Text

Rev 1 to Assessment of Doses in Unit 2 CR Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel
	ML20195D022
Person / Time
Site:	Beaver Valley
Issue date:	01/26/1998
From:	Duranko M, Ireland R, Loinhardo A; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20195C985	List: L-94-014, Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression; L-98-195, Provides Response to RAI as Requested During 980924 Conference Call to Support Review of LAR 120.LAR Described Unreviewed Safety Question Resulting from Increase in Locked Rotor Accident Dose Consequences; ML20195D022;
References
	ERS-MPD-91-035, ERS-MPD-91-035-R01, ERS-MPD-91-35, ERS-MPD-91-35-R1, NUDOCS 9811170274
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& Am @y A9.621 Health Physics Department REVISION 1

2 3 Subject Assessment Of The Doses In The Unfr. 2 PAGE 1 OF A '

Control Room Due To A 1.ocked Rotor Accident At i

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@ RSC Reg'd RSC Not Reg'd Required Purpose To calculate the doses to the control room personnel resulting from the Locked Rotor Accident at Unit 2. Assumption of 187. fuel damage and the use of the new fuel is made. r,,,,.,, u 4 c {f3,(,/. g

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A Heatth Physics Department Resision 1 Table of Contents i

Purpose 1

Discussion 3

Methodology 3

Input Data / Assumptions 5

j i

Control Room Modeling, Dose Rate Evaluation 7

Control Room Modehng, Dose Evaluation 7

Calculation 8

1. Source Term Development t

2. Determine Transfer Lambdas 8

3. Calculation ofEAB Dose 9

4. Release Models 9

Results 10 Conclusion 11 References 12 Attachment's 1 - Revision 0 Dose Rate Evaluation Graph Deleted i

2. Revision 0 Dose Rate Evaluation TRAILS Printouts Deleted i

3. Revision 0 Dose Evaluation TRAILS Printouts Deleted

4. NUS ControlRoom X / Q Letter 14

5. Revision 1 Control Room Dose Rate Evaluation 17

6. Unit 2 LRA Source Term Development Table 18

7. Revision 1 Dose Evaluation TRAILS Printouts and Input Files 20

8. Revision 1 Dose Rate Evaluation TRAILS Printouts and Input Files 71 Appendices

1. Generic Control Room Modeling (rev.1) and Addendum 122

2. Determination of RCS Volume, S/G Liquid and Steam Volumes for DBA 133

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ERS-MPD-91-035 Page Health Physics Department Revision 1 DISCUSSION A

This analysis is made to document the Control Room (CR) dose estimate for a Locked Rotor Accident (LRA) at Unit 2. In addition, the offsite dose as a result of a LRA at Unit 2, previously documented in ERS-MPD-91-22 [Ref: 2], is documented.

This analysis is similar to that done for the Unit 1 LRA, documented in Reference [1] References

[1] and [2] should be consulted for further information concerning the background for this calculation. In revision 1 of this calculation, the information from References [1] and [2] required for this calculation is included.

As a result ofissues documented in Condition Reports 972304 and 972390 involving control room habitability, BVPS control room dose calculations were reevaluated. The reevaluation initially involved an identified non conservative fan flowrate assumption used in control room radiation dose calculations (i.e., maximum versus minimum control room emergency pressurization fan flowrate). Refer to Appendix 1, Revised Generic Control Room Modeling, rev.1 and Addendum.

A complete extent of condition re-review ofinput assumptions then identified several other prudent conservative changes to implement (i.e., RCS mass and steam generator liquid and steam masses) which were also factored into the BVPS dose calculations. Refer to Appendix 2, Determination of RCS Volume, S/G Liquid and Steam Volumes for DBA Radiological Calculation.

Subsequently, a test was conducted involving the complete discharge of the BVPS CREBAPS bottled air system. The test results suggested that the value used in the BVPS dose calculation for minimum possible CREBAPS air bottle discharge flowrate, which was previously thought to have been chosen as a conservatively low value, may not have been chosen to be low enough to bound all possible conditions.

As a result, the Control Room and offsite doses post BVPS-2 Locked Rotor Accident were recalculated. In addition to the control room ventilation parameters that were changed, the Reactor Coolant System (RCS) and Steam Generator (SG) volumes used in this calculation were changed to the bounding values provided in Appendix 2. These changes resulted in the recalculation of source terms, release lambdas, control room filter efficiency and the control room radiation monitor alarm time. All are documented as part of this revision. The revised EAB and LPZ X/Q values (ERS-SFL-96-21, Ref: 22) where used to calculate offsite dose. Finally Control Room Occupancy Factors and Progeny Ingrowth were used during the recalculation of all doses.

METHODOLOGY This analysis will be performed using the TRAILS code documented in Reference [23]. TRAILS is a simple FORTRAN program that mechanizes the solution of first order linear equations and A

dose calculations. Although the code was originally dccumented in detail in Reference [3], the more recent PC version used is documented in Reference [23].

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ERS-MPD-91 -035 me Health Physics Department Revision 1 I

The code implements a model of the release that incorporates one or two compartments (or nodes) prior to the release to the environment. The transport of radioactive material through the system is governed by simple first order linear equations based on the postulated flow rates and 4

1 the radionuclide decay constants.

A The TRAILS-PC program provides several options for calculations. The offsite dose calculational methods used are those provided in Regulatory Guide 1.4 [Ref: 4]. Thyroid dose conversion factors and breathing rates are those provided in TID 14844 [Ref: 5] and Regulatory Guide 1.4.

l The 0-2 hour EAB doses and the 0-8 hour LPZ doses are evaluated. The release modeling that is utilized is similar to that used by SWEC in the evaluation in References 8 and 9 and by DLC in l

Reference 1. In that analysis, SWEC performed an evrJuation of Control Room doses due to a

)

locked rotor accident at Unit 1 in order to meet Unit 2 licensing commitments, assuming no fuel failures.

i The Control Room is treated as a compartment with variable (by time step) :ntake, filtration, X/Q, breathing rate, and exhaust rates. For this analysis the duration Control Room doses (30 days) will be analyzed.

Since the Control Room doses are sensitive to the timing of Control Room isolation initiated by area radiation monitors, an evaluation of the Control Room dose rate at various times post-accident is assessed first.

Based on these results, an isolation time is postulated and included as an analysis assumption during evaluation of Control Room dose over the duration of the accident.

The analyses address the following release components:

1.

Release ofiodine activity from the three steam generators due to technical specification primary-to-secondary leakage. Iodine partitioning is assumed. The activity is based on 18%

fuel clad failure, with the fuel clad activity based on Standard Review Plan [Ref: 10]

assumptioris (i.e.,30% Kr-85,10% all others), with the exception ofI-131, which is assumed to be 12% in keeping with the conclusions of NUREG/CR-5009 [Ref: 12].

2.

Same as #1, but for noble gases with no credit for partitioning.

A 3.

Case 3 assessed the release of activity into the RCS and hence to the three steam generators by an iodine spike that occurs concurrent with the locked rotor. This case is eliminated in revision 1. Release of radioactivity, specifically iodine, from fuelis accounted for in case 1 in the assumption of 18 % fuel clad failure. Assuming a concurrent iodine spike is redundant. Using case I to account for fuel as a source term is bounding, in that the dose consequence of case 1 is larger than that of case 3.

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Release of the initial activity contained in the steam in all three steam generators at time = 0.

This activity based on technical specifications.

5.

Release of the initial activity ofiodine contained in the secondary liquid in all three steam generators at time = 0. (Noble gases are assumed to be in the steam space). This activity i

based on technical speci6 cations.

Releases from steam generators are based on the steam mass releases described in References 11 and 16.

INPUT DATA / ASSUMPTIONS 1.

General Methodology Based On SRP 15.3.3-15.3.4

[10]

2.

Core Inventory From Table 11.1-1 Based On 2766 MWt

[11]

3.

Core-Gap Fractions Kr-85 0.30

[10]

I-131 0.12

[12]

Other 0.10

[10]

The assumptions ofReferences 10 and 12 are included, even though they are not specifically applicable to a locked rotor accident. This is conservative.

4.

Fraction OfRods In DNB = 18%

[13]

5.

Fraction ofRods Assumed Failed = 18% (Section 15.3.3)

[10]

g Inputs 6 and 7 were inputs for Case 3 and are deleted. Case 3 (concurrent iodine spike)is eliminated in revision 1. Release of radioactivity, specifically iodine, from fuel is accounted for in case 1 in the assumption of 18 % fuel clad failure. Assuming a concurrent iodine spike is redundant. Using case 1 to account for fuel as a source term is bounding, in that the dose consequence of case 1 is larger than that of case 3.

8.

RCS Volutne = 3.5IE+5 lbm (Appendix 2) 9.

RCS Primary-To-Secondary Leakage = 1 gpm Total (Tbl.15.3-3)

[11]

10. Steam Generator Mass (Appendix 2)

Liquid = 92000 lbm Steam = 7190 lbm A

NOTE: Appendix 2 provides RCS, SG liquid and SG steam mass value ranges with the bounding value to be used. Sensitivity testing reveals that the minimum RCS and SG liquid volumes and the maximum SG steam volume are the bounding parameters for this calculation.

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Steam Generator Mass Release (Tbl.15.3-3)

[11, 16]

l 0-2 hours = 443,878 lbm 2-8 hours = 793,664 lbm

12. Iodine Partitioning In Steam Generators = 0.01 (Tbl.15.3-3)

[11, 16]

13. Duration Of Plant Cooldown By Secondary System (Tbl.15.3-3)

[11, 16]

i.e., duration of release = 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

14. X/Q Values For The Control Room (sec/m')

[14]

0-8 hr - 1 WE-4 24-96 hr - 5.96E-5 l

8-24 hr - 7.86E-5

%-720 hr - 3.76E-5

15. Control Room Volume: 1.73E5 cu.ft. (Sec. 6.4)

[11, 16]

l

16. Control Room Normal Intake: 500 cu.fl./ min. (Sec. 6.4)

[11, 16]

300 cu.ft./ min. From Unit 1 And 200 cu.ft./ min. From Unit 2 d

17. Control Room Pressurization Rate:

Fan - 1030 cu.fl./ min.

(Appendix 1)

Bottles - 600 cu.ft/ min.

i Note: A bounding value of 0 cu.ft./ min. was used for Bottles in this calculation.

l

18. Control Room Infiltration: 10 cu.ft./ min. (Sec. 6.4)

[11]

19. Control Room Filter Efficiency: 95%

[15, 16]

A To account for the filter bypass indicated in Item 18, this is modified by:

1030(0.95) + 10(0) = 0.94 1030 + 10

20. Control Room Purge Flow: 16900 cu.ft./ min.

(Appendix 1)

21. PurgeInitiation At 8 Hours

[11]

22. Purge Duration 0.5 Hours

[9]

8

23. Control Room Occupancy Factors:

[10]

0 -1 day 1.0 1 - 4 days 0.6 4 - 30 days 0.4

24. Receptor Distances (Tbl.15.0-11)

[11]

EAB = 547 meters i '

LPZ = 3.6 miles (5794 meters) l I

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A ERS-MPD-91-035 pase Health Physics Department Revision 1 A

25. X/Q Values for EAB and LPZ (sec/m')

[22]

0-2 hours EAB 1.25E-3 0-8 hours LPZ 6.04E-5 8-24 hours LPZ 4.33E-5 l

1-4 days LPZ 2.10E-5 4-30 days LPZ 7.44E-6 CONTROL ROOM MODELING. DOSE RATE EVALUATION l

For the dose rate evaluation, the Control Room intake and exhaust are set to 500 cu.ftlmin., with l

no filtration. Time steps selected were based on trial calculations which identified the most likely times for the dose rate to reach the safety limit of 1 mR/hr. Note that this value is different than the alarm setpoint of the Control Room monitors. This is explained in Reference [17].

A A graph of control room dose rate versus time based on TRAILS runs performed using the l

parameter changes noted is included in Attachment 5. The TRAILS print outs and input files are I

also included in Attachment 8.

The chart shows that the safety limit of l mrem / hour is reached at about 1700 seconds after the start of the accident. Note that the control room dose rate is evaluated in dose equivalent units of mrem /hr. However, since the monitor detects photons the difference between mR and mrem is considered negligible. With the addition of the 155 second response delay time [Ref: 18], the time to automatic control isolation is 1855 seconds. Since it is reasonable to assume operator i

manual actions after 30 minutes (1800 seconds), it will be assumed that the operators will manually initiate isolation at T = 30 minutes CONTROL ROOM MODELING. DOSE EVALUATION In order to be consistent with the results above, the Control Room isolation was assumed to occur at 1800 seconds or 30 minutes.

A i

For the one hour period after isolation the only intake is the unfiltered 10 cu.ft/ min. infiltration.

The exhaust is equal to 610 cu.fl. / min, but the doses are calculated with the exhaust equal to the infiltration rate of 10 cu.fl. / min, a bounding condition.

At one hour following isolation, the Control Room ventilation realigns for filtered intake up to 1030 cu.ft/ min (Appendix 1). This is added to the 10 cu.ft/ min. infiltration to yield 1040 cu.ft/ min. exfiltration. This ventilation continues until eight hours after the start of the accident.

At eight hours a Control Room purge is initiated. It continues until 8.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months at which time the normal system arrangement is restored.

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1lealth Physics Department Revision 1 CALCULATION th

1. Source Term Development documents the development of the source terms used for the different cases involved with the locked rotor accident. All of the input data and calculations are summarized in tabular fonn.

The gap activity is calculated from the core inventory values provided in Table 11.1-1 of the Unit 2 UFSAR [Ref: 11], using the core-gap fractions provided as input Item # 3. The gap activity is used as the basis for RCS activity rather than UFSAR Table 11.1-2 as the latter is based on equilibrium activity (i.e., credit for letdown cleanup). The instantaneous increase is modeled herein. The 18 % gap release is determined from the gap activity as follows:

18 % F.F. gap release (Ci) = gap activity x 0.18 i

This analysis assumes that the gap release is instantaneously and homogeneously dispersed throughout the RCS. The initial technical specification (TS) concentration (uCi/gm) in the RCS is converted to activity in Ci and added to the gap release activity to obtain the total activity available for release via a primary to secondary leak.

NOTE: In this analysis, reference is made to TS concentrations in the RCS and the SGs. The BVPS-2 TS [Ref: 19] do not providc isotopic limits, but rather specify dose equivalent iodine (DE-I-131) concentration of 1.0 uCi/gm in the RCS and 0.1 uCi/gm in the SGs.

Isotopic values that equate to these limits were developed by SWEC for the control room habitability effort in Reference 20. These isotopic values will be referred to as the "TS concentrations" in this package. Their derivation is detailed in Attachment 6.

The TS activities (Ci) for the RCS liquid, the SG liquid and the SG steam, for each radionuclide, are calculated as follows: Note the factor of 3 included in SG calculations represents 3 SGs.

TS RCS (Ci) = TS Conc. (uCi/gm) x 3.51E+5 lbm x 453.59 gm/lbm x 1E-6 Ci/uCi TS SG liquid (Ci) = TS Conc. (uCi/gm) x (3 x 9.20E+4 lbm) x 453.59 gm/lbm x 1E-6 Ci/uCi TS SG steam (Ci) = TS Conc. (uCi/gm) x (3 x 7.19E+3 lbm) x 453.59 gm/lbm x IE-6 Ci/uCi

2. Determine Transfer Lambdas The RCS leak rate lambda is calculated as follows:

RCS A = (1.0 g:1/ min x 1/60 min /sec x 8.34 lbm/ gal) / 3.5IE+5 lbm = 3.960E-7 sec

The SG release lambdas are calculated as follows: The 0.01 is the iodine partitioning in the SG factor and is applicable since the partitioned iodine remains in the SGs.

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IIcalth Physics Department Revision 1 b

4 SG A (0-2 hr) = (((443878 lbm / 2 hr) x 1/3600 hr/s) / (3 x 9.20E+4 lbm)) x 0.01 = 2.234E-6 s S'G A (2-8 hr) = (((793664 lbm / 6 hr) x 1/3600 hr/s) / (3 x 9.20E+4 lbm)) x 0.01 = 1.331E-6 s d

The 0-2 hr value will be used as the base value. The multiplier for the 2-8 hr period is calculated as follows:

1.331E-6 / 2.234E-6 = 0.596 To model the initial steam release as a puff, the release lambda for this case was taken as 1.285E-4 3 s. This was based on a SWEC assumption of 99.99% of the release being complete by 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (0.0833 days). However, it was subsequently decided to increase this by a factor of 100, since initial code runs showed significant activity remaining in the steam generator at time = 2 hrs. The original was calculated as follows:

N = N* e*, where N = activity remaining at time t and N* is starting activity in(N/N') = -At in((1.0 - 0.9999) /1.0) = -0.0833 days x A A = 111 day" = 1.285E-3 s4 i

d 4

The final value is then 1.285E-3 s x 100 = 1.285E-1 s

3. Calculation ofEAB Dose All of the TRAILS runs used LPZ X/Q values as inputs. The EAB 0-2 hour dose is calculated by multiplying the LPZ 0-2 hour doses by the ratio of the EAB 0-2 hour X/Q value / LPZ 0-8 hour X/Q value. The ratio is:

1.25E-3 / 6.04E-5 = 20.70

4. Release Models NOTE: In this package, the terms "model" and " case" are used to denote components of the overall solution, rather than an alternative solution. The total consequence is the sum of the consequences of the individual models or cases.

The total calculation is broken down into parts or cases which correspond to different swse and release parameters. These cases are:

1. TS leakage ofiodines into the 3 SGs from the RCS. The RCS is modeled as compartment I and the 3 SGs together are modeled as compartment 2. Transfer lambdas determined above are used. SG lambdas were reduced by a factor of 100 to account for partitioning. The RCS I

release is modeled at a constant rate for 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months , while the SG release is halted at 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The source term was taken from Column P of Attachment 6.

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ERS-MPD-91-035 me 10 Health Physics Department Roision 1 A

= 2. This case evaluates the TS leakage of noble gases from the RCS to the SGs. Since no holdup of noble gases is assumed in the 3 SGs, the release is modeled as being directly from the RCS l

to the environment. The RCS is modeled as compartment 2 (Compartment 1 is not used.)

The RCS transfer lambda determined above is the basis for the release. The release is halted after 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months The source term was taken from Column P of Attachment 6.

3. Case 3 is deleted in revision 1 since case 1 accounts for fuel iodine.

4. This case evaluates the release of the initial activity in the steam space of all 3 SGs. The SGs j

are modeled as compartment 2.- (Compartment 1 is not used.) The activity in the steam space L

is as shown in Column L of Attachment 6. The release duration is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

l

5. This final case evaluates the release of the initial activity in the secondary liquid in all 3 SGs.

L The SGs are modeled as compartment 2. (Compartment 1 is not used.) The activity in the secondary liquid is as shown in Column K of Attachment 6. The release duration is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SG transfer lambdas are reduced by a factor of 100 to account for partitioning inside the SGs.

1 The addition of the Control Room to the calculation is accomplished by insertion of suitable L

parameters for the flows, volumes, fdtration rates, and X/Q values. The Control Room X/Q parameters were determined by NUS Corporation using the methodology in Reference [14].

A The TRAILS print outs and input files are included in Attachment 7.

l RESULTS A

The results of the 4 cases are as follows. The dose from Case 3, as noted in the Methodology section, was not calculated in revision 1.

Control Room Doses - Duration Results (rev. 0)

Results (rev.1)

Thymid Photon Beta Thyroid Photon Beta Case (mrem)

(mrem)

(mrem) 1 1.07E+03 6.23E-02 4.31E-01 1.63E+03 1.37E-01 1.56E+00 2

0.00E+00 1.07E+01 1.48E+02 0.00E+00 1.59E+01 2.20E+02 L

3 7.39E+00 5.16E-04 3.41 E-03 0.00E+00 0.00E+00 0.00E+00 4

4.44E-01 1.74E-05 1.23E-04 4.83E-01 2.12E 1.84E-04 L

5 3.58E+00 1.34E-04 1.08E-03 3.78E+00 1.60E-04 1.48E-03 Total 1.08E+03 1.08E+01 1.48E+02 1.63E+03 1.60E+01 2.22E+02 Total (rem) 1.08E+00 1.08E-02 1.48E-01 1.63E+00 1.60E-02 2.22E-01 L

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LPZ Doses 0 -2 hours Previous (ERS-MPD-91-022, ri) Results Revised (ERS-MPD-91-035, ri) Results Thyroid Photon Beta Thyroid Photon Beta Case (mrem)

(mrem)

(mrem) 1 1.59E+03 3.64E+00 1.02E+00 1.75E+03 4.08E+00 1.16E+00 2

0.00E+00 1.64E+02 1.02E+02 0.00E+00 1.68E+02 1.04E+02 3

3.80E+00 1.15E-02 3.04E-03 0.00E+00 0.009+00 0.00E+00 8

3.26E-01 3.60E-04 1.15E-04 3.03E-01 3.19E-04 1.27E-04 5

7.12E+00 6.43E-03 2.42E-03 6.08E+00 5.59E-03 2.10E-03 Total 1.60E+03 1.67E+02 1.03E+02 1.76E+03 1.72E+02 1.05E+02 Total (rem) 1.60E+00 1.67E-01 1.03E-01 1.76E+00 1.72E-01 1.05E-01 EAB 0 - 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Doses (mrem)

Ratio's Thyroid Photon Beta Revised 20.70 3.63E+04 3.55E+03 2.18E+03 Previous 20.37 3.25E+04 3.41 E+03 2.09E+03 LPZ 0-8 hour Doses Previous (ERS-MPD-91-022, ri) Results Revised (ERS-MPD-91-035, r1) Results Thyroid Photon Beta Thyroid Photon Beta Case (mrem)

(mrem)

(mrem) 1 1.43E+04 1.84E+01 6.15E+00 1.57E+04 2.11 E+01 7.45E+00 1

2 0.00E+00 3.29E+02 2.11 E+02 0.00E+00 3.37E+02 2.16E+02 3

1.16E+02 1.93E-01 6.04E-02 0.00E+00 0.00E+00 0.00E+00 4

3.26E-01 3.60E-04 1.15E-04 3.03E-01 3.19E-04 1.27E-04 i

5 1.89E+01 1.45E-02 5.79E-03 1.61E+01 1.27E-02 5.17E-03 Total 1.44E+04 3.48E+02 2.17E+02 1.57E+04 3.58E+02 2.23E+02 Total (rem) 1.44E+01 3.48E-01 2.17E-01 1.57E+01 3.58E-J1 2.23E-01 CONCLUSION The dose limits in GDC 19, Reference [21] and the Standard Review Plan, Reference [10), for the Control Room are :

Whole Body gamma -

5 rem Thyroid -

30 rem Beta Skin dose -

30 rem A

The recalculated Control Room doses as the result of a Locked Ro or Accident are increased over the previously calculated numbers. However, the results are still well below the limits in GDC 19

[Ref: 21]. Both the EAB and the LPZ doses increased over the previously calculated numbers.

However the results are a fraction of the allowable doses in 10CFR100.

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Health Physics Department Revision 1 REFERENCES l

1.

ERS-SFL-89-021, Safety Analysis OfThe Dose Consequences Of A Locked Rotor i

Accident At BVPS-1 With 18% Fuel Failure - EAB. LPZ. Control Room,1989 2.

ERS-MPD-91-022, Offsite Dose Consequences Of A Locked Rotor Accident At Unil 2 With 18% Failed Fuel 3.

DLC, Calculation ERS-SFL-089-020, TRAILS: Transport Of Radioactive Material In Linear Systems.1989 4.

NRC, Assumotions Used For Evaluatine The Potential Radiological Consequences Of A Loss Of Cooiant Accident For Pressurized Water Reactors. Regulatory Guide 1.4,1974 4

5.

USAEC, Calculation Of Distance Factors For Power And Test Reactor Sites. TID-14844, 1962 6.

ORNL, DRALIST: Radioactive Decay Data For Aeolication To Radiation Dosimetry And Radiological Assessments. DLC-80,1981 7.

D. C. Kocher, Radioactive Decay Data Tables. DOE /rIC-11026,1981 8.

SWEC, Calculation 12241-UR(B)-449, Doses In The BV1 And BV2 Combined Control Room Due To A Locked Rotor Accident And A Loss OfNon-Emergency AC Power To Sjation Auxiliaries Accident At Unit 1 With 500 cfm Normal Ventilation.1987 i

9.

SWEC, Calculation 12241-UR(VB)-456, Combined BVl-BV2 Control Room Habitability Due To Desien Basis Accidents fExcept LOCA) At BVI,1987

10. NRC, Standard Review Plan For The Review Of Safety Analysis Reports For Nuclear Power Plants. LWR Edition. NUREG-0800,1984

11. DLC, Unit'2 Updated Final Safety Analysis Report

12. NRC, Assessment Of The Use Of Extended Burnup Fuel In Light Water Power Reactors, NUREG/CR-5009,1988

13. Westinghouse, ltr 89DL*-G-0055, dtd 7/13/89, Rods In DNB For Locked Roto Event l

14. Halliburton NUS Environmental Corporation ltr ARP-91-444, dtd 10/8/91, Control Room l

X/O Values For BVPS (Attachment 4) l

15. USNRC, Safety Evaluation Report, related to the operation of BVPS, Unit 2

RTL: n/a Form: RE 1.103 3 9/91 h

D a

ERS-MPD-91-035 m

(3 Health Physics Department Revision i d

16. DLC, BVPS - Units 1 and 2 Joint Control Room Radiation Dose Analysis - DCP 611 CWO 942. Lir ND1NEM:1144 dtd 4n/87

17. SWEC, Calculation 12241-UR(B)-272-0, Control Room Area Radiation Monitor Alarm Set Point with Control Room Purcing 81.rs. following Event,1985

18. DLC, Calculation ERS-SFL-93-005, !;afety Analysis of Conseauences of Control Room Damoer Response Delav (Limitorque 10 CFR 21) -- Unit 1 Accidents.1993

19. DLC, Unit 2 Technical Specifications

20. SWEC, Calculation 12241-UR(B)-233-1, BV2 Tech Spec Primary Coolant And Secondary Side Concentrations - Using TID 14844 Iodine Dose Conversion Factors,1983

21. USNRC, Criterion 19. Title 10 Code of Federal Regulations Part 50, Appendix A

22. DLC, Calculation ERS-SFL-96-021, RG 1.145 Short-Term X/O Values for EAB and LPZ.

U1 and U2. Base On 1986 - 1995 Observations.1996

23. DLC, Calculation ERS-SFL-96-004, TRAILS __PC Transport of Radioactive material In Linear Systems. PC version v1.0,1996

RTL: n/a Fonn: RE 1.103 3 9/92 n =ne @

ERS-MPD-91-035 pase h'

~ Health Physics Department Revnion !

ATTACHMFNT4 l

- du HALLIBURTON NUc. -

i<

a.; i.. %.,

~

'M/ Environmental Corporation

.snetu m u u m n v., s,.s... e :

8. st Dil k %Mt str a M su g l g%!,

. m, :......

I\\\\ bi

s.

4.s ARP-91-444 (50tober 8, 1991 Mr. Steve La Vie Duquesne. Light company Beaver Valley Power Station P.

O.

Box 4 Shippingport, PA 15077

Subject:

Control Room X/Q Values for BVPS

References:

1)

RALLIBURTON NUS Proposal No. P8808227 2)

Duquesne Light Company Purchase Order No.

D068239 3)

Telecon From S. La Vie to M. Septoff August 9, 1991 4)

Letter from J. Ramsdell to M.

Septoff August 15, 1991

Dear Steve:

This letter presents the X/Q values guitable for design basis accident releases from selected plant vents to the BVPS common control room intake. The methodology used is presented by Ramsdell in N" REG /CR-5055 as modified by NUREG/CP-0116, by discussions with Ramaiell in September 1991 (Refere.nce 4) and a paper presented in Atmeapheric Environment, Volume 24B, No. 3, pp 377-388, 1990. The work was performed in accordance with the descriptlon contained in Reference 3 as approved by reference 2.

It is noted that all work was performed using approved project procedures in accordance with the HALLIBURTON NUS ESD Quality Assurance Manual, Revision 6.

. Tables 1 and 2 presents the X/Q values for the selected plant vents for~ Unit 1 and Unit 2, respectively, for averaging periods of 0-8 hours, 8-24 hours, 1-4 days, and 4-30 days.

The release points, distances'and directions to the common control room intake, and building cross sectional areas were those provided in an analysis performed by Stone and Webster Corporation using the Murphy and Campe methodology.

Duquesne Light Company provided this information to us on September 6,

1991.

Five years of meteorological data for the period January 1986 through December 1990 were used.

Results of the Murphy and Campe methodology are also presented in the tables for comparison.

It is seen that, for the 0-8 hr averaging period reductions in X/O values as compared to those obtained using the Murphy and Campe methodology range from a factor of 2 to over an order of magnitude, trehorroleo. goc.s airst sen is c.s fuor a e learico.iro.I sater ss o.:Ist I

__.m

.. ~._- _ _.

RTL: n/a Form: RE 1.103-3 9/92 N kWD ERS-MPD-91-035 mse /f lleakh Physics Department Revision 1 ATTACHMFNT 4 Mr. Steve La vie ARP-91-444 October 8, 1991 Page 2 A report describing the methodology and results with a comparison with the Murphy and Campe methodology suitable for presentation to j'

the' NRC will be prepared. The computer code and its documentation l

will be provided with the report.

Further, as we discussed, a scientific paper could also be prepared suitable for presentation

.at a DOE /NRC Nuclear Air Cleaning Conference.

As part of MALLIBURTON NUS Quality Assurance procedures a Division Quality Assurance Review Board (DQARB) was convened to review the technical and quality aspects of the analysis. The results of the l

DQARB indicate that (1) the docu=entation for the computer code generated for the analysis should be revised to provide additional information related to code identification and its use, and (2) the need to clarify the relationship between the test cases and the hand calculations used to verify the correct operation of the code.

Therefore, the results provided in ti a tables should be considered as preliminary until the DQARB approves, 3.e documentation, receives I

the clarification, and completes its review. It is expected that this will be completed early next week.

If you have any questions please call me.

Sincerely, D

Michael Septoff Project Manager Enclosures cc:

A. Toblin i

W. McIntire 1

l l

i l

l

~ ~.. -.. - -..

-- -__~ _. _

_ ~. -... _

.~.-

RTL: n/a Fonn: RE 1.103-3 9'92

) (Dxp=me Lk)t ERS-MPD-91-035 Pase

//

Ilealth Physics Department Revision 1 ATT ACHAENT 4 TABLE 1 DESIGN BASIS ACCIDENT X/Q VALUES (sec/m3) FOR SELECTED BVPS PLANT VEtITS TO THE COMMON CONTROL ROOM INTAKE - UNIT Release Point Methodology 0-8 hr 8-24 hr 1-4 day 4-30 day Containment Ramsdell 4.33E-4 2.04E-4 1.46E-4 8.84E-5 Edge Murphy-Campe 2.88E-3 1.90E-3 6.62E-4 1.41E-4 Containment Ramsdell 2.73E-4 1.28E-4 9.17E-5 5.57E-5 Top Murphy-Campe 2.51E-3 1.66E-3 5.77E-4 1.23E-4 Auxiliary Ramsdell 4.30E-3 2.01E-3 1.49E-3 9.25E-4 Building Murphy-Campe 8.24E-3 6.01E-3 2.32E-3 6.18E-4 Main Ramsdell 7.60E-4 3.51E-4 2.59E-4 1.58E-4 Steamvalve Murphy-Campe 2.97E-3 1.94E-3 6.92E-4 1.54E-4 Service Ramsdell 6.25E-4 3.04E-4 2.36E-4 1.57E-4 i

Building Murphy-Campe 7.47E-3 5.09E-3 1.88E-3 4.93E-4 Turbine Ramsdell 2.43E-3 1.22E-3 8.90E-4 6.26E-4 Building Murphy-Campe 7.81E-3 5.55E-3 2.11E-3 7.11E-4 Gas Waste Ramsdell 5.11E-4 2.15E-4 1.65E-4 1.14E-4 Storage' Murphy-Campe 2.03E-2 1.51E-2 5.99E-3 1.32E-3 Vault u.

l TABLE 2 DESIGN BASIS ACCIDENT X/Q VALUES (sec/m3) FOR SELECTED

)

BVPS PLANT VENTS TO THE COMMON CONTROL ROOM INTAKE - UNIT 2 Release Point Methodology 0-8 hr 8-24 hr 1-4 day 4-30 day Containment Ramsdell 1.8BE-4 9.32E-5 7.06E-5 4.18E-5 Edge Murphy-Campe 4.16E-3 2.81E-3 1.09E-3 1.58E-4 containment Ramsdell 1.20E-4 5.91E-5 4.45E-5 2.64E-5 Top Murphy-Campe 3.65E-3 2.47E-3 9.56E-4 1.39E-4 Auxiliary Ramsdell 1.04E-3 5.15E-4 4.04E-4 2.46E-4 Building Murphy-Campe 1.33E-2 9.30E-3 3.94E-3 1.20E-3 Main Ramsdell 1.59E-4 7.86E-5 5.96E-5 3.76E-5 Steamvalve Murphy-Campe 7.75E-3 5.63E-3 1.99E-3 3.26E-4 l

l Service Ramsdell 2.21E-4 1.11E-4 8.51E-5 5.17E-5 Building Murphy-Campe 5.42E-3 3.62E-3 1.43E-3 3.31E-4

~

l Turbine Ramsdell 2.72E-4 1.43E-4 1.10E-4 6.30E-5 Building Murphy-Campe 6.46E-3 4.90E-3 2.00E-3 5.75E-4 Cas Waste Ramsdell 1.74E-3 9.36E-4 7.69E-4 5.55E-4 Storage Murphy-Campe 1.23E-1 1.04E-1 5.08E-2 2.00E-2 Vault l

HALLIBURTON NUS I

I

.i

RTL: n/a Form: RE 1.103 3 9/93

% (DS"'S udi ERS-MPD-91-035 5*8*

d Health Physics Department Revision 1 A

Control Room Dose Rate Evaluation Control Room Dose Rate as the Result of Unit 2 LRA 1.4 i

1.2 be

/

Gl~i"

/

0.4 c'

s

/

O 0.0 0

200 400 000 800 1000 1200 1400 1000 1800 2000 2200 2400 2000 Time (seconds)

Case 1 Case 2 Case 4 Case 5 Total Time Photon Photon Photon Photon Doserate seconds mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem /hr 60 8.60E-08 1.03E-05 7.27E-04 8.60E-02 6.08E-08 7.29E-06 9.81E-09 1.18E-06 8.60E-02 180 1.70E-06 9.13E-05 5.17E-03 2.21E-01 2.42E-07 7.23E-06 7.81E-08 3.51E-06 2.21E-01

)

300 5.69E-06 2.50E-04 9.13E-03 3.25E-01 2.40E-07 7.16E-06 1.55E-07 5.81E-06 3.2SE-01 600 5.06E-05 9.59E-04 3.53E-02 5.21E-01 5.90E-07 6.99E-06 7.21E-07 1.15E-05 5.22E-01 900 1.27E-04 2.08E-03 4.97E-02 6.74E-01 5.76E-07 6.83E-06 1.18E-06 1.69E-05 6.76E-01 1200 2.35E-04 3.56E-03 6.16E-02 8.06E-01 5.63E-07 6.67E-06 1.63E-06 2.22E-05 8.10E-01 1500 3.72E-04 5.35E-03 7.21E-02 9.24E-01 5.50E-07 6.52E-06 2.07E-06 2.74E-05 9.29E-01 1800 5.33E-04 7.43E-03 8.14E-02 1.03E+00 5.37E-07 6.37E-06 2.49E-06 3.23E-05 1.04E+00 2100 7.16E-04 9.75E-03 8.98E-02 1.13E+00 5.25E-07 6.22E-06 2.90E-06 3.72E-05 1.14E+00 2400 9.19E-04 1.23E-02 9.74E-02 1.21E+00 5.12E-07 6.08E-06 3.29E-06 4.18E-05 1.22E+00 2700 1.14E-03 1.50E-02 1.04E-01 1.29E+00 5.01E-07 5.94E-06 3.67E-06 4.63E-05 1.31E+00 Totat 4.10E-03 6.07E-01 4.90E-06 1.82E-05 This table and graph summarize the control room dose rate evaluation as the result of control room ventilation and RCS / SG volume changes detailed in revision 1 of this package. The dose rate in the control room will reach 1 mrem /hr at approximately 1700 seconds post accident. This time plus the 155 second response delay will result in automatic control isolation at approximately 1855 seconds post accident. However, manual operator isolation is assumed to occur by 1800 seconds post accident. The TRAILS print outs and input files associated with the Control Room Dose Rate Evaluation are included in Attachment 8.

RTI: n/a Form: RE 1.103-3 9/92 WD ERS-MPD-91-035 Page l7 IIcalth Physics Department Revision 1 A

Unit 2 LRA Source Term Development Table - Part 1 A

B C

D E

Unit 2 Ts=1ucugm B1 C1 FSAR SWEC-Ratio of:

SWEC-SFL-96-11 S ".1uCVgm Table SRP &

UR(B)-233 TS UR(B)-233 SWEC-Ratio of:

11.1-1 NUREGI RCS DE-l-131/

Ratio of:

UR(B)-233 TS Radio-Core CR-5009 Conc.

1% FF P/S leak /

S/G liquid DE-l-131/

Nuclide Activity Fuel Clad

@1% FF DE-l-131 steam flow Conc.

1% FF Ci x E7 Fractions uCl/gm

(-)

@1% FF DE-l-131 Kr.a3M 1.2 0.10 4.34E-01 2.61E-01 4.31E-05 uCi/gm

(-)

Kr-85M 3

0.10 2.12E+00 2.61E-01 4.31E-05 L131 1.30E-03 5.29E+01 Kr-as 0.068 0.30 1.12E+01 2.61E-01 4.31E-05 L132 3.84E-04 5.29E+01 Kr-87 5.9 0.10 1.21E+00 2.61E-01 4.31E-05 L133 1.86E-03 5.29E+01 Kr-88 8.3 0.10 3.23E+00 2.61E-01 4.31E-05 L134 8.56E-06 5.29E+01 Kr.as 11 0.10 1.02E-01 2.61E 4.31E-05 L135 8.32E-04 5.29E+01 4

xe 131M 0.042 0.10 1.09E-01 2.61E-01 4.31E-05 xe.133M 0.37 0.10 3.11E+00 2.61E-01 4.31E-05 x.-133 16 0.10 2.65E+01 2.61E-01 4.31E-05 xe-135u 4.2 0.10 1.10E+00 2.61E-01 4.31E-05 xe-135 4.1 0.10 3.25E+00 2.61E-01 4.31E-05 x 137 14 0.10 1.65E-01 2.61E-01 4.31E-05 x.-138 14 0.10 6.80E-01 2.61E-01 4.31E-05 List 6.9 0.12 2.54E+00 2.61E-01 L132 9.9 0.10 8.85E-01 2.61E-01 i

i-133 16 0.10 3.96E+00 2.61E-01 L134 18 0.10 5.54E-01 2.61E-01 L135 14 0.10 2.13E+ 00 2.61E-01 Col A-Unit 2 UFSAR Table 11.1-1 Core Activities in ci x 1E7.

Col B - SRP / NUREG/CR5009 Fuel Clad Fractions used in Calc. Pkg.

Col C - SWEC-UR(B)-233 Primary Reactor Coolant Concentration (uCi/gm) at 1% Failed Fuel (FF).

Col B1 - SWEC-UR(B)-233 Steam Generator (S/G) Uquid Concentration (uCi/gm) at 1% Failed Fuel (FF).

Col C1 - Ratio of Tech Spec DE-l-131 (0.10 uCl/gm) / DE-1131 calculated from 1% FF Sec. Uquid Activity.

Col D - Ratio of Tech Spec DE-l-131 (0.10 uCl/gm) / DE-1131 calculated from 1% FF RCS Activity.

Col E - SWECA)R(B)-233 Ratio of Primary to Secondary Leak Rate (1 gpm x 8.34 lbm/g x 60 m/hr) /

Steam Flow (1.16E7 lbm/hr).

RTL: n/a Form: RE 1.103 3 9/93

$ kWD ERS-MPD-91-035 Pase 11 Health Physics Department Revision I h

Unit 2 LRA Source Term Development Table - Part 2 Case 5 Case 4 Case 1,2 H

I J

K L

M N

O P

Radio-Gap Secondary Secondary Sec. Uq.

Sec. Stm 18% Gap RCS T/S T/S RCS Total RCS Nuclide Activity Liquid Steam 3-SG 3-SG Release Conc.

Activity Activity Ci uCi/gm uCi/gm Cl Cl Ci uCilgm Cl Ci Kr-83M 120E+06 4.89E-06 4.78E-05 2.16E+05 1.13E-01 1.80E+01 2.16E+05 Kr-8SM 3.00E+06 2.39E-05 2.34E-04 5.40E+05 5.54E-01 8.81E+01 5.40E+05 i

Kr-85 2.04E+05 1.26E-04 1.23E-03 3.67E+04 2.92E+00 4.66E+02 3.72E+04 i

Kr-87 5.90E+06 1.36E-05 1.33E-04 1.06E+06 3.16E-01 5.03E+01 1.06E+06 Kr-88 8.30E+06 3.64E-05 3.56E-04 1.49E+06 8.43E-01 1.34E+02 1.49E+06 Kr-8e 1.10E+07 1.15E-06 1.12E-05 1.98E+06 2.66E-02 4.24E+00 1.98E+06 x.-131 M 4.20E+04 1.23E-06 1.20E-05 7.56E+03 2.85E-02 4.53E+ 00 7.56E+03 l

x 133M 3.70E+05 3.50E-05 3.43E-04 6.66E+04 8.12E-01 1.29E+02 6.67E+04 x 133 1.60E+07 2.98E-04 2.92E-03 2.88E+06 6.92E+00 1.10E+03 2.88E+06 xe issu 4.20E+06 1.24E-05 1.21 E-04 7.56E+05 2.87E-01 4.57E+01 7.56E+05 x 135 4.10E+06 3.66E-05 3.58E-04 7.38E+05 8.49E-01 1.35E+02 7.38E+05 x.-137 1.40E+07 1.86E-06 1.82E-05 2.52E+06 4.31E-02 6.86E+00 2.52E+06 x.-138 1.40E+07 7.66E-06 7.49E-05 2.52E+06 1.78E-01 2.83E+01 2.52E+06 L131 8.28E+06 6.88E-02 6.88E-04 8.61 E+00 6.73E-03 1.49E+06 6.63E-01 1.06E+02 1.49E+06 k132 9.90E+06 2.03E-02 2.03E-04 2.54E+ 00 1.99E-03 1.78E+06 2.31 E-01 3.68E+01 1.78E+06 L133 1.60E+07 9.84E-02 9.84E-04 1.23E+01 9.63E-03 2.88E+06 1.03E+00 1.65E+02 2.88E+06 L134 1.80E+07 4.53E-04 4.53E-06 5.67E-02 4.43E-05 3.24E+06 1.45E-01 2.30E+01 3.24E+06 b1ss 1.40E+07 4.40E-02 4.40E-04 5.51 E+00 4.31 E-03 2.52E+06 5.56E-01 8.85E+ 01 2.52E+06 Col H - Gap Activity (Cl) = Col A x Col B x 1E7 Col 1 - Secondary Uquid Activity Concentration (uCl/gm) = Col B1 x Col C1 Col J - Secondary Steam for Kr's and Xe's (uCilgm) = Col C x Col D x Col E; for lodnes = Col H x 0.01.

(0.01 is the partioning factor)

Col K-Secondary Liquid Total Acitivty (Ci) = Col I x 3 SG x 92000 lbm/SG x 453.59 gm/lbm x 1E-6 Ci/uCi Col L - Secondary Steam Total Acitivty (Ci) = Col J x 3 SG x 7190 lbm/SG x 4b3.59 gm/lbm x 1E-6 Ci/uCi cd M.18 % Failed Fuel Gap Release Activity (Cl) = Col H x 0.18 Col N - Reactor Coolant System Tech Spec (1.0 uCilgm) Activity Concentration (uCl/gm) = Col C x Col D cd o. Tech Spec RCS Acitivty (Ci) = Col N x 351000 lbm x 453.59 gm/lbm x 1E-6 CVuci Col P - Total RCS Activity (Cl) = Col M + Col O

UNIT 2 LOCKED ROTOR CASE 1 (PAGE 1) gy TRAILS PC - Transport of Radioactive Material in Linear Systems, v1.0 d

Case I - Primary to Secondary Iodines / CR & LPZ Dose (1/16/98)[TC913585.DAT)

*

PROGENY INGROWTH ON **

COMP: RCS CCt4P: 3 S/Gs COMP: Control Room

.C VOLUME: 1.730E+05 Cu.Ft.

E..)-

9 '

INITIAL:

1.490E+06 I-131 C1 0.000E+00 I-131 0.000E+00 I-131 y

1.780E+06 I-132 0.000E+00 I-132 0.000E+00 I-132

{

2.880E+06 I-133 0.000E+00 I-133 0.000E+00 I-133 3.240E+06 I-134 0.000E+00 1-134 0.000E+00 I-134

[.

2.520E+06 I-135 0.000E+00 I-135 0.000E+00 I-135 ACT MULT (to uC1):

1.000E+06 1.000E+00 1.000E+00 539ok m

33 0

n.)

am i O.

.a i

eO W

G1 a

r 3

W b

e:

a a.

.g I

E O

'r*

m 3

~

UNIT 2 LOCKED ROTOR CASE 1 (PAGE 2) g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

=p, Case 1 - Primary to Secondary Iodines / CR & LPZ Dose (1/16/98)[TC913585.DAT]

- - PROGENY INGROWTH ON ***

' #5 T

a_.q' REMOVAL:

3.960E-07 1/sec 2.234E-06 1/see 1.000E+01 cfm E

NUC Grp 1 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

@ l NUC Grp 2 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 9.400E-01 y

NUC Grp 3 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 M*.

MULTIPLIERS===>

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1

1.800E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 g

2 5.400E+03

.000 1.00

.000

.000 1.00

.000 1.00 1.00

.000 g

3 7.200E+03

.000 1.00

.000

.000 1.00 000 104.

104.

1.00

~

4 9.Q00E+03

.000 1.00

.000

.596

.000 104.

104.

1.00 5 1.440E+04

.000 1.00

.000

.596 000 104.

104.

1.00 6 2.800E+04

.000 1.00

.000

.596

.000 104.

104.

1.00 7

3.060E+04

.000 1.00

.000

.000 000 1.690E+03 1.690E+03

.000.

8 8.640E+04

.000 1.00

.000

.000 000 50.0 50.0

.000 9 3.456E+05

.000 1.00

.000

.000 50.0 50.0

.000 10 2.592E+06

.000 1.00

.000

.000 50.0 50.0

.000 m.

N CONTROL ROOM --

ENVIRONMENT ---

g X/Q Breathing occupancy X/Q Breathing x,

s/M3 M3/s s/M3 M3/s 9

1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 d-MULTIPLIERS-===>

gg 3

STEP TIME,s Q

~

1 1.000E+03 1.59 1.00 1.00 6.04 1.00 e

2 5.400E+03 1.59 1.00 1.00 6.04 1.00 (D

3 7.200E+03 1.59 1.00 1.00 6.04 1.00

.-4 4

9.000E+03 1.59 1.00 1.00 6.04 1.00 e

5 1.440E+04 1.59 1.00 1.00 6.04 1.00 0

6 2.880E+04 1.59 1.00 1.00 6.04 1.00 (A) 7 3.060E+04

.786 1.00 1.00 4.33 1.00 (Jy 8

8.640E+04

.786 1.00 1.00 4.33 1.00 9 3.456E+05

.596 1.00

.600 2.10 1.00 10 2.592E+06

.376 1.00

.400

.744 1.00 5o-3 3,

N a.

j i:

wb 3

~

m m

. m r-m 1

UNIT 2 LOCKED ROTOR CASE I (PAGE 3) 4Q TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 5p Case 1 - Primary to Secondary Iodines / CR & LPZ Dose (1/16/98)[TC913585.DAT]

- - PROGENY INGRONTH ON ***

lG7 RCS 3 S/Gs AVERAGE

- =-CONTROL ROOM U2 CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD kJh STEP TIME uCi uCi-see uCi uCi-sec uCi uCi/sec uCi uCi/cc uci-sec EF Xe-131m INITIAL 0.000E+00 0.000E+00 0.000E+00 2 l 1

.5000 h 1.976E+07 1.780E+10 1.406E+04 8.447E+06 1.887E+01 1.048E-02 1.179E-03 2.406E-13 9.239E-01 3

2 1.5000 h 5.903E+07 1.419E+11 1.256E+05 2.183E+08 4.877E+02 1.355E-01 3.725E-03 7.603E-13 8.734E+00 M*

b

{,,

3 2.0000 h 7.853E+07 1.238E+11 2.224E+05 3.092E+08 6.907E+02 3.837E-01 5.379E-02 1.098E-11 5.303E+01 4

2.5000 h 9.7 95E+07 1.588E+11 3.467E+05 5.082E+08 6.766E+02 3.759E-01 9.497E-02 1.939E-11 1.350E+02 f(

p.

5 4.0000 h 1.557E+08 6.851E+11 8.803E+05 3.205E+09 4.268E+03 7.903E-01 3.188E-01 6.50SE-11 1.170E+03 6

8.0000 h 3.059E+08 3.330E+12 3.439E+06 2.916E+10 3.883E+04 2.696E+00 1.703E+00 3.476E-10 1.684E+04 g

7 8.5000 h 3.243E+08 5.671E+'.1 3.880E+06 6.583E+09 0.000E+00 0.000E+00 9.121E-02 1.862E-11 9.911E+02 g

8 24.0000 h 8.547E+08 3.325E+13 2.955E+07 8.280E+11 0.000E+00 0.000E+00 6.886E-03 1.406E-12 1.824E+03 9 96.0000 h 2.484E+09 4.590E+14 3.637E+08 4.500E+13 0.000E+00 0.000E+00 3.462E-08 7.067E-18 1.477E+02 10 720.0000 h 1.199E+09 5.542E+15 2.147E+09 4.025E+15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.284E-04 Xe-131m TOTALS 6.039E+15 4.071E+15 4.497E+04 2.117E+04 Xe-133m INITIAL 0.000E+00 0.000E+00 0.000E+00 1

.5000 h 5.402E+08 4.882E+11 3.844E+05 2.315E+08 5.171E+02 2.873E-01 3.213E-02 6.558E-12 2.523E+01 2

1.5000 h 1.581E+09 3.834E+12 3.365E+06 5.889E+09 1.316E+04 3.654E+00 9.954E-02 2.032E-11 2.353E+02 IT1 3

2.0000 h 2.082E+09 3.2 99E+12 5.898E+06 8.236E+09 1.840E+04 1.022E+01 1.428E+00 2.916E-10 1.410E+03 g) 4 2.5000 h

2. 571E+09 4.190E+12 9.102E+06 1.340E+10 1.785E+04 9.914E+00 2.502E+00 5.100E-10 3.566E+03 gg) 5 4.0000 h

3. 965E+ 0 9 1.'77 0E+ 13 2.242E+07 8.270E+10 1.101E+05 2.039E+01 8.177E+00 1.669E-09 3.021E+04 7

6 8.0000 h 7.191E+09 8.114E+13 8.085E+07 7.077E+11 9.423E+05 6.544E+01' 4.065E+01 8.298E-09 4.069E+05 3

i 7

8.5000 h 7.547E+09 1.327E+13 9.030E+07 1.540E+11 0.000E+00 0.000E+00 2.165E+00 4.419E-10 2.362E+04 d-0 24.0000 h 1.466E+10 6.513E+14 5.069E+08 1.587E+13 0.000E+00 0.000E+00 1.345E-01 2.745E-11 4.092E+04 5* "C) 9 96.0000 h.

1.142E+10 3.889E+15 1.673E+09 3.366E+14 0.000E+00 0.000E+00 2.410E-07 4.919E-17 2.669E+03

~~((J 10 720.0000 h 1.464E406 3.090E+15 2.621E+06 8.496E+14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.674E-03 e

Xe-133m TOTALS 7.754E+15 1.203E+15 1.102E+06 5.096E+05

({}

A Xe-133 INITIAL 0.000E+00 0.000E+00 0.000E+00 e

1

.5000 h 7.622E+09 6.883E+12 5.424E+06 3.264E+09 7.292E+03 4.051E+00 4.535E-01 9.258E-11 3.560E+02

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2 1.5000 h 2.240E+10 5.422E+13 4.766E+07 8.330E+10 1.861E+05 5.170E+01 1.411E+00 2.880E-10 3.329E+03 (4}

3 2.0000 h 2.956E+10 4.679E+13 8.373E+07 1.168E+11 2.609E+05 1.450E+02 2.030E+01 4.143E-09 2.002E+04 (yy 4

2.5000 h 3.658E+10 5.955E+13 1.295E+08 1.905E+11 2.536E+05 1.409E+02 3.565E+01 7.278E-09 5.076E+04 5

4.0000 h 5.675E+10 2.526E+14 3.210E+08 1.181E+12 1.572E+06 2.911E+02 1.174E+02 2.397E-08 4.328E+05 6

8.0000 h 1.047E+11 1.172E+15 1.177E+09 1.023E+13 1.362E+07 9.461E+02 5.951E+02 1.215E-07 5.929E+06 7

8.5000 h 1.101E+11 1.933E+14 1.317E+09 2.244E+12 0.000E+00 0.000E+00 3.181E+ 01 6. 4 94 E-0 9 3. 4 62E+ 05 8 24.0000 h 2.295E+11 9.873E+15 7.934E+09 2.418E+14 0.000E+00 0.000E+00 2.216E+00 4.523E-10 6.226E+05 3

9 96.0000 h 2.702E+11 7.371E+16 3.9565+10 6.650E+15 0.000E400 0.000E+00 6.630E-06 1.355E-15 4.575E+04 gp 10 720.0000 h 3.954E+09 1.489E+17 7.000E+09 6.265E+16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.341E-01 3

y Xe-133 TOTALS 2.343E+17 6.956E+16 1.590E+07 7.450E+06 g

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UNIT 2 LOCKED ROTOR CASE 1 (PAGE 4) g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

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' Case 1 - Primary to Secondary Iodines / CR & LPZ Dose (1/16/98}[TC913585.DAT]

** PROGENY INGROWTH ON ***

g-RCS 3 S/Gs AVERAGE CONTROL ROOH Z 1 CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD

$.- h STEP TIME uCi uCi-sec uCi uCi-see uCi uCi/sec uCi uC1/cc uCi-sec EI-

$ 'l Xe-135m INITIAL 0.000E+00 0.000E+00 0.000E+00 1

.5000 h 2.985E+11 3.318E+14 2.124E+08 1.490E+11 3.328E+05 1.849E+02 1.567E+01 3.199E-09 1.344E+04 1;

2 1.5000 h 3.614E+11 1.262E'+15 7.689E+08 1.815E+12 4.055E+06 1.126E+03 2.148E+01 4.385E-09 7.042E+04 E'

4 2.5000 h 3.311E+11 6.112E+14 1.172E+09 1.946E+12 2.590E+06 1.439E+03 1.622E+02 3.310E-08 2.929E+05 k ' %,.{.-

3 2.0000 h 3.478E+11 6.392E+14 9.851E+08 1.584E+12 3.539E+06 1.966E+03 1.648E+02 3.365E-08.1.975E+05 3$ ;I 5

4.0000 h 2.8272+11 1.655E+15 1.599E+09 7.562E+12 1.007E+07 1.865E+03 2.122E+02 4.332E-08 1.070E+06 6

0.0000 h 1.848E+11 3.317E+15 2.078E+09 2.739E+13 3.647E+07 2.532E+03 3.035E+02 6.196E-08 4.133E+06 7

8.5000 h 1.753E+11 3.240E+14 2.097E+09 3.759E'12 0.000E+00 0.000E+00

7. 336E+00 1. 4 97 E-09 1. 3 93E+ 05 3*

8 24.0000 h 3.374E+10 4.793E+15 1.167E+09 9.709E+13 0.000E+00 0.000E+00 5.800E-02 1.184E-11 5.904E+04 9 96.0000 h 1.602E+07 1.142E+15 2.345E+06 5.550E+13 0.000E+00 0.009E+00 1.153E-10 2.355E-20 7.503E+02 10 720.0000 h 2.512E-22 5.42SE+11' 4.497E-22 0.788E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.492E-06 Xe-135m TOTALS 1.408E+16 1.969E+14 5.705E+07 5.976E+06 Xe-135 INITIAL 0.000E+00 0.000EF00 0.000E+00 1

.5000 h 8.337E+10 7.449E+13 5.933E+07 3.545E+10 7.919E+04 4.399E+01 4.968E+00 1.014E-09 3.893E+03 2

1.5000 h 2.413E+11 5.916E+14 5.135E+08 9.075E+11 2.027E+06 5.632E+02 1.511E+01 3.085E-09 3.616E+04 m.

3 2.0000 h 3.106E+11 4.978E+14 8.797E+08 1.242E+12 2.774E+06 1.541E+03 2.151E+02 4.390E-08 2.126E+05 y

4 2.5000 h 3.733E+11 6.164E+14

1. 321E+ 09 1. 971E+ 12 2.624E+06 1.458E+03 3.681E+02 7.515E-OS 5.298E+05 g

5 4.0000 h 5.257E+11 2.450E+15

2. 97 3E+ 0 9 1.141E+ 13 1.519E+07 2.813E+03 1.097E+03 2.238E-07 4.162E+06 y,

6 8.0000 h 7.352E+11 9.364E+15 0.266E+09 8.057E+13 1.073E+08 7.450E+03 4.245E+03 8.664E-07 4.467E+07 9

7 8.5000 h 7.466E+11 1.334E+15 8.933E+09 1.548E+13 0.000E+00 0.000E+00 2.193E+02 4.476E-08 2.445E+06 d-0 24.0000 h 5.187E+11 3.818E+16 1.793E+10 8.589E+14 0.000E+00 0.000E+00 5.094E+00 1.040E-09 3.190E+06 5' "C) 9 96.0000 h 3.679E+09 3.049E+16 5.386E+08 1.720E+15 0.000E+00 0.000E+00 9.285E-08 1.895E-17 7.484E+04

{Q 10 720.0000 h 3.877E-12 1.740E+14 6.941E-12 2.926E+13 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.342E-03 e

Xe-135 TOTALS 8.377E+16 2.720E+15 1.300E+06 5.533E+07 (D

.n I-131 INITIAL 1.490E+12 0.000E+00 0.000E+00 s

1

.5000 h 1.486E+12 2.679E+15 1.058E+09 9.532E+11 2.129E+06 1.183E+03 7.646E+01 1.561E-08 6.983E+04 O

2 1.5000 h 1.479E+12 5.337E+15 3.14?E+09 7.57 8E+12 1.693E+07 4.703E+03 8.859E+01 1.808E-08 2.971E+05 W

3 2.0000 h 1.475E+12 2.659E+15 4.178E+09 6.594E+12 1.473E+07 8.183E+03 1.369E+02 2.794E-08 2.042E+05 g

4 2.5000 h 1.471E+12 2.652E+15

5. 209E+0 9 8. 4 4 9E+12 1.125E+07 6.250E+03 1.623E+02 3.312E-08 2.699E+05 5

4.0000 h 1.460E+12 7.916E+15 8.259E+09 3.639E+13 4.845E+07 8.972E+03 2.687E+02 5.486E-08 1 190E+06 6

8.0000 h 1.431E+12 2.082E+16 1.609E+10 1.758E+14 2.341E+08 1.626E+04 6.398E+02 1.306E-07 7.168E+06 7

8.5000 h 1.428E+12 2.573E+15 1.700E+10 2.986E+13 0.000E+00 0.000E+00 3.400E+01 6.956E-09 3.718E+05 8 24.0000 h 1.321E+12 7.665E+16 4.567E+10 1.769E+15 0.000E+00 0.000E+00 2.193E+00 4.476E-10 6.485E+05 3

9 96.0000 h 9.204E+11 2.874E+17 1.348E+11 2.476E+16 0.000E+00 0.000E+00 6.401E-06 1.307E-15 4.460E+04

}

10 720.0000 h 4.019E+10 6.315E+17 7.197E+10 3.135E+17 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.302E-01 3

g I-131 TOTALS 1.040E+18 3.403E+17 3.276E+08 1.026E+07 E

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UNIT 2 LOCKED ROTOR CASE I (PAGE 5)

- MQ 5p TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 Case 1 - Primary to Secondary Iodines / CR & LPZ Dose (1/16/98)[TC913585.DAT]

- - PROGENY INGROWTH ON ***

RCS 3 S/Gs AVERAGE

-CONTROL ROOM CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi aci-sec uCi uCi/sec uCi uCi/cc uCi-sec SF I-132 INITIAL 1.180E+12 0.000E+00 0.000E+00 l2 1

.5000 h 1.530E+12 2.973E+15

1. 08 9E+ 0 9 1. 032E+12 2.305E+06 1.281E+03 7.699E+01 1.572E-08 7.203E+04 3

2 1.5000 h 1.130E+12 4.752E+15 2.405E+09 6.581E+12 1.470E+07 4.004E+03 6.627E+01 1.353E-08 2.569E+05 E'

3 2.0000 h 9.714E+11 1.888E+15 2.752E+09 4.666E+12

1. 04 2E+ 07 5.7 91E+ 03 8.914E+01 1.820E-08 1.410E+05 5

4 2.5000 h 8.350E+11 1.623E+15 2.956E+09 5.156E+12 6.865C+06 3.814E+03 9.139E+01 1.865E-08 1.626E+05 Y

5 4.0000 h 5.302E+11 3.624E+15 2.998E409 1.637E+13 2.180E+07 4.037E+03 9.857E+01 2.012E-08 5.160E+05 3

6 8.0000 h 1.579E+11 4.426E+15 1.775E+09 3.499E+13 4.658E+07 3.235E+03 8.351E+01 1.705E-08 1.268E+06 f

7 8.5000 h 1.357E+11 2.638E+14 1.624E+09 3.058E+12 0.000E+00 0.000E+00 3.833E+00 7.824E-10 4.655E+04 g

~

8 24.0000 h 1.243E+09 1.599E+15 4.297E+07 2.645E+13 0.000E+00 0.000E+00

2. 4 41E-03 4. 983E-13 2. 905E+ 04 9 96.0000 h 4.230E-01 1.478E+13 6.193E-02 5.832E+11 0.000E+00 0.000E+00 3.481E-18 7.105E-28 1.851E+01 10 720.0000 h 0.000E+00 5.029E+03 0.000E+00 7.635E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.639E-14 I-132 TOTALS 2.116E+16 9.888E+13 1.027E+08 2.492E+06 I-133 INITIAL 2.880E+12 0.000E+00 0.000E+00 1

.5000 h 2.830E+12 5.139E+15 2.014E+09 1.824E+12 4.075E+06 2.264E+03 1.453E+02 2.966E-08 1.330E+05 2

1.5000 h 2.734E+12 1.001E+16 5.817E+09 1.418E+13 3.169E+07 8.802E+03 1.634E+02 3.335E-08 5.558E+05 ry]

3 2.0000 h 2.687E+12 4.878E+15

7. 610E + 0 9 1. 20 9E +13 2.702E+07 1.501E+04 2.490E+02 5.083E-08 3.737E+05

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4 2.5000 h 2.64 0E+12 4.7 94E+15 9.346E+09 1.527E+13 2.033E+07 1.130E+04 2.909E+02 5.938E-08 4.871E*05 gy) 5 4.0000 h 2.506E+12 1.389E+16 1.417E+10 6.376E+13 8.489E+07 1.572E+04 4.612E+02 9.414E-08 2.076E+06 7a,

6 8.0000 h 2.181E+12 3.369E+16 2.452E+10 2.827E+14 3.764E+08 2.614E+04 9.825E+02 2.006E-07 1.134E+07 3

7 8.5000 h 2.143E+12 3.892E+15 2.565E+10 4.516E+13 0.000E+00 0.000E+00 5.156E+01 1.053E-08 5.685E+05 d-8 24.0000 h 1.251E+12 9.247E+16 4.32SE+10 2.055E+15 0.000E+00 0.000E+00 2.093E+00 4.272E-10 8.614E+05 5' 90 9 96.0000 h 1.025E+11 1.190E+17 1.500E+10 S.140E+15 0.OOOE+00 0.000E+00 7.182E-07 1.466E-16 3.644E+04 f,((J 10 720.0000 h 3.920E+01 1.062E+16 7.019E+01 2.075E+15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.251E-02 e

I-133 TOTALS 2.984E+17 1.270E+16 5.444E+08 1.643E+07 (C)

A I-134 INITIAL 3.240E+12 0.000E+00 0.000E+00 e

1

.5000 h 2.180E+12 4.816E+15 1.552E+09 1.602E+12 3.578E+06 1.988E+03 1.065E+02 2.174E-08 1.035E+05

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2.0000 h 6.646E+11 1.468E+15 1.882E+09 3.606E+12 8.057E+06 4.476E+03 6.044E+01 1.234E-08 1.056E+05 (yg 4

2.5000 h 4.472E+11 9.878E+14 1.583E+ 09 3.124E+12 4.160E+06 2.311E+03 4.879E+01 9.960E-09 9.731E+04 5

4.0000 h 1.363E+11 1.413E+15 7.709E+08 6.209E+12 8.267E+06 1.531E+03 2.710E+01 5.533E-09 1.889E+05 6

8.0000 h 5.735E+09 5.935E+14 6.448E+07 4.260E+12 5.673E+06 3.939E+02 5.981E+00 1.221E-09 1.491E+05 7

8.5000 h 3.859E+09 8.524E+12 4.618E+07 9.871E+10 0.000E+00 0.000E+00 2.149E-01 4.387E-11 3.120E+03

}7 8 24.0000 h 1.7 97E+04 1.7 54E+13 6.212E+02 2.419E+11 0.000E+00 0.000E+00 6.959E-08 1.421E-17 8.026E+02 3

9 96.0000 h 3.065E-21 0.166E+07 4.487E-22 2.976E+06 0.000E+00 0.000E+00

4. 973E-38 0.000E+00 2.599E-04 gp 10 720.0000 h 0.000E+00 1.393E-17 0.000E+00 2.068E-18 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.057E-34 3

7, 1-134 TOTALS 1.473E+16 2.634E+13 4.582E+07 9.299E+05 g

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4 UNIT 2 LOCKED ROTOR CASE 1 (PAGE 6) jyg TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 y

Case 1 - Primary to Secondary Iodines / CR & LPZ Dose (1/16/98){TC913585.DAT]

- - PROOENY INGROWTH ON ***

A RCS 3 S/Gs AVERAGE CONTROL ROOM 1

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-see uCi uCi-see uCi uCi/sec uCi uCi/cc uCi-sec E l I-135 INITIAL 2.520E+12 0.000E+00 0.000E+00 j!

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5 4.0000 h 1.647E+12 9.643E+15 9.315E+09 4.407E+13 5.860E+07 1.087E+04 3.034E+02 6.193E-08 1.421E+06 6

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7 8.5000 h 1.021E+12 1.888E+15 1.222E+10 2.190E+13 0.000E+00 0.000E+00 2.524E+01 5.151E-09 2.855E+05 3*

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1.5000 h 6.12E-01 6.12E-01 1.31E-01 1.31E-01 6.67E+01 6.67E+01 1.82E-03 1.06E-03 7.78E-03 7.95E-03 3.95E+00 4.04E+00 2.0000 h 4.97E-01 9.93E-01 1.07E-01 2.13E-01 5.42E+01 1.08E+02 1.16E-03 2.74E-03 4.95E-03 1.17E-02 2.52E+00 5.95E+00 g

2.5000 h 3.61E-01 7.21E-01 7.75E-02 1.55E-01 3.93E+01 7.07E+01 1.46E-03 3.09E-03 6.25E-03 1.39E-02 3.17E+00 6.72E+00 p

4.0000 h 1.40E+00 9.32E-01 3.00E-01 2.00E-01 1.53E+02. 1.02E+02 5.75E-03 4.42E-03 2.46E-02 1.89E-02 1.25E+01 9.59E+00 8.0000 h 5.06E+00 1.27E+00 1.09E+00 2.72E-01 5.52E+02 '1.38E+02 2.50E-02 7.26E-03 1.07E-01 3.10E-02 5.43E+01 1.58E+01 2n 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.16E-03 3.68E-04 4.94E-03 1.57E-03 2.51E+00 7.98E-01 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.30E-03 4.92E-06 5.57E-03 2.10E-05 2.83E+00 1.07E-02 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.06E-05 9.79E-15 4.54E-05 4.18E-14 2.30E-02 2.12E-11 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.41E-14 0.00E+00 6.01E-14 0.00E+00 3.05E-11 0.00E+00 TOTALS 8.01E+00 1.72E+00 8.74E+02 3.81E-02 1.63E-01 8.28E+01

[11 ALL NUCLIDES

.5000 h 3.56E-01 7.13E-01 9.34E-02 1.87E-01 1.14E+02 2.27E+02 1.87E-03 7.14E-03 9.86E-03 3.80E-02 1.25E+01 4.93E+01 y

1.5000 h 2.18E+00 2.18E+00 6.07E-01 6.07E-01 8.82E+02 8.82E+02 '6.48E-03 5.98E-03 3.59E-02 3.46E-02 s.23E+01 5.54E+01 2.0000 h 1.54E+00 3.08E+00 4.56E-01 9.12E-01 7.54E+02 1.51E+03 3.83E-03 9.12E-03 2.44E-02 6.17E-02 3.52E+01 8.46E+01 y

2.5000 h 1.04E+00 2.08E+00 3.20E-01 6.41E-01 5.69E+02 1.14E+03 4.76E-03 9.91E-03 3.41E-02' 7.45E-02 4.61E+01 9.92E+01 3

4.0000 h 3.66E+00 2.44E+00 1.21E+00 8.09E-01 2.40E+03 1.60E+03 1.83E-02 1.41E-02 1.62E-01 1.36E-01 1.98E+02 1.60E+02 d'

8.0000 h 1.23E+01 3.09E+00 4.76E+00 1.19E+00 1.'OE+04 2.76E+03 9.18E-02 2.81E-02 1.15E+00 3.75E-01 1.13E+03 3.59E+02 5* "U 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.45E-03 1.41E-03 5.99E-02 1.93E-02 5.78E+01 1.90E+01

"" Q 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.62E-03 3.73E-05 8.08E-02 5.66E-04 9.53E+01 1.05E+00 e

96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E-04 2.96E-11 1.57E-03 4.21E-10 3.45E+00 2.49E-06 (D.

720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.55E-11 0.00E+00 9.30E-10 0.00E+00 5.60E-06 0.00E+00

.ab TOTALS 2.11E+01 7.45E+00 1.57E+04 1.37E-01 1.56E+00 1.63E+03 eO 00 U1

2 5

r 4

3

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r UNIT 2 LOCKED ROTOR CASE 2 (PAGE 1)

.N TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 y

Case 2 - Primary to Secondary Noble Gases / CR & LPZ Dose (1/15/98)lTC913586.DAT *** PROGENY INGRCMTH CN ***

h COMP: Not used this case COMP: 3 S/Gs COMP: Control Room Z 1 VOLUME: 1.730E+05 Cu.E't.

!. dl 5

INITIAL:

0.000E+00 Kr-83m 2.160E+05 Kr-83m Ci 0.000E+00 Kr-83m

@ l 0.000E+00 Kr-85m 5.400E+05 Kr-85m 0.000E+00 Kr-85m y

0.000E+00 Kr-85 3.720E+04 Kr-85 0.000E+00 Kr-85 E'

O.000E+00 Kr-87 1.060E+06 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.490E+06 Kr-88 0.000E+00 Kr-88 f

0.000E+00 Kr-89 1.9802+06 Kr-89 0.000E+00 Kr-89 0.000E+00 Xe-131m 7.560E+03 Xe-131m 0.000E+00 Xe-131m g

a 0.000E+00 Xe-133m 6.670E+04 Xe-133m 0.000E+00 Xe-133m 2#

0.000E+00 Xe-133 2.880E+06 Xe-133 0.000E+00 Xe-133 O.000E+00 Xe-135m 7.560E+05 Xe-135m

_0.000E+00 Xe-135m 0.000E+00 Xe-135 7.380E+05 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 2.520E+06 Xe-137 0.000E+00 Xe-131 0.000E+00 Xe-138 2.520E+06 Xe-138 0.000E+00 Xe-138 ACT MULT'(to uCil:

1.000E+00 1.000E+06 1.000E+00 ITI M

0)

"O e

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UNIT 2 LOCKED ROTOR CASE 2 (PAGE 2) g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 Case 2 - Primary to Secondary Noble Gases / CR & LPZ Dose (1/15/981[TC913506.DAT *** PROGENY INGROWTN ON ***

E. f g-5 REMOVAL:

0.000E+00 1/sec 3.960E-07 1/see 1.000E+01 cfm f'r 1

NUC Grp 1 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 g l NUC Grp 2 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 9.400E-01 y

NUC Grp 3 REL FR:

O.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

{

MULTIPLIERS===>

STEP TIME XPR XREM XRP XPR XREM XRF XPR XREM XRF 1

1.800E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 2

5.400E+03

.000 1.00

.000

.000 1.00

.000 1.00 1.00

.000 g

3 7.200E+03

.000 1.00

.000

.000 1.00

.000 104.

104.

1.00 4

9.000E+03

.000 1.00

.000

.000 1.00

.000 104.

104.

1.00 5 1.440E+04

.000 1.00

.000

.000 1.00

.000 104.

104.

1.00 6

2.880E+04

.000 1.00

.000

.000 1.00

.000 104.

104.

1.00 7

3.060E+04

.000 1.00

.000

.000 1.690E+03 1.690E+03

.000 0

8.640E+04

.000 1.00

.000

.000 50.0 50.0

.000 9 3.456E+05

.000 1.00

.000

.000 50.0 50.0

.000 10 2.592E+0F

.000 1.00

.000

.000 50.0 50.0

.000 m

N CONTROL ROCH ENVIRONMENT ---

X/Q Breathing Occupancy X/Q Breathing y

s/M3 M3/s s/M3 M3/s 9

1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04

.j-MULTIPLIERS-==>

6* T STEP TIME,s

{ Q, 1

1.800E+03 1.59 1.00 1.00 6.04 1.00 e

2 5.400C+03 1.59 1.00 1.00 6.04 1.00 3 7.200E+03 1.59 1.00 1.00 6.04 1.00

.Wh 4

9.000E+03 1.59 1.00 1.00 6.04 1.00 e

5 1.440E+04 1.59 1.00 1.00 6.04 1.00 Q

6 2.880E+04 1.59 1.00 1.00 6.04 1.00 (A) 7 3.060E+04

.786 1.00 1.00 4.33 1.00 g

8 8.640E+04

.786 1.00 1.00 4.33 1.00 9 3.456E+05

.596 1.00

.600 2.10 1.00 10 2.592E+06

.376 1.00

.400

.744 1.00

T 5r 5

50 N i 5 ;l a

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UNIT 2 LOCKED ROTOR CASE 2 (PAGE 3) g TRAILS PC -- Transport of Radioactive Material in M % r Syst m v1.0 Case 2 - Primary to Secondary Noble Gases / CR & LM., Dose (1/;?/98)(TC913586.DAT *** PROGENY INGROWTH ON

Not used this case 3 S/Gs AVERAGE CONTROL ROQ4 70 CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD

[ ]'

STEP TIME uC1 uC1-sec uC1 uCl-sec uCi uC1/sec uCi uCi/cc uCi-sec g.

Kr-83m INITIAL 0.000E+00 2.160E+11 0.000E+00 a.a l

{

1

.5000 h 0.000E+00 0.000E+00 1.786E+11 3.541E+14 1.402E+08 7.790E+04 4.597E+03 9.384E-07 4.328E+06 2

1.5000 h 0.000E+00 0.000E*00 1.221E+11 5.349E+14 2.118E+08 5.884E+04 3.269E+03 6.673E-07 1.401E+07 3

2.0000 h 0.000E+00 0.000E+00 1.010E+11 2.002E+14 7.927E+07 4.404E+04 7.430E+03 1.517E-06 9.860E+06 f

4 2.5000 h 0.000E+00 0.000E+00 8.350E+10 1.655E+14 6.555E+07 3.642E+04 9.410E+03 1.921E-06 1.527E+07 5

4.0000 h 0.000E+00 0.000E+00 4.721E+10 3.436E+14 1.361E+08 2.520E+04 9.521E+03 1.943E-06 5.117E+07 5

6 8.0000 h 0.000E+00 0.000E+00 1.032E+10 3.493E+14 1.383E+08 9.606E+03 3.955E+03 8.073E-07 7.965E+07 3

7 8.5000 h 0.000E+00 0.000E+00 8.537E+09 1.692E+13 0.000E+00 0.000E+00 1.746E+02 3.565E-08 2.181E+06 5

8 24.0000 h 0.000E+00 0.000E+00 2.408E+07 0.092E+13 0.000E+00 0.000E+00 3.351E-02 6.840E-12 1.130E+06 E-9 96.0000 h 0.000E+00 0.000E+00 3.454E-05 2.289E+11 0.000E+00 0.000E+00 1.817E-19 3.709E-29 2.185E+02 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 3.283E-01 0.000E+00 0.000E+00 0.000E+00 0.000F'00 1.185E-15 Kr-83m TOTALS 0.000E+00 2.046E+15 7.713E+08 1.776E+08 Kr-85m INITIAL 0.000E+00 5.400E+11 0.000E+00 1

.5000 h 0.000E+00 0.000E+00 4.994E+11 9.350E+14 3.703E+08 2.057E+05 1.281E+04 2.615E-06 1.185E+07 2

1.5000 h 0.000E+00 0.000E+00 4.272E+11 1.665E+15 6.592E+08 1.831E+05 1.140E+04 2.326E-06 4.351E+07 j

g I

3 2.0000 h 0.000E+00 0.000E+00 3.952E+11 7.398E+14 2.930E+08 1.628E+05 2.896E+04 5.912E-06 3.700E+07 4

2.5000 h 0.000E+00 0.000E+00 3.655E+11 6.842E+14 2.710E+08 1.505E+05 4.102E+04 8.374E-06 6.345E+07 k @*

5 4.0000 h 0.000E+00 0.000E+00 2.892E+11 1.759E+15 6.968E+08 1.290E+05 5.680E+04 1.160E-05 2.696E+08 6

8.0000 h 0.000E+00 0.000E+00 1.548E+11 3.097E+15 1.226E+09 8.516E+04 4.774E+04 9.746E-06 7.318E+08 hb 7

8.5000 h 0.000E+00 0.000E+00 1.433E+11 2.682E+14 0.000E+00 0.000E+00 2.358E+03 4.813E-07 2.716E+07 8 24.0000 h 0.000E+00 0.000E+00 1.302E+10 3.032E+15 0.000E+00 0.000E+00 1.45eE+01 2.976E-09 2.571E+07 3- =g 9 96.0000 h 0.000E+00 0.000E+00 1.891E+05 3.031E+14 0.000E+00 0.000E+00 8.004E-10 1.634E-19 1.599E+05 3 g 10 720.0000 h 0.000E+00 0.000E+00 2.226E-37 4.401E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.781E-06 Kr-85m TCyrALS 0.000E+00 1.248E+16 3.516E+09 1.210E+09 g

A Kr-85 INITIAL 0.000E+00 3.720E+10 0.000E+00 l

1

.5000 h 0.000E+00 0.000E+00 3.717E+10 6.694E+13 2.651E+07 1.473E+04 9.526E+02 1.945E-07 8.698E+05 Q

j 2

1.5000 h 0.000E+00 0.000E+00 3.712E+10 1.337E+14 5.296E+07 1.471E+04 9.890E+02 2.019E-07 3.495E+06 g

3 2.0000 h 0.000E+00 0.000E+00 3.709E+10 6.679E+13 2.645E+07 1.469E+04 2.715E+03 5.541E-07 3.380E+06 4

2.5000 h 0.000E+00 0.000E+00 3.707E+10 6.675E+13 2.643E+07 1.468E+04 4.154E+03 8.480E-07 6.221E+06 5

4.0000 h 0.000E+00 0.000E+00 3.699E+10 2.000E+14 7.918E+07 1.466E+04 7.191E+03 1.468E-06 3.137E+07 6

8.0000 h 0.000E+00 0.000E+00 3.678E+10 5.311E+14 2.103E+08 1.461E+04 1.039E+04 2.121E-06 1.319E+08 7

8.5000 h 0.000E+00 0.000E+00 3.678E+10 6.620E+13 0.000E+00 0.000E+00 5.543E+02 1.132E-07 6.040E+06

).

8 24.0000 h 0.000E+00 0.000E+00 3.678E+10 2.052E+15 0.000E+00 0.000E+00 3.771E+01 7.697E-09 1.073E+07 3

9 96.0000 h 0.000E+00 0.000E+00 3.676E+10 9.530E+15 0.000E+00 0.000E+00 1.425E-04 2.909E-14 7.828E+05 5

"3" 10 720.0000 h 0.000E+00 0.000E+00 3.659E+10 8.238E+16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.958E+00 k

Kr-85 TOTAL 3 0.000E+00 9.510E+16 4.219E+08 1.948E+08 a

P e

a il 2

E iE N

Q l

w l

b

UNIT 2 LOCKED ROTOR CASE 2 (PAGE 4) d TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 1p g Case 2 - Primary to Secondary Noble Gases / CR & LPZ Dose (1/15/98)[TC913586.DAT *** PROGENY INGROWTH ON ***

s' lh.

Not used this case 3 S/Gs AVERAGE CONTROL ROW CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD E.

STEP TIME uCi uCi-sec uC1 uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec EF ;

Kr-87 INITIAL 0.000E+00 1.060E+12 0.000E+00 y!

1

.5000 h 0.000E+00 0.000E+00 8.066E+11 1.670E+15 6.611E+08 3.673E+05 2.084E+04 4.254E-06 1.988E+07 15 2

1.5000 h 0.000E+00 0.000C+00 4.670E+11 2.237E+15 8.858E+08 2.461E+05 1.255E+04 2.562E-06 5.875E+07 M'

3 2.0000 h 0.000E+00 0.000E+00 3.553E+11 7.355E+14 2.913E+08 1.618E+05 2.626E+04 5.360E-06 3.586E+07 4

2.5000 h 0.000E+00 0.000E+00 2.704E+11 5.596E+14 2.216E+08 1.231E+05 3.060E+04 6.247E-06 5.147E+07

+

5 4.0000 h 0.000E+00 0.000E+00 1.191E+11 9.964E+14 3.946E+08 7.307E+04 2.471E+04 5.043E-06 1.458E+08 6

8.0000 h 0.000E+00 0.000E+00 1.338E+10 6.964E+14 2.758E+08 1.915E+04 6.442E+03 1.315E-06 1.581E+08 q

7 8.5000 h 0.000E+00 0.000E+00 1.019E+10 2.109E+13 0.000E+00 0.000E+00 2.617E+02 5.343E-08 3.473E+06 g

8 24.0000 h 0.000E+00 0.000E+00 2.183E+06 6.729E+13 0.000E+00 0.000E+00 3.814E-03 7.785E-13 1.311E+06 9 96.0000 h 0.000E+00 0.000E+00 1.972E-11 1.442E+10 0.000E+00 0.000E+00 1.303E-25 2.659E-35 1.P11E+01 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 1.302E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.527E-22 Kr-87 TOTALS 0.000E+00 6.983E+15 2.730E+09 4.747E+08 Kr-88 INITIAL 0.000E+00 1.490E+12 0.000E+00 1

.5000 h 0.000E+00 0.000E+00 1.318E+12 2.524E+15 9.995E+08 5.553E+05 3.385E+04 6.909E-06 3.152E+07 2

1.5000 h 0.000E+00 0.000E+00 1.031E+12 4.207E+15

1. 666E+ 09 4.628E+05 2.753E+04 5. 620E-06 1.100E+08 fr]

3 2.0000 h 0.000E+00 0.000E+00 9.119E+11 1.746E+15 6.916E+08 3.842E+05 6.692E+04 1.366E-05 8.679E+07

=g}

4 2.5000 h 0.000E+00 0.000E+00 8.066E+11 1.545E+15 6.117E+08 3.398E+05 9.066E+04 1.851E-05 1.429E+08 g

se,f) 5 4.0000 h 0.000E+00 0.000E+00 5.581E+11 3.644E+15 1.443E+09 2.672E+05 1.106E+05 2.258E-05 5.515E+08 6

8.0000 h 0.000E+00 0.000E+00 2.091E+11 5.119E+15

2. 027E+ 0 9 1. 4 08E+ 05 6.942E+04 1. 417E-05 1.187 E+ 0 9 O

7 8.5000 h 0.000E+00 0.000E+00 1.850E+11 3.542E+14 0.000E+00 0.000E+00 3.279E+03 6.693E-07 3.900E+07 h-8 24.0000 h 0.000E+00 0.000E+00 4.210E+09 2.667E+15 0.000E+00 0.000E+00 5.075E+00 1.036E-09 2.823E+07 5' "C) 9 96.0000 h 0.000E+00 0.000E+00 9.831E+01 6.210E+13 0.000E+00 0.000E+00 4.480E-13 9.146E-23 4.377E+04 f, ((J 10 720.0000 h 0.000E+00 9.000E+00 0.000E+00 1.450E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.864E-09 Kr-88 TOTALS 0.000E+00 2.187E+16 7.439E+09 2.177E+09 (C)

.b Kr-89 INITIAL 0.000E+00 1.980E+12 0.000E+00 8

1

.5000 h 0.000E+00 0.000E+00 2.745E+09 5.408E+14 2.142E+08 1.190E+05 1.204E+03 2.457E-07 1.844E+06 (2) 2 1.5000 h 0.000E+00 0.000E+00 5.275E+03 7.507E+11 2.973E+05 8.258E+01 1.925E-02 3.930E-12 3.292E+05 (A) 3 2.0000 h 0.000E+00 0.000E+00 7.312E+00 1.441E+06 5.705E-01 3.169E-04 2.888E-05 5.895E-15 5.130E+00 gyj 4

2.5000 h 0.000E+00 0.000E+00

1. 014 E-02 1. 9 97E+ 03 7.909E-04 4.394E-07 4.257E-08 8.690E-18 7. 694E-03 5

4.0000 h 0.000E+00 0.000E+00 2.700E-11 2.772E+00 1.098E-06 2.033E-10 4.224E-12 8.623E-22 1.136E-05 6

0.0000 h 0.000E+00 0.000E+00 3.682E-34 7.385E-09 2.925E-15 2.031E-19 4.220E-21 8.614E-31 1.125E-09 7

8.5000 h 0.000E+00 0.000E+00 5.108E-37 1.006E-31 0.000E+00 0.000E+00 3.124 E-25 6. 377E-35 7. 986E-19 35 8 24.0000 h 0.000E+00 0.000E+00 0.000E+00 1.397E-34 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.434E-23 3

9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 gh 6

10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 g

pg Kr-89 TOTALS 0.000E+00 5.415E+14 2.145E+08 2.174E+06 g

d i

F.

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UNIT 2 LOCKED ROTOR CASE 2 (PAGE 5) g i

TRAILS _PC -- Transport of Radioactive Material in linear Systems, v1.0 5p Case 2 - Primary to Secondary Noble Gases / CR & LPZ Dose (1/15/98)[TC913506.DAT * *

PROGENY INGROWTH ON * *

A Not used this case 3 S/Gs AVERAGE

- CONTROL ROOM--- -

50 CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uC1 uCi-sec uCi uCi-see uCi uC1/sec uCi uCi/cc uCi-sec E

Xe-131m INITIAL 0.000E+00 7.560E+09 0.000E+00 22 1

.5000 h 0.000E+00 0.000E+00 7.545E+09 1.359E+13 5.384E+06 2.991E+03 1.934E+02 3.947E-08 1.766E+05 3

2 1.5000 h 0.000E+00 0.000E+00 7.516E+09 2.711E+13 1.074E+07 2.982E+03 2.003E+02 4.088E-08 7.085E+05 K-3 2.0000 h 0.000E+00 0.000E+00

7. 502E+ 09 1. 352E+13 5.352E+06 2.974E+03 5.490E+02 1.121E-07 6.838E+05

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4 2.5000 h 0.000E+00 0.000E+00

7. 4 87E+ 0 9 1. 34 9E+13 5.342E+06 2.968E+03 8.391E+02 1.713E-07 1.257E+06 hf g 4

3 5

4.0000 h 0.000E+00 0.000E+00

7. 4 4 4E+09 4.031E+13 1.596E+07 2.956E+03 1.447E+03 2.954E-07 6.322E+06 p.

6 0.0000 h 0.000E+00 0.000E+00

7. 330E+ 0 9 1. 064 E+14 4.212E+07 2.92SE+03 2.072E+03 4.230E-07 2.639E+07.

7 8.5000 h 0.000E+00 0.000E+00

7. 321E+ 09 1. 319E+13 0.000E+00 0.000E+00 1.104E+02 2.255E-08 1.204E+06 s

8 24.0000 h 0.000E+00 0.000E+00 7.049E+09 4.009E+14 0.000E+00 0.000E+00 7.235E+00 1.477E-09 2.113E+06 9 96.0000 h 0.000E+00 0.000E+00 5.914E+09 1.676E+15 0.000E+00 0.000E+00 2.295E-05 4.684E-15 1.481E+05 10 720.0000 h 0.000E+00 0.000E+00 1.291E+09 6.823E+15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.698E-01 Xe-131m TOTALS 0.000E+00 9.127E+15 8.490E+07 3.901E+07 Xe-133m INITIAL 0.000E+00 6.670E+10 0.000E+00 1

.5000 h

-0.000E+00 0.000E+00 6.621E+10 1.196E+14 4.737E+07 2.632E+04 1.697E+03 3.464E-07 1.551E+06 2

1.5000 h 0.000E+00 0.000E+00 6.525E+1C 2.366E+14 9.371E+07 2.603E+04 1.739E+03 3.549E-07 6.184E+06 pry

,v 3

2.0000 h 0.000E+00 0.000E+00 6.478E+10 1.170E+14 4.634E+07 2.575E+04 4.741E+03 9.678E-07 5.916E+06 gy 4

2.5000 h 0.000E+00 0.000E+00 6.431E+10 1.162E+14 4.601E+07 2.556E+04 7.207E+03 1.471E-06 1.082E+07 f) 5 4.0000 h 0.000E+00 0.000E+00 6.291E+10 3.435E+14 1.360E+08 2.519E+04 1.224E+04 2.498E-06 5.377E+07 7e 6

8.0000 h 0.000E+00 0.000E+00 5.934E+10 8.800E+14 3.485E+08 2.420E+04 1.685E+04 3.440E-06 2.174E+08 3

7 8.5000 h 0.000E+00 0.000E+00 5.895E+10 1.065E+14 0.000E+00 0.000E+00 9.933E+02 1.824E-07 9.780E+06 d-0 24.0000 h 0.000E+00 0.000E+00 4.805E+10 2.975E+15 0.000E+00 0.000E+00 4.954E+01 1.011E-08 1.628E+07 5' "C}

9 96.0000 h 0.000E+00 0.000E+00 1.859E+10 8.042E+15 0.000E+00 0.000E+00 7.247E-05 1.479E-14 9.557E+05

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10 720.0000 h 0.000E+00 0.000E+00 4.959E+06 5.074E+15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.398E+00 s

+

Xe-133m TOTALS 0.000E+00 1.801E+16

.179E+08 3.227E+08

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A Xe-133 INITIAL 0.000E+00 2.880E+12 0.000E+00 e

1

.5000 h 0.000E+00 0.000E+00 2.870E+12 5.175E+15 2.049E+09 1.139E+06 7.356E+04 1.501E-05 6.719E+07

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2 1.5000 h 0.000E+00 0.000E+00 2.851E+12 1.030E+16 4.078E+09 1.133E+06 7.595E+04 1.550E-05 2.691E+08 (g) 3 2.0000 h 0.000E+00 0.000E+00 2.841E+12 5.123E+15 2.029E+09 1.127E+06 2.079E+05 4.244E-05 2.591E+08 (73 4

2.5000 h 0.000E+00 0.000E+00 2.831E+12 5.105E+15 2.022E+09 1.123E+06 3.173E+05 6.477E-05 4.757E+08 5

4.0000 h 0.000E+00 0.000E+00 2.803E+12 1.521E+16 6.024E+09 1.116E+06 5.450E+05 1.112E-04 2.384E+09 6

8.0000 h C.000E+00 0.000E+00 2.727E+12 3.981E+16 1.577E+10 1.095E+06 7.720E+05 1.576E-04 9.068E+09 7

8.5000 h 0.000E+00 0.000E+00 2.720E+12 4.903E+15 0.000E+00 0.000E+00 4.108E+04 8.387E-06 4.485E+08 8 24.0000 h 0.000E+00 0.000E+00 2.502E+12 1.456E+17 0.000E+00 0.000E+00 2.571E+03 5.240E-07 7.754E+08

}

9 96.0000 h 0.000E+00 0.000E+00 1.693E+12 5.370E+17 0.000E+00 0.000E+00 6.577E-03 1.342E-12 5.175E+07 ojf 10 720.0000 h 0.000E+00 0.000E+00 5.492E+10 1.076E+18 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.324E+02 7,

Xe-133 TOTALS 0.000E+00 1.844E+18 3.197E+10 1.460E+10 b

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UNIT 2 LOCKED ROTOR CASE 2 (PAGE 6)

N TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 ay Case 2 - Primary to Secondary Noble Cases / CR & LPZ, Dose (1/15/98)[TC913586.DAT *** PROGENY INGROWTH ON ***

Not used this case 3 S/Gs AVERAGE

-CONTROL ROCM 1*

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD k

STEP TIME uCi uCi-see uCi uCi-sec uCi uC1/see uC1 uC1/cc

-UCi-sec 5-Xe-135m INITIAL 0.000E+00 7.560E+11 0.000E+00 y

1

.5000 h 0.000E+00 0.000E+00 1.951E+11 7.454E+14 2.952E408 1.640E+05 5.867E+03 1.190E-06 6.507E+06 y

2 1.5000 h 0.000E+00 0.000E+00 1.299E+10 2.420E+14 9.583E,07 2.662E+04 4.147E+02 8.466E-08 7.336E+06 E~

f.

3 2.0000 h 0.000E+00 0.000E+00

3. 353E+ 0 9 1. 281E+13 5.073E+06 2.819E+03 2.919E+02 5.958E-08 6.087E+05 4

2.5000 h 0.000E+00 0.000E+00 8.654E+08 3.306E+12 1.309E+06 7.274E+02 1.152E+02 2.351E-08 3.272E+05 h

W.

5 pL 5

4.0000 h 0.000E+00 0.000E+00 1.488E+07 1.130E+12 4.476Et05 0.289E+01 8.669E+00 1.770E-09 1.660E+05 6

8.0000 h 0.000E+00 0.000E+00 2.927E+02 1.977E+10 7.820E+03 5.436E-01 4.982E-02 1.017E-11 1.083E+04 7

8.5000 h 0.000E+00 0.000E+00 7.559E+01 2.887E+05 0.000E+00 0.000E+00 6.865E-04 1.401E-13 2.064E+01 g

8 24.0000 h 0.000E+00 0.000E+00 4.489E-17 1.005E+05 0.000E+00 0.000E+00 2.773E-23 5.661E-33 8.579E-01

~

9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 5.968E-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.465E-20 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-135m TOTALS 0.000E+00 1.005E+15 3.978E+08 1.496E+07 Xe-135 INITIAL O.000E+00 7.380E+11 0.000E+00 1

.5000 h 0.000E+00 0.000E+00 7.253E+11 1.320E+15 5.227E+08 2.904E+05 1.857E+04 3.791E-06 1.703E+07 2

1.5000 h 0.000E+00 0.000E+00 6.761E+11 2.525E+15 9.999E+08 2.77RE+05 1.002E+04 3.678E-06 6.596E+07 m

3 2.0000 h 0.000E+00 0.000E+00 6.506E+11 1.194E+15 4.728E+08 2.627E+05 4.764E+04 9.725E-06 6.006E+07 y

4 2.5000 h 0.000E+00 0.000E+00 6.260E+11 1.149E+15 4.549E+08 2.527E+05 7.020E+04 1.433E-05 1.068E+08 5

4.0000 h 0.000E+00 0.000E+00

5. 57 3E+ 11 3.191E+15 1.264E+09 2.340E+05 1.088E+05 2.221E-05 4.946E+08 y,

6 8.0000 h 0.000E+00 0.000E+00 4.087E+11 6.900E+15 2.732E+09 1.898E+05 1.197E+05 2.444E-05 1.667E+09 3

7 8.5000 h 0.000E+00 0.000E+00 3.935E+11 7.219E+14 0.000E+00 0.000E+00 6.152E+03 1.256E-06 6.888E+07 d-0 24.0000 h 0.000E+00 0.000E+00 1.210E+11 1.289E+16 0.000E+00 0.000E+00 1.287E+02 2.627E-08 8.690E+07 5~ "E) 9 96.0000 h 0.000E+00 0.000E+00 5.053E+08 5.700E+15 0.000E+00 0.000E+00 2.032E-06 4.140E-16 1.857E+06

~Q 10 720.0000 h 0.000E+00 0.000E+00 1.214E-12 2.391E+13 0.000E400 0.000E+00 0.000E+00 0.000E+00 2.932E-02 e

Xe-135 TOTALS 0.000E+00 3.562E+16 6.447E+09 2.570E+09 (O

A Xe-137 INITIAL 0.000E+00 2.520E+12 0.000E+00 e

1

.5000 h 0.000E+00 0.000E*10 1.104E+10 8.317E+14 3.293E+08 1.830E+05 2.231E+03 4.555E-07 3.304E+06 O

2 1.5000 h 0.000E+00 0.000E-e 2.122E+05 3.661E+12 1.450E+06 4.027E+02

1. 42 9E-01 2. 918E-11 7. 3 98E + 05 Q

3 2.0000 h 0.000E+00 0.000E.

9.299E+02 7.002E+ 07 2.773E+01 1.540E-02 9.078E-04 1.853E-13 4.627E+01 g

4 2.5000 h 0.000E+00 0.000E+00 4.076E+00 3.069E+05 1.215E-01 6.752E-05 5.009E-06 1.023E-15 2.927E-01 5

4.0000 h 0.000E+00 0.000E+00 3.431E-07 1.351E+03 5.350E-04 9.907E-08 2.481E-09 5.065E-19 1.620E-03 6

8.0000 h 0.000E+00 0.000E+00 4.672E-26 1.137E-04 4.504E-11 3.128E-15 7.833E-17 1.599E-26 7.962E-07 1

7 8.5000 h 0.000E+00 0.000E+00 2.049E-28 1.542E-23 0.000E+00 0.000E+00 1.833E-20 3.742E-30 1.686E-14 0 24.0000 h 0.000E+00 0.000E+00 0.000E+00 6.794E-26 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.982E-18 y

10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00

~0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 o

9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

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g Xe-137 TOTALS 0.000E+00 8.354E+14 3.308E+08 4.044E+06 g

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UNIT 2 LOCKED ROTOR CASE 2 (PAGE 7) jyg TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

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{d Not used this case-3 S/Gs AVERAGE CONTROL ROOM a

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-see uCi uCi-sec uCi uCi/sec uCi uC1/cc uCi-sec, E !

Xe-138 INITIAL 0.000E+00 2.520E+12 0.000E+00

2 l

1

.5000 h 0.000E+00 0.000E+00 5.780E+11 2.374E+15 9.401E+08 5.223E+05 1.787E+04 3.648E-06 2.010E+07 3

2 1.5000 h 0.000E+00 0.000E400 3.042E+10 6.695E+14 2.651E+08 7.364E+04-1.002E+03 2.046E-07 2.085E+C7 E'

3 2.0000 h 0.000E+00 0.000E+00 6.977E+09 2.865E+13 1.135E+07 6.304E+03 6.254E+02 1.277E-07 1.376E+06 E {.

4 2.5000 h 0.000E+00 0.000E+00 1.600E+09 6.573E+12 2.603E+06 1.446E+03 2.193E+02 4.476E-08 6.639E+05 Y

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4.0000 h 0.000E+00 0.000E+00 1.932E+07 1.933E+12 7.654E+05 1.417E+02 1.351E+01 2.758E-09 2.893E+05 6

8.0000 h 0.000E+00 0.000E+00 1.481E+02 2.361E+10 9.351E+03 6.494E-01 5.524E-02 1.128E-11 1.546E+04 g

7 8.5000 h 0.000E+00 0.000E+00 3.399E+01 1.395E+05 0.000E+00 0.000E+00 6.767E-04 1.381E-13 2.231E+01 Q

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8 24.0000 h 0.000E+00 0.000E+00 5.228E-19 4.157E+04 0.000E+00 0.000E+00 7.082E-25 1.446E-34 7.816E-01 9 96.0000 h 0.000E+00 0.000E+00 0.000E+00 6.395E-16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.180E-22 10 720.0000 h 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-138 TOTALS 0.000E+00 3.081E+15 1.220E+09 4.330E+07 TT1 33 C

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8.0000 h 1.58E-04 3.96E-05 8. 21 E'-0 5 2.05E-05 0.00E+00 0.00E+00 4.45E-05 5.72E-07 4.58C-04 5.90E-06 0.00E+00 0.00E+00 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' 6.42E-08 7.01E-09 6.62E-07 7.22E-00 0.00E+00 0.00E+00 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.25E-09 7.34E-30 2.32E-08 7.5(E-29 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.41E-30 0.00E+00 1.46E-29 0.00E+00 0.00E+00 0.00E+00 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0CE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 2.07E+01 1.01E+01 0.00E+00 1.25E-01 1.2BE+00 0.00E+00 y

ALL NUCLIDES

.5000 h 6.64E+01 1.33E+02 4.5EE+01 9.15E+01 0.00E+00 0.00E+00 2.97E-01 1.09E+00 3.64E+00 1.30E+01 'O.00E+00 0'.00E+00 y

1.5000 h 7.31E+01 7.31E+01 4.21E+01 4.21E+01 0.00E+00 0.00E+00 8.33E-01 6.91E-01 9.59E+00 7.92E+00 0.00E+00 0.00E+00 2.0000 h 2.80E+01 5.61E+01 1.61E+01 3.23E+01 0.00E+00 0.00E+00 5.97E-01 1.65E+00 6.84E+00 1.89E+01- 0.00E+00 0.00E+00 g

2.5000 h 2.45E+01 4.91E+01 1.42E+01 2.84E+01 0.00E+00 0.00E+00 9.74E-01 2.22E+00 1.12E+01 2.57E+01 0.COE+00 0.00E+00 g

4.0000 h 5.80E+01 3.86E+01 3.46E+01 2.31E+01 0.00E+00 0.00E+00 3.77E+00 2.74E+00 4.52E+01 3.39E+01 0.00E+00 0.00E+00 d-8.0000 h 8.73E+01 2.18E+01 6.31E+01 1.58E+01 0.00E+00 0.00E+00 8.80E+00 1.97E+00 1.30E+02 3.29E+01 -0.00E+00 0.00E+00 5' "U 3

8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.11E-01 9.62E-02 5.25E+00 1.69E+00 0.COE+00 0.00E+00

~g 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.02E-01 1.50E-03 7.38E+00 7.00E.02 0.00E+00 0.00E+00 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.56E-03 2.79E-09 2.27E-01 1.59E-07 0.00E+00 0.00E+00 (p

720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.24E-09 0.00E+00 3.57E-07 0.00E+00 0.00E+00 0.00E+00

,yg TOTALS 3.37E+02 2.16E+02 0.00E+00 1.59E+01 2.20E+02 0.00E+00 eO C4 01

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UNIT 2 LOCKED ROTOR CASE 5 (PAGE 4) gg TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 3p Case 5 - Initial Secondary Liquid Iodines / CR & LPZ Dose (1/16/98) [TC913589.DA *** PROGENY INGROWTH ON ***

Not used this case 3 S/Gs AVERAGE OONTROL ROOM---

Q%

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CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD P.,

J STEP TIME uCi uCi-see uCi uCi-sec uCi uC1/see uCi uCi/cc uCi-see E-Xe-135m INITIAL 0.000E+00 0.000E+00 0.000E+00 y! l 1

.5000 h 0.000E+00 0.000E700 6.506E+05 7.240E+08 1.617E+03 8.985E-01 8.817E-02 1.800E-11 7.341E+01 g

2 1.5000 h 0.000E+00 0.000E+00 7.823E+05 2.742E+09 6.12SE+03 1.701E+00 1.181E-01 2.412E-11 3.991E+02 E'

3 2.0000 h 0.000E+00 0.000E+00 7.505E+05 1.382E+09 3.086E+03 1.715E+00 2.240E-01 4.573E-11 3.336E+02 ff w{3 4

2.5000 h 0.000E+00 0.000E+00 7.133E+05 1.318E+09 1.754E+03 9.747E-01 1.843E-01 3.762E-11 3.615E+02 5

4.0000 h 0.000E+00 0.000E+00 6.060E+05 3.556E+09 4.734E+03 8.767E-01 1.382E-01 2.820E-11 8.372E+02 g

6 8.0000 h 0.000E+00 0.000E+00 3.908E+05 7.064E+09 9.406E+03 6.532E-01

8. 591E-02 1.754E-11 1. 427E+03 3

7 8.5000 h 0.000E+00 0.000E+00 3.709E+05 6.854E+08 0.000E+00 0.000E+00 2.278E-03 4.651E-13 4.030E+01 2

8 24.0000 h 0.000E+00 0.000E+00 7.300E+04 1.023E+10 0.000E+00 0.000E+00 2.013E-05 4.110E-15 2.016E+01 5

9 96.0000 h 0.000E+00 0.000E+00 3.840E+01 2.505E+09 0.000E+00 0.000E+00 4.004E-14 8.173E-24 2.605E-01 10 720.0000 h 0.000E+00 0.000E+00 1.466E-27 1.318E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.180E-10 Xe-135m TOTALS 0.000E+00 3.020E+10 2.672E+04 3.493E+03 Xe-135 INITIAL 0.000E+00 0.000E+00 0.000E+00 1

.5000 h 0.000E+00 0.000E+00 1.817E+05 1.625E+08 3.631E+02 2.017E-01 2.606E-02 5.320E-12 1.984E+01 2

1.5000 h 0.000E+00 0.000E+00 5.225E+05 1.284E+09 2.869E+03 7.969E-01 7.879E-02 1.608E-11 1.903E+02 ry]

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gy 4

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6 8.0000 h 0.000E+00 0.000E+00 1.555E+06 1.993E+10 2.653E+04 1.843E+00 1.12eE+00 2.302E-10 1.370E+04 Q

7 8.5000 h 0.000E+00 0.000E+00 1.580E+06 2.822E+09 0.000E+00 0.000E+00 5.833E-02 1.191E-11 6.500E+02 8 24.0000 h 0.000E+00 0.000E+00 1.122E+06 8.163E+10 0.000E+00 0.000E+00 1.396E-03 2.050E-13 8.562E+02 5' "t!

9 96.0000 h 0.000E+00 0.000E+00 8.819E+03 6.736E+10 0.000E+00 0.000E+00 2.636E-11 5.380E-21 2.061E+01 f,((J 10 720.0000 h 0.000E+00 0.000E+00 2.262E-17 4.250E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.812E-07 Xe-135 TOTALS 0.000E+00 1.813E+11 4.095E+04 1.905E+04 (C)

A I-131 INITIAL 0.000E+00 8.610E+06 0.000E+00 e

1

.5000 h 0.000E+00 0.000E+00 8.560E+06 1.545E+10 3.452E+04 1.918E+01 1.240E+00 2.530E-10 1.132E+03

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2 1.5000 h 0.000E+00 0.000E+00 0.461E+06 3.064E+10 6.844E+04 1.901E+01 1.282E+00 2.617E-10 4.539E+03 (4) 3 2.0000 h 0.000E+00 0.000E+00 8.412E+06 1.519E+10 3.392E+04 1.885E+01 1.214E+00 2.478E-10 2.244E+03 (yy 4

2.5000 h 0.000E+00 0.000E+00 8.377E+06 1.511E+10 2.012E+04 1.118E+01 1.098E+00 2.241E-10 2.077E+03 5

4.0000 h 0.000E+00 0.000E+00 8.272E+06 4.495E+10 5.985E+04 1.108E+01 8.516E-01 1.738E-10 5.203E+03 6

8.0000 h 0.000E+00 0.000E+00 7.999E+06 1.171E+11

1. 560E+ 05 1. 083E+ 01 5.820E-01 1.190E-10 9.873E+03 7

8.5000 h 0.000E+00 0.000E+00 7.985E+06 1.439E+10 0.000E+00 0.000E+00 3.104E-02 6.337E-12 3.387E+02

}7 8 24.0000 h 0.000E+00 0.000E+00 7.552E+06 4.334E+11 0.000E+00 0.000E+00 1.997E-03 4.077E-13 5.900E+02 g

9 96.0000 h 0.000E+00 0.000E+00 5.831E+06 1.725E+12 0.000E+00 0.000E+00 5.831E-09 1.190E-18 4.063E+01 OL 10 720.0000 h 0.000E+00 0.000E+00 6.198E+05 5.223E+12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.186E-04 j

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UNIT 2 LOCKED ROTOR CASE 5 (PAGE 5) g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 7p Case 5 - Initial Secondary Liquid Iodines / CR & LPZ Dose (1/16/98) [TC913589.DA *** PROGENY INGROWTH ON ***

Not used this case 3 S/Gs AVERAGE CONTROL ROOM Z

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD kWh STEP TIME uCi uCi-sec uCi uCi-sec uCi uC1/sec uCi uCi/cc uCi-sec 9

I I-132 INITIAL 0.000F'00 2.540E+06 0.000E+00 l$ l 1

.5000 h 0.000E+c0 0.000E+00 2.176E+ 06 4.236E+09 9.463E+03 5.257E+00 3.161E-01 6.452E-11 2.957E+02 2

1.5000 h 0.000E+00 0.000E400 1.597E+06 6.737E+09 1.505E+04 4.181E+00

2. 4 27E-01 4. 955E-11 9. 9 91E+ 02 M'

3 2.0000 h 0.000E+00 0.000E+00 1.368E+06 2.663E+09 5.949E+03 3.305E+00 1.981E-01 4.043E-11 3.945E+02

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4 2.5000 h 0.000E+00 0.000E+00 1.174E+06 2.283E+09 3.040E+03 1.689E+00 1.544E-01 3.151E-11 3.150E+02 5

4.0000 h 0.000E+00 0.000E+00 7.416E+05 5.083E+09 6.767E+03 1.253E+0C 7.727E-02 1.577E-11 5.915E402 3

6 8.0000 h 0.000E+00 0.000E+00 2.179E+05 6.157E+09 8.198E+03 5.693E-01 1.894E-02 3.866E-12 5.259E+02 g

7 8.5000 h 0.000E+00 0.000E+00 1.874E+05 3.641E+08 0.000E+00 0.000E+00 8.693E-04 1.774E-13 1.056E+01

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8 24.0000 h 0.000E+00 0.000E+00 1.7 55E+03 2.218E+09 0.000E+00 0.000E+00 5.535E-07 1.130E-16 6.587E+00 9 96.0000 h 0.000E+00 0.000E+00 6.617E-07 2.096E+07 0.000E+00 0.000E+00 7.893E-22 1.611E-31 4.197E-03 10 720.0000 h 0.000E+00 0.000E400 0.000E+00 7.905E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.985E-18 I-132 TOTALS 0.000E+00 2.976E+10 4.847E+04 3.139E+03 I-133 INITIAL 0.000E+00 1.230E+07 0.000E+00 1

.5000 h 0.000E+00 0.000E+00 1.205E+07 2.191E+10 4.895E+04 2.720E+01 1.745E+00 3.562E-10 1.b98E+03 2

1.5000 h 0.000E+00 0.000E+00 1.156E+07 4.249E+10 9.492E+04 2.637E+01 1.752E+00 3.576E-10 6.294E+03

[T1 3

2.0000 h 0.000E+00 0.000E+00 1.132E+07 2.059E+10 4.601E+04 2.556E+01 1.634E+00 3.336E-10 3.044E+03

=g}

4 2.5000 h 0.000E+00 0.000E+00 1.111E+07 2.019E+10 2.688E+04 1.493E+01 1.456E+00 2.972E-10 2.776E+03 sc (,f) 5 4.0000 h 0.000E+00 0.000E+00 1.049E+07 5.831E+10 7.764E+04 1.438E+01 1.081E+00 2.206E-10 6.751E+03 6

8.0000 h 0.000E+00 0.000E+00 9.000E+06 1.401E+11 1.866E+05 1.296E+01 6.632E-01 1.354E-10 1.180E+04 3

7 8.5000 h 0.000E+00 0.000E+00 8.860E+06 1.608E+10 0.000E+00 0.000E+00 3.481E-02 7.105E-12 3.838E+02 d'

8 24.0000 h 0.000E+00 0.000E+00 5.286E+06 3.861E+11 0.000E+00 0.000E+00 1.413E-03 2.883E-13 5.815E+02 5' "CI 9 96.0000 h 0.000E+00 0.000E+00 4.798E+05 5.192E+11 0.000E+00 0.000E+00 4.848E-10 9.896E-20 2.460E+01

[ ([l 10 720.0000 h 0.000E+00 0.000E+00 4.468E-04 5.183E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.442E-06 a

I-133 TOTALS 0.000E+00 1.277E+12 4.810E+05 3.325E+04 (f)

A I-134 INITIAL 0.000E+00 5.670E+04 0.000E+00 s

1

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2 1.5000 h 0.000E+00 0.000E+00 1.711E+04 9.430E+07 2.107E+02 5.852E-02 2.638E-03 5.386E-13 1.412E+01 (A) 3 2.0000 t 0.000E+00 0.000E+00 1.148E+04 2.539E+07 5.673E+01 3.151E-02 1.686E-03 3.441E-13 3.810E+00 yn 4

2.5000 n 0.000E+00 0.000E+00 7.711E+03 1.705E+07 2.269E+01 1.261E-02 1.029E-03 2.100E-13 2.386E+00 5

4.0000 h 0.000E+00 0.000E+00 2.338E+03 2.431E+07 3.237E+01 5.995E-03 2.551E-04 5.207E-14 2.893E+00 6

8.0000 h 0.000E+00 0.000E+00 9.706E+01 1.014E+07 1.351E+01 9.379E-04 1.614E-05 3.295E-15 9.448E-01 7

8.5000 h 0.000E+00 0.000E+00 6.537E+01 1.443E+05 0.000E+00 0.000E+00 5.802E-07 1.184E-16 8.423E-03 37 8 24.0000 h 0.000E+00 0.000E+00 3.111E-04 2.976E+05 0.000E+00 0.000E+00 1.878E-13 3.835E-23 2.166E-03 3

9 96.0000 h 0.000E+00 0.000E+00 5.880E-29 1.417E+00 0.000E+00 0.000E+00 1.345E-43 0.000E+00 7.014E-10 pp 10 720.0000 h

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UNIT 2 LOCKED ROTOR CASE 5 (PAGE 6)

. gg TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

'g Case 5 - Initial Secondary Liquid Iodines / CR.& LPZ Dose.(1/16/98) (TC913589.DA *** PROGENY INGROWTH CN ***

5 0,_

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1 2

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f 5

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l UNIT 2 LOCKED ROTOR CASE 5 (PAGE 9) jg TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

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8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.20E-08 1.84E-00 2.43E-07 1.20E-08 4.00E-05 1.19E-05

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8.0000 h 1.71E-03 4.27E-04 1.06E-03 2.65E-04 1.56E+00 3.91E-01 1.84E-05 3.71E-06 2.27E-04 4.59E-05 3.34E-01 6.76E-02 d*

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720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.25E-15 0.00E+00 6.49E-14 0.00E+00 9.57E-11 0.00E+00 (O

TOTALS 4.41E-03 2.74E-03 4.03E+00 5.17E-05 6.39E-04 9.42E-01 h

a0 1-134

.5000 h 7.44E-06 1.49E-05 1.59E-06 3.17E-06 9.85E-05 1.97E-04 3.66E-08 1.35E-07 1.55E-07 5.75E-07 9.63E-06 3.57E-05 Q

1.5000 h 8.34E-06 8.34E-06 1.78E-06 1.78E-06 1.10E-04 1.10E-04 9.50E-08 6.39E-08 4.03E-07 2.71E-07 2.50E-05 1.68E-05 g

2.0000 h 2.25E-06 4.49E-06 4.79E-07 9.57E-07 2.97E-05 5.94E-05 2.56E-08 4.08E-08 1.09E-07 1.73E-07 6.75E-06 1.07E-05 2.5000 h 8.99E-07 1.80E-06 1.92E-07 3.83E-07 1.19E-05 2.30E-05 1.60E-08 2.49E-08 6.81E-08 1.0GE-07 4.23E-06 6.56E-06 4.0000 h 1.28E-06 8.55E-07 2.73E-07 1.82E-07 1.70E-05 1.13E-05 1.95E-08 6.17E-09 8.25E-08 2.62E-08 5.12E-06 1.63E-06 8.0000 h 5.35E-07 1.34E-07 1.14E-07 2.85E-08 7.08E-06 1.77E-06 6.35E-09 3.91E-10 2.69E-08 1.66E-09 1.67E-06 1.03E-07 3*

8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.66E-11 1.40E-11 2.40E-10 5.96E-11 1.49E-08 3.70E-09 3

24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.46E-11 4.55E-18 6.18E-11 1.93E-17 3.84E-09 1.20E-15 g

96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.83E-18 0.00E+00 1.20E-17 0.00E+00 7.45E-16 0.00E+00 g

y 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0

p TOTALS 2.07E-05 4.42E-06

2. 7 5r.-04 1.99E-07 8.44E-07 5.24E-05 E.

a B..

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g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

$P, qg

. Case 5 - Initial Secondary Liquid Iodines / CR & LPZ Dose (1/16/98) [TC91358 9. DA *** PROGENY INGROWTH ON ***

M 57

ENVIRONMENT---------

CONTROL ROON-------

f PHOTON-SUBMG BETA-SUBMG THYROID-INHAL PHOTON-SUBMG BETA-SUBMG THYROID-INHAL

@, d

-l DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE " ATE ii-5 mrem mrem /hr mrem mrem /hr arem mrem /hr mrem mrem /hr mrem mrem /hr mrem m r e.-

nr 22 l 3

I-135

.5000 h 5.13E-04 1.03E-03 1.10E-04 2.20E-04 5.60E-02 1.12E-01 2.81E-06 1.10E-05 1.20E-05 4.70E-05 6.10E-03 2.39E-02 y'

1.5000 h 9.44E-04 9.44E-04 2.03E-04 2.03E-04 1.03E-01 1.03E-01 1.06E-05 1.03E-05 4.54E-05 4.39E-05 2.31E-02 2.23E.

2.0000 h 4.33E-04 8.67E-04 9.31E-05 1.86E-04 4.73E-02 9.45E-02 4.87E-06 9.25E-06 2.00E-05 3.95E-05 1.06E-02 2.01E-02 2.5000 h 2.44E-04 4.89E-04 '5.25E-05 1.05E-04 2.66E-02 5.33E-02 4.29E-06 7.95E-06 1.83E-05 3.40E-05 9.30E-03 1.73F-02 NG 4.0000 h 6.57E-04 4.38E-04 1.41E-04 9.41E-05 7.17E-02 4.78E-02 9.72E-06 5.31E-06 4.15E-05 2.27E-05 2.11E-02 1.15E-02 8.0000 h 1.31E-03 3.26E-04 2.80E-04 7.01E-05 1.42E-01 3.56E-02 1.40E-05 2.52E-06 5.99E-05 1.00E-05 3.04E-02.5.47E-03 2*

8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '4.01E-07 1.28E-07 1.71E-06 5.45E-07 8.70E-04 2.77E-04 24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 4.52E-07 1.71E-09 1.93E-06 7.30E-09 9.82E-04 3.71C-06 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.68E-09 3.40E-18 1.57E-06 1.45E-17 0.00E-06 7.38E-15 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.88E-18 0.00E+00 2.09E-17 0.00E+00 1.06E-14 0.00E+00 TOTALS 4.10E-03 8.80E-04 4.47E-01 4.72E-05 2.02E-04 1.02E-01 ALL NUCLIDES

[T]

.5000 h 1.51E-03 3.01E-03 5.50E-04 1.10E-03 1.55E+00 3.10E+00 8.27E-06 2.24E-05 6.05E-05 2.37E-04 1.71E-01 6.74E-01 gy 1.5000 h 2.79E-03 2.79E-03 1.05E-03 1.05E-03 3.04E+00 3.04E+00 3.14E-05 3.04E-05 2.35E-04 2.33E-04 6.81E-01 6.88E-01

,f) 2.0000 h 1.29E-03 2.57E-03 5.01E-04 1.00E-03 1.49E+00 2.98E+00 1.47E-05 2.84E-05 1.15E-04 2.27E-04 3.34E-01 6.48E-01 73 2.5000 h 7.31E-04 1.46E-03 2.90E-04 5.81E-04 8.79E-01 1.76E+00 1.33E-05 2.48E-05 1.0BE-04 2.07E-04 3.07E-01 5.82E-01 3

4.0000 h. 2.01E-03 1.34E-03 8.28E-04 5.52E-04 2.59E+00 1.72E+00 3.15E-05 1.80E-05 2.80E-04 1.71E-04 7.60E-01 4.44E-01 d'

8.0000 h 4.36E-03 1.09E-03 1.95E-03 4.89E-04 6.55E+00 1.64E+00 5.58E-05 1.17E-05 6.22E-04 1.47E-04 1.40E+00 2.93E-01 5' "I) 3 8.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J.87E-06 6.00E-07.2.35E-05 7.61E-06 4 73E-02 1.56E-02

~~ []) '

24.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.58E-06 2.05E-08 3.37E-05 2.74E-07 7.94E-02 9.02E-04 96.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.03E-08 2.49E-14 8.04E-07 3.11E-13 2.98E-03 2.25E-09 (C) 720.0000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.53E-14 0.00E+00 6.90E-13 0.00E+00 5.07E-09 0.00E+00 h

TOTALS 1.27E-02 5.17E-03 1.61E+01 1.60E-04 1.48E-03 3.78E+00 eO C4 U1 3$

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RTL: n/a Fonn: RE 1.103 3 9/93 g (Dr==1e Lkjit ERS-MPD-91-035 Pase #P Health Physics Department Revision 1 CASE 1 INPUT FILE

'L1 ',10,1.00E-5,3.47E-4,1.0,1.0E-4,3.47E-4,0,24,1,2

' Case 1 - Primary to Secondary Iodines / CR & LPZ Dose (1/16/98)[TC913585.DAT]'

'Cl ','RCS',3.960E-7,0.0,0.0,0.0.

'C2 ','3 S/Gs',2.234E-6,0.0,0.0,0.0

'CR ',1.73E5,10.,10.,0.0,0.94,0.0

'PRD',24

0.0

'PRD',24

0.0

'INI',1,00E+6,'Ci ',14

0.0,1.49E+6,1.78E+6,2. 88 E+6,3.24E+6,2. 52E+6,5

0.0

'INI',1.0,' ',24 *0.0

'INI',1,0,' ',24*0.0

' TIM',1800.,5400.,7200.,9000,14400.,28800.,30600.,86400.,3.456ES,2. 592E6

'XPR',10

0.0

'XPR',10

0.0

'XPR',50.0,1.0,4

104.,1690.,3

50.

'XRM',10

1.0

'XRM',3

1.0,3

0.596,4

0.0

'XRM',50.0,1.0,4

104.,1690.,3

50.

'XRF',10* 0.0

'XRF',2

0.0,4

1.0,4

0.0

'XOQ',6*6.04,2*4.33,2.10,0.744

'XBR',10* l.0

'XOQ',6* 1.59,2

0.786,0.596,0.376

'XBR',10

1.0

'OCC',8

1.0,0.6,0.4 i

4 l

RTL: n/a Form: RE 1.103 3 9/93 ha D

ERS-MPD-91-035 ray a Health Physics Department Revision 1 CASE 2 INPUT FILE

'L1 ',10,1.00E-5,3,47E-4,1.0,1.0E-4,3.47E-4,0,24,1,2

' Case 2 - Primary to Secondary Noble Gases / CR & LPZ Dose (1/15/98)[TC913586.DAT)'

'C1 ','Not used this case',0.000E-0,0.0,0.0,0.0

'C2 ','3 S/Gs',3.960E-7,0.0,0.0,0.0 1

'CR ',1.73ES,10.,10.,0.0,0.94,0.0

'PRD',24

0.0

'PRD',24

0.0

'IN1',1.00E+0,' ',24*0.0

)

'INI',1.00E+6,'Ci ',2.16E+5,5.40E+5,3.72E+4,1.06E+6,1.49E+6,1.98E+6,0.0,

7. 56E+3,6. 67E+4,2.88 E+ 6,7. 56E+5,7.38 E+5,2. 52 E+6,2. 52E+6,10

0. 0

'INI',1.0,' ',24

0.0

' TIM',1800.,5400.,7200.,9000,14400.,28800.,30600.,86400.,3.456E 5,2. 592 E6

'XPR',10

0.0

'XPR',10

0.0 i

'XPR',50.0,1.0,4

104.,1.69E+3,3

50.

'XRM',10* 1.0

'XRM',6

1.0,4

0.0

'XRM',50.0,1,0,4

104.,1.69E+3,3

50.

'XRF',10* 0.0

'XRF',10'0.0

'XRF',2

0.0,4

1.0,4

0.0

'XOQ',6*6.04,2*4.33,2.10,0.744

'XBR',10

l.0

'XOQ',6* 1.59,2* 0.786,0.596,0.376

'XBR',10

1.0

'OCC',8

1.0,0.6,0.4

RTL: nh Form: RE I.103-3 9/93

- h k, D " O ERS-MPD-91-035 m 47 ap Health Physics Department Revision 1 CASE 4 INPUT FILE

'L1 ',10,1.00E-5,3.47E-4,1,0,1.0E-4,3.47E-4,0,24,1,2

' Case 4 - Initial Steam Release / CR & LPZ Dose (1/16/98) [TC913588.DAT]'

'Cl ','Not used ths case',0.00E+0,0.0,0,0,0.0

'C2 ','3 S/Gs',1. 85E-1,0.0,0.0,0.0

'CR ',1.73E5,10.,10.,0.0,0.94,0.0

'PRD',24

0.0

'PRD',24

0.0

'INI',1,0,' ',24*0.0

'INI',1.00E+6,'Ci ',4.78 E-5,2.34E-4,1.23 E-3,1.33 E-4,3. 56E-4,1,12E-5,0,0, 1.20E-5,3.43 E-4,2.92E-3,1.21 E-4,3. 58E-4,1.82E-5,7.49E-5,6.73 E-3,1.99E-3, 9.63 E-3,4.43 E-5,4.31 E-3,5

0.0 1

'INI',1.0,' ',24*0.0

' TIM',1800.,5400.,7200.,9000,14400.,28800.,30600.,86400.,3.456 E 5,2. 592 E6

'XPR',10

0.0

'XPR',10

0.0

'XPR',50.0,1.0,4

104.,1.69E+3,3

50.

'XRM',10

1.0

'XRM',4

1.0,6

0.0

'XRM',50.0,1.0,4

104.,1.69E+3,3

50.

'XRF',10 *0.0

'XRF',2

0.0,4

1.0,4

0.0

'XOQ',6

6.04,2 *4.33,2.10,0.744

'XBR',10* 1.0

'XOQ',6

1. 59,2

0.786,0. 596,0.376

'XBR',10

l.0

'OCC',8

1.0,0.6,0.4 l

l l

.- -.. _. - ~ -

-- - ~ - -. -... -.. -.. -...

RTL: n/a Form: RE 1.103 3 9/92 k

E"" D ERS'-M PD-91-035 pas 2 7o

' Health Physics Department Revision 1 CASE 5 INPUT FILE

'L 1 ',10,1.00E-5,3.47E-4,1,0,1.0E-4,3.47E-4,0,24,1,2

' Case 5.- Taitial Secondary Liquid Iodines / CR & LPZ Dose (1/16/98) [TC913589.DAT]'

'C1 ','Not used this case',0.0,0.0,0.0,0.0

'C2 ','3 S/Gs',2.234E-6,0,0,0,0,0.0 1

'CR ',1.73 E5,10.,10.,0.0,0.94,0.0

'PRD',24

0.0

'. PRD',24*0.0

'INI',1,0,' ',24*0.0

)

'INI',1.00E+6,'Ci ',14

0.0,8.61 E+0,2.54E+0,1.23 E+ 1,5. 67E-2,5. 51 E+0,5

0.0

'INI',1.0,' ',24 *0.0

' TIM',1800.,5400.,7200.,9000,14400.,28800.,30600.,86400.,3.456E 5,2. 592 E6

'XPR',10* 0.0

'XPR',10

0.0

'XPR',50.0,1. 0,4

104.,1. 69E+3,3

50.

'XRM',10* 1.0 l

'XRM',3

l.0,3 *0.596,4 *0.0

'XRM',50.0,1.0,4*10e,; 59E+3,3*50.

'XRF',10

0.0

'XRF',10

0.0 l

'XRF',2

0.0,4

1.0,4

0.0

'XOQ',6*6.04,2*4.33,2.10,0.744

'XBR',10

1.0

'XOQ',6

1. 59,2

0.786,0. 596,0.376

'XBR',10

l.0

'OCC',8

l.0,0.6,0.4

l-RTL: n/a Fonn: RE I.103 3 9/93 Nk ao ERS-MPD-91-035 95 r/[

l Ilealth Physics Department Revision i I

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Case 1 - Primary to Secondary Iodines / CR Dose Rate (1/16/98)[TC85DR.DAT)

- - PROGENY INGROWTH ON ***

d.

a..P

=

s ii 4{

REMOVAL:

3.960E-07 1/sec 2.234E-06 1/see 1.000E+01 cfm g

NUC Grp 1 REL FR:

0.000E+00-0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL IT.:

0.000E+00 0.000E+00 INTAKE REDUCT: 9.400E-01 1

NUC Grp 3 REL FR:

O.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00

{

Y(.

MULTIPLIERS = = >

g$;:.

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF u

1 6.000E+01

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 2 1.800E+02

.000 1.00

.000~

.000 1.00

.000 50.0-50.0

.000 2*

3 3.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 4

6.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 5

9.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 6 1.200E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 7

1.500E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 8 1.800E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 9 2.100E+03

.000 1.00

.000

'1.00

.000 50.0 50.0

.000 10 2.40CE+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 m

11 2.700E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 y

CONTROL ROOM ENVIRONMENT ---

y X/Q Breathing Occupancy X/Q Breathing 9

s/M3 M3/s s/M3 M3/s i

1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 5' "U

{~Q MULTI PLIERS-==>

STEP TIME,s e

1 6.000E+01 1.59 1.00 1.00

.000 1.00 (D

2 1.800E+02 1.59 1.00 1.00

.000 1.00

.ak.

3 3.000E+02 1.59 1.00 1.00

.000 1.00 4

6.000E+02 1.59 1.00 1.00

.000 1.00 Q

5 9.000E+02 1.59 1.00 1.00

.000 1.00 (A) 6 1.200E+03 1.59 1.00 1.00

.000 1.00 m

7 1.500E+03 1.59 1.00 1.00

.000 1.00 8

1.800E+03 1.59 1.00 1.00

.000 1.00 9 2.100E+03 1.59 1.00 1.00

.000 1.00 10 2.400E+03 1.59 1.00 1.00

.000 1.00 35 11 2.700E+03 1.59 1.00 1.00

.000 1.00 3

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UNIT 2 LOCKED ROTOR CASE 1 DOSE RATE (PAGE 3) g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

=p Case 1 - Primary to Secondary Iodines / CR Dose Rate (1/16/98)(TC85DR.DAT}

*

PROGENY INGROWTH ON * *

RCS 3 S/Gs AVERAGE CONTROL ROOM---

CURRENT INTEGRD CURRENT INTEGRT WLEASED RELEASE CURRENT CURRENT INTEGRD k,

STEP TIME uC1 uCi-sec uC1 uCi-ser uCi/sec uCi uCi/cc uCi-sec i~r Xe-131m INITIAL 0.000E+00 0.000E+00 0.000E+00

2 l

1

.0167 h 6.602E+05 1.981E+07 1.569E+01 3.138E+02

.OO9E-04 1.168E-05 4.594E-08 9.379E-18 1.182E-06 3

2

.0500 h 1.980E+06 1.584E+08 1.411E+02 0.155E+03 1.822E-02 1.518E-04 1.120E-06 2.286E-16 6.372E-05 E'

3

.0833 h 3.300E+06 3.168E+08 3.919E+02 3.073E+04 6.866E-02 5.721E-04 5.013E-06 1.023E-15 3.557E-04 E

4

.1667 h 6.598E+06 1.485E+09 1.567E+03 2.743E+05 6.127E-01 2.042E-03 3.991E-05 8.147E-15 6.386E-03 Y

5

.2500 h 9.893E+06 2.474E+09 3.523E+03 7.440E+05 1.662E+00 5.540E-03 1.326E-04 2.707E-14 2.531E-02 3

6

.3333 h 1.319E+07 3.462E+09 6.259E+03 1.448E+06 3.234E+00 1.078E-02 3.112E-04 6.353E-14 6.581E-02 E

7

.4167 h 1.6482+07 4.449E+09 9.773E+03 2.385E+06 5.329E+00 1.776E-02 6.032E-04 1.231E-13 1.362E-01 5%

8

.5000 h 1.976E+07 5.436E+09 1.406E+04 3.556E+06 7.945E+00 2.648E-02 1.035E-03 2.113E-13 2.446E-01 9

.5833 h 2.305E+07 6.422E+09 1.913E+04 4.960E+06 1.108E+01 3.694E-02 1.634E-03 3.335E-13 3.991E-01 10

.6667 h 2.633E+07 7.407E+09

2. 4 97 E+ 04 6.596E+06 1.474E+01 4.912E-02 2.425E-03 4.950E-13 6.073E-01 b

11

.7500 h 2.961E+07 8.392E+09 3.158E+04 8.464E+06 1.891E+01 6.303E-02 3.433E-03 7.000E-13 8.770E-01 Xe-131m TOTALS 4.002E+10 2.847E+07 6.360E+01 2.362E+00 Xe-133m INITIAL O.000E+00 0.000E+00 0.000E+00 1

.0167 h 1.822E+07 5.468E+08 4.330E+02 8.660E+03 1.935E-02 3.225E-04 1.268E-06 2.588E-16 3.262E-05 m

2

.0500 h 5.463E+07 4.372E+09 3.893E+03 2.250E+05 5.027E-01 4.189E-03 3.088E-05 6.305E-15 1.158E-03 y

3

.0833 h 9.097E+07 0.736E+09 1.080E+04 8.474E+05 1.893E+00 1.578E-02 1.382E-04 2.821E-14 9.806E-03 4

.1667 h 1.816E+08 4.089E+10 4.312E+04 7.552E+06 1.687E+01 5.624E-02 1.098E-03 2.241E-13 1.758E-01

=

5

.2500 h 2.718E+08 6.801E+10 9.678E+04 2.045E+07 4.569E+01 1.523E-01 3.643E-03 7.437E-13 6.957E-01 9

6

.3333 h 3.616E+08 9.502E+10 1.717E+05 3.974E+07 8.877E+01 2.959E-01 8.535E-03 1.742E-12 1.806E+00 d-7

.4167 h 4.511E+08 1.219E+11 2.676E+05 6.536E+07 1.460E+02 4.867E-01 1.651E-02 3.371E-12 3.731E+00 5' "O 8

.5000 h 5.402E+08 1.487E+11 3.844E+05 9.728E+07 2.173E+02 7.244E-01 2.830E-02 5.776E-12 6.691E+00

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.5833 h 6.290E+08 1.754E+11 5.220E+05 1.355E+08 3.026E+02 1.009E+00 4.458E-02 9.100E-12 1.090E+01 e

10

.6667 h 7.173E+08 2.020E+11 6.803E+05 1.798E+08 4.017E+02 1.339E+00 6.605E-02 1.348E-11 1.656E+01 (f) 11 7500 h 8.054E+08 2.284E+11 8.589E+05 2.304E+08 5.146E+02 1.715E+00 9.335E-02 1.906E-11 2.387E+01 h

Xe-133m TOTALS 1.094E+12 7.771E+08 1.736E+03 6.443E+01 e

O Xe-133 INITIAL 0.000E+00 0.000E+00 0.000E+00 Q

1

.0167 h 2.566E+08 7.699E+09 6.097E+03 1.219E+05 2.724E-01 4.541E-03 1.786E-05 3.645E-15 4.594E-04 g

2

.0500 h 7.693E+08 6.156E+10 5.483E+04 3.169E+06 7.079E+00 5.899E-02 4.350E-04 8.879E-14 2.475E-02 3

.0833 h

1. 2 81E+ 0 9 1. 230E+11 1.522E+05 1.193E+07 2.666E+01 2.222E-01

1. 946E-03 3. 973E-13 1.381E-01 4

.1667 h 2.558E+09 5.760E+11 6.075E+05 1.064E+08 2.377E+02 7.923E-01 1.547E-02 3.158E-12 2.477E+00 5

.2500 h 3.831E+09 9.584E+11 1.364E+06 2.882E+08 6.439E+02 2.146E+00 5.135E-02 1.048E-11 9.804E+00 6

.3333 h

5. 09 9E+ 0 9 1. 34 0E+ 12 2.420E+06 5.602E+0B 1.251E+03 4.172E+00 1.203E-01 2.456E-11 2.546E+01 3

7

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6. 363E+ 0 9 1. 719E+12 3.774E+06 9.218E+08 2.059E+03 6.864E+00 2.329E-01 4.754E-11 5.262E+01 g

8

.5000 h 7.622E+09 2.098E+12 5.424E+06 1.372E+09 3.066E+03 1.022E+01 3.992E-01 8.149E-11 9.439E+01 g

9

.5833 h

8. 877E+09 2. 475E+12 7.368E+06 1.911E+09 4.270E+03 1.423E+01 6.292E-01 1.284E-10 1.538E+02 0

10

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Xe-133 TOTALS 1.543E+13 1.097E+10 2.450E+04 9.095E+02 m

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l UNIT 2 LOCKED ROTOR CASE 1 DOSE RATE (PAGE 4) g TRAILS _PO -- Transport of Radioactive Material in Linear Systems, v1.0 1p y Case 1 - Primary to Secondary Iodines / CR Dose Rate (1/16/98)[TC85DR.DAT]

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3. 319E+11 9. 7 51 E+13 3.147E+08 8.674E+10 1.930E+05 6.459E+02 3.04 9E+01 6.223E-09 7. 94 2E+03 11

.7500 h 3.427E+11 1.013E+14 3.655E+08 1.021E+11 2.280E+05 7.600E+02 3.965E+01 8.094E-09 1.053E+04 Xe-135m TOTALS 6.231E+14 4.092E+11 9.141E+05 3.229E+04 Xe-135 INITIAL 0.000E+00 0.000E+00 0.000E+00 1

.0167 h

2. 67 6E+09 8.020E+10 6.358E+04 1.271E+06 2.839E+00 4.731E-02 1.864E-04 3.804E-14 4.792E-03 IT1 2

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10

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Xe-135 TOTALS 1.683E+14 1.200E+11 2.680E+05 4.964E+03 eO I-131 INITIAL 1.490E+12 0.000E+00 0.000E+00 (4) 1

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8. t 01E+ 00 1. 7 97E-0 9 1. 6 55E+ 03 5

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10

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.7500 h 1.484E+12 4.454E+14 1.583E+09 4.487E+11 1.002E+06 3.341E+03 1.718E+02 3.507E-08 4.625E+04 30 p,

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UNIT 2 LOCKED ROTOR CASE 1 DOSE RATE (PAGE 5) d TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 "y g Case 1 - Primary to Secondary Iodines / CR Dose Rate (1/16/98)(TC85DR.DAT)

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CCHP: Not used this case COMP: 3 S/Gs COMP: Control Room

@ fl8 g%

VOLUME: 1.730E+05 Cu.Ft.

INITIAL:

0.000E+00 Kr-83m 2.160E+05 Kr-83m Ci 0.000E+00 Kr-83m 0.000E+00 Kr-85m 5.400E+05 Kr-85m 0.000E+00 Kr-85m 4

0.000E+00 Kr-8,5 3.720E+04 Kr-85 0.000E+00 Kr-85 d'

O.000E+00 Kr-87 1.060E+06 Kr-87 0.000E+00 Kr-87 0.000E+00 Kr-88 1.490E+06 Kr-88 0.000E+00 Kr-88 p

=

0.000E+00 Kr-89 1.980E+06 Kr-89 0.000E+00 Kr-89 y

0.000E+00 Xe-131m 7.560E+03 Xe-131m 0.000E+00 Xe-131m 5

0.000E+00 Xe-133m 6.670E+04 Xe-133m 0.000E+00 Xe-133m 0.000E+00 Xe-133 2.880E+06 Xe-133 0.000E+00 Xe-133-

~

0.000E+00 Xe-135m 7.560E+05 Xe-135m 0.000E+00 Xe-135m 0.000E+00 Xe-135 7.380E+05 Xe-135 0.000E+00 Xe-135 0.000E+00 Xe-137 2.520E+06 Xe-137 0.000E+00 Xe-137 0.000E+00 Xe-138 2.520E+06 Xe-130 0.000E+00 Xe-138 ACT MULT (to uC1):

1.000E+00 1.000E+06 1.000E+00 TT1 33 (n

n,

5' "U i O.

a eO C4 01 2

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UNIT 2 LOCKED ROTOR CASE 2 DOSE RATE (PAGE 2)

TRAILS _PC -- Transport of Radioactive Material in Linear Systems, d

v1.0 Case 2 - Primary to Secondary Noble Gases / CR Doserate (1/16/98)[TC86DR.DAT]

- - PROGENY INGROWTH Ore ***

7T ap.

X REMOVAL:

0.000E+00 1/sec 3.960E-07 1/see 1.000E+01 cfm E

u NUC Grp 1 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 9.400E-01 j,

NUC Grp 3 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 0

MULTIPLIERS - =>

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1

6.000E+01

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 5

3 2 1.800E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 E~

3 3.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 4

6.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 5 9.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 6 1.200E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000-7 1.500E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 8

1.000E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 9.

2.100E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 10 2.400E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 TT1 11 2.700E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 CONTROL ROOM

ENVIRONMENT ---

M X/Q Breathing Occupancy X/Q Breathing W

s Q]

s/M3 M3/s s/M3 M3/s 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-C4 W

MULTIPLIERS====>

5' T s

STEP TIME,s 1C 1

6.000E+01 1.59 1.00 1.00

.000 1.00 8

2 1.800E+02 1.59 1.00 1.00

.000 1.00 3

3.000E+02 1.59 1.00 1.00

.000 1.00

==h 4

6.000E+02 1.59 1.00 1.00

.000 1.00 80 5 9.000E+02 1.59 1.00 1.00

.000 1.00 6 1.200E+03 1.59 1.00 1.00

.000 1.00 j

(d 7 1.500E+03 1.59 1.00 1.00

.000 1.00 (J1 8 1.800E+03 1.59 1.00 1.00

.000 1.00 9 2.100E+03 1.59 1.00 1.00

.000 1.00 10 2.400E+03 1.59 1.00 1.00

.000 1.00 D

11 2.700E+03 1.59 1.00 1.00

.000 1.00 0"

a w

3 N..

u

a..

.g Y

E!

b we 4

k 1

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UNIT 2 LOCKED ROTOR CASE 2 DOSE RATE (PAGE 3) d TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 1p gqg Case 2 - Primary to Secondary Noble Gases / CR Doserate (1/16/98)[TC86DR.3AT]

- - PROGENY INGROWTH ON ***

P G7 Not used this case 3 S/Gs AVERAGE CONTROL ROOM---

%* d; 1

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD P

STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uC1/cc uCi-sec EF Kr-83m INITIAL 0.000E+00 2.160E+11 0.000E+00 l@

1

.0167 h 0.000E+00 0.000E+00 2.146E+11 1.292E+13 5.116E+06 R.57'E+04

1. 911E+02 3. 900E-08 5.741E+03 i

2

.0500 h 0.000E+00 0.000E+00 2.119E+11 2.559E+13 1.03 4E+07 f ot'04 5.644E+02 1.152E-07 4.540E+04 y'

3

.0833 h 0.000E+00 0.000E+00 2.093E+11 2.527Et13 1.0012+07 e 40 0+ ;4 9.261E+02 1.891E-07 8.950E+04

,{,.

4

.1667 h 0.000E+00 0.000E+00 2.027E+11 6.180E+13 2.447E+07 E ti.,

0 1.782E+03 3.637E-07 4.072E+05 5

.2500 h 0.000E+00 0.000E+00 1.964E+11 5.987E+13 2.371E+07 7.403E 2.571E+03 5.2488-07 6.538E+05 3

6

.3333 h 0.000E+00 0.000E+00

1. 903E+11 5. 8 00E+.'. 3 2.297E+07 7.%'4_+'4 3.298E+03 6.732E-07 8.811E+05 3g 7

.4167 h 0.000E+00 0.000E+00 1.844E+11 5.619E+13 2.225E+07 74417L+o, 3.965E+03 S.094E-07 1.090E+06 8

.5000 h 0.000E+00 0.000E+00 1.786E+11 5.444E+13 2.156E+07 7.186E+04 4.578E+03 9.344E-07 1.282E+06

~

9

.5833 h 0.000E+00 0.000E+00 1.730E+11 5.274E+13 2.039E+07 6.962E+04 5.138E+03 1.049E-06 1.458E+06 10

.6667 h 0.000C+00 0.000E+00 1.676E+11 5.110E+13 2.023E+07 6.745E+04 5.649E+03 1.153E-06 1.619E+06 11 7500 h 0.000E+00 0.000E+00 1.624E+11 4.950E+13 1.96CE+07 6.535E+04 6.113E+03 1.248E-06 1.765E+06 Kr-83m TOTALS 0.000E+00 5.074E+14 2.009E+08 9.296E+06 Kr-85m INITIAL 0.000E+00 5.400E+11 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 5.386E+11 3.236E+13 3.281E+07 2.136E+05 4.795E+02 9.787E-08 1.440E+04 rrt 2

.0500 h 0.000E+00 0.000E+00 5.358E+11 6.446E+13 2.553E+07 2.127E+05 1.427E+03 2.913E-07 1.145E+05 "g) 3

.0833 h 0.000E+00 0.000E+00 5.330E+11 6.413E+13 2.540E+07 2.116E+05 2.359E+03 4.815E-07 2.272E+05 4

.1667 h 0.000E+00 0.000E+00 5.261E+11 1.589E+14 6.291E+07 2.097E+05 4.624E+03 9.439E-07 1.049E+06 73 [,f) 5

.2500 h 0.000E+00 0.000E+00 5.193E+11 1.568E+14 6.210E+07 2.070E+05 6.797E+03 1.388E-06 1.715E+06 3

6

.3333 h 0.000E+00 0.000E+00 5.126E+11 1.548E+14 6.130E+07 2.043E+05 8.883E+03 1.813E-06 2.353E+06 d'

7

.4167 h 0.000E+00 0.000E+00 5.060E+11 1.528E+14 6.050E+07 2.017E+05 1.088E+04 2.221E-06 2.966E+06 5' "CI 8

.5000 h 0.000E+00 0.000E+00

4. 9 94 E+11 1. 508E+14 5.972E+07 1.991E+05 1.280E+04 2.613E-06 3.554E+06

[, ([J 9

.5833 h 0.000E+00 0.000E+00 4.930E+11 1.489E+14 5.895E+07 1.965E+05 1.464E+04 2.988E-06 4.117E+06 e

10

.6667 h 0.000E+00 0.000E+00 4.866E+11 1.469E+14 5.819E+07 1.940E+05 1.639E+04 3.347E-06 4.656E+06 (f) 11

.7500 h 0.000E+00 0.000E+00 4.803E+11 1.450E+14

5. 7 4 4E+07 1. 915E+ 05 1.808E+04 3. 6 90E-06 5.172E+06 Jb Kr-85m TOTALS 0.000E+00 1.376E+15 5.448E+08 2.594E+07 eO Kr-85 INITIAL 0.000E+00 3.720E+10 0.000E+00 (i) 1

.0167 h 0.000E+00 0.000E+00 3.720E+10 2.232E+12 8.839E+05 1.473E+04 3.311E+01 6.760E-09 9.939E+02 (73 2

.0500 h 0.000E+00 0.000E+00 3.720E+10 4.464E+12 1.768E+06 1.473E+04 9.906E+01 2.02?E-09 7.934E+03 3

.0833 h 0.000E+00 0.000E+00 3.720E+10 4.464E+12 1.768E+06 1.473E+04 1.646E+02 3.360E-08 1.582E+04 4

.1667 h 0.000E+00 0.000E+00

3. 719E +10 1.116E+13 4.419E+06 1.473E+04 3.268E+02 6.672E-08 7.378E+04 5

.2500 h 0.000E+00 0.000E+00 3.719E+10 1.116E+13 4.418E+06 1.473E+04 4.867E4 02 9.936E-08 1.221E+05 27 6

.3333 h 0.000E+00 0.000E+00 3.718E+10 1.116E+13 4.418E+06 1.473E+04 6.443E+02 1.315E-07 1.697E+05 3

7

.4167 h 0.000E+00 0.000E+00 3.718E+10 1.115E+13 4.417E+06 1.472E+04 7.996E+02 1.632E-07 2.166E+05

@h 8

.5000 h 0.000E+00 0.000E+00 3.717E+10 1.115E+13 4.417E+06 1.472E+04 9.526E+02 1.945E-07 2.629E+05 g

pe 9

.5833 h 0.000E+00 0.000E+00 3.717E+10 1.115E+13 4.416E+06 1.472E+04 1.103E+03 2.253E-07 3.085E+05 g

pj 10

.6667 h 0.000E+00 0.000E+00 3.717E+10 1.115E+13 4.415E+06 1.472E+04 1.252E+03 2.556E-07 3.534E+05

~

11 7500 h 0.000E+00 0.000E+00 3.716E+10 1.115E+13 4.415E+06 1.472E+04 1.399E+03 2.855E-07 3.977E+05 3'

EL Kr-85 TOTALS 0.000E+00 1.004E+14 3.975E+07 1.929E+06 5

a

?

m pa U2 4

8 tv v

w 3

- _ _ _ _ _ ~

UNIT 2 LOCKED RO'IDR CASE 2 DOSE RATE (PAGE 4) d TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 Case 2 - Primary to Secondary Noble Gases / CR Doserate (1/16/98)[TC86DR.DAT]

- - PROGENY INGROWTH ON ***

9gggg Not used this case 3 S/Gs AVERAGE CONTROL RON-

[

CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-see uci uCi-see uci uCi/sec uCi uCi/cc uCl-sec

P Kr-87 INITIAL 0.000E+00 1.060E+12 0.000E+00 EE 1

.0167 h 0.000E+00 0.000E+00 1.050E+12 6.331E+13 2.507E+07 4.179E+05 9.351E+02 1.909E-07 2.811E+04 2

.0500 h 0.000E+00 0.000E+00 1.031E+12 1.249E+14 4.946E+07 4.122E+05 2.747E+03 5.607E-07 2.213E+05 6'

3

.0833 h 0.000E+00 0.000E+00 1.013E+12 1.227E+14 4.857E+07 4.047E+05 4.482E+03 9.150E-07 4.342E+05 4

.1667 h 0.000E+00 0.?00E+00 9.677E+11 2.970E+14 1.176E+08 3.921E+05 8.506E+03 1.736E-06 1.954E+06 S

t; 5

.2500 h 0.000E+00 0.000E+00 9.246E+11 2.838E+14 1.124E+08 3.746E+05 1.210E+04 2.471E-06 3.097E+C6 E"

6

.3333 h 0.000E+00 0.000E+00 8.835E+11 2.712E+14 1.074E+08 3.579E+05 1.531E+04 J.126E-06 4.117E+06 5

7

.4167 h 0.000E+00 0.000E+00 8.441E+11 2.591E+14 1.026E+08 3.420E+05 1.816E+04 3.707E-06 5.025E+06 8

.5000 h 0.000E+00 0.000E+00 8.066E+11 2.476E+14 9.803E+07 3.268E+05 2.067E+04 4.220E-06 5.029E+06

~

9

.5833 h 0.000E+00 0.000E+00 7.706E+11 2.365E+14 9.367E+07 3.122E+05 2.288E+04 4.671E-06 6.537E+06 10

.6667 h 0.000E+00 0.000E+00 7.363E+11 2.260E+14 8.950E+07 2.983E+05 2.431E+04 5.065E-06 7.157E+06 11

.7500 h 0.000E+00 0.000E+00 7.036E+11 2.159E+14 8.551E+07 2.650E+05 2.649E+04 5.406E-06 7.697E+06 Kr-87 TOTALS 0.000E+00 2.348E+15 9.298E+08 4.210E+07 Kr-88 INITIAL 0.000E+00 1.490E+12 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 1.484E+12 8.922E+13 3.533E+07 5.888E+05 1.321E+03 2.697E-07 3.968E+04 TTI 2

.0500 h 0.000E+00 0.000E+00 1.472E+12 1.773E+14 7.023E+07 5.852E+05

3. 919E+03 8. 001E-07 3.14 8E+05 "K) 3

.0833 h 0.000E+00 0.000E+00 1.460E+12 1.759E+14 6.966E+07 5.805E+05 6.461E+03 1.319E-06 6.232E+05 4

.1667 h 0.000E+00 0.000E+00 1.430E+12 4.335E+14 1.717E+08 5.722E+05 1.257E+04 2.566E-06 2.860E+06 73 (e )

f 5

.2500 h 0.000E+00 0.000E+00 1.401E+12 4.247E+14 1.682E+08 5.606E+05 1.834E+04 3.744E-06 4.642E+06 Q

@! ]II 6

.3333 h 0.000E+00 0.000E+00 1.373E+12 4.161E+14

1. 64 BE+ 08 5.4 93E+05 2.379E+04 4. 857E-06 6.325E+06 7

.4167 h 0.000E+00 0.000E+00 1.345E+12 4.077E+14 1.614E+08 5.382E+05 2.893E+04 5.906E-06 7.913E+06 2"

8

.5000 h 0.000E+00 0.000E+00 1.318E+12 3.994E+14 1.582E+08 5.273E+05 3.377E+04 6.094E-06 9.410E+06

[. ([J 9

.5833 h 0.000E+00 0.000E+00 1.291E+12 3.913E+14 1.550E+08 5.166E+05 3.833E+04 7.825E-06 1.082E+07 8

10

.6667 h 0.000E+00 0.000E+00 1.265E+12 3.834E+14 1.518E+08 5.061E+05 4.262E+04 8.701E-06 1.215E+07 (S) 11 7500 h 0.000E+00 0.000E+00 1.239E+12 3.757E+14 1.488E+08 4.959E+05 4.665E+04 9. 523E-06 1. 33 9E+ 07

-ab Kr-88 TOTALS 0.000E+00 3.674E+15 1.455E+09 6.849E+07 O'

Kr-89 INITIAL 0.000E+00 1.980E+12 0.000E+00 (i) 1

.0167 h 0.000E+00 0.000E+00 1.590E+12 1.067E+14 4.224E+07 7.040E+05 1.421E+03 2.901E-07 4.421E+04 (J1 2

.0500 h 0.000E+00 0.000E+00 1.025E+12 1.544E+14 6.116E+07 5.097E+05 2.764E+03 5.642E-07 2.570E+05 3

.0833 h 0.000E+00 0.000E+00 6.612E+11 9.959E+13 3.944E+07 3.287E+05 2.967E+03 6.056E-07 3.447E+05 4

.1667 h 0 900E+00 0.000E+00 2.208E+11 1.204E+14 4.770E+07 1.590E+05 2.057E+03 4.199E-07 7.288E+05 5

.2500 h 0.J00E+00 0.000E+00 7.372E+10 4.022E+13 1.593E+07 5.309E+04 1.038E+03 2.119E-07 4.365E+05 f{

6

.3333 h 0.000E+00 0.000E+00

2. 4 62E+10 1. 34 3E+13 5.318E+06 1.773E+04 4.621E+02 9.433E-00 2.093E+05 7

.4167 h 0.000E+00 0.000E+00 8.220E+ 09 4. 4 85E+12 1.776E+06 5.920E+03 1.923E+02 3.926E-08 9.082E+04 Eh a

8

.5000 h 0.000E+00 0.000E+00

2. 7 4 5E+ 0 9 1. 4 97E+12 5.930E+05 1.977E+03 7.674E401 1.567E-08 3.721E+04 3

m 9

.5833 h 0.000E+00 0.000E+00 9.165E+08 5.000E+11 1.900E+05 6.601E+02 2.975E+01 6.072E-09 1.469E+04

'p 10

.6667 h 0.000E+00 0.000E+00 3.060E+08 1.670E+11 6.612E+04 2.204E+02 1.129E+01 2.304E-09 5.653E+03 11

.7500 h 0.000E+00 0.000E+00 1.022E+08 5.576E+10 2.200E+04 7.360E+01 4.216E+00 8.606E-10 2.133E+03 El Kr-89 TOTALS 0.000E+00 5.415E+14 2.~44E+08 2.171E+06

?

a 3

l On l

A S

l G

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9 t

l d

i

_ ~ _ _-.~.

i UNIT 2 LOCKED ROTOR CASE 2 DOSE RATE (PAGE 5) jQ TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 1r,qg M

Case 2 - Primary to Secondary Noble Gases / CR Doserate (1/16/ 98) [TC86DR. DAT)

- - PROGENY INGROWTH ON ***

P Not used this case 3 S/Gs AVERAGE

CONTROL ROOM--

Z CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD k

STEP TIME uCi uCl-sec uCi uCi-sec uCi uC1/see uCi uC1/cc uCi-sec EE Xe-131m INITIAL 0.000E+00 7.560E+09 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 7.560E+09 4.536E+11 1.796E+05 2.994E+03 6.729E+00 1.374E-09 2.020E+02 l

2

.0500 h 0.000E+00 0.000E+00 7.559E+09 9.071E+11 3.592E+05 2. 993E+03 2.013E+01 4.109E-09 1.612E+03 y'

(

3

.0833 h 0.000E+00 0.000E+00 7.558E+09 9.070E+11 3.592E+05 2.993E+03 3.345E+01 6.827E-09 3.215E+03 i

4

.1667 h 0.000E+00 0.000E+00 7.555E+09 2.267E+12 8.977E+05 2.992E+03 6.640E+01 1.355E-08 1.499E+04 Y

L 6

.3333 h 0.000E+00 0.000E+00 7.550E+09 2.265E+12 8.971E+05 2.990E+03 1.308E+02 2.671E-08 3.446E+04 jf FL

[

5

.2500 h 0.000E+00 0.000E+00

7. 553E+09 2.266E+12 8.974E+05 2.991E+03 9.886E+01 2.018E-08 2.480E+04 3

j 7

.4167 h 0.000E+00 0.000E+00

7. 54 8E+09 2.265E+12 8.968E+05 2.989E+03 1.623E+02 3.314E-08 4.399E+04

@~

8

.5000 h 0.000E+00 0.000E+00

7. 54 5E+09 2.264E+12 8.965E+05 2.988E+03 1.934E+02 3.947E-08 5.337E+04 9

.5833 h 0.000E+00 0.000E+00 7.543E+09 2.263E+12 8.962E+05 2.987E+03 2.239E+02 4.571E-08 6.261E+04 10

.6667 h 0.000E+00 0.000E+00 7.541E+09 2.263E+12 8.960E+05 2.987E+03 2.540E+02 5.186E-08 7.171E+04 11

.7500 h 0.000E+00 0.000E+00 7.538E+09 2.262E+12 8.957E+05 2.986E+03 2.837E+02 5.791E-08 8.067E+04 Xe-131m TOTALS 0.000E+00 2.038E+13 0.071E+06 3.916E+05 Xe-133m INITIAL 0.000E+00 6.670E+10 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 6.668E+10 4.002E+12 1.585E+06 2.641E+04 5.936E+01 1.212E-08 1.782E+03

[7]

2

.0500 h 0.000E+00 0.000E+00 6.665E+10 8.000E+12 3.168E+06 2.640E+04 1.775E+02 3.623E-08 1.422E+04

"[)

3

.0833 h 0.000E+00 0.000E+00 6.662E+10 7.996E+12 3.166E+06 2.639E+04 2.948E+02 6.018E-08 2.835E+04 ss (,f) 4

.1667 h 0.000E+00 0.000E+00 6.654E+10 1.997E+13 7.909E+06 2.636E+04 5.847E+02 1.194E-07 1.320E+05 5

.2500 h 0.000E+00 0.000E+00 6.646E+10 1.995E+13 7.900E+06 2.633E+04 8.698E+02 1.776E-07 2.183E+05 3

6

.3333 h 0.000E+00 0.000E+00 6.638E+10 1.992E+13 7.890E+06 2.630E+04 1.150E+03 2.348E-07 3.031E+05 d'

7

.4167 h 0.000E+00 0.000E+00 6.630E+10 1.990E+13 7.881E+06 2.627E+04 1.426E+03 2.911E-07 3.865E405 3' "I3 8

.5000 h 0.000E+00 0.000E+00 6.621E+10 1.988E+13 7.871E+06 2.624E+04 1.697E+03 3.464E-07 4.685E+05

[_ (((

9

.5833 h 0.000E+00 0.000E+00 6.613E+10 1.985E+13 7.861E+06 2.620E+04 1.963E+03 4.008E-07 5.491E+05 a

10

.6667 h 0.000E+00 0.000E+00 6.605E+10 1.983E+13 7.852E+06 2.617E+04 2.225E+03 4.543E-07 6.284E+05 (f) 11

.7500 h 0.000E+00 0.000E+00 6.597E+10 1.980E+13 7.842E+06 2.614E+04 2.483E+03 5.069E-07 7.064E+05

-h Xe-133m TOTALS 0.000E+00 1.791E+14 7.093E+07 3.437E+06 sO Xe-133 INITIAL 0.000E+00 2.880E+12 0.000E+00 (4) 1

.0167 h 0.000E+00 0.000E+00 2.880E+12 1.128E+14 6.842E+07 1.140E+06 2.563E+03 5.233E-07 7.694E+04 (y]

2

.0500 h 0.000E+00 0.000E+00 2.879E+12 3.455E+14 1.368E+08 1.140E+06 7.667E+03 1.565E-06 6.141E+05 3

.0833 h 0.00CE+00 0.000E+00 2.878E+12 3.454E+14 1.368E+08 1.140E+06 1.274E+04 2.600E-06 1.225E+06 4

.1667 h 0.000E+00 0.000E+00 2.877E+12 8.633E+14 3.419E+08 1.140E+06 2.528E+04 5.161E-06 5.708E+06 5

.2500 h 0.000E+00 0.000E+00 2.875E+12 8.628E+14 3.417E+08 1.139E+06 3.763E+04 7.682E-06 9.442E+06 37 6

.3333 h 0.000E+00 0.000E+00 2.873E+12 8.623E+14 3.415E+08 1.138E+06 4.979E+04 1.016E-05 1.312E+07 7

7

.4167 h 0.000E+00 0.000E+00 2.872E+12 8.618E+14 3.413E+08 1.138E+06 6.177E+04 1.261E-05 1.674E+07 OL 8

.5000 h 0.000E+00 0.000E+00 2.870E+12 8.613E+14 3.411E+08 1.137E+06 7.355E+04 1.501E-05 2.030E+07 g

9

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p 10

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~

11

.7500 h 0.000E+00 0.000E+00 2.865E+12 0.598E+14 3.405E+08 1.135E+06 1.078E+05 2.201E-05 3.067E+07 30 "L

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UNIT 2 LOCKED ROTOR CASE 2 DOSE RATE (PAGE 6) jQ TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0

=7 Case 2 - Primary to Secondary Noble Gases / CR Doserate [1/16/98)[TC66DR.DAT)

*

PROGENY INGROWTH ON * *

Not used this case 3 S/Gs AVERAGE CONTROL ROOM hl CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD k

STEP TIME uCi uCi-sec uC1 uC1-sec uCi uCi/sec uCi uC1/cc uCi-sec E-Xe-135m INITIAL 0.000E+00 7.560E+11 0.000E+00

2 i l

1

.0167 h 0.000E+00 0.000E+00 7.226E+11 4.435E+13 1.756E+07 2.927E+05 6.434E+02 1.313E-07 1.946E+04 3

2

.0500 h 0.000E+00 0.000E+00 6.602E+11 8.292E+13 3.283E+07 2.736E+05 1.759E+03 3.591E-07 1.452E+05 E'

3

.0833 h 0.000E+00 0.000E+00 6.032E+11 7.576E+13 3.000E+07 2.500E+05 2.671E+03 5.453E-07 2.667E+05 E f.

4

.1667 h 0.000E+00 0.000E+00 4.813E+11 1.620E+14 6.415E+07 2.138E+05 4.241E+03 8.657E-07 1.046E+06 Y

5

.2500 h 0.000E+00 0.000E+00 3.841E+11 1.293E+14 5.119E+07 1.706E+05 5.043E+03 1.029E-06 1.397E+06 3

G 6

.3333 h 0.000E+00 0.000E+00 3.064E+11 1.031E+14 4.084E+07 1.361E+05 5.329E+03 1.088E-06 1.558E+06 S

7

.4167 h 0.000E+00 0.000E+00 2.445E+11 8.229E+13 3.259E+07 1.086E+05 5.279E+03 1.078E-06 1.591E+06 h

8

.5000 h 0.000E+00 0.000E+00 1.951E+11 6.566E+13 2.600E+07 8.668E+04 5.019E+03 1.025E-06 1.543E+06 9

.5833 h 0.000E+00 0.000E+00 1.557E+11 5.239E+13 2.075E+07 6.916E+04 4.640E+03 9.472E-07 1.447E+06 10

.6667 h 0.000E+00 0.000E+00 1.242E+11 4.181E+13 1.656E+07 5.518E+04 4.202E+03 8.577E-07 1.324E+06 11

.7500 h 0.000E+00 0.000E+00 9.911E+10 3.336E+13 1.321E+07 4.403E+04 3.746E+03 7.646E-07 1.189E+06 Xe-135m TOTALS 0.000E+00 8.729E+14 3.457E+08 1.153E+07 Xe-135 INITIAL 0.000E+00 7.380E+11 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 7.380E+11 4.420E+13 1.753E+07 2.922E+05 6.569E+02 1.341E-07 1.972E+04 m

2

.0500 h 0.000E+00 0.000E+00 7.378E+11 8.855E+13 3.507E+07 2.922E+05 1.965E+03 4.011E-07 1.574E+05 y

3

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4

.1667 h 0.000E+00 0.000E+00 7.362E+11 2.211E+14 8.755E+07 2.918E+05 6.470E+03 1.321E-06 1.461E+06 x,

5

.2500 h 0.000E+00 0.000E+00 7.342E+11 2.206E+14 8.735E+07 2.912E+05 9.609E+03 1.961E-06 2.413E+06 9

6

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.3000 h t,. 000E+00 0.000E+ 00 7.253E+11 2.181E+14 8.637E+07 2.879E+05 1.859E+0g 3.794E-06 5.140E+06

[Q 9

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10

.6667 h 0.000E+00 0.000E+00 7.180E+11 2.160E+14 8.552E+07 2.851E+05 2.419E+04 4.938E-06 6.844E+06

(.O 11

.7500 h 0.000E+00 0.000E+00 7.141E+11 2.148E+14 8.507E+07 2.836E+05 2.688E+04 5.486E-06 7.661E+06 h

Xe-135 TOTALS 0.000E+00 1.968E+15 7.793E+08 3.7 61E+ 07 eO Xe-137 INITIAL 0.000E+00 2.520E+12 0.000E+00 Q

1

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2

.0500 h 0.000E+00 0.000E+00 1.464E+12 2.117E+14 8.384E+07 6.986E+05 3.931E+03 8.025E-07 3.561E+05 3

.0833 h 0.000E+00 0.000E+00 1.019E+12 1.474E+14 5.837E+07 4.864E+05 4.554E+03 9.297E-07 5.114E+05 4

.1667 h 0.000E+00 0.000E+00 4.124E+11 2.012E+14 7.969E+07 2.656E+05 3.771E+03 7.699E-07 1.231E+06 5

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6

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7

.4167 h 0.000E+00 0.000E+00 2.730E+10 '.332E+13 5.275E+06 1.758E+04 6.220E+02 1.270E-07 2.647E+05 g.

8

.5000 h 0.000E+00 0.000E+00 1.104E+10 *,389E+12 2.134E+06 7.114E+03 3.004E+02 6.132E-08 1.311E+05 g

y 9

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g 10

.6667 h 0.000E+00 0.000E+00 1.807E+09 8.819E+11 3.492E+05 1.164E+03 6.479E+01 1.323E-08 2.914E+04 11

.7500 h 0.000E+00 0.000E+00 7.312E+08 3.568E+11 1.413E+05 4.709E+02 2.930E+01 5.982E-09 1.331E+04 30 q

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UNIT 2 LOCKED ROTOR CASE 2 DOSE RATE (PAGE 7) gg TRAIL 3_PC -- Transport of Radioactive Material in Linear Systems, v1.0 '

=7 Case 2 - Primary to Secondary Noble Gases / CR Doserate (1/16/98)[TC86DR.DAT]

- - PROGENY INGROKfH ON ***

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2

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3

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.1667 h 0.000E+00 0.000E+00 1.543E+12 5.245E+14 2.077E+08 6.924E+05 1.360E+04 2.776E-06 3.381E+06 34.

c 5

.2500 h 0.000E+00 0.000E+00 1.207E+12 4.104E+14 1.625E+08 5.417E+05 1.586E+04 3.237E-06 4.433E+06 6

.3333 h 0.000E+00 0.000E+00

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8

.5000 h 0.000E+00 0.000E+00 5.780E+11 1.965E+14 7.783E+07 2.594E+05 1.488E+04 3.038E-06 4.619E+06-9

.5833 h 0.000E+00 0.000E+00 4.523E+11 1.530E+14 6.090E+07 2.030E+05 1.349E+04 2.754E-06 4.247E+06-10

.6667 h 0.000E+00 0.000E+00 3.538E+11 1.203E+14 4.764E+07 1.588E+05 1.198E+04 2.445E-06 3.810E+06 11

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1

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3

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- MEe 00000000000 00000000000 00000000000 CfR BS r o

- UOm 00000000000 00000000000 00000000000 R

m SD Ota re N

000000000000 000000000000 000000000000 Tot

- O 000000000000 000000000000 000000000000 O pS T

+ + + ++ + + + + + + +

+ + + +++++++++

s

- O EEEEEEEEEEEE EEEEEEEEEEEE EEEEEEEEEEEE R nl hem 000000000000 000000000000 000000000000 aa PS e 000000000000 000000000000 000000000000 D ri Or ETt

- Dm 000000000000 000000000000 000000000000 i

K

- n -

CI hhhhhhhhhhh hhhhhhhhbhh hhhhhhhhhhh O

C-70370370370 70370370370 70370370370 L P_4 60360360360 60360360360 60360360360 815865310865S 15865310865S 15865310865S 2 S L

L 300012345567.A 100012345567.L 200012345567.A TLe 3

A 3

1 I I s T

1 T

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UNIT 2 LOCKED ROTOR CASE 4 DOSE RATE (PAGE 14) d TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 1P g[

q Case 4 - Initial Steam Release / CR Deserate (1/16/98) [TC88DR.DAT]

- - PROGENY INGROWTH ON ***

E"

ENVIRONMENT---------

CONTROL ROOM-------

PHJTON-SUBMG BETA-SUBMG THYROID-INHAL PHOTON-SUBMG BETA-SUBMG THYROID-INHAL h.

DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE E"

I mrem mrem /hr mrem mrem /h r mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr

[%

I-133

.0167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.6BE-08 2.02E-06 2.08E-07 2.49E-05 3.07E-04 3.6BE-02 y'

.0500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.71E-08 2.01E-06 8.29E-07 2.48E-05 1.22E-03 3.65E-02 t;

.0833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.66E-08 1.99E-06 8.23E-07 2.46E-05 1.21E-03 3.63E-02 6

]f

.1667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.65E-07 1.96E-06 2.03E-06 2.42E-05 3.00E-03 3.57E-02

.2500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.62E-07 1.92E-06 2.00E-06 2.38E-05 2.95E-03 3.51E-02 3

.3333 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.59E-07 1.89E-06 1.96E-06 2.34E-05 2.90E-03 3.45E-02

.4167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.56E-07 1.86E-06 1.93E-06 2.30E-05 2.85E-03 3.39E-02

~*

.5000 h C.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.54E-07 1.83E-06 1.90E-06 2.26E-05 2.80E-03 3.33E-02

.5833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.51E-07 1.80E-06 1.87E-06 2.22E '

2.75E-03 3.27E-02

=

.6667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.48E-07 1.77E-06 1.83E-06 2.18r '

70E-03 3.22E-02

.7500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.46E-07 1.74E-06 1.80E-06 2.14'

?'E-03 3.16E-02 TOTALS 0.00E+00 0.00E+00 0.00E+00 1.39E-06 1.72E-05

't-02 I-134

[T]

.0167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.33E-10 3.98E-08 1.41E-09 1.69E-07

. r4 9 1.05E-05

g)

.0500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.31E-09 3.86E-08 5.54E-09 1.64E-07 3.446-07 1.02E-05

(,f)

.0833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.27E-09 3.74E-08 5.37E-09 1.58E-07 3.33E-07 9.84E-0"

.1667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.99E-09 3.45E-08 1.27E-08 1.46E-07 7.88E-07 9.08E-Oo Q

.2500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.76E-09 3.18E-08 1.17E-08 1.35E-07 7.27E-07 8.38E-06

.3333 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.55E-09 2.94E-08 1.00E-08 1.25E-07 6.71E-07 7.73E-06 5' "II

.4167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.35E-09 2.71E-08 9.97E-09 1.15E-07 6.19E-07 7.14E-06

[, ()

.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.17E-09 2.50E-08 9.20E-09 1.06E-07 5.71E-07 6.58E-06 s

.5833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-09 2.31E-08 8.49E-09 9.79E-08 5.27E-07 6.00E-06 (C)

.6667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.85E-09 2.13E-08 7.84E-09 9.03E-08 4.87E-07 5.61E-06

-h

.7500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.71E-09 1.97E-08 7.23E-09 8.33E-08 4.49E-07 5.17E-06 8

TOTALS 0.00E+00 0.00E+00 0.00E+00 2.13E-08 9.03E-08 5.60E-06 O

(A)

I-135 (yg

.0167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.96E-08 2.35E-06 8.37E-08 1.00E-05 4.25E-05 5.10E-03

.0500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.79E-08 2.33E-06 3.33E-07 9.95E-06 1.69E-04 5.05E-03

.0833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.72E-08 2.31E-06 3.30E-07 9.86E-06 1.68E-04 5.01E-03

.1667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.90E-07 2.25E-06 8.12E-07 9.63E-06 4.12E-04 4.89E-03

.2500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.86E-07 2.20E-06 7.93E-07 9.41E-06 4.03E-04 4.78E-03 3

.3333 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.81E-07 2.15E-06 7.75E-07 9.20E-06 3.94E-04 4.67E-03 EL

.4167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.77E-07 2.10E-06 7.57E-07 8.58E-06 3.05E-04 4.56E-03 3

g

.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.73E-07 2.05E-06 7.40E-07 8.78E-06 3.16E-04 4.46E-03 g

y [

.5833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.69E-07 2.01E-06 7.23E-07 8.58E-06 3.67E-04 4.36E-03

~

.6667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.65E-07 1.96E-06 1.07E-07 8.38E-06 3.59E-04 4.26E-03 3'

{

7500 h 0.00E+00 0.00E+00 0.00E*00 0.00S+00 0.00E+00 0.00E+00 1.62E-07 1.92E-06 6.90E-07 8.19E-06 3.51E-04 4.16E-03 TOTALS 0.00E+00 0.00E+00 0.00E+00 1.58E-06 6.75E-06 3.43E-03 31 S

12 R

gg t

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33333322222 NSr

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BEm 000000000000 EvR V Se 000000000000 sic Or Ot N

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S L

I Ehhhhhhhhhhh O

D C-I70370370370 L P_4 L60360360360 2

C15865310865S S

U00012345567.L TLe N

A I I s T

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T UT A

UNIT 2 LOCKED ROTOR CASE 5 DOSE RATE (PAGE 1).

.MQ TRAILS _PC --. Transport of Radioactive Material in Linear Systems, v1.0 7T Case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) [TC89DR.DAT]

- - PROGENY INGRONTH ON ***

h CCHP: Not used this case CCHP: 3 S/Gs CCHP: Control Room

{

"{

ng VOLUME: 1.730E+05 Cu.Ft.

i g

INITIAL:

0.000E+00 I-131 8.610E+00 I-131-Ci 0.000E+00 I-131 0.000E+00 1-132 2.540E+00 I-132 0.000E+00 I-132 0.000E+00 I-133 1.230E+01 I-133 0.000E+00 I-133 6'

O.000E+00 I-134 5.670E-02 I-134 0.000E+00 1-134 0.000E+00 I-135 5.510E+00 I-135 0.000E+00 I-135 S

ACT MULT (to uC1):

.1.000E+00 1.000E+06

-1.000E+00 ks b

IT1 2

C x,D av i O.

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>=

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UNIT 2 LOCKED ROTOR CASE 5 DOSE RATE (PAGE 2)

MQ TRAILS _PC - Transport of Radioactive Material in Linear Systems, v1.0 "F T

. Case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) [TC89DR.DAT)

- - PROGENY-INGROWTH ON ***

REMOVAL:

0.000E+00 1/see 2.234E-06 1/see 1.000E+01 cfm 9

NUC Grp 1 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 NUC Grp 2 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 9. 4 00E-01

{

NUC Grp 3 REL FR:

0.000E+00 0.000E+00 INTAKE REDUCT: 0.000E+00 0

MULTI PLIERS =->

STEP TIME XPR XREM XRF XPR XREM XRF XPR XREM XRF 1

6.000E+01

.000 1.00

.000

.000 1.00

.000 50.0 50.0'

.000 3

2 1.800E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 3 3.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000

~

4 6.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 5

9.000E+02

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 6 1.200E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 7

1.500E+03

.000 1.00

.000

.000 1.00-

.000 50.0

'50.0

.000 8 1.800E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 9 2.100E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 10 2.400E+03

.000 1.00

.000

.000 1.00

.uoO 50.0 50.0

.000 ITI 11 2.700E+03

.000 1.00

.000

.000 1.00

.000 50.0 50.0

.000 c' @,

CONTROL ROOM ENVIRONMrN;...

X/Q Breathing Occupancy X/Q Breathing

[]

s/M3 M3/s s/M3 M3/s

n. T 1.000E-04 3.470E-04 1.000E+00 1.000E-05 3.470E-04 2

MULTIPLIERS - >

~C STEP TIME,s 8

1 6.000E+01 1.59 1.00 1.00

.000 1.00 2

1.800E+02 1.59 1.00 1.00

.000 1.00

=db 3 3.000E+02 1.59 1.00 1.00

.000 1.00 0'

4 6.000E+02 1.59 1.00 1.00

.000 1.00 5

9.000E+02 1.59 1.00 1.00

.000 1.09 (J) 6 1.200E+03 1.59 1.00 1.00

.000 1.00 (J1 7

1.500E+03 1.59 1.00 1.00

.000 1.00 8 1.800E+03 1.59 1.00 1.00

.000 1.00 9 2.100E+03 1.59 1.00 1.00

.000 1.00 10 2.400E+03 1.59 1.00 1.00

.000 1.00 h

11 2.700E+03 1.59 1.00 1.00

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a

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UNIT 2 LOCKED ROTOR CASE 5 DOSE RATE (PAGE 3) g TRAILS _PC -- Transport of Radiosctive Mcterial in Linear Systems, v1.0 1p y case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) [TC890R.DAT]

** PROGENY INGROWTH ON ***

g-Not used this case 3 S/Gs AWME CONTROL ROQ4

[ 1 CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD E.

STEP TIME uC1 uCi-sec uCi uCi-sec UCi uCi/sec uCi uC1/cc uC1-sec EF Xe-131m INITIAL 0.000E+00 0.000E+00 0.000E+00 2%

1

.0167 h 0.000E+00 0.000E+00 3.815E+00 1.144E+02 2.557E-04 4.261E-06 1.915E-08 3.910E-18 4.791E-07 2

.0500 h 0.000E+00 0.000E+00 1.144E+01 9.153E+02 2.045E-03 1.704E-05 1.718E-07 3.508E-17 1.071E-05 y'

3

.0833 h 0.000E+00 0.000E+00 1.906E+01 1.030E+03 4.088E-03 3.407E-05 4.759E-07 9.714E-17 3.812E-05 m,

f 4

.1667 h 0.000E+00 0.000E+00 3.808E+01 8.572E+03 1.915E-02 6.384E-05 1.088E-06 3.855E-16 3.435E-04 5

.2500 h 0.000E+00 0.000E+00 5.707E+01 1.427E+04 3.189E-02 1.063E-04 4.216E-06 8.607E-16 9.050E-04 3

6

.3333 h 0.000E+00 0.000E+00 7.603E+01 1.997E+04 4.460E-02 1.487E-04 7.438E-06 1.518E-15 1.138E-03 3

7

.4167 h 0.000E+00 0.000E+00 9.495E+01 2.565E+04 5.730E-02 1.910E-04 1.153E-05 2.354E-15 2.836E-03

@~~

8

.5000 h 0.000E+00 0.000E+00 1.138E+02 3.132E+04 6.996E-02 2.332E-04 1.648E-05 3.364E-15 4.193E-03 9

.5833 h 0.000E+00 0.000E+00 1.327E+02 3.698E+04 8.261E-02 2.754E-04 2.226E-05 4.544E-15 5.802E-03 10

.6667 h 0.000E+00 0.000E+00 1.515E+02 4.263E+04 9.523E-02 3.174E-04 2.885E-05 5.890E-15 7.659E-03 11

.7500 h 0.000E+00 0.000E+00 1.703E+02 4.827E+04 1.078E-01 3.594E-04 3.624E-05 7.397E-15 9.756E-03 Xe-131m TOTALS 0.000E+00 2.305E+05 5.150E-01 3.320E-02 Xe-133m INITIAL 0.000E+00 0.000E+00 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 1.782E+01 2.335E+03 5.216E-03 0.694E-05 3.907E-07 7.976E-17 9.774E-06 TT1 2

.0500 h 0.000E+00 0.000E+00 2.332E+02 1.867E+04 4.170E-02 3.475E-04 3.503E-06 7.151E-16 2.183E-04 X) 3

.0833 h 0.000E+00 0.000E+00 3.883E+02 3.729E+04 8.331E-02 6.943E-04 9.695E-06 1.979E-15 7.769E-04 pc (,7) 4

.1667 h 0.000E+00 0.000E+00 7.746E+02 1.745E+05 3.898E-01 1.299E-03 3.840E-05 7.840E-15 6.989E-03 5

.2500 h 0.000E+00 0.000E+00 1.159E+03 2.901E+05 6.480E-01 2.160E-03 8.560E-05 1.747E-14 1.839E-02 Q

6

.3333 h 0.000E+00 0.000E+00 1.541E+03 4.050E+05 9.048E-01 3.016E-03 1.500E-04 3.078E-14 3.52SE-02 2'

7

.4167 h 0.000Ev00 0.000E+00 1.921E+03 5.194E+05 1.160E+00 3.868E-03 2.334E-04 4.764E-14 5.743E-02 5' "t3 8

.5000 h 0.000E+00 0.000E+00 2.300E+03 6.332E+05 1.415E+00 4.715E-03 3.329E-04 6.796E-14 8.476E-02

[, ([l 9

.5833 h 0.000E+00 0.000E+00 2.676E+03 7.464E+05 1.6675+00 5.558E-03 4.489E-04 9.164E-14 1.171E-01 s

10

.6667 h 0.000E+00 0.000E+00 3.050E+03 8.590E+05

1. 9196+00 6.396E-03 5.809E-04 1.186E-13 1.543E-01 (C) 11 7500 h 0.000E+00 0.000E+00 3.422E+03 9.709E+05 2.169E+00 7.230E-03 7.283E-04 1.487E-13 1.962E-01

.h Xe-133m TOTALS 0.000E+00 4.657E+06 1.04CE+01 6.715E-01 eO Xe-133 INITIAL 0.000E+00 0.000E+00 0.000E+00 (i) 1

.0167 h 0.000E+00 0.000E+00 1.096E+03 3.288E+04 7.345E-02 1.224E-03 5.502E-06 1.123E-15 1.376E-04 (J1 2

.0500 h 0.000E+00 0.000E+00 3.285E+03 2.629E+05

5. 872E-01 4. 8 94 E-03 4.934E-05 1.007E-14 3.074E-03 3

.0833 h 0.000E+00 0.000E+00 5.469E+03 5.253E+05 1.173E+00 9.779E-03 1.366E-04 2.788E-14 1.094E-02 4

.1667 h 0.000E+00 0.000E+00 1.091E+04 2.458E+06 5.491E+00 1.030E-02 5.411E-04 1.105E-13 9.846E-02 5

.2500 h 0.000E+00 0.000E+00 1.633E+04 4.088E+06 9.132E+00 3.044E-02 1.207E-03 2.463E-13 2.591E-01 3"

6

.3333 h 0.000E+00 0.000E+00 2.173E+04 5.710E+06 1.276E+01 4.252E-02 2.126E-03 4.339E-13 4. 97 0E-01 d

7

.4167 h 0.000E+00 0.000E+00 2.710E+04 7.325E+06 1.636E+01 5.454E-02 3.292E-03 6.719E-13 8.099E-01

[p 8

.5000 h 0.000E+00 0.000E+00 3.245E+04 0.932E+06 1.995E+01 6.652E-02 4.697E-03 9.588E-13 1.196E+00 g

pn 9

.5833 h 0.000E+00 0.000E+00 3.777E+04 1.053E+07 2.353E+01 7.843E-02 6.336E-03 1.293E-12 1.653E+00 Q

-j 10

.6667 h 0.000E+00 0.000E+00 4.306E+04 1.213E+07 2.709E+01 9.029E-02 8.201E-03 1.674E-12 2.178E+00

~

30 11

.7500 h 0.000E+00 0.000E+0]

4.834E+04 1.371E+07 3.063E+01 1.021E-01 1.029E-02 2.100E-12 2.771E+00 E,

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e UNIT 2 LOCKED ROTOR CASE 5 DOSE RATE (PAGE 4) g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 Case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) [TC89DR.DAT]

- - PROGENY INGROWTH ON ***

5pd Not used this case 3 S/Gs AVERAGE CONTROL ROO4 CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD STEP TIME uCi uCi-sec uCi uC1-sec uCi uCi/sec uC1 uCi/cc uC1-sec EF '

Xe-135m INITIAL 0.000E+00 0.000E+00 0.000E+00 l2 1

.0167 h 0.00CE+00 0.000E+00 4.007E+04 1.212E+06 2.707E+00 4.511E-02 2.004E-04 4.092E-14 5.033E-03 3

2

.0500 h 0.000E+00 0.000E+00 1.148E+05 9.361E+06 2.091E+01 1.743E-01 1.718E-03 3.506E-13 1.084E-01 M*

3

.Gs33 h 0.000E+00 0.000E+00 1.827E+05 1.791E+07 4.001E+01 3.334E-01 4.551E-03 9.289E-13 3.708E-01 I,

4

.1667 h 0.000E+00 0.000E+00 3.267E+05 7.726E+07 1.726E+02 5.754E-01 1.613E-02 3.292E-12 3.048E+00 5

.2500 h 0.000E+00 0.000E+00

4. 3 98E+ 05 1.157E+ 08 2.584E+02 8.612E-01 3.239E-02 6.611E-12 7.256E+00 6

.3333 h 0.000E+00 0.000E+00 5.283E+05 1.458E+08 3.256E+02 1.085E+00 5.157E-02 1.053E-11 1.259E+01 h

7

.4167 h 0.000E+00 0.000E+00 5.973E+05 1.693E+08 3.782E+02 1.261E+00 7.243E-02 1.478E-11 1.861E+01 8

.5000 h 0.000E+00 0.000E+00 6.506E+05 1.875E+08 4.189E+02 1.396E+00 9.407E-02 1.920E-11 2.500E+01

2 9

.5833 h 0.000E+00 0.000E+00 6.915E+05 2.016E+08 4.503E+02 1.501E+00 1.159E-01 2.366E-11 3.152E+01 10

.6667 h 0.000E+00 0.000E+00 7.225E+05 2.123E+08 4.743E+02 1.581E+00 1.375E-01 2.807E-11 3.804E+01 11

.7500 h 0.000E+00 0.000E+00 1.456E+05 2.204E+08 4.924E+02 1.641E+00 1.586E-01 3.237E-11 4.444E+01 Xe-135m TOTALS 0.000E+00 1.358I+09 3.034E+03 1.810E+02 Xe-135 INITIAL 0.000E+00 0.000E+00 0.000E+00 1

.0167 h 0.000E+ 00 0.000E+00 5.850E+03 1.754E+05 3.917E-01 6.529E-03

2. 939E-05 5. 999E-15 7.347E-04 2

.0500 h 0.000E+00 0.000E+00 1.764E+04 1.408E+06 3.146E+00 2.622E-02 2.651E-04 5.411E-14 1.649E-02 ry) 3

.0833 h 0.000E+00 0.000E+00 2.953E+04 2.829E+06 6.321E+00 5.268E-02 7.376E-04 1.506E-13 5.899E-02

g) 4

.1667 h 0.000E+00 0.000E+00 5.962E+04 1.336E+07 2.985E+01 9.950E-02 2.957E-03 6.036E-13 5.361E-01 gg) 5

.2500 h 0.000E+00 3.000E+00 9.003E+04 2.244E+07 5.013E+01 1.671E-01 6.652E-03 1.358E-12 1.424E+00 9

7e 6

.3333 h 0.000E+00 0.000E+00 1.206Fe05 3.159E+07 7.058E+01 2.353E-01 1.100E-02 2.409E-12 2.75'E+00 d'

7

.4167 h 0.000E+00 0.000E+00 1.512E+05 4.07?E+07 9.108E+01 3.036E-01 1.836E-02 3.749E-12 4.5%,2+00 5'"I) 8

.5000 h 0.000E+00 0.000E&OO 1.817E+05 4.993E+07 1.116E+02 3.718E-01 2.630E-02 5.369E-12 6.686E+00 f, (]l 9

.5833 h 0.000E+00 0.000E+00 2.120E+05 5.906E+07 1.319E+02 4.398E-01 3.557E-02 7.260E-12 9.267E+00 10

.6667 h 0.000E+00 0.000E+00 2.421E+05 6.812E+07 1.522E+02 5.073E-01 4.610E-02 9.411E-12 1.224E+01 (C) e 11 7500 h 0.000E+00 0.000E+00 2.719E+05 7.710E+07 1.722E+02 5.741E-01 5.785E-02 1.181E-11 1.558E+01 Xe-135 TOTALS 0.000E+00 3.668E+08 8.194E+02 5.307E+01 a

eO I-131 INITIAL 0.000E+00 8.610E+06 0.000E+00 (A) 1

.0167 h 0.000E+00 0.000E+00 8.600E+06 5.165E+0B 1.154E+03 1.923E+01 4.323E-02 8.825E-12 1.298E+00 2

.0500 h 0.000E+00 0.000E+00 8.605E+06 1.033E+09 2.307E+03 1.923E+01 1.293E-01 2.639E-11 1.036E+01 (yj 3

.0833 h 0.000E+00 0.000E+00 8.602E+06 1.032E+09 2.306E+03 1.922E+01 2.140E-01 4.385E-11 2.065E+01 4

.1667 h 0.000E+00 0.000E+00 8.593E+06 2.579E409 5.7 62E+ 03 1. 921E+ 01 4.263E-01 8.702E-11 9.624E+01 5

.2500 h 0.000E+00 0.000E+00 0.585E+06 2.577E+09 5.756E+03 1.919E+01 6.344E-01 1.295E-10 1.592E+02 6

.3333 h 0.000E+00 0.000E+00 8.577E+06 2.574E+09 5.751E+03 1.917E+01 8.393E-01 1.713E-10 2.211E+02 3

7

.4167 h 0.000E+00 0.000E+00 8.568E+06 2.572E+09 5.745E+03 1.915E+01 1.041E+00 2.125E-10 2.821E+02 8

.5000 h 0.000E+00 0.000E+00 8.560E+06 2.569E+09 5.740E+03 1.913E+01 1.240E+00 2.530E-10 3.422E+02 gp 9

.5833 h 0.000E+00 0.000E+00 8.552E+06 2.567E+09 5.734E+03 1.911E+01 1.435E+00 2.929E-10 4.013E+02 mg 7n 10

.6667 h 0.000E+00 0.000E+00 8.543E+06 2.564E+09 5.729E+03 1.910E+01 1.627E+00 3.322E-10 4.594E+02 3

d.

11 7500 h 0.000E+00 Q.000E+00 8.535E+06 2.562E+09 5.723E+03 1.908E+01 1.817E+00 3.700E-10 5.167E+02 30 t

I-131 TOTALS 0.000E+00 2.315E+10 5.171E+04 2.510E+03 "EL I

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UNIT 2 LOCKED ROTOR CASE 5 DOSE RATE (PAGE 5) g TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 5p Case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) [TC89DR.DAT]

- - PROGENY INGROWTH ON ***

A Not used this case 3 S/Gs AVERAGE

-CONTROL ROOM-----------

02 CURRENT INTEGRD CURRENT INTEGRD RELEASED RELEASE CURRENT CURRENT INTEGRD h.

STEP TIME uCi uCi-sec uCi uCi-sec uCi uCi/sec uCi uCi/cc uCi-sec E

I-132 INITIAL 0.000E+00 2.540E+06 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 2.527E+06 1.520E+08 3.396E+02 5.660E+00 1.269E-02 2.591E-12 3.812E-01 2

.0500 h 0.000E+00 0.000E+00 2.501E+06 3.017E+08 6.739E+02 5.616E+00 3.758E-02 7.671E-12 3.020E+00 M'

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3

.0833 h 0.000E+00 0.000E+00 2.475E+06 2.986E+08 6.670E+02 5.559E+00 6.182E-02 1.262E-11 5.968E+00 4

.1667 h 0.000E+00 0.000E+00

2. 412E+ C6 7. 331E+ 08 1.638E+03 5.459E+00 1.197E-01 2.443E-11 2.728E+01 o

n.

5

.2500 h 0.000E+00 0.000E+00 2.351E+06 7.145E+0B 1.596E+03 5.320E+00 1.737E-01 3.547E-11 4.407E+01 3

7-6

.3333 h 0.000E+00 0.000E+00 2.291E+06 6.963E+08 1.555E+03 5.185E+00 2.242E-01 4.577E-11 5.975E+01 f

7

.4167 5 0.000E+00 0.000E+00 2.233E+06 6.785E+08 1.516E+03 5.053E+00 2.713E-01 5.538E-11 7.437E+01 8

.5000 h 0.000E+00 0.000E+00 2.176E+06 6.613E+08 1.477E+03 4.924E+00 3.151E-01 6.432E-11 8.800E+01 l

9

.5833 h 0.000E+00 0.000E+00 2.121E+06 6.444E+08 1.440E+03 4.799E+00 3.559E-01 7.264E-11 1.007E+02 10

.6667 h 0.000E+00 0.000E+00 2.067E+06 6.280E+08 1.403E+03 4.677E+00 3.937E-01 8.036E-11 1.125E+02 11

.7500 h 0.000E+00 0.000E+00 2.014E+06 6.120E+08 1.367E+03 4.558E+00 4.267E-01 8.751E-11 1.234E+02 I-132 TOTALS 0.000E+00 6.120E+09 1.367E+04 6.394E+02 1-133 INITIAL 0.000E+00 1.230E+07 0.000E+00 1

.0167 h 0.000E+00 0.000E+00 1.229E+07 7.377E+08 1.648E+03 2.747E+01 6.173E-02 1.260E-11 1.853E+00 fr]

2

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3

.0833 h 0.000E+00 0.000E+00 1.226E+07 1.472E+09 3.288E+03 2.740E+01 3.061E-01 6.249E-11 2.944E+01 7s (,f)

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4

.1667 h 0.000E+00 0.000E+00 1.222E+07 3.671E+09 8.201E+03 2.734E+01 6.060E-01 1.237E-10 1.369E+02 5

.2500 h 0.000E+00 0.000E+00 1.217E+07 3.658E+09 8.173E+03 2.724E+01 8.996E-01 1.836E-10 2.260E+02 3

6

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7

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9

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13

.6667 h 0.000E+00 0.000E+00 1.197E+07 3.596E+09 8.033E+03 2.678E+01 2.279E+00 4.652E-10 6.442E+02 (C) 11

.7500 h 0.000E+00 0.000E+00 1.192E+07 3.583E+09 8.005E+03 2.668E+01 2.538E+00 5.181E-10 7.227E+02

.h I-133 TOTALS 0.000E+00 3.270E+10 7.305E+04 3.534E+03 eO I-234 INITIAL 0.000E+00 5.670E+04 0.000E+00 (A) 1

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.0500 h 0.000E+00 0.000E+00 5.448E+04 6.625E+06 1.480E+01 1.233E-01 8.186E-04 1.671E-13 6.615E-02 3

.0833 h 0.000E+00 0.000E+00 5.305E+04 6.451E+06 1.441E+01 1.201E-01 1.325E-03 2.705E-13 1.288E-01 4

.1667 h 0.>00E+00 0.000E+00 4.963E+04 1.540E+07 3.440E+01 1.147E-01 2.463E-03 5.027E-13 5.704E-01 5

.2500 h 0.000E+00 0.000E+00 4.644E+04 1.441E+07 3.218E+01 1.073E-01 3.433E-03 7.007E-13 8.863E-01 3>

6

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7

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.5833 h 0.000E+00 0.000E+00 3.558E+04 1.104E+07 2.466E+01 8.220E-02 5.973E-03 1.219E-12 1.723E+00 g

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.6667 h 0.000E+00 0.000E+00 3.329E+04 1.033E+07 2.307E+01 7.690E-02 6.344E-03 1.295E-12 1.048E+00 11

.7500 h 0.000E+00 0.000E+00 3.115E+04 9.662E+06 2.159E+01 7.195E-02 6.632E-03 1.354E-12 1.947E+00 30 g

I-134 TOTALS 0.000E+00 1.152E+08 2.573E+02 1.120E+01 5

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UNIT 2 LOCKED ROTOR CASE 5 DOSE RATE (PAGE 6) g TRAILS _PC -- Transport of Radioactive haterial in Linear Systems, v1.0 y

Case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) (TC89DR.DAT]

- - PROGENY INGROWTH ON ***

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5. 4 07E+ 06 1. 630E+ 0 9 3.641E+03 1.214E+01 2.682E-01 5.475E-11 6.076E+01 5

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5. 200E+06 1. 570E+0 9 3.507E+03 1.169E+01 7.541E-01 1.539E-10 2.090E+02

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I UNIT 2 LOCKED ROTOR CASE 5 DOSE RATE (PAGE 10)

TRAILS _PC -- Transport of Radioactive Material in Linear Systems, v1.0 MQ Case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) (TC89DR.DAT]

- - PROGENY INGRONTH ON.***

95telt

{ ^ *)9

ENVIRONMENT---------

CONTROL ROOM-------

PHOTON-SUBMG BETA-SUBMG THYRCID-INHAL PHOTON-SUBMG BETA-SUBMG THYROID-INHAL q

DOSE DOSE RATE DOSE DOSE RATE DOSE DOSE RATE -DOSE DOSE RATE DOSE DOSE RATE' DOSE d

mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr mrem mrem /hr ~

DOSE RATE E

i mrem mrem /hr EE.

I I-135

.0167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.36E-09 4.02E-07 1.43E-08 1.72E-06 7.28E-06 8.73E-04 E'

.0500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.67E-08 1.20E-06 1.14E-07 5.13E-06 5.80E-05 2.60E-03

.0933 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.31E-08 1.99E-06 2.27E-07 8.49E-06 1.15E-04 4.31E-03

.1667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.46E-07 3.91E-06 1.05E-06 1.67E-05 5.34E-04 '8.48E-03

.2500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.03E-07 5.77E-06 1.72E-06 2.46E-05 8.76E-04 1.25E-02 9

.3333 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.56E-07 7.56E-06 2.38E-06 '3.23E-05 1.21E-03 1.64E-02 3

.4167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0C 7.03E-07 9.30E-06 3.01E-06 3.98E-05 1.53E-03 2.02E-02

~

.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.46E-07 1.10E-05 3.61E-06 4.69E-05 1.84E 2.38E-02

.5833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.83E-07 1.26E-05 4.20E-06 5.39E-05 2.13E-03 2.74E-02

.6667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.12E-06 1.42E-05 4.77E-06 6.06E-05 2.42E-03 3.08E-02

.7500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00. 0.00E+00 1.25E-06 1.57E-05 5.32E-06 6.71E-05 2.70E-03 3.41E-02 TOTALS 0.00E+00 0.00E+00 0.00E+00 6.18E-06 2.64E-05 1.34E-02 ALL NUCLIDES m

2

.0167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.81E-09 1.18E-06. 7.06E-08 8.47E-06 1.97E-04 2.37E-02

.0500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.81E-08 3.51E-06 5.63E-07 2.53E-05 1.57E-03.7.07E-02 pc (af}

.0833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.55E-07 5.81E-06 1.12E-06 4.20E-05. 3.14E-03 1.17E-01

},

.1667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.21E-07 1.15E-05 5.21E-06 8.30E-05 1.46E-02 2.33E-01 m,

.2500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E-06 1.69E-05 8.59E-06 1.23E-04 2.41E-02.3.46E-01 9 "II

.3333 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.63E-06 2.22E-05 1.19E-05 1.62E-04 3.35E-02 4.57E-01

7. ("I

.4167 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.07E-06 2.74E-05 1.51E-05 2.00E-04 4.27E-02 5.67E-01

.5000 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.49E-06 3.23E-05 1.82E-05 2.37E-04 5.17E-02 6.74E-01 (S)

.5833 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Q.00E+00 0.00E+00 2.90E-06 3.72E-05 2.13E-05 2.74E-04 6.06E-02 7.79E-01

==h

.6667 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.29E-06 4.18E-05 2.43E-05 3.09E-04 6.93E-02 8.83E-01

. s

.7500 h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.67E-06 4.63E-05 2.72E-05 3.43E-04 7.78E-02 9.84E-01

()

TOTALS 0.00E+00 0.00E+00 0.00E+00 1.82E-05 1.34E-04 3.79E-01 (A) 01 d

9-a x

e EL Y.

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ss y

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~

RTL: n/a Fonn: R'I1.103 3 9/91 D

ERS-MPD-91-035 pase "f

Health Physics Department Revision i CASE I DOSE RATE INPUT FILE

'L1 ',11,1.00E-5,3.47E-4,1.0,1,0E-4,3.47E-4,0,24,1,2

' Case 1 - Primary to Secondary Iodines / CR Dose Rate (1/16/98)[TC85DR.DKf]'

'C1 ','RCS',3.960E-7,0.0,0,0,0.0

'C2 ','3 S/Gs',2.234E-6,0.0,0,0,0.0

CR ',1.73E5,10.,10.,0.0,0.94,0.0

'PRD',24 *0.0

'PRD',24*0.0

'INI',1.00E+6,'Ci ',14 *0.0,1.49E+6,1.78E+6,2.88E+6,3.24E+6,2.52E+6,5 *0.0

'INI',1.0,' ',24*0.0

' TIM',60,180,300,600,900,1200,1500,1800,2100,2400,2700

'XPR',11 *0.0

'XPR',11

0.0

'XPR',11 *50

'XRM',11

1.0

'XRM',l l

1.0

'XRM',11

50.0

)

'XRF',11

0.0

'XRF',11

0.0

'XRF',11

0.0

'XOQ',l l *0.00

'XBR',11

1.0

'XOQ',l l

1.59

'XBR',I 1

1.0

'OCC',l l

l.0

......... ~.

. _ ~.

RTL n/a Form: RE 1.103-3 9/93 Na M

ERS-MPD-91-035 Page /M Health Physics Department Revision 1

)

CASE 2 DOSE RATEINPUT FILE

'L1 ',11,1.00E-5,3.47E-4,1.0,1.0E-4,3.47E-4,0,24,1,2

' Case 2 - Primary to Secondary Noble Gases / CR Doserate (1/16/98)[TC86DR.DAT]'

'C1 ','Not used this case',0.000E-0,0.0,0.0,0.0

'C2 ','3 S/Gs',3.960E-7,0,0,0.0,0.0

'CR ',1.73E5,10.,10.,0.0,0.94,0.0 i

'PRD',24*0.0

'PRD',24 *0.0

'INI',1.00E+0,' ',24*0.0

'INI',1.00E+6,'Ci ',2.16E+5,5.40E+5,3.72E+4,1.06E+6,1.49E+6,1.98E+6,0.0,

7. 56E+3,6. 67E+4,2. 88E+6,7. 56E+5,7.38E+5,2.52E+6,2. 52 E+6,10 ' 0. 0 i

'INI',1.0,' ',24*0.0

' TIM',60,180,300,600,900,1200,1500,1800,2100,2400,2700

'XPR',11 *0.0 I

'XPR',11

0.0

'XPR',11 *50

'XRM',11

1.0

'XRM',11

l.0

'XRM',11

50.0

'XRF,11 *0.0

'XOQ',11 *0.00

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1.59

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1.0

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1.0 7.

RTL: n/a Form: RE 1.103 3 9/91

$ (Dr=== @

ERS-MPD-91-035 pase

Health Physics Depanment Revision i CASE 4 DOSE RATE INPUT FILE

'L1 ',11,1.00E-5,3.47E-4,1.0,1.0E-4,3.47E-4,0,24,1,2 Case 4 - Initial Steam Release / CR Doserate (1/16/98) [TC88DR.DAT]'

'Cl ','Not used this case',0.00E+0,0.0,0.0,0.0

'C2 ','3 S/Gs',1.235E-1,0.0,0.0,0.0

'CR ',1.73 ES,10,10.,0.0,0.94,0.0

'PRD',24 *0.0

'INI',1.0,' ',24*0.0

'INI',1.00E+6,'Ci ',4.78E-5,2.34E-4,1.23E-3,1.3 3E-4,3.56E-4,1,12E-5,0.0, 1.20E-5,3.43 E-4,2.92E-3,1.21 E-4,3. 58E-4,1. 82E-5,7.49E-5,6.73 E-3,1. 99E-3, 9.63E-3,4.43E-5,4.31 E-3,5

0.0

'INI',1.0,' ',24

0.0

' TIM',60,180,300,600,900,1200,1500,1800,2100,2400,2700

'XPR',11

0.0.

'XPR',11 *0.0

'XPR',l l *50

'XRM',11

1.0

'XRM',11

1.0

'XRM',11

50.0

'XRF,l l *0.0

'XRF,11 *0.0

' 'XOQ',11 *0.00

'XBR',l l

l.0

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1.59

'XBR',11

1.0

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1.0

.m.. __ _ _._

_. __.. ~. _..

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

RTL: n/a Fonn: RE 1.103 3 A91 db vt m-y e

ERS-MPD-91-035 Pase al Health Physics Department Revision 1 Attaciunent 8 1

CASE 5 DOSE RATE INPUT FILE

. L1 ',11,1.00E-5,3,47E-4,1.0,1.0E-4,3.47E-4,0,24,1,2

' Case 5 - Initial Secondary Liquid Iodines / CR Doserate (1/16/98) [TC89DR.DAT]'

'C1 ','Not used this case',0.0,0.0,0.0,0.0

'C2 ','3 S/Gs',2,234E-6,0.0,0.0,0.0

'CR ',1.73ES,10.,10.,0,0,0.94,0.0

'PRD',24 *0.0

'INI',1.0,' ',24*0.0

'INI',1,00E+6,'Ci ',14

0.0,8.61 E+0,2.54E+0,1.23 E+ 1,5.67E-2,5.51 E+0,5

0.0

'INI',1,0,' ',24*0.0

' TIM',60,180,300,600,900,1200,1500,1800,2100,2400,2700 l

'XPR',11

0.0

'XPR',11

0.0

'XPR',11 *50

'XRM',11

1.0

'XRM',11

l.0

' 'XRM',11 *50.0

'XRF',11 *0.0

'XOQ',11 *0.00

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1.59

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1.0

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1.0

RTI n/a Fana: RE 1.103-3 fM k*D ERS-MPD-91-035 pase I z z-Health Physics Deartment Revision 1 Annandir 1 Note: This appendix was reviewed and approved as part of ERS-SFL-95-008 revision 0. This appendix is ineandad to standankae the modeling :--

. %s and to eliminate the need to re-review these f.nput parameters and ma=n=phans with each new application If a specific deviation froni the information herein is mammary to meet the needs of a particular analysis, it should be described andjustified in the main text of the package Note: This appendix was revised (01/98) to incorporate control room ventilation system design modification detailed in the attachad addandum Revisions marked by rev. bar on right hand side of page.

Generic Control Roosa Modeling This appendix desenbes 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 vray from accident-to-accident and from case-to-case within an accident. Additionally, not all phases may be applicable to di 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 whid this appendix is attached will explain and justify any deviations.

1.

Control Room Ventilation System.2aA21.22 i

The systems in both sides of the control room operate independently, but are interlocked through the Control Room Emergency Breathing Air Pressurization System (CREBAPS).

The following actuate CREBAPS:

.A Containment Isolation Signal, Phase B (CIB) at either unit.

A high-high alarm on IRM-RM-218A or B (Unit 1) or a high alarm on 2RMC*RQ201 or 202 (Unit 2).

Chlorine detection alarms at either unit Note: There is no automatic transfer to emergencypiteredintakefor an isolation actuatedby a chlorine alarm.

Manual operator action.

The normal system alignment is to have the control room envelope ventilation on recirculation at both units, with a small amount of make-up air via throttled intake bypass dampers. The intake flow at each unit is drawn through two in series motor operated damprs (NSA open) The four dampers (two at each unit) receive close signals from CREBAPS. The maximum intake flow is 28,000 cfm at Unit I and 16,900 cfm at Unit 2.2i However, this path at each unit is isolated by a motor operated damper (NSA shut). Bypass lines with a throttled damper and a motor operated damper are balanced to provide an unfiltered intake flow of 300 cfm from Unit I and 200 cfm from Unit 2.25

RTI n/a Form: RE 1.103-3 P/93 ha D

ERS-MPD-91-035 pasa m Health Phymes Department Revision 1 Annendiv 1 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 an anged 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 approximately 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 (NSA shut), two 1000 cfm fans (NSA off), and one HEPA / charcoal filter train. A manual damper downstream of the filter is NSA shut as the NSA is to have Unit 2 supply the emergency filtered intake. At Unit 2, there are two trains of motor operated dampers (NSA shut), fans (NSA off), and HEPA / charcoal filters. At both units, this filtered intake train bypasses the intake dampers.

On a CREBAPS actuation, all four intake dampers and all four exhaust dampers receive a close signal. This isolates the normal intake. The air bottles start to release air to maintain a slight positive pressure. If the actuation was due to CIB or a radiation monitor alarm, a one hour timer is started. No timer is started on a chlorine actuation. When the one hour timer elapses, the Unit 2 emergency Sitered intake dampers open, and an emergency intake fan starts to maintain the control room slightly positive. (The "A" train fan will get the start signal at 60.1 min. the "B" train fan will get the start signal at 60.6 min. The "A" fan has approximately 30 seconds to start and reach the flow rate to satisfy the cfm requirement. If the "A" fan fails to start, or is not producing sufficient flow within the 30 second time period, the "B" fan will start and run and shut off the "A" fan train.)22 The intake is dissipated by ex61tration 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 (28,000 cfm at Unit 1,16,900 cfm at Unit 2)2i,

The control room ventilation intake (4) and exhaust (4) dampers, air handlers (4), and emergency filtered intake fans are powered from emergency AC buses.

R'It n/a Form PS 1.103-3 9/M N

D A

ERS-MPD-91-035 pas.

t 2.<t IIcalth Physics Department Revision 1 Annendiv 1 i

3A 2i.2o 2.

Specific Ventilation Alignment During Accident:

\\

2.1 Prior to the start of the incident (To, T < 0), the control room ventile. tion system is drawing in 500 cfm of unfiltered outside air. 300 cfm of this intake is via Unit I intakes, and 200 cfm is via Unit 2 intakes. The intake is being removed via exfdtration l

through control room penetrations, seals, and doors. Although the motor operated exhaust dampers are open, upstream isolation dampers are shut.

2.2 The accident starts at To. The onset of the radioactive release is typically assumed to occur at To. 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 established 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 Ts. For cases involving manual operator action, Ts = the time of the j

first indication that manual isolation is necessary.

l 2.4 As noted above, the ambient dose rate reaches 1 mR/hr at Ts. 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 + To. For I

S the DBA LOCA case, Ts, Tp, T are assumed to be 0. For the manual isolation I

case, T is assumed to be the time that the manual isolation is complete.

I 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 I 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 Tp = 3 minutes in all Unit I calculations'.

-.. -.. -.~..-.-.- ~ --

RTL n/a Form: RE 1.103 3 9/92

$W#

ERS-MPD-91-035 Page i 2[

Health Physics Department Revision 1 Annentiiv 1 2.4.2 For Unit 2, Reference 6 notes that the ARM ramps up in about 107 seconds to 1 mR/hr. The maximum ramp time was shown to be 128 seconds, which SWEC assumed to be the time used. The damper closure time is 10 seconds, with a signal processing time of 2 seconds. This yields a delay of 140 seconds or, Tp = 2.33 minutes. The SWEC analysis notes that although the Unit 2 ARM does lose power, doing sojust prior to reaching the trip setpo* t does m

not add significantly to the monitor ramp time.

2.4.3 The assumption in the original record of analysis' for Unit 1 is that non-vital AC power is lost just prior to the damper movement.. For Unit 2, SWEC assumed that the loss of non-vital power occurred concurrent with the accident initiation', Although these two bases are different, it must be remembered that the assumption regarding instantaneous transport of the radioactivity to the control room provides margin to compensate for the difference.

2.4.4 In 1993, DLC was notified by Limitorque' that under certain seismic events, the valve opeators 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 maximum 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 increased:,

To = 2.33 min + 15 seconds = 2.58 minutes Unit 2; To = 3 min + 15 seconds

= 3.25 minutes Unit l'"".

2.4.5 For the DBA LOCA, control room isolation is actuated by a CIB signal. No time delay is modeled for diesel loading and damper movement in the licensing basis calculations. In Reference 12, SWEC postulated an environmental transport time of 121 seconds between the Unit I 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 At T, CREBAPS has shut the normal intake dampers, and has shut the exhaust 2.5 I

dampers. An air bleed from the air bottles is commenced. Also at this time, a 60 minute timer is started. During the time between To and T, it is conservatively I

assumed that the control room intake continues at 500 cfm. After T, the intake drops I

to zero and an infiltration rate of 10 cfm is assumed."

1

RTL n/a Fann: RE 1.103 3 M3

)

k ERS-MPD-91-035 pase iM Health Physics Department Revision 1 Annand'y 1 i

l Note: Although the dampers may not be able to close due to loss ofACpower until the dieselgeneratw loads, it is ingportant to note that thefan motors also lase power.

7heflow rate wouldcoast down once thefan motw was de-energized In accordance with Reference H it would be acceptable to assume the intakeflow rate to be 50% of the measured exfiltration rate, w 350 cfm. This is generally not modeled as the

}

diference is generally insigmjicant to the results, and/or would be efectively negated l

by transport time or, ifpower loss didnot occur coincident with the initiating event, by release time delays.

2.6 The pressurization system will bleed air at a rate sufficient to maintain the requisite j

pressure. The actual rate has been determined to range from 776 to 1030 cfm.23 The maximum value of 1030 cfm is the Technical SpaMwa% value of 1000 cfm + 3 %

4

{

allowance for test equipment inaccuracy.2' The minimum value is set at 600 cfm for practical and reliable system operation in accordance with BVPS EM 115790.2d In order to account for the specified infiltration rate, the exfiltration rate is set to the Ex.

Rate + 10 cfm 2.7 At one hour beyond CREBAPS actuation (assumed to be equal to T + 3600s), the air I

i bleed is automatically terminated and outside air is drawn through filters via the j

emergency pressurization intake dampers and fans. Since the exfiltration rate is i

variable (600 - 1030 cfm) and only the exfiltration air is filtered, the filter efficiency is j

reduced to:

i PF = ((0.95 x Rate) + (0.0 x 10)) / (Rate + 10), e.g., for a rate of 776 cfm, j

PF = ((0.95 x 776) + (0.0 x 10)) / (776 + 10) = 0.938 l

2.7.1 Technical specification 3/4.7.7" addresses control room habitability systems.

i Operability requirements require tening for less than 1% leakage and a methyl iodine removal efficiency greater than 99%. In accordance with Regulatory

[

Guide 1.52, assigned efficiencies are 95% for elemental and organic iodines.

2.8 The ventilation system remains in this alignment through the remainder of the event for j

many accident sequences. For the remaining sequences, the control room is purged for j

30 minutes cce..w.er.cing at T=8 hours. The purge and exhaust are unfiltered and have j

minimum flow rates of 28,000 cfm at Unit 1, and 16,900 cfm at Unit 2.2i I

2.9 At the completion of the purge and continuing through to the end of the assessment period (i.e.,720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months ), the flow rates return to their original value of 500 cfm.

3.

Control Room Model Parameters 3.1 Control Room Volume = 1.73E+5 ft3

[4 - Tbl 6.4-1,25]

i i

3.2 Normal ventilation intake: BV1 = 300 cfm; BV2 = 200 cfm

[4 - Tbl 6.4-1,25]

4

R'II,: n/a Fann RE 1.103-3 9/92 ERS-MPD-91-035 PASe 127 Health Physics Department Revision 1 Annendiv 1 3.3 Filter efSciency = 95 %

[12.7 above]

1 3.4 Purge Flow Rate: BV1 = 28,000 cfm; BV2 = 16,900 cfm

[21]

3.5 Air pressurization flow rate for first hour: 600 cfm (23]

3.6 Filtered air intake flow rate: 600 - 1030 cfm (23, 24]

The intakeflow rate range provided by NED is 800 - 1000 cfm 3 %, resultingin boumung waluesfor calculation of 776 - 1030 cfm. ' However BVPS EM 115790 provides a minimumflowforpracticalamireliable system operation of 600 cfm.

3.7 Isolation delays based on radiation monitor actuation AC Power Loss

@ damper [7]

@T=0

[6]

movement Diesel Start n/a(1) n/a(2)

Diesel Sequence n/a(1) n/a(2)

Damper Movement n/a(1) 12 sec

[6]

Sum 77 sec 12 sec

[6]

RMS Response 97 sec

[7]

128 sec

[6]

l Seismic Delay 15 sec

[10,11]

15 sec

[10,11]

Total 195 sec(3) 155 sec (1) U1 T/S ESF actuation timing Table 3.3-5 specifies a control room isolation response of 22 seconds without diesel starting and sequencing and 77 seconds with diesel starting and sequencing included based on CIB. The 22 second i

period would include damper movement, CNMT pressure sensor response time, and circuitry delays. (The actual breakdown is unknown). Per OST,

the diesel start and sequencing delay to the step at which the dampers are powered is 10 + 40 i4 seconds.

(2) The RMS response delay includes the diesel start and sequencing delays.

(3) SWEC rounded the original sum of 174 to 180.

J

-.... - - ~ -.. -

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

RTL nh Fann RE 1.103 3 932 kWD ERS-MPD-91-035 Page /M Health Phymes Department Revision 1 Annandir 1 g

3.8 Isolation delays based on CIB actuation I

AC PowerIms:

@ damper [7]

@T=0

[6]

i movement Diesel Start n/a(1) 10 sec

[18]

Diesel Sequence n/a (1) 40i4 sec [18]

DamperMovement n/a(1) 12 sec

[6]

Sum 77 see 12 sec

[6]

Seismic Delay 15 sec

[10,11]

15 sec

[10,11]

j i

]

Total 92 sec 81 sec (1) See note 1 for datum 3.7.

g 3.9 Control Room X/Q, sec/m' - Unit 1

[3 - Tbl 2.2-12,19,26,27]

1 h== Point 0-8 hrs 8-24 hrs 1-4 days 4-30 days 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 4

~

PAB 4.30E-3 2.01E 1.49E-3 9.25E-4 MSVA 7.60E-4 3.51E-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 5.1IE-4 2.15E-4 1.65E-4 1.14E-4 RWST 3.77E-4 1.81E-4 1.33E-4 8.50E-5 l

F 3.10 Control Room X/Q, sec/m'- Unit 2

[4 - Tbl 15.0-14,19,26,27]

Release Point 6-8 km 8-24 hrs 1-4 days 4-30 days CNMT edge 1.88E-4 9.32E-5 7.06E-5 4.18E-5 CNMT top (SLCRS)l.20E-4 5.91E-5 4.45E-5 2.64E-5

)

PAB 1.0d8-3 5.15E-4 4.04E-4 2.46E-4 MSVA 1.59E-4 7.86E-5 5.%E-5 3.76E-5 Service Bldg 2.21E-4 1.1lE-4 8.51E-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 RWST 8.25E-5 4.07E-5 3.13E-5 1.89E-5 l

3.11 OccupancyFactors

[14,20]

i 0-24 hrs 1.0 1-4 days 0.6

>4 days 0.4 J

.i

. ~.

RTL nh Fonn: RE 1.103 3 9/91 k

ERS-MPD-91-035 u 30 rem thyroid CDE. 'Ihis exceeds the NRC SER accepted value for this dose quantity. In addition, NED discovered that the current design may start the fan (s) as soon as 54.9 minutes and as late as 65.1 minutes aAer the control room isolation sequence is initiated All DBAs crediting this system assume fan start at 60 minutes. Consequally, management decided that the system design be changed to more closely match the current design basis.

2.

Control Room Ventilation System At the direction of NED (ND1MNE:7954, Ref: 24 of the Genenc Contol Room Modichng Appendix) the control room model description to wluch this addedum is =t*=ched is modified as follows:

t

RTL: n/a Form: RE 1.103-3 A9S_

ha ERS-MPD-91-035 pase 132.

Health Physics Department Revision 1 Annendir 1 Generic Control Room Modeling Addendum (continued) 2.

Control Room Vcatilaton System (contmuod)

A. The maxunum value of 1030 cfm should be used for the single fan flow rate for either train of the control room pressurizaten fan systenn (This is a maximumfor DBA analyses. The minimum of 600 cfm is maintained where lowflow rate is limiting B. A and B train fans will get a start signal at 60.1 and 60.6 minutes respectively, aAer start of the "CIB" tuners, with the B train having a separate time delay of 0.5 minutes. If aAer 0.5 minutes the A train is not perfornung as eved B will start and A (if runmng) will stop.

C. Bottled air pressurization will be maintamed during this sequence D. The only time where two fans could be running at the same time should be minimized as B fan starts and shuts A fan down.

In addition to the above, P %ient Engia~ dog requested that NED confirm that the purge fan flow rates of 33,500 cfm for Unit I and 18,000 cfm for Unit 2. Specifically, the muumum expected flow rates are needed as these would be limiting. benner these fans are used to purge the control room of radmactivity aAer release to the environment has ended, the lowest expected flow should be used to bound the accident en==~=

. Response to the engmeering memormadum request (EM 115712, Ref: 21 of the Generic Contol Room Modleling Appendix) rewi.saxi using 28,000 cfm for Unit I and 16,900 cfm for Unit 2 as boundmg values for low flow where the low flow condition is limiting.

9

i RTL' n/a Form: RE 1.103 3 s92 k *"*

ERS-MPD-91-035 page in Health Physics Department Revision 1 Annendir 2 l
Determination of RCS Volume. S/G Liouid and Steam Volumes for DBA Radioloalcal Calculations:
l RCS MASS UNIT 1 AND UNIT 2:
1 Reactor Coolant System (RCS) liquid mass used in several past Radiological Engineering and Stone & Webster Engineering calculation packages has varied from 3.9E5 lbm to 4.2E5 lbm.
During reanalysis of several design basis accidents (DBAs) conducted in January of 1998, this parameter was noted as having influence on radioactivity released from fuel and transferred through the various compartments of a dose analysis model Because different values were documented, determination of a bounding value is necessary.
For Unit 1, UFSAR Table 148-5 gives 9387 ft* (x 0.02221 lbm/ft* @ 577 F = 4.23E5 lbm) for RCS liquid volume. This value was used in more recent consequence analyses. A 1987 letter from DLCo engineering to SWEC (ND1NEM:1144) provided parameters for use in radiological consequence analyses for combined control room habitability. This latter gave 3.9E5110% lbm with a note for the dose analyst to apply uncertainty in the conservative direction. The range is 4.29E5 to 3.51E5 lbm.
DLCo engineering calculation package 10080-DMC-0015 (1989) calculates RCS liquid volume by calculating and addmg major component volumes. This methodology is expected to result in a conservatively low value for volume due to various small volumes not considered. The text notes that although the package uses volumes from Unit 1, design similarities extend validity to Unit 2. Estimated RCS volume and mass is:
ft' PZR PZR Volesch 8 co m po n e nts 100% pwr N o Load R x ve ssel 3707 1
3707 3707 H o t le g 93 3
2 7.9 279 C old le g 225 3
675 675 S u rg e lin e 30 1
30 30 P Z R (full io e d )
840 1
840 340 s/G 1080 3
3240 3240 c o ola nt pu m p 56 3
168 168 TOTAL =
8939 8439 L e ss s /G plu g gin g a t 3 0 % =
-755.6
-755.6 l
ft' 8183.4 7683.4 C o n ve rsio n to Ib m 0.02221 3.6 8 E + 0 5 3.4 6 E + 0 5 10080-DMC-0015 supports use of a lower bounding value of 3.51E5 lbm (3.9E5-10%). The UFSAR listed mass (4.23E5 lbm) supports use of 4.29E5 lbm (3.9ES+10%) as an upper bounding value for RCS mass. In addition, the hot zero power (HZP) mass may be as low as 3.46E5 using 10080-DMC-0015 as a reference and considering pressurizer no load level and full 30% steam generator tube plugging. Because of the small difference between 3.46E5 and 3.51ES (both round to the same two significant digit value), the conservative methodology used to calculate the lower value and the small influence that parameter has on calculated dose, 3.51E5 lbm (based on ND1NEM:1144) is suitable for the bounding, low value. When selecting the bounding value for use in radsological engineenng calculations, the analyst must confirm whether the boundog (conservative) value is the upper or lower mass.
uAss a noc J
RTL n/a Fann: RE 1.103-3 A14 ha ERS-MPD-91-035 page in Health Physics Department Revision 1 Annendir 2 STEAM GENERATOR LIQUID AND STEAM MASS UNIT 1:
Letter ND1NEM:1144 also provides 9.79E4110% lbm for a single steam generator liquid mass and 6.46E3i8% lbm for single steam generator steam mass, again with the direction to the analyst to apply the uncertainty in the appropriate direction. UFSAR listed values and those used previously in DBA calculations fall within this range (97,900 and 6,460 were used). As part of the research performed to confirm the Unit 2 values, Westinghouse was requested to confirm those from ND1NEM;1144 or provide new values for Unit 1. Westinghouse letter NSD-SAE-ESI-98-027 and Engineenng Memorandum 11578 provided the fetSg larmting values to use for Unit 1 accident analyses:
MINIMUM Liquid Mass (each S/G) = 9.34E4 Itwn (basis 103,868-10% bm @ 100% power,30% plugging)
MAXIMUM Liquid Mass (each S/G) = 1.64E5 Itwn (basis 148,513+10% bm @ 10% power 30% plugging)
MlNIMUM Steam Maes (each S/G) = 4.98E3 lbm (basis 5,542-10% lbm O 10% power 30% plugging)
MAXIMUM Steam Mass (each S/G) = 7.08E3 Itwn (beeis 6,436+10% bm O 100% power 0% plugging)
STEAM GENERATOR LIQUID AND STEAM MASS UNIT 2:
The Unit 2 UFSAR listed steam generator liquid mass as 99,200 lbm and steam mass as 8,700 lbm. These values were used in SWEC calculation 12241 UR(B)-445 (1987) which analyzed all Unit 2 accidents except the DBA LOCA for combined control room habitability. The liquid mass referenced source is a 1978 Westinghouse letter (DMW-D-1757) that provides "first drafts of Westinghouse input to Section 11.1 ' Source Terms' for the Beaver Valley 2 FSAR" The steam mass referenced source is calculated using the liquid mass provided in this letter and is documented on a single page interoffice correspondence sheet (attachment B to 12241 UR(B)-
445). Because of the tinhinna reliabiilty of these sources, Westmghouse was requested through G. Kammerdeiner, to provide values for Unit 2. Though the available values for Unit 1 were considered reliable, new values were also requested to confirm them The new bounding values a
for Unit 2 (provided as noted above) are:
MINIMUM Liquid Mass (each S/G) = 9.20E4 lbm (basis 102,230-10% bm O 100% power 20% plugging)
MAXIMUM Liquid Mass (each S/G) = 1.63E5 linn (basis 148,133+10% bm @ 0% power 20% plugging)
MINIMUM Steam Mass (each S/G) = 5.09E3 lbm (basis 5,859-10% hm @ 10% power 20% plugging)
MAXIMUM Steam Mass (each S/G) = 7.19E3 lbm (basis 6,534+10% bm O 100% power 0% plugging)
When selecting the bounding value for use in radiological engineering calculations, the analyst must confirm whether the bounding (conservative) value is the upper or lower (or if power specific, the appropnate value).
MASSESDOC A
_

ML20195D022

Text

Subject:

References:

Dear Steve:

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