L-95-008, Rev 2 to SA of Common CR Eab,Lpz Doses from MSLB Outside of CNMT at Unit 1 W/Increased Primary-to-Secondary Leakage
| ML20136G278 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/24/1997 |
| From: | Ireland R, Kammerdeiner G, Lavie S DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20136G263 | List:
|
| References | |
| ERS-SFL-95-008, ERS-SFL-95-008-R02, ERS-SFL-95-8, ERS-SFL-95-8-R2, NUDOCS 9703170256 | |
| Download: ML20136G278 (139) | |
Text
RTL: A9.621 A d 'D_ouesne Licj1t Form: R E 1.103-1
=
Health Physics Department GPS, LPa REVisIDh'l 2 3 Subject Safety Analysis of the Common Control Roomf poses from PAGE 1 OF a Main Steam Line Break Outside of CNMT at U1 with ERS-SFL-95-008 17 0 + m increased Primary-to-Secondary Leakage Referenca RCM RP EPP T/S 3/4.4.5 EM DCP RIP Review Category Unit 1 Unit 2 !
10 CFR 50.59 E RSC Reg'd RSC Not Req'd 2 l Required i Purpose This calculation package documents an analysis of the postulated dose in the common control room following a main steam line break outside CNMT at Unit 1, with the objective of determining the maximum allowable primary to secondary leakage in the fat.Ited steam generator. This analysis performed in support of a license amendment request for alternate tube plugging criteria (APC).
NOTE: This calculation package documents the evaluation described above. This package DOEs NOT,in of itself, provide autority for any revision 4 in a structurG, system, or component; nor changes in procedures, tests, and experiments described in the plantlicens;ng basis. The data and!ct l
I conclusions of this package shall not be extended to other purposes without explicit concurrence from Raciological Engineering.
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source term based on 0.5 uCi/gm DE I-131; new X/Q.
1 cou nu termi also based on 0,35 uci/em, f/g}fb.n khf "'"!!e ep/ Add EAB, LPZ Cales.
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8Y 10/28/95 Attachments S FM , gfate E Purpose E Data Sheets O cn g E Input Data E Illustrations
< /Op/ f, 5 Assumptions E Results
.- _. E Methodology E References E Printouts 49 te O Code Listings For RSC E BV REtdRDS CENTER O DIR, RadOps 1 E Author: S.F.LaVie -
E CALCULATION FILE O DIR, Radops 2 E G.A. Kammerdeiner MGR, Health Phys:cs O DIR, Safety & Env Sves E R.N. Ireland DIR, RadEng & Health O Trng Dept.. O 9703170256 970310 - ,3(",
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RTL: nh Fum: RE 1.103 3 S92 ERS-SFL-95 008 [h 7A@ sDm m.a nm le M o.p.rtm.n, p ge 2 DISCUSSION
- 1. General Revision 0 of this calculation was performed in support of Unit 1 License Amendment 198.
Revision 0 developed a maximum allowable accident-induced steam generator leakage based l on control room habitability, to supplement an analysis of the offsite consequences performed by l Westinghouse'. These efforts supported a maximum allowable accident induced leakage of 4.5 l
9Pm.
Revision 0 suggested that this leak rate could be increased by (1) decreasing reactor coolant technical specification activity and (2) by changing control room isolation from CIB to SI actua-tion. An analysis was performed to determine the relative benefit from either option. This sensi- !
tivity analysis was documented in ERS KJW-96-0132. The analysis indicated that while shifting to Si actuation of isolation of the control room would reduce control room dose, the offsite dose created a " cap" which limited the effectiveness of this option. Operational assessment performed l on the steam generators in cycle 12, showed indications corresponding to leak rates as high as 4.5 gpm. In order to gain more operating margin, it was decided to pursue reducing the reactor l coolant system technical specification activity to 0.5 Ci/gm or 0.35 Ci/gm D.E.1-131 for cycle
- 13. This analysis will assess both cases. ,
Since revision 0 was performed, short-term accident y/O values were re-calculated. The new values, documented in ERS-SFL 96-0218, will be used herein. ,
Revision 0 addressed only the control room dose. Revision 1 will address offsite dose as well.
The dose equivalent '2'l used in revision 0 was based on the dose conversion factors of TID 148442'. This version uses isotopic concentrations developed DCFs based on ICRP 30+ This will require a T/S amendment..
The MSLB analysis for offsite consequences in the Unit 1 UFSAR5 assumed a 10 gpm primary-to-secondary leak concurrent with the event,1% failed fuel, and an lodine plateout factor of 10. It assumed two cases, a break upstream of the main steam isolation valves, and a break down-stream of the MSIVs for which it was assumed that the MSIV went shut within 5 seconds. Con-trary to current practice, no lodine spiking was assumed.
As part of the Unit 2 Ucensing effort, SWEC performed calculations of the potential control room doses from DBAs at Unit 2 and at Unit 1**. These calculations became part of the licensing basis for BVPS 1 and -2 and have been documented in the UFSARs5 *, Since 1987, there have been various re-analyses made of the control room habitability." '2 '* " '5 " The referenced analyses modified one or more design basis aspect (s) of the original SWEC calculations (refer-ences 6-9). There have been additional re-analyses performed as part of various incident reports. These later analyses address specific situations and are not part of the design basis.
In 1994, Westinghouse performed analyses to support the interim use of steam generator tube plugging limits based on voltage indications. These analyses included re-analysis of the offsite consequences of a postulated main steam line break during which a degraded tube leaks at rates higher than technical specification limits. Based on these analyses, Westinghouse postu-lated that a 6.6 gpm leakage could be tolerated and not exceed EAB thyroid dose of 30 rem.
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i
- RTL
- n/a Ferm: RE 1.103-3 692 DU ERS-SFL-95-008 d
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i Based on corraldon analyses it was determined that the potential 95% / 95% leakage rate associated with a 2.0 volt indication was much lower than 6.6 gpm providing reasonable margin j of safety. In the licensing action, the NRC authorized use of a 1 voit criterion'* for cycle 11.
[
1
' While offsite doses were evaluated in the Westinghouse report, control room doses were not.
The reason behind this omission are beyond the scope of this calculation. In August 1995, the ;
j NRC issued Generic Letter 95-05, Voltaae-Based Roomir Criteria for Westinahouse Steam
- Generator Tubes Affected bv Outside Diameter Stress Corrosion Crackinou t. The generic letter j specified that the accident leak rate acceptability needed to assess the offsite and control room doses. Ucense amendment requests for these attemate plugging criteria must meet the guld-ance of the generic letter.
l j 2. Main Steam Line Break l l The acceptability of the plant design to withstand steam generator leakage and not cause unac- I l ceptable offsite radiological consequences is assessed during plant licensing by the required j analyses of a complete rupture of a single steam generator tube, i.a., the design basis Steam i Generator Tube Rupture (SGTR), and by the inclusion of technical specification primary to- i j secondary leakage rates (and technical specification reactor coolant radioactivity) as an input i parameter to other design basis accidents, such as loss of AC power auxiliaries, CRDM ejection, '
{ and, of specific interest here, main steam line breaks. i 1
) Main steam line breaks are of interest to the issue of degraded steam generator tubes because I i (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 i result in a release of radioactivity to the environment. !
1 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 consequence of the initiating event. Leakage of the steam generator i tubes greater than technical specifications was not postulated in the original analyses of record I 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.
The analyses in reference 1 determined that a postulated leakrate of 6.6 gpm was acceptable from the standpoint of offsite dose (30 rem at the site boundary). The analysis of the coire-sponding control room dose in revision 0 of this package determined that a postulated leakrate of 4.5 gpm was acceptable from the standpoint of control room habitability (30 rem).
METHODOLOGY l
- 1. Overall Methodology The analyses in this package use version 1.0 of the TRAILS _PC (for Iransport of Badioactive material in Linear ftystems), PC version documented in ERS SFL 96-0042 This code is ccm-parable to the DRAGON code used by SWEC in the Reference 8 and 9 analyses, i.e., the i original analyses of record.
- _. .-, . _ - - _ ~ . - . _ . , - . . - . . . ~ - . . - - . . - . . . - - - - - - - . - - . . . . - - . - - - .
RTL: nh Form: RE 1.103 3 892 k HeaMhPhysicsDepanment M ERS-SFL-95408 d i page 4 '
j l
l ' 1.1 Ris version of TRAILS is different from that used in the revision 0 analyses. The significant s j- +
differences are:
1 1.1.1 TRAILS _PC runs on a PC platform in lieu of the minicomputer platform used by the
- original TRAILS.
i- 1.1.2 TRAILS _PC analyses progeny buildup due to the decay of parent nuclides. This will '
result in a slight increase in whole body doses due to the noble gas daughters of
- lodine, i
l 1.2 Re DRAGON and TRAILS _PC codes differ in dose calculational methods:
i
! 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 14844
j and Regulatory Guides 1.4' and 1.2528 1.2.2 TRAILS _PC determines the same dose quantities as did DRAGON, using the same
- data sources for the thyroid dose, and the formulae of Reference 22 for the whole
! body doses. The energy per disintegration values used in the whole body dose
) formulae were taken from the BVPS Radionuclide Data Base ** rather than the j reference stated in Reference 22 (which is no longer in print). TRAILS _PC imple-l ments the infinite to-finite cloud correction algorithm of Murphy and Campe 5. In l previous test calculations performed in Reference 26, close correlations were j demonstrated with the previous DRAGON results. TRAILS _PC can also assess the dose quantities: effective dose equivalent (external) (EDE), skin dose equivalent
- (DE), and thyroid committed dose equivalent (CDE). In accordance with licensing j positions taken in REAP-1.106, Dose Calculation Methodoloav in DBA Analyseser ,
j these dose quantities may be utilized in licensing procedures as substitutes for the outdated corresponding dose quantitles of Reference 22 provided the initial applica-l tion is reviewed by the NRC staff. The NRC staff accepted the use of ICRP-30
- DCFs in revision 0 of this package. Thus, this stipulation is satisfied.
1 j 1.2.3 TRAILS _PC also assesses the committed effective dose equivalent (CEDE) and the l- total effective dose equivalent (TEDE). These dose quantities may not be used for
- showing compliance with 10 CFR Part 100,11, since that guideline specifically j references the whole body and thyroid dose quantities.
4 i
1.3 The DRAGON code does not provide a direct means to handie concurrent iodine spiking.
The method used by SWEC as a work around involves averaging. The TRAILS _PC code can isotopically model initial activity and a constant introduction rate, and, therefore can expileitly model concurrent spiking. Thus, there may be slight differences between the DRAGON and TRAILS _PC cases and results.
- 2. Main Steam Line Break Modeling De radioactivity releases from this accident are add'ressed in a series of cases. The results from applicable cases are summed to obtain the total postulated dose. The cases are (see Attachment 1):
~
RTt.: n/a Form: RE 1.103-3 A92 7A @ MNM m.en c. , o.p.nm.ni ERS-SFL-95-008 d P89* 5
. FRP: Release from Eaulted S/G, Hupture leakage, Ere-incident RCS iodine spike activity.
i Release rate from steam generator equal to release rate from RCS. No hold-up or lodine decontamination credited. Eight hour release. Noble gases and lodines considered. i 1
FRC: Release from Eaulted S/G, Hupture leakage, Qoncurrent RCS iodine spike activity plus l T/S equilibrium activity. Release rate from steam generator equal to release rate from RCS. No hold up or lodine decontamination credited. Eight hour release. Noble gases and lodines considered.
ITN: Release from Intact S/Gs, T/S leakage, RCS Noble gas activity. Release rate from steam generator equal to release rate from RCS. No hold-up credited. Eight hour release.
Noble gases considered. ,
1 ITP: Release from Intact S/G, I/S leakage, Ere-incident lodine 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 , I after one hour.
l Note: Partitioning credit is appropriate whenever the steam generator levelis such that the tube leak location is submerged. In this event, the levelin the intact steam generators will i initially drop, i:ut is assumed to be restored within one hour. See assumption 1.6 below.
1 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 lodine partitioning after one hour.
See note above underITP i
i 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 min-utes.
Note: The 30 minute assumption is based on the assumption used in the original analyses. The exponential transfer lambda associated with the stated release and duration is such that 99.3% of the activity is releasedin the first second. Thus, the assumption will be retained as itis suf6ciently 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.
Note: This partitioning not affected by S/G level since the activity was dispersed in the liquid prior to the event. Case ITP/ITC/ITN address leakage after the start of the event.
ASA: Release from All S/Gs, Eteam space activity initially present in S/G, pre-incident S/G activity, All nuclides. Instantaneous puff release (99.999999% in 1 second.)
. -. .- _._.__..m.. _ . . _ _ _ _ . - _ _ _ _ _ . _ _ _ _ . . ____._ ______ _ _ _ . . .
l' RTL: n/2 Fcrm: RE 1.103-3 As2 D ERS-SFL-95 008 d 3 V u@msne - M page 6 1
For the pre-incident iodine spike cases FTP and ITP, the dose equivalent '8'l technical specifica.
I tion activity of 30 [21] Cl/gm will be used to obtain the pre-incident activities for the five iodine
] nuclides. These will be added to the iodine and noble gas equilibrium concentrations associated :
with the 0.5 [0.35] Cl/gm dose equivalent '8' lodine technical specification.
l
- For the co-incident lodine epike cases FTC and ITC, the iodine appearance rates equal to 500 i times the iodine appearance rate that yields the 0.5 (0.35] Ci/gm dose equivalent '8'l technical
, specification concentrations will be added to the lodine and noble gas equilibrium concentra- l j tions. At four hours post accident, the co-incident spike ceases (modeled by dividing lodine j appearance rates by 500). ;
l
- , For the ITN case, the noble gas concentrations associated with the 0.5 (0.35] Cl/gm dose
{
equivalent '8'l technical specification concentration are used.
] l 4 I i For the FLI and ill cases, the iodine activities in the steam generator liquid phase associated I with the 0.1 Cl/gm secondary equilibrium concentration dose equivalent '8'l technical specifica-
] tion are used. Noble gases are assumed to enter the steam phase immediately. ;
3 1 For the ASA case, the activities in the steam phase associated with the 0.1 Ci/gm secondary l 4 equilibrium concentration dose equivalent '8'l technical specification are used. l l
{ 3. Control Room Modeling The modeling of the control room intake and exhaust is described in Appendix 1 to this calcula-
{ tion package.
j 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
] isolation and pressurization of the control room does not occur. The control room radiation j monitor reading did not exceed the monitor setpoint. Instead, previous analyses have conserva-
- tively assumed that the control room operators would manually initiate control room isolation and pressurization at T=30 minutes. Revision 0 of this analysis showed that manual isolation would j still be required.
INPUT DATA AND ASSUMPTIONS This section documents input data that are applicable to this analysis. Apperdix 1 provides additional input data associated with the control room modeling.
- 1. Assumptions
!i 1.1 The analysis of the main steam line break (MSLB) is based on the guidance provided in Chapter 15.1.5 of Reference 28 and Reference 19.
i 1.2 There is no failed fuel for the MSLB I The Unit 1 UFSAR shows that DNB is not exceeded for a MSLB In accordance with Reference 1
28, no fuel damage need be assumed if DNB is not exceeded.
4 4
RTL.: n/s Form: RE 1.103 3 ff2 YA[ O rn sw10 @s.dPhysicsERS SFL-95-008 d Department page 7 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.
i This is a conservative assumption in that the activity intake during damper movement and diesel start up and sequencing is maximized.
1.5 The control room is isolated by manual operator action within 30 minutes.
The validity of this assumption was challenged by the OSC during review of the technical specifi-cation amendment request for Unit 2. The Procedures group obtained timing data during valida-tion of Unit 2 EOP changes related to that amendment. The results indicated that it would take 17 minutes for the operator to manualisolate the control room. This is well within the thirty minute period assumed. The margin is considered adequate to address uncertainty associated ,
i with the application of these results at Unit 1. See Attachment 2 '
1.6 Incoming air is uniformly distributed throughout the control room volume.
This is a conservative assumption in that the radiation monitors will alarm when the dose from the cloud of gases adjacent to the monitor exceeds the setpoint. Assuming complete mixing
, reduces the concentration and dose, thereby delaying the isolation actuation.
1.7 Loss of power is assumed coincident with the control room isolation actuation.
This assumption differs from that at Unit 2, where, loss ofpower is assumed coincident with the
, accident. The Unit 1 assumption is more conservative. However, the Unit 2 assumption meets i the requirements of 93.1.1.3 of the FSAR that states that a loss of offsite poweris assumed if the postulated event or its effects results in a reactor or turbine trip. This requirement implies a coincidentloss ofpower.
1.8 Unfiitered inleakage of 10 cfm is assumed during control room pressurization.
i i This assumption is consistent with Reference 28, Chapter 6.4.
l 1.9 The level in the unaffected, intact steam generators is restored to greater than 5% narrow range l within one hour.
In response to the rapid pressurization of the main steam line, main steam line isolation (<S00 psigt) will occur, pressurizer level will drop to below the Si actuation setpoint (1845 psigt).
When Si occurs, all three auxiliary feedwater pumps will receive a statt signal and willinject 1 waterinto the steam generators. The EOPs willhave 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 signi6 cant to note, that if the levelis less than 5% 1 1
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- ,
I
RTt.: n/a Fum: RE 1.103 3 992 DNM HeaHh Physks Department ERS-SFL-95-008 d Page 8 tor training scenarios responses indicate that the levelis restored to greater than 5% within 30 minutes from completion of blowdown of the faulted generator. Itis therefore reasonable to assume that partitioning be credited after one hour from the start of the event. The doubling of 1
the expected time to cover the tubes was done to provide additional margin for this qualitative conclusion.
The validity of this assumption was challenged by the OSC during review of the technical speci6 cation amendment request for Unit 2. The Procedures group obtained timing data during valida-tion of Unit 2 EOP changes related to that amendment. The results indicated that it would take 43 minutes to restore level. This is well within the one hour period assumed. The margin is considered adequate to address uncertainty associated with the application of these results at Unit 1. See Attachment 2 4
1.10 The EDE result provided by TRAILS is assumed to correspond to the whole body photon guide-lir'e in SRP 6.4, the skin DE to whole body beta, and the thyroid CDE to thyroid.
in the review of revision 0 to this calculation package, the NRC staff accepted the use of these revised dose quantities.
j 2. Input Data 2.1 Technical Specification Concentrations *, Cl/gm [29]
l e *those concentrations that equate to 0.35 CVgm DE l-131 in RCS; 0.1 pCVgm DE I 131 in i
S/G:
S/G S/G Nuclide RGE lig altam Kr 83m 4.65E-02 4.53E 07 Kr 85m 2.27E-01 2.21E 06 Kr 85 1.20E+00 1.17E-05
- Kr-87 1.30E-01 1.26E 06 Kr 88 3.46E-01 3.37E-06
< Kr-89 1.09E-02 1.07E 07 Xe 131m 1.17E 02 1.14E 07 Xe 133m 3.33E 01 3.25E-06 Xe-133 2.84E+00 2.77E-05 Xe-135m 1.18E-01 1.15E 06 Xe-135 3.48E-01 3.40E-06 Xe-137 1.77E 02 1.72E 07 Xe-138 7.28E 02 7.10E 07 l131 2.72E 01 8.11E 02 8.11E 04 l132 9.48E 02 1.44E 02 1.44E 04 i 1-133 4.24E-01 1.06E 01 1.06E-03 4 l-134 5.93E-02 2.54E 03 2.54E 05 l-135 2.28E 01 3.88E 02 3.88E-04 1
RTU nh Fum: RE 1.103-3 A92 D"M M Ak HealthPhysicsoopertment ERS SFL-95-008 d p,g g i
4 hose concentrations that equate to 0.5 pCi/gm DE I-131 in RCS; 0.1 Ci/gm DEI 131 in S/G: l S/G S/G Nuclide RCS. ((g steam 4 Kr 83m 6.64E-02 6.48E-07 Kr 85m 3.24E-01 3.16E-06 Kr 85 1.71 E+00 1.67E 05 Kr-87 1.85E 01 1.81E 06 Kr 88 4.94E 01 4.82E 06 Kr-89 1.56E 02 1.52E 07 I Xe-131m 1.67E-02 1.63E-07 l Xe-133m 4.76E-01 4.64E-06 Xe-133 4.05E+00 3.95E 05 Xe-135m 1.68E-01 1.64E 06 ;
Xe-135 4.97E-01 4.85 E-06 i Xe-137 2.52E 02 2.46E-07 Xe-138 1.04E-01 1.01 E-06 l-131 3.89E-01 8.11E 02 8.11 E-04 l-132 1.35E 01 1.44E-02 1.44E-04 l133 6.06E 01 1.06E 01 1.06E 03 1-134 8.48E 02 2.54E 03 2.54E 05 l-135 3.26E 01 3.88E 02 3.88E-04 2.2 Pre-incident lodine Spike Concentrations, Ci/gm (29]
d.e.1-131 Corresponding to:
Nuclide 21 uCi/gm 30 uCi/gm I-131 16.3 23.3 1-132 5.69 8.12 1-133 25.4 36.4 l-134 3.56 5.09 l135 13.7 19.6 i
2.3 Concurrent lodine Spike Rate, Ci/sec (29]
d.e.1131 Corresponding to:
Nuclide 0.35 uCi/am 0.5 uCl/gm l-131 0.49E+6 0.70E+6 i 1132 0.92E+6 1.31 E+ 6 l133 1.10E+6 1.57E+6 l-134 1.34E+6 1.92E+6 .
1-135 1.02E+6 1.46E+6 l l
2.4 Concurrent lodine Spike Duration = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (5,9) 2.5 Technical Specification Primary-to-Secondary Leakage (30]
1 150 gpd any one generator,450 gpd total
- l
RT1.: n/2 Fum: RE 1.103-3 A92 ERS SFL-95 008 d
- 7A@%M,a mme o,p.nm.nt @ p,g, 3g 2.6 Primary Coolant Mass = 4.2E5 lbm,1.91E+8 gm (See below]
Note: Table 148 5 of the Unit 1 UFSAR identiMes the Reactor Coolant liquid volume to be 9387 ft'. With the specinc volume of 0.02221 ft'Abm, the mass of the RCS is 4.23E5 lb, or 1.917E8 gm. The Unit 2 value was 1.91E8 gm (4.2E5 lb). Since the values in datum 1 were based on 1.91E8 grams, this latter value will be used herein. In support of the Unit 1 analysis for control room habitability, NED directed SWEC to use 3.9E5 lbm as the RCS liquid volume. This is equal to 1.77E8 grams, or about 7% less than that established for Unit 2. The justification for this value was not documented. Although the smaller value has been used in several analyses performed i since, it now seems appropriate to use the larger value in this application.
I 2.7 Secondary Side Mass (5,9]
Uquid: 97900 lbm = 4.44E+7 gm @ generator Vapor: 6460 lbm = 2.93E+6 gm @ generator 2.8 lodine Partition Factors (28]
4 Faulted S/G: 1.0 Intact S/Gs: 0.01 after one hour 1
2.9 Time to Isolate Faulted S/G = 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (5,9]
2.10 Steam Release from Faulted S/G [5,9]
0-30 minutes: 150,000 lbm
- 30 min.-8 hours
- 1300 lbm l
2.11 Steam Release from Intact S/Gs (5,9]
0-2 hrs: 366,776 lbm
! 2 8 hrt 705,393 lbm i 2.12 BreathMg Rate = 3.47E-4 m3/s (22]
l 2.13 Accident yJQ values [3] )
Location 0-2 Hrs 0-8 Hrs 8-24 Hrs 14 Days 4-30 Days EAB 1.04E 3 LPZ 1.18E 4 6.04E-5 4.33E 5 2.10E-5 7.44E 6 j CALCULATION
- 1. Activities l
The calculations for each of the accidents will be discussed in the individual accident sections. i This section will calculate the release activities that are based on T/S concentrations.
RT1.: n/a Form: RE 1.103-3 492 DucpmSm @ ERS-SFL-95-008 d Ak HeemPhysicsDepartrnent p,g, 33 Datum 2.1 provides the technical specification concentrations, in Cl/gm, in the RCS and in the S/Gs For use in TRAILS _PC, these values must be expressed in terms of activity, in uCl. The conversions are:
RCS: ARCS = CRCS. Cl/gm x 1.91E8 gm SG Uquid: Asa = Cse, Cl/gm x 4.44E7 gm (each S/G)
SG Vapor: Age = CSG, Cl/gm x 2.93E6 gm (each S/G)
Table 1a Technical Specification (0.5 Cl/gm) Equivalent Activities, uCI
@SG @SG Nuclide RCE lig vapor Kr-83m 1.27E+07 1.90E+00 Kr-85m 6.20E+07 9.27E+00 Kr 85 3.27E+08 4.90E+01 Kr 87 3.54E+07 5.29E+00 Kr-88 9.44E+07 1.41 E+01 Kr 89 2.98E+06 4.46E-01 Xe 131m 3.19E+06 4.77E 01 Xe-133m 9.09E+07 1.36E+01 Xe-133 7.74E+08 1.16E+02 Xe-135m 3.21 E+07 4.81 E+00 Xe-135 9.50E+07 1.42E+01 Xe-137 4.82E+06 7.21E 01 Xe-138 1.99E+07 2.97E+00 1131 7.42E+07 3.60E+06 2.38E+03 1132 2.59E+07 6.39E+05 4.22E+02 1-133 1.16E+08 4.71 E+06 3.11 E+03 1-134 1.62E+07 1.13E+05 /.43E+01 1135 6.22E+07 1.72E+06 1.14E+03 Table 1b Technical Specification (0.35 Cl/gm) Equivalent Activities, uCI
@SG @SG Nuclide RQ.1 lig Vapor Kr 83m 8.88E+06 1.33E+00 Kr-85m 4.34E+07 6.49E+00 Kr-85 2.29E+08 3.43E+01 Kr 87 2.48E+07 3.70E+00 Kr88 6.61 E+07 9.89E+00 Kr-89 2.09E+06 3.12 E-01 Xe 131m 2.23E+06 3.34E-01 Xe-133m 6.36E+07 9.52E+00 Xe 133 5.42E+08 8.11 E+01 Xe-135m 2.25E+07 3.37E+00 Xe-135 6.65E+07 9.95E+00 Xe-137 3.38 E+06 5.05E 01 Xe-138 1.39E+07 2.08E+00
l RTL: nh Form: RE 1.103 3 A92 l DS"8N M A k H.ahh Physics Department ERS-SFL-95 008 d Page 12
@SG @SG Nuclide RCA lla Vapor 1131 5.20E+07 3.60E+06 2.38E+03 1132 1.81 E+07 6.39E+05 4.22E+02 l l133 8.10E+07 4.71 E+06 3.11 E+03 l 1134 1.13E+07 1.13E+05 7.43E+01 1135 4.36 E+07 1.72E+06 1.14E+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 lodine Spike, Cl Corresponding to Nuclide 30 uCl/am 21 uCl/am Kr 83m 1.27E+07 8.88E+06 Kr 85m 6.20E+07 4.34E+07 Kr-85 3.27E+08 2.29E+08 Kr87 3.54E+07 2.48E+07 Kr 88 9.44E+07 6.61 E+07 Kr-89 2.98E+06 2.09E+06 -
Xe-131m 3.19E+06 2.23E+06 Xe-133m 9.09E+07 6.36E+07 Xe-133 7.74E+08 5.42E+08 Xe-135m 3.21 E+07 2.25E+07 Xe-135 9.50E+07 6.65E+07 Xe 137 4.82E+06 3.38E+06 Xe-138 1.99E+07 1.39E+07 l131 4.52E+09 3.17E+09 l-132 1.58E+09 1.10E+09 l133 7.07E+09 4.93E+09 l134 9.88E+08 6.91 E+08 l135 3.81 E+09 2.66E+09
" NOTE: This Is conservative. The pre-incident values are based on T/S. Thus, the l- l 131 thru l-135 datum 2.2 values already include the equilibrium lodine values. The l difference is 1-2%
l
- 2. Transfer Coefficients initial transfer coefficients for the model cases are determined in this section. Density based on assumption of 1.0 gm/cc:
3785.43 cc 8.345 1=
gal 453.59gm gal l
RTL n/s Firm: RE 1.103 3 492 l 7A 9 mDMM % o, .n, ERS SFL-95-008 d page 13 l
2.1 FRP, FRC j 1
Base the release rate on a primary to-secondary leakrate. For one gpm:
1.0 gpm = 1.6666E 2 gal /sec = (1.6666E-2 gal /sec)(8.345 lb/ gal) / (4.2E5 lbm) =
= 3.3114E 7 sec '
}
it was determined that a leakage of 8.1 gpm would be limiting for the 0.5 Cl/gm case:
8.1 gpm = 3.3114E-7 x 8.1 = 2.6822E 6 sec' l It was determined that a leakage of 11,75 gpm would be limiting for the 0.35 Cl/gm case:
11,75 gpm = 3.3114E 7 x 11.75 = 3.8909E-6 sec' 4
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 = (3.4722E-3 gal /sec)(8.345 lb/ gal) / (4.2E5 lbm) = 6.8989E 8 sec' l
(Since the release rate represents two S/Gs, the Table 1 RCS activities need not be multi- i plied.) l 2.3 ITP, ITC l
Same as ITN for first hour. After the first hour, the release rate is reduced by a factor of 100 to account for partitioning:
release rate = 6.8989E 8 sec' /100 = 6.8989E-10 sec' The 0-1 hour value will be entered as the base value. The XREM multiplier after one hours is 0.01 (Since the release rate represents two S/Gs, the Table 1 RCS activities need not be multi-plied.)
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 a reduction of 1.0E-6 represents 100% of the activity. The release rate (1) can be found:
0.000001= e4 1800 A = 7.675E 3 sec'
_ _ _ _ - - - . . _ .- _. -- - - . = - -. - . . - - - - - - -
RTL: n/a Form: RE 1.103 3 a92 1_
7A @somD""N o.pem.niM ERS-SFL-95 008 d p g, 34 2.5 Ill 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; and a release of 705,393 lbm in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Both of these values represent the release from both intact S/Gs. Thus, in order to determine the release rate from holt 1 S/G, we divide by the mass of one generators (97,900 lbm) Partitioning applies, thus, the release rate is multiplied by 0.01.
release rate = (366,776 lbm / 7200 sec) / (97,900) x 0.01 = 5.2034E 6 sec' release rate = (705,393 lbm / 21600 sec) / (97,900) x 0.01 = 3.3358E 6 sec' The 0-2 hour value will be entered as the base value. The XREM multiplier after two hours is 3.3358/5.2034 = 0.64. Since we assumed one S/G mass above, the Table 1 activities need not be multiplied.
2.6 ASA I Release from all S/Gs equal to release fraction of 1E-6 in 1 second of activity initially in S/G steam space, all nuc!! des.
0.000001= e*
A = 13.82 seed 3.0 Offsite Dose input files for the cases were prepared and the code run. The FRC cases were run several times with varying primary to secondary flow rates. From these trail runs, it was determined that a leak rate of 8.1 gpm would be the maximum allowable accident-induced leakage for the 0.5 Ci/gm case. For the 0.35 pCi/gm case, the associated leakage was 11.75 gpm. The remaining cases were run with this leak rate, establishing that the EAB dose for the co-incident spike was the limiting case. Attachment 3 provides excerpts from the code run printouts for the 0.5 Cl/gm cases and the results are summa-rized in the results section below. Attachment 5 provides excerpts from the code run printouts for the 0.5 Ci/gm cases and the results are summarized in the results section below.
Not all sub-cases needed to be run for all cases. The ILI and FLI cases are dependent on the second.
ary activity T/S, which does not vary with the RCS T/S activity. These cases, and the ASA and ITN cases are also independent of the lodine spike case. Thus, the result from a printout excerpt may appear in more than one of the results tables below.
4.0 Control Room Dose The parameter input files were edited to reflect the control room isolation assumptions and ran to obtain the postulated control room dose. These were run in conjunction with the LPZ dose cases.
Attachments 3 and 5 provides excerpts from the code run printouts and the results are summarized in the results section below.
RTL: n/a Form: RE 1.103-3 a93 ,
DM"M M A > H.alth Physics Department ERS-SFL-95 008 d page 15 l
RESULTS - 0.5 pCl/gm T/S Activity A maximum allowable accident. induced leakage of 8.1 gpm was established. The corresponding doses are tabulated below. Attachment 4 tabulates the isotopic quantities released.
Postulated EAB Dose (0 2 Hrs)
MSLB - Co-incident lodine Spike EDE Skin DE Thyroid CDE mrom mrom mrom ASA 2.960E 03 1.610E 03 3.430E+00 ill 4.960E 02 2.770E-02 6.300E+01 FLI 1.470E+00 7.950E 01 1.730E+03 ITC 8.120E-01 3.050E 01 1.900E+02 ITN 2.100E-02 2.560E 02 0 Sum non-break flow 2.356E+00 1.155E+00 1.986E+03 FRC - 8.1 gpm 1.100E+02 4.250E+01 2.770E+04 Sum - 8.1 gpm 1.1 E+02 4.4E+01 3.0E+04 Postulated EAB Dose (0-2 Hrs)
MSLB - Pre-incident lodine Spike P-to-S Leak Rate EDE Skin DE Thyroid CDE mrem mrom mrem ASA 2.960E 03 1.610E 03 3.430E+00 ILI 4.960E-02 2.770E 02 6.300E+01 FLI 1.470E+00 7.950E 01 1.730E+03 ITP 7.170E 01 3.460E 01 5.650E+02 ITN 2.100E 02 2.560E-02 0 Sum non-break flow 2.261E+00 1.196E+00 2.361 E+03 FRP - 8.1 gpm 5.160E+01 2.620E+01 4.290E+04 i
Sum 8.1 gpm 5.4E+01 2.7 E+01 4.5 E +04 i
RT1.: n/a Form: RE 1.103 3 Gsf l MNM Ak H.dhPhysicsDepetment ERS-SFL-95408 d page 16 l l
Postulated Control Room Dose (0-30 days)
MSLB - Co-incident lodine Spike !
mrom mrom mrom ASA 1.760E-04 2.070E-03 4.950E+00 ILI 1.170E-03 1.520E 02 3.320E+01 FLI 8.620E 02 1.010E+00 2.430E+03 ITC 9.310E-03 8.150E 02 7.640E+01 ,
ITN 2.000E 03 7.800E 02 0 i Sum non-break flow 9.886E-02 1.187E+00 2.545E+03 FRC - 8.1 gpm 2.810E+00 3.570E+01 2.350E+04 Sum - 8.1 gpm 2.9E+00 3.7E +01 2.6 E+04 Postulated Control Room Dose (0-30 days)
MSLB - Pre-incident lodine Spike P-to-S Leak Rate EDE Skin DE Thyroid CDE mrom mrem mrom ASA 1.760E-04 2.070E 03 4.950E+00 Ill 1.170E-03 1.520E-02 3.320E+01 FLI 8.620E 02 1.010E+00 2.430E+03 ITP 2.000E-02 2.140E 01 4.040E+02 ITN 2.000E-03 7.800E 02 0 Sum non break flow 1.095E 01 1.319E+00 2.872E+03 FRP - 8.1 gpm 1.360E+00 1.920E+01 2.560E+04 Sum - 8.1 gpm 1.5E+00 2.1 E+01 2.8E+04 Postulated LPZ Dose (0-30 days)
MSLB - Co-incident lodine Spike EDE Skin DE Thyroid CDE mrom mrom mrom ASA 1.720E-04 9.340E-05 1.990E 01 ILI 6.800E 03 4.060E 03 1.010E+01 FLI 8.560E-02 4.610E 02 1.000E+02 j ITC 5.710E 02 2.200E 02 1.530E+01 ITN 2.980E-03 4.750E-03 0 Sum non-break flow 1.527E-01 7.700E 02 1.256E+02 FRC - 8.1 gpm 4.390E+01 1.890E+01 1.780E+04 j Sum - 8.1 gpm 4.4E+01 1.9 E+01 1.8 E+04 i
I
RTL: n/a Ferm: RE 1.103-3 A92 DJ'N @
A > H.alth Physies Department ERS SFL 95-008 d page 17 i Postulated LPZ Dose (0-30 days) j MSLB - Pre-incident lodine Spike P to-S Leak Rate EDE Skin DE Thyroid CDE mrem mrem mrem ASA 1.720E 04 9.340E 05 1.990E-01 Ill 6.800E 03 4.060E 03 1.010E+01 FLI 8.560E 02 4.610E-02 1.000E+02 ITP 4.310E-02 2.100E-02 3.470E+01 ITN 2.980E 03 4.750E 03 0 Sum non-break flow 1.387E 01 7.600E 02 1.450E+02 FRP - 8.1 gpm 8.710E+00 4.930E+00 9.380E+03 Sum - 8.1 gpm 8.8E+00 5.0E+00 9.5E+03 RESULTS - 0.35 Cl/gm T/S Activity A maximum allowable accident induced leakage of 11.75 gpm was established. The corresponding doses are tabulated below, Attachment 4 tabulates the isotopic quantities released.
Postulated EAB Dose (0-2 Hrs)
MSLB - Co incident lodine Spike '
EDE Skin DE Thyroid CDE mrem mrem mrem ASA 2.950E 03 1.600E 03 3.430E+00 ill 4.960E 02 2.770E 02 6.300E+01 FLI 1.470E+00 7.950E-01 1.730E+03 ITC 5.680E 01 2.140E 01 1.330E+02 ITN 1.470E-02 1.800E-02 0 Sum non-break flow 2.105E+00 1.056E+00 1.929E+03 FRC - 11.75 gpm 1.110E+02 4.300E+01 2.800E+04 Sum - 11.75 gpm 1.1 E +02 4.4 E + 01 3.0 E +04
RTL: n/a Form: RE 1.103 3 692 DN ERS-SFL-95 OO8 d TAF m.m... o .@.,, page is Postulated EAB Dose (0-2 Hrs)
- MSLB - Pre-incident lodine Spike P-to-S Leak Rate EDE Skin DE Thyroid CDE mrom l mrom mrem l ASA 2.950E 03 1.600E 03 3.430E+00 ;
ILI 4.960E 02 2.770E-02 6.300E+01 l FLI 1.470E+00 7.950E 01 1.730E+03 !
iTP 5.000E 01 2.420E-01 3.960E+02 l ITN 1.470E 02 1.800E-02 0 Sum non-break flow 2.037E+00 1.084E+00 2.192E+03 FRP - 11.75 gpm 5.210E+01 2.640E+01 4.340E+04 Sum - 11.75 gpm 5.4b+01 2.7E+01 4.6E+ 04 Postulated Control Room Dose (0-30 days)
MSLB - Co-incident lodine Spike EDE Skin DE Thyroid CDE mrom mrem mrem ASA 1.760E-04 2.060E 03 4.950E+00 ILI 1.170E-03 1.520E-02 3.320E+01 l FLI 8.620E 02 1.010E+00 2.430E+03 l ITC 6.520E-03 5.710E-02 5.350E+01 ITN 1.400E-03 5.460E 02 0 Sum non-break flow 9.547E-02 1.139E+00 2.522E+03 FRC - 11.75 gpm 2.820E+00 3.580E+01 2.370E+04 l Sum -11.75 gpm 2.9E+00 3.7E+01 2.6E+04 Postulated Control Room Dose (0 30 days)
MSLB - Pre-incident lodine Spike P-to-S Leak Rate EDE Skin DE Thyroid CDE mrom mrem mrem ASA 1.760E-04 2.060E-03 4.950E+00 ILI 1.170E 03 1.520E 02 3.320E+01 FLI 8.620E-02 1.010E+00 2.430E+03 ITP 1.400E 02 1.490E 01 2.830E+02 ITN 1.400E-03 5.460E-02 0 Sum non-break flow 1.029E-01 1.231 E+00 2.751 E+03 FRP - 11.75 gpm 1.360E+00 1.920E+01 2.580E+04 Sum - 11.75 gpm 1.5E+00 2.0E +01 2.9E+04
- - . . . - - ~ . _ . . - . - . . ~ , - -. - - . - . . - . . ... --
RTL: n/a Form: RE 1.103-3 02 i M
Health Physics Department ERS SFL-95 OO8 d page 19 I
l Postulated LPZ Dose (0-30 days)
MSLB - Co-incident lodine Spike
mrom mrom mrom i 1 ASA 1.710E 04 9.280E 05 1.990E-01 I ILI 6.800E 03 4.060E 03 1.010E+01 FLI 8.560E-02 4.610E-02 1.000E+02 ITC 3.990E-02 1.540E-02 1.070E+01 ITN 2.080E 03 3.330E-03 0 i
l Sum non-break flow 1.518E 01 7.558E 02 1.256E+02 FRC - 11.75 gpm 4 410E+01 1.900E+01 1.790E+04 Sum -11.75 gpm 4.4E+01 1.9E+01 - 1.85+04 i Postulated LPZ Dose (0-30 days) l MSLB - Pre-incident lodine Spike P-to-S Leak Rate EDE Skin DE Thyroid CDE l mrom mrom mrem ASA 1.710E 04 9.280E 05 1.990E 01 ILI 6.800E-03 4.060E-03 1.010E+01 FLI 8.560E 02 4.610E-02 1.000E+02 ITP 3.010E-02 1.470E-02 2.430E+01 ITN 2.080E-03 3.330E 03 0 Sum non-break flow 1.248E-01 6.828E-02 1.346E+02 4
FRC - 11.75 gpm 8.700E+00 4.920E+00 9.370E+03 Sum -11.75 gpm 8.8E+00 5.0E+00 9.5b+03 CONCLUSION The analysis documented herein has established that the maximum primary to-secondary leak rate that could be tolerated during a main steam line break outside of CNMT with RCS activity at 0.5 Cl/
gm is 8.1 gpm. The maximum primary-to-secondary leak rate that could be tolerated during a main steam line break outside of CNMT with RCS activity at 0.35 Ci/gm is 11.75 gpm.
REFERENCES
- 1. Westinghouse, Beaver Vallev Power Station 1 Steam Generator Tube Pluaging Criteria for Indications at Tube Suocort Plates. WCAP 14122, dtd 7/94
- 2. DLC, Unit 1 Control Room Isolation Sensitivity Analvsis. ERS KJW 96 013
- 3. DLC, RG1.145 Short Term Accident yf0 Values for EAB and LPZ. Unit 1 and Unit 2. based on 1986-1995 Observations. ERS SFL-96-021
_ _ . . _ . . . . _ _ _ _ _ _ _ _ _ . _ _ . . _ _ . . _ _ _ _ . _ _ _ _ . . _ . _ _ _ - _ _ . _ _ - . ~ .
f RTL: n/a Form: RE 1.103-3 GC2 UU@388N M ERS-SFL-95 008 d Heshh Physics Departnent page 20 l 4. USEPA, Umitino Values of Radionuclide intake and Air Concentration and Dose Conversion 1
Factors for Inhalation. Submersion. and Inhalation Federal Guidance Report No.11, EPA 520/
} 1 88-020
! 5. DLC, Uodated Final Safety Analvsis Reoort Unit 1.
! 6. SWEC, Control Room Habitabirity Due to Desian Basis Accident (exceot LOCA) at BVPS-2.
- 12241 UR(B)-445,1987
12241 UR(B)-190,1987 8.
SWEC, Doses to the Combined Control Room due to LOCA at BVPS-1.12241-UR(B)-450,1987
{ 9. SWEC, Combined BV1-BV2 Control Room Habitabifitv Due to Desian Basis Accidents (exceot l LOCA) at BV1.12241 UR(B)-456,1987 {
1 l 10. DLC, Uodated Final Safety Analvsis Reoort Unit 2.
l 11. DLC, Unit 2 FHA Doses at EAB. LPZ. and Common Control Room. ERS SFL-89-019 !
- 12. DLC, Safety Analysis of the Dose Consecuences of a Locked Rotor Accident at BVPS-1. ERS.
i
{ SFL 89 021 1
- 13. DLC, BVPS Common CR Rad HabihN!ity Durina a DBA SGTR atU2 (based on WCAP-12738.
ERS-SFL-90-030
- 14. DLC, Assessment of the Doses in the U2 CR Due to LRA at U2 - 18% F.F.. ERS MPD 91035 .
- 16. DLC, Cc,mbined Control Room Doses due to SGTR at Unit 1. ERS SFL 92-033 Ana!vsis of FHA in RBC at Unit 1. ERS-SFL-92-034
- 17. DLC, Combined Control Room Doses fem DBAs at Unit 1. ERS SFL 93-005,1993 i l
- 18. USNRC, Beaver Valley Power Station Unit No.1 Amendment 184 to Facility Operating Ucense ,
50-334, February 1995 '
- 19. USNRC, Voltaae Based Reoair Criteria for Westinghouse Steam Generator Tubes Affected by i Outside Diameter Stress Corrosion Crackina. Generic Letter 95-05
- 20. DLC, TRAILS _PC: Transpcrt of Radioactive Material in Unear Systems, PC Version v1.0.
ERS-SFL 96-004
- 21. DiNunno, J.J., etal, Calculation of Distance Factors for Power and Test Reactor Sites. USAEC TID 14844,1962
- 22. USNRC, Assumotions Used for Evaluating the Potential Radioloolcal Consecuences of a Loss of Coolant Accident for Pressurized Water Reactorg Regulatory Guide 1.4, Revision 2; 1974
- 23. USNRC, Assumotions Used for Evaluating the Potential Radiological Coreauences of a Fuel Handlina Accident in the Fuel Handlina and Storace Facility for Boilina and Pressurized Water Reactors. Regulatory Guide 1.25, Revision 0; 1972
- 24. DLC, Beaver Vallev Power Station Radionuclide Database and RADFILE. ERS SFL 84-004, Revision 0; 1984
- 25. Murphy, KG. and Campe, K.W., Nuclear Power Plant Control Room Ventilation Svstem Desian for Meeting General Criterion 19. published in proceedings of 13th AEC Air Cleaning Conference 1 l
i
. ~ . _. ._. . ._- - _. _ . - . ..
1 RTL: n/a Fcrm: RE 1.103-3 A92 D "'"M M Ak Hes2PhysicsDeputment ERS-SFL-95-008 d E 00
- 26. DLC, Combined Control Room Doses Due to DBA's at Unit 2 with Delaved Isolation.
ERS SFL-89-007, Revision 1; 1989 27 DLC, Rose Calculation Methodoloov in DBA Analvses. Radiologicai Engineering Administrative Procedure 1.106. '
- 28. USRNC, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants. NUREG 0800, Revision 5; 1987
- 29. DLC, U1 RCS and Steam Generator Isotooic Concentrations. Pre-incident Soike Concentrations.
and lodine Soike Accearance Rates Corresoondino to 0.35 and 0.5 mci /om RCS Soecific
~
3 Activitv. ERS-SFL-96-012 !
- 30. DLC, Unit 1 Technical Specifications.
ATTACHMENTS
- 1. Main Steam Line Break Model
- 2. Validation of Timing Assumptions J
- 3. 0.5 pCl/gm Case TRAILS _PC Printouts 1
- 4. MSLB isotopic Releases for 0.5 Cl/gm
- 5. 0.35 Ci/gm Case TRAILS _PC Printouts
- 6. MSLB isotopic Releases for 0.35 pCi/gm
- 7. Appendix 1, Control Room Model 1
i
X -.A-- n - 1 ~ ,
f -. - .
1 i
1 1
1 Intentionally Blank .
1 1
1 l
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l 1
1 i
l i
RTL:n/a Form RE 1.103-3 292 Attchment 1 MV4 D ""N @
ygg HeaMh Phymes Deprews ERS-SFL-95-008 d page:
23 0-8 hrs Main Steam Line Break ;
, a -
1 l
hrs; Uk. \ /
4-8 hrs; FRP spike /500 FRC,lTC - - FRC Fau
( y gre.lted, i
Only Rupture Flow, incident Faulted, Rupture Flow, Co- l incident N
/
0-8 hrs RCS 3.9E5 lbm
\ //
ITP ITC Intact, T/S, Pre incident MC950802.DS4 intact, T/S, Co-incident
RTL res Form RE 1.103-3 (S2 A
' Drum Lkfit Health Physics Department ERS-SFL-95-008 d page:
24 x
/
Main Steam Line Break l 0-8 hrs
{r D
\ #
ITN Intact, T/S, Noble Gases RCS _ _
3.9E5 lbm MC950802.DS4
RTL n's Form RE 1.103 3 A92 MYA U"N D Attachment 1 va g Health Physics Depahnt ERS-SFL-95-008 A 25 page:
Main Steam Line Break o-2 hrs l s 2-8 hrs s //
ILI Intact, Liquid Phase, Initial i
1-second 0-0.5 hrs
/ ,'
I Q R l
\ /// \ /
l ASA - -
FLI All, Steam Phase, All Faulted, Liquid Phase, Initial MC950802.DS4
i intentionally Blank i
1 l}
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5 4
e I
i
Duquesne Light Company Nuclear Power Division E6S-SFL-95-008 d Operations Experience Department Attachment 2 Page 27
> MEMORANDUM
^
TO: S.F.LaVie I
FROM: C. O'Neill 7 LOCATION: SOSB-4 l l '
DATE: September 17,1996 i l SUBIECT: MSLB Control Room Isolation Timing Validation l l
In your memo of 7/3/96, you requested assistance in obtaining time-related data for support of the Unit 2 Alternate Plugging Criteria assumptions based on a EOP Simulator Validation. E-2, " Faulted Steam
( Generator Isolation" (IB/2) was validated on September 17,1996 with the following results:
i .
The time from the reactor trip until CREBAPS was manually actuated was approximately 1000 s seconds (=17 minutes)
~
He time from the reactor trip until SG NR level was recovered to >5% in the unaffected SGs was
} approximately 2600 seconds (=43 minutes)
- ' He scenario run was for a 8 E+5 LBM/HR steam break (20%), outside CNMT on the B SG. His case is considered conservative since SLI was delayed which prolonged the SG blowdown and ==vimi=I the mass i loss from the unaffected SGs. For larger breaks, reactor trip, safety injection and SLI occur almost j
a simultaneously, and thus minimize unaffected SG blowdown. It should also be noted that the PO manually throttled total AFW flow to the unaffected SGs to about 365 GPM (per procedure) which is the minimum
[ acceptable AFW flow to provide an adequate heat sink. This action extended SG refill time to its j maximum limit. All other cases would be bounded by this feed flow value.
4
't In conclusion, both objectives were met with considerable margin and appropriate conservative j assumptions.
I will maintain the original data in the appropriate EOP history file. If you have any questions about this information, please call me at X4935.
CO/Img ,
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cc: G. E. Storolis ,
R. M. Vento A'. H. Brunner F. J. Schaffner
. M. P. Flynn T. W. Burns R. N. Ireland -
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. K. J. Winter l
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TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ASA Ct.ce for LPf. / CR dose 0.35 uci/gm [TC950851.DAT] **
- PROGENY ING"100 FIN ON * *
- I COMP: not used COMP: all S/Gs COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
_--__-_ . ____- - - _-____--------___- --___------ -= - - - - - ______-_---
INITIAL: 0.000E+00 Kr-83m 1.330E+00 Kr-83m uCi 0,000E+00 Kr-83m 0.000E+00 Kr-85m 6.490E+00 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 3.430E+01 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 3.700E+00 Kr-87 0.000E+00 Kr-87 0.0000+00 Kr-88 9.890E+00 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 3.120E-01 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 3.340E-01 Xe-131m 0.000E+00 Xe-131m !
0.000E+00 Xe-133m 9.520E+00 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 8.110E+01 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 3.370E+00 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 9.950E+00 Xe-135 0.000E+00 Xe-135 0.300E+00 Xe-137 5.050E-01 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 2.000E+00 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 2.380E+03 I-131 0.000E+00 I-131 0.000E+00 I-132 4.220E+02 I-132 0.000E+00 I-132 0.000E+00 I-133 3.110E+03 I-133 0.000E+00 I-133 0.000E+00 I-134 7.430E+01 I-134 0.000E+00 I-134 0.000E+00 I-135 1.140E+03 I-135 0.000E+00 I-135 ACT MULT (to uci): 1.000E+00 3.000E+00 1.000E+00 f
r I
t t
i ERS-SFL-95-008 d ASA for LPZ / CR (0.35 uCi/gm) Attachment 5 Page j j j
. . - - , - - - - . - . - - - - - - - - - - _ - - - - _ - - _ - _ - - _ _ - - - - _ _ - - -- + - -----_1 --u - - - _ - - - - - - - - -
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ASA Case for LPZ / CR dose 0.35 uCi/gm [TC950851.DAT] *** PROGENY INGROWTH ON ***
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 Crp 2 REL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Crp 3 REL nt: 0.000E+00 0.000E+00 INTAL 2 REDUCT: 0.000E+00 HULTIPLIERS= - >
ETEP TIME XPR XREM XRF XPR XREM XRF YPR XREM XRF 1 6.000E+01 .000 .000 .000 .000 1.00 .000 50.0 50.0 .000 2 1.800E+03 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 3 5.400E+03 .000 .000 .000 .000 000 .000 1.00 70.0 .000 4 7.200E+03 .000 .000 .000 .000 .000 .000 70.0 70.0 1.00 5 1.440E+04 .000 .000 .000 .000 .000 .000 70.0 70.0 1.00 6 2.880E+04 .000 .000 .000 .000 .000 .000 70.0 70.0 1.00 7 3.060E+04 .000 .000 .000 .000 .000 .000 3.350E+03 3.350E+03 .000 8 8.640E+04 .000 .000 .000 .000 .000 .000 50.0 50.0 .000
- 3.456E+05 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 10 2.592E+06 .000 .000 .000 .000 .000 .000 50.0 50.0 .000
CONTROL ROOH -------- ---- ENVIRONMENT ---
X/Q Breathing occupancy X/Q Breathing ;
s/M3 M3/s s/M3 M3/s 1.000E-03 3.470E-04 1.000E+00 1.000E-05 3.470E-04 HULTIPLIERS---->
ETEP TIME,a 1 6.000E+01 2.43 1.00 1.00 6.04 1.00 2 1.800E+03 2.43 1.00 1.00 6.04 1.00 3 5.400E+03 2.43 1.00 1.00 6.04 1.00 4 7.200E+03 2.43 1.00 1.00 6.04 1.00 5 1.440E+04 2.43 1.00 1.00 6.04 1.00 6 2.880E+04 2.43 1.00 1.00 6.04 1.00 7 3.060E+04 1.22 1.00 1.00 4.33 1.00 8 8.640E+04 1.22 1.00 1.00 4.33 1.00 9 3.456E+05 .890 1.00 .600 2.10 1.00 10 2.592E+06 .626 1.00 .400 .744 1.00 ERS-SFL-95-008 d ASA for LPZ / CR (0.35 uCi/gm) 9 Attachment 5 Page$ .1 u m_______ .. _ _ _ _ _ _ _ _ - - -
. . _ . __. .. ___ .. m , . ._.m . .. mm - . -. m . ., . .. . . .- . _ _ . ~ . _ _ _ _ - . t .
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ASA Case for LPE / CR dose 0.35 uCi/gm [TC950851.DAT] *** PROGENY INGROtfrH ON *** .
not used all S/Gs AVERAGE ----------CONTROL ROON-----------
CURRENT INTEGRD CURRENT INTEGRD BRT.FILSED RELEASE CURRENT CURRENT INTEGRD S TEP TIME uCi uCi-sec uCi uC1-sec uCi uCi/sec uCi uC1/cc uCi-sec
, K r-83aa INITIAL 0.000E+00 3.990E+00 0.000E+00 Ar-83m TOTALS 0.000E+00 2.887E-01 3.990E+00 1.356E+01 Kr-85m INITIAL 0.000E+00 1.947E+01 0.000E+00 Kr-85m TOTALS 0.000E+00 1.409E+00 1.947E+01 1.001E+02 Kr-85 INITIAL 0.000E+00 1.029E+02 0.000E+00 Kr-E5 TOTALS 0.000E+00 7.446E+00 1.029E+02 7.767E+02 Kr-87 INITIAL 0.000E+00 1.110E+01 0.000E+00 Kr-87 TOTALS 0.000E+00 8.032E-01 1.110E+01 2.987E+01 Kr-08 INITIAL 0.000E+00 2.967E+01 0.000E+00 Kr-88 TOTAL 5
- 000E+00
. 2.147E+00 2.967E+01 1.271E+02 Kr-89 INITIAL 0.000E+00 9.360E-01 0.000E+00 Kr-83 'IOTALS 0.000E+00 6.771E-02 9.358E-01 1.449E-01 Xa-131m INITIAL 0.000E+00 1.002E+00 0.000E+00 l X3-131m TOTALS 0.000E+00 7.250E-02 1.002E+00 1.149E+01 Xe-133m INITIAL 0.000E+00 2.856E+01 0.000E+00 Xe-133m TOTALS 0.000E+00 2.067E+00 2.856F'G1 2.757E+02 Xe-133 INITIAL O.000Er00 2.433E+02 0.000E+00 X.3-133 TOTALS 0.000E+00 1.760E+01 2.433E+02 2.785E+03 ,
Xe-135m INITIAL D.000E+00 1.011E+01 0.000E+00 $
Xs-135m TOTALS 0.000E+00 7.337E-01 1.014E+01 2.969E+03 Xe-1E INITIAL 0.000E+00 2.985E+01 0.000E+00 Xa-135 TOTALS 0.000E+00 2.160E+00 2.985E+01 3.878E+03 I
Xe-137 INITIAL 0.000E+00 1.515E+00 0.000E+00 t Xe-137 TOTALS 0.000E+00 1.096E-01 1.515E+00 2.834E-01 t Xe-138 INITIAL 0.000E+00 6.240E+00 0.000E+00 Xn-138 TOTALS 0.000E+00 4.515E-01 6.240E+00 4.113E+00 I-131 INITIAL 0.000E+00 7.140E+03 0.000E+00 1-131 TOTALS 0.000E+00 5.166E+02 7.140E+03 5.336E+04 ERS-SFL-95-008 A ASA for LPZ / CR (0.35 uCi/gm)- Attachment S Pagel ] 3 i
TRAILS PC -- Transport of Radioac*,1ve Material in Linear Systents, v1.0 A?A Case for LPZ / CR dose 0.35 uCi/gm [TC950851.DAT] *** PROGENY INGROWTH ON *** i not used all S/Gs AVERAGE ----------CONTROL ROON-- - =
CURRENT INTEGRD CURRENT INTEGRD RELEASED PPTFESE CURRENT CURRENT INTEGRD .
LTEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec I-132 INITIAL O.000E+00 1.266E+03 0.000E+00 I-132 TOTALS 0.000E+00 9.161E+01 1.266E+03 4.888E+03 I-133 INITIAL 0.000E+00 9.330E+03 0.000E+00 I-133 TOTALS 0.000E+00 6.751E+02 9.330E+03 6.429E+04 I-13e INITIAL 0.000E+00 2.229E+02 0.OOOE+00 I-134 TOTALS 0.000E+00 1.613E+01 2.229E+02 4.572E+02 ,
I-135 INITIAL 0.000E+00 3.420E+03 0.000E+00 I-135 TOTALS 0.000E+00 2.475E+02 3.420E+03 1.969E+04 i
s ERS-SFL-95-008 A ASA for LPZ / CR (0.35 uCi/gm) - Attachment 5 Page 1 ] 4
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ASA Case for LPE / CR dose 0.35 uci/gm [TC950851.DAT) *** PROGENY INGROWTH OK ***
- - -- - -----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 uren/hr aren ares /hr arem mres/hr mrem aren/hr mrem aren/hr~ arem aren/hr Kr-83m TOTALS 3.58E-12 0.00E+00 0.00E+00 2.07E-12 0.00E+00 0.00E+00 Kr-85m TOTALS 3.04E-08 6.01E-08 0.00E+00 2.66E-08 1.04E-06 0.00E+00 Kr-85 TOTALS 2.21E-09 3.09E-07 0.00E+00 2.83E-09 7.88E-06 0.00E+00 r
Kr-37 TOTALS 9.50E-08 2.25E-07 0.00E+00 4.34E-08 2.05E-06 0.00E+00 Kr-88 TOTALS 6.42E-07 1.41E-07 0.00E+00 4.67E-07 2.05E-06 0.00E+00 Kr-89 '
TOTALS 1.82E-08 ,
1.98E-08 0.00E+00 4.79E-10 1.03E-08 0.00E+00 Xe-131m i TOTAL 3 8.22E-11 9.11E-10 0.00E+00 1.60E-10 3.53E-08 0.00E+00 Xa-133m 1.77E-06 0.00E+00 !
TOTALS 8.15E-09 5.42E-08 0.00E+00 1.34E-08 Xa-133 TOTALS 8.21E-08 1.55E-07 0.00E+00 1.59E-07 6.00E-06 0.00E+00 X:2-135m TOTALS 4.17E-08 1.33E-08 0.00E+00 2.07E-06 1.31E-05 0.00E+00 Xe-135 .
TOTALS 7.16E-08 1.17E-07 0.00E+00 1.58E-06 5.12E-05 0.00E+00 Xe-137 TOTALS 2.77E-09 4.19E-08 0.00E+00 8.80E-11 2.65E-08 0.00E+00 Xe-138 TOTALS 7.49E-08 5.57E-08 0.00E+00 8.38E-09 1.24E-07 0.00E+00 1-131 TOTALS 2.61E-05 1.38E-05 1.62E-01 3.31E-05 3.48E-04 4.08E+00 ,
ERS-SFL-95-008 Ai ASA for LPZ / CR (0.35 uCi/gm) Attachment 5 Page }
~ TRAILS _PC -- Transport of Radioactive Material in Linear Syeless, v1.0 *** PROGENY INGROWTH ON ***
ASA Case for LPZ / CR dose 0.35 uCi/<pm [TC950851.DAT]
ENVIRONNENT- -------- -------CONTROL ROOM-------
SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY '"DE-INHAL External EDE DOSE RATE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE mrem area /hr nrem aren/hr mrem arem/hr narem mren/hr u.am mram/hr mram mren/hr I-132 2.23E-03 TOTALS 2.89E-05 8.54E-06 1.71E-04 1.89E-05 1.11E-04 I-133 8.20E-01 3.52E-02 6.41E-05 1.3 ?-03 TOTALS 5.48E-05 5.09E-05 I-134 3.47E-05 5.87E-06 1.93E-06 5.00E-06 2.05E-06 1.34E-05 TOTALS I-135 4.37E-02 5.46E-05 1.65E-05 2.24E-03 5.34E-05 3.22E-04 TOTALS ALL NUCLIDES 1.16E-02 1.39E+00 1.03E-02 9.28E-05 5.57E-03 1.99E-01 1.20E+01 5.00E-07 5.99E-05 5.39E-06 6.46E-04
.0167 h 1.71E-04 6.42E-01 1.27E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.72E-05 5.26E-05 2.95E-04 5.78E-04
.5000 h 0.00E+00 9.86E-01 0.00E+00 0.00E+00 0.80E+00 0.00E+00 4.46E-05 3.75E-05 4.99E-04 4.28E-04 1.12E+00 1.5000 h 0.00E+00 0.00E+00 4.63E-01 8.69E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.73E-05 3.18E-05 1.99E-04 3.69E-04 2.0000 h 0.00E+00 5.25E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.69E-05 1.68E-05 5.61E-04 2.08E-04 1.37E+00 4.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.90E-05 5.08E-06 4.99E-04 6.79E-05 1.32E+00 1.92E-01 8.C000 h 0.00E+00 8.5000 h 0.00E+00 0.00E+C'. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.34E-07 1.49E-08 5.81E-06 2.00E-07 1.65E-02 5.73E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.69E-08 5.89E-10 9.38E-07 8.65E-09 2.97E-03 3.48E-05 24.C000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.79E-09 8.51E-16 2.62E-08 1.04E-14 1.16E-04 9.28E-11 96.C000 h 0.00E+00 720.6000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.89E-15 0.00E+00 2.30E-14 0.00E+00 2.09E-10 0.00E+00 9.28E-05 1.99E-01 1.76E-04 2.06E-03 4.95E+00 TOTALS 1.71E-04 ERS-SFL-95-008 A ASA for LPZ / CR (0.35 uCi/gm) Attachment 5 Pagel } g
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 *** PROGENY INGROWTH ON ***
ITC Case for LPZ / CR dose 0.35 uC1/gu iTC950854.DAT)
COMP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
INITIAL: 0.000E+00 I-131 5.200E+07 I-131 uci 0.000E+00 I-131 0.000E+00 I-132 1.810E+07 I-132 0.000E+00 I-132 0.000E+00 I-133 8.100E+07 I-133 0.000E+00 I-133 0.000E+00 I-134 1.130E+07 I-134 0.000E+00 I-134 0.000E+00 I-135 4.360E+07 I-135 0.000E+00 I-135 1.000E+00 1.000E+00 1.000E+00 ACT MULT (to uci) : --______- -- ..-- .___ --_______ ..--_____---.__. .---_--_.-_------_-- ,
PRODUCTION,uci/s: 0.000E+00 I-131 4.900E+05 I-131 INTAKE: 1.000E+01 CEM O.000E+00 I-132 9.200E+05 I-132 0.000E+00 I-133 1.100E+06 I-133 0.000E+00 I-134 1.340E+06 I-134 0.000E+00 I-135 1.020E+06 I-135 t
i r
ERS-SFL-95-008 A ITC for LPZ/CR (0.35 uCi/gm) Attachment 5 Page 1 ] 7
-_---_ - - . _ . - _ _ - - _ _ _ _ _ - - _ - = _ - _ _ _ _ _ _ _
TRAILS _PC -- Transport of Radioactive Material in Linear Systemas, v1.0 ITC Case for LPZ / CR dose 0.35 uCi/gm [TC950854.DAT] *** PROGENY INGROWTH ON ***
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 m: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL m: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 MULTIPLIERS ==>
ETEP TIME XPR XREN XRF XPR XREN XRF XPR XREM XRF 1 1.800E+03 .000 .000 000 1.00 1.00 .000 50.0 50.0 .000 2 3.600E+03 .000 .000 .000 1.00 1.00 .000 1.00 70.0 .000 3 5.400E+03 .000 .000 .000 1.00 1.000E-02 .000 1.00 70.0 .000 4 7.200E+03 .000 .000 .000 1.00 1.000E-02 .000 70.0 70.0 1.00 5 1.440E+04 .000 .000 .000 1.00 1.000E-02 .000 70.0 70.0 1.00 6 2.880E+04 .000 .000 .000 2.000E-03 1.000E-02 .000 70.0 70.0 1.00 7 3.060E+04 .000 .000 .000 .000 .000 .000 3.350E+03 3.350E+03 .000 8 8.640E+04 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 9 3.456E+05 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 10 2.592E+06 .000 .000 .000 .000 .000 .000 50.0 50.0 .000
CONTROL ROOM -------- ---- ENVIRONMENT ---
X/O Breathing occupancy X/O Breathing s/M3 M3/s s/M3 H3/s 1.000E-03 ?.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS - >
STEP TIME,a 1 1.800E+03 2.43 1.00 1.00 6.04 1.00 2 3.600E+03 2.43 1.00 1.00 6.04 1.00 ;
3 5.400E+03 2.43 1.00 1.00 6.04 1.00 4 7.200E+03 2.43 1.00 1.00 6.04 1.00 5 1.440E+04 2.43 1.00 1.00 6.04 1.00 6 2.880E+04 2.43 1.00 1.00 6.04 1.00 7 3.060E+04 1.22 1.00 1.00 4.33 1.00 8 8.640E+04 1.22 1.00 1.00 4.33 1.00 9 3.456E+05 .890 1.00 .600 2.10 1.00 10 2.592E+06 .626 1. J .400 .744 1.00 ERS-SFL-95-008 A ITC for LPZ/CR (0.35 uCi/gm) Attachment 5 Page } } g
- _ _ . = _ _ _
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITC Ccse for LPZ / CR dose 0.35 uci/gm [TC950854.DAT] *** PROGENY INGROWTH ON ***
not used intact S/G AVERAGE ----------CONTROL ROOH-----------
CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uC1 uCi-see uCi uCi-sec uCi uCi/sec uci uC1/cc uCi-sec Xa-131m INITIAL 0.000E+00 0.000E+00 0.000E+00 Xa-131m TOTALS 0.000E+00 4.822E+13 1.078E+01 8.144E+01 X2-133m INITIAL 0.000E+00 0.000E+00 0.000E+00 Ka-133m TOTALS 0.000E+00 4.962E+13 3.196E+02 2.339E+03 Xa-133 INITIAL 0.000E+00 0.000E+00 0.000E+00 Xa-133 TOTALS 0.000E+00 1.683E+15 4.565E+03 3.371E+04 X3-135m INITIAL 0.000E+00 0.000E+00 0.000E+00 Xa-135m TOTALS 0.000E+00 8.361E+13 6.390E+04 1.396E+05 Xe-135 INITIAL 0.000E+00 0.000E+00 0.000E+00 Xa-135 TOTALS 0.000E+00 5.067E+14 4.548E+04 3.085E+05 I-131 INITIAL O.000E+00 5.200E+07 0.000E+00 I-131 TOTALS 0.000E+00 6.596E+15 3.344E+05 5.065E+05 I-132 INITIAL 0.000E+00 1.810E+07 0.000E+00 I-132 TOTALS 0.000E+00 1.588E+14 4.634E+05 4.220E+05 I-133 INITIAL 0.000E+00 8.100E+07 0.000E+00 I-133 TOTALS 0.000E+00 1.723E+15 7.158E+05 1.011E+06 I-334 INITIAL 0.000E+00 1.130E+07 0.000E+00 I-134 TOTALS 0.000E+00 8.808E+13 5.252E+05 2.915E+05 I-135 INITIAL 0.000E+00 4.360E+07 0.000E+00 I-135 TOTALS 0.000E+00 5.067E+14 6.080E+05 7.477E+05 ERS-SFL-95-008 A ITC for LPZ/CR (0.35 uCi/gm) Attachment S Pagel 19
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITC Case for LPZ / CR dose 0.35 uci/gm tTC950854.DAT] e** PROGENY INGROWTH ON ***
ENVIRONMENT--------- --- -- --C0NTROL ROOM-------
External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL EW DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr arem aren/hr arem aren/hr arem mrem /hr nresa aren/hr arem aren/hr Xs-131m TOTALS 8.85E-10 9.81E-09 0.00E+00 1.13E-09 2.50E-07 0.00E+00 Xe-133m TOTALS 9.12E-08 6.06E-07 0.00E+00 1.13E-07 1.50E-05 0.00E+00 Xe-133 TOTALS 1.54E-06 2.91E-06 0.00E+00 1.93E-06 7.26E-05 0.00E+00 Xe-_135m TOTAL 3 2.63E-04 8.35E-05 0.00E+00 9.75E-05 6.17E-04 0.00E+00 Xa-135 TOTALS 1.09E-04 1.78E-04 0.00E+00 1.26E-04 4.08E-03 0.00E+00 I-131 TOTALS 1.22E-03 6.45E-04 7.57E+00 3.15E-04 3.30E-03 3.87E+01 I-132 TOTALS 1.06E-02 3.13E-03 6.25E-02 1.64E-03 9.62E-03 1.'93E-01 I-133 TOTALS 4.20E-03 3.90E-03 2.70E+00 1.01E-03 1.86E-02 1.29E+01 I-134 TOTAL 3 1.38E-02 4.55E-03 1.18E-02 1.30E-03 8.53E-03 2.21E-02 I-135 TOTALS 9.71E-03 2.94E-03 3.99E-01 2.03E-03 1.22E-02 1.66E+00 ALL NUCLIDES
.5000 h B.69E-03 1.74E-02 3.25E-03 6.49E-03 1.98E+00 3.95E+00 6.94E-04 2.65E-03 5.21E-03 2.00E-02 3.34E+00 1.32E+01 1.C100 h 2.35E-02 4.70E-02 8.84E-03 1.77E-02 5.53E+00 1.11E+01 1.18E-03 2.10E-03 9.03E-03 1.63E-02 6.35E+00 1.23E+01 1.5!00 h 3.58E-04 7.16E-04 1.37E-04 2.73E-04 9.06E-02 1.81E-01 9.12E-04 1.58E-03 7.21E-03 1.27E-02 5.76E+00 1.08E+01 2.0000 h 4.63E-04 9.26E-04 1.79E-04 3.58E-04 1.26E-01 2.51E-01 6.97E-04 1.23E-03 5.71E-03 1.02E-02 5.08E+00 9.55E+00 4.0*00 h 2.67E-03 1.33E-03 1.07E-03 5.34E-04 8.46E-01 4.23E-01 1.66E-03 5.56E-04 1.47E-02 5.31E-03 1.54E+01 6.12E+00 8.0100 h 4.25E-03 1.06E-03 1.95E-03 4.89E-04 2.17E+00 5.43E-01 1.36E-03 2.16E-04 1.49E-02 2.77E-03 1.73E+01 3.05E+00 8.5200 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.84E-05' 6.10E-07 2.36E-04 8.00E-06 2.61E-01 9.08E-03 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.37E-06 1.56E-08 3.40E-05 2.56E-07 4.63E-02 5.27E-04 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.39E-08 1.32E-14 7.22E-07 1.73E-13 1.74E-03 1.32E-09 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.92E-14 0.00E+00 3.76E-13 0.00E+00 2.97E-09 0.00E+00 TUTAI.S 3.99E-02 1.54E-02 1.07E+01 6.52E-03 5.71E-02 5.35E+01 ERS-SFL-95-008 d ITC for LPZ/CR (0.35 uCi/gm) Attachment 5 Page12 0
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TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITN cme for LPE / CR dose [TC950856.DAT) *** PROGENY INGROWTH ON ***
COMP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
INITIAL: 0.000E+00 Kr-83m 8.880E+06 Kr-83m uC1 0.000E+00 Kr-83m 0.000E+00 Kr-85m 4.340E+07 Kr-SSm 0.000E+00 Kr-85m 0.000E+00 Kr-85 2.290E+08 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 2.480E+07 Kr-87 0.000E+00 Kr-87 C.000E+00 Kr-88 6.610E+07 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 2.090E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 2.230E+06 Xe-131m 0.000E+00 Xe-131m i 0.000E+00 Xe-133m 6.360E+07 Xe-133m 0.000E+00 Xe-133m !
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0.000E+00 Xe-138 1.390E+07 Xe-138 0.000E+00 Xe-138 +
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TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITH Case for LPE / CR dose tTC950856.DAT] *** PROGENY INGRONTH ON ***
not used intact S/G AVERAGE --- - - -
CONTROL ROOH-----------
CURRENT INTEGRD CURRENT INTEGRD RELEASED RETRASE CURRENT CURRENT INTEGRD gTEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 8.880E+06 0.000E+00 Kr-83m TOTALS 0.000E+00 8.435E+10 5.538E+03 1.551E+04 Kr-85m INITIAL 0.000E+00 4.340E+07 0.000E+00 Kr-85m TOTALS 0.000E+00 1.009E+12 4.942E+04 2.051E+05 Kr-05 INITIAL 0.000E+00 2.290E+08 0.000E+00 Kr-85 TOTALS 0.000E+00 5.908E+14 4.545E+05 2.458E+06 Kr-87 INITIAL 0.000E+00 2.480E+07 0.000E+00 Kr-87 TOTALS 0.000E+00 1.637E+11 1.115E+04 2.371E+04 Kr-98 INITIAL 0.000E+00 6.610E+07 0.000E+00 Kr-88 TOTALS 0.000E+00 9.741E+11 5.768E+04 2.045E+05 Kr-89 INITIAL 0.000E+00 2.090E+06 0.000E+00 Kr-99 TOTALS 0.000E+00 5.717E+08 3.944E+01 6.093E+00 Xa-131m INITIAL 0.000E+00 2.230E+06 0.000E+00 Xa-131m TOTALS 0.000E+00 2.717E+12 4.383E+03 2.361E+04 Xa-133m INITIAL 0.000E+00 6.360E+07 0.000E+00 Xo-133m TOTALS 0.000E+00 1.733E+13 1.198E+0S 6.337E+05 ,
Xo-133 INITIAL 0.000E+00 5.420E+08 0.000E+00 Xa-133 TOTALS 0.000E+00 3.637E+14 1.055E+06 5.659E+06 Xa-135m INITIAL O.000E+00 2.250E+07 0.000E+00 Xa-135m TOTALS 0.000E+00 2.991E+10 2.064E+03 1.125E+03 Xa-135 INITIAL 0.000E+00 6.650E+07 0.000E+00 Xa-135 TOTALS 0.000E+00 3.172E+12 9.979E+04 4.748E+05 Xa-137 INITIAL 0.000E+00 3.380E+06 0.000E+00 Xa-137 TOTALS 0.000E+00 1.121E+09 7.731E+01 1.439E+01 Xa-138 INITIAL 0.000E+00 1.390E+07 0.000E+00 Xe-138 TOTALS 0.000E+00 1.700E+10 1.173E+03 6.081E+02 ERS-SFL-95-008 d ITN for LPZ/CR (0.35 uCi/gm) Attachment 5 Page 12 3
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TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITN Case for LPE / CR dose [TC950856.DAT] *** PROGENY INGROWTH ON ***
- ---------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 mren/hr mrem arem/hr uren aren/hr arem mren/hr arem arem/hr mrem aren/hr Kr-83m TOTALS 4.97E-09 0.00E+00 0.00E+00 2.36E-09 0.00E+00 0.00E+00 Kr-85m TOTALS 7.73E-05 1.53E-04 0.00E+00 5.45E-05 2.14E-03 0.00E+00 Kr-85 TOTALS 9.76E-06 1.37E-03 0.00E+00 8.96E-06 2.49E-02 0.00E+00 Kr-87 TOTALS 9.54E-05 2.26E-04 0.00E+00 3.45E-05 1.63E-03 0.00E+00 Er-88 TOTALS 1.25E-03 2.75E-04 0.00E+00 7.52E-04 3.29E-03 0.00E+00 ,
t i
Kr-89 TOTALS 7.68E-07 8.34E-07 0.00E+00 2.01E-08 4.35E-07 0.00E+00 i
Xe-131m ,
TOTALS 3.60E-07 3.99E-06 0.00E+00 3.29E-07 7.25E-05 O.00E+00 Xm-133m TOTALS 3.42E-05 2.27E-04 0.00E+00 3.07E-05 4.06E-03 0.00E+00 X9-133 TOTALS 3.56E-04 6.73E-04 0.00E+00 3.24E-04 1.22E-02 0.00E+00 Xa-135m TOTALS 8.48E-06 2.70E-06 0.00E+00 7.85E-07 4.97E-06 0.00E+00
-X2-135 TOTALS 2.39E-04 3.90E-04 0.00E+00 1.93E-04 6.27E-03 0.00E+00 Xe-137 TOTALS 1.41E-07 2.14E-06 0.00E+00 4.47E-09 1.35E-06 0.00E+00 Xa-138 TOTALS 1.41E-05 1.05E-05 0.00E+00 1.24E-06 1.83E-05 0.00E+00 ERS-SFL-95-008 A ITN for LPZ/CR (0.35 uCi/gm) Attachment 5 Page 12 4
' TRAILS PC -- Transport of Radioactive Naterial in Linear Systems, v1.0 ITN Case for LPE / CR dose [TC950856.DAT] *** PROGENY INGRONTH ON ***
-----ENVIRONMENT---- ----
CONTROL ROOM-------
External EDE SKIN-DE THY CDE-INRAL External EDE SKIN-DE TNY CDE-INNAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATT.
arena aram/hr arem aren/hr arena unrea/hr arem aren/hr arean aram/hr arem aren/hr ALL NUCLIDES
.5000 h 2.62E-04 5.23E-04 2.96E-04 5.92E-04 0.00E+00 0.00E+00 2.10E-05 8.05E-05 4.80E-04 1.86E-03 0.00E+00 0.00E+00 1.0C00 h 2.22E-04 4.43E-04 2.65E-04 5.31E-04 0.00E+00 0.00E+00 3.56E-05 6.33E-05 8.48E-04 1.55E-03 0.00E+00 0.00E+00 1.5000 h 1.96E-04 3.92E-04 2.47E-04 4.95E-04 0.00E+00 0.00E+00 2.85E-05 5.12E-05 7.15E-04 1.32E-03 0.00E+00 0.00E+00 2.0200 h 1.76E-04 3.51E-04 2.34E-04 4.68E-04 0.00E+00 0.00E+00 4.29E-05 1.18E-04 1.15E-03 3.21E-03 0.00E+00 0.00E+00 4.0000 h 5.52E-04 2.7 2-04 8.42E-04 4.21E-04 0.00E+00 0.00E+00 3.65E-04 2.32E-04 1.15E-02 7.85E-03 0.00E+00 0.00E+00 8.0G00 h 6.78E-04 1.69E-04 1.44E-03 3.61E-04 0.00E+00 0.00E+00 8.86E-04 2.20E-04 3.88E-02 1.11E-02 0.00E+00 0.00E+00 8.5!00 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.87E-05 6.20E-07 9.52E-04 3.29E-05 0.00E+00 0.00E+00 24.0100 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.34E-06 1.77E-08 1.64E-04 1.86E-06 0.00E+00 0.00E+00 96.0%00 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.63E-08 3.84E-14 6.28E-06 5.82E-12 0.00E+00 0.00E+00 720.CC00 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.59E-14 0.00E+00 1.33E-11 0.00E+00 0.00E+00. 0.00E+00 TOTALS 2.08E-03 3.33E-03 0.00E+00 1.40E-03 5.46E-02 0.00E+00 ERS-SFL-95-008 d ITN for LP71CR (0.35 uCi/gm) Attachment S Page 12 5
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 FRC Case for LPZ / CR dose for 11.75 gpm [TC950840.DAT] *** PROGENY INGROWTH ON ***
COMP: not used COMP: Affected S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
INITIAL: 0.000E+00 Kr-83m 8.880E+06 Kr-83m uci 0.000E+00 Kr-83m 0.000E+00 Kr-85m 4.340E+07 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 2.290E+08 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 2.480E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 6.610E+07 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 2.090E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 2.230E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 6.360E+07 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 5.420E+08 Xe-133 0.000E+00 Ye-133 0.000E+00 Xe-135m 2.250E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Ye-135 6.650E+07 Xe-135 0.000E+00 Ke-135 0.000E+00 Xe-137 3.380E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 1.390E+07 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 5.200E+07 I-131 0.000E+00 I-131 0.000E+00 I-132 1.810E+07 I-132 0.000E+00 I-132 0.000E+00 I-133 8.100E+07 I-133 0.000E+00 I-133 0.000E+00 I-134 1.130E+07 I-134 0.000E+00 I-134 0.000E+00 I-135 4.360E+07 I-135 0.000E+00 I-135 ACT HULT (to uC1) : 1.000E+00 1.000E+00 1.000E+00 PRODUCTION,uci/s: 0.000E+00 I-131 4.900E+05 I-131 INTAKE: 1.000E+01 CEM 0.000E+00 I-132 9.200E+05 I-132 0.000E+00 I-133 1.100E+06 I-133 0.000E+00 I-134 1.340E+06 I-134 0.000E+00 I-135 1.020E+06 I-135 ERS-SFL-95-008 d FRC for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment S Page 12 6
TRAILS,PC -- Transport of Radioactive Material in Linear Systems, v1.0 ERC Crxe for LPE / CR dose for 11.75 gpm [TC950840.DAT] *** PROGENY INGROWTH ON ***
REMOVAL: 0.000E+00 1/sec 3.891E-06 1/sec 1.000E+01 cfm NUC Crp 1 REL ER: 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 Crp 3 REL ER: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 MULTIPLIERS - =>
STEP TIME XPR XREN XRF XPR XREM XRF XPR XREN XRF 1 1.800E+03 .000 .000 .000 1.00 1.00 .000 50.0 50.0 .000 2 3.600E+03 .000 .000 .000 1.00 1.00 .000 1.00 70.0 .000 3 5.400E+03 .000 .000 .000 1.00 1.00 .000 1.00 70.0 .000 4 7.200E+03 .000 .000 .000 1.00 1.00 .000 70.0 70.0 1.00 5 1.440E+04 .000 .000 .000 1.00 1.00 .000 70.0 70.0 1.00 6 2.880E+04 .000 .000 .000 2.000E-03 1.00 .000 70.0 70.0 1.00 7 3.060E+04 .000 .000 .000 .000 .000 .000 3.350E+03 3.350E+03 .000 8 8.640E+04 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 9 3.456E+05 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 10 2.592E+06 .000 .000 .000 .000 .000 .000 50.0 50.0 .000
CONTROL ROOH -------- ---- ENVIRONMENT ---
X/O Breathing Occupancy I/O Breathing s/M3 M3/s s/M3 M3/s 1.000E-03 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS >
CTEP TIME,a 1 1.800E+03 2.43 1.00 1.00 6.04 1.00 2 3.600E+03 2.43 1.00 1.00 6.04 1.00 3 5.400E+03 2.43 1.00 1.00 6.04 1.00 4 7.200E+03 2.43 1.00 1.00 6.04 1.00 5 1.440E+04 2.43 1.00 1.00 6.04 1.00 6 2.880E+04 2.43 1.00 1.00 6.04 1.00 7 3.060E+04 1.22 1.00 1.00 4.33 1.00 8 8.640E+04 1.22 1.00 1.00 4.33 1.00 9 3.456E+05 .890 1.00 .600 2.10 1.00 10 2.592E+06 .626 1.00 .400 .744 1.00 ERS-SFL-95-008 d FRC for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 127
--- _ _ _ . _ _ _ - _-_. _ _ _ _ _ _ ._ _ _ = _- . = _ _ . . - _ ._ .. . ._. - __
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 Mtc Cu e for LPE / CR dose for 11.75 gpm [TC950840.DAT] * * *PROGDR INGROWTH ON * *
- not used Affected S/G AVERAGE ----------CONTROL ROOH-----------
CURRENT INTEGRD CURRENT INTEGRD RET.FASED BFT.FASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uC1/cc uCi-sec Kr-83m INITIAL 0.000E+00 8.880E+06 0.000E+00 Kr-83m TOTALS 0.000E+00 8.152E+10 3.030E+05 8.442E+05 Kr-85m INITIAL 0.000E+00 4.340E+07 0.000E+00 Kr-85m TOTALS 0.000E+00 9.477E+11 2.669E+06 1.105E+07
+
Kr-85 INITIAL 0.000E+00 2.290E+08 0.000E+00 Kr-85 TOTALS 0.000E+00 5.296E+14 2.428E+07 1.315E+08 i
Kr-G7 INITIAL O.000E+00 2.480E+07 0.000E+00 Kr-87 TOTALS 0.000Et00 1.597E+11 6.142E+05 1.299E+06 Kr-23 INITIAL 0.000E+00 6.610E+07 0.000E+00 Kr-88 TOTALS 0.000E+00 9.288E+11 3.132E+06 1.107E+07 Kr-89 INITIAL 0.000E+00 2.090E+06 0.000E+00 Kr-@@ TOTALS 0.000E+00 5.711E+08 2.222E+03 3.433E+02 Xe-131m INITIAL 0.000E+00 2.230E+06 0.000E+00 Xe-131m TOTALS 0.000E+00 4.677E+13 2.803E+05 1.504E+06 Xa-133m INITIAL 0.000E+00 6.360E+07 0.000E+00 Xe-133m TOTALS 0.000E+00 6.125E+13 7.761E+06 4.092E+07 Xs-133 INITTAL 0.000E+00 5.420E+08 0.000E+00 X3-133 TOIALS 0.00CE+00 1.874E+15 7.579E+07 4.040E+08 Xa-135m INITIAL O.000E+00 2.250E+07 0.000E+00 Xa-135m TOTALS 0.000E+00 7.848E+13 1.379E+08 1.674E+08 Xa-135 INITIAL 0.000E+00 6.650E+07 0.000E+00 X3-135 TOTALS 0.000E+00 4.704E+14 1.931E+08 9.418E+08 Xe-137 INITIAL 0.000E+00 3.380E+06 0.000E+00 Xa-137 TOTALS 0.000E+00 1.119E+09 4.354E+03 8.104E+02 Xa-138 INITIAL 0.000E+00 1.390E+07 0.000E+00 X9-138 TOTALS 0.OGOE+00 1.692E+10 6.584E+04 3.419E+04 I-131 INITIAL 0.000E+00 5.2OOE+07 0.000E+00 I-131 TOTALS 0.000E+00 6.071E+15 5.676E+08 2.254E+08 ERS-SFL-95-008 A FRC for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 12 8
v1.0 TRAILD_PC -- Transport of Radioactive Material in Linear Systemas, *** PROGENY INGROWTH ON ***
ERC Case for LPZ / CR dose for 11.75 gpa [TC950840.DAT]
Affected S/G AVERAGE ----------CCNTROL ROOH-----------
not used CURRENT INTEGRD ItFY.RR *ED RELEASE CURRENT CURRENT INTEGRD CURRENT INTEGRD STEP TIME uC1 uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec 0.000E+00 1.810E+07 0.000E+00 I-133 INITIAL 1.412E+08 I-132 TOTALS 0.000E+00 1.529E+14 4.950E+08 0.000E+00 8.100E+07 0.000E+00 I-133 INITIAL 4.443E+08 I-133 TOTALS 0.000E+00 1.598E+15 1.162E+09 INITIAL 0.000E+00 1.130E+07 0.000E+00 I-134 6.308E+07 I-134 TOTALS 0.000E+00 8.657E+13 3.326E+08 0.000E+00 4.360E+07 0.000E+00 I-135 INITIAL 3.088E+08 I-135 TOTALS 0.000E+00 4.766E+14 8.784E+08 L
i ERS-SFL-95-008 d FRC for LPZ / CR 11.75 gpm (0.35 uCi/gm) ' Attachment S Page 12 9
.~, -.. . - - . . . . . . . . . . - .. . . . - . ..- . . ~ ~ . . . .- . . . . . . . ..
TRAIL 3_PC -- Transport of Radioactive Material in Linear Systems, v1.0 ERC Ccse for LPE / CR dose for 11.75 gpa [TC950840.DAT] *** PROGENY INGROWTH ON ***
- ----- ---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 uren aren/hr arena aren/hr arem mram/hr arem aren/hr Kr-83m TOTALS 2.72E-07 0.00E+00 0.00E+00 1.29E-07 0.00E+00 0.00E+00 Kr-85m TOTALS 4.17E-03 8.24E-03 0.00E+00 2.94E-03 1.15E-01 0.00E+00 ,
i Kr-85 TOTALS 5.21E-04 7.29E-02 0.00E+00 4.80E-04 1.33E+00 0.00E+00 I f
Kr-87 TOTALS 5.26E-03 1.25E-02 0.00E+00 1.89E-03 8.91E-02 0.00E+00 [
Kr-88 TOTALS 6.78E-02 1.49E-02 0.00E+00 4.07E-02 1.78E-01 0.00E+00 L
Kr-89
'EDTALS 4.32E-05 4.70E-05 0.00E+00 1.13E-06 2.45E-05 0.00E+00 Xa-131m TOTALS 2.30E-05 2.55E-04 0.00E+00 2.10E-05 4.62E-03 0.00E+00 l Xe-133m TOTALS 2.21E-03 1.47E-02 0.00E+00 1.98E-03 2.62E-01 0.00E+00 i
Xs-133 l TOTALS 2.56E-02 4.83E-02 0.00E+00 2.31E-02 8.70E-01 0.00E+00 i Xa-135m l TOTALS 5.67E-01 1.80E-01 O.00E+00 1.17E-01 7.40E-01 0.00E+00 9
Xa-135 TOTALS 4.63E-01 7.55E-01 0.00E+00 3.84E-01 1.24E+01 0.00E+00 i
Xe-137 TOTALS 7.96E-06 1.21E-04 0.00E+00 2.52E-07 7.58E-05 0.00E+00 Xe-138 TOTALS 7.90E-04 5.88E-04 0.00E+00 6.97E-05 1.03E-03 0.00E400 I-1 11 TOTALS 2.08E+00 1.10E+00 1.28E+04 1.40E-01 1.47E+00 1.72E+04 r
ERS-SFL-95-008 A .
FRC for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 13 0
TRAILS _PC -- Transport of Radioactive Material in Linear Systemas, v1.0 FRC Case for LPE / CR dose for 11.75 gpm [TC950840.DAT] *** PROGENY INGROWTH ON ***
ENVIRONNENT---- -----
--- - ---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 aresa aren/hr arem mren/hr arena aren/hr arem aren/hr arem arem/hr arem aren/hr I-132 TOTALS 1.13E+01 3.34E+00 6.68E+01 5.47E-01 3.22E+00 6.44E+01 I-133
, TOTALS 6.82E+00 6.34E+00 4.38E+03 4.43E-01 8.19E+00 5.66E+03 I-134 TOTALS 8.76E+00 2.88E+00 7.46E+00 2.82E-01 1.85E+00 4.78E+00 I-135 TOTALS 1.40E+01 4.24E+00 5.76E+02 8.38E-01 5.04E+00 6.85E+02 ALL NUCLIDES
.5100 h 5.04E-01 1.01E+00 1.99E-01 3.98E-01 1.11E+02 2.22E+02 4.02E-02 1.54E-01 3.20E-01 1.23E+00 1.88E+02 7.40E+02 1.0000 h 1.33E+00 2.66E+00 5.11E-01 1.02E+00 3.10E+02 6.21E+02 6.83E-02 1.22E-01 5.55E-01 1.01E+00 3.57E+02 6.90E+02 1.5000 h 2.01E+00 4.03E+00 7.78E-01 1.56E+00 5.06E+02 1.01E+03 5.60E-02 1.04E-01 4.70E-01 8.83E-01 3.41E+02 6.73E+02 2.0E00 h 2.59E+00 5.19E+00 1.01E+00 2.02E+00 6.99E+02 1.40E+03 6.74E-02 1.62E-01 6.00E-01 1.49E+00 4.20E+02 1.00E+03 4.0000 h 1.48E+01 7.40E+00 5.95E+00 2.98E+00 4.67E+03 2.33E+03 5.94E-01 3.95E-01 6.14E+00 4.30E+00 4.04E+03 2.88E+03 8.0100 h 2.29E+01 5.72E+00 1.06E+01 2.64E+00 1.16E+04 2.90E+03 1.94E+00 5.57E-01 2.69E+01 8.43E+00 1.78E+04 5.56E+03 8.5100 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.71E-02 1.54E-03 7.18E-01 2.42E-02 4.76E+02 1.66E+01 24.CC00 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.76E-03 3.54E-05 1.01E-01 7.28E-04 8.43E+01 9.53E-01 95.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.75E-05 2.66E-11 2.05E-03 6.46E-10 3.15E+00 2.37E-06 720.CC00 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.86E-11 0.00E+00 1.44E-09 0.00E+00 5.33E-06 0.00E+00 TOTALS 4.41E+01 1.90E+01 1.79E+04 2.82E+00 3.58E+01 2.37E+04 ERS-SFL-95-008 [1\
FRC for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 131
TRAILS _PC -- Transport of Radioactive Material in I.inear Systems, v1.0 ITP Case for LPF. / CR dose [TC950855.DAT] *** PROGENY INGROWTH ON ***
COMP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
INITIAL: 0.000E+00 I-131 3.170E+09 I-131 uC1 0.000E+00 I-131 0.000E+00 I-132 1.100E+09 I-132 0.000E+00 I-132 0.000E+00 I-133 4.930E+09 I-133 0.000E+00 I-133 0.000E+00 I-134 6.910E+08 I-134 0.000E+00 I-134 0.000E+00 I-135 2.660E+09 I-135 0.000E+00 I-135 ACT MULT (to uci) : 1.000E+00 1.000E+00 1.000E+00 ERS-SFL-95-008 d ITP for LPZ / CR (0.35 uCi/gm) Attachment 5 Page 13 2
. . . . . . _ . . _ . - _ _ . __.m_ _ __m . ...m _ __ .. . _ _ _ _ . . . . . _ _._,._ _. . ~ . .
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITP Case for LPZ / CR dose [TC950855.DATj *** PROGENY INGROWTH ON ***
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: 0.0002+00 NUC Crp 2 REL IR: 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 1.800E+03 .000 .000 .000 .000 1.00 .000 50.0 50.0 .000 2 3.600E+03 .000 .000 .000 .000 1.00 .000 1.00 70.0 .000 3 5.400E+03 .000 .000 .000 .000 1.000E-02 .000 1.00 70.0 .000 4 7.200E+03 .000 .000 .000 .000 1.000E-02 .000 70.0 70.0 1.00 5 1.440E+04 .000 .000 .000 .000 1.000E-02 .000 70.0 70.0 1.00 G 2.880E+04 .000 .000 .000 .000 1.000E-02 .000 70.0 70.0 1.00 7 3.060E+04 .000 .000 .000 .000 .000 .000 3.350E+03 3.350E+03 .000 8 8.640E+04 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 9 3.456E+05 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 10 2.592E+06 .000 .000 .000 .000 .000 .000 50.0 50.0 .000
CONTROL ROOM -------- ---- ENVIRONMENT --- >
X/Q Breathing occupancy X/Q Breathing ,
s/M3 M3/s s/M3 M3/s 1.000E-03 3.470E-04 1.000E+00 1.000E-05 3.470E-04 MULTIPLIERS >
ETEP TIME,s 1 1.800E+03 2.43 1.00 1.00 6.04 1.00 2 3.600E+03 2.43 1.00 1.00 6.04 1.00 3 5.400E+03 2.43 1.00 1.00 6.04 1.00 4 7.200E+03 2.43 1.00 1.00 6.04 1.00 5 1.440E+04 2.43 1.00 1.00 6.04 1.00 6 2.880E+04 2.43 1.00 1.00 6.04 1.00 7 3.060E+04 1.22 1.00 1.00 4.33 1.00 8 8.640E+04 1.22 1.00 1.00 4.33 1.00 9 3.456E+05 .890 1.00 .600 2.10 1.00 10 2.592E+06 .626 1.00 .400 .744 1.00 i
L ERS-SFL-95-008 d ITP for LPZ / CR (0.35 uCi/gm) Attachment 5 Page133
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITP Crse for LPZ / CR dose [TC950855.DAT) *** PROGENY INGROWTH ON ***
not used intact S/G AVERAGE - - -
-- ---CONTROL ROOH-----------
CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT -INIEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Xe-131m INITIAL 0.000E+00 0.000E+00 0.000E+00 Xe-131m TOTALS 0.000E+00 2.151E+13 1.693E+01 2.685E+02 Xa-133m INITIAL 0.000E+00 0.000E+00 0.000E+00 Xa-133m TOTALS 0.000E+00 1.533E+13 3.582E+02 5.435E+03 Xa-133 INITIAL 0.000E+00 0.000E+00 0.000E+00 Xe-133 TOTALS 0.000E+00 5.201E+14 5.094E+03 7.807E+04 Xe-135m INITIAL 0.000E+00 0.000E+00 0.000E+00 Xa-135m TOTALS 0.000E+00 1.506E+13 7.359E+04 3.009E+05 Xa-135 INITIAL 0.000E+00 0.000E+00 0.000E+00 Ye-135 TOTALS 0.000E+00 9.129E+13 3.154E+04 4.284E+05 I-131 INITIAL 0.000E+00 3.170E+09 0.000E+00 I-131 TOTALS 0.000E+00 2.937E+15 8.400E+05 2.941E+06 I-132 INITIAL 0.000E+00 1.100E+09 .
0.000E+00 I-132 TOTALS 0.000E+00 1.314E+13 2.417E+05 4.914E+05 I-133 INITIAL 0.000E+00 4.930E+09 0.000E+00 I-133 TOTALS 0.000E+00 5.324E+14 1.278E+06 4.190E+06 I-134 INITIAL 0.000E+00 6.910E+08 0.000E+00 I-134 TOTALS 0.000E+00 3.146E+12 1.196E+05 1.457E+05 9
I-135 INITIAL 0.000E+00 2.660E+09 0.000E+00 I-135 TOTALS 0.000E+00 9.130E+13 6.566E+05 1.858E+06 i
\
ERS-SFL-95-008 d ITP for LPZ / CR (0.35 uCi/gm) - Attachment 5 Page13 4
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 *** PROGENY INGRONTH ON ***
ITP Case for LPZ / CR dose [TC950855.DAT]
--ENVIRONMENT--- -- -- -------CONTROL ROOM-------
External EDE SKIN-DE THY CDE-INEAL External EDE SKIN-DE TNY CDE-INHAL DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE arem arem/hr arem aren/hr aram arem/hr mram arem/hr aram aram/hr arem arem/hr Xa-131m 1.39E-09 1.54E-08 0.00E+00 3.74E-09 8.25E-07 0.00E+00 TOTALS Xa-133m TOTALS 1.02E-07 6.79E-07 0.00E+00 2.63E-07 3.48E-05 '0.00E+00 Xa-133 1.72E-06 3.25E-06 0.00E+00 4.47E-06 1.68E-04 0.00E+00 TOTALS Xa-135m TOTALS 3.03E-04 9.62E-05 0.00E+00 2.10E-04 1.33E-03 0.00E+00 Xm-135 TOTALS 7.57E-05 1.23E-04 0.00E+00 1.75E-04 5.66E-03 0.00E+00 I-131 TOTALS 3.07E-03 1.62E-03 1.90E+01 1.83E-03 1.92E-02 2.2SE+02 I-132 TOTALS 5.52E-03 1.63E-03 3.26E-02 1.90E-03 1.12E-02 2.24E-01 I-133 TOTALS 7.51E-03 6.97E-03 4.82E+00 4.18E-03 7.72E-02 5.34E+01 I-134 TOTALS 3.15E-03 1.04E-03 2.68E-03 6.52E-04 4.26E-03 1.10E-32 I-135 TOTAL 3 1.05E-02 3.17E-03 4.31E-01 5.04E-03 3.03E-02 4.12E+00 ALL NUCLIDES
.5100 h 1.50E 3.00E-02 7.15E-03 1.43E-02 1.14E+01 2.28E+01 1.24E-03 4.83E-03 1.19E-02 4.65E-02 1.93E+01 7.61E+01 1.0500 h 1.38E-02 2. 7 6E-02 6.76E-03 1.35E-02 1.14E+01 2.27E+01 2.21E-03 4.03E-03 2.15E-02 3.99E-02 3.61E+01 6.85E+01 1.5C00 h 1.28E-04 2.55E-04 6.44E-05 1.29E-04 1.13E-01 2. 2 6E-01 1.83E-03 3.32E-03 1.84E-02 3.38E-02 3.22E+01 6.03E+01 2.0t00 h 1.19E-04 2.38E-04 6.17E-05 1.23E-04 1.12E-01 2.24E-01 1.51E-03 2.76E-03 1.56E-02 2.88E-02 2.83E+01 5.32E+01 4.0100 h 4.14E-04 2.07E-04 2.27E-04 1.13E-04 -4.43E-01 2.21E-01 3.97E-03 1.39E-03 4.32E-02 1.59E-02 8.37E+01 3.23E+01 8.CC00 h 6.48E-04 1.62E-04 3.92E-04 9.79E-05 8.58E-01 2.15E-01 3.18E-03 4.13E-04 3.83E-02 5.33E-03 8.19E+01 1.21E+01 8.5600 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.52E-05 1.20E-06 4.56E-04 1.57E-05 1.03E+00 3.60E-02 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.21E-06 4.23E-08 7.19E-05 6.31E-07 1.86E-01 2.16E-03 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00' O.00E+00 0.00E+00 1.26E-07 5.31E-14 1.87E-06 6.44E-13 7.20E-03 5.67E-09 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E-13 0.00E+00 1.42E-12 0.00E+00 1.28E-08 0.00E+00 TOTALS 3.01E-02 1.47E-02 2.43E+01 1.40E-02 1.49E-01 2.83E+02 ERS-SFL-95-008 A ITP for LPZ / CR (0.35 uCi/gm) . Attachment 5 Page13 5
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 FRP Case for dose 11.75 gpa [TC950867.DAT] *** PROGENY INGROWTH ON ***
COMP: not used COMP: Affected S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
INITIAL: 0.000E+00 Kr-83m 8.880E+06 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 4.340E+07 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 2.290E+08 Kr-85 0.000E+00 Kr-85 L
0.000E+00 Kr-87 2.480E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 6.610E+07 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 2.090E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 2.230E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 6.360E+07 Ke-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 5.420E+08 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 2.250E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 6.650E+07 Ke-135 0.000E+00 Xe-135 0.000E+00 Xe-137 3.380E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 1.390E+07 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 3.170E+09 I-131 0.000E+00 I-131 0.000E+00 I-132 1.100E+09 I-132 0.000E+00 I-132
- 0.000E+00 I-133 4.930E+09 I-133 0.000E+00 I-133 0.000E+00 I-134 6.910E+08 I-134 0.000E+00 I-134 0.000E+00 I-135 2.660E+09 I-135 0.000E+00 I-135 ACT MULT (to uCi): 1.000E+00 1.000E+00 1.000E+00 ERS-SFL-95-008 d FRP for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 13 6
TRAIL 5_PC -- Trantport cf Radioactive Material in Linear systems, v1.0 R P Case for dose 11.75 gpm (TC950867.DAT) * *
- PROGENY INGROWrH ON * *
- _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _------------- -=-_ _-
REMOVAL: 0.000E+00 1/sec 3.891E-06 1/sec 1.000E+01 cfm NUC Grp 1 REL m: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL m: 0.000E+00 O.000E+00 INTAKE REDUCT: 9.360E-01 NUC Crp 3 REL n: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 MULTIPLIERS >
STEP TIME XPR XREN XRF XPR XREN XRF XPR XREN XBF 1 1.800E+03 .000 .000 .000 .000 1.00 .000 50.0 50.0 .000 2 3.600E+03 .000 000 .000 .000 1.00 .000 1.00 70.0 .000 3 5.400E+03 .000 .000 .000 .000 1.00 .000 1.00 70.0 .000 4 7.200E+03 .000 .000 .000 .000 1.00 .000 70.0 70.06 1.00 5 1.440E+04 .000 .000 .000 .000 1.00 .000 70.0 70.0 1.00 6 2.880E+04 .000 .000 .000 .000 1.00 .000 70.0 70.0 1.00 7 3.060E+04 .000 .000 .000 .000 .000 .000 3.350E+03 3.350E+03 .000 8 8.640E+04 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 9 3.456E+05 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 10 2.592E+06 .000 .000 .000 .000 .000 .000 50.0 50.0 .000
CONTROL ROOM -------- ---- ENVIRONMENT ---
X/Q Breathing occupancy X/Q Breathing s/M3 M3/s s/M3 M3/s 1.000E-03 3.470E-04 1.000E+00 1.000E-05 3.470E-04 HULTIPLIERS - =>
STEP TIME,s 1 1.800E+03 2.43 1.00 1.00 6.04 1.00 2 3.600E+03 2.43 1.00 1.00 6.04 1.00 3 5.400E+03 2.43 1.00 1.00 6.04 1.00 4 7.200E+03 2.43 1.00 1.00 6.04 1.00 5 1.440E+04 2.43 1.00 1.00 6.04 1.00 6 2.880E+04 2.43 1.00 1.00 6.04 1.00 7 3.060E+04 1.22 1.00 1.00 4.33 1.00 8 8.640E+04 1.22 1.00 1.00 4.33 1.00 9 3.456E+05 .890 1.00 .600 2.10 1.00 10 2.592E+06 .626 1.00 .400 .744 1.00 ERS-SFL-95-008 d FRP for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 13 7
- . - . . . . ~ . - .
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 FRP Case for dose 11.75 gpa [TC950867.DAT] a *
- PROGENY INGROWTH ON * *
- not used Affected S/G AVERAGE - - - - - - -
-CONTROL ROOM-----------
CURRENT INTEGRD CURRENT INTEGRD RELEASED RepuE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 8.880E+06 0.000E+00 Kr-G3m' TOTALS 0.000E+00 8.152E+10 3.030E+05 8.442E+05 Kr-S5m INITIAL O.000E+00 4.340E+07 0.000E+00 Kr-85m TOTALS 0.000E+00 9.477E+11 2.669E+06 1.105E+07 Kr-85 1NITIAL 0.000E+00 2.290E+08 0.000E+00 Kr-E5 T7FALS 0.000E+00 5.296E+14 2.428E+07 1.315E+08 Kr-87 INITIAL 0.000E+00 2.480E+07 0.000E+00 ,
Kr-87 TOTALS 0.000E+00 1.597E+11 6.142E+05 1.299E+06 t
Kr-88 INITIAL 0.000E+00 6.610E+07 0.000E+00 v Kr-83 TOTALS 0.000E+00 9.288E+11 3.132E+06 3.107E+07 ,
Kr-89 INITIAL 0.000E+00 2.090E+06 0.000E+00 Kr-SS TOTALS 0.000E+00 5.711E+08 2.222E+03 3.433E+02 ,
Xe-131m INITIAL 0.000E+00 2.230E+06 0.000E+00 Xe-131m TOTALS 0.000E+00 2.167E+13 2.687E+05 1.461E+06 i Xe-133m INITIAL 0.000E+00 6.360E+07 0.000E+00 Xe-133m TOTALS 0.000E+00 2.933E+13 7.09CE+06 3.784E+07 Xa-133 INITIAL O.000E+00 5.420E+08 0.000E+00 l Xe-133 TOTALS 0.000E+00 7.918E+14 6.630E+07 3.596E+08 Xa-135m INITIAL O.000E+00 2.250E+07 0.000E+00 Xa-135m TOTALS 0.000E+00 1.397E+13 3.078E+07 4.674E+07 f Xe-135 INITIAL 0.000E+00 6.650E+07 0.000E+00 ,
X3-135 TOTALS 0.000E+00 8.512E+13 5.779E+07- 3.062E+08 Xe-137 INITIAL 0.000E+00 3.380E+06 0.000E+00
> Xa-137 TOTALS 0.000E+00 1.119E+09 4.354E+03 8.104E+02
, Xe-138 INITIAL 0.000E+00 1.390E+07 0.000E+00 X3-138 TOTALS 0.000E+00 1.692E+10' 6.584E+04 3.419E+04 ,
I-131 INITIAL 0.000E+00 3.170E+09 0.000E+00 I-131 TOTALS 0.000E+00 2.631E+15 3.314E+08 2.706E+08 ERS-SFL-95-008 d I FRP for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Page .13 8
.__m . _ . . _ - - m, .. _ . . . . . . . . . . . . . _ _
. ._ . _ . . . . , _ . . . __ ._,1 i
TRAILS PC -- Transport of Radioactive Material in Linear Systemas, v1.0 IRP Case for dose 11.75 gpa [TC950867.DAT] ***PROJ1i3tY INGROWTH ON ***
not used Affected $',G AVERAGE -CONTROL ROON - -=
CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD ,
ETE'P TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec '
I-132 INITIAL 0.000E+00 1.100E+09 0.000E+00 I-132 TOTALS 0.000E+00 1.260E+13 4.494E+07 3.531E+07 I-133 INITIAL 0.000E+00 4.930E+09 0.000E+00 I-133 TOTALS 0.000E+00 4.829E+14 4.599E+0B 3.735E+08 I-134 INITIAL 0.000E+00 6.910E+08 0.000E+00 I-134 TOTALS 0.000E+00 3.092E+12 1.201E+07 8.872E+06 I-135 INITIAL 0.000E+00 2.660E+09 0.000E+00 I-135 TOTALS 0.000E+00 8.471E+13 1.923E+08 1.545E+08 i
i L
i I
I i
i 1
ERS-SFL-95-008 /A FRP for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment S Page 13 9
i TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ERP Case for dose 11.75 gpm [TC950867.DAT] *** PROGENY INGROWTH ON ***
- - --------ENVIRONMENT--------- -------CONTROL ROOM-------
External EDE SKIN-DE TNY 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 aree/hr aram aren/hr arem arem/hr arem aren/hr aram arem/hr arem aren/hr '
Kr-83m TOTALS 2.72E-07 0.00Et00 0.00E+00 1.29E-07 0.OOE+00 0.00E+00 Kr-85m TOTALS 4.17E-03 8.24E-03 0.00E+00 2.94E-03 1.15E-01 0.00E+CO Kr-SS TOTALS 5.21E-04 7.29E-02 0.00E+00 4.80E-04 1.33E+00 0.00E+00 Kr-87 TOTALS 5.26E-03 1.25E-02 0.00E+00 1.89E-03 8.91E-02 0.00E+00 Kr-88 TOTALS 6.78E-02 1.49E-02 0.00E+00 4.07E-02 1.78E-01 0.00E+00 Kr-89 TOTALS 4.32E-05 4.70E-05 0.00E+00 1.13E-06 2.45E-05 0.00E+00 Xe-131m TOTALS 2.20E-05 2.44E-04 0.00E+00 2.04E-05 4.49E-03 0.00E+00 Xe-133m TOTALS 2.02E-03 1.35E-02 0.00E+00 1.83E-03 2.42E-01 0.00E+00 Ye-133 ~
TOTALS 2.24E-02 4.23E-02 0.00E+00 2.06E-02 7.75E-01 0.00E+00 r
Xa-135m TOTALS 1.27E-01 4.02E-02 0.00E+00 3.26E-02 2.06E-01 0.00E+00 ,
I Xe-135 I TOTALS 1.39E-01 2.26E-01 0.00E+00 1.25E-01 4.04E+00 0.00E+00 Xe-137 TOTALS 7.96E-06 1.21E-04 0.00E+00 2.52E-07 7.58E-05 0.00E+00 Xa-138 TOTALS 7.90E-04 5.88E-04 0.00E+00 6.97E-05 1.03E-03 0.00E+00 I-131 TOTALS 1.21E+00 6.39E-01 7.50E+03 1.68E-01 1.76E+00 2.07E+04 t
ERS-SFL-95-008 d FRP for LPZ / CR 11.75 gpm (0.35 uCi/gm) Attachment 5 Pagel 4 0
- - . . _ . - _ _ _ _ _ _ . _ _ _ . _ ._m _ ______.m _. _
TRAILS _PC -- Transport of Radioactive Material in Linear Systemas, v1.0 IRP Case for dose 11.75 gpa [TC950867.DAT) - *** PROGENY INGROWTH ON ***
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 aren aren/hr arena nresa/hr aram area /hr mram arem/hr aram area /hr arem mree/hr I-132 TOTALS 1.03E+00 3.03E-01 6.07E+00 1.37E-01 8.05E-01 1.61E+01 I-133 TOTALS 2.70E+00 2.51E+00 1.73E+03 3.73E-01 6.88E+00 4.76E+03 I-134 TOTALS 3.16E-01 1.04E-01 2.69E-01 3.97E-02 2.60E-01 6.72E-01 l
I-135 TOTALS 3.07E+00 9.29E-01 1.26E+02 4.19E-01 2.52E+00 3.43E+02*
t ALL NUCLIDES
.5000 h 8.59E-01 1.72E+00 4.18E-01 8.37E-01 6.42E+02 1.28E+03 7.11E-02 2.76E-01 6.95E-01 2.72E+00 1.09E+03 4.28E+03 1.0000 h 7.82E-01 1.56E+00 3.92E-01 7.84E-01 6.34E+02 1.27E+03 1.26E-01 2.30E-01 1.26E+00 2.33E+00 2.03E+03 3.85E+03 ,
1.5000 h 7.18E-01 1.44E+00 3.71E-01 7.41E-01 6.26E+02 1.25E+03 1.06E-01 1.94E-01 1.08E+00 2.02E+00 1.83E+03 3.47E+03 .
2.0000 h 6.65E-01 1.33E+00 3.53E-01 7.05E-01 6.18E+02 1.24E+03 9.56E-02 1.88E-01 1.03E+00 2.11E+00 1.72E+03 3.42E+03 4.6000 h 2.27E+00 1.14E+00 1.27E+00 6.37E-01 2.40E+03 1.20E+03 3.51E-01 1.67E-01 4.54E+00 2.40E+00 6.64E+03 3.23E+03 8.C000 h 3.40E+00 8.50E-01 2.11E+00 5.27E-01 4.45E+03 1.11E+03 5.99E-01 1.40E-01 1.04E+01 2.72E+00 1.22E+04 2.93E+03 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.20E-02 4.03E-04 2.33E-01 7.96E-03 2.51E+02 8.74E+00 24.C000 h 0.00E+00 0.00E+00 0.00E+0C O.00E+00 0.00E+00 0.00E+00 1.69E-03 1.29E-05 3.57E-02 3.06E-04 4.51E+01 5.24E-01 SS.C000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.77E-05 1.53E-11 9.22E-04 4.78E-10 1.75E+00 1.37R-06 720.C000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.40E-11 0.00E+00 1.08E-09 0.00E+00 3.10E-06 0.00E+00 TOTALS 8.70E+00 4.92E+00 9.37E+03 1.36E+00 1.92E+01 2.58E+04 l
ERS-SFL-95-008 d ,
FRP for LPZ / CR 11.75 gpm (0.35 u.Ci/gm) Attachment 5 Pagel 41
TRAILS PC -- Transport of' Radioactive Material in Linear Systems, v1.0 ASA Case for EAB dose 0.35 uci/gm [TC950841.DAT] *** PROGENY INGROWTH ON ***
COMP: not used COMP: all S/Gs COMP: Contral Room VOLUME: 1.730E+f 'i cu.Ft.
INITIAL: 0.000E+00 Kr-83m 1.330E+00 Kr-83m uC1 0.000E+00 Kr-83m 0.000E+00 Kr-85m 6.490E+00 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 3.430E+01 Kr-85 0.000E+00 Kr-85 0.000E+00 Kr-87 3.700E+00 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 9.890E+00 Kr-88 0.000E+00 Kr-88 i 0.000E+00 Kr-89 3.120E-01 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 3.340E-01 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 9.520E+00 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 8.110E+01 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 3.370E+00 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Ze-135 9.950E+00 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 5.050E-01 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 2.080E+00 Xe-238 0.000E+00 Xe-138 0.000E+00 I-131 2.380E+03 I-131 0.000E+00 I-131 0.000E+00 I-132 4.220E+02 I-132 0.000E+00 I-132 0.000E+00 I-133 3.110E+03 1-133 0.000E+00 I-133 0.000E+00 I-134 7.430E+el I-134 0.000E+00 I-134 0.000E+00 I-135 1.140G+03 I-135 0.000E+00 I-135 ACT MULT (to uC1) : 1.000E+00 3.00f>E+00 1.000E+00 L
ERS-SFL-95-008 d ASA for EAB (0.35 uCi/gm) Attachment S Page14 2
_.,.mb L m.sL a s TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ASA Case for EAB dose 0.35 uci/gm [TC950841.DAT] *** PROGENY INGROWTH ON ***
REMOVAL: 0.000E+00 1/sec 1.382E+01 1/sec 1.000E+01 cfm NUC Grp 1 REL m: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL m: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL n: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 MULTIPLIERS >
XPR XREM XRF XPR XREN XRF XPR XREN XRF [
STEP TIME 1 6.000E+01 .000 .000 .000 .000 1.00 .000 50.0 50.0 .000 2 1.800E+03 .000 .000 .000 .000 .000 .000 50.0 50.0 .000 3 5.400E+03 .000 .000 .000 .000 .000 .000 1.00 70.0 000 4 7.200E+03 .000 .000 .000 .000 .000 .000 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,a 1 6.000E+01 .000 1.00 1.00 1.04 1.00 2 1.800E+03 .000 1.00 1.00 1.04 1.00 i 3 5.400E+03 .000 1.00 1.00 1.04 1.00 4 7.200E+03 .000 1.00 1.00 1.04 1.00 h
.l F
i ERS-SFL-95-008 A ASA for EAB (0.35 uCi/gm) Attachment 5 Pagel 4 3 !
TRAILS _PC -- Transport of Radioactive Katerial in Linear Systems, v1.0 *** PROGENY INGROWTH ON ***
ASA Case for EAB dose 0.35 uci/gm tTC950841.DAT]
not used all S/Gs AVERAGE ----------CONTROL ROON-----------
CURRENT INTEGRD CURRENT INTEGRD BRTRASED RELEASE CURRENT CURRENT INTEGRD !
ETEP TIME uCi uCi-sec uC1 uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 3.990E+00 0.000E+00 TOTALS 0.000E+00 2.887E-01 3.990E+00 0.000E+00 Kr-83m Kr-85m INITIAL 0.000E+00 1.947E+01 0.000E+00 Kr-85m MTALS 0.000E+00 1.409E+00 1.947E+01 0.000E+00 Kr-85 INITIAL 0.000E+00 1.029E+02 0.000E+00 Kr-85 TOTALS 0.000E+00 7.446E+00 1.029E+02 0.000E+00 Kr-87 INITIAL 0.000E+00 1.110E+01 0.000E+00 0.000E+00 i Kr-87 TOTALS 0.000E+00 8.032E-01 1.110E+01 t
Kr-88 INITIAL 0.000E+00 2.967E+01 0.000E+00 Kr-38 TOTALS 0.000E+00 2.147E+00 2.967E+01 0.000E+00 Kr-89 INITIAL 0.000E+00 9.360E-01 0.000E+00 Kr-89 TOTALS 0.OOOE+00 6.771E-02 9.358E-01 0.000E+00 Xe-131m INITIAL 0.000E+00 1.002E+00 0.000E+00 Xe-131m TOTALS 0.000E+00 7.250E-02 1.002E+00 0.000E+00 ;
Xe-133m INITIAL 0.000E+00 2.856E+01 0.000E+00 Xe-133m TOTALS 0.000E+00 2.067E+00 2.856E+01 0.000E+00 Xe-133 INITIAL 0.000E+00 2.433E+02 0.000E+00 ;
Xe-133 TOTALS 0.000E+00 1.760E+01 2.433E+02 0.000E+00 I
Xs-135m INITIAL 0.000E+00 1.011E+01 0.000E+00 Xa-135m TOTALS 0.000E+00 7.337E-01 1.014E+01 0.000E+00 Xa-135 INITIAL 0.000E+00 2.985E+01 0.000E+00 Xa-135 TOTALS 0.000E+00 2.160E+00 2.985E+01 0.000E+00 Xe-137 INITIAL 0.000E+00 1.515E+00 0.000E+00 ,
Xe-137 TOTALS 0.000E+00 1.096E-01 1.515E+00 0.000E+00 .
Xe-138 INITIAL 0.000E+00 6.240E+00 0.000E+00 Xe-138 TOTALS 0.000E+00 4.515E-01 6.240E+00 0. 00 0m.M0 I-131 INITIAL 0.000E+00 7.140E+03 0.000E+00 I-131 TOTALS 0.000E+00 5.166E+02 7.140E+03 0.0005600 ;
i ERS-SFL-95-008 d ASA for EAB (0.35 uCi/gm). Attachment 5 PageI d d '
TRAILS PC -- Transport of Radioactive Material in Linear systeens, v1.0 ASA Case for EAB dose 0.35 uci/gua (TC950841.DAT) *** PROGENY'INGROWFH ON ***
not used all s/Gs AVERAGE ~- -CONTROL ROOM--=
CURRENT INTEGRD CURRENT INTEGRD RELEASED RET.EESE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec. uCi uCi-sec uCi uC1/sec- uCi uCi/cc uCi-sec INITIAL 0.000E+00 1.266E+03 0.000E+00 I-132 0.000E+00 I-132 Totat.m 0.000E+00 9.161E+01 1.266E+03 ;
l INITIAL 0.000E+00 9.330E+03 0.000E+00 I-133 0.000E+00 l I-133 TOTar.m 0.000E+0C 6.751E+02 9.330E+03
.)
0.000E+00 2.229E+02 0.000E+00' I-134 INITIAL 0.000E+00 1.613E+01 2.229E+02 0.000E+00 I-134 TOTALS I-135 INITIAL 0.000E+00 3.420E+03 0.000E+00 3.420E+03 0.000E+00 i I-135 Totar.m 0.000E+00 2.475E+02 f
t l
l i
I t
I f
r i
i ERS-SFL-95-008 A ASA for EAB (0.35 uCi/gm) Attachment 5 Pagel 4 5 i
i
. - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - ___ m_
. ...m. . . , _ . . -. ...- _ _ _ . . _ . . _ . . - . . . _ _ . . . . . . _ . - _ . . _ . . _ _ . . . _ . . . _ . _ . - _ . _ _ _ _ . . . - _ . . _ - .
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ,
ASA Case for EAR dose 0.35 uci/gm [TC950841.DAT] *** PROGENY INGROWTH ON ***
ENVIRONNENT- -- ------ ------ -C0NTROL ROOM-------
External EDE SKIN-DE THY CDS-INHAL External EDE SKIN-DE THY CDE-IN8tAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr arem aren/hr arem arem/hr mram arem/hr aram aremn/hr aram arem/hr Kr-33m TOTALS 6.17E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-35m TOTALS 5.24E-07 1.04E-06 0.00E+00 0.ME+00 0.00E+00 0.00E+00 Kr-85 TOTALS 3.81E-08 5.32E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-97 TOTALS 1.64E-06 3. 8 tsE-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-E8 TOTALS 1.11E-05 2.43E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-09 i TOTALS 3.14E-07 3.41E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Xa-131m i
TOTALS 1.42E-09 1.57E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
Xe-133m TON.* 1.40E-07 9.32E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 TOTALS 1.41E-06 2.67E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .
Xa-135m TOTALS 7.18E-07 2.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 t TOTALS 1.23E-06 2.01E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xs-137 TOTALS 4.77E-08 7.22E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Xa-138 TOTALS 1.29E-06 9.59E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 TOTALS 4.50E-04 2.37E-04 2.7BE+00 0.00E+DO 0.00E+00 0.00E+00 i
i ERS-SFL-95-008 [1\
ASA for EAB (0.35 uCi/gm)- Attachment 5 Page 1 f G
_ _ _ _ _ _ . _ _ _ . _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ ,___ _ . _ _ _ _t , __.__m.______
____ _ __.+ _ . - _ _ _ _ _ _ _ _ _ _ , - - - _ . _ _ _ - _ _ , ____ _ _ _ _ _ - . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
.. . _ . - -. - -- -. - . .- -- . _ - . ~ ~ -. ._~. . . . - = . - . . . . . - .~-1 . ._
b TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ASA Case for EAB dose 0.35 uci/gm [TC950841.DAT] *** PROGENY INGROWTH ON *** ,
-- -------ENVIRONNENT- -------- --
CONTROL ROON-------
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 aram/hr arem mren/hr arem aren/hr arem aren/br mrem mren/hr arem mram/hr I-132 TOTALS 4.97E-04 1.47E-04 2.94E-03 0.00E+00 0.00E+00 0.00E+00 I-133
- TOTALS 9.43E-04 8.76E-04 6.06E-01 0.00E+00 0.00E+00 0.00E+00 I-134 TOTALS 1.01E-04 3.32E-05 8.61E-05 0.00E+00 0.00E+00 0.00E+00 I-135 TOTALS 9.41E-04 2.85E-04 3.86E-02 0.00E+00 0.00E+00 0.00E+00 ,
ALL NUCLIDES
.0167 h 2.95E-03 1.77E-01 1.60E-03 9.59E-02 3.43E+00 2.06E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
.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.C000 h 0.00E+00 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 0.00E+00 0.00E+00 TOTALS 2.95E-03 1.60E-03 3.43E+00 0.00E+00 0.00E+00 0.00E+00 k
E I
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ERS-SFL-95-008 A ASA for EAB (0.35 uCi/gm) Attachment S Page 14 7 1
_ .._m .-.. _ . - _._..,_4 _.m _. __
.._.,_m _ .
L
' TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITC Case for EAR dose 0.35 uci/gm [TC950844.DAT] *** PROGENY INGRONTH ON.***
COMP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
- - - - - - - - - - - - _ -__ = - - - - - - - - - - - - - ..__- ------ .------------_ .- _ ---.-----------
INITIAL: 0.000E+00 I-131 5.200E+07 I-131 uCi 0.000E+00 I-131 0.000E+00 I-132 1.810E+07 I-132 0.000E+00 I-132 l 0.000E+00.I-133 8.100E+07 I-133 0.000E+00 I-133 ,
0.000E+00 I-134 1.130E+07 I-134 0.000E+00 I-134 i I
0.000E+00 I-135 4.360E+07 I-135 0.000E+00 I-135 ACT MULT (to uCi) : 1.000E+00 1.000E+00 1.000E+00 PRODUCTION,uci/s: 0.0(;,E+00 I-131 4.900E+05 I-131 INTAKE: 1.000E+01 CEM 0.000E+0u I-132 9.200E+05 I-132 0.000E+00 I-133 1.100E+06 I-133 0.000E+00 I-134 1.340E+06 I-134 0.000E+00 I-135 1.020E+06 I-135 i
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ERS-SFL-95-008 A ITC for EAB (0.35 uCi/gm) Attachment 5 Page j d 8 t
. m. . .. ..
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ,
ITC Case for EAB dose 0.35 uci/gm (TC950844.DAT) * *
- PROGENY INGRolfTH ON * *
- REPAVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfm NUC Grp 1 'AL FR: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp E REL nt: 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 HULTIPLIERS====>
XPR XREN XRF XPR XREM XRF XPR XREN XRF ETEP TIME
.000 1.00 1.00 .000 50.0 50.0 .000 1 1.800E+03 .000 .000
.000 .000 .000 1.00 1.00 .000 1.00 70.0 .000 ;
2 3.600E+03 3 5.400E+03 .000 .000 .000 1.00 1.000E-02 .000 1.00 70.0 .000 ,
4 7.200E+03 .000 .000 .000 1.00 1.000E-02 .000 10.0 70.0 1.00
CONTROL ROOH -------- ---- ENVIRONMENT ---
X/Q Breathing occupancy X/Q Breathing s/M3 M3/s s/M3 H3/s 0.000E+00 3.470E-04 1.000E+00 1.000E-03 3.470E-04 HULTIPLIERS= - >
STEP TIME,a 1 1.800E+03 .000 1.00 1.00 1.04 1.00 2 3.600E+03 .000 1.00 1.00 1.04 1.00 3 5.400E+03 .000 1.00 1.00 1.04 1.00 4 7.200E+03 .000 1.00 1.00 1.04 1.00 I
ERS-SFL-95-008 A ITC for EAB (0.35 uCi/gm) Attachment S Pagel d 9
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITC Case for EAB dose 0.35 uci/gm (TC950844.DAT] *** PROGENY INGROWTH ON ***
not used intact 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 0.000E+00 0.000E+00 0.000E+00 Xo-131m INITIAL 0.000E+00 XQ-131m TOTALS 0.000E+00 2.343E+08 2.250E+00 Xe-133m INITIAL 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.268E+09 6.965E+01 0.000E+00 Xe-133m TOTALS Xo-133 INITIAL 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.028E+11 9.829E+02 0.000E+00 XQ-133 TOTALS Xo-135m INITIAL 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.907E+12 4.045E+04 0.000E+00 Xe-135m TOTALS Xe-135 INITIAL 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.169E+12 1.108E+04 0.000E+00 Xo-135 TOTALS I-131 INITIAL 0.000E+00 5.200E+07 0.000E+00 I-131 TOTALS 0.000E+00 1.304E+13 2.383E+05 0.000E+00 I-132 INITIAL 0.000E+00 1.810E+07 0.000E+00 I-132 TOTALS 0.000E+00 1.979E+13 3.866E+05 0.000E+00 I-133 INITIAL 0.000E+00 8.100E+07 0.000E+00 I-133 TOTALS 0.000E+00 2.845E+13 5.206E+05 0.000E+00 I-134 INITIAL 0.000E+00 1.130E+07 0.000Et00 I-134 TOTALS 0.000E+00 2.190E+13 4.803E+05 0.000E+00 I-135 INITIAL 0.000E+00 4.360E+07 0.000E+00' I-135 TOTALS -
0.000E+00 2.49FE+13 4.634E+05 0.000E+00 ERS-SFL-95-008 A ITC for EAB (0.35 uCi/gm) Attachment 5 Page15 0
. . _ ~ . . _ . . . -- - . _ . _ _ _ _ - . _ . _ . . . - ~ . . . . __ -.s. m . __ . . . . m. . . , _ _ _ _ _ . . . _ _ _ _ . . .
- i TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITC Case for EAB dose 0.35 uci/ gum [TC950844.DAT] *** PROGENY INGROWTH ON ***
--- ------ENVIRONNENT--------- ----.--CONTROL ROOM-------
4 External EDE SKIN-DE THY CDE-INHAL External EDE SKIM-DE TNY CDE-INHAL ,
DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr uren urem/hr aren . area /hr arem areun/hr arem aram/hr arem aren/hr Xo-131m TOTALS 3.18E-09 3.52E-08 0.00E+00 0.00E+00 0.00E+00. 0.00E+00 Ka-133m TOTALS 3.42E-07 2.27E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 >
XO-133 TOTALS 5.71E-06 1.08E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l I
Xe-135m TOTALS 2.86E-03 9.10E-04 0.00E+00 0.00E+00' O.00E+00 0.00E+00 Xe-135 j TOTALS 4.58E-04 7.46E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 TOTALS 1.50E-02 7.92E-03 9.29E+01 0.00E+00 0.00E+00 0.00E+00 I-132 TOTALS 1.52E-01 4.49E-02 8.99E-01 0.00E+00 0.00E+00 0.00E+00 ,
i 1
I-133 !
TOTALS 5.26E-02 4.89E-02 3.38E+01 0.00E+00 0.00E+00 0.00E+00 I-134 [
TOTALS 2.18E-01 7.16E-02 1.85E-01 0.00E+00 0.00E+00 0.00E+00 t I-135 {
TOTALS 1.27E-01 3.86E-02 5.23E+00 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES l
.5000 h 1.50E-01 2.99E-01 5.59E-02 1.12E-01 3.40E+01 6.81E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
1.0000 h 4.05E-01 8.09E-01 1.52E-01 3.04E-01 9.53E+01 1.91E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t 1.5000 h 6.17E-03 1.23E-02 2.35E-03 4.70E-03 1.56E+00 3.12E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '
2.0000 h 7.97E-03 1.59E-02 3.08E-03 6.16E-03 2.16E+00 4.32E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ;
TOTALS 5.68E-01 2.14E-01 1.33E+02 0.00E+00 0.00E+00 0.00E+00 I F
t i
ERS-SFL-95-008 /A ITC for EAB (0.35 uCi/gm) Attachment 5 Pagej 3 }
_ . .~. __ . - . . . _ m._ _ - , _____ -. . .._..
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITN Case for EAB dose [TC950846.DAT] *** PROGENY INGROWTH ON ***
i COMP: not used COMP: intact S/G COMP: Cot. trol Room VOLUME: 1.730E+05 Cu.Ft. t INITIAL: 0.000E+00 Kr-83m 8.880E+06 Kr-83m uCi 0.000E+00 Kr-83m 0.000E+00 Kr-85m 4.340E+07 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 2.290E+08 Kr-85 0.000E+00 Kr-85 O.000E+00 Kr-87 2.480E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 6.610E+07 Fr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 2.090E+06 Kr-89 C.000E+00 Kr-89 0.000E+00 Xe-131m 2.230E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Ke-133m 6.360E+07 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 5.420E+08 Xe-133 0.000E+00 Xe-133 i
0.000E+00 Xe-135m 2.250E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 6.650E+07 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 3.380E+06 Ke-137 0.000E+00 Xe-137 0.000E+00 Xe-138 1.390E+07 Xe-138 0.000E+00 Ze-138 ACT MULT (to uC1) : 1.000E+00 1.000E+00 1.000E+00 L
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ERS-SFL-95-008 A ITN for EAB (0.35 uCi/gm)- Attachment 5 Page15 2
- - _ _ _ . _ _ . _ _ _ _ _ ___________ _ __ _ ______ _ __ ___ _ _ _____________________ _ ______ _-. _____________________J
1 TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 *** PROGENY INGROWTH ON ***
ITN Case for EAB dose [TC950846.DAT]
-_--_------_------- - - - = - - - -.._=----------- --------------------------- -----_-------- _ - - -
REMOVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfm 0.000E+00 0.000E+00 INTAME REDUCT: 0.000E+00 NUC Crp 1 REL M:
NUC Grp 2 REL n: 0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 3 REL FR: -------- - ==_ ==----------------- ------------- -----
.---------------= _-
f MULTIPLIERS ====> XRF XPR XREN XRF XPR XREM XRF XPR XREN j ETEP TIME 50.0 .000 1 1.800E+03 .000 .000 .000 .000 1.00 .000 50.0
.000 .000 .000 1.00 .000 1.00 70.0 .000 2 3.600E+03 .000
.000 .000 .000 1.00 .000 1.00 70.0 .000 :
3 5.400E+03 .000 '
.000 .000 .000 .000 1.00 .000 70.0 70.0 1.00 4 7.200E+03 CONTROL ROOM ---- ENVIROttdENT ---
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 y
MULTIPLIER $= - >
ETEP TIME,a 1 1.800E+03 .000 1.00 1.00 1.04 1.00 2 3.600E+03 .000 1.00 1.00 1.04 1.00 3 5.400E+03 .000 1.00 1.00 1.04 1.00 4 7.200E+03 .000 1.00 1.00 1.04 1.00 ERS-SFL-95-008 A ITN for EAB (0.35 uCi/gm) Attachment S Page 15 'l
-. _ . _ - = - _ . .. .__ _ _ - - -.. - - _ -- - - -_ - . - - = __ - _ _ ___ _. . _ . _
- - - _ _ . _ . ,m _._
h TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITN Case for EAR dose [TC950846.DAT] *** PROGENY INGRONTH ON ***
not used intact S/G AVERAGE ----------CONTROL ROON-----------
CURRENT INTEGRD CURRENT INTEGRD RELEASED RETsm*E CURRENT CURRENT INTT.GRD STEP TIME uCi uCi-sec uCi uCi-sec uC1 uCi/sec uCi uCi/cc uCi-sec !
Kr-83m INITIAL 0.000E+00- R.880E+06 0.000E+00 Kr-83m TOTALS 0.000E+00 4.482E+10 3.092E+03 0.000E+00 l
Kr-85m INITIAL 0.000E+00 4.340E+07 0.000E+00 Kr-85m TOTALS 0.000E+00 2.687E+11 1.854E+04 0.000E+00 'l i
Kr-85 INITIAL 0.000E+00 2.290E+08 0.000E+00 Kr-85 TOTALS 0.000E+00 1.648E+12 1.137E+05 0.000E+00 I
i Kr-87 INITIAL 0.000E+00 2.480E+07 0.000E+00 t Kr-87 TOTara 0.000E+00 1.087E+11 7.500E+03 0.000E+00 Kr-88 INITIAL O.000E+00 6.610E+07 0.000E+00 '
Kr-88 TOTALS 0.000E+00 3.765E+11 2.597E+04 0.000E+00 Kr-89 M TIAL 0.000E+00 2.090E+06 0.000E+00 Kr-89 TOTALS 0.000E+00 5.~717E+08 3.944E+01 0.000E+00 i
Xa-131m INITIAL 0.000E+00 2.230E+06 0.000E+00 Xe-131m TOTRY m 0.000E+00 1.601E+10 1.105E+03 0.000E+00 .
Xe-133m INITIAL 0.000E+00 6.360E+07 0.000E+00 Xe-133m TOTarm 0.000E+00 4.518E+11 3.117E+04 0.000E+00 Xe-133 INITIAL 0.000E+00 5.420E+08 0.000E+00 Xe-133 TOTALS 0.000E+00 3.883E+12 2.679E+05 0.000E+00 Xe-135m INITIAL 0.000E+00 2.250E+07 0.000E+00 Xa-135m Toemr.m 0.000E+00 2.978E+10 2.054E+03 0.000E+00 Xe-135 INITIAL 0.000E+00 6.650E+07 0.000E+00 Xe-135 TOTALS 0.000E+00 4.475E+11 3.087E+04 0.000E+00 Xe-137 INITIAL 0.000E+00 3.380E+06 0.000E+00 Xa-137 TOTALS 0.000E+00 1.121E+09 7.731E+01 0.000E+00 Xe-138 INITIAL 0.000E+00 1.390E+07 0.000E+00 Xe-138 TOTALS 0.000E+00 1.695E+10 1.170E+03 0.000E+00 ERS-SFL-95-008 A ITN for EAB (0.35 uCi/gm) Attachment 5 Page 15 el
- -- .. - ~ ._s.. -- - - - - - ..- - - - - - - - ..-- -n - ..-. w. .u ..- - - -s. -- w. - - s ~
i
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TRAILS PC -- Tra7 sport of Radioactive Material in Linear Systems, v1.0 ITN Case for EAR dose [TC950846.DAT] *** PROGENY INGROWTH ON *** ,
T
.-- -----ENVIRONMENT---- ----- -- -- ---CONTROL ROOM-------
I External EDE SKIN-DE- THY CDE-INHAL External EDE SKIM-DE THY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem mres/hr aram arem/hr arem area /hr arem arem/hr arem ares /hr aren .aren/hr ;
Kr-83m r TOTALS 4.78E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t Kr-85m TOTALS 4.99E-04 9.85E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ;
i Kr-85 TOTALS 4.21E-05 5.88E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J i Kr-07 TOtar.t 1.11E-03 2.62E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 >
i Kr-C8 t TOTALS 9.68E-03 2.13E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,.
t Kr-89 [
TOTALS 1.32E-05 1.44E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 [
t Xe-131m !
TOTALS 1.56E-06 1.73E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .
I Xe-133m s TOTaf.* 1.53E-04 1.02E-03 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 i
s Xe-133 TotaY M 1.56E-03 2.94E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135m TOTALS 1.45E-04 4.62E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Xe-135 TOTALS 1.28E-03 2.08E-03 0.00E+00 'O.00E+00 0.00E+00 0.00E+00 !
4 Xe-137 TOTALS 2.43E-06 3.69E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
Xe-138 i TOTALS 2.42E-04 1.80E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l l
i ERS-SFL-95-008 A ITN for EAB (0.35 uCi/gm) Attachment 5 Page15 5 . .
t
TRAILS _PC -- Transport of Radioactive Material in Linear Systemas, v1.0 ITN Case for EAB dose [TC950846.DAT] ***PROGENT INGROWTH ON ***
ENVIRONMENT -------- -------CONTROL ROOM-------
External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE THE CDE-INEAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE mrem mress/hr aresa nresa/hr aren mress/hr arem area /hr mresa arem/hr mresa aren/hr ALL NUCLIDES
.5000 h 4.50E-03 9.01E-03 5.09E-03 1.02E-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 3.81E-03 7.63E-03 4.57E-03 9.14E-03 0.00E+00 0.00E+00 0.00E+00 0.0GE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 3.37E-03 6.75E-03 4.26E-03 8.52E-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 2.0000 h 3.02E-03 6.05E-03 4.03E-03 8.05E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 TOTALS 1.47E-02 1.80E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-95-008 A ITN for EAB (0.35 uCi/gm) - Attachment S Page15 6
- _ . - _ _ . = - _ - _
, . - ~ . . . . . - ,
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 FRC Case for EAB dose for 11.75 gpa [TC950839.DAT] *** PROGENY INGRONTH ON ***
COMP: not used COMP: Affected S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft. !
_________--=--- -_____________ ___________
INITIAL: 0.000E+00 Kr-83m 8.800E+06 Kr-83m uCi 0.000E+00 Kr-83m ,
0.000E+00 Kr-85m 4.340E+07 Kr-85m 0.000E+00 Kr-85m 0.000E+00 Kr-85 2.290E+08 Kr-85 0.000E+00 Kr-85 .
0.000E+00 Kr-87 2.480E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 6.610E+07 Kr-88 0.000E+00 Kr-88 ,
0.000E+00 Kr-89 2.090E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 2.230E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Xe-133m 6.360E+07 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 5.420E+08 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 2.250E+07 Xe-135m 0.000E+00 Xe-135m j 0.000E+00 Xe-135 6.650E+07 Xe-135- 0.000E+00 Xe-135 O.000E+00 Xe-137 3.380E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Ze-138 1.390E+07 re-138 0.000E+00 Xe-138 5.200E+07 I-131 0.000E+00 I-131 i 0.000E+00 I-131 0.000E+00 I-132 1.810E+07 I-132 0.000E+00 I-132 0.000E+00 I-133 8.100E+07 I-133 0.000E+00 I-133 0.000E+00 I-134 1.130E+07 I-134 0.000E+00 I-134 ;
0.000E+00 I-135 4.360E+07 I-135 0.000E+00 I-135 ACT MULT (to uC1) : 1.000E+00 1.000E+00 1.000E+00 t
=_____ - ___________ - - - - ___________
l PRODUCTION,uci/s: 0.000E+00 I-131 4.900E+05 I-131' INTAKE: 1.000E+01 CEM l 0.000E+00 I-132 9.200E+05 I-132 l 0.000E+00 I-133 1.100E+06 I-133 O.000E+00 I-134 1.340E+06 I-134 0.000E+00 I-135 1.020E+06 I-135 t
f l
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ERS-SFL-95-008 A FRC for EAB 11.75 gpm (0.35 uCi/gm) Attachment S Page15 7 i
TRAILS PC -- Transport of Radioactivo Material in. Linear Systems, v1.0 ETtc Case for EAB dose for 11.75 gpm [TC950839.DAT] *** PROGENY INGROWTH ON ***
REMOVAL: 0.000E+00 1/sec 3.891E-06 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.C00E+00
_-_---__ ___---_-_ -----------_--__-____--- -=- ___---------__._
MULTIPLIERS - > ,
2TEP TIME XPR. XREN XRF XPR XREN XRF XPR XREN XRF ;
1 1.800E+03 .000 .000 .000 1.00 1.00 .000 50.0 50.0 .000 ;
2 3.600E+03 .000 .000 .000 1.00 1.00 .000 1.00 70.0 .000 3 5.400E+03 .000 .000 .000 1.00 1.00 .000 1.00 70.0 .000 4 7.200E+03 .000 .000 .000 1.00 1.00 .000 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,a 1 1.800E+03 2.43 1.00 1.00 1.04 1.00 2 3.600E+03 2.43 1.00 1.00 1.04 1.00 3 5.400E+03 2.43 1.00 1.00 1.04 1.00 1 4 7.200E+03 2.43 1.00 1.00 1.04 1.00 !
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ERS-SFL-95-008 d FRC for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page15 8 .
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 FRC Case for EAR dose for 11.75 gym [TC950839.DAT] *** PROGENY INGROWTN ON ***
not used Affeeted S/G AVERAGE ----------CONTROL ROOM-- - -- - - - - =
CURRENT INTEGRD CURRENT INTEGRD RFfra*ED mermaeE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec Kr-832 INITIAL 0.000E+00 8.880E+06 0.000E+00 Kr-83m TOTALS 0.000E+00 4.429E+10 1.723E+05 'O.000E+00
-Kr-85m INITIAL 0.000E+00 4.340E+07 0.000E+00 Kr-85m TOTALS 0.000E+00 2.652E+11 1.032E+06 0.000E+00
,' Kr-85 INITIAL 0.000E+00 2.290E+08 0.000E+00 Kr-E5 TOTALS 0.000E+00 1.626E+12 6.326E+06 0.000E+00 Kr-87 IWITIAL 0.000E+00 2.480E+07 0.000E+00 Kr-87 TOTALS 0.000E+00 1.075E+11 4.182E+05 0.000E+00 Kr-88 INITIAL 0.000E+00 6.610E+07 0.000E+00 Kr-88 TOTALS 0.000E+00 3.718E+11 1.446E+06 0.000E+00 Kr-89 INITIAL 0.000E+00 2.090E+06 0.000E+00 Kr-89 TOTALS 0.000E+00 5.711E+08 2.222E+03 0.000E+00 i
Xe-131m INITIAL 0.000E+00 2.230E+06 0.000E+00 Xa-131m TOTALS 0.000E+00 1.603E+10 6.236E+04 0.000E+00 Xe-133m INITIAL 0.000E+00 6.360E+07 0.OOGE+00 Xa-133m TOTALS 0.000E+00 4.529E+11 1.762E+06 0.000E+00 1
Xe-133 INITIAL 0.000E+00 5.420E+08 0.000E+00 Xa-133 TOTALS 0.000E+00 3.931E+12 1.530E+07 0.000E+00 Xa-135m INITIAL 0.000E+00 2.250E+07 0.000E+00 Xa-135m TOTALS 0.000E+00 2.904E+12 1.130E+07 0.000E+00 Xa-135 INITIAL 0.000E+00 6.650E+07 0.000E+00 Xa-135 TOTALS 0.000E+00 1.595E+12 6. 204E+06 0.000E+00 j Xe-137 INITIAL 0.000E+00 3.380E+06 0.000E+00 Xa-137 TOTALS 0.000E+00 1.119E+09 4.354E+03 0.000E+00 Xe-138 INITIAL 0.000E+00 1.390E+07 0.000E+00
' Xe-138 TOTALS 0.000E+00 1.688E+10 6.566E+04 0.000E+00 I-131 INITIAL 0.000E+00 5.200E+07 0.000E+00 I-131 TOTALS 0.000E+00 1.292E+13 5.027E+07 0.000E+00 ERS-SFL-95-008.d FRC for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 15 9
. TRAILS _PC -- Transport of Radioactive Material in Linear Systests, v1.0 FRC Case for EAR dose for 11.75 gpa [Tc950839.DAT]
- e
- PROGENY INGROWTH ON * *
- not used Affected S/G AVERAGE ----------CONTROL ROON----- ---
CURRENT INTEGRD CURRENT INTEGRD PFYFA9ED RELEASE CURRENT CURRENT INTEGRD ETEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec' uCi uCi/cc uCi-sec I-132 INITIAL 0.000E+00 1.810E+07 0.000E+00 I-132 TOTALS 0.000E+00 1.963E+13 7.638E+07 0.000E+00 I-133 INITIAL 0.000E+00 8.100E+07 0.000E+00 I-133 TOTALS 0.000E+00 2.819E+13 1.097E+08 0.000E+00 I-134 INITIAL 0.000E+00 1.130E+07 0.000E+00 I-134 TOTALS 0.000E+00 2.175E+13 8.462E+07 0.000E+00 I-135 INITIAL 0.000E+00 4.360E+07 0.000E+00 I-135 TOTALS 0.000E+00 2.474E+13 9.627E+07 0.000E+00 ERS-SFL-95-008 /_6 FRC for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 16 0
4 TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0
- PROGENY INGROWTH ON ***
FRC Case for EAB dose for 11.75 gpm tTC950839.DAT]
--- ---CONTROL ROOM-- - --
- --- ---ENVIRONMENT - ------
SKIN-DE THY CDE-INHAL SKIN-DE THY CDE-INHAL External EDE External EDE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE mrem arem/hr arem aren/hr mrem area /hr arem arem/hr arem arem/hr arem mrem /hr Kr-83m 0.00E+00 0.00E+00 0.00E+00 2.66E-06 0.00E+00 0.00E+00 TOTALS Kr-85m 0.00E+00 0.00E+00 0.00E+00 2.78E-02 5.49E-02 0.00E+00 TOTALS Kr-E5 0.00E+00 0.00E+00 TovarA 2.34E-03 3.27E-01 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 6.16E-02 1.46E-01 Kr-88 0.00E+00 5.39E-01 1.19E-01 0.00E+00 0.00E+00 0.00E+00 TOTALS Kr-89 0.00E+00 0.00E+00 8.09E-04 0.00E+00 0.00E+00 TOTALS 7.45E-04 Xe-131m 0.00E+00 0.00E+00 0.00E+00 TOTALS 8.814-05 9.76E-04 0.00E+00 Xe-133m 0.00E+00 0.00E+00 8.65E-03 5.75E-02 0.00E+00 0.00E+00 TOTALS Xe-133 0.00E+00 0.00E+00 8.88E-02 1.68E-01 0.00E+00 C.00E+00 TOTALS Xe-135m 0.00E+00 0.00E+00 8.00E-01 2.54E-01 0.00E+00 0.00E+00 TOTALS Xa-135 0.00E+00 0.00E+00 TOTALS 2.56E-01 4.18E-01 0.00E+00 0.00E+00 Xe-137 0.00E+00 0.00E+00 TOTALS 1.37E-04 2.00E-03 0.00E+00 0.00E+00 Xe-138 0.00E+00 1.01E-02 0.00E+00 0.00E+00 0.00E+00 TOTALS 1.36E-02 I-131 0.00E+00 1.67E+00 1.96E+04 0.00E+00 0.00E+00 TOTALS 3.17E+00 ERS-SFL-95-008 d FRC for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page j g j
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 FRC Case for EAB dose for 11.75 gpm [TC950839.DAT] *** PROGENY INGROWTH ON ***
- - ------ENVIRONNENT- -------- - -
CONTROL ROOM---- - --
SKIN-DE THY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL External EDE DOSE RATE DOSE DOSE BATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE arem area /hr -mram area /hr mrem aren/hr arem area /hr arem arem/hr arem arem/hr I-132 8.87E+00 1.78E+02 0.00E+00 0.00E+00 0.00E+00 TOTALS 3.00E+01 I-133 TOTALS 1.11E+01 1.03E+01 7.12E+03 0.00E+00 0.00E+00 0.00E+00 I-134 3.84E+01 1.26E+01 3.27E+01 0.00E+00 0.00E+00 0.00E+00 TOTALS I-135 2.65E+01 8.01E+00 1.09E+03 0.00E+00 0.00E+00 0.00E+00 TOTALS ALL NUCLIDES
.5000 h 8.67E+00 1.73E+01 3.43E+00 6.86E+00 1.92E+03 3.83E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.58E+01 8.80E+00 1.76E+01 5.34E+03 1.07E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2.29E+01 6.94E+01 1.34E+01 2.68E+01 8.72E+03 1.74E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 3.47E+01 4.47E+01 8.93E+01 1.74E+01 3.48E+01 1.20E+04 2.41E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h TOTALS 1.11E+02 4.30E+01 2.80E+04 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-95-00 Attachment 5 Page 1 g 2
/1 FRC for EAB 11.75 gpm (0.35 uCi/gm)
_ _ . _ _ _ _ _ _ _ - _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ m _mm -__:__-______- _ - _ _ _ _ _ _ _ _ _ - _ - _ _ m-__ - -___-_.__-m -__m --am__
f TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 *** PROGENY INGROWTH ON ***
ITP Case for EAR dose [TC950845.DAT]
4 COMP: not used COMP: intact S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
INITIAL: 0.000E+00 I-131 3.170E+09 I-131 uCi 0.000E+00 I-131 0.000E+00 I-132 1.100E+09 I-132 0.000E+00 I-132'
- 0.000E+00 I-133 4.930E+09 I-133 0.000E+00 I-133 0.000E+GO I-134 6.910E+08 I-134 0.000E+00 I-134
- 0.000E+00 I-135 2.660E+09 I-135 0.000E+00 I-135 l
1.000E+00 1.000E+00 1.000E+00 Acr Mutt (to uct) : ---------------------
.......- . _ _ _ =---- - .
l I
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ERS-SFL-95-008 A ITP for EAB (0.35 uCi/gm) Attachment 5 Page 16 3
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _
_ . _ . . . . . . _ . . _. . ~ - . . . . - - . - . . ~.- . ,- . . . . - . . . .- . .. . _.~ ~ -
- I TRAILS _PC -- Transport of Radioactive Material in Line,ar Systemas, v1.0 I ITP Case for EAB dose [TC950845.DAT} *** PROGENY INGROWTH ON ***
REMOVAL: 0.000E+00 1/sec 6.899E-08 1/sec 1.000E+01 cfaa NUC Grp 1 REL ER: 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR: 0.OOOE+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 3 REL ER: 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 .000 .000 .000 .000 1.00- .000 50.0 50.0 .000 2 3.600E+03 .000 .000 .000 .000 1.00 .000 1.00 70.0 .000 t 3 5.400E+03 .000 .000 .000 .000 1.000E-02 .000 1.00 70.0 .000 I
4 7.200E+03 .000 .000 .000 .000 1.000E-02 .000 70.0 70.0 1.00 i
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 .000 1.00 1.00 1.04 1.00 2 3.600E+03 .000 1.00 1.00 1.04 1.00 3 5.400E+03 .000 1.00 1.00 1.04 1.00 4 7.200E+03 .000 1.00 1.00 1.04 1.00 i
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i ERS-SFL-95-008 A ITP for EAB (0.35 uCi/gm) Attachment 5 Pagel 6 4
.__ _ . _ . . _ _ . _ . _ _ . _. _. . m . - _ _ _ _ . . . _ . . _ . -._
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 *** PROGENY INGROWTH ON ***
ITP Case for EAB dose [TC950845.DATI not used intact S/G AVERAGE ----------CONTROL ROOM-- -
INTEGRD !
CURRENT INTEGRD CURRENT INTEGBD REY.Ra4ED per.ra *E - CURRENT CURRENT RTEP TIME uCi ECi-sec uCi uC1-sec uCi uCi/sec uCi uC1/cc ' uCi-sec .
O.000E+00 0.000E+00 0.000E+00 Xe-131m INITIAL 0.000E+00 Xe-131m TOTALS 0.000E+00 6.043E+08 1.076E+01 ,
i 0.000E+00 0.000E+00 0.000E+00 ,
Xe-133m INITIAL 0.000E+00 Xe-133m TOTALS 0.000E+00 1.307E+10 2.356E+02 O.000E+00 0.000E+00 0.000E+00 Xe-133 INITIAL 0.000E+00 Xe-133 TOTALS 0.000E+00 1.850E+11 3.327E+03 .
t 0.000E+00 0.000E+00 0.000E+00 Xe-135m INITIAL 0.000E+00 Xe-135m TOTALS 0.000E+00 2.361E+12 6.950E+04 d i'
Xa-135 INITIAL 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ,
Xa-135 TOTALS 0.000E+00 1.230E+12 2.243E+04 I-131 INITIAL 0.000E+00 3.170E+09 0.000E+00 ,
0.000E+00 2.274E+13 7.936E+05 0.000E+00 I-131 TOTALS I-132 INITIAL 0.000E+00 1.100E+09 0.000E+00 TOTALS 0.000E+00 5.947E+12 2.376E+05 0.000E+00 I-132 I-133 INITIAL 0.000E+00 4.930E+09 0.000E+00 ,
I-133 TOTALS 0.000E+00 3.433E+13 1.216E+06 0.000E+00 I-134 INITIAL 0.000E+00 6.910E+08 0.000E+00
- I-134 TOTALS 0.000E+00 2.499E+12 1.191E+05 0.000E+00 I-135 INITIAL 0.000E+00 2.660E+09 0.000E+00 I-135 TOTALS 0.000E+00 1.727E+13 6.327E+05 0.000E+00 P
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1 ERS-SFL-95-008 A l ITP for EAB (0.35 uCi/gm) Attachment S Page16 5 l
,_ m__. ..__...m .m . . . .. m _ _ . . _ _ _. _.
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ITV Case for EAB dose ITC950845.DAT] *** PROGENY INGROWTH ON ***
.... ..---ENVIRONMENT--------- -------CONTROL ROOM-- -----
External EDE SKIN-DE THY CDE-INHAL External EDE SKIN-DE TNY CDE-INHAL DOSE DOSE RATE DOSE DOSE RATE POSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE arem arem/hr mrem aren/hr urem arem/hr arem aren/hr arera mram/hr sarem nren/hr Xe-131m TorALS 1.52E-08 1.68E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XP 133m TOTALS 1.16E-06 7.69E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 X:2-133 TOTALS 1.93E-05 3.65E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xr,-135m TOTALS 4.92E-03 1.56E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 X:w135 TOTALS 9.26E-04 1.51E-03 0.00E+00 0.00E+00 0.00E+JO 0.00E+00 I-131 TOTALS 5.00E-02 2.64E-02 3.09E+02 0.00E+00 0.00E+00 0.00E+00 I-132 TOTALS 9.34E-02 2.76E-02 5.52E-01 0.00E+00 0.00E+00 0.00E+00 I-133 TO'_ALS .23E-01 1.14E-01 7.90E+01 0.00E+00 :.1. 00E+ 00 0.OOE+00 s I-134 TOTALS 5.40E-02 1.78E-02 4.60R-02 0.00E+00 0.00E+00 0.00E+00 I-135 i TOTALS 1.74E-01 5.26E-02 7.15E+00 0.00E+00 0.00E+00 0.OOE+00 ALL NUCLIDES
.5000 h 2.59E-01 5.17E-01 1.23E-G1 2.46E-01 1.97E+02 3.93E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.0000 h 2.37E-01 4.75E-01 1.16E-01 2.33E-01 1.95E+02 3.91E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.5000 h 2.20E-03 4.39E-03 1.11E-03 2.22E-03 1.94E+00 3.89E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 2.05E-03 4.10E-03 1.06E-03 2.12E-03 1.93E+00 3.86E+00 0.00E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 5.00E-01 2.42E-01 3.96E+02 0.00E+00 0.00E+00 0.00E+00 i
ERS-SFL-95-008 d I ITP for EAB (0.35 uCi/gm) .9tachment 5 Page ] G G l
- ~ . . - _ - .
. . . ~ . - . - - - - . .- . -
TRAILS PC -- Transport of Radioactive Material in Linear Systems, v1.0 ERP Crse for EAB dose 11.75 gpa [TC950866.DAT] *** PROGENY INGRONTH ON ***
COMP: not used COMP: Affected S/G COMP: Control Room VOLUME: 1.730E+05 Cu.Ft.
=- ----------------- - - - - - - - - - - - - - - - -
INITI Z: 0.000E+00 Kr-83m 8.880E+06 Kr-83m uC3 e.MOE+00 Kr-83m O.000E+00 Kr-85m 4.340E+07 Kr-85m 0.060ra00 Kr-85m 0 000E+00 Kr-85 2.290E+08 Kr-85 0;OLOE+00 Kr-85 6.000E+00 Kr-87 2.480E+07 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-68 6.610E+07 Kr-88 0.000E+00 Kr-88 0.000E+00 Kr-89 2.090E+06 Kr-89 0.000E+00 Kr-89 0.000E+00 1e-131m 2.230E+06 Xe-131m 0.000E+00 Xe-131m 0.000E+00 Ze-133m 6.360E+07 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 5.420E+08 Xe-133 0.000E+00 Xe-133 0.000E+00 Xe-135m 2.250E+07 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 6.650E+07 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 3.380E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 1.39eE+07 Xe-138 0.000E+00 Xe-138 0.000E+00 I-131 3.174+19 I-131 0.000E+00 I-131 0.000E+00 I-132 1.10~@ 09 I-132 0.000E+00 I-132 0.000E+00 I-133 4.930E+09 I-133 0.000E+00 I-133 0.OO3E+00 I-134 6.910E+08 I-134 0.000E+00 I-134 0.000E+00 I-135 2.660E+09 I-135 0.000E+00 I-135 ACT MULT (to uC1) : 1.000E+00 1.000E+00 1.000E+00 ERS-SFL-95-008 d FRP for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page16 7
TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 *** PROGENY INGROWTH ON'***
FRP Case for EAB dose 11.75 gpm [TC950866.DAt]
REMOVAL: 0.000E+00 1/sec 3.891E-06 1/sec 1.000E+01 cfm 0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 1 REL FR:
0.000E+00 0.000E+00 INTAKE REDUCT: 9.360E-01 NUC Grp 2 REL FR: INTAKE REDUCT: 0.000E+00 0.000E+00 0.000E+00 NUC Grp 3 REL FR: -------------------------------------------------------
HULTIPLIERS >
XREM XRF XPR XREM XRF XPR XBEM XRF ETEP TIME XPR
.000 .000 .000 1.00 .000 50.0 50.0 .000 1 1.900E+03 .000 70.0 .000 2 3.600E+03 .000 .000 .000 .000 1.00 .000 1.00 000 .000 .000 1.00 .000 1.00 70.0 .000 3 5.400E+03 .000 70.0 70.0 1.00 4 7.200E+03 .000 .000 .000 .000 1.00 .000
CONTROL ROON -------- ---- ENVIRONMENT ---
X/O 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 HULTIPLIERS >
CTEP TIME,s 1 1.800E+03 .000 1.00 1.00 1.04 1.00 2 3.600E+03 .000 1.00 1.00 1.04 1.00 3 5.400E+03 .000 1.00 1.00 1.04 1.00 4 7.200E+03 .000 1.00 1.00 1.04 1.00 ERS-SFL-95-008 d FRP for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page16 8
-_. = ._ _ ._ -_
TRAILS _PC -- Transport of Radioactive Haterial in Linear Systems, v1.0 ERP Case for EAB doso 11.75 gpm (TC950866.DAT] *** PROGENY INGROWTH ON ***
not used Affected S/G AVERAGE ----------CONTROL ROOM-----------
CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-see uCi uCi-sec uCi uC1/sec uCi uCi/cc uCi-sec Kr-83m INITIAL 0.000E+00 8.880E+06 0.000E+00 Kr-83m TOTALS 0.000E+00 4.429E+10 1.723E+05 0.000E+00 i
Kr-85m INITIAL 0.000E+00 4.340E+07 0.000E+00 Kr-85m TOTALS 0.000E+00 2.652E+11 1.032E+06 0.000E+00 Kr-85 INITIAL 0.000E+00 2.290E+08 0.000E+00 Kr-85 TOTALS 0.000E+00 1.626E+12 6.326E+06 0.000E+00 Kr-87 INITIAL 0.000E+00 2.480E+07 0.000E+00 Kr-87 TOTALS 0.000E+00 1.075E+11 4.182E+05 0.000E+00 Kr-88 INITIAL 0.000E+00 6.610E+07 0.000E+00 Kr-88 TOTALS 0.000E+00 3.718E+11 1.446E+06 0.000E+00 Kr-89 INIiIAL 0.000E+00 2.090E+06 0.000E+00 Kr-89 TOTALS 0.000E+00 5.711E+08 2.222E+03 0.000E+00 X6 t' .. INITIAL 0.000E+00 2.230E+06 0.000E+00 Xe .sim TOTALS 0.000E+00 1.639E+10 (.376E+04 0.000E+00 Xe-13 M INITIAL O.000E+00 6.360E+07 0.000E+00 Xe-133m TOTALS 0.000E+00 4.585E+11 1.784E+06 0.000E+00 Xa-133 INITIAL 0.000R+00 5.420E+08 0.000E+00 Xu-133 TOTALS 0.OOOE+00 4.011E+12 1.561E+07 0.000E+00 i
Xe-135m INITIAL O.000E+00 2.250E+07 0.000E+00 Xe-135m TOTALS 0.000E+00 2.354E+12 9.160E+06 0.000E+00 Xa-135 INITIAL 0.000E+00 6.650E+07 -
0.000E+00 Xs-135 TOTALS 0.000E+00 1.650E+12 6.419E+06 0.000E+00 X2-137 INITIAL 0.000E+00 3.380E+06 0.000E+00 Xa-137 TOTALS 0.000E+00 1.119E+09 4.354E+03 0.000E+00 Xe-138 Ih1TIAL 0.000E+00 1.390E+07 0.000E+00 Xe-138 TOTALS 0.000E+00 1.688E+10 6.566E+04 0.000E+00 I-131 INITIAL 0.000E+00 3.170E+09 0.000E+00 I-131 TOTALS 0.000E+00 2.243E+13 8.726E+07 0.000E+00 ERS-SFL-95-008 d FRP for EAB 11.75 gpm (0.35 uCVgm) Attachment 5 Page j 6 9 l
TRAILS _PC -- Transp;rt (f Radioactive Waterial in Linear systems, v1.0 FRP Case for EAR dose 11.75 gpa [TC950866.DAT] *** PROGENY INGROtrIN ON ***
not used Affected s/G AVERAGE ----------CONTROL ROOH-----------
CURM3C INTEGRD CURREriT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TINE uCi uC1-sec uCi .uCi-sec uCi uC1/mee uC1 uCi/cc uCi-sec ,
I-132 INITIAL 0.000E+00 1.lf0E+09 0.000E+00 I-132 TOTALS 0.000E+00 5.874E+12 2.286E+07 0.000E+00 I-133 INITIAL 0.000E+00 4.930E+09 0.000E+00 I-133 IOTALs 0.000E+00 . 2.387E+13 1.318E+08 0.000E+00 I-134 IMITIAL 0.000E+00 6.310E+08 0.000E+00 I-134 TOTALS 0.000E+00 2.473E+12 9.623E+06 0.000E+00 I-135 INITIAL 0.000E+00 2.660E+09 0.000E+00 1-135 TOTALS 0.000E+00 1.705E+13 6.632E+07 0.000E+00 l
O I
ERS-SFL-95-008 d FRP for EAB 11.75 gpm (0.35 uCl/gm) Attachment 5 Page 170
. - _ _ . - . . . , - -. . .n.- .. _ . . _ . . . - . . . . . ~ ~ - . . . . . . . _ ~ _ . ..
TRAILS _PC -- Transport of Radioactive Material in Linear systems, v1.0 *** PROGENY INGROWTH ON ***
ERP Case for EAB dose 11.75 gpsa (TC950866.DAT)
- - --- --ENVIRONMENT--------- -------CONTROL ROOM-------
External EDE SKIN-DE TNY CDE-INHAL External EDE SKIN-DE THY CDE-INHAL DOSE RATE DDSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE mram aren/hr mresa arem/hr aream area /hr arem area /hr arena mram/hr arem mresa/hr Kr-83m 2.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS Kr-85m 2.78E-02 5.49E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTJJ.3 Kr-85 2.34E-03 3.27E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS Kr-87 TOTALS 6.16E-02 1.46E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Kr-08 TOTALS 5.39E-01 1.19E-01 0.00E+00 0.00E+00 0.00E+00~ 0.00E+00 Ka-00 TOTALS 7.45E-04 8.09E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xa-131m TOTALS 9.01E-05 9.98E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xa-133m TOTALS 8.76E-03 5.82E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 TOTALS 9.05E-02 1.71E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xa-135m i TOTALS 6.48E-01, 2.06E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t Xa-135 TOTALS 2.65E-01 4.32E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 TOTALS 1.37E-04 2.08E-03 0.0G2:00 0.00E+00 J.00E+00 0.00E+00 Xe-138 TOTALS 1.36E-02 1.01E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 TOTALS 5.50E+00 2.90E+00 3.40E+04 0.00E+00 0.00E+00 0.00E+00 ERS-SFL-95-008 d FRP for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page j 7 }
- - . . ~ . . .. . - - - . . . .
TRAILS _PC -- Transport of Radioactive katerial in Linear Systems, v1.0 FRP Case for EAB dose 11.75 gpa [TC950866.DAT] * *
- PROGENY INGR06fTH ON * * *
ENVIRONNENT--- - ---- ----- - -CONTROL ROOM-------
External EDE SKIN-DE TNY CDE-INHAL External EDE SKIN-DE THY DE-INHAL DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE kATE arem aren/hr arem mren/h- arem arem/hr mrem aren/hr mrem aren/hr aren mrem /hr I-132 8.98E+00 2.65E+00 5.31E+01 0.00E+00 0.00E+00 0.00E+00 TOTALS I-133 TOTALS 1.33E+01 1.24E+01 8.56E+03 0.00E+00 0.00E+00 0.00E+00 I-134 TOTALS 4.36E+00 1.43E+00 3.72E+00 0.00E+00 0.00E+00 0.00E+00 I-135 TOTALS 1.82E+01 5.52E+00 7.49E+02 0.00E+00 0.00E+00 0.00E+00 ALL NUCLIDES
.5000 h 1.48E+01 2.96E+01 7.20E+00 1.44E+01 1.11E+04 2.21E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.0000 h 1.35E+01 2.69E+01 6.75E+00 1.35E+01 1.09E+04 2.18E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J.5000 h 1.24E+01 2.47E+01 6.38E+00 1.28E+01 1.08E+04 2.15E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.0000 h 1.15E+01 2.29E+01 6.07E+00 1.21E+01 1.06Et04 2.13E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 5.21E+01 2.64E+01 4.34E+04 0.00E+00 0.00E+00 0.00E+00 P
ERS-SFL-95-008 d FRP for EAB 11.75 gpm (0.35 uCi/gm) Attachment 5 Page 172
isotopic Release 0-2 hour Co-incident lodine Spike - 0.35 uCi/gm base ASA ILI FLI ITC ITN FFIC SUM uCI uCi uCi uCI uCI uCI Cl Kr43m 3.990E+00 0 0 0 3.092E+03 1.723E+05 1.8E-01 Kr45m 1.947E+01 0 0 0 1.854E+04 1.032E+06 1.1 E+00 Kr45 1.029E+02 0 0 0 1.137E+05 6.326E+06 6.4E+ 00 Kr47 1.110E+01 0 0 0 7.500E+03 4.182E+05 4.3E 01 Kr48 2.967E+01 0 0 0 2.597E+04 1.446E+06 1.5E+00 Kr49 9.358E-01 0 0 0 3.944E+01 2.222E+03 2.3E-03 Xe-131m 1.002E+00 3.484E+00 3.464E+00 2.250E+00 1.105E+03 6.236E+04 6.3E-02 Xe-133m 2.856E+01 6.339E+01 6.464E+01 6.965E+01 3.117E+04 1.762E+06 1.8E+00 Xe-133 2.433E+02 8.973E+02 9.104E+02 9.829E+02 2.679E+05 1.530E+07 1.6E+01 Xe-135m 1.014E+01 7.780E+03 2.523E+04 4.045E+04 2.054E+03 1.130E+07 1.1 E+01 Xe-135 2.985E+01 4.040E+03 3.998E+03 1.108E+04 3.087E+04 6.204E+06 6.3E+00 Xe-137 1.515E+00 0 0 0 7.731E+01 4.354E+03 4.4E-03 Xe-138 6.240E+00 0 0 0 1.170E+03 6.566E+04 6.7E-02 '
1-131 7.140E+03 1.319E+05 3.600E+06 2.383E+05 0 5.027E+07 5.4E+01 l-132 1.266E+03 1.768E+04 6.321E+05 3.866E+05 0 7.638E+07 7.7E+01 1-133 9.330E+03 1.676E+05 4.704E+06 5.206E+05 0 1.097E+08 1.2E+02 l-134 2.229E+02 2.097E+03 1.099E+05 4.803E+05 0 8.462E+07 8.5E+01 1-135 3.420E+03 5.709E+04 1.713E+06 4.634E+05 0 9.627E+07 9.9E+01 EC950815.XLS ERS-SFL-95-008 A Attachment 6 Page 17.3
_ _ _ . . _ . , _ . _ . . _. _ _ _ . . . _ _ . . . _ _ . . _ _ . _ ~__ _ _ _ . _ _ _
f Isotopic Release 0-2 Hour Pre-incident lodine Spike - 0.35 uCi/gm basis ASA ILI FLI ITP ITN FRP SUM.
uCl uCI uCI uCI uCI uCI Cl 3.990E+00 0 0 0 3.092E+03 1.723E+05 1.8E-01 Kr-83m 1.947E+01 0 0 0 1.854E+04 1.032E+06 1.1 E+00 Kr-85m 1.029E+02 0 0 0 1.137E+05 6.326E+06 6.4E+00 Kr-85 1.110E+01 0 0 0 7.500E+03 4.182E+05 4.3E-01 Kr-87 Kr-88 2.967E+01 0 0 0 2.597E+04 1.446E+06 1.5E+00 Kr-89 9.358E-01 0 0 0 3.944E+01 2.222E+03 2.3E-03 Xe-131m 1.002E+00 3.484E+00 3.464E+00 1.076E+01 1.105E+03 6.376E+04 6.5E-02 Xe-133m 2.856E+01 6.339E+01 6.464E+01 2.356E+02 3.117E+04 1.784E+06 1.8E+00 2.433E+02 8.973E+02 9.104E+02 3.327E+03 2.679E+05 1.561E+07 1.6E+01 Xe-133 Xe-135m 1.014E+01 7.780E+03 2.523E+04 6.950E+04 2.054E+03 9.160E+06 9.3E+00 Xe-135 2.985E+01 4.040E+03 3.993E+03 2.243E+04 3.087E+04 6.419E+06 6.5E+00 i Xe-137 1.515E+00 0 0 0 7.731E+01 4.354E+03 4.4E-03 Xe-138 6.240E+00 0 0 0 1.170E+03 6.566E+04 6.7E-02 1-131 7.140E+03 1.319E+05 3.600E+06 7.936E+05 0 8.726E+07 9.2E+01 I-132 1.266E+03 1.768E+04 6.321 E+05 2.376E+05 0 2.286E+07 2.4E+01 ,
1-133 9.330E+03 1.676E+05 4.704E+06 1.216E+06 0 1.318E+08 1.4E+02 l-134 2.229E+02 2.097E+03 1.099E+05 1.191 E+05 0 9.623E+06 9.9E+00 l-135 3.420E+03 5.709E+04 1.713E+06 6.327E+05 0 6.632E+07 6.9E+01 EC950815.XLS ERS-SFL-95-008 d Attachment 6 Page 17 4
_ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _
Isotopic Releass 30 day Co-incident lodine Spike - 0.35 uCilgm base ASA ILI FL1 ITC ITN FFIC SUM uCI uCI uCl uCI uCi uCi Cl 0 0 0 5.538E+03 3.030E+05 3.1 E-01 Kr-83m 3.990E+00 1.947E+01 0 0 0 4.942E+04 2.669E+06 2.7E+00 Kr-85m 1.029E+02 0 0 0 4.545E+05 2.428E+07 2.5E+01 Kr-85 1.110E+01 0 0 0 1.115E+04 6.142E+05 6.3E-01 Kr-87 2.96/E+01 0 0 0 5.768E+04 3.132E+06 3.2E+00 Kr-88 9.358E-01 0 0 0 3.944E+01 2.222E+03 2.3E-03 Kr-89 1.002E+00 3.472E+01 3.464E+00 1.078E+01 4.383E+03 2.803E+05 2.8E-01 Xe-131m 2.856E+01 5.856E+02 6.464E+01 3.196E+02 1.198E+05 7.761 E+06 7.9E+00 Xe-133m 2.433E+02 8.420E+03 9.104E+02 4.565E+03 1.055E+06 7.579E+07 7.7E+01 Xe-133 1.014E+01 1.970E+04 2.523E+04 6.390E+04 2.064E+03 1.379E+08 1.4E+02 Xe-135m 3.038E+04 3.998E+03 4.548E+04 9.979E+04 1.931 E+08 1.9E+02 -
Xe-135 2.985E+01 0 0 0 7.731E+01 4.354E+03 4.4 E-03 Xe-137 1.515E+00 6.240E+00 0- 0 0 1.173E+03 6.584E+04 6.7E-02 -
' Xe-138 I-131 7.140E+03 3 683E+05 3.600E+06 3.344E+05 0 5.676E+08 5.7E+02 l-132 1266E+03 2.860E+04 6.321E+05 4.634E+05 0 4.950E+08 5.0E+02 I-133 9.330E+03 4.349E+05 4.704E+06 7.158E+05 0 1.162E+09 1.2E+03 I-134 2.229E+02 2.429E+03 1.099E+05 5.252E+05 0 3.326E+08 3.3E+ 02 1-135 3.420E+03 1.265E+05 1.713E+06 6.080E+05 0 8.784E+08 8.8E+02 EC950815.XLS ERS-SFL-95-008 lh Attachment 6 Page ,{ 7 5
- . . - - - =.. -. -. - .
i Isotopic Release 0-30 day Pre-incident lodine Spike - 0.35 uCi/gm base !
ASA ILI FLI ITP ITN FRP SUM uCI uCi ' uCI uCi uCI uCi Cl Kr-83m 3.990E+00 0 0 0 5.538E+03 3.030E+05 3.1 E-01 Kr-85m 1.947E+01 0 0 0 4.942E+04 2.669E+06 2.7E+00 Kr-85 1.029E+02 0 0 0 4.545E+05 2.428E+07 2.5E+01 1.110E+01 0 0 0 1.115E+04 6.142E+05 6.3E-01 ;
Kr-87 Kr-88 2.967E+01 0 0 0 5.768E+04 3.132E+06 3.2E+00 Kr-89 9.358E-01 0 0 0 3.944E+01 2.222E+03 2.3E-03 i Xe-131m 1.002E+00 3.472E+01 3.464E+00 1.693E+01 4.383E+03 2.687E+05 2.7E-01 i Xe-133m 2.856E+01 5.856E+02 6.464E+01 3.582E+02 1.198E+05 7.095E+06 7.2E+00 i Xe-133 2.433E+02 8.420E+03 9.104E+02 5.094E+03 1.055E+06 6.630E+07 6.7E+01 :
Xe-135m 1.014E+01 1.970E+04 2.523E+04 7.359E+04 2.064E+03 3.078E+07 3.1 E+01 Xe-135 2.985E+01 3.038E+04 3.998E+03 3.154E+04 9.979E+04 5.779E+07 5.8E+01 Xe-137 1.515E+00 0 0 0 7.731E+01 4.354E+03 4.4E-03 Xe-138 6.240E+00 0 0 0 1.173E+03 6.584E+04 6.7E-02 '
1-131 7.140E+03 3.683E+05 3.600E+06 8.400E+05 0 3.314E+08 3.4E+02 l-132 1.266E+03 2.860E+04 6.321 E+05 2.417E+05 0 4.494E+07 4.6E+01 l l-133 9.330E+03 4.349E+05 4.704E+06 1.278E+06 0 4.599E+08 4.7E+02 1-134 2.229E+02 2.429E+03 1.099E+05 1.196E+05 0 1.201E+07 1.2E+01 l-135 3.420E+03 1.265E+05 1.713E+06 6.566E+05 0 1.923E+08 1.9E+02 ;
EC950815.XLS ERS-SFL-95-008 A Attachment 6 Pag ( 7 6
- _ _ _ _ _ _.___...___m.___ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ ,
RTL: n/a Form: RE 1.103-3 092 M App ndix 1 TA @Dgmie M seahh Physics Department ERS-SFL-95 008 d i d
No'e:
. This appendix was reviewed and approved as part of ERS-SFL 95408 revision o. This appen6ix is intended to standardize the modering assumptions and to eliminate the need to re-review these input parameters and assumptions wrth each now application, if a specific deviation j from the informaton herein is necessary to meet the needa of a particular analysis,it should be described and jushfied in the main text of the '
paca ge.
Generic Control Room Modeling
- 1. General This appendix describes the generic modeling of the Unit 1/ Unit 2 common control room. This modeling is 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 I 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. I
^
1
- 2. Control Room Ventilation System'm
]
Figures 1 and 2 litustrate the normal system alignment of tb L1 and U2 control room ventilation systems.
The systems in both sides of the control room operate independently, but are interlocked through the 1 Control Room Emergency Breathing Air Pressurization System (CREBAPS). The following actuate i CREBAPS: 1 1
. A Containment Isolation Signal, Phase B (CIB) at either unit.
i 1
-
- A high-high alarm on 1RM-RM 218A or B (Unit 1) or a high alarm on 2RMC*RO201 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.
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 di 'oer 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 the 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, there is a single filtered emergency intake train comprised of motor operated dampers (NS A 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 osoeom.-
RTI.; nh Form: RE 1.103-3 S92 2g App ndix 1 ERS-SFL-95 OO8 d TA @Dnwne u ny,uo.p.nm.m M 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.
4 On a CREBAPS actuation, all four intake dampers and all four exhaust dampers recolve a close signal.
This isolates the normai 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 room 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) uampers, 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, seats, and doors.
l 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' 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 activity introduction. Once the alarm trip setpoint is reached, there will be delay in the damper movement. The total delay time is identified as To The isolation time, T,,
, equals T, + T o. 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'.
2.4.2 For Unit 2, Reference 6 notes taat 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, To = 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.
x:ssosotPMS
RTL: n/a Fmn: RE1.103-3 692 ggDuquesne M ERS-SFL-95 008 d Appendix 1 Teg w. o. n.e. page A13 2.4.3 The assumption in the original record of analysis 7 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 Umitorque' 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; To= 3 min + 15 seconds =
3.25 minutes Unit 20*".
2.4.5 For the DBA LOCA, control room isolation is actuated by a CIS 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.
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 thir W,e, 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 diesel genera- {
tor 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 chn This is generally not modeled as the difference is generally insignificant to the overall results.
2.6 The pressurization system will bleed air at a rate sufficient to maintain the requisite pressure. Based I 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 Tp 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 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 specifica'tlon 3/4.7.7 addresses control room habitability systems. Operability requirements require testing for less than 1% leakage and a methyliodine removal etficiency greater than 99%. In accordance with Regulatory Guide 1.52, assigned efficiencies are 95%
for elemental and organiclodines.
1 1
,c n ~s 1
RT1.: n/a Ferm: RE 1.1c3-3 A52 ggD4"N D ERS-SFL-G5-008 Ai Appendix 1 page A1-4 l Health I'hysies Department 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. {
i I
2.9 At the completion of the purge and continuing through to the end of the assessment period (i.9.,720 ,
hours), the flow rates return to their original value of 500 cfm. l l
- 3. Control Room Model Parameters I 3.1 Control Room Volume = 1.73E+5 ft2 [4 - Tbl 6.4-1]
I 3.2 Normal ventilation intake: BV1 = 300 cfm; BV2 = 200 cfm [4 - Tbl 6.4-1] i 3.3 Filter efficiency = 93.6% [12.7 above]
3.4 Purge Flow Rate: BV1 = 33,500 cfm; BV2 = 18,000 cfm [3 - 69.13.4, 4 - Tbl 9.4-3]
l l
Note: the licensing basis calculations assumed a purge flow of 20,000 cfm. The flow thru the ACUS l was subsequently determined to be 18,000 which is reflected on U2 UFSAR Figure 9.4 1 and Table l 9.4-3. These values conflict with the value in Table 6.41, which appears to be outdated. Purging was l not a significant factorin 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 cfm. However, by lasting the amount of air bottle flow needed to maintain the requisite pressure differential, the ex6ftration rate has been deemed to be 690 cfm +
10 ckn unfiltered inleakage. Thus, the intake will be constrained by the exfiltration capability. Thus, the analysis assumes an fan intake flow rate of 700 cim.
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 a seconds without diesel starting and sequencing ar.d 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 circu'rtry 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.
AC95C401.P%,5
RTL: n/a Form: RE1.1013 292 Appendix 1 ggDuquesne @ ERS-SFL-95-008 d Ah HealthPhysicsDepartment p g , 43,3
- (2) The RYS response delay includes tiie 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 Diecd Start n/a (1) 10 sec (18]
Diesel Sequence n/a (1) 40 2 4 sec (18]
Damper Movement n/a (1) 12 sec [6] i Sum 77 see 12 sec (6)
I Seismic Delay 15 sec (10,11) 15 sec (10,11]
1 Total 92 sec 81 sec (1) See note 1 for datum 3.7. l 3.9 Control Room y/Q, sec/m2- Unit 1 (3 - Tbl 2.2-12,19]
Release Point 0-8 hrs 8 24 hrs 1-4 davs 4 30 davs 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 9.2SE-4 l 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/Q, sec/m8- Unit 2 (4 - Tbl 15.0-14,19]
Hgj.t.ase Point 0-8 hrs 8 24 hrs 1-4 days 4 30 davs CNMT edge 1.88E-4 9.32E-5 7.06E-5 4.18E-5 CNMT top (SLCRS) 1.20E-4 5.91E 5 4.45E 5 2.64E-5 PAB 1.04E 3 5.15E-4 4.04E-4 2.46E 4 MSVA 1.59E 4 7.86E-5 5.96E-5 3.76E-5 Service Bk!g 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 1-4 days 0.6
>4 days 0.4 u:esoeci.ms
RTL: nh Form: RE 1.103-3 A91 jQ
%NW o.M App:ndix 1 ERS SFL-95 008 d pase ^1-8
.e.
REFERENCES
- 1. DLC, BVPS-1 Ooeratina Manual. Chapter 44C
- 2. DLC, BVPS-2 Ooeratina Manual. Chapter 44C
- 3. DLC, Uodated Final Safety Analysis Recort Unit 1.
- 4. DLC, Uodated Final Safety Analvsis Reoort Unit 2.
- 5. USNRC, Criterion 19. Title 10 Code of Federal Regulations Part 50, Appendix A
12241 UR(B)-445, Revision 0; 1987
- 7. SWEC, Combined BV1-BV2 Control Room Habitability Due to Desian Basis Accidents (exceot LOCA) at Sy_,1.,12241 UR(B)-456, Revision 0,1987
- 8. Limitorque, Potentialtv Reoortable 10 CFR Part 21 Condition. ltr dtd 12/7/92
- 9. OLC,10 CFR Part 21 Notice: Limitoraue Declutchina Mechanism. EM104392 dtd 12/21/92
- 10. DLC, Safety Analvsis of Consecuences of Control Room Damoer Resoonse Delav (Limitorau61Q,CFR 21)
- Unit 1 Accidents. ERS-SFL-93-005, Revision 0; 1993
- 11. DLC, Safety Analvsis of Consecuences of Control Room Damoer Resoonse Delav (Limitoraue 10 CFR 21)
- Unit 2 Accidents. ERS-SFL-93-004, Revision 0; 1993
- 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, P.evision 5; 1987 ($6.4.3) !
- 15. DLC, Technical Specification 3/4.7.7 (U1 and U2)
- 16. USNRC. Desian. Testina. and Maintenance Criteria for Postaccident Enaineered Safetv Feature Atmo-sphere Cleanuo System Air Filtration and Adsorotion Units of Llaht Water Cooled Nuclear Power Plants.
Regulatory Guide 1.52, Revision 2; 1978
- 17. DLC, BVPS 1 Operating Manual OST 1.36.3 (4)
- 18. DLC, BVPS-2 Operating Manual OST 2.36.3
- 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 Control Room Ventilation System Desian for Meetina General Criterion 19. published in proceedings of 13th AEC Air Cleaning Conference acaso owws
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i i ATTACHMENT D
! Beaver Valley Power Station, Unit No. 1 l Proposed Technical Specification Change No. 240 l
j Information copy of proposed UFSAR changes.
l l
i i
i i
l l
l l
l l
i BVPS-1-UPDATED FSAR Rev. 13 (1/95) a 1
X/O * (3.14S Sy z + cA) u (2.2-2) where: X = concentration (units /m3)
Q = source release rate (unit /sec)
S y = horizontal diffusion parameter (m)
S z = vertical diffusion parameter (m)
] u = mean wind speed (m/sec)
A = cross-sectional area of containment (1,600 m 2) i c = building shape factor = 0.5 (dimensionless)
For the period 2-24 hours following the start of a release, it is assumed that the wind direction varies over one sector under "F" l stability conditions and 0.84 m/sec wind speed. Inasmuch as the longest observed on-site wind direction persistence under stable conditions ("F" stability) was one occurrence for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, this assumption is conservative.
For the period from 24-96 hours, it is assumed that the mean wind direction is varying within the sector of interest 50 percent of the time. During this time, the stability is assumed to be "D" l with a 2.0 m/sec wind speed and "F" with a 0.9 m/sec wind speed.
For the period from 4-30 days, meteorological conditions characteristic of the lowest dispersion have been chosen. These conditions, and those for the other time periods, are also presented in Table 2.2-5.
The results of the calculations for the four time periods comprising the 30 day model are shown in Figure 12 of Appendix 2A.2 which presents curves of X/Q versus distance. If an independent evaluation of the above results is desired, see Appendix 2A which provides the pertinent data.
In support of a re-analysis performed on the design basis loss-of-coolant accident (LOCA) in 1983, the X/Q values for the DBA meteorologywerere-deteygggyg5y e9 a e and formulae l of Regulatory Guide 1.145. The analyses were performed on hourly averaged meteorological data collected during the period from January 1 to December 31, 1982. The data recoverability for this period was 94.3 percent. As a result of these X/Q analyses, the maximum sector 0.5 percent X/Q value was determined to be more limiting than the 5 percent site X/Q value. Table 2.2-11 the values used in the re-analysis of the design basis tabul LOCA.
{gy NSMTA 2.2-8
o l
, INSERT A l In 1996, short-term diffusion estimates were re-calculated"* using the USNRC computer code PAVAN"*. Input data were hourly meteorological observations collected by the onsite meteorological monitoring program between 00001/1/86 and 230012/31/95. The 0.5% sector dependent and the 5% sector independent values defined in Regulatory Guide 1.145"* were determined and are tabulated in Tables 2.2-11a and 2.2-11b. Data recoverability during this ten year period was 99.6%. The minimum recoverability for any year in this period was 99%. This re-analysis indicated a maximum 0-2 hour exclusion area boundary 0.5% value of 1.04E-3 sec/m' (NW sector).
This value is 17% more restrictive than the value determined in 1983. As such, the values in Tables 2.2-11a and 2.2-11b will be used for radiological consequence analyses performed subsequent to 1996. l 1
l l
l l
l
l BVPS-1-UPDATED FSAR ,
Rav. 13 '(1/95) 1 l .
- 15. USNRC NUREG/CR-2858, " PAVAN: An Atmospheric Dispersion Program for Evaluating Design Basis Accidental Releases of Radioactive Materials from Nuclear Power Stations", Pacific Northwest Laboratory (November 1982).
- 16. DLC Calculation ERS-SFL-83-015jrO,
- 17. Halliburton NUS Environmental Corpo ation, Control Room X/Q Values for the Beaver Valley Power Sta ion, 1991.
- 18. Ramsdell, J.V., Atmospheric Diffusion for Control Room Habitability Assessments, NUREG/CR-505 , 1988.
1 i
-~
Qccident Analysis X/O Values,1983.
l
- 19. DLC Calculation ERS-SFL-96-021 ro, RG 1.145 Short Term Accident X/O Values for EAB and LPZ, Unit 1 and Unit 2, based on 1986-1995 Observations,1996 l.
! 2.2-13
^
l BVPS-1 UPDATED FSAR I l
O TABLE 2.2-11a 0.5% Accideant Analysis 0- to 2-Hour X/O Values
- at the Exclusion Area Boundary (1/1/86 - 12/31/95)
Downwind Downwind Sector X/Q Sector Distance (m) (sec/m )
N 610 5.41 E-4 ,
NNE 610 3.31 E-4 l
NE- 610 2.11 E-4 ;
ENE 610 1.84E-4 !
E 610 1.85E-4 l ESE 610 2.01 E-4 SE 610 1.86E-4 i SSE 610 1.92E-4 i S 610 2.08E-4 I SSW 610 2.36E-4 1 2
SW 610 3.17E-4 WSW 610 3.93E-4 W 610 5.67E-4 WNW 610 8.00E-4 NW 610 1.04E-3 NNW 610 7.35E-4 l Maximum Value (NW) 1.04E-3 5% Site Value 6.09E-4 Ref: ERS-SFL-96-021 r0,1996 NOTE The data above were generated in 1996. Appendix 2A and Table 2.2-11 values were used for analyses performed prior to 1996.
i i
BVPS-1 UPDATED FSAR TABLE 2.2-11b 0.5% Accident Analysis X/O Values for Various Time Periods at the Low Population Zone Boundary (1/1/86 - 12/31/95) 1 Downwind Distance sec/m* j Sector (m) 0-2 Hrs 0-8 Hrs 8-24 Hrs 1-4 days 4-30 days N 5794 5.22E-5 2.42E-5 1.64E-5 7.12E-6 2.14E-6 NNE 5794 2.79E-5 1.33E-5 9.16E-6 4.09E-6 1.29E-6 NE 5794 1.66E-5 8.16E-6 5.72 E-6 2.65E-6 8.76E-7 l ENE 5794 1.40E 5 7.50E-6 5.49E-6 2.80E-6 1.06E-6 E 5794 1.32E-5 6.52 E-6 4.59E-6 2.14 E-6 7.17E-7 ,
ESE 5794 1.28E-5 6.16E-6 4.27E-6 1.93E-6 6.19E-7 SE 5794 1.45E-5 6.95E-6 4.81 E-6 2.17E-6 6.92E-7 SSE 5794 1.47E-5 6.80E-6 4.62E-6 2.00E-6 5.99E-7 S 5794 1.64 E-5 7.51 E-6 5.09E-6 2.18E-6 6.48E-7 ,
SSW 5794 1.88E-5 8.68E-6 5.90E-6 2.55E-6 7.65E-7 l SW 5794 2.80E-5 1.30E-5 8.83E-6 3.83E-6 1.15E-6 i WSW 5794 4.22E-5 1.99E-5 1.37E-5 6.08E-6 1.89E-6 W 5794 6.41 E-5 3.00E-5 2.06E-5 9.03E-6 2.77E-6 i WNW 5794 9.06E-5 4.58E-5 3.26E-5 1.56E-5 5.38E-6 NW- 5794 1.18E-4 6.04E-5 4.33E-5 2.10E-5 7.44E-6 NNW 5794 8.32E-5 3.94E-5 2.71 E-5 1.21 E-5 3.78E-6 Max, Value (N'N) 1.18E-4 6.04E-5 4.33E-5 2.10E-5 7.44E-6 l
5% Site Value 6.68E-5 3.77E-5 2.83E-5 1.52E-5 6.23E-6 Ref: ERS-SFL-96-021 r0,1996 ,
NOTE '
The data above were generated in 1996. Appendix 2A and Table 2.2-11 values were used for :
analyses performed prior to 1996. l i
I
BVPS-1-UPDATED FSAR R@v. 14 (1/96) i
\
Loss of Coolant Accident
~
H. - '
l I. Rod Ejection Accident i
The BV1-BV2 Control Room is habitable for all Design Basis j
Accidents at Beaver Valley Power Station Unit 1 with the following provisions:
I. CONTROL ROOM ISOLATION A. Automatic Control' Room Isolation Isolation by area radiation monitor signal (at a i Control Room environment gamma dose rate of 1 mrem /hr) will occur for the following: l Small Line Break Waste Gas System Line Rupture ;
s Single Locked Rotor Accident i Isolation by Containment Isolation Phase B (CIB) signal will occur for the major Loss of Coolant Accident I (LOCA).
B. Manual Control Roor Isolation Manual operator action is required (automatic isolation will not occur) at t = 30 minutes post-accident initiation to isolate the Control Room for:
Main Steamline Break II. PURGING OF CONTROL ROOM ATMOSPHERE Requirements for purging the Control Room atmosphere after each accident at the rate of(jJ7Edg.cfm for a minimum of 30 minutes are as follows: 9 -
G V 80)
A. Locked Rotor Accident ,pygk g g L,Ag, A m y Purging no later than t = 8 hr post-accident initiation. Purging at any time after releases have been terminated will reduce the 30-day integrated dose.
B. Rod Ejection Accident, Fuel Handling Accident, Waste j Gas System Rupture, "ri- Strrrlin Err t, Steam j Generator Tube Rupture, Small Line Break, Major LOCA, Loss of AC Power Purging is not required, however, purging at t = 8 hr or after releases have stopped will reduce the 30-day integrated doses.
11.3-24 l
l j
i BVPS-1-UPDATED FSAR Rav. 13 (1/95) i I
References to Section 11.3 r
- 1. Combined BV1-BV2 Control Room Habitability Due to Design Basis Accidents (except LOCA) at BV-1, Calculation Identification l Number 12241/14110.39, UR(B)-456, dated April 24, 1987.
- 2. Doses to the BV1 Control Room Due to a LOCA at BV1, l Calculation Identification Number 14110.39, UR(B)-457, dated l May 11, 1987.
- 3. DLC Calculation ERS-SFL-93-00 ,rD, Safety Analysis of ,
Consequences of Control Room Dampe ponse Delay (Limiterque '
10 CFR 21) - Unit 1 Accidents, dated May 3 993.
- 4. DLC Calculation ERS-SFL-92-0 3,rl, ombined Control Room Doses Due to SGTR at Unit 1.
5 . In.t Ca lcA4m s es - sn - % -59, % fe b A"dh S $ of g' Ceuum (m(<ol be , Eg tr-z, boses %a Mom N u< bue Ibak CUM q Cogh,yue d 01 (x> 'h l Acreased Prmcag -b- Ce 66g 19 9 6> .
l l
l 11.3-26
.. . . .. . - . - . _ . . . - . . _ . . . ~ . . .- . . - -_
BVPS-1-UPDATED FSAR Rev. 12 (1/94)
TABLE 11.3-7 POSTULE.'ED CONTROL ROOM ACCIDENT DOSE. rem 6 (Oesign Basis Accidents at Unit 1)
Accident Thyroid Gamma Beta Notes.
Main Steam Line Break - - = - = = - - -
4 Co-incident Spike 2 (. . o 2AE-3 3.7E-2 EJ l Pre-incident Spike 29.0 t.5C-3 2.0 E-2 45 j Small Line Break 27.0 3.0E-3 2.6E-2 1 )
^
Steam Generator Tube Rupture Co-incident Spike 1.6 6.8E-4 1.7E-2 4 l Pre-incident Spike 5.1 7.7E-4 1.8E-2 4 Rod Ejection Accident 12.0 1.1E-3 8.9E-3 4 Fuel Handling Accident 4.3 1.4E-2 8.3E-1 4 Locked Rotor Accident 19.0 2.1E-1 2.9 1,5 Loss of Auxiliary AC Power 8.0E-1 7.1E-5 2.7E-3 4 Waste Gas System Rupture Line Break --
3.1E-3 1.3E-2 1 Tank Rupture --
7.1E-4 1.3 4 DBA LOCA 14.3 1.7E-1 4.0E-1 3 l
Notes:
- 1. Control Room isolation by area radiation monitor signal based on a setpoint with a safety limit dose rate of 1 mrem /hr gamma in the Control Room.
/ ___---
- 2. an g o g ac n M*37mintrtes.,pc
- 3. Control Isolation actuated by CIB signal.
- 4. No action required.
- 5. Purge of Control Room atmosphere for a minimum of 30 minutes at 33,000 cfm no later than T=8 hr post-accident initiation.
- 6.
Reference:
ERS-SFL-93-0 .ro , F rES -C it- 95 -oo et 1 of 1 M%97 _
1 INSERT B
- 2. Isolation by manual operator action at T=30 minutes post-accident. In support of Altemate Repair Criteria for steam generators (ref. USNRC GL 95-05) the Main Steam Line Break thyroid doses were maximized within applicable limits in order to establish the maximum allowable accident-induced leakage against which tube leakage projections, based on voltage indications, are compared. Values shown are based on 11.75 gpm primary-to-secondary leakage (0-2 hour Exclusion Area Boundary thyroid dose limiting). See Section 14.2.5.1.3.
1 I
1 J
l
! l
. 1 u
l l
l l
1 1
. .. -_ . - - - - . - . - __ . - - - ~ . - -
l BVPS-1-UPDATED FSAR Rev. 5 (1/90)
J- ,
j '
' The sequence of events is shown in Table 14.2-2.
Radioloaical consecuences M$$I
' sThe source of radiation discharged to the environment from a stea l'ne rupture presumes a primary to secondary system leak. Te ab nce of such a leak precludes the discharge of any radioac ve mate al to the environment from the secondary system.
I For p oses of analyzing the environmental consequence of a J hypothesi d steam line rupture, it is assumed that a 10 gp primary i to seconda system leak rate exists simultaneously with ilibrium i
reactor coo nt activity due to 1 percent failed fuel. T is model is l very conserva ve since continued base load operation ith a 10 gpm
- primary to sec dary leak rate with 1 percent f led fuel is
- unlikely; howeve the activity values used reflect continued power operation. The logen activity, which is assu d to be released during the steam l'ne break, includes a redu lon factor of 10 resulting from expecte plateout.
Two mechanisms of seco ary coolant release o the environment are
- investigated. The firs case considers a main steam line rupture I upstream of the main str m -trip and no aturn valves (see Figure
. 10.3-1).
The second case presumes a ma stea line break downstream of the i main steam trip valve and extern t the leak collection structure.
l For this case, the activity relea is for 5 seconds duration which is the time before the main steam 1 e trip valve may be closed.
In the calculations, it has een co ervatively assumed that the
- secondary side pressure drops lmost instantaneously to atmospheric pressure and te primary a tem pressure decreases
- linearly to 350 psia fro 2,250 psia in 4 hours. This
- corresponds to a c oldown rato on the der of 50*F per hour.
heat removal At this time, the res ual. stem is placed in operation to continue cooling the reactor coo nt system. The reactor coolant stem pressure during this pe od is assumed to
!' be maintained const t at 350 psia. The resid 1 heat removal system is capable of cooling the react ~or coolant stem to less
, than 200*F in 4 hours. Eight hours following he accident the reactor coo ant pumps can be shut off and the rea or coolant
- system- pressu reduced to atmospheric. At this me, the 1 primary-to-sec ndary leakage drops essentially to zero. The eakage has been asumed. proportional to the square root o the l
primary-to- econdary differential pressure. The radioac(thvity i
- contained in the secondary side of the affected steam genera or l consists of the equilibrium concentration of ' fission produc
- accumul ted from an assumed operational primary to secondary leak o l I
J 5 i i
1
)
14.2-24
__ .. . . _ __ _ __.~.-_____._._._._ _._ _ _ . . . _ . _ _
T 4
INSERT C f Radiological Coasequences i i
The radiological consequences of a main steam line break (MSLB) were re-analyzed in support of 4
^
-the Alternate Repair Criteria (ARC) for steam generators (ref. USNRC GL 95-05)( *.The MSLB is of -
interest due to the rapid depre'ssurization of the secondary side and the high differential pressure across the steam generator tubes that can occur. Such conditions can result in accident-induced
- primary-to-secondary leakage. The ARC ailows steam generator tubes having defects to remain in ,
4 service with higher non-destructive examination (NDE) indications than would have been allowed
. under prior repair criteria, subject to conditions established in technical specifications. One such requirement is to project, on the basis of the NDE indication (voltage), the potential MSLB-induced j leakage (95% prediction with 95% confidence), and the offsite and control room operator doses that j could result. -
[ ~
In lieu of calculating the radiological consequence of this event with each operating cycle, an analysis was performed to establish a maximum allowable accident-induced leakage, against which
! the cycle leakage projections could be compared. This leakage rate is the maximum primary-to-l' secondary leakage that could occur with offsite and control room operator doses remaining within applicable limits. This re-analysis showed that the 30 rem 0-2 hour thyroid dose at the exclusion i area boundary was limiting with a projected leakage of 11.75 gpm. Since steam generator tubes i i' with NDE indications corresponding to potential leak rates greater than 11.75 gpm will be repaired, this is expected to be the bounding case for future operating cycles.
The MSLB is assumed to occur between the containment wall and the main steam isolation valve, resulting in an unisolable release path to the environment. This re-analysis was performed using the guidance of the. Standard Review Plan (SRP)" with two exceptions: (1) the dose calculation methodology (See Section 14B.8.5) is based on ICRP-26 and ICRP-30 principles rather than that described in the'SRP, and (2) the primary-to-secondary leak rate is the 95% prediction 95%
confidence leak rate projected on the basis of NDE indications rather than the value established by technical specification.
The analysis assumes that the unit is operating with technical specification primary and secondary j coolant specific activities, in conjunction with this snalysis, the reactor coolant system specific activity technical specification was reduced from if.i Ci/gm to 0.35 pCi/gm. A primary-to-secondary technical specification leakrate of 150 gpd is atsumed in all steam generators prior to the event and ;
in the remaining steam generators post-event. The thermodynamic analysis indicates that DNB is i not exceeded and, therefore, no fuel damage is projected..The analysis was performed assuming two iodine spike cases, pre-incident iodine spike, and a:cident-initiated spike (co-incident). Offsite power is assumed to be lost making the condenser unavailable for steam dump.
The release sources considered include: pre-event liquid and steam activity in all steam generaiors, primary-to-secondary leakage during the event. The release of primary-to-secondary leakage is assumed to continue for eight hours. Significant analysis inputs are listed in Table 14.2-8.
The 0-2 hour doses at the exclusion area boundary for the co-incident iodine spike case were 30 rem thyroid committed dose equivalent (CDE),0.11 rem effective dose equivalent (EDE), 0.04 rem skin dose equivalent (DE). The low population zone (LPZ) doses for the co-incident spike case were 18 rem thyroid CDE,0.04 rem EDE,0.02 skin DE. These co-incident iodine spike doses are a small fraction of the 10 CFR Part 100 guidelines are therefore acceptable.
~ .. _ _ . . _ . . _ . _ . _ _ . . . . . _ . _ . _ - . . _ . .
\
INSERT C (Continued) !
l The 0-2 hour doses at the exclusion area boundary for the pre-incident spike case were 46 rem thyroid CDE,0.05 rem EDE,0.03 rem skin DE. The LPZ doses for the pre-incident spike case were ,
9.5 rem thyroid CDE, <0.01 rem EDE, <0.01 skin DE. These pre-incident iodine spike doses are less !
than 10 CFR Part 100 guidelines are therefore acceptable.
The dose to control room operators was also assessed and is documented in Section 11.3. Isotopic releases to the environment are listed in Table 14.2-9 l
l I
l 1
. . ._ .. _.. . _ .. _ .._ _ . _ _ _ _ _ _ . _ _ _ _ ~ . _ _ _ _ . _ -
i BVPS-1-UPDATED FSAR Ray. 8 (1/90) l
} gpm, plus the fission product activity which is ad d during the l st ?.ine break accident. For this particular ca , it is assumed i the ontrolled discharged radioactive effluent released directly to the en onment.
1 The 2 hour do at the site boundary ,000 feet) assuming a ground
! level release is roximately 18 r to the thyroid and 0.06 rem to
- the whole body.
1
, The dose at the low populat boundary (3.6 miles) from the activity
! released during the dur on f the steam line break accident-(8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) is approximate 1.3 re o the thyroid and 0.01 rem to the j whole body.
- For the seco case, which assumes a steam ne break downstream of j the main s am trip valve, a total of 5,610 lb secondary coolant f escapes o. the environment before the . trip va closes. The ,
result g dose at the site boundary assuming a ground el release l is ess than 0.16 rem to the thyroid and a negligible do to the l le body. i 14.2.5.1.4 Conclusions l The analysis has shown that the criteria stated earlier in this section are satisfied.
t l Although DNB and possible clad perforation following a steam pipe I rupture are not necessarily unacceptable and not precluded in the
} criterion, the above analysis, in fact, shows that no DNB occurs for i any rupture assuming the most reactive assembly stuck in its' fully withdrawn position.
7 14.2.5.2 Major Rupture of a Main Feedwater Pipe I 14.2.5.2.1 Identification of-causes and' Accident Description feedwater line rupture'is defined as a break in a feedwater 4
A major pipe _large enough to prevent the addition of sufficient feedwater to the steam generators to maintain shell-side fluid inventory in the steam- generators. If the break is postulated in a feedline between the check valve and the steam generator, fluid from the steam
- generator may also be discharged through the break. Further, a break in this location could preclude the subsequent addition of auxiliary feedwater to the affected steam generator. (A break upstream of the feedline check valve would affect the nuclear steam supply system
- only as a loss of feedwater. This case is covered by the evaluation i in Section 14.1.8.)
the size of the break and the plant operating 4
Depending upon conditions at the time of the break, the break could causedischarge either a j
reactor coolant system cooldown (by excessive energy l Potential through the break), or a reactor coolant system heatup. secondary pipe from a reactor coolant system cooldown resulting Therefore, only the i rupture is evaluated in Section 14.2.5.1.
14.2-25 i
i BVPS-1-UPDATED FSAR xav. 12 (1/94)
References to Section 14.2 (CONT'D)
- 12. S. Altomare and R. F. Barry, "The TURTLE 24.0 Diffusion Depletion Code," WCAP-7758, Westinghouse Electric Corporation (September 1971) .
I
- 13. R. F. Barry, LEOPARD -
A Spectrum Dependent Non-Spatial '
Depletion Code for the IBM-7094." WCAP-3269-26, Westinghouse Electric Corporation (September 1963).
l- 14. " RADIOISOTOPE, A Computer Program for Calculating Residual l Activities in a Closed System After One or More Decay l
Periods," RP-1, Stone & Webster Engineering Corporation l (November 1972).
- 15. " ACTIVITY A Computer Program for Calculating Fission Product Activity in Fuel, Coolant, and Selected Tanks for a Nuclear l Power Plant," 'RP-3, Stone & Webster Engineering Corporation (January 1973).
- 16. "IONEXCHANGER, A Computer Program for Determining Gamma Activities in Ion Exchangers or Tanks as a Function of Time .
for Constant -Feed Activity," RP-2, Stone & Webster i Engineering Corporation (December 1972). I
- 17. M. S. .Baldwin, M. M. Merrian, H. S. Schenkle, and D. J. Van De Walle, "An Evaluation of Loss of Flow Accidents Caused by Power System Frequency Transients in Westinghouse PWRs,"
WCAP-8424, Revision 1, June 1975.
ci 3
- 18. DLC Calculation ERS-SFL--89-02 S ety Analysis of the Dose Consequences of a Locked Rotor Acc BVPS-1 with 18%
Fuel Failure -- EAB, LPZ, Control Ro , l994
- 19. ANSI /ANS-5.1-1979, "American National Standard for Decay
. Heat Power in Light Water Reactors," August 1979.
IHsERT P J l
(;
14.2-53
I INSERT D i 20. USNRC, " Voltage Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking", Generic Letter 95-05.
- 21. USNRC, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power
. Plants". NUREG-0800.
! 22. DLC Calculation ERS-SFL-95-008 r2, Safety Analysis of the Common Control Room, EAB, LPZ, Doses from a Main Steam Line Break Outside of CNMT at U1 with increased Primary-to-Secondary Leakage,1996.
1 I
BVPS-1 UPDATED FSAR TABLE 14.2-10 PARAMETERS USED IN MAIN STEAM LINE BREAK ANALYSIS Desian Case Power, MWt 2766 Offsite AC Power Lost Initial Primary Coolant Activity, Dose Equivalent 1-131, Ci/gm 0.35 initial Secondary System Activity, Dose Equivalent 1-131, Ci/gm 0.1 initial Primary and Secondary Isotopic Concentrations Table 148-15 Concurrent lodine Spike Appearance Rates Table 148-16 Pre-incident todine Spike Concentrations Table 148-16 lodine Spike Duration, hour 4 Primary-to-Secondary leak rate Pre-event, any SG, gpd 150 Affected SG, gpm 11.75 Post-event, each unaffected SG, gpd 150 Steam Generator Fluid Content Liquid, Ibm @ 97,900 l Steam, Ibm @ 6460 RCS Fluid Content, Ibm 390,000 i Steam Release from Affected SG, Ibm i 0-30 minutes 150,000 30 min-8 hrs 1300 Steam Release from Intact SG, Ibm 0-2 hours 366,776 2-8 hours 705,393 Duration of Release, hours 8 lodine Partition Factor Affected SG 1.0 intact SGs (initially) 1.0 Intact SGs (after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 0.01 Offsite x/Q Values, sec/m Tables 2.2-11a, 2.2-11b Control Room Volume, ft 173,000 Control Room Normal Intake, cfm 500 Control Room Isolation Manual Actuation at T=30 minutes Control Room Purge >T=8 hours 33,500 cfm for 30 minutes Control Room x/O Values, sec/m' Table 2.2-12 Dose Calculation Method Se.; tion 148.8.5 Analysis Reference ERS-SFL-95-008 r2
BVPS-1 UPDATED FSAR TABLE 14.2-11 MSLB ENVIRONMENTAL RELEASES. Ci Co-incident lodine Spike Case Nuclide 0-2 Hours Duration
, Kr-83m 1.8E-01 3.1 E-01 i
Kr-85m 1.1 E+00 2.7E+00 Kr-85 6.4E+00 2.5E+01 Kr-87 4.3E-01 6.3E-01
^
Kr-88 1.5E+00 3.2E+00 Kr-89 2.3E-03 2.3E-03 1
Xe-131m 6.3E-02 2.8E-01 Xe-133m 1.8E+00 7.9E+00 Xe-133 1.6E+01 7.7E+01 Xe-135m 1.1 E+01 1.4E+02 Xe-135 6.3E+00 1.9E+02 Xe-137 4.4E-03 4.4E-03
- Xe-138 6.7E-02 6.7E-02 1-131 5.4E+01 5.7E+02 1-132 7.7E+01 5.0E+02 1-133 1.2E+02 1.2E+03 1-134 8.5E+01 3.3E+02 1-135 9.9E+01 8.8E+02 i
Ref: ERS-SFL-95-008 r2 i
O i
n 1
I
BVPS-1 UPDATED FSAR TABLE 14.2-11 (con't)
MSLB ENVIRONMENTAL RELEASES Ci Pre-Incident lodine Spike Case Nyuclide 0-2 Hours Duration Kr-83m 1.8E-01 3.1 E-01 Kr-85m 1.1 E+00 2.7E+00 Kr-85 6.4E+00 2.5E+01 Kr-87 4.3E-01 6.3E-01 Kr-88 1.5E+00 3.2E+00 Kr-89 2.3E-03 2.3E-03 Xe-131m 6.5E-02 2.7E-01 Xe-133m 1.8E+00 7.2E+00 Xe-133 1.6E+01 6.7E+01 Xe-135m 9.3E+00 3.1 E+01 Xe-135 6.5E+00 5.8E+01 Xe-137 4.4E-03 4.4E-03 Xe-138 6.7E-02 6.7E-02 1-131 9.2E+01 3.4E+02 1-132 2.4E+01 4.6E+01 1-133 1.4E+02 4.7E+02 1-134 9.9E+00 1.2E+01 1-135 6.9E+01 1.9E+02 Ref: ERS-SFL-95-008 r2
- ~ - . . . -. . . . . - _ . - - - . ~ . __ . - - . - . - . . . - .. . - -
4 27?S-1-UPDATED FSAR Rev. 0 (1/82)
B' = boron concentration reduction rate by feed and bleed, ppm per second E = removal efficiency of purification cycle for nuclide 1 = radioc.ctive decay constant V = escape rate coefficient for diffusion into coolant 1 Subscript c refers to core 4
Subscript w refers to coolant Subscript i refers to parent nuclide 2 M S E R . T ,# ,
Subscript j refers to daughter nuclide 14B.5 TRITIUM PRODUCTION WITHIN A LIGHT WATER REACTOR j 14B.5.1 General - Overall Sources 4
- Within- a light water reactor, tritium is formed from several
] sources. The most abundant potential source ' in a PWR is the i
fissioning of the uraniun within the nuclear fuel, which yields tritium as a ternary fission product. Tritium atoms cre l l generated in the fuel at a rate of approximately 8 x 10 s atoms
~
per fission, or 1.04 x 10 2 curies per MWt per day. If there are any boron bearing control rods in the core, these can also be a potential source of tritium to the reactor coolant. These potential sources of tritium are only present in the reactor
- . coolant as they would diffuse through the fuel and control rod l i cladding.
l A direct source of tritium is the reaction of neutrons with I
- dissolved boron in the reactor coolant. Boron is used in the j reactor coolant for reactivity control in PWR. The boren '
concentration is approximately 1,000 ppm at the beginning of the cycle and is reduced to near zero at the end of core life.
Neutron reactions with lithium are also a direct source of
- tritium. Lithium is present in the reactor coolant for pH control, and as a product of boron reactions with neutrons. The amount of lithium present in the reactor coolant, however, is carefully controlled to approximately 2.2 ppm by
- demineralization. An extremely small amount of tritium is also 1
produced by neutron reactions with naturally occurring deuterium
., in light water.
4
- ~ The purpose of the following discussion is to review these sources in some detail as to their relative significance, and with respect to present operating experience.
i 14D-4
.r.. -,
INSERT E 148.4.1 Reactor Coolant and Secondary System Equilibrium Activities The reactor coolant activities tabulated in Table 148-6 are based on 1.0% failed fuel. While these activities were the basis of most design basis radiological analyses performed during original licensing, current analysis practice is to base many of these analyses on the primary and secondary equilibrium activities that correspond to the specific activity limits for reactor coolant and secondary coolant provided in technical specifications. Table 148-15 tabulates these equilibrium activities.
I 148.4.2 Reactor Coolant System lodine Spiking Two cases of iodine spiking are considered in current design basis radiological analyses. The first is the pre-incident spike which occurs such that the technical specification maximum 21 pCi/gm dose equivalent 1-131 concentrations are reached just prior to accident initiation. The second case is the iodine spike that is initiated by the accident transient (i.e., co-incident spike) For this case, regulatory practice requires analyses to include an iodine spike appearance rate that is 500 times the iodine ,
appearance rate that would result in RGS equilibrium concentrations equal to the 0.35 Ci/gm I technical specification. Table 14B-16 tabulates the pre-incident spike concentrations and the co- .
incident iodine spike appearance rates.
BVPS .-UPDATED FSAR Rev. 2 (1/84)
BR = Breathing Rate (cu.M/sec) Table 14B-ll DCFT (i) =
Dose conversion factor for radiciodine isotope, i, (rem /Ci) 14B 8.4 Dose Models for Realistic Case Under the realistic evaluation of the DBA LOCA, the whole body dose model is based on deep-deposition rather than surface energy deposition, tissues f61 including consideration of the attenuation by body The whole body dose model also includes the contri-butions from the radiciodines in the release.
14B.9 e
CONTAINMENT LEAKAGE MODEL - DBA CASE I8I e<see.TB This section describes the model used to estimate the quantity of radionuclides released to the environment by leakage from the containment building, using design basis assumptions. The realistic case leakage model is described in Section 14B.10.
14B.9.1 Radiciodine Figure 148-1 illustrates, schematically, the leakage model. The centainment free volume is assumed to censist of two regions: a sprayed region and an unsprayed region. The processes acting simultaneously on the activity in the unsprayed region are:
- a. Radioactive decay
- b. Leakage from containment
- c. Thermally induced exchange with sprayed region For the sprayed region, scavanging of iodine by chemical sprays is added to the list above. This scavanging is effective on elemental and particulate species of iodine. The chemical removal continues until the maximum spray decontamination facter (DF) is reached. This DF is based on the iodine concentration in the recirculation spray and the iodine partitioning factor.
The transport of radiciodi-nes in and between the two regions is modeled as a first order linear process. The activity in the sprayed region (subscript "s") and in the unsprayed region (subscript "u") is determined as a function of the removal processes identified above, Z, and the exchange between regions, E, by the following differential expression: l dA ( s) /dt = E (u) xA (u) -
Z(s)xA(s) dA (u) /dt = E(s)xA(s) -
Z (u)xA (u)
The activity released to the environment, 0, as a function of leakage, L, is given by:
.= .
l
{, - INSERT F ;
i i
.l- .
148.8.5 Updated Dose Calculation Models ;
i Commencing with analyses performed in 1995, the whole body-gamma dose, beta skin dose, and l 1 thyroid dose commitments described in Section 148.8.1 - 14B.8.4 have been calculated using the !
dose quantities described in this section. l
- . Effective Do'se Ecuivalent (EDE) as described in ICRP-2602). Replaces the traditional whole body )
j- gamma dose quantity. Like the whole body dose it replaces, the EDE model~ assumes that the
- receptor is immersed in a semi-infinite cloud. The EDE model estimates the dose to each organ in
- the body due to radiation from this cloud, applies a weighting factor to each organ dose, and sums i
- the weighted doses to obtain the EDE. '
j- D EDE = X/ O
- E(Oi xCEDE) i i i
, where:
Deos = Effective Dose Equivalent (EDE)
Q4 = Activity of nuclide i released i x/Q = Atmospheric dispersion factor
, = Dose conversion factor for nuclide i (DOE /EH-0070,1988)"')
CEDEi i
! For the control room dose analyses, the EDE is corrected to account for the finite volume of the control room using the method of Murphy-Campe":
i y0.338
- EDE)
DEDECR " 1173 i
! where: l j; D EDEcR = Effective Dose Equivalent (EDE) for control room
]
i' V = volume of control room, ft i
. Skin Dose Eauivalent (skin DE) as described in ICRP-26. Replaces the traditional beta skin dose-i quantity. Assumes that the receptor is immersed in a semi-infinite cloud.
i-
, D SKIN = X/ O
- E(O xi CSKIN ) 6 i
where:
l .DSMN = Skin Dose Equivalent (skin DE) l Qi = Activity of nuclide i released j x/Q = Atmospheric dispersion factor I CSKINi
= Dose conversion factor for nuclide I (DOE /EH-0070,1988)
I e
y -v- ,6-. , , - = ,,y y - ,m -
L. INSERT F (Continu:d)
L Thyroid Committed Dose Eauivalent (thyroid CDE) as described in ICRP-26 and ICRP-30"5) .
[ Replaces the traditional thyroid dose quantity based on the critical organ model of ICRP-2M used in TID 14844W DCDE thy
- X /O
- E(O xi CCDE x BR) 6 where:
D CDEt ny = Thyroid Committed Dose Equivalent (CDE)
Q, = Activity of nuclide i released x/Q = Atmospheric dispersion factor BR = Breathing rate 3.47E-4 m'/sec,0-8 hours 1,75E-4 m /sec,8-24 hours 2.32E-4 m /sec, >24 hours 3.47E 4 m'/sec,0-30 day control room analysis C CDE, = Dose conversion factor for nuclide i (USEPA FGR11,1988)"8) i l
1 l
f
l BVPS-1-Lesn.cs ESAR> Rev. 2 (1/84)
,a
! leakage through liner welds using this ultra conservative analysis is 80.12 ft3/ day (for BVPS-1). The results of the evaluation are presented in Table 14B-10. This analysis provides justification for the 50 percent conservatively effective SLCRS on BVPS-1.
14B.10.2 Release Model A single region model was used in the realistic case. This model used expressions similar to those in Section 14B.9.2, expanded to include removal by sprays for radiciodines. Figure 14B-1 illus-trates the release pathways.
TMSEA7~ dD l
l 14B-13
. _. .._._ . _.- . _ . . . _ . . _ . . . . _ . . _ ._ _.__ _ _ _ _ . _ _ . ~ . . _ . . _ _ _ _ _ . . _ _ _ _ _ . _ . .
, . INSERT G
-14B.11 Computer Programs 1
The following are brief descriptions of computer codes used to perform radiological analyses.
U ')
TRAILS _PC i
Program TRAILS _PC evaluates the transport of radioactivity from a source volume through one or ,
- j. two compartments to the environment and main control room. The program provides estimates of l activity released, doses, and dose rates. TRAILS _PC implements the dose calculation methodology described in Section 14B.8.5. TRAILS,.PC provides for direct modeling of co-incident iodine spiking as an independent production source. Decay progeny ingrowth can be modeled. The control room is modeled as a compartment with variable intake flow, filtration, and exhaust flow parameters.
TRAILS, an earlier variant, has similar capabilities with the exception of decay progeny ingrowth.
4' U
- ASCOT _PC "
L
- - Program ASCOT _PC models the transport of radioactivity released through the containment to the
- environment and main control room. ASCOT _PC is based on the program TRAll,S_PC, but t
provides for a two region (sprayed and unsprayed) modeling of the containment. ASCOT, an earlier 4
variant, has similar capabilities with the exception of decay progeny ingrowth.
l QADCG and QAD/CGGP_PC"
! These programs are variants of the QAD point kemel +1 ding program written at the Los Alamos Scientific Laboratory by R.E. Malenfant. The QADCG vemon implements a combinatorial geometry i i
method of describing problem geometry. The QAD/CGGP_PC version implements combinatorial !
i geometry and the geometric progression build-up factor algorithm. At BVPS, these codes are used
, only for photon shielding calculations.
1 I
i' j i.
i r
1 1
1 J
, , ,.,r _. - - . . . -
, BVPS-1-UPDATED FSAR Rev. 2 (1/84)
4 References to Appendix 14B
- 1. J. J. DiNunno, et. al, " Calculation of Distance Factors for Power and Test Reactor Sites," TID 14844, U.S. ?.tomic Energy Commission (March 1962).
- 2. M. E. Meek and B. F. Rider, " Summary of Fission Produce I Yields for U-235, U-238, Pu-239, and Pu-241 at Thermal Fission Spectrum and 14 MeV Neutron Energies," APED-5398, General Electric Corporation (March 1968).
- 3. D. F. Toner and J. S. Scott, " Fission Product Release for UO2 ," Nuclear Safety, Volume III No. 2 (December 1961).
- 4. J. Belle, Uranium Dioxide: Properties and Nuclear Applica-tions, Naval Reactors Division of Reactor Development,
, United States Atomic Energy Commission (1961).
- 5. A. H. Booth, "A Suggested Method for Calculating the Dif-fusion of Radioactive Rare Gas Fission Products From UO Fuel Elements," DCI-27, Atomic Energy Canada, Limited (1957).
- 6. D. C. Kocher, " Dose Rate Conversion Fators for External Exposure to Photons and Electrons", NUREG/CR-1918, August 1981.
- 7. ICRP, " Report of Committee II on Permissible Dose for Internal Radiation", ICRP-2, 1959.
- 8. DLC Calculation Package ERS-SFL-83-0 6 r-2, Ee-dMbl3s4 of )&A LecA,(9g4
- 9. DLC Calculation Package ERS-SFL-83-01 c 0, hhWe 6:54. less ofblmt kckt,1993
, 10. Phone memo between C. J. Code of Stone & Webster and Malvin Tower of Virginia Electric Power Company (March 20, 1973),
(5 / SEA 7" hO 14B-14
l INSERT H
- 11. USNRC, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power 1 Plants", NUREG-0800.
- 12. ' ICRP, " Recommendations of the International Commission on Radiological Protection", ICRP Publication 26,1977.
- 13. Kocher, DC, " External Dose-Rate Conversion Factors for Calculation of Dose to the Public", !
DOE /EH-0070,1988.
- 14. Murphy, K.G. 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.
{
- 15. ICRP, " Limits for intakes of radionuclides by Workers", ICRP Publication 30,1978. !
- 16. Eckerman, K.F., etal," Limiting Values of Radionuclide intake and Air Concentration and Dose )
Conversion Factors for Inhalation, Submersion, and Ingestion", EPA-520/1-88-020,1988.
- 17. DLC Calculation ERS-SFL-96-004 r1, TRAILS _PC: Transport of Radioactive Materialin Linear Systems, PC Version,1996.
- 18. DLC Calculation ERS-SFL-96-017 r1, ASCOT _PC: Assessment of Containment Transport, PC Version,1996.
- 19. DLC Calculation ERS-SFL-96-001 r1, QAD/CGGP_PC, a Point Kemel Photon Shielding Code i With Combinatorial Geometry and Geometric Progression Buildup Factors,1996. I
- 20. DLC Calculation ERS-SFL-96-012 r1, U1 RCS and Steam Generator Isotopic Concentrations, Pre-incident Spike Concentrations, and lodine Spike Appearance Rates Corresponding to 0.35 and 0.5 uCi/gm RCS Specific Activity,1996.
. ... . - . . . -.~.
9 t
4 BVPS-1 UPDATED FSAR TABLE 148-15 PRIMARY AND SECONDARY EQUILlBRIUM ACTIVITIES Correspondina to 0.35 uCi/am Dose Eauivalent I-131 in RCS* i 1
RCS Liquid Steam I Nuclide uCi/am uCi/am uCi/am }
Kr-83m 4.65E-02 4.53E-07 l Kr-85m 2.27E-01 2.21 E-06 Kr-85 1.20E+00 1.17E-05 Kr-87 1.30E-01 1.26E-06 Kr-88 3.46E-01 3.37E-06 Kr-89 1.09E 02 1.07E-07 Xe-131m 1.17E-02 1.14E-07 l l Xe-133m 3.33E-01 ' 3.25E-06 )
Xe-133 2.84E+00 2.77E-05 -l Xe-135m 1.18E-01 1.15E-06 )
Xe-135 3.48E-01 3.40E-06 Xe-137 1.77E-02 1.72E-07 Xe-138 7.28E-02 7.10E-07 l
1-131 2.72E-01 8.11 E-02 8.11 E-04 l-132 9.48E-02 1.44E-02 1.44E-04 l-133 4.24E-01 1.06E-01 1.06E-03
- l-134 5.93E-02 2.54E-03 2.54E-05 l-135 2.28E-01 3.88E-02 3.88E-04
- Steam generator liquid based on 0.1 pCi/gm D.E.1-131 in steam generator.
ref: ERS-SFL-96-012 r1
t
, BVPS-1 UPDATED FSAR >
TABLE 14B-16 RCS LODINE SPIKE ACTIVITIES Pre-incident Concentration, pCi/gm (Corresponding to 21 Ci/gm d.e.1-131) 1-131 16.3 1-132 5.69 l-133 25.4 l-134 3.56 l-135 13.7 Co-incident lodine Spike Appearance Rates, Ci/sec (500x Equilibrium Rate for 0.35' Ci/gm d.e.1-131) 1-131 0.49 1 1132 0.92 ;
l-133 1.10 l-134 1.34
'l-135 1.02 ;
4 i
ref; ERS-SFL-96-012 r1 - '
-i i
I 4