ML20135F758

Rev 0 to SM-96-1100-001, MSLB Allowable Tube Leakage

ML20135F758
Person / Time
Site:	Farley
Issue date:	04/01/1996
From:	Wehrenberg J SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20135F756	List: ML20135F754 ML20135F758
References
SM-96-1100-001, SM-96-1100-001-R00, SM-96-1100-1, SM-96-1100-1-R, NUDOCS 9703130428
Download: ML20135F758 (27)

Text

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l Ca.lculation Cover Sheet Southern Company Services L l Calculation Number SM-96-1100-001 Project Discipline Farley Nuclear Plant Mechanical l Objectne RLA Number I Determine the allowable primary to-secondary leakage in the event of a steam line break. 96-1100 Subject /litle MSLB Allowable Tube Leakage , m Design Engmeers Signature // - f Date Last Page Number j J. A. Wehrenberg // /, 3/22 / 96 62 l

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Contents

'I opic

/ Page Attachments Number of Pages Purpose of Calculation /

l/I TACT 5 Output Files 46 Summary of Conclusions l l

Criteria l l I

I Major Lquation Sources /

2 Ikrivation Methods Assumptions 2

List References 3 llody of Calculations 4 4

safety Related g Yes Nonsafety-Related That Could Yes No impact Safety Related No Recor'd of Revisions Rev. No Description Originator / Reviewer / ProJ Lngr.

Date Date Date o Original issue

%,g,p gjg ,

b Notes:

1 9703130428 970307 PDR ADOCK 05000348 P PDR

CaJcdlation Cover Sheet Southern Company Services Project Calculation Number I Farley Nuclear Plant SM-961100-001

$ubject/litic $heet MSL11 Allowable Tube Leakage I of 62 l l

l Purpose :

In support of the steam generator alternate repair criteria developed for ODSCC at tube support plates (TSPs)

under Generic Letter 95-05, this calculation determines the allowable primary-to-secondary leakage in the -

l event of a steam line break. The analysis is similar to that submitted to the NRC by letter dated 6/4/92 with i the following exceptions:

1. The thyroid dose conversion factors ofICRP-30 should be used.

2. The acceptance criteria should be those of the SRP (NUREG-0800) section 15.1.5.

3. The initial primary coolant iodine activity for an accident initiated iodine spike should be 0.5 pCi/gm and for the pre-accident iodine spike the activity should be 30 Ci/gm.

4. An evaluation of the control room operator dose should also be included.

Criteria : I l

SRP 15.1.5 indicates:

1. for an MSLB with an assumed preaccident iodine spike the calculated doses should not ,

exceed the guideline values of 10 CFR Part 100, Section 1I (25 Rem whole-body or 300 Rem thyroid),and

2. for an MSLB with the equilibrium iodine concentration for continued full power operation in combination with an assumed accident initiated iodine spike, the calculated doses should not exceed a small fraction of the above guideline values,i.e.10 percent or 2.5 Rem and 30 Rem respectively for the whole body and thyroid doses.

In addition, the control room operator dose is limited by 10 CFR 50, Appendix A, General Design Criterion 19, to 5 Rem whole-body or its equivalent to any part of the body. This latter is taken as 30 Rem thyroid.

Conclusions :

l l Based on the criteria above, the maximum allowable steam generator tube leakage in the steam generator with the main steam line break is 20 gpm.

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Calculation Cover Sheet Southern Company Services Project Calculation humber Farley Nuclear Plant SM 961100-001 Subject /Dtle Sheet MSLB Allowable Tube Leakage 2 of 62 Ma_ior Eauntions :

The calculations are prepared using the TACT V computer code, installed on a NEC P90 computer. Proper operation of the program was verified by running the test problems and comparing the output to that provided in reference 4. A listing of the TACT 5 directory is included at the end of the calculations. The equations for the numerical solutions for activity transport, and the equations for the resultant doses are described and discossed in reference 4. Equations used to derive input values for the computer analyses are explained in the body of the calculation.

Assumntions :

1. Whole body doses have been previously found not to be near the acceptance criteria. Reference 1 indicates that similar analyses, i.e. with an iodine spike, did not have limiting whole body doses. Reference 8d indicates that whole body doses are several orders of magnitude below thyroid doses without consideration ofiodine spiking, which would increase thyroid doses significantly but would have no significant impact on whole body doses. Therefore only thyroid doses are considered, consistent with references 1 and 7. I i

2. RCS initial dose equivalent iodine activities are calculated based on the isotopic ratios currently used in I the FSAR and the dose conversion factors from ICRP-30. The isotopic ratios are shown in FSAR Table  ;

11.1-2, based on reference 5, and the dose conversion factors are taken from reference 4a (appendix E). J

3. Reference 7 modeled the RCS cleanup via the letdown system. RCS mass is taken from reference 6, and includes the volume of the CVCS. The CVCS cleanup is not modeled in the current calculation, but the volume is included so the cleanup may be easily included in the model in the future.

4. Secondary side steam releases, iodine partition factors, and iodine spike appearance rates are taken from reference 1, except the ruptured generator steam release which is taken from reference 8b as it is slightly more conservative than reference 1.

5. Site boundary and LPZ accident x/Qs are assumed equal to the current FSAR values (reference 8c).

6 Control room parameters are taken from reference 8a as modified by references 9 and 10 (x/Q, volume, and maximum flow rate).

Calculation Cover Sheet Southern Company Services Project Calculation Number Farley Nuclear Plant SM 96-1100-001 hubject/l'itle Sheet MSLB Allowable Tube Leakage 3 of 62 References :

1. APC letter," Request for Additional Information Concerning the Steam Generator Alternate Pluggmg j Criteria", dated June 4,1992. l

2. Title 10 CFR; Section 50, Appendix A; and Section 100.11.

3. NUREG-0800," Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," Section 15.1.5, Revision 1, July 1981.

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4. TACT 5 Documentation

a. NUREG/CR-5106, " User's Guide for the TACTS Computer Code," June 1988.

b. NS-94-02, " Verification of TACT 5," 4/15/92.

5. Radiation Analysis Design Manual, Joseph M. Farley Plant, Table 6-5,4/72.

6. FNP Uprate Analysis Input Assumptions, Westinghouse Letter ALA-95-756,12/15/95.

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7. NRC letter," Issuance of Amendment - Joseph M. Farley Nuclear Plant, Unit 1," 9/28/95.

8. FSAR Sections and Tables:

a. Table 15.4-16 (Control Room Parameters)  !

b. Table 15.4-23 (MSLB Input Parameters)

c. Table 2.3-12 (Offsite x / Q Parameters)

d. Section 15.4.2.1.4 (MSLB Radiological Consequences)

9. DCP 95-0-8863-1-1 (Control room normal HVAC)

10. FNP Calculations 42.01, Rev. O and 41.07, Rev. O.

I1. FNP-1-RCP-252, Revision 30," Radiation Monitoring System Setpoints."

12. U-262532, Victoreen Radiation Monitoring Tech. Manual  ;

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Calculation Cover Sheet Southern Company Services Project Calculation Number Farley Nuclear Plant SM-96-1100-001 Sutject/litic Sheet MSLB Allowable Tube Leakage 4 of 62 l Body of Calculation :

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1. Dose Eauivalent Iodine Source Term The dose equivalent iodine inventory for 30 Ci/gm is calculated as described in assumption 1:

l Isotope RCS Concentration ICRP-30 DCF Relative DEIni FNPDEI30 l l pCi/gm Concentration Source Term '

6 6 I-131 2.5 1.1 x 10 2.750 x 10 23.3 6 6 l l-132 0.9 0.0063 x 10 0.006 x 10 8.38 6 6 1-133 4.0 0.18 x 10 0.720 x 10 37.2 6 6 I-134 0.6 0.0011 x 10 0.001 x 10 5.59 6

I-135 2.2 0.031 x 10 0.068 x 10 6 20.5 6

Total 3.545 x 10 6 6 Then the RCS concentrations are multiplied by the ratio of 30 x 1.1 x 10 / 3.545 x 10 = 9.309 and the resulting values are entered into file FNPDEI30 as Ci / MWt and the remainder of the date is taken from reference 4a:

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e Calculation Cover Sheet Southern Company Services Projcet Calculation Number Farley Nuclear Plant SM-96-1100-001 Subject /litic Sheet MSLB Allowable Tube Leakage 5 of 62 1

l 2 3 3 0 0 t i i 133 WHOLEDDY SKIN THYROlD 9.219000E-06 3.720000E+01 l

HALOGENS 9.110000E-02 8.900000E-021.800000E 05 l ELEM. ORG. PART. 0.0 0.0 0.0 1 131 0.0 0.0 0.0 9.963996E-07 2.330000E+01 3 1 0 0 0 0 0 5.590000E-02 3.070000E-021.100000E 06 1 134 0.0 0.0 0.0 2.228000E-04 5.590000E+00 0.0 0.0 0.0 4.110000E-01 1.420000E-01 1.100000E 03 l I 1- 0 0 0 0 0 0.0 0.0 0.0 1 132 0.0 0.0 0.0 8.269001E-05 8.380000E+00 4 1 0 0 0 0 0 3.550000E-01 1.100000E-016.300000E 03 I I35 0.0 0.0 0.0 2.864000E-05 2.050000E+0i 0.0 0.0 0.0 2.490000E-017.860000E-02 3.100000E 04 2 1 0 0 0 0 0 0.0 0.0 0.0 0.0 0.0 0.0 5 l 0 0 0 0 0

Calculation Cover Sheet Southern Company Services Project Calculation Number j Farley Nuclear Plant SM.%1100-001

< Subjectflitic Sheet MSLB Allowable Tube Leakage 6 of 62 i

2. Pre-accident lodine Snike RCS Parameters:

4 The RCS mass from reference 6 is 425,763 lbs and the CVCS mass is 30,900 lbs, for a total of 456,663 lbs, I 8 3 or 2.073 x 10 gm. The RCS volume is 9984 ft , and the equivalent RCS + CVCS volume entered as node 1 4

in the TACT 5 modelis 9984 ft3 x 456,663 / 425,763 = 1.071 x 10 ft'.

i-Steam Generator Parameters:

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i 8 Intact generators (TACT 5 node 2) steam release is 479,000 lbs ( reference 1 and 8b) = 2.175 x 10 gm. The

' initial inventory is assumed to be the technical specification limit 0.1 ' Ci/gm . Since the source term file is 8 4 based on 30 pCi/gm, the initial inventory is set to 2.175 x 10 gm x 1 x 10 Ci / pCi x 0.1/ 30 = 0.725 so that when multiplied by the source term file the results are DEI curies. The releases are processed through a l

i. 90% efficient filter to simulate the 0.1 partition fraction (reference 1) for steam releases. The volume is arbitrarily input as 1,000 ft3 and the release rate entered to ensure the entire volume is exhausted to the 3

atmosphere: 50 cfm x 120 min = 6,000 ft = 6 volumes. Review of the TACT 5 output verifies that  !

insignificant activity remains in the intact generators after two hours.

7 j . Rupturedgenerator (TACT 5 node 3) steam release is 96,200 lbs (reference 8b) = 4.367 x 10 gm. As above a the initial inventory is assumed to be 0.1 Ci / gm and the computer input is set to 4

} 4.367 x 10' gm x 1 x 10 Ci / Ci x 0.1/ 30 = 0.1456 so that when multiplied by the source term file the

results are DEI curies. No filter is modeled as the ruptured generator is assumed to dry out and release 100%

( of the contained activity. The volume is arbitrarily input as 1,000 ft3 and the release rate entered to ensure j the entire volume is exhausted to the atmosphere in 30 minutes:

3 500 cfm x 30 min = 15,000 ft = 15 volumes. Review of the TACT 5 output verifies that insignificant

activity remains in the ruptured generator after 30 minutes.

The steam generator tube leakage from the RCS to the ruptured generator is modeled as a direct transfer to i the atmosphere without filtration as the partition factor is taken as 1 (reference 1). The transfer rate (cfm) is

! parametrically varied until the site boundary thyroid dose is approximately equal to the acceptance criteria (300 Rem). The annotated input file (FNPMSLBP.in)is shown below:

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

Calculation Cover Sheet Southern Company Services Project Calculauon Number Farley Nuclear Plant SM 96-1100-001 hubject/lille Sheet MSLB Allowable Tube Leakage 7 of 62

'c:fnpdei30 '

'c:LTAPE ','c:MTAPE ','c:NTAPE '

Farley Main Steam Line Break (MSLB) with 30 uCi/gm Pre-accident i Spike '

0, 0,1,1, 0 3, 2

' RCS ','intactSG','RuptrdSG' 5

1.000 E+00, 0.000E+00 Power = 1, with no decay 1.000E+00, 0.000E+00 Release fraction = 1 0.000 E+00,0.000E+00 No plateout 1.000E+00,0.000E+00,0.000E+00 Activity is all elemental 1.000E+00,0.000E+00, 0.000E+00 1.071 E+4,1.000E+03,1.000 E+03 RCS, Intact SG, Ruptured SG volumes TIME INTERVAL ',0,0,0,0,2,0.000E+00,2.778E-06 Short time interval, may be used to verify initial activity

'INITI AL FRACTION',0,0,0,0,3,2.073E+02,7,250E-01,1.465E-01 Initial inventory factors for RCS, Intact SG, and Ruptured SG (small numerical error in the latter will not impact results).

' FILTER EFF ',1,1,0,1,3, 0.000 E+ 00, 0.000 E+00, 0.000 E+00 No filtration for tube leakage

' FILTER EFF ' 1,1,0,2,3,0.900E+02,0.000E+00,0.000E+00

, 90 % filter for intact SG

' FILTER EFF ' 1,1,0,3,3, 0.000 E+ 00, 0.000 E +00, 0.000 E +00

, No filtration for ruptured SG TRANSFER CFM

• 0,0,0,1,4,1.640E+01,1.000E+00,0.000E+00,0.000E+00

, Tube leak rate, varied parametrically until the site boundary thyroid dose is apprevimately at the acceptance criteria.

TRANSFER CFM ' 0,0,0,2,4, 5.000 E+ 01, 0.000 E+00, 1.000 E+00, 0.000 E+00

, Intact SG exhaust rate TRANSFER CFM ',0,0,0,3,4, 5.000 E +02, 0.000 E+00, 0.000 E+00, 1.000 E +00 Ruptured SG exhaust rate

' DOSE PARAMS

• 0,0,0,0,5,7.600E-04,3.470E-04,2.800E-04,3.470E-04,1.000E 50

, X/ Q and breathing rates for Site Boundary and LPZ. The last entry is an arbitrarily small leak rate required by TACT 5, but not used in the calculation.

71ME INTERVAL ',0,0,0,0,2,2,778E-06,5.000E-01

' FILTER EFF ' 1,1,0,1,3, 0.000 E+00, 0.000 E+00, 0.000 E+00

' FILTER EFF ' I ,1,0,2,3, 0.900 E+ 02, 0.000 E+00, 0.000 E +00

' FILTER EFF ',1,1,0,3,3, 0.000 E+00, 0.000 E +00, 0.000 E+00 TRANSFER CFM ' 0,0,0,1,4, 1.640 E+01, 1.000 E+00, 0.000 E+00, 0.000 E +00 TRANSFER CFM ' 0,0,0,2,4, 5.000 E+01, 0.000 E+00, 1.000 E+00, 0.000 E+00

' TRANSFER CFM ' 0,0,0,3,4, 5.000 E+02, 0.000 E+00, 0.000 E+00, 1.000 E+00

' DOSE PARAMS ' 0,0,0,0.5,7.600E-04,3.470E-04,2.800E-04,3.470E-04,1.000E 50 TIME INTERVAL ',0,0,0,0,2,5.000E-01, l.000E+00

' FILTER EFF ' 1,1.0,1,3, 0.000 E+00, 0.000 E+00, 0.000 E+00

' FILTER EFF ',1,1,0,2,3, 0.900E+02, 0.000 E+00, 0.000 E+00

' FILTER EFF ' I ,1,0,3,3, 0.000 E+00, 0.000 E+00, 0.000 E+00

' TRANSFER CFM ' 0,0,0,1,4, 1.640 E +01, 1.000 E+00, 0.000 E+00, 0.000 E+ 00

' TRANSFER CFM ' 0,0,0,2,4, 5.000 E+01, 0.000 E+00, 1.000 E+ 00, 0.000 E+00

' TRANSFER CFM ' 0,0,0.3,4, 1.000 E+00, 0.000 E+00, 0.000 E+00, 1.000 E+00

, Exhaust rate reduction has no impact because there is no significant activity left in the generator.

' DOSE PARAMS ',0,0,0,0.5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470 E-04, 1.000 E-50

Calculation Cover Sheet Southern Company Services Project Calculation Number Farley Nuclear Plant SM-96 1100-001

Sub. ject /litic Sheet MSLD Allowable Tube Leakage 8 of 62 TIME INTERVAL ',0,0,0,0,2,1.000E+00,2.000E+00

, 'F1LTER EFF ', I ,1,0,1,3, 0.000 E+ 00, 0.000 E+00, 0.000 E+00

' FILTER EFF ',1,1,0,2,3, 0.900 E+02, 0.000 E+00, 0.000 E+00

' FILTER EFF ' I,1,0,3,3,0.000E+00,0.000E+00,0.000E+00 4

TRANSFER CFM ' 0,0,0,1,4, 1.640 E+01, 1.000 E+00, 0.000 E+00, 0.000 E+00 TRANSFER CFM ' 0,0,0,2,4, 5.000E+ 01, 0.000 E+00, 1.000 E+00, 0.000 E+00 TRANSFER CFM ',0,0,0,3,4, 1.000 E+00, 0.000 E +00, 0.000 E+00. 1.000 E +00

' DOSE PARAMS ' 0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, ' a.470 E-04, 1.000 E-50 TIME INTERVAL ',0,0,0,0,2,2.000E+00,8.000E+00 i TRANSFER CFM ',0,0,0,1,4, 1.640 E+01, 1.000 E+00, 0.000 E+00, 0.000 E+00

' DOSE PARAMS ',0.0,0,0,5,0.000E+00,3.470E-04,1.100E-04,3.470E-04,1.000E 50 Site boundary X / Q set to zero 1- to terminate the problem.

'END ' 0,0,0,0,0, 0.000E+00, 0.000 E+00, 0.000 E+00

] The resultant leak rate which yields a site boundary thyroid dose of about 300 Rem is then 16.4 R3 / min x 7,48 gal / R3 = 122 gpm.

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Calculation Cover Sheet Southern Company Services l'roject Calculauon Number Farley Nuclear Plant SM-96-1100-001 hubjcet/litle Sheet MSLB Allowable Tube Leakage 9 of 62

3. Accident Initiated Iodine Snike

! RCS Parameters:

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The RCS is modeled as above, except the initial inventory for the accident initiated iodine spike is based on l l 0.5 Ci / gm and a time dependent iodine spike is assumed. The initial inventory is set to 2

2.073 x 10 x 0.5 / 30 = 3.455. The time dependent iodine spike is modeled as a release from the core

, (TACT 5 node 4) to the RCS, where the core contains a large inventory of dose equivalent iodine which will not be depleted during the course of the accident. Based on reference 1, the accident initiated iodine spike corresponding to 500 times the appearance rate for i pCi / gm are halved to estimate the spike for an initial

, concentration of 0.5 Ci / gm:

)

Isotope 1 Ci / gm 0.5 Ci / gm Spike Rate Spike Rate i

(Ci / sec) (Ci / sec) 1-131 1.34 0.67 ,

1-132 2.53 1.265

) 1-133 3,05 1.525 l-134 3.9 1.95 1-135 2.87 1.435 5

Then the core inventory is set at 0.67 Ci / sec x 3600 sec / hr x 8 hr x 10 = 1.930 x 10 Ci where the factor of 10 ensures the depletion of the core will not significantly impact the spike rate. The source term file ,

(FNPDE130) has values of Ci / gm, but is interpreted by TACT 5 as Ci / MWt. Since the core power, release fraction and plateout fraction are set to 1, the initial inventory is set to 5 3 1.93 x 10 +23.3 = 8.283 x 10 so that when multiplied by the source term file the results are DEI curies. For an assumed I cfm transfer rate, the volume of the core is based on 0.67 Ci / see x 60 sec / min = 1.93 x 105 Ci x 1 cfm + volume, or volume = 4800 ft3.

Steam Generator Parameters:

The steam generators are modeled as above. The transfer rate (cfm) is parametrically varied until the site boundary thyroid dose is approximately equal to the acceptance criteria (30 Rem). The annotated (indicating differences from FNPMSLBP.in above) input file (FNPMSLBA.in) is shown below:

a Calculation Cover Sheet Southern Company Services lioject Calculation Number Farley Nuclear P! ant SM-96-1100-001 -

Subject /litle Sheet MSLB Allowable Tube Lcakage 10 of 62

'c:fnpdei30

'c:LTAPE ','c:MNPE '.'c:NTAPE '

Farley Main Steam Line Break (MSLB)

• I with Accident Initiated i Spike 0, 0,1, I, 0 4, 2 Number of nodes increased to include the core

' RCS ','IntactSG','RuptrdSG',' Core ' Core node added 6

1.000E+00, 0.000E+00 1.000E+00,0.000E+00 0.000E+00,0.000E+00 1.000 E+00, 0.000E+00, 0.000E+00 1.000E+00, 0.000E+00, 0.000E+00 1.071 E+4, 1.000E+03, 1.000 E+03, 4.800 E+3 Volume of the core node is added

' TIME INTERVAL ',0,0,0,0,2,0.000E+00,2.778E-06

'IN ITI AL FRACTION',0,0,0,0,4, 3.455 E+00, 7.250E-01,1.465E-01, 8.283 E+03 Initial inventory of the core node added

' FILTER EFF ',1,1,0,1,3, 0.000 E+00, 0.000 E+00, 0.000 E +00

' FILTER EFF ',1,1,0,2,3, 0.900 E+02, 0.000 E4 00, 0.000E+00

' FILTER EFF ' 1,1,0,3,3, 0.000 E+ 00, 0.000 E+00, 0.000 E+00 TRANSFER CFM ',0,0,0,1,4, 2.700 E+00, 1.000 E+00, 0.000 E+00, 0.000 E+00 Tube leak rate, varied parametrically TRANSFER CFM ',0,0,0,2,4, 5.000 E+01, 0.000 E+00, 1.000 E+00, 0.000 E+00 TRANSFER CFM ',0,0,0,3,4, 5.000 E+02, 0.000 E+00, 0.000 E +00, 1.000 E+00 TRANSFER CFM ',0,0,0,4,4,0.000E+00, l.000E+00,0.000E+00,0.000E+00 Transfer from the core to the RCS added

' DOSE PARAMS

• 0,0,0,0,5,7.600E-04,3.470E-04,2.800E-04,3.470E-04,1.000E-50 TIME INTERVAL ',0,0,0,0,2,2.778E-06,5.000E-01

' FILTER EFF ',1,1,0,1,3, 0.000 E +00, 0.000 E+00, 0.000 E+00

' FILTER EFF ' 1,1,0,2,3,0.900E+02,0.000E+00,0.000E+00

' FILTER EFF - ',1,1,0,3,3, 0.000 E +00, 0.000 E +00, 0.000 E+00

' TRANSFER CFM ' 0,0,0,1,4, 2.700 E+00, 1.000 E+00, 0.000E+00, 0.000 E+00 TRANSFER C FM ',0,0,0,2,4, 5.000 E+0 l , 0.000 E+00, 1.000 E+ 00, 0.000 E+00 TRANSFER CFM ',0,0,0,3,4, 5.000 E+02, 0.000 E+00, 0.000 E+ 00, 1.000 E +00 TRANSFER CFM ',0,0,0,4,4, 0.000 E+00, 1.000 E +00, 0.000 E+00, 0.000 E+00

' DOSE PARAMS ',0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470 E-04, 1.000 E-50 TIME INTERVAL ',0,0,0,0,2,5.000E-01,1.000E+00

' FILTER EFF ' 1,1,0,1,3,0.000E+00,0.000E+00,0.000E+00

' FILTER EFF ' 1,1,0,2,3,0.900E+02,0.000E+00,0.000E+00

' FILTER EFF ' I ,1,0,3,3, 0.000 E+ 00, 0.000 E+00, 0.000 E+00 TRANSFER CFM ' 0,0,0,1,4, 2.700 E+00, 1.000E+00, 0.000E+00, 0.000 E+00 l

TRANSFER CFM ',0,0,0,2,4, 5.000 E+ 01, 0.000 E+ 00, 1.000 E+00, 0.000 E+00 TRANSFER CFM ',0,0,0,3,4, 1.000 E +00, 0.000 E+00, 0.000 E+ 00, 1.000 E + 00 TRANSFER CFM ' 0,0,0,4,4, 0.000 E+ 00, 1.000 E+ 00, 0.000 E+00, 0.000 E +00

' DOSE PARAMS ' 0,0,0,0.5, 7.60G E-04, 3.470E-04, 2.800 E-04, 3.470E-04, 1.000 E-50 TIME INTERVAL ',0,0,0,0,2,1.000E+00,1.500E+00

' FILTER EFF ' 1,1,0,1,3, 0.000 E+00, 0.000 E+00, 0.000E+00

' FILTER EFF ',1,1,0,2,3, 0.900 E+02, 0.000 E+00, 0.000 E+00

' FILTER EFF ',1,1,0.3.3, 0.000 E+00, 0.000 E+00, 0.000E+00 TRANSFER CFM ',0,0,0,1,4, 2.700 E+00, 1.000 E + 00, 0.000 E+ 00, 0.000 E +00

' TRANSFER CFM ' 0,0,0,2,4, 5.000 E+01, 0.000E+00, 1.000E+00, 0.000 E+00

..  ;. i Calculation Cover Sheet Southern Company Services Project Calculation Number l

Farley Nuclear Plant SM-96-1100-001 hubjectflitle Sheet MSLB Allowable Tube Leakage 11 of 62 TRANSFER CFM ' 0,0,0,3,4, 1.000 E+00, 0.000 E+00, 0.000 E+00, 1.000 E+00 TRANSFER CFM ',0,0,0,4,4, 0.000 E+00, 1.000E+00, 0.000 E+00, 0.000E+00

' DOSE PARAMS ' 0,0,0,0.5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470E-04,1.000 E-50 TlME INTERVAL ',0,0,0,0,2,1.500E+00,2.000E+00

' FILTER EFF ' 1,1,0,1,3,0.000E+00,0.000E+00,0.000E+00

' FILTER EFF ',1,1,0,2,3, 0.900 E+02, 0.000 E+00, 0.000 E +00

' FILTER EFF ',1,1,0,3,3, 0.000 E+00, 0.000 E+00, 0.000 E+00

' TRANSFER CFM ',0,0,0,1,4, 2.700 E +00, 1.000 E+00, 0.000 E+00, 0.000 E+00 TRANSFER CFM ',0,0,0,2,4, 5.000 E +01, 0.000 E+00, 1.000 E+00, 0.000 E+00 TRANSFER CFM ',0,0,0,3,4, 1.000 E+00, 0.000 E+00, 0.000 E+00, 1.000 E +00 TRANSFER CFM ' 0,0,0,4,4, 0.000 E+00, 1.000 E+00, 0.000 E+00, 0.000E+00

' DOSE PARAMS ' 0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470E-04, 1.000 E-50 TIME INTERVAL ',0,0,0,0,2,2.000E+00,8.000E+00

' TRANSFER CFM ' 0,0,0,1,4, 2.700 E+00, 1.000 E+00, 0.000 E+00, 0.000E+00 TRANSFER CFM ',0,0,0,4,4, 0.000 E+00, 1.000 E+00, 0.000 E+00, 0.000 E +00

' DOSE PARAMS ',0,0,0,0,5, 0.000 E+00, 3.470 E-04, 1.100 E-04, 3.470 E-04, 1.000 E-50 l

'END ',0,0,0,0,0, 0.000 E+00, 0.000 E+00, 0.000 E+00 l l

I The resultant leak rate which yields a site boundary thyroid dose of about 30 Rem is then 3 3 2,7 ft / min x 7.48 gal / ft = 20.2 gpm. The maximum allowable technical specification tube leakage for the two intact generators is 140 gpd x 2 + 24 hr / day + 60 min / hr = 0.194 gpm, so the maximum allowable tube leakage for the ruptured generator is 20 gpm.

l

Calculation Cover Sheet Southern Company Services Project Calculanon Number Farley Nuclear Plant SM-96-1100 001 Subject / fille Sheet MSLB Allowable Tube Leakage 12 of 62

4. Control Room Thyroid Dose for Pre-Accident Iodine Snike The pre-accident iodine spike yields the most limiting site boundary thyroid dose, and is therefor used as the base for the control room thyroid dose calculation. Input file FNPMSLBP.in is modified to include the control room as node 4. Physical parameters are input as per assumption 6:

5 Volume = 1.14,x 10 ft' Normal HVAC Intake Rate = 1350 cfm w/o filtration Unfiltered Inleakage = 10 cfm Pressurization Mode Intake Rate = 450 cfm 3 3 x / Q = 3.28 x 10 sec / m Intake Filter Efficiency = 99%

Recirculation Flow Rate = 3000 cfm (less 10%)

Recirculation Filter Efficiency = 95%

A review of the outp"ut from the offsite analyses indicates that the smallest short term (2.778 x 10-6 sec) release is 4.826 x 10 Ci, so that the control room intake concentration would be at least 4

4.286 x 10" Ci + 2.778 x 10 hr x (3.28 x 10'3 sec / m 3) x (hr / 3600 sec) = 1.4 x 10" pCi / cc which exceeds the setpoint for the radiation monitor (1.2 x 10" Ci l i3i / cc, excluding other isotopes, references 11 and 12) and automatic isolation should occur rapidly. This is assumed to occur 1 minute after the accident.

Because TACT 5 will not allow transfer from the environment back into a node the equivalent direct transfer rates Releaseto the rate control (cfm) room x x / Q (sec / m xvia unitatmosp)heric conversion factors releases x Control RoomareIntake calculated Rate (cfm),as:

or 3 3 release rate (cfm) x (3.28 x10'3 sec / m ) x (min / 60 sec) x (m / 35.3 ft') x intake rate (cfm) which 4

simplifies to: release rate x intake rate x 1.549 x 10 . Additionally, the intact generator iodine partition factor (0.1) is included in the transfer rate, and for the pressurization mode of control room operation, the transfer rates are multiplied by 0.01 for the intake filtration:

Release Normal Pressurized Unfiltered Normal Pressurized Unfiltered Rate intake Intake Inleak Transfer Transfer Transfer (cfm) (cfm) (cfm) (cfm) (cfm x 10-2) (cfm x 10") (cfm x 10") l RCS 16.4 1350 450 10 3.429 1.143 2.54 Intact 50 1350 450 10 1.05 0.3485 0.7745 SG Rupt. 500 1350 450 10 104.5 34.85 77.45 SG Since TACT 5 allows only one transfer between node pairs. the unfiltered transfer must be added to each of the others to arrive at a single value for entry into the code. The input file (FCRMSLBP.in) is shown below:

1

l l

i Calculation Cover Sheet Southern Company Services l Project Calculation Number Farley Nuclear Plant SM-96-1100-001

~

l Subject / fide Sheet MSLB Allowable Tube Leakage 13 of 62 l

I 1

'c:fnpdei30 '

'c:LTAPE ','c:MTAPE ','c:NTAPE '

Farley Main Steam Line Break (MSLB) Control Room '

l Dose with 30 uCi/gm Pre-accident i Spike I l

0, 0, I,1, 0 4, 2 ]'

Added I node

' RCS ','IntactSG','RuptrdSG','Cntrl_Rm' Added control room (CR) node 8 Increased number of time steps to smooth out the l control room iodine concentration changes input to EXEL spreadsheet. j l .000E+00, 0.000E+00 1.000E+00, 0.000E+00 0.000E+00, 0.000E+00 1.000 E+00,0.000E+00, 0.000 E+00 1.000E+00, 0.000E+00, 0.000E+00 1.071 E+4,1.000E+03,1.000E+03,1.14 E+05 Added control room volume TIME INTERVAL ',0,0,0,0,2,0.000E+00,2.778E-06

'I N ITI A L FRACTION',0,0,0,0,4, 2.073 E+02, 7.250 E-01, 1.465 E-01, 0.000 E+ 00 No initial activity in the control room

' FILTER EFF ' 1,1,0,1,3,0.000E+00,0.000E+00,0.000E+00

' FILTER EFF ',1,1,0,2,3, 0.900 E+02, 0.000 E +00, 0.000 E+00

'FlLTER EFF ',1, I ,0,3,3, 0.000 E+00, 0.000 E+00, 0.000 E+00 TRANSFER CFM ',0,0,0,1,5, 1.640 E+01, 1.000 E+00, 0.000 E+00, 0.000 E+ 00, 3.454 E-02 Add RCS transfer to CR TRANSFER CFM ' 0,0,0,2,5, 5.000 E+01, 0.000E+00, 1.000E+00, 0.000 E+00, 1.058 E-02

, Add intact SG transfer to CR TRANSFER CFM ' 0,0,0,3,5, 5.000E+02, 0.000E+00, 0.000E+00, 1.000 E+00, 1.053 E+00

, Add ruptured SG transfer to CR

' TRANSFER CFM ',0,0,0.4,5,1,360E+03,0.000E+00,0.000E+00,0.000E+00,0.000E+00 ' DOSE PARAMS ',0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470 E-04, 1.000 E-50

' TIME INTERVAL ',0,0,0,0,2,2.778E-06,1.667E-02 Additional time step l

'F1LTER EFF ' I,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00 I

'F1LTER EFF ',1,1,0,2,3, 0.900 E+02, 0.000 E+ 00, 0.000 E+00 i

' FILTER EFF ',1,1,0,3,3, 0.000 E +00, 0.000 E+00, 0.000 E+00 I TRANSFER CFM ' 0,0,0,1,5, 1.640 E+0 l , 1.000E+00, 0.000E+00, 0.000 E+00, 3.454 E-02

' TRANSFER CFM ' 0,0,0,2,5, 5.000 E+01, 0.000 E+00, 1.000E+00, 0.000 E+00, 1.058 E-02 TRANSFER CFM ' 0,0,0,3,5, 5.000 E+ 02, 0.000 E+00, 0.000 E+00, 1.000 E+00, 1.053 E+00 TRANSFER CFM ',0,0,0,4,5, 1.360 E+03, 0.000 E+ 00, 0.000 E+00, 0.000 E +00, 0.000 E+00

' DOSE PARAMS ' 0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470 E-04, 1.000 E-50 TIME INTERVAL ',0,0,0,0,2, I.667E-02,1.667E-01 Additional time step to start CR pressurization mode of operation.

' FILTER EFF ' I ,1,0,1,3, 0.000E+00, 0.000 E +00, 0.000E+00

' FILTER EFF ' 1,1,0,2,3, 0.900 E+02, 0.000 E+00, 0.000 E+00

, l

' FILTER EFF ',1,1,0,3,3, 0.000 E+ 00, 0.000 E+00, 0.000 E +00

' FILTER EFF ' I ,1,0,4,5, 0.000 E+ 00, 0.000 E+00, 0.000 E+00, 0.000 E+00, 9.500 E+0 i

, Add CR recirculation filter TRANSFER CFM ' 0,0,0,1,5, l .640E+01,1.000E+00, 0.000E+00, 0.000E+00, 3.683 E-04

, Change RCS transfer to CR TRANSFER CFM ',0,0,0,2,5, 5.000 E+01, 0.000 E +00, 1.000 E +00, 0.000 E+00, 1.123 E-04 Change intact SG transfer to CR

' TRANSFER CFM ',0,0,0,3,5,5.000E+02,0.000E+00,0.000E+00,1.000E+00,1.123E-02 Change Ruptured SG transfer to CR

! TRANSFER CFM ',0,0,0,4,5, 4.600 E+02, 0.000 E+ 00, 0.000 E+00, 0.000E+00, 2.700 E+03 Add CR recirculation flow

' DOSE PARAMS ' 0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470 E-04, 1.000 E-50

Calculation Cover Sheet - Southern Company Services L Project Calculauon Number Farley Nuclear Plant SM-96-1100-001 Subject /litle Sheet MSLB Allowable Tube Leakage 14 of 62 TIME INTERVAL ',0,0,0,0,2,1.667E-01,5.000E-01

' FILTER EFF ', I ,1,0,1,3, 0.000 E +00, 0.000 E+00, 0.000 E+00

' FILTER EFF ' 1,1,0,2,3, 0.900E+02, 0.000 E+00, 0.000 E+00

' FILTER EFF ',1,1,0,3,3, 0.000 E+00, 0.000 E+00, 0.000 E+00

' FILTER EFF ', I ,1,0,4,5, 0.000 E+00, 0.000 E+ 00, 0.000 E+00, 0.000 E+00, 9.500 E+ 01 TRANSFER CFM ' 0,0,0,1,5, 1.640 E+01, 1.000 E+00, 0.000 E+00, 0.000E+00, 3.683 E-04 TRANSFER CFM ',0,0,0,2,5, 5.000 E+01, 0.000 E+ 00, 1.000 E+ 00, 0.000 E+00, 1.123 E-04 TRANSFER CFM ' 0,0,0.3,5, 5.000 E+02, 0.000 E+00, 0.000 E+00, 1.000 E+00, l .123 E-02 TRANSFER CFM ' 0,0,0,4,5, 4.600 E+02, 0.000 E+00, 0.000 E+00, 0.000 E+00, 2.700 E+03

' DOSE PARAMS ' 0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470 E-04, 1.000 E-50 TIME INTERVAL ',0,0,0,0,2,5.000E-01,1.000E+00

' FILTER EFF ' 1,1,0,1,3, 0.000 E+00, 0.000 E+00, 0.000 E+00

' FILTER EFF ' 1,1,0,2,3,0.900E+02,0.000E+00,0.000E+00

' FILTER EFF ' I ,1,0,3,3, 0.000 E+00, 0.000 E+00, 0.000 E+ 00

'F1LTER EFF ' I ,1,0,4,5, 0.000 E+00, 0.000 E+00, 0.000 E+00, 0.000E+00, 9.500 E+0 I

' TRANSFER CFM ' 0,0,0,1,4,1.640E+01,1.000E+00, 0.000E+00, 0.000E+00 TRANSFER CFM ' 0,0,0,2,4, 5.000 E+01, 0.000 E+00, 1.000 E+00, 0.000 E+00 TRANSFER CFM ' 0,0,0,3,4, 1.000 E+00, 0.000E+00, 0.000 E+00, 1.000 E+00 1

TRANSFER CFM ' 0,0,0,4,5. 4.600 E+02, 0.000 E+00, 0.000 E+00, 0.000 E+00, 2.700 E+03

' DOSE PARAMS ',0,0,0,0,5, 7.600 E-04, 3.470 E-04, 2.800 E-04, 3.470 E-04, 1.000 E-50 TIME INTERVAL ',0,0,0,0,2,1.000E+00,2.000E+00

' FILTER EFF ' 1,1,0,1,3, 0.000 E+ 00, 0.000 E+00, 0.000 E+00

' FILTER EFF ' 1,1,0,2,3, 0.900 E+02, 0.000 E+00, 0.000 E+00

' FILTER EFF ', I ,1,0,3,3, 0.000 E+00, 0.000 E +00, 0.000 E+00 TlLTER EFF ', I ,1,0,4,5, 0.000 E+00, 0.000 E+00, 0.000 E+00, 0.000 E+00, 9.500 E+01 TRANSFER CFM ' 0,0,0,1,4, 1.640 E+01, 1.000 E+00, 0.000 E +00, 0.000 E +00 TRANSFER CFM ',0,0,0,2,4, 5.000 E+01, 0.000 E+00, 1.000 E+ 00, 0.000 E+ 00 TRANSFER CFM

• 0,0,0,3,4, 1.000 E+00, 0.000 E+00, 0.000 E +00, 1.000 E +00 TRANSFER CFM ',0,0,0,4,5, 4.600 E+ 02, 0.000 E +00, 0.000 E+ 00, 0.000 E+00, 2.700 E+03

' DOSE PARAMS ',0,0,0,0,5,7.600E-04,3.470E-04,2.800E-04,3.470E-04,1.000E 50 l TIME INTERVAL ',0,0,0,0,2,2.000E+00,4.000E+00 Add new time step

' FILTER EFF ' I ,1.0,4,5, 0.000E+00, 0.000 E+00, 0.000 E+00, 0.000 E+00, 9.500 E+01 TRANSFER CFM ' 0,0,0,1,4, 1.640 E+01, 1.000 E+00, 0.000 E+00, 0.000 E+ 00 TRANSFER CFM ',0,0,0,4,5, 4.600 E+02, 0.000 E+00, 0.000 E+ 00, 0.000 E+00, 2.700 E+03

' DOSE PARAMS ',0,0,0,0,5,0.000E+00,3.470E-04,1.100E-04,3.470E 04,1.000E-50 TIME INTERVAL ',0,0,0,0,2,4.000E+00,8.000E+00

' FILTER EFF ' I ,1,0,4,5, 0.000 E+00, 0.000 E+00, 0.000 E+00, 0.000 E+00, 9.500E+01 TRANSFER CFM ' 0,0,0,1,4,1.640E+01,1.000E+00,0.000E+00,0.000E+00 TRANSFER CFM ' 0,0,0,4,5, 4.600 E+02, 0.000 E+00, 0.000 E+00, 0.000 E+00, 2.700 E+03

' DOSE PARAMS ',0,0,0,0,5, 0.000 E+00, 3.470 E-04, 1.100 E-04, 3.470 E-04, 1.000 E-50

'END ' 0,0,0,0,0, 0.000 E+00, 0.000 E+00, 0.000 E+00

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

. .i Calculation Cover Sheet Southern Company Services Project Calculauon Number Farley Nuclear Plant SM-96-1100-001 Subject /litic Sheet i

MSLB Allowable Tube Leakage 15 of 62 The control room thyroid dose is then calculated for each time step, using an EXCEL spreadsheet, as:

l Activity (Ci) x Breathine Rate (m /3 sec) x Dose Conversion Factor (Rem / Ci) x 35.29 (ft2 Lm 2) x 3600 (sec/ hr)

~

3 i- 1.14 x 10' ft Where the activity is taken from the TACT 5 output file, the breathing rate is 3.47 X 10" and the dose conversion factors are taken from TACT 5:

Time (br) Activity 1131 (Ci) 1132 (Ci) 1133 (Ci) 1134 (Ci) 1135 (Ci) i 2.78E-06 3.23E-06 1.16E-06 5.15E-06 7.74E-07 2.84E-06 1.67E-02 1.85E-02 6.61E-03 2.95E-02 4.37E-03 1.62E-02 1.50E-01 1.59E-02 5.44E-03 2.53E-02 3.34E-03 1.38E-02 3.33E-01 1.18E-02 3.68E-03 1.86E-02 1.91E-03 9.91 E-03 5.00E-01 8.52E-03 2.28E-03 1.32E-02 9.20E-04 6.79E-03 1.00E+00 5.99E-03 1.20E-03 9.02E-03 2.91 E-04 4.32E-03 1 l

2.00E+00 4.56E-03 5.05E-04 6.46E-03 4.48E-05 2.69E-03 l 4.00E+00 3.10E-03 1.06E-04 3.90E-03 1.25E-06 1.23E-03 Exposure 1131 Ci-hr 1132 Ci-hr 1133 Ci-br 1134 Ci-br 1135 Ci-hr l

8.96E-12 3.22E-12 1.43E-11 2.15E-12 7.88E-12 3.08E-04 1.10E-04 4.91 E-04 7.28E-05 2.70E-04 2.39E-03 8.16E-04 3.79E-03 5.01E-04 2.06E-03 3.95E-03 1.23E-03 6.21 E-03 6.35E-04 3.30E-03 4.26E-03 1.14E-03 6.61 E-03 4.60E-04 3.39E-03 5.99E-03 1.20E-03 9.02E-03 2.91E-04 4.32E-03 9.11 E-03 1.01E-03 1.29E-02 8.96E-05 5.38E-03 1.24 E-02 4.24E-04 1.56E-02 5.00E-06 4.91 E-03 SUM = 3.84E-02 5.93E-03 5.46E-02 2.05E-03 2.36E-02 DCF (Rem /Ci) = 1.10E+06 6.30E+03 1.80E+05 1.10E+03 3.10E+04 Thyroid Dose (Rem) = 1.63E+01 1.44E-02 3.80E+00 8.74E-04 2.83E-01 TotalThyroid Dose (Rem) = 2.04E+01

Calculation Cover Sheet Southern Company Services Project Calculauon Number Farley Nuclear Plant SM-96 1100-001 I Subject /i nic Sheet MSLB Allowable Tube Leakage 16 of 62 l

l TACT 5 Directory Volume in drive C is DISK _C Volume Serial Number is IE29-0BDF Directory of C:\ TACT 5 I

<DIR> 03-29-95 I:40p

. < DIR> 03-29-95 1:40p l

VEGPFHA <DIR> 04-05-95 9:37a '

VEGPSPRA < DIR> 04-05 95 9:33a ARVSRVLK <DIR> 07-26-95 10:56a SAM l_OUT 2 36,100 04-05-95 12:40p NEC P 90 verification TACTS EXE 140,696 05-14-92 9:45a RUNTACTSBAT 15 09-22-87 3:37p  !

MLWRICRP 02 41,848 03 13-86 12:13p l MLWRICRP 30 33,237 01-01-80 1:33a EXAMPLEl INP 1,48511-23-57 8:56a EXAMPLE 2 INP 5,26012-15-87 12:18p TACT 5MD EXE 71,899 03-21-94 4:0lp TACTSMN EXE ' 35,13103-14-94 2:20p TACTSND EXE $6,825 03 21-94 4:03p SAMl_NUC 7,406 04-Il-94 1:50p SAM l_INP 1,458 03 31-94 2:36p i SAM l_OUT 0 36,100 04 11-94 1:51p Original file installation SALTAPE 29,004 04-05-95 12:4Ip SAMTAPE 26,412 04-05-95 12:41p SAM 2_NUC 7,406 04 11-94 1:50p I SAM 2_DAT 5,195 04-14-94 7:22a l SAM 2_OUT 0 24649 04-14-94 7:23a Original file installation VEGP_NUC I,406 04 27-94 8:53a SAM 2_OUT 2 20 649 04-05 95 12:4lp NEC P-90 verification SAMl_OUT 1 36,100 06-21-94 7:57a Dell verification SAM 2_OUT 1 20,649 06-21-94 8:04a Dell verification VELTAPE 15,306 06-16-95 9:18a VEMTAPE 11,852 06-16-95 9:18a FNPFilA < DI R> 02-01-96 1:44p FNPFHACR OT2 71,746 02-0196 8:32a FNP_NUC 6,38212-18 95 6:58a FNPFHACR IN2 9,366 02-01-96 8:31a FHADIR DOC 0 02-01-96 6:28p LTAPE 50,832 02-0196 8:34a FNPFHACT IN 3,305 01 31-96 1:54p MTAPE 23,768 02-01-96 8:34a FNPHFACT OTI 35,348 01-31-96 10:12a FNPFHACR INI 9,308 01-31-96 5:36p FNPFHAFB OUT 17,475 01-23-96 5:17p FNPFHACR OUT 77,209 0131-96 4:29p FNPFHAFB IN 1,65101-23-96 5:17p FNPFH ACR IN 9,45101-31-96 4:29p FNPGAP30 5,970 01-15-96 II:30a FNPFHACT OTI 35,348 01-31 96 1:56p FNPGAP02 5,969 01-15-96 10:44a FNPFH ACT INI 3,305 01-31-96 1:55p 48 file (s) 1,069,869 bytes FNPFHACT OUT 35,348 01-31-96 1:55p 338,411,520 bytes free

' ~

Calculation Cover Sheet Southern Company Services

. Project Calculau n Number.

Farley Nuclear Plant SM-96-1100-001 Subject /htle '**'

MSLB Allowable Tube Leakage g7 g7 g i

4 ATTACHMENT 1 -TACT 5 OUTPUT FILES i

( kob han s mi ch l

l l

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

3 . i.

)

, CALCULATION FOR THYROID DOSE IPRMS)

MULTI NODE CONTAINMENT WITH

< START , EXCLUSION RADIUS LOW POPULATION ZDud CONTROL ROOM

TIME EACH ACCUM. EACH ACCUM. EACH ACCUM.

! (HRS) STEP STEP STEP

, 0.000E+00 1.128E-04 1.128E-04 4.157E-05 4.157E-05 0.000E+00 0.000E+00 j 2.778E-06 3.681E+00 3.681E+00 1.356E+00 1.356E+00 0.000E+00 0.000E+00 j 5.000E-01 5.344E+00 9.025E+00 1.969E+00 3.325E+00 0.000E+00 0.000E+00 f 1.000E+00 8.496E+00 1.752E+01 3.130E+00 6.455E+00 0.000E+00 0.000E+00 1.500E+00 1.163E+01 2.915E+01 4.285E+00 1.074E+01 0.000E+00 0.000E+00

2.000E+00 0.000E+00 2.915E+01 5.194E+01 6.268E+01 0.000E+00 0.000E+00 l TOTAL 2.915E+01 TOTAL 6.268E+01 TOTAL 0.000E+00 1 NO MORE CASES END OF EXECUTION i

k i

EYc e wT FRopt o uT >T of a _

FNP D ET 20 (WPS W :) l 1

bb h.

l

. t

'c:fnpdei30 l

c;LTAPE '

, 'c:MTAPE ' ,' c:NTAPE '

Farley Main Steam Line Break (MSLB) '

' with Accident Initiated I Spike '

l 0, 0, 1, 1, 0 4, 2 RCS '

, 'IntactSG','RuptrdSG',' Core '

6 1.000E+00, 0.000E+00 1.000E+00, 0.000E+00 0.000E+00, 0.000E+00 1.000E+00, 0.000E+00, 0.000E+00 1.000E+00, 0.000E+00, 0.000E+00 1.071E+4, 1.000E+03, 1.000E+03, 4.800E+3 i

' TIME INTERVAL '

,0,0,0,0,2, 0.000E+00, 2.778E-06

' INITIAL FRACTION',0,0,0,0,4, 3.455E+00, 7.250E-01, 1.465E-01, 8.283E+03

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00 l

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00

' ,0,0,0,3,4, 5.000E+02, 0.000E+00, 0.000E+00, 1.000E+00

' TRANSFER CFM

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00 l

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E

' TIME INTERVAL '

,0,0,0,0,2, 2.778E-06, 5.000E-01 I

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00 i

' FILTER EFF

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,3,4, 5.000E+02, 0.000E+00, 0.000E+00, 1.000E+00

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E l

' TIME INTERVAL '

,0,0,0,0,2, 5.000E-01, 1.000E+00

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,3,4, 1.000E+00, 0.000E+00, 0.000E+00, 1.000E+00

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E

' TIME INTERVAL '

,0,0,0,0,2, 1.000E+00, 1.500E+00

' FILTER EFF- '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00

' ,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00

' TRANSFER CFM

' TRANSFER CFM '

,0,0,0,3,4, 1.000E+00, 0.000E+00, 0.000E+00, 1.000E+00

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E

' TIME INTERVAL '

,0,0,0,0,2, 1.500E+00, 2.000E+00

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00

' TRANSFER CFM '

,0,0,0,3,4, 1.000E+00, 0.000E+00, 0.000E+00, 1.000E+00

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00

. . _.. . . . _ . . - . _ . . . _ . ._ . _ _ . _ . _ . _ _. _ _ . . . . .._._.._.__.m s'

s

' DOSE PARAMS ',0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E

'T,IME INTERVAL '

,0,0,0,0,2, 2.000E+00, 8.000E+00 i

' TRANSFER'CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, O.000E+00, O.000E+00

' TRANSFER-CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00 l ' DOSE PARAMS '

,0,0,0,0,5, 0.000E+00, 3.470E-04, 1.100E-04, 3.470E-04, 1.000E

,0,0,0,0,0, 0.000E+00, 0.000E+00, 0.000E+00 l 'END i

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. i 2 3 3 0 0 1 1 WlIOLEBDY SKIN THYROID HALOGENS ELEM. ORG. PART.

I 131 9.963996E-07 2.330000E+01 5.590000E-02 3.070000E-02 1.100000E 06 0.0 0.0 0.0 0.0 0.0 0.0 1 1 0 0 0 0 0 I 132 8.269001E-05 8.380000E+00 3.550000E-01 1.100000E-01 6.300000E 03 I 0.0 0.0 0.0 0.0 0.0 0.0 2 1 0 0 0 0 0 I 133 l 9.219000E-06 3.720000E+01 1 9.110000E-02 8.900000E-02 3.800000E 05 0.0 0.0 0.0 0.0 0.0 0.0 3 1 0 0 0 0 0 I 134 2.228000E-04 5.590000E+00 4.110000E-01 1.420000E-01 1.100000E 03 0.0 0.0 0.0 i 0.0 0.0 0.0 4 1 0 0 0 0 0 I 135 2.864000E-05 2.050000E+01 2.490000E-01 7.860000E-02 3.100000E 04 0.0 0.0 0.0 0.0 0.0 0.0 5 1 0 0 0 0 0 FuPDLI50

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1 1

'1 ENCLOSURE 2 '

1 Results of Calculation based on ICRP-02 l

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CALCULATION FOR THYROID DOSE (REMS) l MULTI NODE CONTAINMENT WITH ESF l START EXCLUSION RADIUS LOW POPULATION ZONE CONTROL ROOM TIME EACH ACCUM. EACH ACCUM. EACH ACCUM.

(HRS) STEP STEP STEP 0.000E+00 1.455E-04 1.455E-04 5.361E-05 5.361E-05 0.000E+00 0.000E+00 2.778E-06 4.741E+00 4.741E+00 1.747E+00 1.747E+00 0.000E+00 0.000E+00 5.000E-01 6.868E+00 1.161E+01 2.530E+00 4.277E+00 0.000E+00 0.000E+00 1.000E+00 1.090E+01 2.251E+01 4.015E+00 8.292E+00 0.000E+00 0.000E+00 1.500E+00 1.490E+01 3.740E+01 5.488E+00 1.378E+01 0.000E+00 0.000E+00 2.000E+00 0.000E+00 3.740E+01 6.596E+01 7.974E+01 0.000E+00 0.000E+00 TOTAL 3.740E+01 TOTAL 7.974E+01 TOTAL 0.000E+00 1 NO MORE CASES END OF EXECUTION g yc i a pi f"4 0.1 O ApuT CS FvP b E r cm ( Tr ap o ?_ B c Fr)

FnP Ms@ A iN 2 (flo7 PinRT OF CAUuLATiw S M - ?G - Ilo o - 0 01) l i

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'c:LTAPE '

, 'c:MTAPE c:NTAPE '

i Farley Main Steam Line Break (MSLB) '

]

with Accident Initiated I Spike 0, 0, 1, 1, 0 4, 2 RCS '

, 'IntactSG','RuptrdSG',' Core '

6 j 1.000E+00, 0.000E+00 1.000E+00, 0.000E+00 0.000E+00, 0.000E+00  !

1.000E+00, 0.000E+00, 0.000E+00 l 1.000E+00, 0.000E+00, 0.000E+00 d 1.071E+4, 1.000E+03, 1.000E+03, 4.800E+3

' TIME INTERVAL '

,0,0,0,0,2, 0.000E+00, 2.778E-06

' INITIAL FRACTION',0,0,0,0,4, 3.455E+00, 7.250E-01, 1.465E-01, 8.283E+03

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00 l

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00 l

' TRANSFER CFM ' ,0,0,0,2,4, 5.000E+01,-0.000E+00, 1.000E+00, 0.000E+00 l

' TRANSFER CFM '

,0,0,0,3,4, 5.000E+02, 0.000E+00, 0.000E+00, 1.000E+00 )

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E l

' TIME INTERVAL '

,0,0,0,0,2, 2.778E-06, 5.000E-01  !

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00 )

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00 l

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00 l

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00  !

' TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00 j

' TRANSFER CFM '

,0,0,0,3,4, 5.000E+02, 0.000E+00, 0.000E+00, 1.000E+00 1

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00 )

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E l

' TIME INTERVAL '

,0,0,0,0,2, 5.000E-01, 1.000E+00

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00 l

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00 3

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00 i

' TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00 l

' TRANSFER CFM '

,0,0,0,3,4, 1.000E+00, 0.000E+00, 0.000E+00, 1.000E+00

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00 l

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E  !

' TIME INTERVAL '

,0,0,0,0,2, 1.000E+00, 1.500E+00 l

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00  ;

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00  ;

' ,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00

' FILTER EFF i

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00 j

TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00 i

' TRANSFER CFM '

,0,0,0,3,4, 1.000E+00, 0.000E+00, 0.000E+00, 1.000E+00  ;

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00

' DOSE PARAMS '

,0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E j

' TIME INTERVAL '

,0,0,0,0,2, 1.500E+00, 2.000E+00 j

' FILTER EFF '

,1,1,0,1,3, 0.000E+00, 0.000E+00, 0.000E+00 1

' FILTER EFF '

,1,1,0,2,3, 0.900E+02, 0.000E+00, 0.000E+00 l

' FILTER EFF '

,1,1,0,3,3, 0.000E+00, 0.000E+00, 0.000E+00 i

' TRANSFER CFM '

,0,0,0,1,4, 2.700E+00, 1.000E+00, 0.000E+00, 0.000E+00 ,

' TRANSFER CFM '

,0,0,0,2,4, 5.000E+01, 0.000E+00, 1.000E+00, 0.000E+00 l

' TRANSFER CFM '

,0,0,0,3,4, 1.000E+00, 0.000E+00, 0.000E+00, 1.000E+00

' TRANSFER CFM '

,0,0,0,4,4, 0.000E+00, 1.000E+00, 0.000E+00, 0.000E+00 l

l 1

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

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

' . .* g... .

l ..'.

! ' DOSE PARAMS ' 0,0,0,0,5, 7.600E-04, 3.470E-04, 2.800E-04, 3.470E-04, 1.000E l ' TIME INTERVAL

, 0,0,0,0,2,-.2.000E+00,-8.000E+00 l TRANSFER CFM

, 0,0,0,1,4, 2.700E+00,.1.000E+00, 0.000E+00, 0.000E+00

.' 0,0,0,4,4, 0.000E+00, 1.000E+00, l ' TRANSFER CFM , 0.000E+00, 0.000E+00 l ' DOSE PARAMS '

, 0,0,0,0,5, 0.000E+00,-3.470E-04, 1.100E-04, 3.470E-04,=1.000E g 'END '

, 0,0,0,0,0, O.000E+00, O.000E+00, O.000E+00 l

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3 1 1 i WHOLEBDY SKIN THYROID l HALOGENS ELEM. ORG. PART. l I 131 '

9.963996E-07 1.989000E+01 1 5.590000E-02 3.070000E-02 1.480000E 06 0.0 0.0 0.0 0.0 0.0 0.0 1 1 0 0 0 0 0 l' I 132 8.269001E-05 7.160000E+00 l 3.550000E-01 1.100000E-01 5.350000E 04 l 0.0 0.0 0.0 O.0 0.0 0.0 l 2 1 0 0 0 0 0 I 133 9.219000E-06 3.183000E+01 l 9.110000E-02 8.900000E-02 3.970000E 05 l

, 0.0 0.0 0.0 0.0 0.0 0.0 3 1 0 0 0 0 0 I 134 2.228000E-04 4.770000E+00 -

4.110000E-01 1.420000E-01 2.537000E 04 0.0 0.0 0.0 0.0 0.0 0.0 4 1 0 0 0 0 0 I 135 i 2.864000E-05 1.751000E+01 2.490000E-01 7.860000E-02 1.2350000E 05 l 0.0 0.0 0.0 0.0 0.0 0.0 5 1 0 0 0 0 0 I I

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