474E+07 2.923E+10 2.856E+04 1.586E+01 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.217E+07 2.415E+10 2.359E+04 1.310E+01 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.006E+07 1.995E+10 1.948E+04 1.082E+01 0.000E+00 0.000E+00 0.000E+00 Kr-83m TOTALS 0.000E+00 1.087E+11 1.062E+05 0.000E+00 Kr-85m INITIAL 0.000E+00 1.050E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 9.701E+07 1.817E+11 1.775E+05 9.862E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 8.963E+07 1.679E+11 1.640E+05 9.112E+01 0.000E+00 0.000E+00 0.000E+00 ,

3 1.5000 h 0.000E+00 0.000E+00 8.281E+07 1.551E+11 1.515E+05 8.418E+01 0.000E+00 0.000E+00 0.000E+00 e l

4 2.0000 h 0.000E+00 0.000E+00 7.651E+07 1.433E+11 1.400E+05 7.778E+01 0.000E+00 0.000E+00 0.000E+00 Kr-85m TOTALS 0.000E+00 6.481E+11 6.331E+05 0.000E+00 !

Kr-85 INITIAL 0.000E+00 5.560E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.550E+08 9.999E+11 9.768E+05 5.427E+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 5.540E+08 9.982E+11 9.751E+05 5.417E+02 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 5.531E+08 9.964E+11 9.733E+05 5.407E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 5.521E+08 9.946E+11 9.716E+05 5.398E+02 0.000E+00 0.000E+00 0.000E+00 Kr-85 TOTALS 0.000E+00 3.989E+12 3.897E+06 0.000E+00 Kr-87 INITIAL 0.000E+00 6.020E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 4.57 6E+07 9.477E+10 9.258E+04 5.143E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 3.478E+07 7.203E+10 7.037E+04 3.909E+01 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 2.644E+07 5.475E+10 5.349E+04 2.972E+01 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 2.010E+07 4.162E+10 4.066E+04 2.259E+01 0.000E+00 0.000E+00 0.000E+00 Kr-87 TOTALS 0.000E+00 2.632E+11 2.571E+05 0.000E+00 i Kr-88 INITIAL 0.000E+00 1.600E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.414E+08 2.709E+11 2.646E+05 1.470E+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.249E+08 2.392E+11 2.338E+05 1.299E+02 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.104E+08 2.115E+11 2.066E+05 1.148E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 9.752E+07 1.869E+11 1.825E+05 1.014E+02 0.000E+00 0.000E+00 0.000E+00 Kr-88 TOTALS 0.000E+00 9.086E+11 8.875E+05 0.000E+00 Kr-89 INITIAL 0.000E+00 5.060E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.007E+03 1.382E+09 1.350E+03 7.499E-01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 9.703E+00 1.914E+06 1.86FE+00 1.038E-03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.344E-02 2.650E+03 2.589E-03 1.438E-06 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.861E-05 3.670E+00 3.585E-06 1.991E-09 0.000E+00 0.000E+00 0.000E+00 Kr-89 TOTALS 0.000E+00 1.384E+09 1.352E+03 0.000E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 5 3

TRAILS -- Transport of Radioactive Material in Linear SyPtems, v2.0 B C Case for dose for EAB 2.95 gpu [TC961017.DAT]

not used faulted S/G AVERAGE -----

CONTROL ROOM CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xe-131m INITIAL 0.000E+00 5.410E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.394E+06 9.724E+09 9.499E+03 5.277E+00 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 5.378E+06 9.695E+09 9.470E+03 5.261E+00 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 5.362E+06 9.666E+09 9.442E+03 5.246E+00 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 5.34 6E+06 9.637E+09 9.414E+03 5.230E+00 0.000E+00 0.000E+00 0.000E+00 Xw-131m TOTALS 0.000E+00 3.872E+10 3.782E+04 0.000E+00 Xa-133m INITIAL 0.000E+00 1.550E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.537E+08 2.778E+11 2.714E+05 1.50SE+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.524E+08 2.755E+11 2.692E+05 1.495E+02 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.512E+08 2.732E+11 2.669E+05 1.483E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.499E+08 2.710E+11 2.647E+05 1.471E+02 0.000E+00 0.000E+00 0.000E+00 Xa-133m TOTALS 0.000E+00 1.098E+12 1.072E+06 0.000E+00 Xa-133 INITIAL 0.000E+00 1.320E+09 0.000E+00 1 0.5000 h 0.000E+C0 0.000E+00 1.314E+09 2.371E+12 2.316E+06 1.287E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.308E+09 2.360E+12 2.305E+06 1.281E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.302E+09 2.349E+12 2.29.5E+06 1.275E+03 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.296E+09 2.339E+12 2.285E+06 1.269E+03 0.000E+00 0.000E+00 0.000E+00 Xa-133 TOTALS 0.000E+00 9.419E+12 9.201E+06 0.000E+00 Xa-135m INITIAL 0.000E+00 5.460E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.408E+07 5.381E+10 5.257E+04 2.920E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 3.629E+06 1.387E+10 1.355E+04 7.529E+00 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 9.355E+05 3.576E+09 3.494E+03 1.941E+00 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 2.412E+05 9.220E+08 9.007E+02 5.004E-01 0.000E+00 0.000E+00 0.000E+00 Xe-135m TOTALS 0.000E+00 7.218E+10 7.051E+04 0.000E+00 Xe-135 INITIAL 0.000E+00 1.610E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.547E+08 2.841E+11 2.775E+05 1.542E+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.487E+08 2.730E+11 2.667E+05 1.482E+02 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.429EtOS 2.624E+11 2.563E+05 1.424E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.373E+08 2.521E+11 2.463E+05 1.368E+02 0.000E+00 0.000E+00 0.000E+00 Xe-135 TOTALS 0.000E+00 1.072E+12 1.047E+06 0.000E+00 Xe-137 INITIAL 0.000E+00 8.190E+06 0.000E+00 1 0.5000 h 9.000E+00 0.000E+00 3.586E+04 2.702E+09 2.640E+03 1.467E+00 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.570E+02 1.183E+07 1.156E+01 6.421E-03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 6.874E-0*t 5.180E+04 5.061E-02 2.811E-05 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 3.010E rJ 2.268E+02 2.216E-04 1.231E-07 0.000E+00 0.000E+00 0.000E+00 Xe-137 TOTALS 0.000E+00 2.714E+09 2.652E+03 0.000E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 5 4

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for EAB 2.95 gpa [TC961017.DAT]

not used faulted S/G AVERAGE -- CONTROL ROOM- --- ---

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/see uCi uCi/cc uCi-sec Xe-138 INITIAL 0.000E+00 3.380E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.745E+06 3.183E+10 3.109E+04 1.727E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.775E+06 7.294E+09 7.125E+03 3.958E+00 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 4.067E+05 1.671E+09 1.633E+03 9.070E-01 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000F+00 0.000E+00 9.319E+04 3.830E+08 3.741E+02 2.078E-01 0.000E+00 0.000E+00 0.000E+00 Xa-138 TOTALS 0.000E+00 4.118E+10 4.023E+04 0.000E+00 I-131 INITIAL 0.000E+00 1.260E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 2.569E+09 2.427E+12 2.371E+06 1.317E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 5.004E+09 6.817E+12 6.659E+06 1.700E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 7.430E+09 1.119E+13 1.093E+07 6.074E+03 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 9.847E+09 1.555E+13 1.519E+07 8.439E+03 0.000E+00 0.000E+00 0.000E+00 I-131 TOTALS 0.000E+00 3.599E+13 3.515E+07 0.000E+00 I-132 INITIAL 0.000E+00 4.390E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 4.245E+09 3.956E+12 3.864E+06 2.141E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 7.852E+09 1.097E+13 1.072E+07 5.953E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.095E+10 1.699E+13 1.660E+07 9.221E+03 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.361E+10 2.216E+13 2.165E+07 1.203E+04 0.000E+00 0.000E+00 9.000E+00 I-132 TOTALS 0.000E+00 -5.408E+13 5.283E+07 0.000E+00 I-133 INITIAL 0.000E+00 1.970E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.687E+09 5.310E+12 5.188E+06 2.882E+03 0.000E+00 0.000E+00 0.C00E+00 2 1.0000 h 0.000E+00 0.000E+00 1.108E+10 1.510E+13 1.475E+07 8.196E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.00DE+00 0.000E+00 1.637E+10 2.471F+13 2.414E+07 1.341E+04 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 2.156E+10 3.415E+13 3.336E+07 1.853E+04 0.000E+00 0.000E+00 0.000E+00

.I-133 TOTALS 0.000E+00 7.928E+13 7.744E+07 0.000E+00 I-134 INITIAL 0.000E+00 2.750E+07 0.000E+00 ,

1 0.5000 h 0.000E+00 0.000E+00 5.485E+09 5.286E+12 5.164E+06 2.869E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 9.155E+09 1.339E+13 3.308E+07 7.269E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.162E+10 1.884E+13 1.841E+07 1.023E+04 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.328E+10 2.251E+13 2.199E+07 1.222E+04 0.000E+00 0.000E+00 0.000E+00 I-134 TOTALS 0.000E+00 6.003E+13 5.864E+07 0.000E+00 I-135 INITIAL 0.000E+00 1.060E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.024E+09 4.657E+12 4.549E+06 2.527E+03 0.000E+00 0.000E+00 0.000E+00 2 1,0000 h 0.000E+00 0.000E+00 9.682E+09 1.327E+13 1.297E+07 7.203E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.409E+10 2.144E+13 2.094E+07 1.163E+04 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.827E+10 2.917E+13 2.849E+07 1.583E+04 0.000E+00 0.000E+00 0.000E+0G I-135 TOTALS 0.000E+00 6.853E+13 6.695E+07 0.000E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 5 5

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TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for EAB 2.95 gpm [TC961017.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATr. DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr xt-138 0.5000 h 8.89E-03 1.78E-02 6.62E-03 1.32E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2.04E-03 4.08E-03 1.52E-03 3.03E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 4.67E-04 9.34E-04 3.47E-04 6.95E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.07E-04 2.14E-04 7.96E-05 1.59E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.CdE+00 TOTALS 1.15E-02 8.56E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 0.5000 h 2.07E-01 4.13E-01 1.09E-01 2.18E-01 1.28E+03 2.56E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00F+00 1.0000 h 5.81E-01 1.16E+00 3.06E-01 6.13E-01 3.59E+03 7.19E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 9.53E-01 1.91E+00 5.03E-01 1.01E+00 5.90E+03 1.18E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.32E+00 2.65E+00 6.99E-01 1.40E+00 8.20E+03 1.64E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.07E+00 1.62E+00 1.90E+04 0.00E+00 0.00E+00 0.00E+00 I-132 0.5000 h 2.10E+00 4.20E+00 6.21E-01 1.24E+00 1.24E+01 2.49E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 5.83E+00 1.17E+01 1.72E+00 3.45E+00 3.45E+01 6.90E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 9.03E+00 1.81E+01 2.67E+00 5.34E+00 5.34E+01 1.07E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.18E+01 2.36E+01 3.48E+00 6.96E+00 6.97E+01 1.39E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 2.87E+01 8.50E+00 1.70E+02 0.00E+00 0.00E+00 0.00E+00 I-133 0.5000 h 7.26E-01 1.45E+00 6.74E-01 1.35E+00 4.67E+02 9.33E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2.07E+00 4.13E+00 1.92E+00 3.84E+00 1.33E+03 2.65E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 1.5000 h 3.38E+00 6.76E+00 3.14E+00 6.28E+00 2.17E+03 4.34E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 4.67E+00 9.34E+00 4.34E+00 8.67E+00 3.00E+03 6.00E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.08E+01 1.01E+01 6.97E+03 0.00E+00 0.00E+00 0.00E+00 I-134 0.5000 h 3.24E+00 6.49E+00 1.07E+00 2.13E+00 2.76E+00 5.52E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 8.22E+00 1.64E+01 2.70E+00 5.40E+00 7.00E+00 1.40E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 1.16E+01 2.31E+01 3.80E+00 7.60E+00 9.84E+00 1.97E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.38E+01 2.76E+01 4.54E+00 9.08E+00 1.18E+01 2.35E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.68E+01 1.21E+01 3.14E+01 0.00E+00 0.00E+00 0.00E+00 I-135 0.5000 h 1.73E+00 3.46E+00 5.24E-01 1.05E+00 7.11E+01 1.42E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 4.94E+00 9.88E+00 1.49E+00 2.99E+00 2.03E+02 4.06E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 7.97E+00 1.59E+01 2.41E+00 4.82E+00 3.27E+02 6.55E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.09E+01 2.17E+01 3.28E+00 6.56E+00 4.46E+02 8.91E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 2.55E+01 7.71E+00 1.05E+03 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 5 8

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 Mtc Case for dose for EAB 2.95 gpm (TC961017.DAT]

---ENVIRONMENT- ------- -------C0NTROL ROOM--- ---

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CEE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE aren h@ arem aren/hr arem aren/hr arem aren/hr arem arenVhr arem aren/hr ALL NUCLIDES 0.5000 h 8.22E+00 1.64E+01 3.24E+00 6.47E+00 1.83E+03 3.66E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2.18E+01 4.36E+01 8.36E+00 1.67E+01 5.16E+03 1.03E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 3.31E+01 6.61E+01 1.27E+01 2.54E+01 8.46E+03 1.69E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 4.26E+01 8.51E+01 1.65E+01 3.31E+01 1.17E+04 2.35E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.06E+02 4.08E+01 2.72E+04 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 5 9

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TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITP Case for EAR dose [IC961027.DAT]

not used intact S/G AVERAGE ---

CONTROL ROOM - --

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I-131 INITIAL 0.000E+00 7.730E+09 0.000E+00 I-131 IOTALS 0.000E+00 5.545E+13 1.935E+06 0.000E+00 I-132 INITIAL 0.000E+00 2.700E+09 0.000E+00 I-132 TOTALS 0.000E+00 1.460E+13 5.832E+05 O.000E+00 I-133 INITIAL 0.000E+00 1.210E+10 0.000E+00 I-133 TOTALS 0.000E+00 8.426E+13 2.984E+06 0.000E+00 I-134 INITIAL 0.000E+00 1.690E&O9 0.000E+00 I-134 TOTALS 0.000E+00 6.111E+12 2.914E+05 0.000E+00 I-135 INITIAL 0.000E+00 6.490E+09 0.000E+00 I-135 TOTALS 0.000E+00 4.215E+13 1.544E+06 0.000E+00 ALL NUCLIDES 0.000E+00 2.608E+10 0.000E+00 0.000E+00 6 STEP 4 ERS-SFL-96-010 ITP Case for EAB Dose AttCahment 4 Page 61

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITP Case for EAB dose [TC961027.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE TNY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem aren/hr arem mress/hr arem arem/hr arem area /hr arem arem/hr arem aren/hr I-131 TOTALS 1.69E-01 8.90E-02 1.04E+03 0.00E+00 0.00E+00 0.00E+00 I-132 TOTALS 3.17E-01 9.38E-02 1.88E+00 0.00E+00 0.00E+00 0.00E+00 I-133 TOTALS 4.18E-01 3.88E-01 2.68E+02 0.00E+00 0.00E+00 0.00E+00 I-134 TOTALS 1.83E-01 6.01E-02 1.56E-01 0.00E+00 0.00E+00 0.00E+00 I-135 TOTALS 5.88E-01 1.78E-01 2.41E+01 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES 0.5000 h 8.69E-01 1.74E+00 4.14E-01 8.28E-01 6.65E+02 1.33E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 7.91E-01 1.58E+00 3.87E-01 7.75E-01 6.61E+02 1.32E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 7.29E-03 1.46E-02 3.66E-03 7.32E-03 6.57E+00 1.31E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 6.78E-03 1.36E-02 3.48E-03 6.96E-03 6.53E+00 1.31E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.67E+00 8.09E-01 1.34E+03 0.00E+00 0.00E+00 0.00E+00 i

ERS-SFL-96-010 ITP Case for EAB Dose Attcahment 4 Page 6 2

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ERP Case for 2.95 gpm EAB dose [Tc961019.DAT]

COMP: not used COMP: Faulted S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

INITIAL: 0.000E+00 Kr-83m 2.160E+07 Kr-83m uci 0.000E+00 Kr-83m 0.000E+00 Kr-85m 1.050E+08 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 5.560E+08 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 6.020E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.600E+08 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 5.060E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 5.410E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.55CE+08 Xe-133m 0.000E+00 Xe-133m D.000E+00 Xe-133 1.320E+0L Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 5.460E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 1.610E+08 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 8.190E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 3.380E+07 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 7.730E+09 I-131 0.000E+00 I-131 0.000E+00 I-132 2.700E+09 I-132 0.000E+00 I-132 0.000E+00 I-133 1.210E+10 I-133 0.000E+00 I-133 0.000E+00 I-134 1.690E+09 I-134 0.000E+00 I-134 0.000E+00 I-135 6.490E+09 I-135 0.000E+00 I-135 ACT MULT (to uCi) : 1.000E+00 1.000E+00 1.000E+00

___ -------_. __=_____

=_ _

ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 6 3

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpea EAB dose [TC961019.DAT]

REMOVAL: 0.000E+00 1/sec 9.769E-07 1/sec 1.000E+01 cfm NUC Grp 1 REL ER: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 MULTIPLIERS->

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 l

3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 CONTROL ROOM -

ENVIRONMENT --- I X/Q Breathing Occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 MULTIPLIERS->

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 1.44 1.00 2 3.600E+03 2.72 1.00 1.00 1.44 1.00 3 5.400E+03 2.72 1.00 1.00 1.44 1.00 4 7.200E+03 2.72 1.00 1.00 1.44 1.00 i

I e

ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 6 tj

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm EAB dose [TC961019.DAT]

not used Faulted S/G AVERAGE ----------CONTROL ROOH-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 2.160E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.784E+07 3.539E+10 3.457E+04 1.921E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.474E+07 2.923E+10 2.856E+04 1.586E+01 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.217E+07 2.415E+10 2.359E+04 1.310E+01 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.006E+07 1.995E+10 1.948E+04 1.082E+01 0.000E+00 0.000E+00 0.000E+00 Kr-83m TOTALS 0.000E+00 1.087E+11 1.062E+05 0.000E+00 Kr-85m INITIAL 0.000E+00 1.050E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 9.701E+07 1.817E+11 1.775E+05 9.862E+01 0.000E+00 0.000E+00 0.OOOE+00 2 1.0000 h 0.000E+00 0.000E+00 8.963E+07 1.679E+11 1.640E+05 9.112E+31 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 8.281E+07 1.551E+11 1.515E+05 8.418E+01 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 7.651E+07 1.433E+11 1.400E+05 7.778E+01 0.000E+00 0.000E+00 0.000E+00 Kr-85m TOTALS 0.000E+00 6.481E+11 6.331E+05 0.000E+00 Kr-85 INITIAL 0.000E+00 5.560E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.550E+08 9.999E+11 9.768E+05 5.427E+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 5.540E+08 9.982E+11 9.751E+05 5.417E+02 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 5.531E+08 9.964E+11 9.733E+05 5.407E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 5.521E+08 9.946E+11 9.716E+05 5.398E+02 0.000E+00 0.000E+00 0.000E+00 Kr-85 TOTALS 0.000E+00 3.989E+12 3.897E+06 0.000E+00 Kr-87 INITIAL 0.000E+00 6.020E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 4.576E+07 9.477E+10 9.258E+04 5.143E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 3.478E+07 7.203E+10 7.037E+04 3.909E+01 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 2.644E+07 5.475E+10 5.349E+04 2.972E+01 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 2.010E+07 4.162E+10 4.066E+04 2.259E+01 0.000E+00 0.000E+00 0.000E+00 Kr-87 TOTALS 0.000E+00 2.632E+11 2.571E+05 0.000EF00 Kr-88 INITIAL 0.000E+00 1.600E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.414E+08 2.709E+11 2.646E+05 1.470E+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.249E+08 2.393E+11 2.338E+05 1.299E+02 0.OOOE+00 0.OCOE+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.104E+08 2.115E+11 2.066E+05 1.148E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 9.752E+07 1.869E+11 1.825E+05 1.014E+02 0.000E+00 0.000E+00 0.000E+00 Kr-88 TOTALS 0.000E+00 9.086E+11 8.875E+05 0.000E+00 Kr-89 INITIAL 0.000E+00 5.060E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.007E+03 1.382E+09 1.350E+03 7.499E-01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 9.703E+00 1.914E+06 1.869E+00 1.038E-03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.344E-02 2.650E+03 2.589E-03 1.438E-06 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.861E-05 3.670E+00 3.585E-06 1.991E-09 0.000E+00 0.000E+00 0.000E+00 Kr-89 TOTALS 0.000E+00 1.384E+09 1.352E+03 0.000E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 6 5

TRAILS -- Transport of Radioactive Material in Linear systems, v2.0 FRP Case for 2.95 gym EAB dose [TC961019.DAT]

not used Faulted S/G AVERAGE CONTROL ROON CURRENT INTEGRD CURRENT INTEGRD PumaAED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec.

Xe-131m INITIAL 0.000E+00 5.410E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.394E+06 9.724E+09 9.499E+03 5.277E+00 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 5.378E+06 9.695E+09 9.470E+03 5.261E+00 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 5.362E+06 9.666E+09 9.442E+03 5.246E+00 0.000E+00 0.000E+00 0.000E+00~

4 2.0000 h 0.000E+00 0.000E+00 5.346E+06 9.637E+09 9.414E+03 5.230E+00 0.000E+00 0.000E+00 0.000E+00 Xe-131m TOTALS 0.000E+00 3.872E+10 3.782E+04 0.000E+00 Xa-133m INITIAL 0.000E+00 1.550E+0B 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.537E+08 2.778E+11 2.714E+05 1.508E+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.524E+08 2.755E+11 2.692E+05 1.495E+02 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.512E+08 2.732E+11 2.669E+05 1.483E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.499E+08 2.710E+11 2.647E+05 1.471E+02 0.000E+00 0.000E+00 0.000E+00 Xa-133m TOTALS 0.000E+00 1.098E+12 1.072E+06 0.000E+00 Xe-133 INITIAL 0.000E+00 1.320E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.314E+09 2.371E+12 2.316E+06 1.287E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.308E+09 2.360E+12 2.305E+06 1.281E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.302E409 2.349E+12 2.295E+06 1.275E+03 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.296E+09 2.339E+12 2.285E+06 1.269E+03 0.000E+00 0.000E+00 0.000E+00 Xe-133 TOTALS 0.000E+00 9.419E+12 9.201E+06 0.000E+00 Xa-135m INITIAL 0.000E+00 5.460E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.408E+07 5.381E+10 5.257E+04 2.920E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 3.629E+06 1.387E+10 1.355E+04 7.529E+00 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 9.355E+05 3.576E+09 3.494E+03 1.941E+00 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.0 h M O 0.000E+00 2.412E+05 9.220E+08 9.007E+02 5.004E-01 0.000E+00 0.000E+00 0.000E+00 Xe-135m TOTALS 0.000E+00 7.218E+10 7.051E+04 0.000E+00 Xa-135 INITIAL 0.000E+00 1.610E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.547E+08 2.841E+11 2.775E+05 1.542E+02 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.487E+08 2.730E+11 2.667E+05 1.482E+02 0.000E+00 0.0COE+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.429E+08 2.624E+11 2.563E+05 1.424E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.373E+08 2.521E+11 2.463E+05 1.368E+02 0.000E+00 0.000E+00 0.000E+00 Xa-135 TOTALS 0.000E+00 1.072E+12 1.047E+06 0.000E+00 Xe-137 INITIAL 0.000E+00 8.190E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 3.586E+04 2.702E+09 2.640E+03 1.467E+00 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.570E+02 1.183E+07 1.156E+01 6.421E-03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 6.874E-01 5.180E+04 5.061E-02 2.811E-05 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 3.010E-03 2.268E+02 2.216E-04 1.231E-07 0.000E+00 0.000E+00 0.000E+00 Xe-137 TOTALS 0.000E+00 2.714E+09 2.652E+03 0.000E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 66

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm EAB dose [TC961019.DAT]

not used Faulted S/G AVERAGE ----------CONTROL ROOM-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xa-138 INITIAL 0.000E+00 3.380E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.745E+06 3.183E+10 3.109E+04 1.727E+01 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.775E+06 7.294E+09 7.125E+03 3.958E+00 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 4.067E+05 1.671E+09 1.633E+03 9.070E-01 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 9.319E+04 3.830E+08 3.741E+02 2.078E-01 0.000E+00 0.000E+00 0.000E+00 Xe-138 TOTALS 0.000E+00 4.118E+10 4.023E+04 0.000E+00 I-131 INITIAL 0.000E+00 7.730E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.703E+09 1.389E+13 1.357E+07 7.538E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 7.675E+09 1.384E+13 1.352E+07 7.511E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 7.648E+09 1.379E+13 1.347E+07 7.484E+03 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 7.621E+09 1.374E+13 1.342E+07 7.458E+03 0.000E+00 0.000E+00 0.000E+00 I-131 TOTALS 0.000E+00 5.526E+13 5.398E+07 0.000E+00 I-132 INITIAL 0.000E+00 2.700E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 2.318E+09 4.508E+12 4.403E+06 2.446E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.990E+09 3.870E+12 3.781E+06 2.100E+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.709E+09 3.323E+12 3.246E+06 1.803E+03 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.467E+09 2.853E+12 2.787E+06 1.548E+03 0.000E+00 0.000E+00 0.000E+00 I-132 TOTALS 0.000E+00 1.455E+13 1.422E+07 0.000E+00 I-133 INITIAL 0.000E+00 1.210E+10 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.188E+10 2.158E+13 2.108E+07 1.171E+04 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 1.166E+10 2.119E+13 2.070E+07 1.15094ai 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 1.145E+10 2.080E+13 2.032E+07 * -

t 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 1.124E+10 2.042E+13 1.995E+07 A 0.000E+00 0.000E+00 0.000E+00 I-133 TOTALS 0.000E+00 8.399E+13 8.204E+07 0.000E+00 I-134 INITIAL O.000E+00 1.690E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.136E+09 2.511E+12 2.453E+06 1.363E+03 0.000E+00 0.000E+00 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 7.638E+08 1.688E+12 1.649E+06 9.160E+02 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 5.135E+08 1.135E+12 1.108E+06 6.158E+02 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 3.452E+08 7.628E+11 7.452E+05 4.140E+02 0.000E+00 0.000E+00 0.000E+00 I-134 TOTALS 0.000E+00 6.096E+12 5.955E+06 0.000E+00 I-135 INITIAL 0.000E+00 6.490E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 6.148E+09 1.137E+13 1.111E+07 6.171E+03 0.000E+00 0.000E+C0 0.000E+00 2 1.0000 h 0.000E+00 0.000E+00 5.823E+09 1.077E+13 1.052E+07 5.8462+03 0.000E+00 0.000E+00 0.000E+00 3 1.5000 h 0.000E+00 0.000E+00 5.516E+09 1.020E+13 9.967E+06 5.537E+03 0.000E+00 0.000E+00 0.000E+00 4 2.0000 h 0.000E+00 0.000E+00 5.225E+09 9.665E+12 9.441E+06 5.245E+03 0.000E+00 0.000E+00 0.000E+00 I-135 TOTALS 0.000E+00 4.201E+13 4.104E+07 0.000E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page G 7

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TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm EAB dose [TC961019.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INEAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSH RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr Xe-138 0.5000 h 8.89E-03 1.78E-02 6.62E-03 1.32E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2.04E-03 4.08E-03 1.52E-03 3.03E-03 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 4.67E-04 9.34E-04 3.47E-04 6.95E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.07E-04 2.14E-04 7.96E-05 1.59E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.15E-02 8.56E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 0.5000 h 1.18E+00 2.37E+00 6.24E-01 1.25E+00 7.32E+03 1.46E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 1.18E+00 2.36E+00 6.22E-01 1.24E+00 7.30E+03 1.46E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 1.17E+00 2.35E+00 6.20E-01 1.24E+00 7.27E+03 1.45E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.17E+00 2.34E+00 6.18E-01 1.24E+00 7.24E+03 1.45E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 4.71E+00 2.48E+00 2.91E+04 0.00E+00 0.00E+00 0.00E+00 I-132 0.5000 h 2.40E+00 4.79E+00 7.08E-01 1.42E+00 1.42E+01 2.83E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2. 0 6E+00 4.11E+00 6.08E-01 1.22E+00 1.22E+01 2.43E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 1.77E+00 3.53E+00 5.22E-01 1.04E+00 1.04E+01 2.09E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.52E+00 3.03E+00 4.48E-01 8.96E-01 8.97E+00 1.79E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 7.74E+00 2.29E+00 4.58E+01 0.00E+00 0.00E+00 0.00E+00 I-133 0.5000 h 2.95E+00 5.90E+00 2.74E+00 5.48E+00 1.90E+03 3.79E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+DO 1.0000 h 2.90E+00 5.80E+00 2.69E+00 5.38E+00 1.86E+03 3.72E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E^00 1.5000 h 2.84E+00 5.69E+00 2.64E+00 5.28E+00 1.83E+03 3.66E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 2.79E+00 5.59E+00 2.59E+00 5.19E+00 1.79E+03 3.59E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.15E+01 1.07E+01 7.38E+03 0.00E+00 0.00E+00 0.00E+00 I-134 0.5000 h 1.54E+00 3.00E+00 5.06E-01 1.01E+00 1.31E+00 2.62E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 1.04E+00 2.07E+00 3.40E-01 6.81E-01 8.82E-01 1.76E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 6.96E-01 1.39E+00 2.29E-01 4.58E-01 5.93E-01 1.19E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Et00 2.0000 h 4.68E-01 9. 3 6E-01 1.54E-01 3.08E-01 3.98E-01 7.97E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.74E+00 1.23E+00 3.18E+00 0.00E+00 0.00E+00 0.00E+00 1-135 0.5000 h 4.23E+00 8.46E+00 1.28E+00 2.56E+00 1.74E+02 3.47E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 4.01E+00 8.01E+00 1.21E+00 2.42E+00 1.65E+02 3.29E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 3.80E+00 7.59E+00 1.15E+00 2.30E+00 1. 5 6E+ 02 3.12E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 3.60E+00 7.19E+00 1.09E+00 2.18E+00 1.48E+02 2.95E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.56E+01 4.73E+00 6.42E+02 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 70

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpa EAB dose [TC961019.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHFL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem aren/hr arem aresa/hr arem nr.em/hr arem mress/hr arem arem/hr arem aren/hr ALL NUCLIDES 0.5000 h 1.25E+01 2.50E+01 6.10E+00 1.22E+01 9.41E+03 1.8BE+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 1.14E+01 2.27E+01 5.69E+00 1.14E+01 9.34E+03 1.87E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 1.04E+01 2.09E+01 5.36E+00 1.07E+01 9.26E+03 1.85E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 9.69E+00 1.94E+01 5.09E+00 1.02E+01 9.20E+03 1.84E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 4.40E+01 2.22E+01 3.72E+04 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 .

FRP 2.95 gpm Cases Attachment 4 Page 7 }

l ERS-SFL-96-010 l Attachm:;nt 4 Pega 72 l

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I l

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TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ASA Case for LPE dose [TC961002.DAT]

COMP: not used COMP: all S/Gs COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

-- . - - _ = = . - _---- ===-_--- . . - -

INITIAL: 0.000E+00 Kr-83m 1.920E+01 Kr-83m UCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 9.340E+01 Kr-85m . 0.000E+00 Kr-85m 0.000E400 Kr-85 4.930E+02 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 5.360E+01 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.430E+02 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 4.490E+00 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 4.810E+00 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.380E+02 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.170E+03 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 4.850E+01 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 1.430E+02 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 7.290E+00 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 3.010E+01 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 2.710E+03 I-131 0.000E+00 I-131 0.000E+00 I-132 8.020E+02 I-132 0.000E+00 I-132 0.000E+00 I-133 3.890E+03 I-133 0.000E+00 I-133 0.000E+00 I-134 1.790E+01 I-134 0.000E+00 I-134 0.000E+00 I-135 1.740E+03 I-135 0.000E+00 I-135 ACT MULT (to uC1) : 1.000E+00 3.000E+00 1.000E+00

.-------- _ _____=__ .- .....---------- _. _ _ _ _

ERS-SFL-96-0,10 ~

ASA case for CR/LPZ Dose Attachment 4 Page (e

TRAILS -- Transport of Radioactive Material in Linear systems, v2.0 AJA Case for LPE dose [TC961002.DAT]

_ _ _ _ _ _ _ _ _ - - - - - __ - - . - - - __ _ _ - - = = - _ _ _ - ...- ___________

REMOVAL: 0.000E+00 1/sec 1.382E+01 1/sec 1.000E+01 cfm NUC Grp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

- - - . . . _ . - - _ _ - . - - - - _ _ ______ - = _ _ _ _ _ _ _ _ _ _ _ _ - -- - - - - -

-= -

MULTIPLIERS->

STEP TIME XPR XREN XRF XPR XREM XRF XPR XREM XRF 1 6.000E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 70.0 70.0 1.00 5 1.440E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 70.0 70.0 1.00 6 2.880E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 70.0 70.0 1.00 7 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 8 8.640E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 9 3. 45 6E+ 05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 10 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00

- = CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Dreathing occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 HULTIPLIERS=====>

STEP TIME,s 1 6.000E+01 2.72 1.00 1.00 7.07 1.00 2 1.800E+03 2.72 1.00 1.00 7.07 1.00 3 5.400E+03 2.72 1.00 1.00 7.07 1.00 4 7.200E+03 2.72 1.00 1.00 7.07 1.00 5 1.440E+04 2.72 1.00 1.00 7.07 1.00 6 2.880E+04 2.72 1.00 1.00 7.07 1.00 7 3.060E+04 1.43 1.00 1.00 7.07 1.00 8 8.640E+04 1.43 1.00 1.00 7.07 1.00 0 3.456E+05 1.10 1.00 0.600 7.07 1.00 10 2.592E+06 0.630 1.00 0.400 7.07 1.00 ERS-SFL-96-010 ASA case for CR/LPZ Dose Attachment 4 Page 7 d

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ASA Case for LPE dose [TC961002.DAT]

not used all S/Gs AVERAGE ----------CONTROL ROON-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD 7,TEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/see uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 5.760E+01 0.000E+00 Kr-83m TOTALS 0.000E+00 4.168E+00 5.760E+01 2.191E+01 Kr-85m INITIAL 0.000E+00 2.802E+02 0.000E+00 Kr-85m TOTALS 0.000E+00 2.027E+01 2.802E+02 1.612E+02 Kr-85 INITIAL 0.000E+00 1.479E+03 0.000E+00 Kr-85 TOTALS 0.000E+00 1.0703+02 1.479E+03 1.250E+03 Kr-87 INITIAL 0.000E+00 1.608E+02 0.000E+00 Kr-87 TOTALS 0.000E+00 1.164E+01 1.608E+02 4.843E+01 Kr-88 INITIAL 0.000E+00 4.290E+02 0.000E+00 Kr-88 TOTALS 0.000E+00 3.104E+01 4.290E+02 2.058E+02 Kr-89 INITIAL 0.000E+00 1.347E+01 0.000E+00 Kr-89 TOTALS 0.000E+00 9.744E-01 1.347E+01 2.334E-01 Xe-131m INITIAL 0.000E+00 1.443E+01 0.000E+00 Xe-131m TOTALS 0.000E+00 1.044E+00 1.443E+01 1.211E+01 Xe-133m INITIAL 0.000E+00 4.140E+02 0.000E+00 Xe-133m TOTALS 0.000E+00 2.996E+01 4.140E+02 3.372E+02 Xs-133 INITIAL 0.000E+00 3.510E+03 0.000E+00 Xa-133 TOTALS 0.000E+00 2.540E+02 3.510E+03 2.920E+02 Xe-135m INITIAL 0.000E+00 1.455E+02 0.000E+00 Xe-135m TOTALS 0.000E+00 1.053E+01 1.455E+02 1.160E+01 Xe-135 INITIAL 0.000E+00 4.290E+02 0.000E+00 Xo-135 TOTALS 0.000E+00 3.104E+01 4.290E+02 2.965E+02 Xe-137 INITIAL 0.000E+00 2.187E+01 0.000E+00 Xs-137 TOTALS 0.000E+00 1.582E+00 2.187E+01 4.580E-01 Xa-138 INITIAL 0.000E+00 9.030E+01 0.000E+00 Xe-138 TOTALS 0.000E+00 6.534E+00 9.029E+01 6.663E+00 I-131 INITIAL 0.000E+00 8.130E+03 0.000E+00 I-131 TOTALS 0.000E+00 5.883E+02 8.130E+03 6.801E+03 I-132 INITIAL 0.000E+00 2.406E+03 0.000E+00 ERS-SFL-96-010 ASA case for CR/LPZ Dose Attachment 4 Page 7 5

I-132 TOTALS 0.000E+00 1.741E+02 2.406E+03 1.040E+03 I-133 INITIAL 0.000E+00 1.167E+04 0.000E+00 I-133 TOTALS 0.000E+00 8.444E+02 1.167E+04 9.002E+03 I-134 INITIAL 0.000E+00 5.370E+01 0.000E+00 I-134 TOTALS 0.000E+00 3.886E+00 5.370E+01 1.233E+01 I-135 INITIAL 0.000E+00 5.220E+03 0.000E+00 I-135 TOTALS 0.000E+00 3.777E+02 5.220E+03 3.364E+03 ERS-SFL-96-010 ASA case for CR/LPZ Dose Attachment 4 Page 76

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ASK Case for LPZ dose [TC961002.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem ures/hr arem aren/hr arem arem/hr mrem aren/hr arem aree/hr are aren/hr Kr-83m TOTALS 6.05E-11 0.00E+00 0.00E+00 3.34E-12 0.00E+00 0.00E+00 Kr-85m TOTALS 5.13E-07 1.01E-06 0.00E+00 4.28E-08 1.68E-06 0.00E+00 Kr-85 TOTALS 3.72E-08 5.20E-06 0.00E+00 4.56E-09 1.27E-05 0.00E+00 Kr-87 TOTALS 1.61E-06 3.82E-06 0.00E+00 7.04E-08 3.32E-06 0.00E+00 Kr-88 TOTALS 1.09E-05 2.39E-06 0.00E+00 7.56E-07 3.31E-06 0.00E+00 Kr-89 TOTALS 3.07E-07 3.33E-07 0.00E+00 7.71E-10 1.67E-08 0.00E+00 Xa-131m TOTALS 1.39E-09 1.54E-08 0.00E+00 1.69E-10 3.72E-08 0.00E+00 Xa-133m TOTALS 1.38E-07 9.19E-07 0.00E+00 1.63E-08 2.16E-06 0.00E+00 Xe-133 TOTALS 1.39E-06 2.62E-06 0.00E+00 1.67E-07 6.29E-06 0.00E+00 Xa-135m TOTALS 7.00E-07 2.23E-07 0.00E+00 8.10E-09 5.12E-08 0.00E+00 Xa-135 TOTALS 1.20E-06 1.96E-06 0.00E+00 1.21E-07 3.92E-06 0.00E+00 Xe-137 TOTALS 4.68E-08 7.09E-G7 0.00E+00 1.42E-10 4.28E-08 0.00E+00 Xa-138 TOTALS 1.27E-06 9.43E-07 0.00E+00 1.36E-08 2.01E-07 0.00E+00 I-131 TOTALS 3.48E-05 1.84E-05 2.15E-01 4.22E-06 4.43E-05 5.20E-01 ERS-SFL-96-010 ASA case for CR/LPZ Dose Attachment 4 Page 7 7

t

-[

I-132 TOTALS 6.43E-05 1.90E-05 3.80E-04 4.03E-06 2.37E-05 4.74E-04 l I-133 TOTALS 8.02E-05 7.45E-05 5.15E-02 8.98E-06 1.66E-04 1.15E-01 I-134 TOTALS 1.66E-06 5.44E-07 1.41E-06 5.52E-08 3.61E-07 9.34E-07 ERS-SFL-96-010 ASA case for CR/LPZ Dose Attachment 4 Page 78

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ASA Case for LPZ dose [TC961002.DAT]

ENVIRONMENT------- -

C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE -

arem aren/hr arem aren/hr arem arem/hr mrem arem/hr arem aren/hr arem aren/hr !

I-135 TOTALS 9.76E-05 2.95E-05 4.01E-03 9.13E-06 5.49E-05 7.46E-03 ALL NUCLIDES 0.0167 h 2.97E-04 1.78E-02 1.62E-04 9.72E-03 2.710-01 1.63E+01 8.27E-08 9.92E-06 8.99E-07 1.08E-04 1.51E-03 1.81E-01 0.5000 h 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.45E-06 8.5?E-06 4.85E-05 9.39E-05 8. 3 6E-02 1.65E-01 1.5000 h 0.00E+00 0. 00E-$ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.17E-06 5.97E-06 8.01E-05 6.79E-05 1.46E-01 1.28E-01 2.0000 h 0.00E+00 0.00E300 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.74E-06 5.02E-06 3.14E-05 5.80E-05 6.03E-02 1.13E-01 4.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.29E-06 2.57E-06 8.67E-05 3.15E-05 1.77E-01 6.82E-02 7' 8.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.81E-06 7.33E-07 7.43E-05 9.89E-06 1.72E-01 2.49E-02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.26E-08 2.14E-09 8.46E-07 2.91E-08 2.13E-03 7.42E-05 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.35E-09 7.88E-11 1.34E-07 1.24E-09 3.84E-04 4.48E-06 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.39E-10 1.11E-16 3.81E-09 1.76E-15 1.49E-05 1.18E-11 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.46E-1G 0.00E+00 3.93E-15 0.00E+00 2.67E-11 0.00E+00 TOTALS 2.97E-04 1.62E-04 2.71E-01 2.76E-05 3.23E-04 6.43E-01 ERS-SFL-96-010 ASA case for CR/LPZ Dose Attachment 4 Page 79

_. . _ _ _ _ . _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ - - _ . - - _. . . ._ , _ a

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ILI Case for LPZ dose [TC961003.DAT]

COMP: not used COMP: intact S/Gs COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

INITIAL: 0.000E+00 I-131 3.090E+06 I-131 uci 0.000E+00 I-131 0.000E+00 I-132 9.140E+0S I-132 0.000E+00 I-132 0.000E+00 I-133 4.430E+06 I-133 0.000E+00 I-133 0.000E+00 I-134 2.040E+04 I-134 0.000E+00 I-134 0.000E+00 I-135 1.980E+06 I-135 0.000E+00 I-135 ACT MULT (to uci): 1.000E+00 1.000E+00 1.000E+00 ERS-SFL-96-010 Ill case for CR/LPZ Dose Attachment 4 Page 8 0

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ILI Case for LPZ dose [TC961003.DAT]

-- ____ =- _--------------

REMOVAL: 0.000E+00 1/sec 5.130E-06 1/sec 1.000E+01 cfm NUC Crp 1 REL R: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Crp 2 REL FR: 0.000E+00 0.000E+00 IltTAKE REDUCT: 9.360E-01 NUC Crp 3 REL M: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 MULTIPLIERS - >

ETEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 4 1.440E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.640 0.000E+00 70.0 70.0 1.00 5 2.880E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.640 0.000E+00 70.0 70.0 1.00 6 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 7 8.640E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 8 3.456E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 0 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00

CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS->

$TEP TIME,s 1 1.800E+03 2.72 1.00 1.00 7.07 1.00 2 5.400E+03 2.72 1.00 1.00 7.07 1.00 3 7.200E+03 2.72 1.00 1.00 7.07 1.00 4 1.440E+04 2.72 1.00 1.00 7.07 1.00 5 2.880E+04 2.72 1.00 1.00 7.07 1.00 6 3.060E+04 1.43 1.00 1.00 7.07 1.00 7 8.640E+04 1.43 1.00 1.00 7.07 1.00 8 3. 45 6E+ 05 1.10 1.00 0.600 7.07 1.00 9 2.592E+06 0.630 1.00 0.400 7.07 1.00 ERS-SFL-96-010 ill case for CR/LPZ Dose Attachment 4 Page b 1

l TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ILI Case for LPZ dose [TC961003.DAT]

not used intact S/Gs AVERAGE - CONTROL ROON- ---

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I

I-131 INITIAL 0.000E+00 3.090E+06 0.000E+00 I-131 TOTALS 0.000E+00 2.575E+12 3.119E+05 3.416E+04 I-132 INITIAL 0.000E+00 9.140E+05 0.000E+00 I-132 TOTALS 0.000E+00 1.044E+10 4.035E+04 4.061E+03 I-133 INITIAL 0.000E+00 4.430E+06 0.000E+00 I-133 TOTALS 0.000E+00 4.350E+11 4.036E+05 4.382E+04 I-134 INITIAL 0.000E+00 2.040E+04 0.000E+00 I-134 TOTALS 0.000E+00 9.091E+07 4.324E+G2 3.796E+01 I-135 INITIAL 0.000E+00 1.980E+06 0.000E+00 I-135 TOTALS 0.000E+00 6.304E+10 1.437E+05 1.529E+04 ALL NUCLIDES 0.000E+00 2.089E+05 0.000E+00 0.000E+00 9 STEP 9 ERS-SFL-96-010 ILI case for CR/LPZ Dose Attachment 4 Page 8 2

TRAILS -- Trt.mport cf Radiscctive Material in Linear fyotems, v2.0 ILI case for LPE dose [TC961003.DAT)

ENVIRONMENT--------- -------CONTROL -ROOM-------

External EDE SKIN-DE TRY CDE-INHAL Extern.11 EDE SKIN-DE THY CDE-INHAL DOSE DOS 5 RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem areun/hr arem aren/hr arem arem/hr arem arem/hr arem mren/hr mrem atem/hr I-131 TOTALS 1.34E-03 7.05E-04 8.26E+00 2.12E-05 2.23E-04 2.61E+00 I-132 TOTALS 1.08E-03 3.19E-04 6.38E-03 1.57E-05 9.26E-05 1.85E-03 I-133 TOTALS 2.77E-03 2.58E-03 1.78E+00 4.37E-05 8.0BE-04 5.59E-01 I-134 TOTALS 1.33E-05 4.38E-06 1.14E-05 1.70E-07 1.11E-06 2.88E-06 I-135 TOTALS 2.69E-03 8.13E-04 1.10E-01 4.15E-05 2.50E-04 3.39E-02 ALL NUCLIDES 0.5000 h 9.44E-04 1.89E-03 4.85E-04 9.71E-04 9.45E-01 1.89E+00 7.54E-06 2.95E-05 7.76E-05 3.04E-04 1.53E-01 6.02E-01 1.5000 h 1.71E-03 1.71E-03 9.04E-04 9.04E-04 1.85E+00 1.85E&OO 2.53E-05 2.17E-05 2.66E-04 2.32E-04 5.43E-01 4.89E-01 2.0000 h 7.80E-04 1.56E-03 4.22E-04 8.45E-04 9.04E-01 1.81E+00 1.05E-05 2.04E-05 1.13E-04 2.22E-04 2.43E-01 4.82E-01 4.0000 h 1.75E-03 8.76E-04 9.84E-04 4.92E-04 2.25E+00 1.12E+00 3.41E-05 1.44E-05 3.81E-04 1.65E-04 8.70E-01 3.96E-01 8.0000 h 2.70E-03 6.75E-04 1.62E-03 4.05E-04 4.22E+00 1.05E+00 4.39E-05 8.83E-06 5.25E-04 1.09E-04 1.37E+00 3.03E-01 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.54E-07 2.57E-08 9.32E-06 3.20E-07 2.60E-02 9.05E-04

, 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+C0 1.13E-07 9.4GE-10 1.46E-06 1.31E-08 4.68E-03 5.46E-05 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.86E-09 1.31E-15 3.95E-08 1.50E-14 1.82E-04 1.44E-10 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.91E-15 0.00E+00 3.29E-14 0.00E+00 3.25E-10 0.00E+00 TOTALS 7.89E-03 4.42E-03 1.02E+01 1.22E-04 1.37E-03 3.21E+00 i

ERS-SFL-96-010 ill case for CR/LPZ Dose Attachment 4 Page 8 3

4 TIULILs -- Transport of Radioactive Material in Linear systems, v2.0 FLI Case for LPE dose [TC961004.DAT]

COMP: not usod COMP: faulted s/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

. - = - - - _ _ _ _ _ _ _ _ _ = - - - .- - - - - - - _ _ _

INITIAL: 0.000E+00 I-131 3.090E+06 I-131 uCi 0.000E+00 I-131 0.000E+00 I-132 9.140E+05 I-132 0.000E+00 I-132 0.000E+00 I-133 4.430E+06 I-133 0.000E+00 I-133 0.000E+00 I-134 2.040E+04 I-134 0.000E+00 I-134 0.000E+00 I-135 1.980E+06 I-135 0.000E+00 I-133 ACT NULT (to uC1): 1.000E+00 1.000E+00 1.000E+00 ERS-SFL-96-010 FLI case for CR/LPZ Dose Attachment 4 Page 8 gj

- - ---_m - - * - - - - - *"-M= w .- -we - - - - + + , - - - _ _ - - ._--_.m_. -

i r

i TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 i FLI Case for LPE dose [TC961004.DAT]

_____________== - ____________=_ _ - _ - __ __==___________ = - _- ---

______ = --

REMOVAL: 0.000E+00 1/sec 7.675E-03 1/sec 1.000E+01 cfm NUC Crp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Crp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 l NUC Crp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

--_ ----...____ _____ ____==_......--- _ ......._. _-------..._--__ _ _ ---_==_ _

MULTIPLIERS - > i STEP TIME XPR XREN XRF XPR XREM XRF XPR XREM XRF l 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 4 1.440E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 5 2.880E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 6 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 7 8.640E+04 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 8 3.456E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 9 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00

CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS - >

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 7.07 1.00 2 5.400E+03 2.72 1.00 1.00 7.07 1.00 3 7.200E+03 2.72 1.00 1.00 7.07 1.00 4 1.440E+04 2.72 1.00 1.00 7.07 1.00 5 2.880E+04 2.72 1.00 1.00 7.07 1.00 6 3.060E+04 1.43 1.00 1.00 7.07 1.00 7 8.640E+04 1.43 1.00 1.00 7.07 1.00 8 3.456E+05 1.10 1.00 0.600 7.07 1.00 9 2.592E+06 0.630 1.00 0.400 7.07 1.00 ERS-SFL-96-010 Fu case for CR/LPZ Dose Attachment 4 Page 8 5

TRAILS -- Transport of Radioactive Materiaal in Linear Systemas, v2.0 FLI Case for LPE dose [TC962006.DAT]

not used faulted S/G AVERAGE ----CONTROL ROOM --

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-see uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I-131 INITIAL 0.000E+00 3.090E+06 0.000E+00 I-131 TOTALS 0.000E+00 4.026E+08 3.090E+06 2.521E+06 I-132 INITIAL 0.000E+00 9.140E+05 0.000E+00 I-132 TOTALS 0.000E+00 1.178E+08 9.041E+05 3.846E+05 I-133 INITIAL 0.000E+00 4.430E+06 0.000E+00 I-133 TOTALS 0.000E+00 5.765E+08 4.425E+06 3.334E+06 ,

t I-134 INITIAL 0.000E+00 2.040E+04 0.000E+00 I-134 TOTALS 0.000E+00 2.584E+06 1.983E+04 4.499E+03 I-135 INITIAL 0.000E+00 1.980E+06 0.000E+00 I-135 TOTALS 0.000E+00 2.570E+08 1.973E+06 1.246E+06 ALL NUCLIDES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C STEP 9 h

l ERS-SFL-96-010 FLI case for CR/LPZ Dose ~ Attachment 4 Page 8 0

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 FLI Case for LPE dose [TC961004.DAT]

i l

ENVIRONMENT--------- -------CONTROL ROOM-------

l External EDE SKIN-DE TIE CDE-INHAL External EDE SKIN-DE THY CDE-INHAL l

DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem meesm/hr mrem areum/hr mrem aress/hr arem arem/hr arem arenn/hr nrem aress/hr l I-131 TOTALS 1.32E-02 6.98E-03 8.19E+01 1.57E-03 1.64E-02 1.93E+02 I-132

. TOTALS 2.42E-02 7.14E-03 1.43E-01 1.49E-03 8.77E-03 1.75E-01 I

I-133 TOTALS 3.04E-02 2.82E-02 1.95E+01 3.32E-03 6.14E-02 4.25E+01 I-134 TOTALS 6.12E-04 2.01E-04 5.21E-04 2.01E-05 1.32E-04 3.41E-04 I-135 TOTALS 3.69E-02 1.12E-02 1.51E+00 3.38E-03 2.03E-02 2.76E+00 ALL NUCLIDES 0.5000 h 1.05E-01 2.11E-01 5.37E-02 1.07E-01 1.03E+02 2.06E+02 8.41E-04 3.28E-03 8.59E-03 3.36E-02 1.67E+01 6.57E+01 1.5000 h 9.94E-08 9.93E-08 5.16E-08 5.16E-08 1.03E-04 1.03E-04 2.76E-03 2.31E-03 2.88E-02 2.45E-02 5.80E+01 5.10E+01 2.0000 h 8.93E-20 1.79E-19 4.80E-20 9.60E-20 1.02E-16 2.03E-16 1.06E-03 1.94E-03 1.13E-02 2.09E-02 2.39E+01 4.49E+01 4.0000 h 8.50E-26 4.25E-26 4.64E-26 2.32E-26 1.01E-22 5.05E-23 2.83E-03 9.97E-04 3.13E-02 1.14E-02 7.05E+01 2.71E+01 8.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.26E-03 2.86E-04 2.68E-02 3.54E-03 6.82E+01 9.87E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.44E-05 8.34E-07 3.03E-04 1.04E-05 8.46E-01 2.95E-02 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.66E-06 3.08E-08 4.76E-05 4.25E-07 1.52E-01 1.78E-03 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.31E-08 4.26E-14 1.29E-06 4.88E-13 5.93E-03 4.70E-09 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.47E-14 0.00E+00 1.07E-12 0.00E+00 1.06E-08 0.00E+00 TOTALS 1.05E-01 5.37E-02 1.03E+02 9.78E-03 1.07E-01 2.38E+02 !

ERS-SFL-96-010 FLl case for CR/LPZ Dose Attachment 4 Page 8 7

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITC Case for LPE dose [TC961005.DAT]

COMP: not used COMP: intact S/G COMP: Control Rooum VOLUME: 1.730E+05 Cu.Ft.

_ _ _ -- =--

INITIAL: 0.000E+00 I-131 1.260E+08 I-131 uCi 0.000E+00 I-131 0.000E+00 I-132 4.390E+07 I-132 0.000E+00 I-132 0.000E+t0 I-133 1.970E+08 I-133 0.000E+00 I-133 0.000E+C0 I-134 2.750E+07 I-134 0.000E+00 I-134 0.000E+00 I-135 1.060E+08 I-135 0.000E+00 I-135 ACT MULT (to uci) : 1.000E+00 1.000E+00 1.000E+00

_ - - - - = - - - - _ - - - - - - - - - - _ . - - - - - - - - - - - - - --

PRODUCTION,uci/s: 0.000E+00 I-131 1.360E+06 I-131 INTAKE: 1.000E+01 CEM 0.000E+00 I-132 2.520E+06 I-132 0.000E+00 I-133 3.080E+06 I-133 0.000E+00 I-134 3.680E+06 I-134 [

0.000E+00 I-135 2.810E+06 I-135 ERS-SFL-96-010 iTC case for CR/LPZ Dose Attachment 4 Page 88

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITC Case for LPZ dose [TC961005.DAT]

_______- _ _ _ _ - - - - _ _ _ _ = - - - - _ - - - _ - --- = ___ _----- - - _ _ _ = _ _ _

REMOVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfm NUC Grp 1 REL ER: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 ,

NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

--________________.________- =_-- - =---- ____ - ---____ ___

MULTIPLIERS->

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.000E-02 0.000E+00 1.00 70.0 0.000E+00 '

4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.000E-02 0.000E+00 70.0 70.0 1.00 5 1.440E+04 0.000E+00 0.000E+00 0.000E+00 1.00 1.000E-02 0.000E+00 76.0 70.0 1.00 6 2.880E+04 0.000E+00 0.000E+00 0.000E+00 2.000E-03 1.000E-02 0.000E+00 70.0 70.0 1.00 7 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 '

8 8.640E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 9 3.456E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 10 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 t

CONTROL ROOM -- ---

ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 ;

MULTIPLIERS - >

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 7.07 1.00 2 3.600E+03 2.72 1.00 1.00 7.07 1.00 3 5.400E+03 2.72 1.00 1.00 7.07 1.00 4 7.200E+03 2.72 1.00 1.00 7.07 1.00 5 1.440E+04 2.72 1.00 1.00 7.07 1.00 ,

6 2.880E+04 2.72 1.00 1.00 7.07 1.00 7 3.060E+04 1.43 1.00 1.00 7.07 1.00 j 8 8.640E+04 1.43 1.00 1.00 7.07 1.00 9 3. 45 6E+ 05 1.10 1.00 0.600 7.07 1.00 10 2.592E+06 0.630 1.00 0.400 7.07 1.00 i

ERS-SFL-96-010 ITC case for CR/LPZ Dose Attachment 4 Page 8 9

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITC Case for LPZ dose tTC961005.DAT]

not used intact S/G AVERAGE - - - - -

=-CONTROL ROOM ---

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD CTEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I-131 INITIAL 0.000E+00 1.260E+08 0.000E+00 I-131 TOTALS 0.000E+00 1.829E+16 9.233E+05 1.555E+05 I-132 INITIAL 0.000E+00 4.390E+07 0.000E+00 I-132 TOTALS 0.OOOE+00 4.349E+14 1.268E+06 1.291E+05 I-133 INITIAL 0.000E+00 1.970E+08 0.000E+00 I-133 TOTALS 0.000E+00 4.822E+15 1.997E+06 3.139E+05 I-134 INITIAL 0.000E+00 2.750E+07 0.000E+00 I-134 TOTALS 0.000E+00 2.419E+14 1.442E+06 8.952E+04 I-135 INITIAL 0.000E+00 1.060E+08 0.000E+00 I-135 TOTALS 0.000E+00 1.395E+15 1.671E+06 2.295E+05 ALL NUCLIDES 0.000E+00 1.498E+09 0.000E+00 0.000E+00 0 STEP 10 ERS-SFL-96-010 ITC case for CR/LPZ Dose Attachment 4 Page9 0

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITC Cue for LPE dose [TC961005.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INEAL DOSE DOSE PATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mresa ares /hr arena arem/hr mrom mrem /hr mrem area /hr mrem arem/hr arem aree/hr I-131 TOTALS 3.95E-03 2.09E-03 2.45E+01 9.66E-05 1.01E-03 1.19E+01 I-132 TOTALS 3.39E-02 1.00E-02 2.00E-01 5.00E-04 2.94E-03 5.89E-02 I-133 TOTALS 1.37E-02 1.27E-02 8.82E+00 3.13E-04 5.79E-03 4.00E+00 I-134 TOTALS 4.45E-02 1.46E-02 3.78E-02 4.00E-04 2.62E-03 6.78E-03 I-135 TOTALS 3.13E-02 9.45E-03 1.28E+00 6.23E-04 3.75E-03 5.09E-01 ALL NUCLIDES 0.5000 h 2.78E-02 5.56E-02 1.04E-02 2.08E-02 6.36E+00 1.27E+01 2.12E-04 8.08E-04 1.59E-03 6.09E-03 1.03E+00 4.04E+00 1.0000 h 7.51E-02 1.50E-01 2.83E-02 5.65E-02 1.79E+01 3.59E+01 3.58E-04 6.36E-04 2.74E-03 4.93E-03 1.95E+00 3.78E+00 1.3000 h 1.14E-03 2.29E-03 4.35E-04 8.70E-04 2.94E-01 5.88E-01 2.76E-04 4.77E-04 2.17E-03 3.81E-03 1.77E+00 3.32E+00 2.0000 h 1.48E-03 2.95E-03 5.68E-04 1.14E-03 4.08E-01 8.16E-01 2.10E-04 3.69E-04 1.70E-03 3.03E-03 1. 5 6E+ 0 0 2.94E+00 4.0000 h 8.47E-03 4.23E-03 3.36E-03 1.68E-03 2.75E+00 1.38E+00 4.93E-04 1.63E-04 4.23E-03 1.47E-03 4.73E+00 1.88E+00 8.0000 h 1.33E-02 3.32E-03 5.89E-03 1.47E-03 7.06E+00 1.77E+00 3.79E-04 5.64E-05 3.63E-03 5.71E-04 5.33E+00 9.40E-01 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.79E-06 1.60E-07 4.87E-05 1.65E-06 8.06E-02 2.80E-03 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.12E-07 4.03E-09 6.91E-06 5.39E-08 1.43E-02 1.62E-04 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.15E-08 3.91E-15 1.58E-07 4.65E-14 5.37E-04 4.07E-10 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.62E-15 0.00E+00 1.01E-13 0.00E+00 9.16E-10 0.00E+00 TOTALS 1.27E-01 4.89E-02 3.48E+01 1.93E-03 1.61E-02 1.65E+01 ERS-SFL-96-010 ITC case for CR/LPZ Dose Attachment 4 Page 9 i

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for LPE dose [TC961006.DAT]

COMP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

INITIAL: 0.000E+00 Kr-83m 2.160E+07 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 1.050E+08 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 5.560E+08 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 6.020E+07 Kr-87 'O.000E+00 Kr-87 0.000E+00 Kr-88 1.600E+08 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 5.060E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 5.410E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.550E+08 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.320E+09 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 5.460E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 1.610E+08 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 . 8.190E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 3.380E+07 Xe-138 0.000E+00 Xe-138 ACT MULT (to uCi) : 1.000E+00 1.000E+00 1.000E+00 ERS-SFL-96-010 ITN case for CR/LPZ Dose Attachment 4 Page g 3

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for LPE dose [TC961006.DAT]

--- ==

REMOVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfm NUC Crp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Crp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

___.- ______ _ _ . _ _ _ -- --= - - _ _ -- -=- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _. . - - -

MULTIPLIERS - >

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XBF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 5 1.440E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 6 2.880E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 7 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 8 8.640E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 9 3.456E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 10 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00

--- CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS->

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 7.07 1.00 2 3.600E+03 2.72 1.00 1.00 7.07 1.00 3 5.400E+03 2.72 1.00 1.00 7.07 1.00 4 7.200E+03 2.72 1.00 1.00 7.07 1.00 5 1.440E+04 2.72 1.00 1.00 7.07 1.00 6 2.880E+04 2.72 1.00 1.00 7.07 1.00 7 3.060E+04 1.43 1.00 1.00 7.07 1.00 8 8.640E+04 1.43 1.00 1.00 7.07 1.00 0 3.456E+05 1.10 1.00 0.600 7.07 1.00 10 2.592E+06 0.630 1.00 0.400 7.07 1.00 ERS-SFL-96-010 ITN case for CR/LPZ Dose Attachment 4 Page 93

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for LPE dose [TC961006.DAT]

not used intact S/G AVERAGE --

-- = CONTROL ROON CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-63m INITIAL 0.000E+00 2.160E+07 0.000E+00 Kr-83m TOTALS 0.000E+00 2.052E+11 1.347E+04 4.223E+03 Kr-85m INITIAL 0.000E+00 1.050E+08 0.000E+00 Kr-85m TOTALS 0.000E+00 2.440E+12 1.196E+05 5.554E+04 Kr-05 INITIAL 0.000E+00 5.560E+08 0.000E+00 Kr-85 TOTALS 0.000E+00 1.434E+15 1.104E+06 6.680E+05 Kr-87 INITIAL 0.000E+00 6.020E+07 0.000E+00 Kr-87 TOTALS 0.000E+00 3.974E+11 2.707E+04 6.443E+03 Kr-88 INITIAL 0.000E+00 1.600E+08 0.000E+00 Kr-88 TOTALS 0.000E+00 2.358E+12 1.396E+05 5.541E+04 Kr-89 INITIAL 0.000E+00 5.060E+06 0.000E+00 Kr-89 TOTALS 0.000E+00 1.384E+09 9.549E+01 1.651E+00 Xa-131m INITIAL 0.000E+00 5.410E+06 0.000E+00 Xe-131m TOTALS 0.000E+00 6.593E+12 1.063E+04 6.411E+03 Xa-133m INITIAL 0.000E+00 1.550E+08 0.000E+00 Xe-133m TOTALS 0.000E+00 4.223E+13 2.920E+05 1.729E+05 Xa-133 INITIAL 0.000E+00 1.320E+09 0.000E+00 Xe-133 TOTALS 0.000E+00 8.450E+14 2.563E+06 1.537E+06 X2-135m INITIAL 0.000E+00 5.460E+07 0.000E+00 Iw-135m TOTALS 0.000E+00 7.259E+10 5.008E+03 3.056E+02 Ka-135 INITIAL 0.000E+00 1.610E+08 0.000E+00 Xe-135 TOTALS 0.000E+00 7.606E+12 2.394E+05 1.274E+05 Xe-137 INITIAL 0.000E+00 8.190E+06 0.000E+00 Xa-137 TOTALS 0.000E+00 2.715E+09 1.873E+02 3.902E+00 Xe-138 INITIAL 0.000E+00 3.380E+07 0.000E+00 Xa-138 TOTALS 0.000E+00 4.134E+10 2.852E+03 1.655E+02 ALL NUCLIDES 0.000E+00 5.779E+08 0.000E+00 0.000E+00 0 STEP 10 ERS-SFL-96-010 ITN case for CR/LPZ Dose Attachment 4 Page g d

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for LPE dose [TC961006.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr arem arem/hr mrem aren/hr arem arem/hr mrem arem/hr arem aren/hr Kr-83m TOTALS 1.42E-08 0.00E+00 0.00E+00 6.44E-10 0.00E+00 0.00E+00 Kr-85m TOTALS 2.19E-04 4.32E-04 0.00E+00 1.48E-05 5.80E-04 0.00E+00 Kr-85 TOTALS 2.77E-05 3.88E-03 0.00E+00 2.44E-06 6.78E-03 0.00E+00 Kr-87 TOTALS 2.71E-04 6.43E-04 0.00E+00 9.36E-06 4.42E-04 0.00E+00 Kr-88 TOTALS 3.54E-03 7.79E-04 0.00E+00 2.04E-04 8.92E-04 0.00E+00 Kr-89 TOTALS 2.18E-06 2.36E-06 0.00E+00 5.46E-09 1.18E-07 0.00E+00 Xa-131m TOTALS 1.02E-06 1.13E-05 0.00E+00 8.93E-08 1.97E-05 0.00E+00 Xe-133m TOTALS 9.75E-05 6.48E-04 0.00E+00 8.37E-06 1.11E-03 0.00E+00 Xe-133 TOTALS 1.01E-03 1.91E-03 0.00E+00 8.80E-05 3.31E-03 0.00E+00 Xo-135m TOTALS 2.41E-05 7.66E-06 0.00E+00 2.13E-07 1.35E-06 0.00E+00 X2-135 TOTALS 6.72E-04 1.10E-03 0.00E+00 5.19E-05 1.68E-03 0.00E+00 Xa-137 TOTALS 4.01E-07 6.07E-06 0.00E+00 1.21E-09 3.65E-07 0.00E+00 Xe-138 TOTALS 4.00E-05 2.98E-05 0.00E+00 3.37E-07 4.99E-06 0.00E+00 l

ERS-SFL-96-010 ITN case for CR/LPZ Dose Attachment 4 Page 9 5

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITN Case for LPE dose [TC961006.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INEAL External EDE SKIN-DE TRY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr arem arem/hr mrem arem/hr arem mreum/hr arem area /hr arem area /hr ALL NUCLIDES 0.5000 h 7.42E-04 1.48E-03 8.40E-04 1.68E-03 0.00E+00 0.00E+00 5.68E-06 2.18E-05 1.30E-04 5.06E-04 0.00E+00 0.00E+00 1.0000 h 6.28E-04 1.26E-03 7.53E-04 1.51E-03 0.00E+00 0.00E+00 9.66E-06 1.72E-05 2.30E-04 4.21E-04 0.00E+00 0.00E+00

.1.5000 h 5.55E-04 1.11E-03 7.02E-04 1.40E-03 0.00E+00 0.00E+00 7.72E-06 1.39E-05 1.94E-04 3.58E-04 0.00E+00 0.00E+00

-2.0000 h 4.98E-04 9.95E-04 6.63E-04 1.33E-03 0.00E+00 0.00E+00 1.16E-05 3.20E-05 3.11E-04 8.71E-04 0.00E+00 0.00E+00 4.0000 h 1.56E-03 7.82E-04 2.39E-03 1.19E-03 0.00E+00 0.00E+00 9.89E-05 6.30E-05 3.12E-03 2.13E-03 0.00E+00 0.00E+00 8.0000 h 1.92E-03 4.80E-04 4.10E-03 1.02E-03 0.00E+00 0.00E+00 2.40E-04 5.96E-05 1.05E-02 3.02E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.06E-06 1.68E-07 2.5BE-04 8.93E-06 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.32E-07 4. 7 6E-09 4.45E-05 5.05E-07 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.51E-08 1.01E-14 1.70E-06 1.57E-12 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.25E-14 0.00E+00 3.58E-12 0.00E+00 0.00E+00 0.00E+00 TOTALS 5.90E-03 9.45E-03 0.00E+00 3.79E-04 1.48E-02 0.00E+00 ERS-SFL-96-010 ITN case for CR/LPZ Dose Attachment 4 Page 9 (j

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

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 ERC Case for dose for LPE 2.95 gpaa [TC961016.DAT]

COMP: not used COMP: faulted S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

INITIAL: 0.000E+00 Kr-83m 2.160E+07 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 1.050E+08 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 5.560E+08 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 6.020E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.600E+08 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 5.060E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 5.410E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.550E+08 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.320E+09 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 5.460E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 1.610E+08 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 8.190E+06 Xe-137 0.000E+00 Xe-1L37 0.000E+00 Xe-138 3.380E+07 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 1.260E+08 I-131 0.000E+00 I-131 0.000E+00 I-132 4.390E+07 I-132 0.000E+00 I-132 0.000E+00 I-133 1.970E+08 I-133 0.000E+00 I-133 0.000E+00 I-134 2.750E+07 I-134 0.000E+00 I-134 0.000E+00 I-135 1.060E+08 I-135 0.000E+00 I-135 ACT MULT (to uCi) : 1.000E+00 1.000E+00 1.000E+00

- - - - - - - - - - - - - = _ ---------------

- _ - - - - - - - _ = - _ = . _ - - - = - - - - - - - - - - - - - _ . _ - -

PRODUCTION,uci/s: 0.000E+00 I-131 1.360E+06 I-131 INTAKE: 1.000E+01 CEM 0.000E+00 I-132 2.520E+06 I-132 0.000E+00 I-133 3.080E+06 I-133 0.000E+00 I-134 3.680E+06 I-134 0.000E+00 I-135 2.810E+06 I-135 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 9 7

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 RC Case for dose for LPE 2.95 gpm (TC961016.DAT]

-=====___________- _=-- _ _ _ - - = = . .- --- -------.-- --

--- =__

REMOVAL: 0.000E+00 1/sec 9.769E-07 1/sec 1.000E+01 cfm NUC Crp 1 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Crp 2 REL M: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 '

NUC Crp 3 REL M: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

______--------- . = - - = - - - - - - - - - - - - - - - - - - - - - - = _ _ _ ..----- _____-- ------------- --

MULTIPLIERS->

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.OOOE+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 70.0 70.0 1.00 5 1.440E+04 0.000E+00 0.000E+00 0.000E+00 1.00 1.00 0.000E+00 70.0 70.0 1.00 6 2.880E+04 0.000E+00 0.000E+00 0.000E+00 2.000E-03 1.00 0.000E+00 70.0 70.0 1.00 7 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 i 8 8.640E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.OOOE+00 9 3.456E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 10 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 ,

CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS - >

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 7.07 1.00 2 3.600E+03 2.72 1.00 1.00 7.07 1.00 3 5.400E+03 2.72 1.00 1.00 7.07 1.00 4 7.200E+03 2.72 1.00 1.00 7.07 1.00 5 1.440E+04 2.72 1.00 1.00 7.07 1.00 6 2.880E+04 2.72 1.00 1.00 7.07 1.00 7 3.060E+04 1.43 1.00 1.00 7.07 1.00 8 8.640E+04 1.43 1.00 1.00 7.07 1.00 9 3.456E+05 1.10 1.00 0.600 7.07 1.00 10 2.592E+06 0.630 1.00 0.400 7.07 1.00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 9 8

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPZ 2.95 gpm (TC961016.DAT]

not used faulted S/G AVERAGE ----------CONTROL ROOM-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uC1-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 2.160E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.784E+07 3.539E+10 3.457E+04 1.921E+01 1.939E+00 3.958E-10 1.825E+03 2 1.0000 h 0.000E+00 0.000E+00 1.474E+07 2.923E+10 2.856E+04 1.586E+01 1.453E+00 2.965E-10 3.030E+03 3 1.5000 h 0.000E+00 0.000E+00 1.217E+07 2.415E+10 2.359E+04 1.310E+01 1.091E+00 2.226E-10 2.272E+03 4 2.0000 h 0.000E+00 0.000E+00 1.006E+07 1.995E+10 1.948E+04 1.082E+01 2.304E+00 4.704E-10 3.112E+03 5 4.0000 h 0.000E+00 0.000E+00 4.681E+06 5.061E+10 4.944E+04 6.867E+00 3.208E+00 6.548E-10 2.050E+04 6 8.0000 h 0.000E+00 0.000E+00 1.015E+06 3.453E+10 3.373E+04 2.343E+00 1.385E+00 2.827E-10 2.812E+04 7 8.5000 h 0.000E+00 0.000E+00 B.396E+05 1.664E+09 0.000E+00 0.000E+00 3.437E-03 7.016E-13 4.145E+02 8 24.0000 h 0.000E+00 0.000E+00 2.368E+03 7.957E+09 0.000E+00 0.000E+00 6.596E-07 1.346E-16 2.241E+01 9 96.0000 h 0.000E+00 0.000E+00 3.397E-09 2.251E+07 0.000E+00 0.000E+00 3.576E-24 7.301E-34 4.300E-03 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 3.228E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.332E-20 Kr-83m TOTALS 0.000E+00 2.035E+11 1.894E+05 5.929E+04 Kr-85m INITIAL 0.000E+00 1.050E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 9.701E+07 1.817E+11 1.775E+05 9.862E+01 1.051E+01 2.145E-09 9.716E+03 2 1.0000 h 0.000E+00 0.000E+00 8.963E+07 1.679E+11 1.640E+05 9.112E+01 8.805E+00 1.797E-09 1.733E+04 3 1.5000 h 0.000E+00 0.000E+00 8.281E+07 1.551E+11 1.515E+05 8.418E+01 7.394E+00 1.509E-09 1.454E+04 4 2.0000 h 0.000E+00 0.000E+00 7.651E+07 1.433E+11 1.400E+05 7.778E+01 1.747E+01 3.566E-09 2.268E+04 5 4.0000 h 0.000E+00 0.000E+00 5.576E+07 4.722E+11 4.613E+05 6.407E+01 3.649E+01 7.448E-09 2.032E+05 6 8.0000 h 0.000E+00 0.000E+00 2.961E+07 5.949E+11 5.811E+05 4.036E+01 3.359E+01 6.856E-09 4.992E+05 7 8.5000 h 0.000E+00 0.000E+00 2.740E+07 5.129E+10 0.000E+00 0.000E+00 9.325E-02 1.903E-11 1.024E+04 8 24.0000 h 0.000E+00 0.000E+00 2.491E+06 5.797E+11 0.000E+00 0.000E+00 5.765E-04 1.177E-13 1.017E+03 9 96.0000 h 0.000E+00 0.000E+00 3.617E+01 5.795E+10 0.000E+00 0.000E+00 3.165E-14 6.461E-24 6.325E+00 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 8.415E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.473E-10 Kr-85m TOTALS 0.000E+00 2.404E+12 1.676E+06 7.780E+05 Kr-85 INITIAL 0.000E+00 5.560E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.550E+08 9.999E+11 9.768E+05 5.427E+02 6.005E+01 1.22 6E-08 5.483E+04 2 1.0000 h 0.000E+00 0.000E+00 5.540E+08 9.982E+11 9.751E+05 5.417E+02 5.437E+01 1.110E-08 1.029E+05 3 1.5000 h 0.000E+00 0.000E+00 5.531E+08 9.964E+11 9.733E+05 5.407E+02 4.933E+01 1.007E-08 9.324E+04 4 2.0000 h 0.000E+00 0.000E+00 5.521E+08 9.946E+11 9.716E+05 5.398E+02 1.259E+02 2.570E-08 1.591E+05 5 4.0000 h 0.000E+00 0.000E+00 5.482E+08 3.961E+12 3.869E+06 5.374E+02 3.529E+02 7.204E-08 1.790E+06 6 8.0000 h 0.000E+00 0.000E+00 5.405E+08 7.839E+12 7.658E+06 5.318E+02 5.739E+02 1.171E-07 6.927E+06 7 8.5000 h 0.000E+00 0.000E+00 5.40SE+08 9.730E+11 0.000E+00 0.000E+00 1.721E+00 3.514E-10 1.773E+05 8 24.0000 h 0.000E+00 0.000E+00 5.405E+08 3.016E+13 0.000E+00 0.000E+00 1.171E-01 2.390E-11 3.331E+04 9 96.0000 h 0.000E+00 0.000E+00 5.402E+08 1.401E+14 0.000E+00 0.000E+00 4.425E-07 9.032E-17 2.431E+03 10 720.0000 h 0.000E+00 0.000E+00 5.377E+03 1.211E+15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.186E-03 Kr-85 TOTALS 0.000E+00 1.398E+15 1.542E+07 9.339E+06 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page g g

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 n c Case for dose for LPZ 2.95 gpm [TC961016.DAT]

not used faulted S/G AVERAGE ----------CONTROL ROOM-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-see uCi uCi/sec uCi uCi/cc uCi-sec Kr-87 INITIAL 0.000E+00 6.020E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 4.576E+07 9.477E+10 9.258E+04 5.143E+01 4.992E+00 1.019E-09 4.761E+03 2 1.0000 h 0.000E+00 0.000E+00 3.478E+07 7.203E+10 7.037E+04 3.909E+01 3.441E+00 7.024E-10 7.498E+03 3 1.5000 h 0.000E+00 0.000E+00 2.644E+07 5.475E+10 5.349E+04 2.972E+01 2.377E+00 4.853E-10 5.174E+03 4 2.0000 h 0.000E+00 0.000E+00 2.010E+07 4.162E+10 4.066E+04 2.259E+01 4.623E+00 9.437E-10 6.433E+03 5 4.0000 h 0.000E+00 0.000E+00 6.708E+06 8.785E+10 8.582E+04 1.192E+01 4.838E+00 9.876E-10 3.425E+04 6 8.0000 h 0.000E+00 0.000E+00 7.475E+05 3.911E+10 3.821E+04 2.653E+00 1.250E+00 2.551E-10 3.208E+04 7 8.5000 h 0.000E+00 0.000E+00 5.692E+05 1.178E+09 0.000E+00 0.000E+00 2.853E-03 5.828E-13 3.691E+02 8 24.0000 h 0.000E+00 0.000E+00 1.219E+02 3.758E+09 0.000E+00 0.000E+00 4.160E-08 8.491E-18 1.430E+01 9 96.0000 h 0.000E+00 0.000E+00 1.101E-15 8.051E+05 0.000E+00 0.000E+00 1.421E-30 0.000E+00 2.084E-04 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 7.274E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.119E-27 Kr-87 TOTALS 0.000E+00 3.951E+11 3.811E+05 9.059E+04 Kr-88 INITIAL 0.000E+00 1.600E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.414E+08 2.709E+11 2.646E+05 1.470E+02 1.533E+01 3.129E-09 1.428E+04 2 1.0000 h 0.000E+00 0.000E+00 1.249E+08 2.393E+11 2.338E+05 1.299E+02 1.228E+01 2.507E-09 2.474E+04 3 1.5000 h 0.000E+00 0.000E+00 1.104E+08 2.115E+11 2.066E+05 1.148E+02 9.865E+00 2.014E-09 1.985E+04 4 2.0000 h 0.000E+00 0.000E+00 9.752E+07 1.869E+11 1.825E+05 1.014E+02 2.229E+01 4.550E-09 2.939E+04 5 4.0000 h 0.000E+00 0.000E+00 5.943E+07 5.537E+11 5.409E+05 7.513E+01 3.949E+01 8.060E-09 2.323E+05 6 8.0000 h 0.000E+00 0.000E+00 2.208E+07 5.432E+11 5.306E+05 3.685E+01 2.662E+01 5.435E-09 4.477E+05 7 8.5000 h 0.000E+00 0.000E+00 1.954E+07 3.741E+10 0.000E+00 0.000E+00 7.069E-02 1.443E-11 8.058E+03 8 24.0000 h 0.000E+00 0.000E+00 4.446E+05 2.817E+11 0.000E+00 0.000E+00 1.094E-04 2.234E-14 6.086E+02 9 96.0000 h 0.000E+00 0.000E+00 1.038E-02 6.558E+09 0.000E+00 0.000E+00 9.659E-18 1.972E-27 9.435E-01 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 1.531E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.330E-14 Kr-88 TOTALS 0.000E+00 2.331E+12 1.959E+06 7.769E+05 Kr-89 INITIAL 0.000E+00 5.060E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.007E+03 1.382E+09 1.350E+03 7.499E-01 1.298E-02 2.649E-12 1.989E+01 2 1.0000 h 0.000E+00 0.000E+00 9.703E+00 1.914E+06 1.869E+00 1.038E-03 1.630E-05 3.328E-15 3.482E+00 3 1.5000 h 0.000E+00 0.000E+00 1.344E-02 2.650E+03 2.589E-03 1.438E-06 2.053E-08 4.190E-18 4.374E-03 4 2.0000 h 0.000E400 0.000E+00 1.861E-05 3.670E+00 3.585E-06 1.991E-09 7.323E-11 1.495E-20 5.580E-06 5 4.0000 h 0.000E+00 0.000E+00 6.843E-17 5.089E-03 4.971E-09 6.904E-13 1.666E-14 3.401E-24 1.978E-08 6 8.0000 h 0.000E+00 0.000E+00 0.000E+00 1.871E-14 1.828E-20 1.269E-24 3.064E-26 6.254E-36 4.475E-12 7 8.5000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.275E-31 0.000E+00 4.451E-24 8 24.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.442E-29 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 0.00CE+00 0.000E+00 0.000E+00 0.000R+00 0.000E+00 0.000E+00 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr-89 TOTALS 0.000E+00 1.384E+09 1.352E+03 2.337E+01 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 ()

i TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 r Mtc Case for dose for LPE 2.95 gpst [TC961016.DAT]

not used faulted S/G AVERAGE - - - - - -

CONTROL ROOM-CURRENT INTEGRD CUltRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xe-131m INITIAL 0.000E+00 5.410E+06 0.000E+00 t 1 0.5000 h 0.000E+00 0.000E+00 5.394E+06 9.724E+09 9.499E+03 5.277E+00 5.836E-01 1.191E-10 5.330E+02 f' 2 1.0000 h 0.000E+00 0.000E+00 5.378E+06 9.695E+09 9.470E+03 5.261E+00 5.277E-01 1.077E-10 9.992E+02 3 1.5000 h 0.000E+00 0.000E+00 5.362E+06 9.666E+09 9.442E+03 5.246E+00 4.782E-01 9.762E-11 9.045E+02 4 2.0000 h 0.000E+00 0.000E+00 5.346E+06 9.637E+09 9.414E+03 5.230E+00 1.219E+00 2.489E-10 1.541E+03 5 4.0000 h 0.000E+00 0.000E+00 5.283E+06 3.826E+10 3.738E+04 5.191E+00 3.401E+00 6.943E-10 1.727E+04 j 6 8.0000 h 0.000E+00 0.000E+00 5.158E+06 7.517E+10 7.343E+04 5.099E+00 5.480E+00 1.119E-09 6.635E+04 7 8.5000 h 0.000E+00 0.000E+00 5.152E+06 9.279E+09 0.000E+00 0.000E+00 1.642E-02 3.351E-12 1.693E+03 l 8 24.0000 h 0.000E+00 0.000E+00 4.961E+06 2.821E+11 0.000E+00 0.000E+00 1.075E-03 2.195E-13 3.141E+02 9 96.0000 h 0.000E+00 0.000E+00 4.162E+06 1.179E+12 0.000E+00 0.000E+00 3.411E-09 6.963E-19 2.202E+01 10 720.0000 h 0.000E+00 0.000E+00 9.083E+05 4.802E+12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.983E-05

' Xe-131m TOTALS 0.000E+00 6.424E+12 1.486E+05 8.963E+04 Xe-133m INITIAL 0.000E+00 1.550E+08 0.000E+00 [

1 0.5000 h 0.000E+00 0.000E+00 1.537E+08 2.778E+11 2.714E+05 1.508E+02 1.663E+01 3.395E-09 1.520E+04 '

2 1.0000 h 0.000E+00 0.000E+00 1.524E+0B 2.755E+11 2.692E+05 1.495E+02 1.496E+01 3.054E-09 2.840E+04 3 1.5000 h 0.000E+00 0.000E+00 1.512E+08 2.732E+11 2.669E+05 1.483E+02 1.348E+01 2.752E-09 2.557E+04 l 4 2.0000 h 0.000E+00 0.000E+00 1.499E+08 2.710E+11 2.647E+05 1.471E+02 3.419E+01 6.979E-09 4.330E+04 5 4.0000 h 0.000E+00 0.000E+00 1.450E+08 1.062E+12 1.037E+06 1.440E+02 9.342E+01 1.907E-08 4.775E+05 !

6 8.0000 h 0.000E+00 0.000E+00 1.356E+08 2.020E+12 1.973E+06 1.370E+02 1.445E+02 2.950E-08 1.775E+06 7 8.5000 h 0.000E+00 0.000E+00 1.347E+08 2.433E+11 0.000E+00 0.000E+00 4.306E-01 8.790E-11 4.459E+04 j 8 24.0000 h 0.000E+00 0.000E+00 1.098E+08 6.799E+12 0.000E+00 0.00CE+00 2.388E-02 4.874E-12 7.847E+03 ,

9 96.0000 h 0.000E+00 0.000E+00 4.249E+07 1.838E+13 0.000E+00 0.000E+00 3.493E-08 7.131E-18 4.607E+02 t 10 720.0000 h 0.000E+00 0.000E+00 1.133E+04 1.160E+13 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.739E-04 [

Xe-133m TOTALS 0.000E+00 4.119E+13 4.082E+06 2.418E+06 j t

Xe-133 INITIAL 0.000E+00 1.320E+09 0.000E+00 l 1 0.5000 h 0.000E+00 0.000E+00 1.314E+09 2.371E+12 2. 316E+ 06 1. 287E+ 03 1.422E+02 2.902E-08 1.299E+05 2 1.0000 h 0.000E+00 0.000E+00 1.308E+09 2.360E+12 2.305E+06 1.281E+03 1.284E+02 2.620E-08 2.432E+05 [

3 1.5000 h 0.000E+00 0.000E+00 1.302E+09 2.349E+12 2.295E+06 1.275E+03 1.162E+02 2.371E-08 2.198E+05 !

4 2.0000 h 0.000E+00 0.000E+00 1.296E+09 2.339E+12 2.285E+06 1.269E+03 2.957E+02 6.035E-08 3.740E+05 5 4.0000 h 0.000E+00 0.000E+00 1.273E+09 9.250E+12 9.036E+06 1.255E+03 8.199E+02 1.674E-07 4.172E+06 [

6 8.0000 h 0.000E+00 0.000E+00 1.228E+09 1.801E+13 1.759E+07 1.222E+03 1.306E+03 2.665E-07 1.587E+07 t 7 8.5000 h 0.000E+00 0.000E+00 1.225E+09 2.207E+12 0.000E+00 0.000E+00 3.906E+00 7.974E-10 4.032E+05 8 24.0000 h 0.000E+00 0.000E+00 1.125E+09 6.550E+13 0.000E+00 0.000E+00 2.440E-01 4.980E-11 7.369E+04 I 9 96.0000 h 0.000E+00 0.000E+00 7.564E+08 2.406E+14 0.000E+00 0.000E+00 6.205E-07 1.267E-16 4.909E+03 ;

10 720.0000 h 0.000E+00 0.000E+00 2.435E+07 4.786E+14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.249E-02 i Xa 133 TOTALS 0.000E+00 8.236E+14 3.583E+07 2.150E+07 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 101

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPE 2.95 gpst [TC961016.DAT]

not used faulted S/G AVERAGE ----------CONTROL ROOM-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uC1/cc uCi-sec Xe-135m INITIAL O.000E+00 5.460E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.408E+07 5.381E+10 5.257E+04 2.920E+01 1.788E+00 3.649E-10 1.982E+03 2 1.0000 h 0.000E+00 0.000E+00 3.629E+06 1.387E+10 1.355E+04 7.529E+00 4.180E-01 8.532E-11 1.692E+03 3 1.5000 h 0.000E+00 0.000E+00 9.355E+05 3.576E+09 3.494E+03 1.941E+00 9.795E-02 1.999E-11 3.960E+02 4 2.0000 h 0.000E+00 0.000E+00 2.412E+05 9.220E+08 9.007E+02 5.004E-01 6.472E-02 1.321E-11 1.393E+02 5 4.0000 h 0.000E+00 0.000E+00 1.065E+03 3.188E+08 3.115E+02 4.326E-02 4.907E-03 1.002E-12 1.071E+02 6 8.0000 h 0.000E+00 0.000E+00 2.079E-02 1.415E+06 1.382E+00 9.597E-05 1.056E-05 2.155E-15 6.127E+00 7 8.5000 h 0.000E+00 0.000E+00 5.369E-03 2.050E+01 0.000E+00 0.000E+00 8.180E-09 1.670E-18 2.651E-03 8 24.0000 h 0.000E+00 0.000E+00 3.188E-21 7.138E+ 00 0.000E+00 0.000E+00 3.304E-28 6.745E-38 1.022E-05 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 4.239E-18 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.129E-25 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-135m TOTALS 0.000E+00 7.250E+10 7.082E+04 4.323E+03 Xe-135 INITIAL 0.000E+00 1.610E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.547E+08 2.841E+11 2.775E+05 1.542E+02 1.675E+01 3.419E-09 1.539E+04 2 1.0000 h 0.000E+00 0.000E+00 1.487E+08 2.730E+11 2.667E+05 1.482E+02 1.460E+01 2.979E-09 2.816E+04 3 1.5000 h 0.000E+00 0.000E+00 1.429E+08 2.624E+11 2.563E+05 1.424E+02 1.275E+01 2.602E-09 2.457E+04 4 2.0000 h 0.000E+00 0.000E+00 1.373E+08 2.521E+11 2.463E+05 1.368E+02 3.133E+01 6.395E-09 4.011E+04 5 4.0000 h 0.000E+00 0.000E+00 1.171E+08 9.139E+11 8.928E+05 1.240E+02 7.587E+01 1.549E-08 4.028E+05 6 8.0000 h 0.000E+00 0.000E+00 8.516E+07 1.444E+12 1.411E+06 9.796E+01 9.282E+01 1.895E-08 1.240E+06 7 8.5000 h 0.000E+00 0.000E+00 8.199E+07 1.504E+11 0.000E+00 0.000E+00 2.680E-01 5.471E-11 2.849E+04 8 24.0000 h 0.000E+00 0.000E+00 2.521E+07 2.686E+12 0.000E+00 0.000E+00 5.606E-03 1.144E-12 3.787E+03 9 96.0000 h 0.000E+00 0.000E+00 1.053E+05 1.188E+12 0.000E+00 0.000E+00 8.854E-11 1.807E-20 8.090E+01 10 720.0000 h 0.000E+00 0.000E+00 2.530E-16 4.982E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.278E-06 Xe-135 TOTALS 0.000E+00 7.459E+12 3.350E+06 1.783E+06 Xe-137 INITIAL 0.000E+00 8.190E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 3.586E+04 2.702E+09 2.640E+03 1.467E+00 3.060E-02 6.245E-12 4.531E+01 2 1.0000 h 0.000E+00 0.000E+00 1.570E+02 1.183E+07 1.156E+01 6.421E-03 1.215E-04 2.480E-14 9.887E+00 3 1.5000 h 0.000E+00 0.000E+00 6.874E-01 5.180E+04 5.061E-02 2.811E-05 4.037E-07 9.874E-17 3.927E-02 4 2.0000 h 0.000E+00 0.000E+00 3.010E-03 2.268E+02 2.216E-04 1.231E-07 5.452E-09 1.113E-18 1.615E-04 5 4.0000 h 0.000E+00 0.000E+00 1.106E-12 9.974E-01 9.744E-07 1.353E-10 3.943E-12 8.050E-22 1.795E-06 6 8.0000 h 0.000E+00 0.000E+00 1.493E-31 3.665E-10 3.580E-16 2.486E-20 7.245E-22 1.479E-31 1.279E-09 7 8.5000 h 0.000E+00 0.000E+00 6.550E-34 4.929E-29 0.000E+00 0.000E+00 9.532E-27 1.946E-36 1.160E-19 8 24.0000 h 0.000E+00 0.000E+00 0.000E+00 2.171E-31 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.111E-24 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xo-137 TOTALS 0.000E+00 2.714E+09 2.652E+03 5.524E+01 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 2

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPZ 2.95 gpm [TC961016.DAT]

not used faulted S/G AVERAGE ----------CONTROL ROOM-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xe-138 INITIAL 0.000E+00 3.380E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.745E+06 3.183E+10 3.109E+04 1.727E+01 1.011E+00 2.064E-10 1.137E+03 2 1.0000 h 0.000E+00 0.000E+00 1.775E+06 7.294E+09 7.125E+03 3.958E+00 2.101E-01 4.290E-11 9.154E+02 3 1.5000 h 0.000E+00 0.000E+00 4.067E+05 1.671E+09 1.633E+03 9.070E-01 4.377E-02 8.935E-12 1.904E+02 4 2.0000 h 0.000E+00 0.000E+00 9.319E+04 3.830E+08 3.741E+02 2.078E-01 2.571E-02 5.249E-12 5.839E+01 5 4.0000 h 0.000E+00 0.000E+00 2.569E+02 1.135E+08 1.109E+02 1.540E-02 1.605E-03 3.277E-13 3.850E+01 6 8.0000 h 0.000E+00 0.000E+00 1.953E-03 3.139E+05 3.066E-01 2.129E-05 2.167E-06 4.422E-16 1.842E+00 7 8.5000 h 0.000E+00 0.000E+00 4.483E-04 1.840E+00 0.000E+00 0.000Et00 1.492E-09 3.045E-19 5.352E-04 8 24.0000 h 0.000E+00 0.000E+00 6.896E-24 5.483E-01 0.000E+00 0.000E+00 1.561E-30 0.000E+00 1.723E-06 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 8.435E-21 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.803E-27 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-138 TOTALS 0.000E+00 4.129E+10 4.034E+04 2.342E+03 I-131 INITIAL 0.000E+00 1.260E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 2.569E+09 2.427E+12 2.371E+06 1.317E+03 1.456E+02 2.973E-08 1.330E+05 2 1.0000 h 0.000E+00 0.000E+00 5.004E+09 6.817E+12 6.659E+06 3.700E+03 1.368E+02 2.792E-08 2.540E+05 3 1.5000 h 0.000E+00 0.000E+00 7.430E+09 1.119E+13 1.093E+07 6.074E+03 1.341E+02 2.738E-08 2.438E+05 4 2.0000 h 0.000E+00 0.000E+00 9.847E+09 1.555E+13 1.519E+07 8.439E+03 2.008E+02 4.099E-08 3.027E+05 5 4.0000 h 0.000E+00 0.000E+00 1.943E+10 1.055E+14 1.030E+08 1.431E+04 5.906E+02 1.206E-07 2.964E+06 6 8.0000 h 0.000E+00 0.000E+00 1.892E+10 2.761E+14 2.698E+08 1.873E+04 1.207E+03 2.464E-07 1.366E+07 7 8.5000 h 0.000E+00 0.000E+00 1.889E+10 3.403E+13 0.000E+00 0.000E+00 3.614E+00 7.378E-10 3.728E+05 8 24.0000 h 0.000E+00 0.000E+00 1.787E+10 1.025E+15 0.000E+00 0.000E+00 2.325E-01 4.747E-11 6.878E+04 9 96.0000 h 0.000E+00 0.000E+00 1.380E+10 4.081E+15 0.000E+00 0.000E+00 6.789E-07 1.386E-? 6 4.730E+03 10 720.0000 h 0.000E+00 0.000E+00 1.466E+09 1.236E+16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.381E-02 I-131 TOTALS 0.000E+00 1.791E+16 4.079E+08 1.800E+07 I-132 INITIAL 0.000E+00 4.390E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 4.245E+09 3.956E+12 3.864E+06 2.147E+03 2.208E+02 4.507E-08 2.066E+05 2 1.0000 h 0.000E+00 0.000E+00 7.852E+09 1.097E+13 1.072E+07 5.953E+03 1.802E+02 3.679E-08 3.593E+05 3 1.5000 h 0.000E+00 0.000E+00 1.095E+10 1.699E+13 1.660E+07 9.221E+03 1.560E+02 3.184E-08 3.016E+05 4 2.0000 h 0.000E+00 0.000E+00 1.361E+10 2.216E+13 2.165E+07 1.203E+04 2.ziCF+02 4.650E-08 3.483E+05 5 4.0000 h 0.000E+00 0.000E+00 2.098E+10 1.272E+14 1.243E+08 1.726E+04 5.122E+02 1.046E-07 2.846E+06 6 8.0000 h 0.000E+00 0.000E+00 6.239E+09 1.749E+14 1.709E+08 1.187E+04 4.584E+02 9.357E-08 6.857E+06 7 8.5000 h 0.000E+00 0.000E+00 5.366E+09 1.042E+13 0.000E+00 0.000E+00 1.183E+00 2.414E-10 1.381E+05 8 24.0000 h 0.000E+00 0.000E+00 5.023E+07 6.350E+13 0.000E+00 0.000E+00 7.531E-04 1.537E-13 8.961E+03 9 96.0000 h 0.000E+00 0.000E+00 1.894E-02 6.001E+11 0.000E+00 0.000E+00 1.074E-18 2.192E-28 5.710E+00 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 2.263E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.143E-15 I-132 TOTALS 0.000E+00 4.307E+14 3.479E+08 1.107E+07 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 3

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPZ 2.95 gpm [TC961016.DAT) not used faulted S/G AVERAGE - - - - - = - -- - CONTROL ROOM-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec j I-133 INITIAL 0.000E+00 1.970E+08 0.000Et00 1 0.5000 h 0.000E+00 0.000E+00 5.687E+09 5.310E+12 5.188E+06 2.882E+03 3.163E+02 6.457E-08 2.896E+05 2 1.0000 h 0.000E+00 0.000E+00 1.108E+10 1.5106,15 1.475E+07 8.196E+03 2.932E+02 5.986E-08 5.481E+05 3 1.5000 h 0.000E+00 0.000E+00 1.637E+10 2.471E+13 2.414E+07 1.341E+04 2.844E+02 5.805E-08 5.197E+05 4 2.0000 h 0.000E+00 0.000E+00 2.156E+10 3.415E+13 3.336E+07 1.853E+04 4.269E+02 8.714E-08 6.431E+05 5 4.0000 h 0.000E+00 0.000E+00 4.141E+10 2.276E+14 2.223E+08 3.088E+04 1.228E+03 2.507E-07 6.222E+06 6 8.0000 h 0.000E+00 0.000E+00 3.582E+10 5.550E+14 5.422E+08 3.765E+04 2.295E+03 4.684E-07 2.675E+07 7 8.5000 h 0.000E+00 0.000E+00 3.523E+10 6.394E+13 0.000E+00 0.000E+00 6.770E+00 1.382E-09 7.069E+05 8 24.0000 h 0.000E+00 0.000E+00 2.102E+10 1.535E+15 0.000E+00 0.OOOE+00 2.747E-01 5.608E-11 1.131E+05 9 96.0000 h 0.000E+00 0.000E+00 1.908E+09 2.064E+15 0.000E+00 0.000E+00 9.429E-08 1.925E-17 4.784E+03 10 720.0000 h 0.000E+00 0.000E+00 1.777E+00 2.061E+14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.642E-03 I-133 TOTALS 0.000E+00 4.731E+15 8.419E+08 3.580E+07 I-134 INITIAL 0.000E+00 2.750E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.485E+09 5.286E+12 5.164E+06 2.869E+03 2.630E+02 5.368E-08 2.556E+05 2 1.0000 h 0.000E+00 0.000E+00 9.155E+09 1.339E+13 1.308E+07 7.269E+03 1.700E+02 3.470E-08 3.825E+05 3 1.5000 h 0.000E&OO 0.000E+00 1.162E+10 1.884E+13 1.841E+07 1.023E+04 1.198E+02 2.446E-08 2.570E+05 4 2.0000 h 0.000E+00 0.000E+00 1.328E+10 2.251E+13 2.199E+07 1.222E+04 1.702E+02 3.475E-08 2.650E+05 5 4.0000 h 0.000E+00 0.000E+00 1.599E+10 1.078E+14 1.053E+08 1.463E+04 2.775E+02 5.666E-08 1.737E+06 6 8.0000 h 0.000E+00 0.000E+00 6.989E&O8 6.978E+13 6.816E+07 4.734E+03 9.776E+01 1.996E-08 1.992E+06 7 8.5000 h 0.000E+00 0.000E+00 4.707E+08 1.039E+12 0.000E+00 0.000E+00 1.975E-01 4.031E-11 2.830E+04 8 24.0000 h 0.000E+00 0.000E+00 2.240E+03 2.143E+12 0.000E+00 0.000E+00 6.394E-08 1.305E-17 7.374E+02 9 96.0000 h 0.000E+00 0.000E+00 4.234E-22 1.020E+07 0.000E+00 0.000E+00 4.569E-38 0.000E+00 2.388E-04 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 1.928E-18 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.706E-34 I-134 TOTALS 0.000E+00 2.408E+14 2.321E+08 4.917E+06 I-135 INITIAL 0.000E+00 1.060E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.024E+09 4.657E+12 4.549E+06 2.527E+03 2.726E+02 5.564E-08 2.510E+05 2 1.0000 h 0.000E+00 0.000E+00 9.682E+09 1.327E+13 1.297E+07 7.203E+03 2.444E+02 4.988E-08 4.645E+05 3 1.5000 h 0.000E+00 0.000E+00 1.409E+10 2.144E+13 2.094E+07 1.163E+04 2.301E+02 4.696E-08 4.266E+05 4 2.0000 h 0.000E+00 0.000E+00 1.827E+10 2.917E+13 2.849E+07 1.583E+04 3.438E+02 7.017E-08 5.194E+05 3 4.0000 h 0.000E+00 0.000E+00 3.290E+10 1.861E+14 1.818E+08 2.525E+04 9.251E+02 1.888E-07 4.809E+06 6 8.0000 h 0.000E+00 0.000E+00 2.139E+10 3.850E+14 3.761E+08 2.612E+04 1.398E+03 2.855E-07 1.749E+07 7 8.5000 h 0.000E+00 0.000E+00 2.030E+10 3.752E+13 0.000E+00 0.000E+00 3.981E+00 8.125E-10 4.282E+05 8 24.0000 h 0.000E+00 0.000E+00 3.996E+09 5.598E+14 0.000E+00 0.000E+00 5.330E-02 1.088E-11 5.081E+04 9 96.0000 h 0.000E+00 0.000E+00 2.102E+06 1.371E+14 0.000E+00 0.000E+00 1.060E-10 2.164E-20 6.895E+02 10 720.0000 h 0.000E+00 0.000E+00 8.024E-23 7.216E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.371E-06 I-135 TOTALS O.000E+00 1.374E+15 6.248E+08 2.444E+07 ALL NUCLIDES 0.000E+00 2.029E+09 0.000E+00 0.000E+00 6 STEP 10 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 4

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 HtC Case for dose for LPE 2.95 gpm [TC961016.DAT]

ENVIRONMENT--------- -------CONTR0L ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-PE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrea/hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr Kr-83m 0.5000 h 3.63E-08 7.26E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.78E-10 1.06E-09 0.00E+00 0.00E+00 0. ME+ 00 0.00E+00 1.0000 h 3.00E-08 6.00E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.62E-10 7.97E-10 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 1.5000 h 2.48E-08 4.96E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.46E-10 5.99E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 2.05E-08 4.09E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.74E-10 1.26E-09 0.00E+00 0.00E+00 0.00EF00 0.00E+00 4.0000 h 5.20E-08 2.60E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.13E-09 1. 7 6E- 09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.0000 h 3.54E-08 8.86E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.29E-09 7.60E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 6.32E-11 1.89E-12 0.00E+00 0.00E+00 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.42E-12 3.62E-16 0.00E+00 0.00E+00 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.93E-16 1.96E-33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.42E-33 0.00E+00 0.00E+00 0.00M+00 0.00E+00 0.00E+00 TOTALS 1.99E-07 0.00E+00 0.00E+00 9.04E-09 0.00E+00 0.00E+00 Kr-G5m 0.5000 h 3.2SE-04 6.50E-04 6.41E-04 1.28E-03 0.00E+00 0.00E+00 2.58E-06 1.00E-05 1.01E-04 3.95E-04 0.00E+00 0.00E+00 1.0000 h 3.00E-04 6.00E-04 5.93E-04 1.19E-03 0.00E+00 0.00E+00 4.60E-06 8.42E-06 1.81E-04 3.31E-04 0.00E+00 0.00E+00 1.5000 h 2.77E-04 5.55E-04 5.48E-04 1.10E-03 0.00E+00 0.00E+00 3.86E-06 7.07E-06 1.52E-04 2.78E-04 0.00E+00 0.00E+00 2.0000 h 2.56E-04 5.13E-04 5.06E-04 1.01E-03 0.00E+00 0.00E+00 6.02E-06 1.67E-05 2.37E-04 6.56E-04 0.00E+00 0.00E+00 4.0000 h 8.44E-04 4.22E-04 1.67E-03 8.33E-04 0.00E+00 0.00E+00 5.40E-05 3.49E-05 2.12E-03 1.37E-03 0.00E+00 0.00E+00 8.0000 h 1.06E-03 2.66E-04 2.10E-03 5.25E-04 0.00E+00 0.00E+00 1.33E-04 3.21E-05 5.21E-03 1.26E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.72E-06 8.92E-08 1.07E-04 3.50E-06 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.70E-07 5.51E-10 1.06E-05 2.17E-08 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.01E-09 3.03E-20 ?.96E-08 1.19E-18 0.03E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.69E-20 0.00E+00 1. 45E-18 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.07E-03 6.06E-03 0.00E+00 2.07E-04 8.12E-b? 0.00E+00 Kr-85 0.5000 h 2.46E-05 4.91E-05 3.43E-03 6.87E-03 0.00E+00 0.00E+00 2.00E-07 7.89E-07 5.57E-04 2.19E-03 0.00E+00 0.00E+00 1.0000 h 2.45E-05 4.90E-05 3.43E-03 6.86E-03 0.00E+00 0.00E+00 3.75E-07 7.14E-07 1.04E-03 1.99E-03 0.00E+00 0.00E+00 1.5000 h 2.45E-05 4.89E-05 3.42E-03 6.84E-03 0.00E+00 0.00E+00 3.40E-07 6.48E-07 9.46E-04 1.80E-03 0.00E+00 0.00E+00 2.0000 h 2.44E-05 4.88E-05 3.42E-03 6.83E-03 0.00E+00 0.00E+00 5.80E-07 1.65E-06 1.61E-03 4.60E-03 0.00E+00 0.00E+00 4.0000 h 9.73E-05 4.86E-05 1.36E-02 6.80E-03 0.00E+00 0.00E+00 6.53E-06 4.63E-06 1.82E-02 1.29E-02 0.00E+00 0.00E+00 8.0000 h 1.93E-04 4.81E-05 2.69E-02 6.73E-03 0.00E+00 0.00E+00 2.53E-05 7.54E-06 7.03E-02 2.10E-02 0.00E+00 0.00Et00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.47E-07 2. 2 6E-08 1.80E-03 6.29E-05 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.21E-07 1.54E-09 3.38E-04 4.28E-06 0.00E+00 0.00E+00 56.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.32E-09 5.81E-15 1.48E-05 1.62E-11 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.34E-14 0.00E+00 3.73E-11 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.88E-04 5.42E-02 0.00E+00 3.41E-05 9.48E-02 0.00E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 5

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPE 2.95 gpa [Tc961016.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DCSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE nrem mren/hr arem aren/hr mrem arem/hr arem arem/hr mrem mrem /hr arem aren/hr Kr-87 0.5000 h 9.27E-04 1.85E-03 2.20E-03 4.40E-03 0.00E+00 0.00E+00 6.92E-06 2.61E-05 3.27E-04 1.23E-03 0.00E+00 0.00E+00 1.0000 h 7.05E-04 1.41E-03 1.67E-03 3.34E-03 0.00E+00 0.00E+00 1.09E-05 1.80E-05 5.14E-04 6.50E-04 0.00E+00 0.00E+00 1.5000 h 5.36E-04 1.07E-03 1.27E-03 2.54E-03 0.00E+00 0.00E+00 7.52E-06 1.24E-05 3.55E-04 5.87E-04 0.00E+00 0.00E+00 t 2.0000 h 4.07E-04 8.14E-04 9.66E-04 1.93E-03 0.00E+00 0.00E+00 9.35E-06 2.42E-05 4.41E-04 1.14E-03 0.00E600 0.00E+00 4.0000 h 8.60E-04 4.30E-04 2.04E-03 1.02E-03 0.00E+00 0.00E+00 4.98E-05 2.53E-05 2.35E-03 1.19E-03 0.06E+00 0.00E+00 8.0000 h 3.83E-04 9.57E-05 9.08E-04 2.27E-04 0.00E+00 0.00E+00 4.66E-05 6.54E-06 2.20E-03 3.09E-04 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5. 3 6E-07 1.49E-08 2.53E-05 7.05E-07 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.08E-08 2.18E-13 9.81E-07 1.03E-11 0.00E+00 0.00E+00 06.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.82E-13 0.00E+00 8.58E-12 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.14E-36 0.00E+00 1.95E-34 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.82E-03 9.06E-03 0.00E+00 1.32E-04 6.22E-03 0.00E+00 Kr-88 0.5000 h 6.70E-03 1.34E-02 1.48E-03 2.95E-03 0.00E+00 0.00E+00 5.25E-05 2.03E-04 2.30E-04 8.89E-04 0.00E+00 0.00E+00 1.0000 h 5.92E-03 1.18E-02 1.30E-03 2.61E-03 0.00E+00 0.00E+00 9.09E-05 1.63E-04 3.98E-04 7.12E-04 0.00E+00 0.00E+00 1.5000 h 5.23E-03 1.05E-02 1.15E-03 2.30E-03 0.00E+00 0.00E+00 7.29E-05 1.31E-04 3.20E-04 5.72E-04 0.00E+00 0.00E+00 2.0000 h 4.52E-03 9.25E-03 1.02E-03 2.04E-03 0.00E+00 0.00E+00 1.00E-04 2.95E-04 4.73E-04 1.29E-03 0.00E+00 0.00E+00 4.0000 h 1.37E-02 6.85E-03 3.02E-03 1.51E-03 0.00E+00 0.00E+00 8.54E-04 5.23E-04 3.74E-03 2.29E-03 0.00E+00 0.00E+00 8.0000 h 1.34E-02 3.36E-03 2.96E-03 7.40E-04 0.00E+00 0.00E+00 1.65E-03 3.52E-04 7.21E-03 1.54E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.96E-05 9.35E-07 1.30E-04 4.10E-06 0.00E+00 0.00E+00 -

24.0000 h 0.00E+00 0.00E+00 0.0b2+00 0.00E+00 0.00E+00 0.00E+00 2.24E-06 1.45E-09 9.80E-06 6.34E-09 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.08E-09 1.28E-22 9.12E-09 5.60E-22 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.22E-22 0.00E+00 5.37E-22 0.00E+00 0.00E+00 0.00E+00 TOTALS 4.96E-02 1.09E-02 0.00E+00 2.86E-03 1.25E-02 0.00E+00 Kr-89 0.5000 h 3.08E-05 6.15E-05 3.34E-05 6.68E-05 0.00E+00 0.00E+00 6.57E-08 1.54E-07 1.42E-06 3.34E-06 0.00E+0C 0.00E+00 1.0000 h 4. 2 6E-08 8.52E-08 4.63E-08 9.25E-08 0.00E+00 0.00E+00 1.15E-08 1.94E-10 2.49E-07 4.19E-09 0.00E+00 0.00E+00 1.5000 h 5.90E-11 1.18E-10 6.41E-11 1.28E-10 0.00E+00 0.00E+00 1.45E-11 2.44E-13 3.13E-10 5.28E-12 0.00E+00 0.00F400 2.0000 h 8.17E-14 1.63E-13 8.87E-14 1.77E-13 0.00E+00 0.00E+00 1.84E-14 8.71E-16 3.99E-13 1.88E-14 0.00E+00 0.00E+00 4.0000 h 1.13E-16 5.66E-17 1.23E-16 6.15E-17 0.00E+00 0.00E+00 6.54E-17 1.98E-19 1.41E-15 4.29E-18 0.00E+00 0.00E+00 8.0000 h 4.16E-28 1.04E-28 4.52E-28 1.13E-28 0.00E+00 0.00E+00 1.48E-20 3.65E-31 3.20E-19 7-88E-30 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.47E-32 0.00E+00 3.18E-31 0.00E+00 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.14E-37 0.00E+00 2.46E-36 0.00E+00 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

, TOTALS 3.08E-05 3.35E-05 0.00E+00 7.73E-08 1.67E-06 0.00E+00 i

ERS-SFL-96-0 FRC 2.95 gpm Cases Attachment 4 Page U6 1 ),0

TRAILS -- Tranrport cf Radicactive Matcrial in Linear Systems, v2.0 FRC Case for dose for LPZ 2.95 gpa (TC961016.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DO3E DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem mrem /hr arem mrem /hr arem mrem /hr arem mren/hr mrem mrem /hr arem arem/hr Xa-131m 0.5000 h 9.12E-07 1.82E-06 1.01E-05 2.02E-05 0.00E+00 0.00E+00 7.43E-09 2.93E-08 1.64E-06 6.46E-06 0.00E+00 0.00E+00 1.0000 h 9.10E-07 1.82E-06 1.01E-05 2.02E-05 0.00E+00 0.00E+00 1.39E-08 2.65E-08 3.07E-06 5.84E-06 0.00E+00 0.00E+00 1.5000 h 9.07E-07 1.81E-06 1.01E-05 2.01E-05 0.00E+00 0.00E+00 1.26E-08 2.40E-08 2.78E-06 5.29E-06 0.00E+00 0.00E+00 2.0000 h 9.04E-07 1.81E-06 1.00E-05 2.00E-05 0.00E+00 0.00E+00 2.15E-08 6.12E-08 4.74E-06 1.35E-05 0.00E+00 0.00E+00 4.0000 h 3.59E-06 1.79E-06 3.98E-05 1.99E-05 0.00E+00 0.00E+00 2.41E-07 1.71E-07 5.31E-05 3.76E-05 0.00E+00 0.00E+00 8.0000 h 7.05E-06 1.76E-06 7.82E-05 1.95E-05 0.00E+00 0.00E+00 9.25E-07 2.75E-07 2.04E-04 6.06E-05 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2. 3 6E-0 8 8.24E-10 5.20E-06 1.82E-07 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.38E-09 5.39E-11 9.65E-07 1.19E-08 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.84E-10 1.71E-16 4.06E-08 3.77E-14 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.89E-16 0.00E+00 8.58E-14 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.43E-05 1.58E-04 0.00E+00 1.25E-06 2.75E-04 0.00E+00 Xa-133m 0.5000 h 9.06E-05 1.81E-04 6.02E-04 1.20E-03 0.00E+00 0.00E+00 7.36E-07 2.90E-06 9.74E-05 3.84E-04 0.00E+00 0.00E+00 1.0000 h 8.99E-05 1.80E-04 5.97E-04 1.19E-03 0.00E+00 0.00E+00 1.38E-06 2.61E-06 1.82E-04 3.45E-04 0.00E+00 0.00E+00 1.5000 h 8.91E-05 1.78E-04 5.92E-04 1.18E-03 0.00E+00 0.00E+00 1.24E-06 2.35E-06 1.64E-04 3.11E-04 0.00E+00 0.00E+00 2.0000 h 8.84E-05 1.77E-04 5.87E-04 1.17E-03 0.00E+00 0.00E+00 2.10E-06 5.96E-06 2.77E-04 7.89E-04 0.00E+00 0.00E+00 4.0000 h 3.46E-04 1.73E-04 2.30E-03 1.15E-03 0.00E+00 0.00E+00 2.31E-05 1.63E-05 3.06E-03 2.15E-03 0.00E+00 0.00E+00 8.0000 h 6.59E-04 1.65E-04 4.38E-03 1.09E-03 0.00E+00 0.00E+00 8.60E-05 2.52E-05 1.14E-02 3.33E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.16E-06 7.51E-08 2.86E-04 9.93E-06 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.80E-07 4.16E-09 5.03E-05 5.51E-07 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.34E-08 6.09E-15 1.77E-06 8.06E-13 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.31E-14 0.00E+00 1.73E-12 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.36E-03 9.06E-03 0.00E+00 1.17E-04 1.55E-02 0.00E+00 Xe-133 0.5000 h 9.14E-04 1.83E-03 1.73E-03 3.46E-03 0.00E+00 0.00E+00 7.44E-06 2.93E-05 2.80E-04 1.10E-03 0.00E+00 0.00E+00 1.0000 h 9.10E-04 1.82E-03 1.72E-03 3.44E-03 0.00E+00 0.00E+00 1.39E-05 2.65E-05 5.24E-04 9.96E-04 0.00E+00 0.00E+00 1.5000 h 9.06E-04 1.81E-03 1.71E-03 3.43E-03 0.00E+00 0.00E+00 1.26E-05 2.39E-05 4.74E-04 9.01E-04 0.00E+00 0.00E+00 2.0000 h 9.02E-04 1.80E-03 1.71E-03 3.41E-03 0.003+00 0.00E+00 2.14E-05 6.10E-05 8.06E-04 2.29E-03 0.00E+00 0.00E+00 4.0000 h 3.57E-03 1.78E-03 6.74E-03 3.37E-03 0.00E+00 0.00E+00 2.39E-04 1.69E-04 8.99E-03 6.36E-03 0.00E+00 0.00Et00 8.0000 h 6.94E-03 1.74E-03 1.31E-02 3.28E-03 0.00E+00 0.00E+00 9.09E-04 2.69E-04 3.42E-02 1.01E-02 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.31E-05 8.05E-07 8.69E-04 3.03E-05 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.22E-06 5.03E-08 1.59E-04 1.89E-06 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.69E-07 1.28E-13 6.35E-06 4.81E-12 0.00E+00 0.00E+00 723,0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.86E-13 0.00E+00 1.08E-11 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.41E-02 2.67E-02 0.00E+00 1.23E-03 4.63E-02 0.00E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 7 a

TRAILS -- hansport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPE 2.95 gpm [TC961016.DAT]

ENVIRONMENT-------- -

CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr Xe-135m 0.3000 h 2.53E-04 5.06E-04 8.04E-05 1.61E-04 0.00E+00 0.00E+00 1.38E-06 4.49E-06 8.76E-06 2.84E-05 0.00E+00 0.00E+00 1.0000 h 6.52E-05 1.30E-04 2.07E-05 4.15E-05 0.00E+00 0.00E+00 1.18E-06 1.05E-06 7.48E-06 6.65E-06 0.00E+00 0.00E+00 1.5000 h 1.68E-05 3.36E-05 5.35E-06 1.07E-05 0.OOE+00 0.00E+00 2.76E-07 2.46E-07 1.75E-06 1.56E-06 0.00E+00 0.00E+00 2.0000 h 4.33E-06 8.67E-06 1.38E-06 2.76E-06 0.00E+00 0.00E+00 9.72E-08 1.63E-07 6.15E-07 1.03E-06 0.00E+00 0.00E+00 4.0000 h 1.50E-06 7.49E-07 4.77E-07 2.38E-07 0.00E+00 0.00E+00 7.48E-08 1.23E-08 4.73E-07 7.80E-08 0.00E+00 0.00E+00 8.0000 h 6.65E-09 1.66E-09 2.11E-09 5.29E-10 0.00E+00 0.00E+00 4.28E-09 2.65E-11 2.71E-08 1.68E-10 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.85E-12 2.06E-14 1.17E-11 1.30E-13 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.14E-15 0.30E-34 4.51E-14 5.25E-33 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.73E-34 0.00E+00 1.09E-33 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.41E-04 1.08E-04 0.00E+00 3.02E-06 1.91E-05 0.OOE+00 Xe-135 0.5000 h 7.79E-04 1.56E-03 1.27E-03 2.54E-03 0.00E+00 0.00E+00 6.27E-06 2.46E-05 2.03E-04 7.97E-04 0.00E+00 0.00E+00 1.0000 h 7.49E-04 1.50E-03 1.22E-03 2.44E-03 0.00E+00 0.00E+00 1.15E-05 2.14E-05 3.72E-04 6.94E-04 0.00E+00 0.00E+00 1.5000 h 7.20E-04 1.44E-03 1.17E-03 2.35E-03 0.00E+00 0.00E+00 1.00E-05 1.87E-05 3.25E-04 6.06E-04 0.00E+00 0.00E+00 2.0000 h 6.92E-04 1.38E-03 1.13E-03 2.25E-03 0.00E+00 0.00E+00 1.63E-05 4.60E-05 5.30E-04 1.49E-03 0.00E+00 0.00E+00 4.0000 h 2.51E-03 1.25E-03 4.09E-03 2.04E-03 0.00E+00 0.00E+00 1.64E-04 1.11E-04 5.32E-03 3.61E-03 0.00E+00 0.00E+00 8.0000 h 3.96E-03 9.90E-04 6.46E-03 1.61E-03 0.00E+00 0.00E+00 5.05E-04 1.36E-04 1.64E-02 4.41E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.16E-05 3.93E-07 3.76E-04 1.27E-05 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.54E-06 8.22E-09 5.00E-05 2.67E-07 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.98E-08 1.30E-16 6.41E-07 4.21E-15 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.08E-16 0.00E+00 6.75E-15 0.00E+00 0.00E+00 0.00E+00 TOTALS 9.41E-03 1.53E-02 0.00E+00 7.27E-04 2.36E-02 0.00E+00 Xe-137 0.5000 h 5.65E-06 1.13E-05 8.56E-05 1.71E-04 0.00E+00 0.00E+00 1.41E-08 3.42E-08 4.24E-06 1.03E-05 0.00E+00 0.00E+00 1.0000 h 2.47E-08 4.95E-08 3.75E-07 7.49E-07 0.00E+00 0.00E+00 3.07E-09 1.36E-10 9.25E-07 4.09E-08 0.00E+00 0.00E+00 1.5000 h 1.08E-10 2.17E-10 1.64E-09 3.28E-09 0.00E+00 0.00E+00 1.22E-11 5.41E-13 3.67E-09 1.63E-10 0.00E+00 0.00E+00 2.0000 h 4.74E-13 9.49E-13 7.18E-12 1.44E-11 0.00E+00 0.00E+00 5.02E-14 6.10E-15 1.51E-11 1.84E-12 0.00E+00 0.00E+00 4.0000 h 4.09E-15 1.04E-15 3.16E-14 1.58E-14 0.00E+00 0.00E+00 5.58E-16 4.41E-18 1.68E-13 1.33E-15 0.00E+00 0.00E+00 8.0000 h 7.66E-25 1.92E-25 1.16E-23 2.90E-24 0.00E+00 0.00E+00 3.97E-19 8.10E-28 1.20E-16 2.44E-25 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.60E-29 1.07E-32 1.09E-26 3.21E-30 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.66E-34 0.00E+00 2.91E-31 0.00E+00 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.03E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 5.68E-06 8.59E-05 0.00E+00 1.72E-08 5.17E-06 0.00E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 8

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPZ 2.95 gym [TC961016.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr Xe-138 0.5000 h 4.37E-04 8.73E-04 3.25E-04 6.50E-04 0.00E+00 4.00E+00 2.32E-06 7.42E-06 3.43E-05 1.10E-04 0.00E+00 0.00E+00 1.0000 h 1.00E-04 2.00E-04 7.44E-05 1.49E-04 0.00E+00 'O.00E+00 1.86E-06 1.54E-06 2. 7 6E-05 2.28E-05 0.00E+00 0.00E+00 1.5000 h 2.29E-05 4.59E-05 1.71E-05 3.41E-05 0.00E+00 0.00E+00 3.88E-07 3.21E-07 5.74E-06 4.75E-06 0.00E+00 0.00E+00 2.0000 h 5.25E-06 1.05E-05 3.91E-06 7.82E-06 0.00E+00 0.00E+00 1.19E-07 1.89E-07 1.76E-06 2.79E-06 0.00E+00 0.00E+00 4.0000 h 1.56E-06 7.79E-07 1.16E-06 5.79E-07 0.00E+00 0.00E+00 7.84E-08 1.18E-08 1.16E-06 1.74E-07 0.00E+00 0.00E+00 8.0000 h 4.31E-09 1.08E-09 3.20E-09 8.01E-10 0.00E+00 0.00E+00 3.75E-09 1.59E-11 5.56E-08 2.35E-10 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.09E-12 1.09E-14 1.61E-11 1.62E-13 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.51E-15 0.00E+00 5.20E-14 0.00E+00 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.20E-36 0.00E+00 3.26E-35 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+0G 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 5.66E-04 4.2 C-04 0.00E+00 4.77E-06 7.06E-05 0.00E+00 I-131 0.5000 h 1.02E-02 2.03E-02 5.35E-03 1.07E-02 6.28E+01 1.26E+02 8.26E-05 3.26E-04 8.67E-04 3.42E-03 1.02E+01 4.01E+01 1.0000 h 2.85E-02 5.70E-02 1.50E-02 3.01E-02 1.76E+02 3.53E+02 1.58E-04 3.06E-04 1.66E-03 3.21E-03 1.94E+01 3.77E+01 1.5000 h 4.68E-02 9.36E-02 2.47E-02 4.94E-02 2.90E+02 5.79E+02 1.51E-04 3.00E-04 1.59E-03 3.15E-03 1.87E+01 3.69E+01 2.0000 h 6.50E-02 1.30E-01 3.43E-02 6.86E-02 4.02E+02 8.05E+02 1.88E-04 4.49E-04 1.97E-03 4.71E-03 2.32E+01 5.53E+01 4.0000 h 4.41E-01 2.21E-01 2.33E-b3 1.16E-01 2.73E+03 1.37E+03 1.84E-03 1.32E-03 1.93E-02 1.39E-02 2.27E+02 1.63E+02 8.0000 h 1.15E+00 2.89E-01 6.09E-01 1.52E-01 7.15E+03 1.79E+03 8.49E-03 2.70E-03 8.91E-02 2.83E-02 1.04E+03 3.32E+02 8.5000 h 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.32E-04 8.08E-06 2.43E-03 8.48E-05 2.85E+01 9.95E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.27E-05 5.20E-07 4.49E-04 5.46E-06 5. 2 6E+ 00 6.40E-02 96.0000 h 0.00E+00 0.00E+0) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.76E-06 1.52E-12 1.85E-05 1.59E-11 2.17E-01 1.87E-07 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.43E-12 0.00E+00 3.60E-11 0.00E+00 4.22E-07 0.00E+00 TOTALS 1.75E+00 9.21E-01 1.08E+04 1.12E-02 1.1'JE-01 1.38E+03 I-132 0.5000 h 1.03E-01 2.06E-01 3.05E-02 6.10E-02 6.11E-01 1.22E+00 8.01E-04 3.08E-03 4.71E-03 1.81E-02 9.42E-02 3.63E-01 1.0000 h 2.86E-01 5.72E-01 8.46E-02 1.69E-01 1.69E+00 3.39E+00 1.39E-03 2.51E-03 8.19E-03 1.48E-02 1.64E-01 2.96E-01 1.5000 h 4.43E-01 8.87E-01 1.31E-01 2.62E-01 2.62E+00 5.24E+00 1.17E-03 2.18E-03 6.87E-03 1.28E-02 1.38E-01 2.56E-01 2.0000 h 5.78E-01 1.16E+00 1.71E-01 3.42E-01 3.42E+00 6.84E+00 1.35E-03 3.18E-03 7.94E-03 1.87E-02 1.59E-01 3.74E-01 4.0000 h 3.32E+00 1.66E+00 9.81E-01 4.90E-01 1.96E+01 9.82E+00 1.10E-02 7.15E-03 6.49E-02 4.20E-02 1.30E+00 8.41E-01 8.0000 h 4.56E+00 1.14E+00 1.35E+00 3.37E-01 2.70E+01 6.75E+00 2.66E-02 6.39E-03 1.56E-01 3.76E-02 3.13E+00 7.53E-01 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.35E-04 1.65E-05 3.15E-03 9.70E-05 6.30E-02 1.94E-03 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.47E-05 1.05E-08 2.04E-04 6.18E-08 4.09E-03 1.24E-06 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E-08 1.50E-23 7.81E-08 8.81E-23 1.56E-06 1.76E-21 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.26E-23 0.00T*00 7.42E-23 0.00E+00 1.49E-21 0.00E+00 TOTALS 9.29E+00 2.75E+00 5.50E+01 4.29E-02 2.52E-01 5.05E+00 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 10 9

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPZ 2.95 gpsa [TC961016.DATI

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INNAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem arem/hr arem nren/hr mrem mrem /hr mrem area /hr arem arem/hr mrem arem/hr I-133 0.5000 h 3.57E-02 7.13E-02 3.31E-02 6.62E-02 2.29E+01 4.5BE+01 2.89E-04 1.14E-03 5.34E-03 2.10E-02 3.69E+00 1.45E+01 1.0000 h 1.01E-01 2.03E-01 9.422-02 1.88E-01 6.51E+01 1.30E+02 5.47E-04 1.05E-03 1.01E-02 1.95E-02 6.99E+00 1.35E+01 1.5000 h 1.66E-01 3.32E-01 1.54E-01 3.08E-01 1.07E+02 2.13E+02 5.18E-04 1.02E-03 9.58E-03 1.89E-02 6.63E+00 1.31E+01 2.0000 h 2.29E-01 4.59E-01 2.13E-01 4.26E-01 1.47E+02 2.95E+02 6.41E-04 1.53E-03 1.19E-02 2.83E-02 8.20E+00 1.96E+01 4.0000 h 1.53E+00 7.64E-01 1.42E+00 7.09E-01 9.82E+02 4.91E+02 6.21E-03 4.41E-03 1.15E-01 8.15E-02 7.93E+01 5.64E+01 8.0000 h 3.73E+00 9.32E-01 3.46E+00 8.65E-01 2.39E+03 5.99E+02 2. 67E -02 8.24E-03 4.93E-01 1.52E-01 3.41E+02 1.05E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.05E-04 2.43E-05 1.30E-02 4.49E-04 9.01E+00 3.11E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.13E-04 9.86E-07 2.08E-03 1.82E-05 1.44E+00 1.26E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.867-06 3.39E-13 5.29E-05 6.26E-12 3.66E-02 4.33E-09 720.0000 h 0.00E+90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.55E-13 0.00E+00 1.21E-11 0.00E+00 8.37E-09 0.00E+00 TOTALS 5.79E+00 5.37E+00 2.72E+03 3.57E-02 6.60E-01 4.56E+02 I-134 0.5000 h 1.59E-01 3.18E-01 5.23E-02 1.05E-01 1.36E-01 2.71E-01 1.14E-03 4.24E-03 7.48E-03 2.77E-02 1.94E-02 7.18E-02 1.0000 h 4.03E-01 8.07E-01 1.33E-01 2.65E-01 3.43E-01 6.87E-01 1.71E-03 2.74E-03 1.12E-02 1.79E-02 2.90E-02 4.64E-02 1.5000 h 5.68E-01 1.14E+00 1.87E-01 3.73E-01 4.83E-01 9.66E-01 1.15E-03 1.93E-03 7.52E-03 1.26E-02 1.95E-02 3.27E-02 2.0000 h 6.78E-01 1.36E+00 2.23E-01 4.46E-01 5.77E-01 1.15E+00 1.19E-03 2.74E-03 7.75E-03 1.79E-02 2.01E-02 4.64E-02 4.0000 h 3.25E+00 1.62E+00 1.07E+00 5.34E-01 2.77E+00 1.38E+00 7.77E-03 4.47E-03 5.08E-02 2.92E-02 1.32E-01 7.57E-02 8.0000 h 2.10E+00 5.25E-01 6.91E-01 1.73E-01 1.79E+00 4.47E-01 8.91E-03 1.57E-03 5.83E-02 1.03E-02 1.51E-01 2.67E-02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.27E-04 3.18E-06 8.28E-04 2.08E-05 2.15E-03 5.39E-05 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.30E-06 1.03E-12 2.16E-05 6.73E-12 5.59E-05 1.74E-11 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.41E-13 0.00E+00 4.19E-12 0.00E+00 1.09E-11 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 7.16E+00 2.35E+00 6.09E+00 2.20E-02 1.44E-01 3.73E-01 I-135 0.5000 h 8.51E-02 1.70E-01 2.57E-02 5.15E-02 3.49E+00 6.99E+00 6.81E-04 2.66E-03 4.10E-03 1.60E-02 5.56E-01 2.18E+00 1.0000 h 2.42E-01 4.85E-01 7.33E-02 1.47E-01 9.96E+00 1.99E+01 1.26E-03 2.39E-03 7.59E-03 1.44E-02 1.03E+00 1.95E+00 1.5000 h 3.92E-01 7.83E-01 1.18E-01 2.37E-01 1.61E+01 3.22E+01 1.16E-03 2.25E-03 6.97E-03 1.35E-02 9.46E-01 1.84E+00 2.0000 h 5.33E-01 1.07E+00 1.61E-01 3.22E-01 2.19E+01 4.38E+01 1.41E-03 3.36E-03 8.48E-03 2.02E-02 1.15E+00 2.74E+00 4.0000 h 3.40E+00 1.70E+00 1.03E+00 5.14E-01 1.40E+02 6.98E+01 1.30E-02 9.03E-03 7.85E-02 5.44E-02 1.07E+01 7.38Et00 8.0000 h 7.03E+00 1.76E+00 2.13E+00 5.32E-01 2.89E+02 7.22E+01 4.75E-02 1.37E-02 2.86E-01 8.22E-02 3.88E+01 1.12E+01 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.16E-03 3.89E-05 6.99E-03 2.34E-04 9.49E-01 3.18E-02 24.0000 h 0.00E+00 0.00E+00 0.00E+03 0.00E+00 0.00E+00 0.00E+00 1.38E-04 5.21E-07 8.30E-04 3.13E-06 1.13E-01 4.25E-04 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.12E-06 1.04E-15 6. 7 6E-06 6.23E-15 9.17E-04 8.46E-13 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.49E-15 0.00E+00 8. 9 EE-15 0.00E+00 1.22E-12 0.00E+00 TOTALS 1.17E+01 3.53E+00 4.80E+02 6.63E-02 3.99E-01 5.42E+01 ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page 110

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ERC Case for dose for LPE 2.95 gym [TC961016.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE .

arem aren/hr arem aren/hr mrem arem/hr arem mrem /hr arem arem/hr arem aren/hr ,

ALL NUCLIDES 0.5000 h 4.04E-01 8.08E-01 1.59E-01 3.18E-01 9.00ES01 1.80E+02 3.08E-03 1.17E-02 2.43E-02 9.34E-02 1.45E+01 5.72E+01 1.0000 h 1.07E+00 2.14E+00 4.10E-01 8.21E-01 2.54E+02 5.07E+02 5.20E-03 9.24E-03 4.20E-02 7.57E-02 2. 7 6E+ 01 5.34E+01 1.5000 h 1.62E+00 3.25E+00 6.25E-01 1.25E+00 4.15E+02 8.31E+02 4.25E-03 7.87E-03 3.53E-02 6.60E-02 2.64E+01 5.21E+01 2.0000 h 2.09E+00 4.18E+00 8.12E-01 1.62E+00 5.76E+02 1.15E+03 4.94E-03 1.17E-02 4.24E-02 1.02E-01 3.27E+01 7.81E+01 4.0000 h 1.20E+01 5.98E+00 4.76E+00 2.38E+00 3.87E+03 1.94E+03 4.13E-02 2.73E-02 3.72E-01 2.51E-01 3.18E+02 2.27E+02 ;

8.0000 h 1.86E+01 4.65E+00 8.29E+00 2.07E+00 9.86E+03 2.46E+03 1.21E-01 3.34E-02 1.23E+00 3.53E-01 1.43E+03 4.50E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.83E-03 9.33E-05 3.00E-02 1.01E-03 3.85E+01 1.34E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.40E-04 2.10E-06 4.21E-03 3.39E-05 6.82E+00 7.71E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.97E-06 2.00E-12 1.02E-04 4.40E-11 2.55E-01 1.91E-07 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+30 0.00E+00 4.40E-12 0.00E+00 9.8CE-11 0.00E+00 4.31E-07 0.00E+00 TOTALS 3.58E+01 1.51E+01 1.51E+04 1.83E-01 1.78E+00 1.89E+03 l

ERS-SFL-96-010 FRC 2.95 gpm Cases Attachment 4 Page i11

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITP Case for LPE dose [TC961007.DAT]

CadP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

INITIAL: 0.000E+00 I-131 7.730E+09 I-131 uci 0.000E+00 I-131 0.000E+00 I-132 2.700E+09 I-132 0.000E+00 I-132 0.000E+00 I-133 1.210E+10 I-133 0.000E+00 I-133 0.000E+00 I-134 1.690E+09 I-134 0.000E+00 I-134 0.000E+00 I-135 6.490E+09 I-135 0.000E+00 I-135 ACT MULT (to uCi) : 1.000E+00 1.000E+00 1.000E+00 ERS-SFL-96-010 ITP case for CR/LPZ Dose Attachment 4 Page } } 2

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITP Case for LPE dose [TC961007.DAT]

====_. ______ __

REMOVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfm NUC Grp 1 REL ER: 0.000E+DO 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

___ == - - - - - - -

= - - - - - - - .-=--- . -------

MULTIPLIERS - >

STEP TIME XPR XREM XRF XPR XREM .7.a XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000EF00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E&00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.000E-02 0.00CL+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.000E-02 0.000E+00 70.0 70.0 1.00 5 1.440E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.000E-02 0.000E+00 70.0 70.0 1.00 6 2.880E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.000E-02 0.000E+00 70.0 70.0 1.00 7 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 0 8.640E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 9 3.456E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 10 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0002+00 0.000E+00 50.0 50.0 0.000E+00

---. CONTROL ROOM -------- ---- ENVIRONMENT ---

X/Q Breathing occupancf X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS - >

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 7.07 1.00 2 3.600E+03 2.72 1.00 1.00 7.07 1.00 3 5.400E+03 2.72 1.00 1.00 7.07 1.00 4 7.200E+03 2.72 1.00 1.00 7.07 1.00 5 1.440E+04 2.72 1.00 1.00 7.07 1.00 6 2.880E+04 2.72 1.00 1.00 7.07 1.00 7 3.060E+04 1.43 1.00 1.00 7.07 1.00 8 8.640E+04 1.43 1.00 1.00 7.07 1.00 9 3.456E+05 1.10 1.00 0.600 7.07 1.00 10 2.592E+06 0.630 1.00 0.400 7.07 1.00 ERS-SFL-96-010 ITP case for CR/LPZ Dose Attachment 4 Page 113

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 ITP Case for LPE dose tTC961007.DAT]

not used intact S/G AVERAGE --

CONTROL ROOM- - - - -

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD CTEP TIME uCi uCi-sec uC1 uCi-sec uCi uC1/sec uCi uCi/cc uCi-sec I-131 INITIAL 0.000E+00 7.730E+09 0.000E+00 I-131 TOTALS 0.000E+00 7.162E+15 2.048E+06 8.028E+05 I-132 INITIAL 0.000E+00 2.700E+09 0.000E+00 I-132 TOTALS 0.000E+00 3.225E+13 5.934E+05 1.350E+05 I-133 INITIAL 0.000E+00 1.210E+10 0.000E+00 I-133 TOTALS 0.000E+00 1.307E+15 3.137E+06 1.151E+06 I-134 INITIAL 0.000E+00 1.690E+09 0.000E+00 I-134 TOTALS 0.000E+00 7.693E+12 2.925E+05 3.988E+04 I-135 INITIAL 0.000E+00 6.490E+09 0.000E+00 I-135 TOTALS 0.000E+00 2.227E+14 1.602E+06 5.075E+05 ALL NUCLIDES 0.000E+00 5.819E+08 0.000E+00 0.000E+00 6 STEP 10 ERS-SFL-96-010 ITP case for CR/LPZ Dose Attachment 4 Page 1 ] d

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ITP Case for LPE dose [TC961007.DAT]

ENVIRONNENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem arem/hr arem mresa/hr mrem arem/hr mrem aren/hr arem aremi/hr I-131 TOTALS 8.77E-03 4.63E-03 5.43E+01 4.99E-04 5.24E-03 6.14E+01 I-132 TOTALS 1.58E-02 4.68E-03 9.37E-02 5.23E-04 3.08E-03 6.16E-02 I-133 TOTALS 2.16E-02 2.00E-02 1.39E+01 1.15E-03 2.12E-02 1.47E+01 I-134 TOTALS 9.02E-03 2.96E-03 7.68E-03 1.78E-04 1.17E-03 3.02E-03 I-135 TOTALS 3.00E-02 9.06E-03 1.23E+00 1.38E-03 8.29E-03 1.13E+00 ALL NUCLIDES 0.5000 h 4.27E-02 8.54E-02 2.03E-G2 4.07E-02 3.26E+01 6.53E+01 3.37E-04 1.31E-03 3.22E-03 1.26E-02 5.28E+00 2.08E+01 1.0000 h 3.88E-02 7.77E-02 1.90E-02 3.80E-02 3.24E+01 6.49E+01 5.95E-04 1.08E-03 5.80E-03 1.07E-02 9.87E+00 1.87E+01 1.5000 h 3.58E-04 7.16E-04 1.80E-04 3.59E-04 3.23E-01 6.45E-01 4.91E-04 8.89E-04 4.90E-03 8.98E-03 8.79E+00 1.65E+01 2.0000 h 3.33E-04 6.66E-04 1.71E-04 3.42E-04 3.21E-01 6.41E-01 4.05E-Od 7.36E-04 4.13E-03 7.60E-03 7.75E+00 1.45E+01 4.0000 h 1.15E-03 5.76E-04 6.19E-04 3.09E-04 1.27E+00 6.33E-01 1.05E-03 3.68E-04 1.12E-02 4.06E-03 2.29E+01 8.81E+00 8.0000 h 1.78E-03 4.44E-04 1.03E-03 2.58E-04 2.45E+00 6.13E-01 8.32E-04 1.06E-04 9.56E-03 1.28E-03 2.24E+01 3.30E+00 Q.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.06E-06 3.09E-07 1.09E-04 3. 7 6E-06 2.83E-01 9.85E-03 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E-06 1.08E-08 1.70E-05 1.49E-07 5.08E-02 5.90E-04 C6.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.25E-08 1.42E-14 4.49E-07 1.63E-13 1.97E-03 1.55E-09 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.14E-14 0.00E+00 3.58E-13 0.0CE+00 3.49E-09 0.00E+00 TOTALS 8.52E-02 4.14E-02 6.95E+01 3.73E-03 3.90E-02 7.73E+01 ERS-SFL-96-010 ITP case for CR/LPZ Dose Attachment 4 Page 115

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gym LPE dose [TC961018.DAT)

COMP: not used COMP: Faulted S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.

_ =- --

INITIAL: 0.000E+00 Kr-83m 2.160E+07 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 1.050E+08 Kr-85m 0.000E+00 Kr-8'%

0.000E+00 Kr-85 5.560E+08 Kr-85 0.000E+00 K.-85 0.000E+00 Kr-87 6.020E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.600E+08 14 '88 0.000E+00 K1-88 0.000E+00 Kr-89 5.060E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 5.410E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 1.550E+0B Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 1.320E+09 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 5.460E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 1.610E+08 Xe-135 0.000E+00 Xe-135 0.000E+00 Ze-137 8.190E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 3.380E+07 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 7.730E+09 I-131 0.000E+00 I-131 0.000E+00 I-132 2.700E+09 I-132 0.000E+00 I-132 0.000E+00 I-133 1.210E+10 I-133 0.000E+00 I-133 O.000E+00 I-134 1.690E+09 I-134 0.000E+00 I-134 0.000E+00 I-135 6.490E+09 I-135 0.000E+00 I-135 ACT MULT (to uci) : 1.000E+00 1.000E+00 1.000E+00

=-__-- - - - . ___ - -

_-_------ ___=

j ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page1 ] G

T' TAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpu LPE dose [TC961018.DAT]

_ - _ - - - - - - ___ ------------- . - _ - - - -- ---.- _ ._- :-==___-- _.---

REMOVAL: 0.000E+00 1/sec 9.769E-07 1/sec 1.000E+01 cfm NUC Grp 1 REL R: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp'2 REL m: 0.000E+00 0.000E+00 INTAFE REDUCT: 9.360E-01 NUC Grp 3 REL m: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

- - . _ . _ -=_ ---- - - - - - . . _ . . . . . - - _ _ _ . - - _ _ - _ - _ - - - . . - - - - - - - - - -

MULTIPLIERS->

STEP TDE XPR XREM XRF XPR XREM XRF XPR XREM XRF 1 1.800E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 50.0 50.0 0.000E+00 2 3.600E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 3 5.400E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 1.00 70.0 0.000E+00 4 7.200E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 5 1.440E+04 0.000X+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 6 2.880E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.00 0.000E+00 70.0 70.0 1.00 7 3.060E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.350E+03 3.350E+03 0.000E+00 8 8.640E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 9 3.456E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00 20 2.592E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 50.0 50.0 0.000E+00

CONTROL ROOM ---- =

ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathity s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS->

STEP TIME,s 1 1.800E+03 2.72 1.00 1.00 7.07 1.00 2 3.600E+03 2.72 1.00 1.00 7.07 1.00 3 5.400E+03 2.72 1.00 1.00 7.07 1.00 4 7.200E+03 2.72 1.00 1.00 7.07 1.00 5 1.440E+04 2.72 1.00 1.00 7.07 1.00 6 2.880E+04 2.72 1.00 1.00 7.07 1.00 7 3.060E+04 1.43 1.00 1.00 7.07 1.00 8 8.640E+04 1.43 1.00 1.00 7.07 1.00 9 3.456E+05 1.10 1.00 0.600 7.07 1.00 10 2.592E+06 0.630 1.00 0.400 7.07 1.00 ERS-SFL-96-01 FRP 2.95 gpm Cases Attachment 4 Page 11

{

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm LPZ dose [TC961018.DAT]

not used Faulted S/G AVERAGE ----------CONTROL ROOH-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD LTEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 2.160E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.784E+07 3.539E+10 3.457E+04 1.921E+01 1.939E+00 3.958E-10 1.825E+03 2 1.0000 h 0.000E+00 0.000E+00 1.474E+07 2.923E+10 2.856E+04 1.586E+01 1.453E+00 2.965E-10 3.030E+03 3 1.5000 h 0.000E+00 0.000E+00 1.217E+07 2.415E+10 2.359E+04 1.310E+01 1.091E+00 2.226E-10 2.272E+03 4 2.0000 h 0.000E+00 0.000E+00 1.006E+07 1.995E+10 1.948E+04 1.082E+01 2.304E+00 4.704E-10 3.112E+03 5 4.0000 h 0.000E+00 0.000E+00 4.681Et06 5.061E+10 4.944E+04 6.867E+00 3.208E+00 6.548E-10 2.050E+04 6 8.0000 h 0.000E+00 0.000E+00 1. 015E+ 0 6 3. 453E+10 3.373E+04 2.343E+00 1.385E+00 2.827E-10 2.812E+04 7 8.5000 h 0.000E+00 0.000E+00 8.396E+05 1.664E+09 0.000E+00 0.000E+00 3.437E-03 7.016E-13 4.145E+02 8 24.0000 h 0.000E+00 0.000E+00 2.368E+03 7.957E+09 0.000E+00 0.000E+00 6.596E-07 1.346E-16 2.241E+01 9 96.0000 h 0.000E+00 0.000E+00 3.397E-09 2.251E+07 0.000E+00 0.000E+00 3.576E-24 7.301E-34 4.300E-03 10 720.0000 h 0.000E+00 0.C00E+00 0.000E+00 3.228E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.332E-20 Kr-83m TOTALS 0.000E+00 2.035E+11 1.894E+05 5.929E+04 Kr-85m INITIAL 0.000E+00 1.050E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 9.701E+07 1.817E+11 1.775E+05 9.862E+01 1.051E+01 2.145E-09 9.716E+03 2 1.0000 h 0.000E+00 0.000E+00 8.963E+07 1.679E+11 1.640E+05 9.112E+01 8.805E+00 1.797E-09 1.733E+04 3 1.5000 h 0.000E+00 0.000E+00 8.281E+07 1.551E+11 1.515E+05 8.418E+01 7.394E+00 1.509E-09 1.454E+04 4 2.0000 h 0.000E+00 0.000E+00 7.651E+07 1.433E+11 1.400E+05 7.778E+01 1.747E+01 3.566E-09 2.268E+04 5 4.0000 h 0.000E+00 0.000E+00 5.576E+07 4.722E+11 4.613E+05 6.407E+01 3.649E+01 7.448E-09 2.032E+05 6 8.0000 h 0.000E+00 0.000E+00 2.961E+07 5.949E+11 5.811E+05 4.036E+01 3.359E+01 6.856E-09 4.992E+05 7 8.5000 h 0.000E+00 0.000E+00 2.740E+07 5.129E+10 0.000E+00 0.000E+00 9.325E-02 1.903E-11 1.024E+04 8 24.0000 h 0.000E+00 0.000E+00 2.491E+06 5.797E+11 0.000E+00 0.000E+00 5.765E-04 1.177E-13 1.017E+03 9 96.0000 h 0.000E+00 0.000E+00 3.617E+01 5.795E+10 0.000E+00 0.000E+00 3.165E-14 6.461E-24 6.325E+00 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 8.415E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.473E-10 Kr-85m TOTALS 0.000E+00 2.404E+12 1.676E+06 7.780E+05 Kr-85 INITIAL 0.000E+00 5.560E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.550E+08 9.999E+11 9.768E+05 5.427E+02 6.005E+01 1.226E-08 5.483E+04 2 1.0000 h 0.000E+00 0.000E+00 5.540E+08 9.982E+11 9.751E+05 5.417E+02 5.437E+01 1.110E-08 1.029E+05 3 1.5000 h 0.000E+00 0.000E+00 5.531E+08 9.964E+11 9.733E+05 5.407E+02 4.933E+01 1.007E-08 9.324E+04 4 2.0000 h 0.000E+00 0.000E+00 5.521E+08 9.946E+11 9.716E+05 5.398E+02 1.259E+02 2.570E-08 1.591E+05 5 4.0000 h 0.000E+00 0.000E+00 5.482E+08 3.961E+12 3.869E+06 5.374E+02 3.529E+02 7.204E-08 1.790E+06 6 8.0000 h 0.000E+00 0.000E+00 5.405E+08 7.839E+12 7.658E+06 5.318E+02 5.739E+02 1.171E-07 6.927E+06 7 8.5000 h 0.000E+00 0.000E+00 5.405E+08 9.730E+11 0.000E+00 0.000E+00 1.721E+00 3.514E-10 1.773E+05 0 24.0000 h 0.000E+00 0.000E+00 5.405E+08 3.016E+13 0.000E+00 0.000E+00 1.171E-01 2.390E-11 3.331E+04 9 96.0000 h 0.000E+00 0.000E+00 5.402E+08 1.401E+14 0.000E+00 0.000E+00 4.425E-07 9.032E-17 2.431E+03 10 720.0000 h 0.000E+00 0.000E+00 5.377E+08 1.211E+15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.186E-03 Kr-85 TOTALS 0.000E+00 1.398E+15 1.542E+07 9.339E+06 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 1 ] 8

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 D P Case for 2.95 gpm LPZ dose [TC961018.DAT]

not used Faulted S/G AVERAGE = - -

--CONTROL ROOH-- --- -

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-see uCi uCi/sec uCi uCi/cc uCi-sec Kr-87 INITIAL 0.000E+00 6.020E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 4.576E+07 9.477E+10 9.258E+04 5.143E+01 4.992E+00 1.019E-09 4.761E+03 2 1.0000 h 0.000E+00 0.000E+00 3.47BE+07 7.203E+10 7.037E+04 3.909E+01 3.441E+00 7.024E-10 7.498E+03 3 1.5000 h 0.000E+00 0.000E+00 2.644E+07 5.475E+10 5.349E+04 2.972E+01 2.377E+00 4.853E-10 5.174E+03 4 2.0000 h 0.000E+00 0.000E+00 2.010E+07 4.162E+10 4.066E+04 2.259E+01 4.623E+00 9.437E-10 6.433E+03 5 4.0000 h 0.000E+00 0.000E+00 6.708E+06 8.785E+10 8.582E+04 1.192E+01 4.838E+00 9.876E-10 3.425E+04 6 8.0000 h 0.000E+00 0.000E+00 7.475E+05 3.911E+10 3.821E+04 2.653E+00 1.250E+00 2.551E-10 3.208E+04 7 8.5000 h 0.000E+00 0.000E+00 5.692E+05 1.178E+09 0.000E+00 0.000E+00 2.855E-03 5.828E-13 3.691E+02 8 24.0000 h 0.000E+00 0.000E+00 1.219E+02 3.758E+09 0.000E+00 0.000E+00 4.160E-08 8.491E-18 1.430E+01 9 96.0000 h 0.000E+00 0.000E+00 1.101E-15 8.051E+05 0.000E+00 0.000E+00 1.421E-30 0.000E+00 2.084E-04 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 7.274E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.119E-27 Kr-87 TOTALS 0.000E+00 3.951E+11 3.811E+05 9.059E+04 Kr-88 INITIAL 0.000E+00 1.600E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.414E+0e 2.709E+11 2.646E+05 1.470E+02 1.533E+01 3.129E-09 1.428E+04 2 1.0000 h 0.000E+00 0.000E+00 1.249E+08 2.393E+11 2.338E+05 1.299E+02 1.228E+01 2.507E-09 2.474E+04 3 1.5000 h 0.000E+00 0.000E+00 1.104E+08 2.115E+11 2.066E+05 1.148E+02 9.865E+00 2.014E-09 1.985E+04 4 2.0000 h 0.000E+00 0.000E+00 9.752E+07 1.869E+11 1.825E+05 1.014E+02 2.229E+01 4.550E-09 2.939E+04 5 4.0000 h 0.000E+00 0.000E+00 5.943E+07 5.537E+11 5.409E+05 7.513E+01 3.949E+01 8.060E-09 2.323E+05 6 8.0000 h 0.000E+00 0.000E+00 2.208E+07 5.432E+11 5.306E+05 3.685E+01 2.662E+01 5.435E-09 4.477E+05 7 8.5000 h 0.000E+00 0.000E+00 1.954E+07 3.741E+10 0.000E+00 0.000E+00 7.069E-02 1.443E-11 8.058E+03 8 24.0000 h 0.000E+00 0.000E+00 4.446E+05 2.817E+11 0.000E+00 0.000E+00 1.094E-04 2.234E-14 6.086E+02 9 96.0000 h 0.000E+00 0.000E+00 1.038E-02 6.558E+09 0.000E+00 0.000E+00 9.659E-18 1.972E-27 9.435E-01 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 1.531E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.330E-14 Kr-88 TOTALS 0.000E+00 2.331E+12 1.959E+06 7.769E+05 Kr-89 INITIAL 0.000E+00 5.060E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.007E+03 1.382E+09 1.350E+03 7.499E-01 1.298E-02 2.649E-12 1.989E+01 2 1.0000 h 0.000E+00 0.000E+00 9.703E+00 1.914E+06 1.869E+00 1.038E-03 1.630E-05 3.328E-15 3.482E+00 3 1.5000 h 0.000E+00 0.000E+00 1.344E-02 2.650E+03 2.589E-03 1.438E-06 2.053E-08 4.190E-18 4.374E-03 4 2.0000 h 0.000E+00 0.000E+00 1.861E-05 3.670E+00 3.585E-06 1.991E-09 7.323E-11 1.495E-20 5.580E-06 5 4.0000 h 0.000E+00 0.000E+00 6.843E-17 5.089E-03 4.971E-09 6.904E-13 1.666E-14 3.401E-24 1.978E-08 6 8.0000 h 0.000E+00 0.000E+00 0.000E+00 1.871E-14 1.828E-20 1.269E-24 3.064E-26 6.254E-36 4.475E-12 7 8.5000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.275E-31 0.000E+00 4.451E-24 8 24.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.442E-29 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr-C9 TOTALS 0.000E+00 1.384E+09 1.352E+03 2.337E+01 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 1 ] 9

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpa LPE doJe tTC961018.DAT]

not used Faulted S/G AVERAGE CONTROL ROOM---

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xe-131m INITIAL 0.000E+00 5.410E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 5.394E+06 9.724E+09 9.499E+03 5.277E+00 5.836E-01 1.191E-10 5.330E+02 2 1.0000 h 0.000E+00 0.000E+r2 5.378E+06 9.695E+09 9.470E+03 5.261E+00 5.277E-01 1.077E-10 9.992E+02 3 1.5000 h 0.000E+00 0.000l 5.362E+06 9.666E+09 9.442E+03 5.246E+00 4.782E-01 9.762E-11 9.045E+02 4 2.0000 h 0.000E+00 0.0' ;' JO 5.346E+06 9.637E+09 9.414E+03 5.230E+00 1.219E+00 2.489E-10 1.541E+03 5 4.0000 h 0.000E+00 0.0c E+00 5.283E+06 3.826E+10 3.738E+04 5.191E+00 3.401E+00 6.943E-10 1.727E+04 6 8.0000 h 0.000E+00 0.000E+00 5.158E+06 7.517E+10 7.343E+04 5.099E+00 5.480E+00 1.119E-09 6.635E+04 7 8.5000 h 0.000E+00 0.000E+00 .5.152E+06 9.279E+09 0.000E+00 0.000E+00 1.642E-02 3.351E-12 1.693E+03 8 24.0000 h 0.000E+00 0.000E+00 4.961E+06 2.821E+11 0.000E+00 0.000E+00 1.075E-03 2.195E-13 3.141E+02 9 96.0000 h 0.000E+00 0.000E+00 4.162E+06 1.179E+12 0.000E+00 0.000E+00 3.411E-09 6.963E-19 2.202E+01 10 720.0000 h 0.000E+00 0.000E+00 9.083E+05 4.802E+12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.983E-05 Xe-131m TOTALS 0.000E+00 6.424E+12 1.486E+05 8.963E+04 Xe-133m INITIAL 0.000E+00 1.550E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.537E+08 2.778E+11 2.714E+05 1.508E+02 1.663E+01 3.395E-09 1.520E+04 2 1.0000 h 0.000E+00 0.000E+00 1.524E+08 2.755E+11 2.692E+05 1.495E+02 1.496E+01 3.054E-09 2.840E+04 3 1.5000 h 0.000E+00 0.000E+00 1.512E+08 2.732E+11 2.669E+05 1.483E+02 1.348E+01 2.752E-09 2.557E+04 4 2.0000 h 0.000E+00 0.000E+00 1.499E+08 2.710E+11 2.647E+05 1.471E+02 3.419E+01 6.979E-09 4.330E+04 5 4.0000 h 0.000E+00 0.000E+00 1.450E+08 1.062E+12 1.037E+06 1.440E+02 9.342E+01 1.907E-08 4.775E+05 6 8.0000 h 0.000E+00 0.000E+00 1.356E+08 2.020E+12 1.973E+06 1.370E+02 1.445E+02 2.950E-08 1.775E+06 7 8.5000 h 0.000E+00 0.000E+00 1.347E+08 2.433E+11 0.000E+00 0.000E+00 4.306E-01 8.790E-11 4.459E+04 8 24.0000 h 0.000E+00 0.000E+00 1.098E+08 6.799E+12 0.000E+00 0.000E+00 2.388E-02 4.874E-12 7.847E+03 9 96.0000 h 0.000E+00 0.000E+00 4.249E+07 1.838E+13 0.000E+00 0.000E+00 3.493E-08 7.131E-18 4.607E+02 10 720.0000 h 0.000E+00 0.000E+00 1.133E+04 1.160E+13 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.739E-04 Xa-133m TOTALS 0.000E+00 4.119E+13 4.082E+06 2.418E+06 Xa-133 INITIAL 0.000E+00 1. 320E+ 0 9 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.314E+09 2.371E+12 2.316E+06 1.287E+03 1.422E+02 2.902E-08 1.299E+05 2 1.0000 h 0.000E+00 0.000E+00 1.308E+09 2.360E+12 2.305E+06 1.281E+03 1.284E+02 2.620E-08 2.432E+05 3 1.5000 h 0.000E+00 0.000E+00 1.302E+09 2.349E+12 2.295E+06 1.275E+03 1.162E+02 2.371E-08 2.198E+05 4 2.0000 h 0.000E+00 0.000E+00 1.296E+09 2.339E+12 2.285E+06 1.269E+03 2.957E+02 6.035E-00 3.740E+05 5 4.0000 h 0.000E+00 0.000E+00 1.273E+09 9.250E+12 9.036E+06 1.255E+03 8.199E+02 1.674E-07 4.172E+06 6 8.0000 h 0.000E+00 0.000E+00 1.228E+09 1.801E+13 1.759E+07 1.222E+03 1.306E+03 2.665E-07 1.587E+07 7 8.5000 h 0.000E+00 0.000E+00 1.225E+09 2.207E+12 0.000E+00 0.000E+00 3.906E+00 7.974E-10 4.032E+05 8 24.0000 h 0.000E+00 0.000E+00 1.125E+09 6.550E+13 0.000E+00 0.000E+00 2.440E-01 4.980E-11 7.369E+04 9 96.0000 h 0.000E+00 0.000E+00 7.564E+08 2.406E+14 0.000E+00 0.000E+00 6.205E-07 1.267E-16 4.909E+03 10 720.0000 h 0.000E+00 0.000E+00 2.435E+07 4.786E+14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.249E-02 Xa-133 TOTALS 0.000E+00 8.236E+14 3.583E+07 2.150E+07 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 12 0

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm LPZ dose [TC961018.DAT]

not used Faulted S/G AVERAGE ----------CONTROL ROOM-----=- -

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xe-135m INITIAL 0.000E+00 5.460E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.408E+07 5.381E+10 5.257E+04 2.920E+01 1.788E+00 3.649E-10 1.982E+03 2 1.0000 h 0.000E+00 0.000E+00 3.629E+06 1.387E+10 1.355E+04 7.529E+00 4.180E-01 8.532E-11 1.692E+03 3 1.5000 h 0.000E+00 0.000E+00 9.355E+05 3.576E+09 3.494E+03 1.941E+00 9.795E-02 1.999E-11 3.960E+02 4 2.0000 h 0.000E+00 0.000E+00 2.412E+05 9.220E+08 9.007E+02 5.004E-01 6.472E-02 1.321E-11 1.393E+02 5 4.0000 h 0.000E+00 0.000E+00 1.065E+03 3.188E+08 3.115E+02 4.326E-02 4.907E-03 1.002E-12 1.071E+02 6 8.0000 h 0.000E+00 0.000E+00 2.079E-02 1.415E+06 1.382E+00 9.597E-05 1.056E-05 2.155E-15 6.127E+00 7 8.5000 h 0.000E+00 0.000E+00 5.369E-03 2.050E+01 0.000E+00 0.000E+00 8.180E-09 1.670E-18 2.651E-03 8 24.0000 h 0.000E+00 0.000E+00 3.188E-21 7.138E+00 0.000E+00 0.000E+00 3.304E-28 6.745E-38 1.022E-05 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 4.239E-18 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.129E-25 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xa-135m TOTALS 0.000E+00 7.250E+10 7.082E+04 4.323E+03 Xe-135 INITIAL 0.000E+00 1.610E+08 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.547E+08 2.841E+11 2.775E+05 1.542E+02 1.675E+01 3.419E-09 1.539E+04 2 1.0000 h 0.000E+00 0.000E+00 1.487E+08 2.730E+11 2.667E+05 1.482E+02 1.460E+01 2.979E-09 2.816E+04 3 1.5000 h 0.000E+00 0.000E+00 1.429E+08 2.624E+11 2.563E+05 1.424E+02 1.275E+01 2.602E-09 2.457E+04 4 2.0000 h 0.000E+00 0.000E+00 1.373E+08 2.521E+11 2.463E+05 1.368E+02 3.133E+01 6.395E-09 4.011E+04 5 4.0000 h 0.000E+00 0.000E+00 1.171E+08 9.139E+11 8.928E+05 1.240E+02 7.587E+01 1.549E-08 4.028E+05 6 8.0000 h 0.000E+00 0.000E+00 8.516E+07 1.444E+12 1.411E+06 9.796E+01 9.282E+01 1.895E-08 1.240E+06 7 8.5000 h 0.000E+00 0.000E+00 8.199E+07 1.504E+11 0.000E+00 0.000E+00 2.680E-01 5.471E-11 2.849E+04 8 24.0000 h 0.000E+00 0.000E+00 2. 521E+ 07 2. 68 6E+12 0.000E+00 0.000E+00 5.606E-03 1.144E-12 3.787E+03 9 96.0000 h 0.000E+00 0.000E+00 1.053E+05 1.188E+12 0.000E+00 0.000E+00 8.854E-11 1.807E-20 8.090E+01 10 720.0000 h 0.000E+00 0.000E+00 2.530E-16 4.982E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.278E-06 Xe-135 TOTALS 0.000E+00 7.459E+12 3.350E+06 1.783E+06 Xe-137 INITIAL 0.000E+00 8.190E+06 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 3.586E+04 2.702E+09 2.640E+03 1.467E+00 3.060E-02 6.245E-12 4.531E+01 2 1.0000 h 0.000E+00 0.000E+00 1.570E+02 1.183E+07 1.156E+01 6.421E-03 1.215E-04 2.480E-14 9.887E+00 3 1.5000 h 0.000E+00 0.000E+00 .874E-01 5.180E+04 5.061E-02 2.811E-05 4.837E-07 9.874E-17 3.927E-02 4 2.0000 h 0.000E+00 0.000E+00 3.010E-03 2.268E+02 2.216E-04 1.231E-07 5.452E-09 1.113E-18 1.615E-04 5 4.0000 h 0.000E+00 0.000E+00 1.106E-12 9.974E-01 9.744E-07 1.353E-10 3.943E-12 8.050E-22 1.795E-06 6 8.0000 h 0.000E+00 0.000E+00 1.493E-31 3.665E-10 3.580E-16 2.486E-20 7.245E-22 1.479E-31 1.279E-09 7 8.5000 h 0.000E+00 0.000E+00 6.550E-34 4.929E-29 0.000E+00 0.000E+00 9.532E-27 1.946E-36 1.160E-19 8 24.0000 h 0.000E+00 0.000E+00 0.000E+00 2.171E-31 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.1112-24 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-137 TOTALS 0.000E+00 2.714E+09 2.652E+03 5.524E+01 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page } g j

TPLILS -- Transport of Radioactive Material in Linear Systemas, v2.0 UtP Case for 2.95 gpa LPE dose [TC961018.DAT]

Faulted S/G AVERAGE -- CONTROL ROOM------= --

not used - - - - - -

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xa-138 INITIAL 0.000E+00 3.380E+07 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.745E+06 3.183E+10 3.109E+04 1.727E+01 1.011E+00 2.064E-10 1.137E+03 2 1.0000 h 0.000E+00 0.000E+00 1.775E+06 7.294E+09 7.125E+03 3.950E+00 2.101E-01 4.290E-11 9.154E+02 3 1.5000 h 0.000E+00 0.000E+00 4.067E+05 1.671E+09 1.633E+03 9.070E-01 4.377E-02 8.935E-12 1.904E+02 4 2.0000 h 0.000E+00 0.000E+00 9.319E+04 3.830E+08 3.741E+02 2.078E-01 2.571E-02 5.249E-12 5.839E+01 5 4.0000 h 0.000E+00 0.000E+00 2.569E+02 1.135E+08 1.109E+02 1.540E-02 1.605E-03 3.277E-13 3.850E+01 6 8.0000 h 0.000E+00 0.000E+00 1.953E-03 3.139E+05 3.066E-01 2.129E-05 2.167E-06 4.422E-16 1.842E+00 7 8.5000 h 0.000E+00 0.000E+00 4.483E-04 1.840E+00 0.000E+00 0.000E+00 1.492E-09 3.045E-19 5.352E-04 8 24.0000 h 0.000E+00 0.000E+00 6.896E-24 5.483E-01 0.000E+00 0.000E+00 1.561E-30 0.000E+00 1.723E-06 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 8.435E-21 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.803E-27 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-138 TOTALS 0.000E+00 4.129E+10 4.034E+04 2.342E+03 I-131 INITIAL 0.000E+00 7.730E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 7.703E+09 1.389E+13 1.357E+07 7.538E+03 8.334E+02 1.701E-07 7.612E+05 2 1.0000 h 0.000E+00 0.000E+00 7.675E+09 1.384E+13 1.352E+07 7.511E+03 7.532E+02 1. 537E-07 1. 42 6E+06 3 1.5000 h 0.000E+00 0.000E+00 7.648E+09 1.379E+13 1.347E+07 7.484E+03 6.821E+02 1.392E-07 1.290E+06 4 2.0000 h 0.000E+00 0.000E+00 7.521E+09 1.374E+13 1.342E+07 7.458E+03 6.757E+02 1.379E-07 1.222E+06 5 4.0000 h 0.000E+00 0.000E+00 7.513E+09 5.448E+13 5.322E+07 7.392E+03 6.545E+02 1.336E-07 4.783E+06 6 8.0000 h 0.000E+00 0.000E+00 7. 303E+ 09 1. 067E+14 1.042E+08 7.236E+03 6.254E+02 1.277E-07 9.182E+06 7 8.5000 h 0.000E+00 0.000E+00 7. 2 90E+ 09 1. 313E+13 0.000E+00 0.000E+00 1,873E+00 3.823E-10 1.931E+05 8 24.0000 h 0.000E+00 0.000E+00 6.895E+09 3.956E+14 0.000E+00 0.000E+00 1.205E-01 2.460E-11 3.564E+04 9 96.0000 h 0.000E+00 0.000E+00 5.323E+09 1.575E+15 0.000E+00 0.000E+00 3.517E-07 7.180E-17 2.451E+03 10 720.0000 h 0.000E+00 0.000E+00 5.659E+08 4.768E+15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.154E-03 I-131 TOTALS 0.000E+00 6.968E+15 2.114E+08 1.890E+07 I-132 INITIAL 0.000E+00 2.700E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 2.318E+09 4.508E+12 4.403E+06 2.446E+03 2.516E+02 5.136E-08 2.354E+05 2 1.0000 h 0.000E+00 0.000E+00 1.990E+09 3.870E+12 3.781E+06 2.100E+03 1.959E+02 3.999E-08 4.005E+05 3 1.5000 h 0.000E+00 0.000E+00 1.709E+09 3.323E+12 3.246E+06 1.803E+03 1.529E+02 3.121E-08 3.122E+05 4 2.0000 h 0.000E+00 0.000E+00 1.467E+09 2.853E+12 2.787E+06 1.548E+03 1.305E+02 2.664E-08 2.541E+05 5 4.0000 h 0.000E+00 0.000E+00 7.975E+08 7.910E+12 7.727E+06 1.073E+03 7.103E+01 1.450E-08 6.875E+05 6 8.0000 h 0.000S+00 0.000E+00 2.356E+08 6.635E+12 6.482E+06 4.501E+02 2.324E+01 4.744E-09 5.628E+05 7 8.5000 h 0.000E+00 0.0002+00 2.026E+08 3.936E+11 0.000E+00 0.000E+00 5.996E-02 1.224E-11 7.001E+03 8 24.0000 h 0.000E+00 0.000E+00 1.897E+06 2.398E+12 0.000E+00 0.000E+00 3.819E-05 7.795E-15 4.544E+02 0 96.0000 h 0.000E+00 0.000E+00 7.153E-04 2.266E+10 0.000E+00 0.000E+00 5.445E-20 1.111E-29 2.895E-01 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 8.544E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.129E-16 I-132 TOTALS 0.000E+00 3.191E+13 2.843E+07 2.460E+06 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 122

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm LPZ dose [TC961018.DAT]

not used Faulted S/G AVERAGE ----------CONTROL ROOM-----------

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-fsec I-133 INITIAL 0.000E+00 1.210E+10 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.188E+10 2.158E+13 2.108E+07 1.171E+04 1.286E+03 2.624E-07 1.177E+06 2 1.0000 h 0.000E+00 0.000E+00 1.166E+10 2.119E+13 2.070E+07 1.150E+04 1.145E+03 2.336E-07 2.184E+06 3 1.5000 h 0.000E+00 0.000E+00 1.145E+10 2.080E+13 2.032E+07 1.129E+04 1.021E+03 2.085E-07 1.947E+06 4 2.0000 h 0.000E+00 0.000E+00 1.124E+10 2.042E+13 1.995E+07 1.108E+04 9.968E+02 2.035E-07 1.816E+06 5 4.0000 h 0.000E+00 0.000E+00 1.044E+10 7.802E+13 7.622E+07 1.059E+04 9.107E+02 1.859E-07 6.838E+06 6 8.0000 h 0.000E+00 0.000E+00 9.011E+09 1.398E+14 1.366E+08 9.484E+03 7.773E+02 1.587E-07 1.198E+07 7 8.5000 h 0.000E+00 0.000E+00 8.862E+09 1.609E+13 0.000E+00 0.000E+00 2.293E+00 4.681E-10 2.395E+05 8 24.0000 h 0.000E+00 0.000E+00 5.287E+09 3.862E+14 0.000E+00 0.000E+00 9.306E-02 1.900E-11 3.831E+04 9 96.0000 h 0.000E+00 0.000E+00 4.799E+08 5.193E+14 0.000E+00 0.000E+00 3.194E-08 6.520E-18 1.621E+03 10 720.0000 h 0.000E+00 0.000E+00 4.470E-01 5.185E+13 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.562E-04 I-133 TOTALS 0.000E+00 1.275E+15 2.948E+08 2.622E+07 STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I-134 INITIAL 0.000E+00 1.690E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 1.136E+09 2.511E+12 2.453E+06 1.363E+03 1.249E+02 2.550E-08 1.214E+05 2 1.0000 h 0.000E+00 0.000E+00 7.638E+08 1.688E+12 1.649E+06 9.160E+02 7.615E+01 1.5551-08 1.772E+05 3 1.5000 h 0.000E+00 0.000E+00 5.135E+08 1.135E+12 1.108E+06 6.158E+02 4. 653E+01 9. 4 9f E-09 1. 081E+05 4 2.0000 h 0.000E+00 0.000E+00 3.452E+08 7.628E+11 7.452E+05 4.140E+02 3.110E+01 6.349E-09 6.868E+04 5 4.0000 h 0.000E+00 0.000E+00 7.051E+07 1.245E+12 1.216E+06 1.689E+02 6.893E+00 3.407E-09 1.087E+05 6 8.0000 h 0.000E+00 0.000E+00 2.942E+06 3.063E+11 2.992E+05 2.078E+01 5.200E-01 1.062E-10 2.819E+04 7 8.5000 h 0.000E+00 0.000E+00 1.981E+06 4.374E+09 0.000E+00 0.000E+00 1.051E-0.5 2.144E-13 1.506E+02 8 24.0000 h 0.000E+00 0.000E+00 9.429E+00 9.020E+09 0.000E+00 0.000E+00 3.401E-10 6.943E-20 3.923E+00 9 96.0000 h 0.000E+00 0.000E+00 1.782E-24 4.293E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.270E-06 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 8.114E-21 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-134 TOTALS 0.000E+00 7.661E+12 7.470E+06 6.125E+05 I-135 INITIAL O.000E+00 6.490E+09 0.000E+00 1 0.5000 h 0.000E+00 0.000E+00 6.148E+09 1.137E+13 1.111E+07 6.171E+03 6.656E+02 1.359E-07 6.129E+05 2 1.0000 h 0.OOOE+00 0.000E+00 5.823E+09 1.077E+13 1.052E+07 5.846E+03 5.718E+02 1.167E-07 1.111E+06 3 1.5000 h 0.000E+00 0.000E+00 5.516E+09 1.020E+13 9.967E+06 5.537E+03 4.923E+02 1.005E-07 9.556E+05 4 2.0000 h 0.000E+00 0.000E+00 5.225E+09 9.665E+12 9.441E+06 5.245E+03 4.636E+02 9.463E-08 8.596E+05 5 4.0000 h 0.000E+00 0.000E+00 4.207E+09 3.382E+13 3.304E+07 4.589E+03 3.682E+02 7.517E-08 2.955E+06 6 8.0000 h 0.000E+00 0.000E+00 2.727E+09 4.916E+13 4.802E+07 3.335E+03 2.408E+02 4.916E-08 4.179E+06 7 8.5000 h 0.000E+00 0.000E+00 2.588E+09 4.782E+12 0.000E+00 0.000E+00 6.855E-01 1.399E-10 7.374E+04 8 24.0000 h 0.000E+00 0.000E+00 5.094E+08 7.135E+13 0.000E+00 0.000E+00 9.179E-03 1.874E-12 8.750E+03 9 96.0000 h 0.000E+00 0.000E+00 2.679E+05 1.748E+13 0.000E+00 0.000E+00 1. 825E-11 3.72 6E-21 1.187E+02 10 720.0000 h 0.000E+00 0.000E+00 1.023E-23 9.197E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.361E-07 I-135 TOTALS 0.000E+00 2.186E+14 1.221E+08 1.076E+07 ALL NUCLIDES 0.000E+00 1.129E+09 0.000E+00 0.000E+00

@ STEP 10 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 12 3

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpa LPE dose [TC961018.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE PATE DOSE DOSE RATE DOSE DOSE RATE arem area /hr mrem area /hr mrem arem/hr mrem mren/hr mrem mren/hr mrem area /hr Kr-83m 0.5000 h 3.63E-08 7.26E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.78E-10 1.06E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 3.00E-08 6.00E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.62E-10 7.97E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 2.48E-08 4.96E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.46E-10 5.99E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 2.05E-08 4.09E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.74E-10 1.26E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.0000 h 5.20E-08 2.60E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.13E-09 1.76E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.0000 h 3.54E-08 8.86E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.29E-09 7.60E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.32E-11 1.89E-12 0.00E+00 0.00E+00 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.42E-12 3.62E-16 0.00E+00 0.00E+00 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.93E-16 1.96E-33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.42E-33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.99E-07 0.00E+00 0.00E+00 9.04E-09 0.00E+00 0.00E+00 Kr-85m 0.5000 h 3.25E-04 6.50E-04 6.41E-04 1.28E-03 0.00E+00 0.00E+00 2.58E-06 1.00E-05 1.01E-04 3.95E-04 0.00E+00 0.00E+00 1.0000 h 3.00E-04 6.00E-04 5.93E-04 1.19E-03 0.00E+00 0.00E+00 4.60E-06 8.42E-06 1.81E-04 3.31E-04 0.00E+00 0.00E+00 1.5000 h 2.77E-04 5.55E-04 5.48E-04 1.10E-03 0.00E+00 0.00E+00 3.86E-06 7.07E-06 1.52E-04 2.78E-04 0.00E+00 0.00E+00 2.0000 h 2. 5 6E-04 5.13E-04 5.06E-04 1.01E-03 0.00E+00 0.00E+00 6.02E-06 1.67E-05 2.37E-04 6.56E-04 0.00E+00 0.00E+00 4.0000 h 8.44E-04 4.22E-04 1.67E-03 8.33E-04 0.00E+00 0.00E+00 5.40E-05 3.49E-05 2.12E-03 1.37E-03 0.00E+00 0.00E+00 8.0000 h 1.06E-03 2.66E-04 2.10E-03 5.25E-04 0.00E+00 0.00E+00 1.33E-04 3.21E-05 5.21E-03 1.26E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.72E-06 8.92E-08 1.07E-04 3.50E-06 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.70E-07 5.51E-10 1.06E-05 2.17E-08 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.01E-09 3.03E-20 3.96E-08 1.19E-18 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.69E-20 0.00E+00 1.45E-18 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.07E-03 6.06E-03 0.00E+00 2.07E-04 8.12E-03 0.00E+00 Kr-85 0.5000 h 2.46E-05 4.91E-05 3.43E-03 6.87E-03 0.00E+00 0.00E+00 2.00E-07 7.89E-07 5.57E-04 2.19E-03 0.00E+00 0.00E+00 1.0000 h 2.45E-05 4.90E-05 3.43E-03 6.86E-03 0.00E+00 0.00E+00 3.75E-07 7.14E-07 1.04E-03 1.99E-03 0.00E+00 0.00E+00 1.5000 h 2.45E-05 4.89E-05 3.42E-03 6.84E-03 0.00E+00 0.00E+00 3.40E-07 6.48E-07 9.46E-04 1.80E-03 0.00E+00 0.00E+00 2.0000 h 2.44E-05 4.88E-05 3.42E-03 6.83E-03 0.00E+00 0.00E+00 5.80E-07 1.65E-06 1.61E-03 4.60E-03 0.00E+00 0.00E+00 4.0000 h 9.73E-05 4.86E-05 1.36E-02 6.80E-03 0.00E+00 0.00E+00 6.53E-06 4.63E-06 1.82E-02 1.29E-02 0.00E+00 0.00E+00 8.0000 h 1.93E-04 4.81E-05 2.69E-02 6.73E-03 0.00E+00 0.00E+00 2.53E-05 7.54E-06 7.03E-02 2.10E-02 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.47E-07 2.26E-08 1.80E-03 6.29E-05 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.21E-07 1.54E-09 3.38E-04 4.28E-06 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.32E-09 5.81E-15 1.48E-05 1.62E-11 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.34E-14 0.00E+00 3.73E-11 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.88E-04 5.42E-02 0.00E+00 3.41E-05 9.48E-02 0.00E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page { y

TRAILS -- Transport of Radioactive Material in Linear Systeens, v2.0 PRP Case for 2.95 gpua LPE dose [TC961018.DAT]

ENYIRONMEN7------ - - -

CONTROL ROOM-------

External EDE SKIN-DE TRY CDE-INRAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE GTE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem nrem/hr arem i esa/hr arena uresa/hr arena mresa/hr arem arem/hr urema urem/hr Kr-87 0.5000 h 9.27E-04 1.85E-03 2.20E-C"4 1.40E-03 0.00E+00 0.00E+00 6.92E-06 2.61E-05 3.27E-04 1.23E-03 0.00E+00 0.00E+00 1.0000 h 7.05E-04 1.41E-03 1.67E-03 3.34E-03 0.00E+00 0.00E+00 1.09E-05 1.80E-05 5.14E-04 8.50E-04 0.00E+00 0.00E+00 1.5000 h 5.36E-04 1.07E-03 1.27E-03 2.54E-03 0.00E+00 0.00E+00 7.52E-06 1.24E-05 3.55E-04 5.87E-04 0.00E+00 0.00E+00 2.0000 h 4.07E-04 8.14E-04 9.66E-04 1.93E-03 0.00E+00 0.00E+00 9.35E-06 2.42E-05 4.41E-04 1.14E-03 0.00E+00 0.00E+00 4.0000 h 8.60E-04 4.30E-04 2.04E-03 1.02E-03 0.00E+00 0.00E+00 4.98E-05 2.53E-05 2.35E-03 1.19E-03 0.00E+00 0.00E+00 8.0000 h 3.83E-04 9.57E-05 9.08E-04 2.27E-04 0.00E+00 0.00E+00 4.66E-05 6.54E-06 2.20E-03 3.09E-04 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00F+00 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 5.36E-07 1.49E-08 2.53E-05 7.05E-07 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.08E-08 2.18E-13 9.81E-07 1.03E-11 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00M+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.82E-13 0.00E+00 8.58E-12 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.14E-36 0.00E+00 1.95E-34 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.82E-03 9.06E-03 0.00E+00 1.32E-04 6.22E-03 0.00E+00 Kr-88 0.5000 h 6.70E-03 1.34E-02 1.48E-03 2.95E-03 0.00E+00 0.00E+00 5.25E-05 2.03E-04 2.30E-04 8.89E-04 0.00E+00 0.OOE+00 1.0000 h 5.92E-03 1.18E-02 1.30E-03 2.61E-03 0.00E+00 0.00E+00 9.09E-05 1.63E-04 3.98E-04 7.12E-04 0.00E+00 0.00E+00 1.5000 h 5.23E-03 1.05E-02 1.15E-03 2.30E-03 0.00E+00 0.00E+00 7.29E-05 1.31E-04 3.20E-04 5.72E-04 0.00E+00 0.00E+00 2.0000 h 4.62E-03 9.25E-03 1.02E-03 2.04E-03 0.00E+00 0.00E+00 1.08E-04 2.95E-04 4.73E-04 1.29E-03 0.00E+00 0.00E+00 4.0000 h 1.37E-02 6.85E-03 3.02E-03 1.51E-03 0.00E+00 0.00E+00 8.54E-04 5.23E-04 3.74E-03 2.29E-03 0.00E+00 0.00E+00 8.0000 h 1.34E-02 3.36E-03 2.96E-03 7.40E-04 0.00E+00 0.00E+00 1.65E-03 3.52E-04 7.21E-03 1.54E-03 0.00E+00 0.00E+00 0.3000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.96E-05 9.35E-07 1.30E-04 4.10E-06 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.24E-06 1.45F-09 9.80E-06 6.34E-09 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 2.08E-09 1.28E-22 9.12E-09 5.60E-22 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.22E-22 0.00E+00 5.37E-22 0.00E+00 0.00E+00 0.00E+00 TOTALS 4.96E-02 1.09E-02 0.00E+00 2.86E-03 1.25E-02 0.00E+00 Kr-89 0.5000 h 3.08E-05 6.15E-05 3.34E-05 6.68E-05 0.00E+00 0.00E+00 6.57E-08 1.54E-07 1.42E-06 3.34E-06 0.00E+00 0.00E+00 1.0000 h 4.26E-08 8.52E-08 4.63E-08 9.25E-08 0.00E+00 0.00E+00 1.15E-08 1.94E-10 2.49E-07 4.19E-09 0.00E+00 0.00E400 1.5000 h 5.90E-11 1.18E-10 6.41E-11 1.28E-10 0.00E+00 0.00E+00 1.45E-11 2.44E-13 3.13E-10 5.28E-12 0.00E+00 0.00E+00 2.0000 h 8.17E-14 1.63E-13 8.87E-14 1.77E-13 0.00E+00 0.00E+00 1.84E-14 8.71E-16 3.99E-13 1.88E-14 0.00E+00 0.00E+00 4.0000 h 1.13E-16 5.66E-17 1.23E-16 6.15E-17 0.00E+00 0.00E+00 6.54E-17 1.98E-19 1.41E-15 4.29E-18 0.00E+00 0.00E+00 8.0000 h 4.16E-28 1.04E-28 4.52E-28 1.13E-28 0.00E+00 0.00E+00 1.48E-20 3.65E-31 3.20E-19 7.88E-30 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.47E-32 0.00E+00 3.18E-31 0.00E+00 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.14E-37 0.00E+00 2.46E-36 0.00E+00 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.08E-05 3.35E-05 J.00E+00 7.73E-08 1.67E-06 0.00E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 12 5

i I

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm LPZ dose [TC961018.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr l Xe-131m 0.5000 h 9.12E-07 1.02E-06 1.01E-05 2.02E-05 0.00E+00 0.00E+00 7.43E-09 2.93E-08 1.64E-06 6.46E-06 0.00E+00 9.00E+00 1.0000 h 9.10E-07 1.82E-06 1.01E-05 2.02E-05 0.00E+00 0.00E+00 1.39E-08 2.65E-08 3.07E-06 5.84E-06 0.00E+00 0.00E+00 1.5000 h 9.07E-07 1.81E-06 1.01E-05 2.01E-05 0.00E+00 0.00E+00 1.26E-08 2.40E-08 2.78E-06 5.29E-06 0.00E+00 0.00E+00 2.0000 h 9.04E-07 1.81E-06 1.00E-05 2.00E-05 0.OOE+00 0.00E+00 2.15E-08 6.12E-08 4.74E-06 1.35E-05 0.00E+00 0.00E+00 4.0000 h 3.59E-06 1.79E-06 3.98E-05 1.99E-05 0.00E+00 0.00E+00 2.41E-07 1.71E-07 5.31E-05 3.76F-05 0.00E+00 0.00E+00 8.0000 h 7.05E-06 1.76E-06 7.82E-05 1.95E-05 0.00E+00 0.00E+00 9.25E-07 2.75E-07 2.04E-04 6.060-05 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.36E-08 8.24E-10 5.20E-06 1.820-07 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.38E-09 5.39E-11 9.65E-07 1.19E-08 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.84E-10 1.71E-16 4.06E-08 3.772-14 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.89E-16 0.00E+00 8.58E-14 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.43E-05 1.58E-04 0.00E+00 1.25E-06 2.75E-04 0.00E+00 Xe-133m 0.5000 h 9.06E-05 1. 81E-0 4 6.02E-04 1.20E-03 0.00E+00 0.00E+00 7.36E-07 2.90E-06 9.74E-05 3.84E-04 0.00E+00 0.00E+00 1.0000 h 8.99E-05 1.80E-04 5.97E-04 1.19E-03 0.00E+00 0.00E+00 1.38E-06 2.61E-06 1.82E-04 3.45E-04 0.00E+00 0.00E+00 1.5000 h 8.91E-05 1.78E-04 5.92E-04 1.18E-03 0.00E+00 0.00E+00 1.24E-06 2.35E-06 1.64E-04 3.11E-04 0.00E+00 0.00E+00 2.0000 h 8.84E-05 1.77E-04 5.87E-04 1.17E-03 0.00E+00 0.00E+00 2.10E-06 5.96E-06 2.77E-04 7.89E-04 0.00E+00 0.00E+00 4.0000 h 3.46E-04 1.73E-04 2.30E-03 1.15E-03 0.00E+00 0.00E+00 2.31E-05 1.63E-05 3.06E-03 2.15E-03 0.00E+00 0.00E+00 8.0000 h 6.59E-04 1.65E-04 4.38E-03 1.09E-03 0.00E+00 0.00E+00 8.60E-05 2.52E-05 1.14E-02 3.33E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.16E-06 7.51E-08 2.86E-04 9.93E-06 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.80E-07 4.16E-09 5.03E-05 5.51E-07 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.34E-08 6.09E-15 1.77E-06 8.06E-13 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.31E-14 0.00E+00 1.73E-12 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.36E-03 9.06E-03 0.00E+00 1.17E-04 1.55E-02 0.00E+00 Xm-133 0.5000 h 9.14E-04 1.83E-03 1.73E-03 3.46E-03 0.00E+00 0.00E+00 7.44E-06 2.93E-05 2.80E-04 1.10E-03 0.00E+00 0.00E+00 1.0000 h 9.10E-04 1.82E-03 1.72E-03 3.44E-03 0.00E+00 0.00E+00 1.39E-05 2.65E-05 5.24E-04 9.96E-04 0.00E+00 0.00E+00 1.5000 h 9.06E-04 1.81E-03 1.71E-03 3.43E-03 0.00E+00 0.00E+00 1.26E-05 2.39E-05 4.74E-04 9.01E-04 0.00E+00 0.00E+00 2.0000 h 9.02E-04 1.80E-03 1.71E-03 3.41E-03 0.00E+00 0.00E+00 2.14E-05 6.10E-05 8.06E-04 2.29E-03 0.00E+00 0.00E+00 4.0000 h 3.57E-03 1.78E-03 6.74E-03 3.37E-03 0.00E+00 0.00E+00 2.39E-04 1.69E-04 8.99E-03 6. 3 6E-03 0.00E+00 0.00E+00 8.0000 h 6.94E-03 1.74E-03 1.31E-02 3.28E-03 0.00E+00 0.00E+00 9.09E-04 2.69E-04 3.42E-02 1.01E-02 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.31E-05 8.05E-07 8.69E-04 3.03E-05 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.22E-06 5.03E-08 1.59E-04 1.89E-06 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.69E-07 1.28E-13 6.35E-06 4.81E-12 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2. 8 6E-13 0.00E+00 1.08E-11 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.41E-02 2.67E-02 0.00E+00 1.23E-03 4.63E-02 0.00E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 12 6

TRAILS -- Transport of Radioactive Material in Linear Systsums, v2.0 FRP Case for 2.95 gpa LPE dose [TC961018.DAT]

ENYIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOF1 RATE DOSE DOSE RATE arem arem/hr arem aren/hr arem arem/hr mrem aren/hr arem aram/hr arem mree/hr Xa-135m 0.5000 h 2.53E-04 5.06E-04 8.04E-05 1.61E-04 0.00E+00 0.00E+00 1.38E-06 4.49E-06 8.76E-06 2.84E-05 0.00E+00 0.00E+00 1.0000 h 6.52E-05 1.30E-04 2.07E-05 4.15E-05 0.00E+00 0.00E+00 1.18E-06 1.05E-06 7.48E-06 6.65E-06 0.00E+00 0.00E+00 1.5000 h 1.68E-05 3.36E-05 5.35E-06 1.07E-05 0.00E+00 0.00E+00 2.76E-07 2.46E-07 1.75E-06 1.56E-06 0.00E+00 0.00E+00 2.0000 h 4.33E-06 8.67E-06 1.38E-06 2.76E-06 0.00E+00 0.00E+00 9.72E-08 1.63E-07 6.15E-07 1.03E-06 0.00E+00 0.00E+03 4.0000 h 1.50E-06 7.49E-07 4.77E-07 2.38E-07 0.00E+00 0.00E+00 7.48E-08 1.23E-08 4.73E-07 7.80E-08 0.00E+G9 0.00L+00 8.0000 h 6.65E-09 1.66E-09 2.11E-09 5.29E-10 0.00E+00 0.00E+00 4.28E-09 2.65E-11 2.71E-08 1.68E-10 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.85E-12 2.06E-14 1.17E-11 1.30E-13 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.14E-15 8.30E-34 4.51E-14 5.25E-33 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.73E-34 0.00E+00 1.09E-33 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 TOTALS 3.41E-04 1.08E-04 0.00E+00 3.02E-06 1.91E-05 0.00E+00 Xa-135 0.5000 h 7.79E-04 1.56E-03 1.27E-03 2.54E-03 0.00E+00 0.00E+00 6.27E-06 2.46E-05 2.03E-04 7.97E-04 0.00E+00 0.00E+00 1.0000 h 7.49E-04 1.50E-03 1.22E-03 2.44E-03 0.00E+00 0.00E+00 1.15E-05 2.14E-05 3.72E-04 6.94E-04 0.00E+00 0.00E+00 1.5000 h 7.20E-04 1.44E-03 1.17E-03 2.353-03 0.00E+00 0.00E+00 1.00E-05 1.87E-05 3.25E-04 6.06E-04 0.00E+00 0.00E+00 2.0000 h 6.92E-04 1.38E-03 1.13E-03 2.25E-03 0.00E+00 0.00E+00 1.63E-05 4.60E-05 5.30E-04 1.49E-03 0.00E+00 0.00E+00 4.0000 h 2.51E-03 1.25E-03 4.09E-03 2.04E-03 0.00E+00 0.00E+00 1.64E-04 1.11E-04 5.32E-03 3.61E-03 0.00E+00 0.00E+00 8.0000 h 3.96E-03 9.90E-04 6.46E-03 1.61E-03 0.00E+00. 0.00E+00 5.05E-04 1.36E-04 1.64E-02 4.41E-03 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.16E-05 3.93E-07 3.76E-04 1.27E-05 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.54E-06 8.22E-09 5.00E-05 2.67E-07 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.98E-08 1.30E-16 6.41E-07 4.21E-15 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.08E-16 0.00E+00 6.75E-15 0.00E+00 0.00E+00 0.00E+00 TOTALS 9.41E-03 1.53E-02 0.00E+00 7.27E-04 2.36E-02 0.00E+00 Xa-137 0.5000 h 5.65E-06 1.13E-05 8.56E-05 1.71E-04 0.00E+00 0.00E+00 1.41E-08 3.42E-08 4.24E-06 1.03E-05 0.00E+00 0.00E+00 1.0000 h 2.47E-08 4.95E-08 3.75E-07 7.49E-07 0.00E+00 0.00E+00 3.07E-09 1.36E-10 9.25E-07 4.09E-08 0.00E+00 0.00E+00 1.5000 h 1.08E-10 2.17E-10 1.64E-09 3.28E-09 0.00E+00 0.00E+00 1.22E-11 5.41E-13 3.67E-09 1.63E-10 0.00E+00 0.00E+00 2.0000 h 4.74E-13 9.49E-13 7.18E-12 1.44E-11 0.00E+00 0.00E+00 5.02E-14 6.10E-15 1.51E-11 1.84E-12 0.00E+00 0.00E+00 4.0000 h 2.09E-15 1.04E-15 3.16E-14 1.58E-14 0.00E+00 0.00E+00 5.58E-16 4.41E-18 1.68E-13 1.33E-15 0.00E+00 0.00E+00 8.0000 h 7.66E-25 1.92E-25 1.16E-23 2.90E-24 0.00E+00 0.00E+00 3.97E-19 8.10E-28 1.20E-16 2.44E-25 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.60E-29 1.07E-32 1.09E-26 3.21E-30 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.66E-34 0.00E+00 2.91E-31 0.00E+00 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E4SO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*JO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 5.68E-06 8.59E-05 0.00E+00 1.72E-08 5.17E-06 0.00E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 127

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ERP Case for 2.95 gpm LPZ dose [TC961018.DAT]

ENVIRONMENT--------- --- ----CONTROL ROOM-------

External EDE SKIN-DE TRY CDE-INHAL Extern 1L1 EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE BATE DOSE DOSE RATE DOSE DOSE RATE

arena urem/hr arem arem/hr arem aren/hr arem aren/hr arem aren/hr arem aren/hr XQ-138 0.5000 h 4.37E-04 8.73E-04 3.25E-04 6.50E-04 0.00E+00 0.00E+00 2.32E-06 7.42E-06 3.43E-05 1.10E-04 0.00E+00 0.00E+00 1.0000 h 1.00E-04 2.00E-04 7.44E-05 1.49E-04 0.00E+00 0.00E+00 1.86E-06 1.54E-06 2.76E-05 2.28E-05 0.00E+00 0.00E+00 1.5000 h 2.29E-05 4.59E-05 1.71E-05 3.41E-05 0.00E+00 0.00E+00 3.88E-07 3.21E-07 5.74E-06 4.75E-06 0.00E+00 0.00E+00 2.0000 h 5.25E-06 1.05E-05 3.91E-06 7.82E-06 0.00E+00 0.00E+00 1.19E-07 1.89E-07 1.76E-06 2.79E-06 0.00E+00 0.00E+00 4.0000 h 1.56E-06 7.79E-07 1.16E-06 5.79E-07 0.00E+00 0.00E+00 7.84E-08 1.18E-08 1.16E-06 1.74E-07 0.00E+00 0.00E+00 8.0000 h 4.31E-09 1.08E-09 3.20E-09 8.01E-10 0.00E+00 0.00E+00 3.75E-09 1.59E-11 5.56E-08 2.35E-10 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.09E-12 1.09E-14 1.61E-11 1.62E-13 0.00E+00 0.00E+00 [

24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.51E-15 0.00E+00 5.20E-14 0.00E+00 0.00E+00 0.00E+00 C6.0000 h 0.0GE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.20E-36 0.00E+00 3.26E-35 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 [

TOTALS 5.66E-04 4.21E-04 0.00E+00 4.77E-06 7.06E-05 0.00E+00 t

I-131 0.5000 h 5.81E-02 1.16E-01 3.06E-02 6.13E-02 3.59E+02 7.19E+02 4.73E-04 1.86E-03 4.96E-03 1.96E-02 5.82E+01 2.30E+02 1.0000 h 5.79E-02 1.16E-01 3.05E-02 6.11E-02 3.58E+02 7.16E+02 8.86E-04 1.68E-03 9.30E-03 1.77E-02 1.09E+02 2.07E+02 ,

1.5000 h 5.77E-02 1.15E-01 3.04E-02 6.09E-02 3.57E+02 7.14E+02 8.02E-04 1.53E-03 8.41E-03 1.60E-02 9.87E+01 1.88E+02 2.0000 h 5.75E-02 1.15E-01 3.03E-02 6.06E-02 3.56E+02 7.11E+02 7.59E-04 1.51E-03 7.97E-03 1.59E-02 9.35E+01 1.86E+02 I 4.0000 h 2.28E-01 1.14E-01 1.20E-01 6.01E-02 1.41E+03 7.05E+02 2.97E-03 1.46E-03 3.12E-02 1.54E-02 3.66E+02 1.80E+02 8.0000 h 4.46E-01 1.12E-01 2.35E-01 5.88E-02 2.76E+03 6.90E+02 5.70E-03 1.40E-03 5.99E-02 1.47E-02 7.02E+02 1.'72E+02 I 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.20E-04 4.19E-06 1.26E-03 4.40E-05 1.48E+01 5.16E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.21E-05 2.69E-07 2.32E-04 2.83E-06 2.73E+00 3.32E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.13E-07 7.87E-13 9.59E-06 8.26E-12 1.12E-01 9.69E-08 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.78E-12 0.00E+00 1.87E-11 0.00E+00 2.19E-07 0.00E+00 TOTALS 9.05E-01 4.77E-01 5.60E+03 1.17E-02 1.23E-01 1.45E+03 I-132 0.5000 h 1.18E-01 2.35E-01 3.48E-02 6.95E-02 6.96E-01 1.39E+00 9.12E-04 3.51E-03 5.37E-03 2.06E-02 1.07E-01 4.13E-01 1.0000 h 1.01E-01 2.02E-01 2.99E-02 5.97E-02 5.97E-01 1.19E+00 1.55E-03 2.73E-03 9.13E-03 1.61E-02 1.83E-01 3.22E-01 1.5000 h 8.67E-02 1.73E-01 2.56E-02 5.13E-02 5.13E-01 1.03E+00 1.21E-03 2.13E-03 7.12E-03 1.25E-02 1.42E-01 2.51E-01 2.0000 h 7.e4E-02 1.49E-01 2.20E-02 4.40E-02 4.40E-01 8.81E-01 9.85E-04 1.82E-03 5.79E-03 1.07E-02 1.16E-01 2.14E-01 4.0000 h 2.06E-01 1.03E-01 6.10E-02 3.05E-02 1.22E+00 6.10E-01 2.66E-03 9.91E-04 1.57E-02 5.83E-03 3.14E-01 1.17E-01 8.0000 h 1.73E-01 4.33E-02 5.12E-02 1.28E-02 1.02E+00 2.56E-01 2.18E-03 3.24E-04 1.28E-02 1.91E-03 2.57E-01 3.82E-02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.71E-05 8.37E-07 1.60E-04 4.92E-06 3.19E-03 9.85E-05 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.76E-06 5.33E-10 1.04E-05 3.13E-09 2.07E-04 6.27E-08 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.73E-10 7.60E-25 3.96E-09 4.47E-24 7.92E-08 8.94E-23 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.40E-25 0.00E+00 3.76E-24 0.0GE+00 7.53E-23 0.00E+00 TOTALS 7.59E-01 2.24E-01 4.49E+00 9.53E-03 5.61E-02 1.12E+00 ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 12 8

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm LPZ dose (TC961018.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE TRY CDE-INHAL DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE I DOSE DOSE RATE DOSE arem area /hr mrem mrem /hr mrem mren/hr arem arem/hr arem aren/hr arem aren/hr I-133 0.5000 h 1.45E-01 2.90E-01 1.35E-01 2.69E-01 9.31E+01 1.86E+02 1.17E-03 4.62E-03 2.17E-02 8.53E-02 1.50E+01 5.90E+01 1.0000 h 1.42E-01 2.85E-01 1.32E-01 2.64E-01 9.14E+01 1.83E+02 2.18E-03 4.11E-03 4.03E-02 7.59E-02 2.78E+01 5.25E+01 1.5000 h 1.40E-01 2.79E-01 1.30E-01 2.59E-01 8.97E+01 1.79E+02 1.94E-03 3.67E-03 3.59E-02 6.78E-02 2.48E+01 4.69E+01 2.0000 h 1.37E-01 2.74E-01 1.27E-01 2.55E-01 8.81E+01 1.76E+02 1.81E-03 3.58E-03 3.35E-02 6.61E-02 2.32E+01 4.5BE+01 4.0000 h 5.24E-01 2.62E-01 4.87E-01 2.43E-01 3.37E+02 1.68E+02 6.82E-03 3.27E-03 1.26E-01 6.04E-02 8.72E+01 4.18E+01 8.0000 h 9.39E-01 2.35E-01 8.72E-01 2.18E-01 6.03E+02 1.51E+02 1.19E-02 2.79E-03 2.21E-01 5.16E-02 1.53E+02 3.57E+01 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.39E-04 8.23E-06 4.41E-03 1.52E-04 3.05E+00 1.05E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.82E-05 3.34E-07 7.06E-04 6.17E-06 4.88E-01 4.27E-03 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.70E-07 1.15E-13 1.79E-05 2.12E-12 1.24E-02 1.47E-09 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.22E-13 0.00E+00 4.10E-12 0.00E+00 2.84E-09 0.00E+00 TOTALS 2.03E+00 1.88E+00 1.30E+03 2.62E-02 4.83E-01 3.34E+02 I-134 0.5000 h 7.56E-02 1.51E-01 2.49E-02 4.97E-02 6.44E-02 1.29E-01 5.43E-04 2.01E-03 3.55E-03 1.32E-02 9. 2 0E-03 3.41E-02 1.0000 h 5.08E-02 1.02E-01 1.67E-02 3.34E-02 4.33E-02 8.66E-02 7.93E-04 1.23E-03 5.18E-03 8.02E-03 1.34E-02 2.08E-02 1.5000 h 3.42E-02 6.84E-02 1.12E-02 2.25E-02 2.91E-02 5.82E-02 4.84E-04 7.49E-04 3.16E-03 4.90E-03 8.20E-03 1.27E-02 E 2.0000 h 2.30E-02 4.60E-02 7.55E-03 1.51E-02 1.96E-02 3.91E-02 3.07E-04 5.01E-04 2.01E-03 3.28E-03 5.21E-03 8.49E-03 4.0000 h 3.75E-02 1.88E-02 1.23E-02 6.16E-03 3.19E-02 1.60E-02 4.86E-04 1.11E-04 3.18E-03 7.26E-04 8.24E-03 1.88E-03 l 8.0000 h 9.23E-03 2.31E-03 3.03E-03 7.58E-04 7.85E-03 1.96E-03 1.26E-04 8.38E-06 8.25E-04 5.48E-05 2.14E-03 1.42E-04 l 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.74E-07 1.69E-08 4.41E-06 1.11E-07 1.14E-05 2.87E-07 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.75E-08 5.48E-15 1.15E-07 3.58E-14 2.97E-07 9.28E-14 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.GCM+00 0.00E+00 0.00E+00 3.41E-15 0.00E+00 2.23E-14 0.00E+00 5.78E-14 0.00E+00 ?

720.0000 h 0.00E+00 0.00E+00 0.00E+00 4.00Et00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 2.30E-01 7.57E-02 1.96E-01 2.74E-03 1.79E-02 4.64E-02 I-135 0.5000 h 2.08E-01 4.15E-01 6.28E-02 1.26E-01 8.53E+00 1.71E+01 1.66E-03 6.50E-03 1.00E-02 3.91E-02 1.36E+00 5.31E+00 1.0000 h 1.97E-01 3.93E-01 5.95E-02 1.19E-01 8.08E+00 1.62E+01 3.01E-03 5.58E-03 1.81E-02 3.36E-02 2.46E+00 4.56E+00 !

1.5000 h 1.86E-01 3.73E-01 5.64E-02 1.13E-01 7.65E+00 1.53E+01 2.59E-03 4.81E-03 1.56E-02 2.89E-02 2.12E+00 3.93E+00 2.0000 h 1.77E-01 3.53E-01 5.34E-02 1.07E-01 7.25E+00 1.45E+01 2.33E-03 4.53E-03 1.40E-02 2.73E-02 1.91E+00 3.70E+00 l 4.0000 h 6.18E-01 3.09E-01 1.87E-01 9.34E-02 2.54E+01 1.27E+01 8.02E-03 3.60E-03 4.83E-02 2.16E-02 6.55E+00 2.94E+00 8.0000 h 8.98E-01 2.24E-01 2.72E-01 6.79E-02 3.69E+01 9.22E+00 1.13E-02 2.35E-03 6.82E-02 1.42E-02 9.27E+00 1.92E+00 i 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-04 6.69E-06 1.20E-03 4.03E-05 1.63E-01 5.47E-03 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.37E-05 8.96E-08 1.43E-04 5.40E-07 1.94E-02 7.33E-05 !

96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.93E-07 1.78E-16 1.16E-06 1.07E-15 1.58E-04 1.46E-13 720.C000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.56E-16 0.00E+00 1.54E-15 0.00E+00 2.09E-13 0.00E+00 TOTALS 2.28E+00 6.91E-01 9.38E+01 2.92E-02 1.76E-01 2.38E+01 I

h ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 129

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

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 2.95 gpm LPE dose [TC961018.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE !

arem mrem /hr arem arem/hr mrem arem/hr arem arem/hr mrem arem/hr arem mren/hr ALL NUCLIDES 0.5000 h 6.14E-01 1.23E+00 3.00E-01 5.99E-01 4.62E+02 9.24E+02 4.84E-03 1.88E-02 4.74E-02 1.85E-01 7.47E+01 2.94E+02 '

1.0000 h 5.58E-01 1.12E+00 2.79E-01 5.59E-01 4.58E+02 9.17E+02 8.56E-03 1. 5 6E-02 8.53E-02 1.57E-01 1.40E+02 2.65E+02 1.5000 h 5.12E-01 1.02E+00 2.63E-01 5. 2 6E-01 4.55E+02 9.10E+02 7.14E-03 1.31E-02 7.29E-02 1.35E-01 1.26E+02 2.39E+02 2.C000 h 4.76E-01 9.51E-01 2.50E-01 5.00E-01 4.51E+02 9.03E+02 6.36E-03 1.24E-02 6.77E-02 1.36E-01 1.19E+02 2.36E+02 4.0000 h 1.64E+00 8.18E-01 9.00E-01 4.50E-01 1.77E+03 8.87E+02 2.23E-02 1.03E-02 2.68E-01 1.34E-01 4.60E+02 2.25E+02 ;

8.0000 h 2.49E+00 6.23E-01 1.49E+00 3.72E-01 3.40E+03 8.50E+02 3.46E-02 7.70E-03 5.10E-01 1.24E-01 8.65E+02 2.10E+02 6.27E-01 !

8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.57E-04 2.23E-05 1.06E-02 3.66E-04 1.80E+01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.47E-05 7.60E-07 1.71E-03 1.66E-05 3.23E+00 3.75E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.29E-06 1.04E-12 5.23E-05 3.22E-11 1.2SE-01 9.83E-08 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 2.31E-12 0.00E+00 7.26E-11 0.00E+00 2.22E-07 0.00E+00 ;

TOTALS 6.29E+00 3.48E+00 7.00E+03 8.47E-02 1.06E+00 1.80E+03 L

t ERS-SFL-96-010 FRP 2.95 gpm Cases Attachment 4 Page 13() !

TRAILS -- Transport of Radioactive Material in Linear Syste.as, v2.0 FRC Case for dose for LPZ 1 gpm [TC961008.DAT]

ENVIRONMENT-------- -

C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DN RATk' DOSE DOSE RATE D0ai, DOSE RATE DOSE DOSE RATE arem mresn/hr mrem mren/hr mrem mresm/hr arem mren/hr larem mrem /hr arem aren/hr ALL NUCLIDES 0.5000 h 1.37E-01 2.74E-01 5.39E-02 1.08E-01 3.05E+01 6.10E+01 1.04E-03 3.98E-03 8.25E-03 3.17E-02 4.93E+00 1.94E+01 1.0000 h 3.63E-01 7.27E-01 1.39E-01 2.78E-01 8.60E+01 1.72E+02 1.76E-03 3.13E-03 1.42E-02 2.57E-02 9.37E+00 1.81E+01 1.5000 h 5.51E-01 1.10E+00 2.12E-01 4.24E-01 1.41E+02 2.82E+02 1.44E-03 2. 0"TE-03 1.20E-02 2.24E-02 8.95E+00 1.77E+01 2.0000 h 7.10E-01 1.42E+00 2.76E-01 5.51E-01 1.96E+02 3.91E+02 1.68E-03 3.97E-03 1.44E-02 3.47E-02 1.11E+01 2.65E+01 4.0000 h 4.07E+00 2.03E+00 1.62E+00 8.10E-01 1.32E+03 6.59E+02 1.40E-02 9.27E-03 1.26E-01 8.53E-02 1.08E+02 7.73E+01 8.0000 h 6.36E+00 1.59E+00 2.84E+00 7.09E-01 3.37E+03 8.43E+02 4.14E-02 1.14E-02 4.20E-01 1.21E-01 4.87E+02 1.54E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.67E-04 3.19E-05 1.03E-02 3.45E-04 1.32E+01 4.58E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.16E-04 7.19E-07 1.44E-03 1.16E-05 2.33E+00 2.63E-02 06.0000 h 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 2.04E-06 6.83E-13 3.49E-05 1.51E-11 8.70E-02 6.54E-08 730.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.50E-12 0.00E+00 3.36E-11 0.00E+00 1.47E-07 0.00E+00 TOTALS 1.22E+01 5.14E+00 5.14E+03 6.25E-02 6.07E-01 6.45E+02 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 MC Case for dose for LPZ 3 gpm [TC961009.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem arem/hr mrem mrem /hr ALL NUCLIDES 0.5000 h 4.11E-01 8.21E-01 1.62E-01 3.23E-01 9.15E+01 1.83E+02 3.13E-03 1.19E-02 2.47E-02 9.50E-02 1.48E+01 5.82E+01 1.0000 h 1.09E+00 2.18E+00 4.17E-01 8.35E-01 2.58E+02 5.16E+02 5.29E-03 9.40E-03 4.27E-02 7.70E-02 2.81E+01 5.43E+01 1.5000 h 1.65E+00 3.30E+00 6.35E-01 1.27E+00 4.22E+02 8.45E+02 4.33E-03 8.00E-03 3.59E-02 6.71E-02 2.68E+01 5.30E+01 2.0000 h 2.13E+00 4.25E+00 8.25E-01 1.65E+00 5.85E+02 1.17E+03 5.02E-03 1.19E-02 4.31E-02 1.04E-01 3.32E+01 7.94E+01 4.0000 h 1.22E+01 6.08E+00 4.84E+00 2.42E+00 3.94E+03 1.97E+03 4.20E-02 2.77E-02 3.78E-01 2.55E-01 3.24E+02 2.31E+02 8.0000 h 1.89E+01 4.73E+00 8.43E+00 2.11E+00 1.00E+04 2.51E+03 1.23E-01 3.40E-02 1.25E+00 3.59E-01 1.45E+03 4.57E+02 8.50C0 h 0.00E+00 0.00E+00 0.00E+00 0.00R+00 0.00E+00 0.00E+00 2.88E-03 9.48E-05 3.05E-02 1.03E-03 3.92E+01 1.36E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.46E-04 2.14E-06 4.28E-03 3.45E-05 6.93E+00 7.84E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.07E-06 2.03E-12 1.04E-04 4.48E-11 2.59E-01 1.94E-07 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.47E-12 0.00E+00 9.96E-11 0.00E+00 4.38E-07 0.00E+00 TOTALS 3.64E+01 1.53E+01 1.53E+04 1.86E-01 1.81E+00 1.92E+03 ERS-SFL-96-010 FRC Cases for EAB / LPZ / CR Attachment 4 Pagel 3 i

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 B C Case for dose for LPE 5 gpat [TC961010.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem mrem /hr mrent mrem /hr arem arem/hr arem mrem /hr arem arem/hr arem area /hr I-135 TOTALP 1.97E+01 5.95E+00 8.08E+02 1.12E-01 6.73E-01 9.14E+01 ALL NUCLIDES 0.5000 h 6.84E-01 1.37E+00 2.69E-01 5.38E-01 1.52E+02 3.05E+02 5.21E-03 1.99E-02 4.12E-02 1.58E-01 2.46E+01 9.70E+01 1.0000 h 1.81E+00 3.63E+00 6.95E-01 1.39E+00 4.29E+02 8.59E+02 8.82E-03 1.57E-02 7.11E-02 1.28E-01 4.68E+01 9.05E+01 1.5000 h 2.75E+00 5.49E+00 1.06E+00 2.11E+00 7.03E+02 1.41E+03 7.21E-03 1.33E-02 5.98E-02 1.12E-01 4.47E+01 8.83E+01 2.0000 h 3.54E+00 7.07E+00 1.37E+00 2.75E+00 9.74E+02 1.95E+03 8.36E-03 1.98E-02 7.18E-02 1.73E-01 5.53E+01 1.32E+02 4.0000 h 2.02E+01 1.01E+01 8.05E+00 4.02E+00 6.54E+03 3.27E+03 6.98E-02 4.61E-02 6.29E-01 4.24E-01 5.20E+02 3.84E+02 8.0000 h 3.13E+01 7.82E+00 1.39E+01 3.48E+00 1.65E+04 4.14E+03 2.05E-t.d 5.61E-02 2.07E+00 5.93E-01 2.40E+03 7.56E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.76E-05 1.57E-04 5.04E-02 1.70E-03 6.46E+01 2.25E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.72E-04 3.54E-06 7.07E-03 5.69E-05 1.15E+01 1.30E-01 06.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-05 3.36E-12 1.71E-04 7.38E-11 4.28E-01 3.21E-07 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.39E-12 0.00E+00 1.64E-10 0.00E+00 7.24E-07 0.00E+00 TOTALS 6.03E+01 2.54E+01 2.53E+04 3.09E-01 3.00E+00 3.19E+03 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRC Case for dose for LPZ 7 gpm [TC961011.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem arem/hr mrem mrem /hr mrem mrem /hr ALL NUCLIDES 0.5000 h 9.57E-01 1.91E+00 3.77E-01 7.54E-01 2.13E+02 4.27E+02 7.30E-03 2.79E-02 5.77E-02 2.21E-01 3.45E+01 1.36E+02 1.0000 h 2.54E+00 5.07E+00 9.72E-01 1.94E+00 6.01E+02 1.20E+03 1.23E-02 2.19E-02 9.95E-02 1.79E-01 6.55E+01 1.27E+02 1.5000 h 3.84E+00 7.68E+00 1.48E+00 2.96E+00 9.83E+02 1.97E+03 1.01E-02 1.87E-02 8.36E-02 1.57E-01 6.25E+01 1.24E+02 2.0000 h 4.94E+00 9.88E+00 1.92E+00 3.84E+00 1.36E+03 2.72E+03 1.17E-02 2.77E-02 1.00E-01 2.42E-01 7.74E+01 1.85E+02 4.0000 h 2.82E+01 1.41E+01 1.12E+01 5.61E+00 9.12E+03 4.56E+03 9.74E-02 6.43E-02 8.78E-01 5.91E-01 7.51E+02 5.36E+02 8.0000 h 4.34E+01 1.09E+01 1.93E+01 4.83E+00 2.30E+04 5.74E+03 2.85E-01 7.80E-02 2.88E+00 8.23E-01 3.34E+03 1.05E+03 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.61E-03 2.18E-04 7.00E-02 2.36E-03 8.99E+01 3.13E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.94E-04 4.91E-06 9.81E-03 7.90E-05 1.59E+01 1.80E-01 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.39E-05 4.66E-12 2.37E-04 1.02E-10 5.94E-01 4.46E-07 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E-11 0.00E+00 2.28E-10 0.00E+00 1.01E-06 0.00E+00 TOTALS 8.39E+01 3.53E+01 3.52E+04 4.31E-01 4.18E+00 4.44E+03 ERS-SFL-96-010 FRC Cases for EAB / LPZ / CR Attachment 4 Page132

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 PRC Case for dose for EAB 1 gym [TC961028.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE TRY CDE-INHAL 4

DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE ~ DOSE RATE arem meen/hr arem arem/hr arem arem/hr arena aren/hr arem aren/hr arem aram/hr I-135 4

TOTALS 8.66E+00 2.62E+00 3.55E+02 0. 00P 00 0.00E+00 0.00E+00 ALL NUCLIDES 0.5000 h 2.79E+00 5.58E+00 1.10E+00 2.20E+00 6.21E+02 1.24E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 7.40E+00 1.48E+01 2.84E+00 5.67E+00 1.75E+03 3.50E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

, 1.5000 h 1.12E+01 2.24E+01 4.32E+00 8.64E+00 2.87E+03 5.75E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.45E+01 2.89E+01 5.61E+00 1.12E+01 3.98E+03 7.97E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ 0.00E+00 0.00E+00 TOTALS 3.59E+01 1.39E+01 9.23E+03 0.00E+00 0.00E+00 0.00E+00 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0

, Mtc Case for dose for EAB 3 gym [TC961029.DAT]

ENYIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE -THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE COSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem ares /hr arem aren/hr arem aren/hr arem arem/hr arem aren/hr arem arem/hr I-135 TOTALS 2.59E+01 7.84E+00 1.06E+03 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES 0.5000 h 8.36E+00 1.67E+01 3.29E+00 6.58E+00 1.86E+03 3.73E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2.22E+01 4.44E+01 8.50E+00 1.70E+01 5.25E+03 1.05E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 3.36E+01 6.72E+01 1.29E+01 2.S9E+01 8.60E+03 1.72E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 4.33E+01 8.66E+01 1.68E+01 3.3CE+01 1.19E+04 2.38E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,0.00E+00 0.00E+00 TOTALS 1.07E+02 4.15E+01 2.76E+04 0.00E+00 0.00E+00 0.00E+00 C

ERS-SFL-96-010 FRC Cases for EAB / LPZ/ CR Attachment 4 Page 133

i I

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0' BC Case for dose for EAR 5 gym [TC961030.DAT] i

ENVIRONNENT--------- -------C0NTROL ROOM-------

External EDE sEIN-DE TRY CDE-INEAL External EDE SKIN-DE TRY CDE-INEAL ;

DOSE Dose RATE DOSE Dose RATE Dose Dose RATE Dose DOSE RATE nose Dose RATE Dose Dose RATE arem arem/hr arem aren/hr arem aren/hr arem arem/hr aren area /hr arem area /hr I-135 1.77E+03 0.00E+00 0.00E+00 TOTALS 4.31E+01 1.31E+01 0.00E+00 I

ALL NUCLIDES ;

0.5000 h 1.39E+01 2.79E+01 5.48E+03 1.10E+01 3.10E+03 6.21E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !

1.0000 h 3.69E+01 7.39E+01 1.42E+01 2.83E501 8.75E+03 1.75E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !

1.5000 h 5.60E+01 1.12E+02 2.15E+01 4.31E+01 1.43E+04 2.86E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s 2.0000 h 7.20E+01 1.44E+02 2.80E+01 5.59E+01 1.98E+04 3.97E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i TOTALS 1.79E+02 6.91E+01 4.60E+04 0.00E+00 0.00E+00 0.00E+00 ,

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 D C Case for dose for EAB 7 gym [TC961031.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

-External EDE SKIN-DE TRY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE Dose RATE DOSE DOSE RATE ,

arem uren/hr -arem arem/hr arem area /hr arem aress/hr arena aren/hr arem mren/hr -

I-135 !

TOTALS C -EM01 1.82E+01 2. 4tsE+03 0.00E+00 0.00E+00 0.00E+00 [

ALL NUCLIDES .

0.5000 h 1.95E+01 3.90E+01 7.67E+00 1.53E+01 4.34E+03 8.69E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !

1.0000 h 5.17E+01 1.03E+02 1.98E+01 3.96E+01 1.22E+04 2.45E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 7.82E+01 1.56E+02 3.01E+01 6.02E+01 2.00R+04 4.00E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 2.0000 h 1.01E+02 2.01E+02 3.91E+01 7.81E+01 2.77E+04 5.54E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f TOTALS 2.50E+02 9.f>6E+01 6.43E+04 0.00E+00 0.00E400 0.00E+00

i i

ERS-SFL-96-Og0 Attachment 4 Page d d FRC Cases for EAB / LPZ / CR j

~. - -z_ . - - ,. - - - -, .- m. - - - - - , ,-__ .-~ _ _- - . - - ,,,

TRAILS -- Transport of Radioactive Material in Linear systems, v2.0 ERP Case for LPZ dose [TC961012.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE ItATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr mrem ares /hr aren mrem /hr mrem aren/hr mrem arem/hr mrem aren/hr ALL NUCLIDES 0.5000 h 2.08E-01 4.17E-01 1.02E-01 2.03E-01 1.57E+02 3.13E+02 1.64E-03 6.38E-03 1.61E-02 6.27E-02 2.53E+01 9.98E+01 1.0000 h 1.89E-01 3.79E-01 9.49E-02 1.90E-01 1.56E+02 3.11E+02 2.90E-03 5.28E-03 2.89E-02 5.33E-02 4.74E+01 8.98E+01 1.5000 h 1.74E-01 3.48E-01 8.95E-02 1.79E-01 1.55E+02 3.09E+02 2.42E-03 4.44E-03 2.47E-02 4.59E-02 4.27E+01 8.10E+01 2.0000 h 1.62E-01 ?.24E-01 8.51E-02 1.70E-01 1.54E+02 3.07E+02 2.16E-03 4.20E-03 2.30E-02 4.60E-02 4.03E+01 8.00E+01 4.0000 h 5.58E-01 2. *7 9E-01 3.07E-01 1.54E-01 6.05E+02 3.03E+02 7.59E-03 3.51E-03 9.11E-02 4.56E-02 1.56E+02 7.66E+01 8.0000 h 8.56E-01 2.14E-01 5.12E-01 1.28E-01 1.17E+03 2.92E+02 1.18E-02 2.64E-03 1.74E-01 4.26E-02 2.95E+02 7.18E+01 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.25E-04 7.64E-06 3.64E-03 1.25E-04 6.16E+00 2.14E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.24E-05 2.60E-07 5.86E-04 5.68E-06 1.11E+00 1.28E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.83E-07 3.57E-13 1.79E-05 1.10E-11 4.28E-02 3.37E-08 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.92E-13 0.00E+00 2.49E-li 0.00E+00 7.59E-08 0.00E+00 TOTALS 2.15E+00 1.19E+00 2.40E+03 2.88E-02 3.62E-J1 6.14E+02 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 3 gpm LPE dose ['IC961013.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INEAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE ! ATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /br mrem mrem /hr mrem arern/hr mrem mrem /hr ALL NUCLIDES 0.5000 h 6.25E-01 1.25E+00 3.05E-01 6.09E-01 4.70E+02 9.39E+02 4.93E-03 1.91E-02 4.82E-02 1.88E-01 7.60E+01 2.99E+02 1.0000 h 5.67E-01 1.13E+00 2.84E-01 5.68E-01 4.66E+02 9.32E+02 8.71E-03 1.58E-02 8.67E-02 1.60E-01 1.42E+02 2.69E+02 1.5000 h 5.21E-01 1.04E+00 2.68E-01 5.35E-01 4.63E+02 9.25E+02 7.26E-03 1.33E-02 7.42E-02 1.38E-01 1.28E+02 2.43E+02 2.0000 h 4.84E-01 9.67E-01 2.54E-01 5.08E-01 4.59E+02 9.18E+02 6.47E-03 1.26E-02 6.88E-02 1.38E-01 1.21E+02 2.40E+02 4.0000 h 1.66E+00 8.31E-01 9.16E-01 4.58E-01 1.80E+03 9.02E+02 2.27E-02 1.05E-02 2.73E-01 1.36E-01 4.68E+02 2.29E+02 8.0000 h 2.53E+00 6.33E-01 1.51E+00 3.79E-01 3.46E+03 8.65E+02 3.52E-02 7.83E-03 5.18E-01 1.26E-01 8.79E+02 2.13E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.68E-04 2.27E-05 1.08E-02 3.72E-04 1.83E+01 6.37E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.62E-05 7.73E-07 1.74E-03 1.68E-05 3.29E+00 3.82E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.33E-06 1.06E-12 5.32E-05 3.27E-11 1.27E-01 1.00E-07 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.35E-12 0.00E+00 7.38E-11 0.00E+00 2.25E-07 0.00E+00 TOTALS 6.39E+00 3.54E+00 7.12E+03 8.61E-02 1.08E+00 1.84E+03 ERS-SFL-96-010 FRP Cases for EAB / LPZ / CR Attachment 4 Page 13 9

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 nt.P Case for 5 gpm LPZ dose [TC961014.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY'CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr ALL NUCLIDES 0.5000 h 1.04E+00 2.08E+00 5.07E-01 1.01E+00 7.82E+02 1.56E+03 8.21E-03 3.19E-02 8.03E-02 3.13E-01 1.27E+02 4.98E+02 1.0000 h 9.43E-01 1.89E+00 4.73E-01 9.45E-01 7.75E+02 1.55E+03 1.45E-02 2.64E-02 1.44E-01 2.66E-01 2.37E+02 4.49E+02 1.5000 h 8.66E-01 1.73E+00 4.45E-01 8.90E-01 7.69E+02 1.54E+03 1.21E-02 2.22E-02 1.24E-01 2.29E-01 2.13E+02 4.05E+02 2.0000 h 8.03E-01 1.61E+00 4.22E-01 8.44E-01 7.62E+02 1.52E+03 1.08E-02 2.10E-02 1.15E-01 2.29E-01 2.01E+02 3.99E+02 4.5000 h 2.75E+00 1.38E+00 1.52E+00 7.57E-01 2.98E+03 1.49E+03 3.78E-02 1.74E-02 4.53E-01 2.26E-01 7.78E+02 3.80E+02 8.0000 h 4.16E+00 1.04E+00 2.49E+00 6.22E-01 5.68E+03 1.42E+03 5.83E-02 1.29E-02 8.57E-01 2.09E-01 1.45E+03 3.52E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.10E-03 3.74E-05 1.78E-02 6.13E-04 3.02E+01 1.05E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E490 1.59E-04 1.27E-06 2.87E-03 2.78E-05 5.43E+00 6.30E-02 96.0000 h 0.00E+00 0.003+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.04E-06 1.75E-12 8.77E-05 5.39E-11 2.10E-01 1.65E-07 1 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0e 3.88E-12 0.00E+00 1.22E-10 0.00E+00 3.72E-07 0.00E+00 TOTALS 1.06E+01 5.85E+00 1.18E+04 1.43E-01 1.79E+00 3.05E+03 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 5 gpm LPZ dose [TC961015.DAT]

ENVIRONMENT- -------- -------CONTROL ROOM- ------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mrem /hr mrem mre.m/hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr ALL NUCLIDES 0.5000 h 1.46E+00 2.91E+00 7.10E-01 1.42E+00 1.09E+03 2.19E+03 1.15E-02 4.46E-02 1.12E-01 4.38E-01 1.77E+02 6.97E+02 1.0000 h 1.32E+00 2.64E+00 6.61E-01 1.32E+00 1.08E+03 2.17E+03 2.03E-02 3.69E-02 2.02E-01 3.73E-01 3.31E+02 6.28E+02 1.5000 h 1.21E+00 2.42E+00 6.21E-01 1.24E+00 1.07E+03 2.15E+03 1.69E-02 3.10E-02 1.73E-01 3.20E-01 2.98E+02 5.66E+02 2.0000 h 1.12E+00 2.24E+00 5.88E-01 1.18E+00 1.06n+03 2.12E+03 1.51E-02 2.93E-02 1.60E-01 3.21E-01 2.81E+02 5.58E+02 4.0000 h 3.83E+00 1.91E+00 2.11E+00 1.05E+00 4.15E+03 2.07E+03 5.28E-02 2.43E-02 6.33E-01 3.15E-01 1.09E+03 5.31E+02 8.0000 h 5.75E+00 1.44E+00 3.44E+00 8.59E-01 7.84E+03 1.96E+03 8.10E-02 1.79E-02 1.19E+00 2.89E-01 2.02E+03 4.88E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.53E-03 5.19E-05 2.47E-02 8.49E-04 4.18E+01 1.46E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.20E-04 1.77E-06 3.97E-03 3.85E-05 7.52E+00 8.73E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.32E-06 2.42E-12 1.21E-04 7.46E-11 2.91E-01 2.29E-07 720.G000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.38E-12 0.00E+00 1.68E-10 0.00E+00 5.16E-07 0.00E+00 TOTALS 1.47E+01 8.12E+00 1.63E+04 1.99E-01 2.50E+00 4.25E+03 ERS-SFL-96-010 FRP Cases for EAB / LPZ / CR Attachment 4 Page 13 9

i TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 ,

NRP Case for 5 gym LPE dose [TC961014.DAT]

-----ENYIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INEAL External EDE SKIN-DE THY CDE-INEAL [

DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE BATE arem aren/hr uren aren/hr arem aren/hr area arem/hr arem arem/hr arem arem/hr I-135 TOTALS 3.84E+00 1.16E+00 1.58E+02 4.02E-02 2.42E-01 3.29E+01 4

ALL NUCLIDES 0.5000 h 1.04E+00 2.0BE+00 5.07E-01 1.01E+00 7.82E+02 1.56E+03 6.70E-03 2.60E-02 6.56E-02 2.56E-01 1.03E+02 4.07E+02 1.0000 h 9.43E-01 1.89E+00 4.73E-01 9.45E-01 7.75E+02 1.55E+03 1.18E-02 2.15E-02 1.18E-01 2.17E-01 1.93E+02 "t . 6e+ 02 -

, 1.5000 h 8.66E-01 1.73E+00 4.45E-01 8.90E-01 7.69E+02 1.54E+03 9.87E-03 1.81E-02' 1.01E-01 1.87E-01 1.74E+02 3.~t0E+02 i 2.0000 h 8.03E-01 1.61E+00 4.22E-01 8.44E-01 7.62E+02 1.52E+03 8.79E-03 1.71E-02 9.35E-02 1.87E-01 1.64E+02 3.262+02 l 4.0000 h 2.75E+00 1.38E+00 1.52E+00 7.57E-01 2.98E403 1.49E+03 3.08E-02 1.42E-02 3.70E-01 1.84E-01 6.35E+02 3.10E+02 ;

8.000C h 4.16E+00 1.04E+00 2.49E+00 6.22E-01 5.68E+03 1.42E+03 4.76E-02 1.05E-02 6.99E-01 1.70E-01 1.19E+03 2.87E+02 l 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.00E-04 3.05E-05 1.46E-02 5.00E-04 2.46E+01 8.58E-01 ;

24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.30E-04 1.04E-06 2.34E-03 2.27E-05 4.432+00 5.14E-02 r 96.G000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.13E-06 1.43E-12 7.16E-05 4.40E-11 1.71E-01 1.35E-07 l 720.0000 h f.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.17E-12 0.00E+00 9.93E-11 0.00E+00 3.04E-07 0.00E+00 f TOTALS 1.06E+01 5.85E+00 1.18E+04 1.17E-01 1.46E+00 2.49E+03 i TRAILS -- Transport of Radioactive Material in Linear Systms, v2.0 {

ERP Case for 7 gym LPE dose [TC961015.DAT] ,

t

ENYIRONMENT--------- -------C0NTROL ROOM------- ,

TRY CDE-INHAL External EDE SKIN-DE THY CDE-INEAL External EDE SKIN-DE DOSE DOSE RATE DOSE DOSE BATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE !

arem mram/hr arem area /hr arem arem/hr arem aren/hr arem area /hr arem arem/hr j I-135 TOTALS 5.33E+00 1.61E+00 2.19E+02 5.61E-02 3.38E-01 4.59E+01 i t

ALL NUCLIDES f 0.5000 h 1.46E+00 2.91E+00 7.10E-01 1.42E+00 1.09E+03 2.19E+03 9.37E-03 3.64E-02 9.17E-02 3.58E-01 1.45E+02 5.C9E+02 1.0000 h 1.32E+00 2.64E+00 6.61E-01 1.32E+00 1.08E+03 2.17E+03 1.66E-02 3.01E-02 1.65E-01 3.04E-01 2.70E+02 5.12E+02 1.5000 h 1.21E+00 2.42E+00 6.21E-01 1.24E+00 1.07E+03 2.15E+03 1.38E-02 2.53E-02 1.41E-01 2.62E-01 2.43E+02 4.62E+02 2.0000 h 1.12E+00 2.24E+00 5.88E-01 1.18E+00 1.06E+03 2.12E+03 1.23E-02 2.39E-02 1.31E-01 2.62E-01 2.29E+02 4.56E+02 l 4.0000 h 3.83E+00 1.91E+00 2.11E+00 1.05E+00 4.15E+03 2.07E+03 4.31E-02 1.98E-02 5.16E-01 2.57E-01 8.87E+02 4.33E+02 8.0000 h 5.75E+00 1.44E+00 3.44E+00 8.59E-01 7.84E+03 1.96E+03 6.61E-02 1.46E-02 9.71E-01 2.36E-01 1.65E+03 3.98E+02 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.25E-03 4.23E-05 2.02E-02 6.93E-04 3.42E+01 1.19E+00 !

24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.80E-04 1.44E-06 3.24E-03 3.14E-05 6.14E+00 7.12E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.34E-06 1.98E-12 9.91E-05 6.09E-11 2.37E-01 1.87E-07 730.C000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 4.39E-12 0.00E+00 1.37E-10 0.00E+00 4.21E-07 0.00E+00 '

TOTALS 1.47E+01 8.12E+00 1.63E+04- 1.63E-01 2.04E+00 3.47E+03 ERS-SFL-96-010 FRP Cases for EAB / LPZ / CR Attachment 4 Page 137 .

i

_ _ _ _ _ . m___._ _.. . _ _ _ _ . _ _ _ . . _ _ _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _____.______.___._._______..___.._____________m

TRAILS -- Transport of Radioactive Material in Linear Systemas, v2.0 FRP Case for 1 gpua EAB dose [TC961032.DAT]

ENVIRONMENT------- -

CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-IK!IAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem aren/hr marem aresm/hr mrem mrema/hr marem stren/hr arena stresm/hr mrem arem/hr I-135 TOTALS 5.31E+00 1.61E+00 2.18E+02 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES 0.5000 h 4.24E+00 8.49E+00 2.07E+00 4.14E+00 3.19E+03 6.38E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 3.86E+00 7.71E+00 1.93E+00 3.86E+00 3.17E+03 6.34E+03 0.00E+00 0.00E+00 0.00E+00 0.90E+00 0.00E+00 0.00E+00 1.5000 h 3.55E+00 7.10E+00 1.82E+00 3.65E+00 3.15E+03 6.30E+C3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 3.30E+00 6.59E+00 1.73E+00 3.47E+00 3.13E+03 6. 2 6E+ 03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0P 0.00E+00 TOTALS 1.49E+01 7.56E+00 1.26E+04 0.00E+00 0.00E+00 0.00E+f0 e

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 3 gpea EAB dose [TC961033.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem aresm/hr arem mresm/hr mresa mrese/hr arem mresa/hr mrem aren/hr arest aresn/hr I-135 TOTALS 1.59E+01 4.81E+00 6.53E+02 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES 0.5000 h 1.2*/E+01 2.55E+01 6.20E+00 1.24E+01 9.57E+03 1.91E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 1.15E+01 2.31E+01 5.79E+00 1.16E+01 9.49E+03 1.90E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 1.06E+01 2.12E+01 5.45E+00 1.09E+01 9.42E+03 1.88E*04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+b0 0.00E+00 2.0000 h 9.85E+00 1.97E+f1 5.18E+00 1.04E+01 9.35E+03 1.87E+04 0.00E+00 0.00E+00 C.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 4.47E+01 2.26E+01 3.78E+04 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 FRP Cases for EAB / LPZ / CR Attachment 4 Page 138

TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 PRP Case for 5 gpsa ELB dose [TC961034.DAT]

ENVIRONMENT--------- -------CONTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE BATE DOSE DOSE RATE arem aren/hr arem arem/hr arem ares /hr arem mrem /hr mrem arem/br area arem/hr I-135 TOTALS 2.64E+01 7.99E+00 1.09E+03 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES 0.5000 h 2.12E+01 4.24E+01 1.03E+01 2.07E+01 1.59E+04 3.19E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0C 0.00E+00 1.0000 h 1.92E+01 3.84E+01 9.63E+00 1.93E+01 1.58E+04 3.16E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0CE+00 0.00E+00 1.5000 h 1.76E+01 3.53E+01 9.06E+00 1.81E+01 1.57E+04 3.13E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.C000 h 1.63E+01 3.27E+01 8.59E+00 1.72E+01 1.55E+04 3.10E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 7.44E+01 3.76E+01 6.29E+04 0.00E+00 0.00E+00 0.00E+00 TRAILS -- Transport of Radioactive Material in Linear Systems, v2.0 FRP Case for 7 gpm EAB dose [TC961035.DAT]

ENVIRONMENT--------- -------C0NTROL ROOM-------

External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr aren arem/hr arem arem/hr arem area /hr mrem aren/hr arem arem/hr I-135 TOTALS 3.69E+01 1.12E+01 1.52E+03 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES 0.50001h 2.97E+01 5.93E+01 1.45E+01 2.89E+01 2.23E+04 4.46E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.C000th 2.69E+01 5.37E+01 1.35E+01 2.69E+01 2.21E+04 4.41E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000ih 2.46E+01 4.92E+01 1.26E+01 2.53E+01 2.19E+04 4.37E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.C000 h 2.28E+01 4.56E+02 1.20E+01 2.40E+01 2.16E+04 4.33E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.04E+02 5.25E+01 8.79E+04 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-96-010 FRP Cases for EAB / LPZ / CR Attachment 4 Page 139

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l Attachment 4 Page 140 1

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ERS-SFL-96-010 Attachment 5 Pagd.il Release to Environment, uCi MSLB,2.95 gpm Primary-to-Secondary Leakage, Concurrent lodine Spike,0-2 hours Case = FRC FLI ITN ITC ILI ASA TOTAL Kr-83m 1.06E+05 0 7.52E+03 0 0 5.76E+01 1.14E+05 Kr-85m 6.33E+05 0 4.49E+04 0 0 2.80E+02 6.78E+05 Kr-85 3.90E+06 0 2.76E+05 0 0 1.48E+03 4.17E+06 Kr-87 2.57E+05 0 1.82E+04 0 0 1.61 E+02 2.75E+05 Kr-88 8.88E+05 0 6.29E+04 0 0 4.29E+02 9.51 E+05 Kr-89 1.35E+03 0 9.55E+01 0 0 1.35E+01 1.46E+03 Xe-131m 3.78E+04 0 2.68E+03 0 0 1.44 E+01 4.05E+04 Xe-133m 1.07E+06 0 7.60E+04 0 0 4.14E+02 1.15E+06 Xe-133 9.20E+06 0 6.52E+05 0 0 3.51 E+03 9.86E+06 Xe-135m 7.05E+04 0 4.99E+03 0 0 1.46E+02 7.56E+04 Xe-135 1.05E+06 0 7.42E+04 0 0 4.29E+02 1.12E+06 Xe-137 2.65E+03 0 1.87E+02 0 0 2.19E+01 2.86E+03 Xe-138 4.02E+04 0 2.84E+03 0 0 9.03E+01 4.32E+04 l-131 3.52E+07 3.09E+06 0 6.57E+05 1.12E+05 8.13E+03 3.90E+07 l-132 5.28E+07 9.04E+05 0 1.06E+06 2.49E+04 2.41 E+03 5.48E+07 l-133 7.74E+07 4.43E+06 0 1.45E+06 1.55E+05 1.17E+04 8.35E+07 l-134 5.86E+07 1.98E+04 0 1.32E+06 3.73E+02 5.37E+01 6.00E+07 l-135 6.70E+07 1.97E+06 0 1.27E+06 6.48E+04 5.22E+03 7.03E+07 t

EC961001.XLS

ERS-SFL-96-010 Attachment 5 Pagd_d.2_

Release to Environment, uCl MSLB,2.95 gpm Primary-to-Secondary Leakage, Preincident lodine Spike,0-2 hours Case = FRP FLI ITN ITP ILI ASA TOTAL Kr-83m 1.06E+05 0 7.52E+03 0 0 5.76E+01 1.14E+05 l Kr-85m 6.33E+05 0 4.49E+04 0 0 2.80E+02 6.78E+05 ;

Kr-85 3.90E+06 0 2.76E+05 0 1.48E+03

~

0 4.17E+06 Kr-87 2.57E+05 0 1.82E+04 0 0 1.61 E+02 2.75E+05 Kr-88 8.88E+05 0 6.29E+04 0 0 4.29E+02 9.51 E+05 Kr-89 1.35E+03 0 9.55E+01 0 0 1.35E+01 1.46E+03 Xe-131m 3.78E+04 0 2.68E+03 0 0 1.44 E+01 4.05E+04 Xe-133m 1.07E+06 0 7.60E+04 0 0 4.14E+02 1.15E+06 Xe-133 9.20E+06 0 6.52E+05 0 0 3.51 E+03 9.86E+06 Xe-135m 7.05E+04 0 4.99E+03 0 0 1.46E+02 7.56E+04 Xe-135 1.05E+06 0 7.42E+04 0 0 4.29E+02 1.12E+06 Xe-137 2.65E+03 0 1.87E+02 0 0 2.19E+01 2.86E+03 Xe-138 4.02E+04 0 2.84E+03 0 0 9.03E+01 4.32E+04 l-131 5.40E+07 3.09E+06 0 1.94E+06 1.12E+05 8.13E+03 5.91E+07 l-132 1.42E+07 9.04E+05 0 5.83E+05 2.49E+04 2.41 E+03 1.57E+07 l-133 8.20E+07 4.43E+06 0 2.98E+06 1.55E+05 1.17E+04 8.96E+07 l-134 5.96E+06 1.98E+04 0 2.91 E+05 3.73E+02 5.37E+01 6.27E+06 l-135 4.10E+07 1.97E+06 0 1.54E+06 6.48E+04 5.22E+03 4.46E+07 EC961001.XLS

ERS-SFL-96-010 Attachment 5 PageW Release to Environment, uCi MSLB,2.95 gpm Primary-to-Secondary Leakage, Concurrent lodine Spike,0-8 hours Case = FRC FLI ITN ITC ILI ASA TOTAL Kr-83m 1.89E+05 0 1.35 E+04 0 0 5.76E+01 2.03E+05 Kr-85m 1.68E+06 0 1.20E+05 0 0 2.80E+02 1.80E+06 Kr-85 1.54E+07 0 1.10E+06 0 0 1.48E+03 1.65E+07 Kr-87 3.81 E+05 0 2.71 E+04 0 0 1.61 E+02 4.08E+05 Kr-88 1.96E+06 0 1.40E+05 0 0 4.29E+02 2.10E+06 Kr-89 1.35E+03 0 9.55E+01 0 0 1.35E+01 1.46E+03 Xe-131m 1.49E+05 0 1.06E+04 0 0 1.44E+01 1.59E+05 Xe-133m 4.08E+06 0 2.92E+05 0 0 4.14E+02 4.37E+06 Xe-133 3.58E+07 0 2.56E+06 0 0 3.51 E+03 3.84E+07 Xe-135m 7.08E+04 0 5.00E+03 0 0 1.46E+02 7.60E+04 Xe-135 3.35E+06 0 2.39E+05 0 0 4.29E+02 3.59E+06 Xe-137 2.65E+03 0 1.87E+02 0 0 2.19E+01 2.86E+03 Xe-138 4.03E+04 0 2.85E+03 0 0 9.03E+01 4.33E+04 l-131 4.08E+08 3.09E+06 0 9.23E+05 3.12E+05 8.13E+03 4.12E+08 l-132 3.48E+08 9.04E+05 0 1.27E +06 4.04E+04 2.41 E+03 3.50E+08 l-133 8.42E+08 4.43E+06 0 2.00E+06 4.04 E+05 1.17E+04 8.49E+08 /

~

l-134 2.32E+08 1.98E+04 0 1.44E+06 4.32E+02 5.37E+01 2.34E+08 l-135 6.25E+08 1.97E+06 0 1.67E+06 1.44 E+05 5.22E+03 6.29E+08 l

EC961001.XLS

, .. - - . . _ -- - =. - -

i ERS-SFL-96-010 Attachment 5 Page f 4 4 Release to Environment, uCl MSLB,2.95 gpm Primary-to-Secondary Leakage, Preincident lodine Spike,0-8 hours Case = FRP FLI ITN ITP ILI ASA TOTAL

. Kr-83m 1.89E+05 0 1.35E+04 0 0 5.76E+01 2.03E+05 i Kr-85m 1.68E+06 0 1.20E+05 0 0 2.80E+02 1.80E+06 2 Kr-85 1.54E+07 0 1.10E+06 0 0 1.48E+03 1.65E+07 l Kr-87 3.81 E+05 0 2.71 E+04 0 0 1.61 E+02 4.08E+05 Kr-88 1.96E+06 0 1.40E+05 0 0 4.29E+02 2.10E+06

Kr-89 1.35E+03 0 9.55E+01 0 0 1.35E+01 1.46E+03 Xe-131m 1.49E+05 0 1.06E+04 0 0 1.44E+01 1.59E+05 j Xe-133m 4.08E+06 0 2.92E+05 0 0 4.14E+02 4.37E+06

Xe-133 3.58E+07 0 2.56E+06 0 0 3.51 E+03 3.84E+07 l Xe-135m 7.08E+04 0 5.00E+03 0 0 1.46E+02 7.60E+04 Xe-135 3.35E+06 0 2.39E+05 0 0 4.29E+02 3.59E+06 Xe-137 2.65E+03 0 1.87E+02 0 0 2.19E+01 2.86E+03

Xe-138 4.03E+04 0 2.85E+03 0 0 9.03E+01 4.33E+04

1-131 2.11 E+08 3.21 E+06 0 2.05E+06 3.12E+05 8.13E+03 2.17E+08

! l-132 2.84E+07 5.66E405 0 5.93E+05 4.04E+04 2.41 E+03 2.96E+07

, 1-133 2.95E+08 4.19E+06 0 3.14 E+06 4.04E+05 1.17E+04 3.03E+08 l-134 7.47E+06 9.72E+04 0 2.93E+05 4.32E+02 5.37E+01 7.86E+06 j 1-135 1.22E+08 1.52E+06 0 1.60E+06 1.44E+05 5.22E+03 1.25E+08 i

EC961001.XLS

RTL: nh Form: RE1.103-3 CC2 ggkm=10 M ERS-SFL-96-010 Appendix 1 Health Physics Department PO i

Note: This appendix was reviewed and approved as part of ERs-SFL-95-008 revision O. This appendix is intended to standardize the modeling assumptions and to eliminate the need to re-review these input parameters and assumptions with each new application. If a specific deviation from the information herein is necessary to meet the needs of a particular analysis,it should be described and justified in the main text of the package.

Generic Control Room Modeling

1. General This appendix describes the generic modeling of the Unit 1/ Unit 2 common control room. This modeling la essentially generic to all accidents. The values of the input parameters may vary from accident-to-accident and from case-to-case within an accident. Additionally, not all phases may be applicable to all cases. For example, radiation monitor initiated isolation might not occur, or may not be credited in the interest of simplifying the analysis (a conservative situation). The calculation package to which this appendix is attached will explain and justify any deviations. Figure 3 illustrates the generic modeling of the phases of alignment during an accident situation. Figure 4 is a representation of the CREBAPS actuation circuitry. ,

1

2. Control Room Ventilation System u .a.

l Figures 1 and 2 illustrate the normal system alignment of the U1 and U2 control room ventilation systems.

The systems in both sides of the control room operate independently, but are interlocked through the Control Room Emergency Breathing Air Prescurization System (CREBAPS). The following actuate CREBAPS:

. A Containment isolation Signal, Phase B (CIB) at either unit.

A high-high alarm on 1RM-RM-218A or B (Unit 1) or a high alarm on 2RMC*RQ201 or 202.

Chlorine detection alarms at either unit Note: There is no automatic transfer to emergency filtered intake for an isolation actuated by a chlorine alarm.

Manual operator action.

The normal system alignment is to have the control room envelope ventilation on recirculation at both units, with a small amount of make-up air via throttled intake bypass dampers. The intake flow at each unit is drawn through two in series motor operated dampers (NSA open) The four dampers (two at each unit) receive close signals from CREBAPS. The maximum intake flow is 33,500 cfm at Unit 1 and 18,000 cfm at Unit 2. However, this path at each unit is isolated by a motor operated damper (NSA shut). Bypass lines with a throttled damper and a motor operated damper are balanced to provide an unfiltered intake flow of 300 cfm from Unit 1 and 200 cfm from Unit 2.

There are two motor operated exhaust dampers at each unit, (NSA open at Unit 1, NSA shut at Unit 2).

These four dampers receive close signals from CREBAPS. At Unit 1, a motor operated damper upstream of the two exhaust dampers (NSA shut) isolates 'he exhaust during recirculation. The 500 cfm intake is dissipated by exfiltration through doorways and other penetrations.

A bottled air pressurization system, comprised of ten air bottles arranged in five sets of two with redundant actuation valves and circuitry, serves both units. Each set of bottles is sized to deliver 200 cfm for one hour in order to maintain control pressure slightly positive with relation to the outside environment.

At Unit 1, thers is a single filtered emergency intake train comprised of motor operated dampers (NSA shut), two 1000 cfm fans (NSA off), and one HEPA / charcoal filter train. A manual damper downstream of the filter is NSA shut as the NSA is to have Unit 2 supply the emergency filtered intake. At Unit 2, there are acssonouws

RTL: n/s Form: RE 1.103-3 C/92 Appendix 1 ERS-SFL-96-010 7A [ Qnmie lidit Health Physics Department page A1-2 two trains of motor operated dampers (NSA shut), fans (NSA off), and HEPA / charcoal filters. At both units, this filtered intake train bypasses the intake dampers.

On a CREBAPS actuation, all four intake dampers and all four exhaust dampers receive a close signal.

This isolates the normal intake. The air bottles start to release air to maintain a slight positive pressure, if the actuation was due to CIB or a radiation monitor alarm, a one hour timer is started. No timer is started on a chlorine actuation. When the one hour timer elapses, the air bleed is halted and the Unit 2 emergency filtered intake dampers open, and an emergency intake fan starts to maintain the control room slightly positive. The intake is dissipated by exfiltration through doorways and other penetrations.

The ventilation systems can be operated to purge the control roorn envelope, by opening the exhaust dampers, opening the full flow intake dampers, and closing the recirculation dampers. The air handlers draw in outside air and exhaust to the environment (33,500 cfm at Unit 1,18,000 cfm at Unit 2).

The control room ventilation intake (4) and exhaust (4) dampers, air handlers (4), and emergency filtered intake fans are powered from emergency AC buses.

2. Specific Ventilation Alignment During Accidents" 2.1 Prior to the start of the incident (T,, T < 0), the control room ventilation system is drawing in 500 cfm of unfiltered outside air. 300 cfm of this intake is via Unit 1 intakes, and 200 cfm is via Unit 2 intakes.

The intake is being removed via exfiltration through control room penetrations, seals, and doors.

Although the motor operated exhaust dampers are open, upstream isolation dampers are shut.

2.2 The accident starts at T,. The onset of the radioactive release is typically assumed to occur at T,.

Note that some of the accidents have multiple release paths and that the releases from these paths may start and terminate at different times. Regardless of the pathway or the timing of the release, activity transport in the buildings and environment is conservatively assumed to be instantaneous.

2.3 For the control room habitability, the process safety limit is set to 1 mR/hr. It was previously estab-lished by SWEC that the GDC 19 criteria 5 could be met if the ambient dose rate was kept less than 1 mR/hr*. The point in time that this dose rate is reached is designated T,. For cases involving manual operator action, T, = the time of the first indication that manual isolation is necessary.

2.4 As noted above, the ambient dose rate reaches 1 mR/hr at T, The monitor reading, however, does not necessarily ramp up at the same rate as the ambient dose rate builds up at. The monitor lag time will be a function of the rate of act:vity introduction. Once the alarm trip setpoint is reached, there will be delay in the damper movement. The total delay time is identified as T o The isolation time, T,,

equals T, + T,. For the DBA LOCA case, T., T,, T, are assumed to be 0. For the manual isolation case, T,is assumed to be the time that the manual isolation is complete.

2.4.1 For Unit 1, the ARM does not lose power. Therefore a loss of power during the monitor reading ramp-up will not cause a delay in the monitor reaching the trip setpoint. Reference 7 indicates that the time to reach 1 mR/hr is 97 seconds. If the power is lost at that time, the dampers will not close for 77 seconds (i.e., diesel start, sequencing, damper movement).

Thus, the maximum delay was shown to be 97 + 77 seconds or slightly less than 3 minutes.

SWEC assumed T, = 3 minutes in all Unit 1 calculations 7 2.4.2 For Unit 2, Reference 6 notes that the ARM ramps up in about 107 seconds to 1 mR/hr. The maximum ramp time was shown to be 128 seconds, which SWEC assumed to be the time used. The damper closure time is 10 seconds, with a signal processing time of 2 seconds.

This yields a delay of 140 seconds or, T, = 2.33 minutes. The SWEC analysis notes that although the Unit 2 ARM does lose power, doing so just prior to reaching the trip setpoint does not add significantly to the monitor ramp time.

acesmouws

RTL: nh Fum: RE1.103-3 SM2 ggDmme @ ERS-SFL-96-010 Appendix 1 page A1-3 Health Physics Department 2.4.3 The assumption in the original record of analysis' for Unit 1 is that non-vital AC power is lost just prior to the damper movement.. For Unit 2, SWEC assumed that the loss of non-vital power occurred concurrent with the accident initiation *. Although these two bases are different, it must be remembered that the assumption regarding instantaneous transport of the radioactivity to the control room provides margin to compensate for the difference.

2.4.4 in 1993, DLC was notified by Limitoique' that under certain seismic events, the valve opera-tors may malfunction and not close upon receipt of the shut signal. This malfunction ceases once the seismic event has abated, and the valve operator goes shut at that time. A maxi-mum delay time of 15 seconds was established, consistent with the design basis assumption of a 15 second seismic envelope. As a result, the isolation delay times in 12.4.2 are in-creased:, T, = 2.33 min + 15 seconds = 2.58 minutes Unit 1; T, = 3 min + 15 seconds =

3.25 minutes Unit 20S".

2.4.5 For the DBA LOCA, control room isolation is actuated by a CIB signal. No time delay is modeled for diesel loading and damper movement in the licensing basis calculations, in Reference 12, SWEC postulated an environmental transport time of 121 seconds between the Unit 1 release point and the control room intake. For Unit 2, Reference 13 provided a transport time of 142 seconds. Both of these transport times are in excess of the damper closure delay times under CIB conditions.

l 2.5 At T,, CREBAPS has shut the normal intake dampers, and has shut the exhaust dampers. An air ;

bleed from the air bottles is commenced. Also at this time, a 60 minute timer is started. During the time between T, and T,, it is conservatively assumed that the control room intake continues at 500 cfm. After T,, the intake drops to zero and an infiltration rate of 10 cfm is assumed".

Note: Although the dampers may not be able to close due to loss of AC power until the dieselgenera- ,

for loads, it is important to note that the fan motors also lose power. The flow rate would coast down once the fan motor was de-energized. In accordance with Reference 14 it would be acceptable to \

assume the intake flow rate to be 50% of the measured exfiltration rate, or 350 cim. This is generally i not modeled as the difference is generallyinsignificant to the overall results.

2.6 The pressurization system will bleed air at a rate sufficient to maintain the requisite pressure. Based on earlier testing, reported in References 6 and 7,690 cfm would be needed to maintain the specified pressure differential. In order to account for the specified infiltration rate, the exfiltration rate is set to 690 + 10 or 700 cfm.

2.7 At one hour beyond CREBAPS actuation (assumed to be equal to T,+ 3600s), the air bleed is auto- .

matically terminated and outside air is drawn through filters via the emergency pressurization intake ;

dampers and fans. Since the exfiltration rate was assumed to be 700 cfm, the fans are assumed to l draw in outside air at a rate of 700 cfm. The emergency intake fans are rated at 1000 cfm, however, the actual intake flow is limited by the available exfiltration flow rate. Note that only 690 cfm of the intake is filtered. The 10 cfm infiltration rate is not filtered. The filter efficiency is reduced to:

pp , (0.95)(690)+(0.0)(10) - 0.936 690 + 10 2.7.1 Technical specification 3/4.7.7" addresses control room habitability systems. Operability requirements require testing for less than 1% leakage and a methyllodine removal efficiency greater than 99%. In accordance with Regulatory Guide 1.52", assigned efficiencies are 95%

for elemental and organic lodines.

acesoeowus

RTL: n/2 Form: RE 1.103-3 (K2 g ERS-SFL-96-010 Appendix 1 7g5' Heahh Physics Department page A1-4 2.8 The ventilation system remains in this alignment through the remainder of the event for many acci-dent sequences. For the remaining sequences, the control room is purged for 30 minutes commenc-ing at T=8 hours. The purge and exhaust are unfiltered and have flow rates of 33,500 cfm at Unit 1, and 18,000 cfm at Unit 2.

2.9 At the completion of the purge and continuing through to the end of the assessment period (i.e.,720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months ), the flow rates return to their original value of 500 cfm.

3. Control Room Model Parameters 3.1 Control Room Volume = 1.73E+5 ft* [4 - Tbl 6.4-1]

3.2 Normalventilation intake: BV1 = 300 cfm; BV2 = 200 cfm [4 - Tbl 6.4-1]

3.3 Filter efficiency = 93.6% [12.7 above]

3.4 Purge Flow Rate: BV1 = 33,500 cfm; BV2 = 18,000 cfm [3 - 99.13.4, 4 - Tbl 9.4-3]

Note: the licensing basis calculations assumed a purge flow of 20,000 cfm. The flow thru the ACUS was subsequently determined to be 18,000 which is reflected on U2 UFSAR Figure 9.4-1 and Table 9.4-3. These values conflict with the value in Table 6.4-1, which appears to be outdated. Purging was not a significant factor in the analyses.

3.5 Air pressurization flow rate for first hour: 690 cfm [3,4,6,7]

3.6 Filtered air intake flow rate: 700 cfm (See below)

The design capacity of the fan is 1000 cim. However, by testing the amount of air bottle flow needed to maintain the requisite pressure differential, the extiltration rate has been deemed to be 690 cfm +

10 cfm unfilteredinleakage. Thus, the intake willbe constrained by the exfiltration capability. Thus, the analysis assumes an fan intake flow rate of 700 cfm.

3.7 isolation delays based on radiation monitor actuation AC Power Loss @ damper [7] @T=0 [6]

movement Diesel Start n/a (1) n/a (2)

DieselSequence n/a (1) n/a (2)

Damper Movement n/a (1) 12 sec [6]

Sum 77 see 12 sec [6]

RMS Response 97 sec [7] 128 sec [6]

Seismic Delay 15 sec [10,11] 15 sec [10,11]

Total 195 sec (3) 155 sec (1) U1 T/S ESF actuation timing Table 3.3-5 specifies a control room isolation response of 22 seconds without diesel starting and sequencing and 77 seconds with diesel starting and sequencing included based on CIB. The 22 second period would include damper movement, CNMT pressure sensor response time, and circuitry delays. (The actual breakdown is unknown). Per OST', the diesel start and sequencing delay to the step at which the dampers are powered is 10 + 40 4 seconds.

Acasosoins

I RTL: n/2 Form: RE 1.103 3 692 l

gg MM Appendix 1 pg5' Heahh Physics Department ERS-SFL-96-010 page A1-5 (2) The RMS response delay includes the diesel start and sequencing delays.

(3) SWEC rounded the original sum of 174 to 180.

3.8 Isolation delays based on CIB actuation AC Power Loss @ damper [7] @T=0 [6]

movement l

Diesel Start n/a (1) 10 sec [18]

DieselSequence n/a (1) 40 4 sec [18]

Damper Movement n/a (1) 12 sec [6]

Sum 77 sec 12 sec [6]

Seismic Delay 15 sec [10,11] 15 sec [10,11]

l Total 92 sec 81 sec !

(1) See note 1 for datum 3.7.

3.9 Control Room yfQ, sec/m8- Unit 1 [3 - Tbl 2.2-12,19]

Bgjggse Point 0 8 hrs 8-24 hrs 14 davs 4-30 dava. l CNMT edge 4.33E-4 2.04E-4 1.46E-4 8.84E-5 CNMT top (SLCRS) 2.73E-4 1.28E-4 9.17E-5 5.57E-5 PAB 4.30E-3 2.01 E-3 1.49E-3 9.25E-4 MSVA 7.60E-4 3.51 E-4 2.59E-4 1.58E-4 Service Bldg 6.25E-4 3.04E-4 2.36E-4 1.57E-4 Turbine Bldg 2.43E-3 1.22E-3 8.90E-4 6.26E-4 Waste Gas Vault 5.11 E-4 2.15E-4 1.65E-4 1.14E-4 3.10 Control Room y/0, sec/m*- Unit 2 [4 - Tbl 15.0-14,19]

Release Point 0-8 hrs 8-24 hrs 1-4 days 4-30 davs CNMT edge 1.80E-4 9.32E-5 7.06E-5 4.18E-5 CNMT top (SLCRS) 1.20E-4 5.91 E-5 4.45E-5 2.64E-5 PAB 1.04E-3 5.15E-4 4.04E-4 2.46E-4 l MSVA 1.59E-4 7.86E 5 5.96E-5 3.7sE-5 Service Bldg 2.21 E-4 1.11 E-4 8.51 E-5 5.17E-5 Turbine Bldg 2.72E-4 1.43E-4 1.10E-4 6.30E-5 Waste Gas Vault 1.74E-3 9.36E-4 7.69E-4 5.55E-4 3.11 Occupancy Factors (20]

0-24 hrs 1.0 14 days 0.6

>4 days 0.4 i

l I

Acasoeot.PMS

. RTL: n/2 Form: RE 1.1054 &t2 Ak HomePhyshDepenment MM ERS-SFL-96-010 Page A1-6 )

REFERENCES l

I

1. DLC, BVPS-1 Operating Manual. Chapter 44C

2. DLC, BVPS-2 Ooeratina Manual. Chapter 44C

3. DLC, Undated Final Safety Analvsis Reoort Unit 1.

4. DLC, Uodated Final Safety Analysis Reoort Unit 2.

l S. USNRC, Criterion 19. Title 10 Code of Federal Regulations Part 50, Appendix A

6. SWEC, Control Room Habitability Due to Deslan Basis Accidents (except LOCA) at BV2.

12241-UR(B)-445, Revision 0; 1987

7. SWEC, Combined BV1-BV2 Control Room Hsitsmiv Due to Desian B--1= Ace! dents (aveent LOCA) at

Byl,12241-UR(B)-456, Revision 0,1987

. 8. Limitorque, Potentially Reoortable 10 CFR Part 21 Condition. ltr dtd 12/7/92 l' 9. DLC,10 CFR Part 21 Notice: Limitoraue Declutchina Mechanism. EM104392 dtd 12/21/92

' 10. DLC, Safety Analvsis of Conseauences of Control Room Damner Response Delav (Limitoraue 10 CFR 21) 4

- Unit 1 Accidents. ERS-SFL-93-005, Revision 0; 1993 l

11. DLC, Safety Analvsis of Conseauences of Control Room Damner Response Delav (Limitoraue 10 CFR 21)

- Unit 2 Accidents. ERS-SFL-93-004, Revision 0; 1993

12. SWEC. Doses to the Combined Control Room due to a LOCA at BVPS-1.12241-UR(B)-450, Revision 1

13. SWEC, FSAR Sec 15.6.5 Loss of Coolant Accident Analvsis Releases and Doses - Site and Control Room.12241 UR(B)-190, Revision 7; 1987

14. USRNC, Standard Review Plan for the Review of Safety Analysis Reoorts for Nuclear Power Plants.

NUREG-0800, Revision 5; 1987 (66.4.3)

15. DLC,- Technical Specification 3/4.7.7 (U1 and U2)

16. USNRC. Deslan. Testina. and Maintenance Criteria for Postaccident Enaineered Safetv Feeture Atmo-schere Cleanuo System Air Filtration and Adsorption Units of Licht Water Cooled Nuclamr Power Plants.

Regulatory Guide 1.52, Revision 2; 1978

17. DLC, BVPS 1 Operating Manual OST 1.36.3 (4)

18. DLC, BVPS-2 Oper'ating Manual OST 2.36.3 l

19. DLC, Control Room X/O Values for the Beaver Vallev Power Station (NUS Reoort EPC-91-1025).

ERS-NUS-92-020, Revision 0; 1992 20 Murphy, K.G. and Campe, K.W., Nuclear Power Plant Conutt Room Ventilation System Desian for Meetina General Criterion 19. published in proceedings of 13th AEC Air Cleaning Conference Ac880001.PM6

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ATTACHMENT E Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Change No. 109 Analysis of tube-to-TSP intersections during a postulated loss of coolant accident with a safe shutdown earthquake event.

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O DLC-96184 Westinghouse Energy Systems Ba 355 Pittsburgh Pennsylvania 15230-0355 Electric Corporation June 17,1996 REF: DLC-96-175 Mr. G. A. Kammerdeiner Duquesne 1.ight Company Beaver Valley Power Station P. O. Box 4 Shippingport, PA. 15077-0004 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNIT 2 STEAM GENERATOR LOCA PLUS SSE LOADS

Dear Mr. Kammerdeiner:

1 This letter replaces the referenced letter DLC-96-175 and provides additional information and references.

In response to your request for an evaluation to determine if any Beaver Valley Unit 2 steam generator tubes are excluded from an Alternate Plugging Criteria (APC) due to a combination of loads from a LOCA and Safe Shutdown Earthquake (SSE) we provide the following.

l Under combined LOCA + SSE loads, the potential exists for permanent deformation of i the tube support plates (TSP) to occur in the vicinity of the wedge groups, with subsequent deformation of tubes. j In developing an alternate plugging criteria (APC), where tubes with specified types of degradation at the TSP could remain in service beyond normal degradation levels,it is necessary to exclude tubes that experience permanent deformation under LOCA + SSE from the APC. Permanent tube deformation for this evaluation is defined as a change in diameter that exceeds 0.025 inch. This letter summarizes the results of an analysis to determine if any tubes need to be excluded from an APC for Beaver Valley Unit 2. -

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Mr. G. A. Kammerdeiner DLC 96184 Page 2 A similar analysis was performed previously for Beaver Valley Unit 1. However, a separate analysis is needed for Unit 2, as the Unit 2 steam generators are Series SIM design, as opposed to Series 51 for Unit 1. There are several differences between the two generator designs that affect the analysis in question. The most fundamental difference between the Series 51 and SIM designs insofar as this analysis is concerned is the number of wedge groups. For the Series 51 design, there are six wedge groups located uniformly amund the plate circumference. For the Series SIM, the number of wedge groups is increased to 12 for TSP 1, and to 14 for the remaining plates. There is also a flow distribution baffle (FDB) aGded to the Series SIM, giving a total of eight TSP, as opposed to seven for the Series 51. The FDB has been added to the design between the old TSP 1 position and the tubesheet. The axial position of the remaining Series SIM plates is identical to the Series 51 plates.

In calculating the wedge loads, it is assumed that the in plane loads are reacted by the various wedge groups based on a cosine distribution of the load. For the LOCA rarefaction load, which acts in the plane of the U-bend, the load is treated as uni directional. For the seismic load, however, the load can act randomly, such that the direction of the load can act normal to any given wedge location.

The number of deformed tubes at each wedge location is calculated based on plate crush tests performed for the Series 51 plates. Four plate samples were tested. Two of the samples were loaded such that the applied load was normal to the tube hole array. For these samples, flow holes were included right out to the edge of the tube pattern. Two additional samples were tested with prototypic hole patterns for the Series 51 plates; j with the hole array being oriented consistent with the wedge azimuthal positions, and '

with flow holes excluded in the region of the plate ad,jacent to the wedge locations. None of the samples tested are directly applicable to the Series SIM wedge location and hole pattern. The closest samples are the two test pieces with the load applied normal to the hole array. It should be noted that although the orientation of the holes relative to the load direction is not prototypic, the hole pattern for these samples (hole diameters and hole pitch), are prototypic for the Series SIM plates.

The tett results for the number of deformed tubes as a function ofload for the most applicable hole arrangement show that for an elastic load less than 105.42 kips, that there will not be any deformed tubes. The maximum wedge load for the Beaver Valley Unit 2 plates is 35.43 kips, well below the 105.42 kips thmshold for tube deformation.

The tube deformation load threshold for the other three tests are 112.23 kips,93.74 kips, and 92.73 kips. Thus, all of the test results show a load threshold for tube deformation that is several times higher that the maximum wedge loads.

Mr. G. A. Kammerdeiner DLC-96-184 Page 3 Based on the significant margin between the maximum wedge load for the Series SIM plates and the threshold for permanent tube deformation in the plate crush tests,it is concluded that there will not be any tubes experience permanent diametral deformation greater than 0.025 inch due to combined LOCA + SSE. Thus, no tubes need to be excluded from the APC criteria for reasons of tube deformation for Beaver Valley Unit 2.

i The above analysis is documented in Westinghouse Calculation Note SM-96-43, which is kept on file in the NSD/SGO Design and Analysis Group.

Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION MemaId k no n k . ,

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Darryl B. Jenkins North America Field Sales cc: R A. Hruby IL D. P. Weakland IL R. D. Bologna IL l

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ML20113B337

Text

Dearadation means a service-induced cracking,

Dear Mr. Kammerdeiner:

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