PY-CEI-NRR-2076, Rev 2 to Nonproprietary Version of Controlled Copy of Dose Calculation Data Base for Application of Revised DBA Source Term to CEI Pnpp

Rev 2 to Nonproprietary Version of Controlled Copy of Dose Calculation Data Base for Application of Revised DBA Source Term to CEI Pnpp

ML20117E825
Person / Time
Site:	Perry
Issue date:	06/14/1996
From:	POLESTAR APPLIED TECHNOLOGY, INC.
To:
Shared Package
ML19311C241	List: ML20117E782 ML20117E789 ML20117E810 PY-CEI-NRR-2076, Rev 2 to Nonproprietary Version of Controlled Copy of Dose Calculation Data Base for Application of Revised DBA Source Term to CEI Pnpp
References
FACA, PSAT-04202U.03, PSAT-04202U.03-R02, PSAT-4202U.3, PSAT-4202U.3-R2, PY-CEI-NRR-2076, NUDOCS 9609030101
Download: ML20117E825 (217)

Text

,

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• ** PY.CEtNRR.2076L 1 Page1of217 POLESTAR PSur 04202u.03 NON-PROPRIETARY Page i ori4 ,

Revision: 2 l I

DOSE CALCULATION DATA BASE FOR APPLICATION OF TIIE REVISED DBA SOURCE TEILM TO TIIE CRI PERRY NUCLEAR POWER PLANT CONTROLLED COPY PLEASE CIRCLEIN RED UPON RECEIPT 1

l

' l PROJECT MGR REVIEWER CEI TECH CONT Print /Sien ' Dals Print /Sinn Dalg Print /Sinn Dals REV: 0 Jama Metcalf Dave leaver Jolm Spano

/s 3/27/96 /s 3/27/96 /s 4/6/96 Reason for Revision: InitialIssue REV: 1 James Metcalf Jun Li ~ John Spano

/s 4/11/96 k 4/11/96 /s 4/11/96 Reasons for Revision: (1) Provide references for items 3.8,3.9,3.10,3.15,3.20, and 3.21; (2) provide final data and referenocs for Items 4.3 and 4.4; (3) provide value and reference for Itern 4.5; (4) provide final data and references for Items 4.6 and 4.7; (5) add Item 4.8; (6) add note to Item 6.6; (7) provide references for items 7.4,7.5, and 7.6; (8) provide references for items 8.1, 8.2, and 8.5; and (9) add Item 9.5 REV: 2 James Metcalf Dave leaver Jolm Spano

/s 6/14/96 /s 6/14/96 /s 6/14/96 Reasons for Revision: (1) Remove " Genetic Note" on cover page, (2) pmvide a thyroid DCF for Cs-137; (3) increase items 3.11 and 3.12 by 50%; (4) make items 3.13/3.14 consistent with items 3.11/3.12; (5) increase item 3.17 by 50%; (6) provide item 4.5;(7) revise items 4.6 and 4.7 to be consistent with Rev I of 04202H.08; (8) pmvide reference for hem 6.5; (9) provide value and reference for item 6.7; (10) change reference for Item 7.5 9609030101 960827 PDR ADOCK 05000440 p PDR

I l armes U.de s2 rrorn J. anacast Pasessar Appsed TecW G ea soun.cos2 Attachment 6 l

s PY-CELNRR.2076L Page 2 cf 217 PSAT 04202U.03 Page 2 of14 Revision: 2

1. Radionnelide Data (References - Mass and Ci Inventories: DRF A41-00054; Decay Constants i

and DCFs: Library Files from LOCADOSE as Documented in Controlled Copy 00126D-1 of LOCADOSE NE319 Provided to Polcstar by Bechtel at j Request ofCEI) 1.1 Core Power - Radiological Calculations - 3758 Mwit) (Rcren nee CEI Cale 3.2.6.4, Rev 0, Pg 3A of33) 1.2 Core loventory @ t'0 (per sec) (10 2 Rem-m'/Ci-sec) {l0* Rem /Ci)

Nuclids 10'Ci DKlambda WB DCF Skin DCF "Divroid DCF K -83m 1.214 1.05E-04 0.00149 0.0136 0.0 Kr-85m 2.519 4.30E 05 2.6 8.31 0.0 Kr-85 0.160 2.05E 09 0.0355 5.01 0.0 Kr-87 4.788 1.51E 04 14.2 52.3 0.0 Kr-88 6.509 6.73E 05 35.8 54.9 0.0 Kr-89 8.159 3.63E-03 32.3 77.1 0.0 Xe-131m 0.115 6.82E 07 0.136 1.78 0.0 Xc-133m 0.648 3.66E 06 0.472 3.84 0.0 Xc-133 19.84 1.53E-06 0.558 1.84 0.0 Xe-135m 4.107 7.38E 04 6.82 11.3 0.0 Xe 135 7.170 2.11E45 3.% 11.5 0.0 I Xe-137 18.01 3.02E-03 3.03 50.1 0.0 Xe-138 16.82 8.15E-04 19.9 40.9 0.0 1-131 10.23 9.98E 07 6.06 11.2 100.0 1-132 14.74 8.43E 05 37.7 61.8 0.59 1-133 20.65 9.21E 06 9.73 22.I 18.0 l-134 22.63 2.20E 04 l 43.8 73.2 0.1 1-135 19.35 2.91E 05 26.4 43 4 30 Cs-134 3.029 1.07E-08 25.4 37.1 4.0 Cs-137 1.745 7.28E 10 0.0 2.8 2.9 Ba-137m Cs-137 daughter 4.53E43 9.70 ,

14.6 0.0 Te-132 14.49 2.46E 06 3.46 j

5.04 21.0 '

l.3 Core Inventory by Mass

• Based on Item 1.1 power + 105% since low power estimate (and low atimate ofmass) is conservative for transport Elcunent g/Mw(t) grams

• i I

mm=========_.m=====

Cs 1.33E402 4.74E 405 1 1.05E+01 3.76E404 Te 2.13E401 7.62E4 04 na 6.58E401 2.35E405 l

Sr 4.15E401 1.49E405 Ce 1.22E+02 4.36E+05

_ . . _ . _ _ _ _ . . __. _ _ _ .._ m.

suas 174e.ss resen J. es scar. Pasesser Appbad TechnetaerG ras sow 21. sos 2 E -2076L Page 3 of 217 PSAT 04202U.03 Page 3 of14 Revision: 2 La 5.56E+01 1.99E+05 Ru 1.06E+02 3.78E+05 Sn 3.93E400 1.41EiO4

, Ag 3.13E400 1.12EiO4 A6 8.87E-03 3.18E401 Be 6.80E-06 2.43E 02 d

Hr 9.79E-01 3.50E403 C 1.20E-06 4.28E-03 Cd 4.90E FOO 1.75E404 Dy 6.00E-02 2.15E+02 Er 2.31E-03 8.28E+00 Eu 7.92E+00 2.84E+04 Ga 1.29E 06 4.61E-03 Gd 3.71E+00 1.33E+04 Ge 2.%E-02 1.06E4 02 i 11 2.46E-03 8.81E+00 llo 6.17E-03 2.21E401 In 8.03E-02 2.88E+02 Kr 1.71E401 6.llE404 Li 9.30E-06 3.33E-02 Mo 1.48E402 5.30E405

. Nb 1.14E+00 4.09E+ 03 Nd 1.72E+02 6.17E+05 Pd 5.63E+01 2.01E405 -

Pm 5.09E400 1.82E+04 Pr 4.99E+01 1.79E405 Rb 1.59E401 5.68E+04 Rh 1.71E401 6.13E404 Sb 1.31E+00 4.68E+03

, Se 2.58E+00 9.23E+03 i Sm 3.43E+01 1.23E405 "It 1.10E-01 3.95E402 - )

Tc 3.48E401 1.25EiOS Tm 2.2SE-06 8.06E-03 Xe 2.31E+02 8.26E+05 Y 2.17E+01 7.78E+ 04 Yb 4.70E-07 1.68E-03 Zn 2.70E-04 9.65E-01 }

Zr- 1.63E402 5.82E t05

2. Source Terms (Reference Calc PSAT 04212II.01, Rev 0) 2.1 Fraction ofcore inventory,0 30 seconds: no releases i 4

4

SN4 Jet 17-50.37

. Attachment 6 Frern J. toescalt, Petestar Apenhed Tectwentogy G Fan s0M31.aos2 py.CEl/NRR.2076L Page 4 of 217 PSAT 04202U.03 Page 4 of14 Revision: 2 2.2 Fraction of core inventory,30 - 1830 seconds: Gases -

Xc, Kr - 2.8E-5 /sec (0.05 total)

Elemental 1 - 1.3E-6 /sec (2.4E-3 total)

Organic 1 - 4.2E-8 /sec (7.5E-5 total)

Aerosols -

lodine - 2.6E-5 /sec (0.0475 total)

Cesium - 2.8E-5 /sec (0.051otal) 2.3 Fraction ofcore inventory, 1830 - 7230 seconds: Gases - Xe, Kr - 1.8E-4 /sec (0.95 total)

Elemental 1 - 2.2E 6 /sec (1.2E-2 total)

Organic I - 6.9E-8 /sec (3.8E-4 total)

Aerosols -

lodine - 4.4E-5 /sec (0.2375 total)

Cesium - 3.7E-5 /sec (0.2 total)

Tellurium - 9.3E-6 /sec(0.05 total)

3. Volumes and Voluinetric Flowrates 3.1 Volume ofDrywell- 276500 ft' (Reference CEI Calc 3.2.6.4, Rev 0, Pg 3 A of33) 3.2 Volume of Wetwelhwer Containment (Unsprayed)- 684226 ft' (Reference CEI Calc 3.2.6.4, Rev 0, Pg 3A of 33) 3.3 Volume ofUpperCetaiament(Sprayed)-481174 ft*

(Reference CEI Calc 3.2.6.4, Rev 0, Pg 3A of33)  !

3.4 Volume ofSuppression Pool - 114379 ft' l (Reference Sht 1, Design Change Control for C1-ECA-036, Rev 0) 3.5 Volume ofUpper Pool Dump - 32573 ft' (Reference Table 4-1, NEDC-31940,  !

March 1991) 3.6 Volume ofAnnulus - 1.96ES ft' (Reference CEI Cale 3.2.6.4, Rev 0, Pg 3A of 33, including 50% decrease to account forincomplete mixing) 3.7 Volume ofControl Room (CR) - 3.44E5 ft' (Reference CEI Calc C1-M26-01, Rev

1. Pg 3a) 3.8 Volume ofOne Main Steamline between MSIVs - 146 ft' (Reference Calo PSAT 0420211.08, Rev 0) 3.9 Volumetric Flowrate, Drywell to Wetwethwer Cont:

(Referenec Calo PSAT 04212H.02,

^

l aM4m 17:51:2s Attachment 6 l rrom J. aseecar. Pdesser wa TechnesoerO Fan soM31 ses2

' PY.CEl/NRR-2076L l

i Page 5 of 217 PSAT 04202U.03 Pag-5of14 Revision: 2 Rev 0 with conversion from cfs to cfm)

From t=0 to t=1830 seconds -0 From t=1830 to t=7230 seconds - 6180 cfm From t=7230 to t=7333 seconds - 0 From t=7333 to t-7344 seconds - 5.4E4 cfm From t=7344 to t=7356 seconds - 1.3E5 cfm From t=7356 to t=7369 seconds - 1.8E5 cfm From t =7369 to t =7383 seconds - 2. l ES ofm From t=7383 to t=7397 seconds - 2.3E5 cfm From t=7397 to t=7411 seconds - 2.5E5 cfm From t=7411 to t=7425 seconds - 2.6E5 cfm From t=7425 to t=7439 seconds - 2.1 E5 cfm From t=7439 to t=7451 seconds - 1.6ES cfm From t=7451 to t=7463 seconds - 1.0E5 cfm From t=7463 to t=7474 seconds - 5.5E4 cfm From t-7474 to t=7484 seconds - 1.2E4 cfm From t=7484 scoonds to end ofproblem - 500 cfm 3.10 Volumetric Flowrate, Wetwell/ lower Cont to Drywell: (Reference Calo PSAT 0421211.02, Rev 0 with conversion from efs to cfm)

From t=0 to t=7484 seconds - 0 From t=7484 scoonds to end ofproblem - 500 cfm 3.11 Volumetric Flowrate, Upper Cont to Environment -

0.67 cfm (Initial) 0.0675 cSn (After 40 seconds)

(Reference Perry Technical Specifications Section 3.6.1.2,0.2tuday x Item 3.3/24 hours / day for first 40 seconds, then from CEI Calo 3.2.6.4, Rev 0, as modified by memo Ortalan to Bordley dated 5/20/96,10.08% of initial value bypasses annulus after 40 seconds) 3.12 Volumetric Flowrate, lower Cont

• to Environment -

1.34 cfm(Initial)

(* includes Drywell volume) 0.135 cfm (Aller 40 seconds)

(Reference Peny Technical Specifications, Section 3.6.1.2,0.2tuday x Item 3.2/24 hours / day for fust 40 seconds, tien from CEI Calo 3.2.6.4, Rev 0, as modified by memo Ortalan to Bordley dated 5/20/96,10.08% of

SM448 9F.s2:17 Frern J. assecaIL Passessa aP%esl Tectorsalmer Q Fem a0M31.SEs2 PY-C I/h -2076L Page 6 of 217 [

i PSAT 04202U.03 Page 6 of14 Revision: 2 initial value bypasses annulus mAer 40 seconds) 3.13 Volumatric Flomate, Upper Cors to Annulus - 0 (initial) 0.603 cfm (AAcr 40 seconds) j i

(Same lasis as item 3.11) i 3.14 Volumetric Flowate, Lower Cont

• to Annulus - 0 (Initial)

(* includes Drywell volume) {

1.205 cfm (AAcr 40 seconds)

(Same basis as item 3.12) 3.15 Volumetric Mixing Flowrate between Upper and lower Coat - 71400 cfm (Reference Calo PSAT 0421211.06, Rev 0) 3.16 Volumetric Flowrate, Annulus to Environment (Filtered)- 2000 ofm (Reference CEI Calc 3.2.6.4, Rev 0 Pg 10 of 33) 3.17 Volumatric Flowrate, ESF leakage:

From t=0.175 to t=720 hours - 15 sph (Reference 10 gph from CEI Calc 3.2.6.4, Rev

0. Pg 9 of33, except startisq; at time ofspray initiation, see item 9.1. Per Scope ofWork attached to PSAT 04202U.01, this value has been increased - see CEI memo Ortalan to Bordley dated 5/20/96 for 15 gph)

From t=24 to t=24.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> - 3000 gph additional (Reference SRP Section 15.6.5, Rev 2, as 50 i

spm) 3.18 Volumetric Flowrate, Environment to CR (Unfiltered).1375 cfm I (Reference CEI Calc 3.2.6.5, Rev 0, Pg 20 of 20, maximum flow of 1375 cfm for immediate isolation case) 3.19 Volumetric Flowrate, CR Recirculation (Filtered)- 2.7E4 cfm i

(Reference Perry Tedmical Specifications Section 3/4.7.2)

andes 17 53 se prom J. esences. Pusesser apped Tecmasser G Faa sos-431.aes:

, $ N @ .2076L Page 7 ef 217 l

PSAT 04202U.03 Page 7 of14 Revision: 2  !

3.20 Volumetric Flowrate, Drywell to All Main Steamlines (Total Imkage):

298 cfh from t=0 to t=7484 scoonds 247 ofh from t=7484 seconds to end (Reference Calc PS AT 0420211.04, Rev 0) 3.21 Volmnetric Flowrate (Maximum), One Main Steamline to Emironment - 191 cfh (Reference Cale PSAT04202H.08 Rev 0) 3.22 Combined MS!V Tested leakrutes - 250 acfh (To be established by Perry Revised Accident Source Term Project - no reference required) 3.23 Por Line MSIV Tested Leakrate - 100 scGi (Same as 3.22) 3.24 Core Spray - One Pump Flowrate at Low RCS Pressure - 7800 gpm (Reference Fax Spano to Metcalf dated I/9/96) 3.25 RHR Cont Spray Mode - One Pump- 5250 gpm (Reference Fax Spano to Metcalfdated I/9/96) _

3.2611, Mixing Fans, One Fan - 500 ofm or 3E4 ofb (Reference CEI Calc 3.2.6.4, Rev 0, Pg 9 of 33)

4. Futes Emelencies, Removal Lambdas, and Decontamination Factors 4.1 Filter Efficiency- Annulus Exhaust Gas Treatment System (AEGTS): l i

(Reference CEI Calc 3.2.6.4, Rev 0, Pg 10 of33, assuming other particulates behave like paniculate iodine) e For Particulate lodine, Cesium (including Be-137m), and Tellurium - 99%

e For Elemental and Organic Iodine and Noble Gasses - 0%

4.2 Filter EfIleiency - CR Rectreulation: (Reference Gilbert & Associates, Inc. Bill of Material for HVAC, Perry Nuclear Power Plant Units I and 2, Sht 170, Issue 2, 4/6/77 and RG 1.52, Rev 2, i assuming other particulates behave like particulate iodine. Per Soope of Work attached to PSAT  ;

04202U.01, CR recirculation delayed - assumed to start at stan offuel release.)

From t-0 to t= I830 i.econds; e For hxline, Cesium (including Ba-137m), and Tellurium - 0%

e For Noble Gasses-0% ,

From :=1830 to t-end ofproblem:

e For Iodine, Cesium (including Ba-137m), and Tellurium - 95%

e For Noble Gasses - 0%

em u.53 se Freen J. naeecast Pusessar AW TecW G Fm seM31 ses2 PY-CEIERR-2076L Page 8 of 217 1

l PSAT 04202U.03 Page 8 of14 l Revision: 2 4.3 Removal (SJ nensation) Lambdas in Drywell: (Reference Cale PSAT 0420211.04, Rev 0 -

l

! values are medians over cited intervals)

For Particulate and Elemental lodine, Cesium (including Da 137m), and Tellurium:

e From t=0 to t=30 seconds - 0 ' hour e From t=30 to t=66 scoonds - 0.084/ hour e From t=66 to t=1867 seconds - 0.184/ hour e

From t= 1867 to t=3203 seconds - 0.25/ hour e

From t=3203 to t=4384 sooonds - 0.35Mour e From t-4384 to t=5862 scoonds - 0.45/ hour From t-5862 to t-7333 seconds - 0.54 tour e

From t=7333 to t=7484 seconds - 0.58/ hour e

From t=7484 to t=9254 seconds - 0.54 tour e

From t=9254 to t=15881 seconds - 0.45/ hour e

From t=15881 to t=30669 scoonds - 0.35/ hour e

From t=30669 to t=51639 scoonds - 0.25/ hour e

From t=51639 to t=100000 seconds - 0.16/ hour e

From t=100000 seconds to end - 0/ hour For Organic lodine and Noble Gasses e From t=0 to end - 0/ hour 4.4 Removal (Spray) Lambdas in Upper Containment (Reference Calc PSAT 04202H.05, Rev 0 - values are end points for cited intervals - ,

conservative since values are generally decreasing - see Item 9.1 for explanation of initial time shift,630 to 690 seconds and Itcan 9.5 for spray dtiration)

For Particulate and Elemental lodine, Cesium (including Da 137m) and Tellurium:

e From t=0 to t=690 seconds - 0/ hour e

From t=690 to t=728 seconds - 8.13/ hour i e

From t=728 to t=924 seconds - 4.32/ hour e

e From t=924 to t=1317 seconds - 3.02/ hour e From t=1317 to t=1710 seconds - 2.52&our e From t=1710 to t=1897 seconds - 14.3/ hour e From t= 1897 to t=2070 seconds - 8.76/ hour e From t=2070 to t=2529 seconds - 5.07/ hour e From t=2529 to t=314I seconds - 3.84/ hour From t=3141 to t=4030 seconds - 3.25/ hour e

From t~4030 to t=5339 seconds - 3.22/ hour e

From t=5339 to t=6702 seconds - 330/ hour e

From t=6702 to t=7377 seconds - 6.55/ hour e

e From t=7377 to t=7760 seconds - 330/ hour From t=7760 to t=11724 seconds - 1.19/ hour e

From t= 11724 to t= 17469 seconds - 0.50/ hour e

e From t=17469 to t=30823 seconds - 0.27/ hour e From t=30823 to t-40039 seconds - 0.23/ hour From t=40039 to t=69513 seconds - 0.20/ hour

Attachment b snMes 1F.s4.57 Prern J. Inescaer. Pasesser ApAnd Tectwissner C Fe soustess2 PY-CEl/NRR-2076L Page 9 of 217 PSAT 04202U.03 Page 9 of14  !

Revision: 2 l e From t=69513 to t=87090 seconds - 0.19/ hour e From t=87090 scoonds to end - 0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> For Organic lodine and Noble Gasses e From t=0 to end - Olhour 4.5 Minimum DF for Elemeatal Iodine in Contaimpent - 70000 (Reference Cale PSAT 0421211.03, Rev 0) 4.6 I'ilter Elliciency for Flowpath From Drywell through Main Steamlines, One Inboard MSIV Failed (Reference Cales PSAT 0420211.08, Rev 1 and .09. Rev o) e For Partimlate lodine, Cesium (including Ba-137m), and Tellurium

- 76.7% from t = 0 to t = 1200 scoonds

- 94.5% from t = 1200 to t = 1800 seconds

- 96.9% from t = 1800 to t = 5400 seconds

- 97.4% from t = 5400 to t = 10800 seconds

- 97.8% from t = 10800 to 1 = 18000 seconds

- 98.0% from t = 18000 to t = 25200 seconds

- 97.6% from t = 25230 to t = 32400 seconds

- 97.1% from t = 32400 to t = 39600 scoonds

- 94.4% from t = 3%00 seconds to end e For ElementalIodine - 50%

e For OrBanic lodine and Noble Gasses - 0*A 4.7 Filter Efficiency for Flowpath From Drywell thrugh Main Steamlines, All 'Ihird Isolation Valves Failed 1 I

(Reference Calos PSAT 0420211.08, Rev 1 and .09, Rev 0) e i For Particulate lodine, Cesium (including Ba-137m), and Tellurium

- 84.2% from i = 0 to t = 1800 scoonds

- 91.2% from t = 1800 to t = 5400 seconds

- 93.0% from t = 5400 to 1 = 10800 scoonds

- 93.7% from t = 10800 to 1 = 18000 seconds

- 92.5*4 from t = 18000 to t = 25200 seconds

- 90.4% from t = 25200 to 1 = 32400 seconds

- 88.0% from t = 32400 to t = 39600 seconds

- 68.0% from t = 39600 seconds to end e For ElementalIodine - 50%

e For Organie lodine and Noble Gasses - 0%

4.8 Release Fraction of Radioiodine in ESF Leakage - 0.1 (Reference SRP 15.6.5, Rev 2)

5. X/Q Values, Bavathing Rates, and Occupancy Factors

I mwumem o sness # ss se reern J. essecas. Polemar apahed Tocevimmer Q Fan sowM.ses2 PY.CEl/NRR-2076L Page 10 0f 217 l

l l

l PSAT 04202U.03 Page 10 of 14 Revision: 2 5.1 X/Q (sec/m'): EAM LPZ CE From t=0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4.3E-4 4.8E 5 7E-5 From t=2 to t=8 hours 4.8E-5 7E-5 From t=8 to t=24 hours 3.3E-5 5.6E 5 From t=24 to t=96 hours 1.4E 5 4.3E 5 t From t=96 to t=720 hours 4.1 E-6 1.5E 5  !

(Reformoc CEI Calo 3.2.6.4, Rev 0, Pg 10 of 33 for EAH and LP7, and Perry Design input  !

Record 3.2.6.5, Rev 1, Anachmers I for CR) l 5.2 Brcathing rates: (Refercmcc CEI Calc 3.2.6.4, Rev 0. Pg 10 of 33) 0 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> - 3.47E-4 m'/sec (used in CR for 0 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />) i 8 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> - 1.75E-4 m'/soe  !

24 - 720 hotus - 2.32E-4 m*/sce I 5.3 CR Occupancy Factors: (Reference SRP Section 6.4, Rev 2)

From t=0 to t=1 day - 1.0 From t=1 to t=4 days - 0.6 ,

i From t=4 to t=30 days - 0.4 1

6. Clwmistry Data 6.1 laitial Pool pH - 6.0 (Average Based on Reference RPI-I103. Rev 1 Data) 6.2 Mass of Chlorido-Beanng Cable Insulation in Containment (Refcrmoc Memo "E" SO-16662, Maloney to Spano dated 10/27/95)

• Hypalon - 2.9E4 lbm o PVC -negligible .

6.3 "Ihickness of Hypalon Jacket - 45 mils (Refermoe Memo "E" SG-16662, Maloney to Spano dated 10/27/95 and Rockbestos letter, Konmk to Zarca dated 10/10/95) 6.4 Mass ofSodium Pentaborate Availabic for Injection - $236 lbm (Reference Perry Tech Specs Section 4.1.5) 6.5 Formula of Sodium Pentaborate - Na20-5Bfh-10HfP

• Natural boron -

(Reference CEI telecon memo, J. Spano, J. Ratchen, D.

leaver, dated 4/19/96) 6.6 Water Volume in Containment (including RCS)- 1.7E5 fP*

' Note that this does not include all possible in-containment water which is conservative for iodine 1

i b

r g,ges num Attachment b j From J. assecadr. Pasesser AW TectmasserG Fan soust eas2 PY-CEl/NRR-2076L Page i1 of 217 PSAT 04202U.03 Page 1 I of14 Revision: 2 l

concentration effect; pH not greatly seraitive (Reference Fax Spano to Metcalfdated 3/22,2896) 1 6.7 Mass ofItcen 6.2 Ilypalon in Dr3well - 3750 lbrn (Reference CEI telecon memo, J. Spano, J.

Maloney, dated 3/1266) 6.8 Referenac Cable OD (Approx Average for Chloride-Bearing)- 2.26 cm (Reference J. Wing. " Post-Accident Gas Generation from Radiolysis of Organic Materials", NUREG-1081, Sepicmber 1984)

7. Fission Predoct Transport Data 7.1 Approximate Containment Dimensions:

• Radius ofDrywell Cyhnder - 36.5 feet (Reference Containment Definition,762E576, Rev 5)

• IIcight of Drywell Cyhnder (Above Support Mat) 76.5 feet

• !!eight of Drywell IIcad (Above Drywell Concrete)- 16.5 feet

• Radius ofDrywellIIcad- 16 feet e Ileight of Containment Above Suppression Pool Surface - 154 feet )

e Radius of Containment Cylinder - 60 feet

• Thickness ofDrywell Wall- 5 feet e

IIcight of Containment Cylinder Above Suppression Pool Surface - 124 feet ,

• i Height ofContainment Cylinder Above Operating Floor - 37.5 feet 7.2 Sedimentation Area in Drywell- 8712 ft2 i

(Reference Fax Spano to Leaver dated 11/1/95 giving date that totals to 4527 A**. This can be added to simple cross-section ofdrywell =

n(36.5 ft)2 = 4185 ft2to obtain the given value.)

i

• Note that addition error in fax would give value 0.8% higher, but I error is small and consenative.

)

7.3 Sedimentation Area in Wetwell/lewer Containment - 5899 A' (Simple cross-section ofcontainment outaide drywell wall = n ((60 ft)2

-(36.5 + 5 ft)'] = $899 ft')

7.4 Vessel ID - 238" (Reference Fax Spano to Metcalfdated 1/29/96) 7.5 Steamline ID - 23.36" (Reference Gilbert Cale INI1G38A, Rev 6, Page 18.1) 7.6 length of Steamline, Inboard MSIV to Outboard MSIV - 49' (Reference Calc 04202}I.08, Rev0) 7.7 length of Stearnlinc, Outboard MSIV to 3rd Isolation Valve - 29' (Reference Calc 04202H.08, i

i

f anses gr.st:as F,orn J. assecaer. Pusesser amshed Techristaar O Fan sown.cos2 Ar.achir.cnt t>

PY-CEl/NRR-2076L l Page 12 of 217 l

l PSAT 04202U.03 Page 12 ofI4 Revision: 2 Rev 0) 7.8 Spray System Parameters (Reference Fax Ortalan to Leaver dated 6/21/95) l

• Mean Spray Falllicight - 53.2'

• r, for drop size distribution - 0.025 cm

• a for drop size distribution - 2.9

8. Therinal-Ilydruidie Data 8.1 Contamment Conditions aRer Blowdown, but Prior to End ofDebris Quench (Up to 7484 seconds) (Reference Cale PSAT 04212H.02, Rev 0)

Marinmm Caroniamern Conditions:

Drywell Pressure Approx 0 to 630 scoonds (sprays on at 630 sec) 32 psia 630 to 1830 sec (and ofgap)- uniform decrease from 32 to 20 psia 1830 to 7333 see (start ofsteam from reflood) - 20 psia 7333 to 7484 see (cud ofsteam from rellood)- 32 psia DrywellTemperature: 330 F -

Containment Pressure: Approx 0 to 630 scoonds (sprays on at 630 sec) uniform increase from 20 to 24 psia 630 to 1830 seo (and of gap)- uniforrn decrease from 24 to 20 psia 1830 to 7333 see (start ofsteam from reflood) - 20 psia 7333 to 7484 sec (end of steam from reflood)- 24 psia Containment Temp: Approx 0 to 630 scoonds (sprays on)- uniform increase from I45 F to 160 F 630 to 1830 sec (end of gap)- unifonn decrease from 160 F to I40 F 1830 to 7333 see (start ofsteam from reflood)- 140 F 7333 see to 7484 sec (cod ofsteam from reflood)- 185 F Minimurn Cornainment Conditions:

\

sness gr.se.22 atwnment o Frern J. assacesr. Pesesser ammed Technessist O Fan sous1.ses2 PY.CELHRR.2076L Page 13 of 217 i

PSAT 042020.03 PaBeI3ofI4 Revision: 2 Drywell and Contauunent Pressure: 1 psi 8 (15.7 psia)

Drywell Temperature: 215 F Containment Temp: 100 F 8.2 Containment Conditions aAcr Dehris Quench (Reference Cale PSAT 04212il.02, Rev 0)  !

Mavimurn Containment Conditions:

Drywell Pressure: 7484 to 86400 sec - 30 psia 1 to 12 days - uniform decrease from 30 to 20 psia 12 to 30 days - unifonn decrease from 20 psia to 18 psia Drywell Temperature: 7484 to 10800 sec -330 F 10800 to 21600 see-320 F 21600 to 86400 see - 250 F 1 to 12 days - uniform decrease from 250 to 150 F 1 12 to 30 days -unifonn decrease from 150 to 130 F Containment Pressure: 7484 to 6ES sec 24 psia t

6ES see to 30 days - uniform Ar- from 24 to 19 psia Containment Temp: 7484 to 86400 see - 185 F 1 to 30 days - uniform decrease to 115 F Minimum Containment Condhions:

Drywell and Contamment Pressure: 1 psig (15.7 psia)

Drywell and Contamment Temperature: 100 F 8.3 Core Power - Thermal-Ilydraulic Calculations - 3729 Mw(t) (Reference Table 4-1, NEDC. 31940, Ma ch 1991) 8.4 Reference Pressure for Detennmation ofInitial Steamline Temgx:rature* - 1060 psia 1

T

, asems 17.se s7 Frern J. sesecalf. Petemer amphed Technetegy G Fem s0M 31 ass 2 Attachment 6 PY-CELHRR-2076L Page 14 of 217 PSAT 04202U.03 Page 14 ofI4 Revision: 2

(' saturation temperature at the pressure specified)

(Reference Table 4-1, NEDC-31940, Mardi 1991) 8.5 Maximum Suppression Pool Temperature 212 F (Reference Calc PSAT 042121LO2, Rev 0) l t

8.6 Minimum ECCS Injection Temperature Post-Blowdown - 100 F (Reference Figure 5-6, NEDC-31940, March 1991 which shows approx 10 F pool temperature increase during first 10 scoonds of l

blowdown and Figure 5-9, same reference, which shows pool temperature in excess of 105 F at same 10 seconds after blowdown and increaamg thercaAcr. ECCS manumed to start at t=7230 scoonds.)

! 8.7 Area of Equipment Transfer Opemng in Refueling Floor - 340 ft2 l

t (Reference 207" x 16%" Opening on Dwg D511025, Rev D)

9. System-Rehnted Data (Other than Volumetde Flows) 9.1 Spray Initiation Time - 10 minutes aAcr low vessel level if 9 psig reached in containment

• i

' (Reference Ieop Diagram 808-309, Sht 5, Rev D)

'Prelimmary data of 10 minutes 9 psig used in thermal-bydraulic and removal lambda calculations - no diange required since outputs of thennal-hydraulic calculation (for donc calculatons ofrecord) would be unchanged and outputs ofremoval lambda calculation are conservative for donc calculatons as long as 11 minutes (4 30 scoonds for reactor blowdown / loss oflevel) is used in the dose calculations -

see item 4.4 9.2 'niird Steamline Isolation Valve Closure Time - Manual action at t=20 min (Reference as Aooeptable Asssumption- Fax Spano to Macalfdated 3/22,28,96) 9.3 RHR HX Kvalue - 440 BTU /seo-F (Reference Tabei 4-1, NEDC 31940, March 1991) l 9.4 Service Water Temp - 85 F (Reference Tabei 4-1, NEDC-31940, March 1991) 9.5 Spray Duration - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after spray start (Reference CEI Calc 3.2.6.4, Rev 0, Pg 11 of33 for 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> duration. 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration being treated parametrically) 4

Attachment 6

. POLESTAR ev.ctt'sna.2076t PSAT 04212H.01 NON-PROPRIETARY P 1 of 6  ;

Rev: 0 234 i CALCULATION TITLE PAGE l i

CALCULATION NUMBER: PSAT 04212H.01 CALCULATIONTITLE:

" Source Term for Use on Perry Application of NUREG-1465" ORIGINATOE CHECKER IND REVIEWER Print /Sicn Date Print /Sicn DJ Print /Sicn Dige  ;

1

! REVISION: 0 ames /1eMatf D

• i f 6- D' **C  !

M f% led 2f96 bEI , Ilfl5L $ L G $lTl94

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2 3

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l REASON FOR REVISION: Nonconformance Rpt 0 -InitialIssue N/A l

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2

! 3 4

i

Attachment 6 l l

.. PY-CE!!NRR-2076L Page 16 of 217 PSAT 04212H.01 Page 2 of 6 Revhl 2 3 4 Table of Contents Section P.ags Purpose 2

Methodology 2

Assumptions 2

References -

4 Calculation 5

Results 6

Conclusions 6

Purpose The purpose of this calculation is to relate the source terms ofReference 1 to the the CEI Perry Nuclear Power Plant,

, Methodology The application of the revised source terms of Reference I to any plant requires the of the plant type (PWR or BWR) and a decision as to the time of the stan of the ga application to Perry the plant type is BWR, and for BWRs (according to Reference 1 the onset of activity release (i.e., the start of the gap release phase) would be c established if PWR timing were used. This is what has been done.

Assumptions Assumption 1:

The 10CFR100 Design Basis Accident (DBA), for purposes of applying the revised DBA source terms ofReference 1, is a large main steamline loss-of-coolant-accident (MSL LOCA).

Justification: i This accident is the current limiting DBA for the containment design, and will also lead to a slower core damage progression and a greater time-integrated airborne ,

, . ~

_ . . . ~-

Acachment 6 PLCE!!NRR-2076L Page 17 of 217 PSAT 04212H.01 Page 3 of 6 Revdl 2 3 4 activity in the drywell (the source of the MSIV leakage and a region not benefitted by the mitigating effects of containment spray) than would a recirculation line LOCA.

Assumption 2:

For application to Perry the PWR timing for the start ofrelease is applied.

This timing is approximated by the use of a 30 second delay from the time of reactor shutdown to that of the start of the gap activity release. Once begun, the gap activity release is assumed to be at a uniform rate over the 30 minute duration of the gap release phase.

Justification:

By the commentary ofReference 1, this is conservative for Perry. Reference I states that for accidents where long-term cooling offuel is maintained (e.g.,for a fuel handling accident), the release of the gap activity in failed pins (during the transient overheating of the fuel or immediately after mechanical damage) must be assumed to be instantaneous. This is a reasonable position. It also states that for accidents where long-term cooling is not maintained (e.g., for the 10CFR100 DBA which is the subject of this calculation), the release of the gap activity in the failed pins would be instantaneous, followed by an additional release (equal to 2/3 of the instantaneous release) over the full duration of the " gap release" (that release which occurs prior to the onset of fuel melting). This may be a reasonable position for an individual pin that has been operating at a high power level, but the timing ofpin failures and the subsequent temperature rise in individual pins varies across core. This variation needs to be considered, as well as the fact that the magnitude of the gap inventory will not be uniform; i.e., higher burnup pins will, to a degree, exhibit higher gap activity.

According to Reference 1, the failures of the first pin is predicted to occur for PWRs at about 30 seconds after the loss ofcoolant; other pin failures will follow.

A review of some of the analyses supporting Reference 1 (e.g., those listed on Tables 3.1 and 3.2 of Reference 1) indicate that the average core temperature can lag the peak core temperature by many minutes; and while this effect accounts for both radial and axial temperature distributions (and only the radial distribution is significant for the issue of relative timing of pin failures), it still suggests that the assumption of all pins failing in unison at approximately 30 seconds after the loss of coolant accident is excessively conservative.

A more reasonable assumption is one of a uniform release (over the duration of the gap release) totaling 1.67 times the assumed maximum gap inventory available for release at the start of the accident. This takes into account both the progressive nature of the pin failures and the additional release which will occur as pins increase in temperature after failure (but prior to fuel melting). In other words, if

Attachment ti PY CEl/NRR-2076L Page 18 of217 PSAT 04212H.01 Page 4 of 6 Revh 2 3 4

- one assumes lat 3% of the core inventory of a radionuclide ofinterest is in the gap at the time of the coolant loss, then 5% would be assumed to be released uniformly over the 30 minute duration of the gap release. This would correspond to a rate of 0.17 % of the core inventory / minute for that radionuclide.

Assumption 3:

HI may be neglected in terms of containment behavior and all iodine other than particulate Csl and organic iodine may be considered 1.

2 Justification:

Referetice 2 states that I and HI will coexist and that I will be favored if hydrogen pressures are low and/or if temperatures are relatively high in the location where equilibnum is attained. Specifically, is seven accident sequences studied in Reference 2, the only sequence in which the overall I + HI release exceeded 0.1%

of the total iodine was a large break PWR LOCA. For this case, the relatively h temperature gradients within the RCS and the relatively low production of

- hydrogen (both due to the low steam generation rates characteristic oflarge break LOCAs) contributed to a relatively high percentage ofnon-Csl iodine (about 3.2%) but also to a relatively low ratio ofHI to I (only 0.4% out of the 3.2%). It should be noted that a large break B28 LOCA was also studied (as one of the other six sequences for which almost no HI or I was found). Given these finding it is evident that for relatively large release fractions ofnon-Csl iodine ,

(characteristic of a PWR large break LOCA), little HI willbe found, and that for BWRs, even for large break LOCAs, little HI will 2be found. 1, on the other hand has non-RCS sources as well as RCS sources and must be consider BWRs. Reference I also requires its consideration.

Once in containment, 2both I and HI are reactive. The solubility ofHI, however, is considerably greater 2than 1 (nearly 3000 times greater on a molar basis); therefo one would expect the persistence of HI as an airborne component to be less than 1 2

in a steam and water environment. For this reason, as well as for its small release relative to I under the conditions where non-Csl iodine releases occur, it is considered reasonable to treat all non-particulate, non-organic iodine in containment as 1 2-l References i

Reference I:

Soffer, L., et al., " Accident Source Terms for Light-Water Nuclear Power Plants",

NUREG-1465, February 1995 a

Reference 2:

Beahm, E. C., et al., " Iodine Chemical Forms in LWR Severe Accidents",

NUREG/CR-5732, April 1992

Attachment 0

' PY-CEl/NRR.2076L Page 19 of 217 PSAT 04212H.01 Page 5 of 6 Revh12 3 4 Reference 3: Taylor, J., " Proposed Issuance of Final NUREG-1465, ' Accident Source Terms for Light-Water Nuclear Power Plants'", SECY-94-300, December 15,1994 l

l Calculation Soecification of Release Phases '

Reference 1 describes four release phases: gap, early in-vessel, ex-vessel, and late in-vessel.

Reference 3 establishes a precedent for advanced reactors (judged to be applicable to opera plants, as well) that only the first two phases need to be considered for DBA applications.

Therefore, two release phases will be referred to: the gap release phase and the fuel release with the fuel release phase making use of only the early in-vessel contribution from Reference 1.

Beginnint Duration. and Release Magnitudes of the Gao Release Phase l

By Assumption 2 the gap release starts at 30 seconds and is uniform over time. By Reference the duration of the gap release is 30 minutes. Release magnitudes are as follows (from Referen

1) given as fractions of core inventory and fractions of core inventory per second: l Noble Gas - 0.05 or 2.8E-5 /sec .

Iodine * ---- particulate (Cs1)- 0.0475 or 2.6E-5 /sec

- - - - elemental - 2.4E-3 or 1.3E-6 /sec

---

organic - 7.5E-5 or 4.2E-8 /see Cesium - 0.05 or 2.8E-5 /sec

• Based on 95% particulate,4.85%

elemental (see Assumption 3), and 0.15% crganic Beginning. Duration. and Release Magnitudes of the Fuel Release Phase This phase begins at 1830 seconds (i.e., at the end of the gap release phase). The duration Reference 1)is 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for BWRs; therefore, this release phase ends 7230 seconds after the beginning of the accident. Release magnitudes are as follows (from Reference 1) given as fractions of core inventory and fractions of core inventory per second:

Noble Gas - 0.95 or 1.8E-4 /sec lodine * -- -- particulate (CsI) - 0.2375 or 4.4E-5 /sec

---

elemental - 1.2E-2 or 2.2E-6 /sec

- - - - organic - 3.8E-4 or 6.9E-8 /see Cesium - 0.2 or 3.7E-5 /see Tellurium - 0.05 or 9.3E-6 /sec

• Based on 95% particulate,4.85%

! Attachment 6 PY.CEl/NRR-2076L

{

j Page 20 of 217 -

l PSAT 04212H.01 Page 6 of 6 1

Revh 2 3 4 elemental (see Assumption 3), and 0.15% organic 1

Results Fraction of core inventory, 0 - 30 seconds: no releases Fraction of core inventory, 30 - 1830 seconds: Gases -

Noble Gas - 2.8E-5 /sec (0.05 total)

Elemental I - 1.3E-6 /sec (2.4E-3 tot)

Organic I - 4.2E-8 /sec (7.5E-5 total)

Aerosols -

Iodine - 2.6E-5 /sec (0.0475 total)

Cesium - 2.8E-5 /sec (0.05 total)

Fraction ofcore inventory, 1830 - 7230 seconds: Gases - I Noble Gas - 1.8E-4 /sec (0.95 total) l Elemental I - 2.2E-6 /sec (1.2E-2 tot) 1 Organic I - 6.9E-8 /sec (3.8E-4 total)

Aerosols -

Iodine - 4.4E-5 /sec (0.2375 total)

Cesium - 3.7E-5 /sec (0.2 total)

Tellurium - 9.3E-6 fsec (0.05 total)

Conclusions The source tenn specification based on Reference I has the fellowing characteristics:

1. Two release phases: a Gap Release Phase beginning at t=30 secons, lasting 1800 second a Fuel Release Phase beginning at t=1830 seconds, lasting 5400 seconds.

2. lodine is in either particulate (dominant, as Csl aerosol) or in gaseous 2 form (as 1 or organic l

l i

l

Anacnme.a o PY-CELHRR 2076L Page 21 of 217 POLESTAR NON-PROPRIETARY PSAT 04212H.02 Page: 1of35 Rev:hl 2 3 4 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04212H.02 CALCULATION TITLE:

"Drywell Sweep-Out Rate and Related Thermal Hydraulic Conditions inside Containment" ORIGINATOR CHECKER IND REVIEWER Print / Sign Date Print / Sign Dale Print / Sign Dal.t REVISION: 0 " elez6 JoL Tr ~

h. A lu-27l% $$5I% , n $4fil 1

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4 REASON FOR REVISION: Nonconformance Rot l

0 - Initial Issue N/A 1

2 3

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PY CEthRR-2076L

' Page 22 of 217 PSAT 04212H.02 Page: 2 of 35 Rev:hl 2 3 4 Table of Contents S.cclion Page Purpose 2 Methodology 2 Assumptions 3 References 8

Calculation 9

Results 34 Conclusions 35 Appendices:

A "Use of a Uniform Sweep-Out Rate During the Release Phase" - 3 Pages B " Steam Generation During Reflood"- 11 pages .

Purpose The purpose of this calculation is to specify the volumetric exchange rates between the Perry drywell and containment during two periods of the problem: during the fission product release (gap release phase from 30 seconds to 1830 seconds and early in-vessel or " fuel" release phase from 1830 seconds to 7230 seconds - see Table 3.6 of Reference 1) and after the fission product release phase (7230 seconds until 30 days which is the end of the dose calculation interval from Reference 2). During (and immediately after) the fission product release phase the flow is only from the drywell to the containment and may be referred to as the " sweep-out" rate.

Methodology In order to specify the volumetric sweep-out rate, it is necessary to know the quantity of water remaining in the vessel after the DBA blowdown, the thermodynamic state in the drywell, and the rate at which steam is produced from the core debris in-vessel up to and including the point in time where the core debris quench is complete (assuming that to be shortly after 7230 seconds, the end of the in-vessel release phase). Beyond 7230 seconds + the reflood/ quench time, the drywell and wetwell/ lower containment are assumed to be well-mixed, but a mixing rate must be

Attxhmem o PY CE1/NRP-2076L l Pege 23 of 217  !

PSAT 04212H.02 Page: 3 of 35 Rev:hl 2 3 4 specified to reflect that assumption. (Note that the mixing rate between the upper containment which is sprayed and the wetwell/ lower containment which is not sprayed is the subject of a separate calculation).

l A manual calculation is shown below which:

e Quantifies the minimum water mass remaining in the vessel after DB A blowdomi, Determines a minimum steaming rate (as a function of time) for that remaining water, and e

Calculates the volumetric flowrate rate (drywell to wetwell/ lower containment) that l

corresponds to that steaming rate and to the final quench of the core debris.

l Assumptions Assumption 1:

Reactor vessel reflood occurs at 7230 seconds, terminating the release and quenching the core debris.

Justification:

This assumption reflects the position that Reference 3 takes with respect to the release phases of Reference 1. Reference 3 refers to an NRC position taken on the advanced light water reactors in Reference 4, which is:

"In a forthcoming paper, the NRC staff will indicate that for evaluation of design basis accidents (DBA) for evolutionaty and passive light-water reactor designs, only the releases asmciated with the gap and early in-vessel release phases will t e used. The inclu tion of the ex-vessel and late in-vessel releases are considered to be unduly conservative for DBA purposes. Such releases would only result from core damage accidents with vessel failure and core-concrete interactions."

This NRC position, as extended to operating reactors by Reference 3, means that vessel failure is not to be included in the DBA. This position also implies, then, that debris coolability must be re-established at about the time of the end of the in-vessel release phase, otherwise, reactor vessel failure would likely follow.

Assumption 2: Suppression pool scrubbing is neglected.

Justification:

It is conservative to neglect pool scrubbing. However, it is also technically true that should design levels of pool bypass exist (A/(K = 1.7 f12 from Section 4 of Reference 5), then most of the flow from the drywell to the wetwell would bypass the pool in any case.

Alanment o PY-CELHRR-2076L Page 24 of 217 PSAT 04212H.02 Page 4 of 35 Rev: 234 Assumption 3: Drywell and wetwell/ lower containment are mixed by the H2 mixing fans following the core debris quench at t = 7230 seconds + time to reflood and quench.

Justification: Once the core debris is quenched in-vessel, the production of hydrogen will cease.

However, the degree of core damage implied by Reference 1 is such that the hydrogen concentration in the containment necessitating operation of the mixing fans will certainly be exceeded during the core degradation prior to quench.

Therefore, it is reasonable to consider the drywell and wetwell/ lower containment (i.e., the entire unsprayed containment) to be mixed post-quench by at least one of the mixing fans and to continue that mixing for the 30-day dose calculation period.

Assumption 4: Containment spray mode of RHR is actuated 10 minutes after start of fission product release (i.e., at 630 seconds).

Justification: Since ECCS is not being credited for reflood for the first 7230 seconds and since reflood can be accomplished by core spray operation alone (high- or low-pressure), one loop of RHR containment spray is assumed to be actuated as designed after a delay of 10 minutes following low coolant level being reached in-vessel. This actuation time would be no more than 10 minutes after the start of the assumed fission product release as long as the containment pressure permissive is satisfied. >

Nine psig (23.7 psia) in the containment is needed to satisfy the pressure permissive for spray actuation (Reference 6, Item 9.1). It is assumed that pool scrubbing is neglected on the basis of design levels of suppression pool bypass ,

being present (as previously discussed) and since the containment will reach a l pressure of at least 19 psia and 1.04 times the initial temperature due solely to  !

airspace compression by air purged from the drywell (see Short-Term Containment Response in the Calculation section, below), it is judged likely that steam bypassed from the drywell will raise the containment pressure the additional 4.7 psi needed for spray actuation. Referring to Exhibit I from Reference 7, a steam partial .

pressure of 4.7 psi requires (1) a saturation temperature of about 160 F (66 F  !

higher than the 94 F given on Page 25 as the expected post-blowdown containment temperature) and (2) an amount of water vapor equal to approximately 15000 lbm (containment free volume of 1.17 x 10' ft' from Reference 6, Items 3.2 and 3.3 divided by 79 ft'/lbm for saturated steam at 160 F and 4.7 psia - see Exhibit 1). If the energy to raise the containment atmosphere temperature also comes from leaking steam, the amount of steam required would be roughly the constant volume heat capacity of the containment atmosphere (approximately 110000 lbm of air x 0.17 BTU /lbm-F) times the temperature change (66 F) divided by 1000 BTU /lbm for condensing steam or slightly more

Attachment t>

PY.CEl/NRR.2076L  !

^

Page 25 of 217 PSAT 04212H.02 Page: 5of35 Rev:@l 2 3 4 Exhibit 1 i

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]) 480 456.58 OA195 LO320 437.1 767A 1304A 0A356 OA378 1A734 4353 095A 1118J 400 883.1 1118.7 450 .

500 467Al 0A197 OA278 449A 755A 1304A _

j 550 470A3 OA190 04487 OA147 L4634 447A 671A 1118A 500 0A421 4004 743.1 1903A 0.6608 03934 L4542 458A 4

600 486.11 0.0201 0.7898 471A 859.4 1118.2 550 700 731A 12032 0A730 0.7734 L4454 469A 648J 1117.7 800 4' 503.10 0.0205 CA554 4913 7093 1901.1 800 518.13 OAB00 OA925 0 3371 1.4296 488A 827J 1116.3 700 1 0J687 5093 088A 1198A 0J108 03045 1.4153 506A 007A 1114A 000 900 531.98 OAtti 0.5006 536A S8BA 1105.4 1000 544A1 0.0216 0.7275 OA744 1A030 513.1 509A 111L1 900 0A456 54L4 649A 1191A 0.7430 0A467 1.3897 538A 5714 1109A 1000 1100 55631 OARSO 0.4001 557A 630.4 1187A 1300 567.21 0.0213 0.7575 OA305 IJ780 55L9 553J 1106A 1100 02619 5713 4113 1183A 05711 OJ056 L3687 5663 536J 1103.0 1300

1300 577A6 0.0237 0J293 585A 5932 ,1178.6 03840 OJ719 L3559 500.0 519A 1099A 1300 1400 587.10 0.0231,, 0.3011 596.7 574.7 1173A 1500 596A3 0.0235 0.7983 0 3491 1.3454 592.7 50L7 1095A 1400 a

' 0.2765 SIL6 556J 1167.9 0.8081 0.5260 1.3351 005.1 486.1 1001.1 1500 3000 635A1 0.0257 0.1878 871.7 1 463.4 1135.1 0A619 0A130 1J849 802.1 403A 1065.6 2000 3500 468.13 0.0387 0.1307 730A 2000 3803 1001.1 0.9128 0.3197 1 3322 717.3 313J 1030A 2500 895.36 0.0346 CA858 802J 117A 1030.3 0A731 0.1885 1.1615 783A 189.3 97L7 3000 8305.2 705.40 0.0503 0A503 90L7 0 902.7 1.0500 0 LO500 87L9

0 8719 3306 1

4 i

Attachment 6 PY CEt/NRR-2076L Page 26 of 217 PSAT 04212H.02 Page: 6 of 35 Rev:hl 2 3 4 than 1000 lbm of additional steam. Therefore, raising the containment atmosphere temperature to 160 F and saturating that atmosphere with steam would require about 16000 lbm of steam.

From the section below on Short-Term Containment Response, the design bypass flowrate is approximately 100-150 lbm/sec during blowdown and will be sustained even after blowdown as the drywell and the containment equalize. Even if the bypass were only one-half this value, sufficient steam would bypass the pool over the approximately 360 seconds of blowdown to reach the necessary 4.7 psi steam partial pressure in the containment for the spray permissive. It should also be noted that in Reference 5, Section 4 it is stated that the containment design pressure of about 30 psia would be exceeded during blowdown for a large LOCA if a bypass area three times design (i.e., A//K greater than 5 fir) were present.

This 30 psia represents an increase over the " design" post-blowdown pressure (

without bypass) of about 10 psi. One would therefore expect that for the design bypass case an increase in the containment pressure (over the design case without bypass) of at least 3-4 psi would be expected during blowdown, bringing the pressure to nearly that for the spray permissive. Given that some hydrogen production, drywell heat-up, and drywell equalization will be occurring post-blowdown for a large steamline LOCA without ECCS, it is cenain that the spr permissive pressure would be reached within 10 minutes of start of fission produ release for a DBA with design pool bypass.

As:ampJon 5:

Following the DBA (main steamline large LOCA inside containment) the water mass remaining in the vessel is that corresponding to the initial inventory from Reference 5 (Section 3.2.1)less the integrated blowdown from Reference 5 (Table 3.3.1.1).

Justification:

The use of a main steamline large LOCA as the DBA is discussed in Reference 8.

Since the mass and energy releases from Reference 5 are maximized to maximize the containment design conditions, this assumption yields a conservatively small value for the water mass remaining in the bottom of the vessel after blowdown.

Assumption 6:

In order to calculate the steaming rate from the core debris, it is assumed that the fraction of the core panicipating in the boil-off of the water mass remaining in the bottom of the vessel post-blowdown increases uniformly from zero at 1830 seconds (end of the gap release phase) to 50% at 7230  !

seconds (end of the in-vessel release phase). i Justification:

This assumption is based in part on Assumption 1. At the end of the in-vessel release all of the core debris will be quenched, both that which has relocated to the l lower part of the vessel and that remaining in the original core region. For

\

Anachmem o PY-CE!'NRR 2076L Page 27 of 217 l

l PSAT 04212H.02 Page: 7 of 35 Rev:hl 2 3 4 l conservatism, the debris remaining in the core region is neglected in the calculation of the steaming rate during core degradation; only the assumed 50% of the core l debris which relocates to the lower part of the vessel and its interaction with the l

residual water (Assumption 5) is included in the quantification of the steam production during the in-vessel release phase. t Assumption 7: The exchange rate between the drywell and the wetwe!!/ lower containment is assumed to be constant during the release phase (up to 7230 seconds). l Justification: This assumption is slightly non-conservative because it overestimates the removal rate from the drywell early in the release phase. However, it does simplify the analysis; and for relatively low removal rates (of the order of one per hour) the

)

underestimate of the late removal compensates nearly completely for the overestimate of the early removal. A further demonstration of the adequacy of this assumption is presented in Appendix A. -

Assumption 8:  !

The fmal core debris quench requires the time it takes minimum ECCS (one core spray pump) to refill the core region, and it involves only the energy stored in the one-half of the core debris assumed not to relocate to the lower part of the vessel. A bottom-up quench is assumed; i.e., the core spray is assumed not to interact with fuel debris on the way down, but rather collects in the vessel head and refloods from below. This mir.imizes steam production which is conservative.

Justification:

Leaving one-half the core uncovered for a period of 7230 seconds (less the blowdown / core uncovery time) results in core debris left in the core region with significant stored energy. The restoration of minimum ECCS will remove this stored energy at a rate determined by the coolant injection rate (drawn from the suppression pool) and the rising water level (reflood rate). To determine the reflood rate, the ECCS injection rate must be reduced by the rate of steam production. The rate of steam production in this analysis corresponds to a low estimate of stored energy in only one-half of the core debris.

If a top-down quench were modeled, steam production would begin immediately as individual spray droplets (at an injection rate of more than 1000 lbm/sec) come in contact with the debris. These droplets have the potential to remove heat at the rate of more than 1000 Mw (i.e., >10' BTU /sec), producing steam at a rate approaching one-tenth that of the initial blowdown or about one drywell volume

' per minute or 60 volumes per hour. This steam would vent from the core debris counter to the spray flow, and some of the steam would be condensed by the counterflowing spray, but since the subcooling of the injection water would be less than 200 BTU /lbm even at an elevated vessel /drywell pressure, only a small

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fraction (e.g.,20 percent or less) would condense. Therefore, a bottom-up I quench, with its delayed and reduced steam production, is conservative. l Reference 9 indicates that the sweep-out rate corresponding to the final core debris quench would be expected to be of the order of 10 drywell volumes per hour.

4 Assumption 9: Core debris remaining in the core region during reflood may be characterized as naked fuel pellets and similar sized debris. It is further  ;

assumed that the height of the debris bed is approximately one-half the l original core height or six feet.

Justification: Much of the core debris observed at TMI-2 and in various core-damage experiments using LWR or LWR-like fuel which has not melted or relocated has exhibited these characteristics.

Assumption 10: Sprays operate for six hours (minimum) after the initiation.

Justification: It is likely that the RHR system operating mode would be changed to pool or shutdown cooling at some point, but six hours of spray operation after initiation reflects a conservative minimum estimate of spray duration. I i

References i

Reference 1: Soffer, L., et al., " Accident Source Terms for Light-Water Nuclear Power Plants",  ;

NUREG-1465, February 1995 Reference 2: DiNunno, J. J., et al.,

• Calculation ofDistance Factors for Power and Test Reactor Sites", TID-14844, March 1962 Reference 3: Leaver, D. E. and Metcalf, J. E., " Generic Framework for Application of Revised Source Term to Operating Plants", EPRI TR-105909, EPRI Research Project 4080-2, November 1995 Reference 4: SECY-94-300, " Proposed Issuance of Final NUREG-1465, ' Accident Source Terms for Light-Water Nuclear Power Plants' ", December 15,1994 Reference 5: " Containment and NSSS Interface", General Electric Data Book 22A3759AL, Rev 2, March 29,1991 i

Reference 6: PSAT 04202U.03, " Dose Calculation Data Base for Application of the Revised DB A Source Term to the CEI Perry Nuclear Power Plant", Revision 0

l l

Attachment b PY<ElNRR 2076L i Page 29 of 217 PSAT 04212H.02 Page: 9 of 35 Rev:@l 2 3 4  !

Reference 7: Babcock and Wilcox, Steam. Its Generation and Use, New York,1963 I

Reference 8: PSAT 04212H.01, " Source Term for Use on Perry Application ofNUREG-1465",

Revision 0 Reference 9: Leaver, D. E., et al., " Licensing Design Basis Source Term Update for the l l

Evolutionary Advanced Light Water Reactor", DOE /ID-10298, September,1990 t

Reference 10: AIF/IDCOR Report 23.lGG 1 Reference 11: McAdams, Heat Transmission, McGraw-Hill, New York,1942 l

Reference 12: Handbook of Chemistry and Physics,51" Edition, 1970-71 Reference 13: NRC Generic Letter 88-20 Reference 14:

" Perry Technical Specifications Improvement - Containment Response Analysis",

General Electric Report NEDC-31940, March 1991 Reference 15: Handbook of Chemistry and Physics,73'd Edition, 1992-93 Reference 16: Keenan and Keyes, The Procerties of Steam, John Wiley a'nd Sons, London,1936 Calculation Minimum mass of water remaining in vessel nost-DB A blowdown Reference 5 provides the following:

e Total Reactor Fluid Inventory - 5.64 x 10' lbm o

Reference 5, Table 3.3.1.1 blowdown rates reproduced as Exhibit 2 Integrating the Exhibit 2 blowdown rates over the first 30 seconds without ECCS (referring to Table 3.3.2.3 of Reference 5, the first 30 seconds is the pre-ECCS blowdown phase), the total blowdown is 5.40 x 10'lbm. This leaves a minimum of 24000 lbm of water in the vessel without ECCS after blowdown. This mass of water is conservative compared to the Mark III reference analysis performed by AIF/IDCOR which indicated that for a large-break LOCA without injection (Reference 10, Figure B-16 for AE sequence) more than 13' of water would remain in the vessel after blowdown. This would mean the entire lower head of the vessel (approximately 2400 ft' or 1.4E5 lbm of water for the IDCOR reference Mark III plant) was predicted to remain filled.

l

Ammkum6 PY-CEl/NRR-2076L Page 300f 217 PSAT 04212H.02 Page: 10 of35 Rev:@l 2 3 4 Exhibit 2 TABLE 3.3.1.1 (MAIN STEAM LINE BREAK) REACTOR PRIMARY SYSTEM BIDWDOWN FIDW RATES AND FLUID ENTHALPY TIME LIQUID FLOW LIQUID ENTHALPY STEAM FIhW STEAM ENTHALPY

.QEfd (LBS/SEC) (BTU /LB)- (LBS/SEC) (BTU /LB)

O. 0 551.6 9850. 1190.7 0.05 0 551.0 11440 1190.8 0.22 0 549.7 8259. 1191.1 0.999 0 545.4 8025. 1192.3 1.000 27000. 545.3 1094 1192.3 2.01 26670. 545.2 1200 1192.3 4.01 25890. 544.2 1419. 1192.5 6.00 19730. 543.6 1273. 1192.7 8.03 19130. 542.7 1425. 1192.9 10.03 18430. 540.2 1560. 1193.5 15.03 16340. 528.0 1805. 1196.1 ~

20.03 14040. 507.8 1880. 1199.7 25.03 11810. 492.7 1794. 1201.7 30.03 9877.

~

492.3 1634.. 1201.8 50.06 5769. ' 356.5 '

652.6 1198.5 70.06 5132, 295.7 230.6 1186.5 90.15 5083. 274.7 125.7 1181.1 100.9 4984. 265.0 91.0 1178.4 119.9 4980. 257.8 62.9 1176.4 140.4 5022. . 254.9 47.7 1175.5 200.4 5213. 255.0 29.1 1175.5 300.3 4450, 236.5 _ 10.2 1170.9 350.9 1207. 220.7 1.6 1164.7 359.9 112.3 219.3 0.14 1164.3 9

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Beyond the blowdown (which ends at 360 seconds after the break), there are three factors which could make this case different from the containment DBA case for steamline break presented in  !

Reference 5. These are as follows:

l

1. Design basis levels of suppression pool bypass,

2. Spray actuation at 10 minutes afterlow level in the reactor vessel, and l

3. Zircaloy oxidation yielding hydrogen and energy.

i These are discussed in order below.

Design Levels of Suppression Pool Bypass:

For A//K values up to and including the design basis value of 1.7 ft2 (see Assumptions 2 and 4),

the containment pressure would increase more rapidly than the containment DBA steamline break analyzed in Reference 5. It is this increase in containment pressure (for large values of A/(K) that would bring about the early actuation of containment sprays. However, even if bypass were not sufficient to pass 16000 lbm of steam during blowdown (in 360 seconds, see Assumption 4),

the sprays could be manually actuated witUn the first half-hour; i.e., before the stan of the fuel

Atahment b PY-CE1/NRR-2076L Page 43 of 217 PSAT 04212H.02 Page 23 of35 Rev: 1234 release at 1830 seconds. Therefore, the assumption of spray start at 10 minutes (after low level in the vessel)is not critical. If there were a bypass ofonly, say, A//K = 0.8 ft2 and the spray did not start, pool scrubbing during the debris quench would be appreciable, and the sprays would have been delayed only an additional 20 minutes. Consider the following:

Mdot = A//K(/2g,p AP) = mass flow rate through the bypass path Figure 3.3.1.14 of Reference 5 shows that the drywell-to-containment differential pressure will be greater than about 7 psid during blowdown, and the density (after the liquid phase dropped out) would be approximately that ofsteam at 20 psia or 0.05 lbm/ft'. For these values (and A//K =

the design basis value 1.7 ft2)

Mdot = 97 libm/sec 1 Earlier in the blowdown when the differential pressure would be twice that and the drywell would be carrying airborne liquid (see Figure 3.3.1.11 of Reference 5) with a density four times as great, j the bypass would be:

I Mdot = 274 lbm/sec ofwhich perhaps one half would be steam. Under these conditions the containment would pressurize rapidly and the estimated 16000 lbm of steam necessary to reach the threshold pressure for containment sprays (see Assumption 4) could be passed in as little as two minutes. Even if the full 360 seconds (six minutes) of blowdown were needed, the corresponding average bypass flowrate (to pass 16000 lbm of steam) would be 44 lbm/see representing an A//K value of about 0.8 ft2

. For bypass values less than 0.08 ft2 the sprays might be delayed, but the pool sembbing during the debris quench would be substantial. Referring back to the table of debris quench steam flowrates on Page 20, it can be seen that during the debris quench an A//K corresponding to a bypass flow of 44 lbm/see would pass only 6300 lbm of steam while the total flow would be about 28000 lbm. Therefore, during the more than one full purge of the drywell associated with this steam flow, the pool bypass would be only slightly greater than 20 %. This would more than compensate for the 20-minute delay in spray actuation during the gap release phase. Therefore, the assumption of design levels of pool bypass is the conservative one, even though that assumption allows crediting of containment sprays somewhat earlier.

Given that the bypass can bring the containment temperature and pressure to 160 F and approximately 24 psia at the time of spray actuation at 630 seconds (and the corresponding drywell pressure perhaps as much as 8 psid higher based on the differential pressure at 30 seconds from Reference 5, Figure 3.3.1.14), the next question is what is the impact of spray operation.

(Note that 30 seconds is the point in the present analysis where the ECCS " fails" guaranteeing that subsequent drywell-to-wetwell differential pressures will be less, at least up until the time of spray actuation).

Attachment 6

• PY-CE!/NRR-2076L Page 44 of 217 PSAT 04212H.02 Page: 24 of 35 Rev:@l 2 3 4 Spray Actuation at 10 Minutes after Low Level in the Reactor Vessel:

The containment spray flowrate is 5250 gpm (726 lbm/sec) with one pump operating (Reference 6, Item 3.25). The RHR HX has a K-factor of 440 BTU /sec-F (Reference 6, Item 9.3) and employs a cooling water temperature of 85 F (Reference 6, item 9.4). Therefore, given that:

Heat Transfer Rate = 440 BTU /sec-F(Tg - 85 F)(based on heat exchanger)

= 726 lbm/see x 1 BTU /lbm-F x (Tg - T,,,,y) (based on spray flow) the spray temperature, in terms of suppression pool temperature, is:

T,,,,y = 0.39(Tg) + 52 F Using Figure 3.3.2.6 of Reference 5 (and remembering that the delayed ECCS case would result

- in a lower containment pressure and temperature at this point in time), the temperature of the suppression pool at the time ofspray initiation would be a maximum of about 155 F. This would result in a maximum initial spray temperature of about 112 F. For this initial spray temperature, the initial condensation rate per pound of spray flow would be about:

(T- - T,,,,y) x 1 BTU /lbm-F/hg = (160 F - 112 F)/960 BTU /lbm @ 20 psia

= 0.05 lbm/lbm For a spray flow of 726 lbm/sec, the initial condensation rate would, therefore, be about 36 ,

Ibm /sec; and if that condensation rate were sustained, the 15000 lbm of steam in the containment atmosphere (see Assumption 4) would be condensed in about seven minutes. Considering the decrease in condensation rate as the spray water temperature increases and the containment temperature decreases, it would, in actuality, take sever'al times longer. For simplicity, it can be assumed that the containment atmosphere temperature will decrease to the average of the instantaneous spray injection temperature and the instantaneous pool temperature in about 20 minutes; i.e., at the time of the start of the fuel release at 1830 seconds. This temperature would not be greater than:

165 F + (165 F x 0.39) + S2 F = 140 F where 165 F is taken from Figure 3.3.2.6 of 2 Reference 5 at 1830 seconds Once this containment temperature is reached, the containment temperature could begin to rise as the pool heats up above 165 F. Were the pool to be subjected to the continuous heat addition of successful ECCS operation (as in the case for the transient presented in Figure 3.3.2.6 of Reference 5), the temperature of the pool could increase over the next several hours to near its design maximum value of 185 F. For this degraded core case, however, the steam generation

Attachment 6 PY-CELHRR-2076L Page 45 of 217 PSAT 04212H.02 Pag 25 of35 Rev: 1234 is very low during the core degradation (4.4 lbm/sec average) and at that low value, the pool is being completely bypassed (see discussion of suppression pool bypass, above). Therefore, the 140 F containment temperature can be assumed to remain constant up until the start of the steam production associated with debris quench (at 7333 seconds). If anything, it would decrease (i.e.,

for a steam load on the sprays of 4.4 lbm/sec, the heat load transferred to the pool would be about 4400 BTU /sec, and with a heat exchanger K-factor of 440 BTU /sec-F and a cooling water temperature of 85 F, the pool temperature could decrease to 95 F and still dissipate this heat load). At the time cf the debris quench, the pool temperature and the containment temperature would increase dramatically, but not to a value greater than the design case. This is discussed further under Long-Term Containment Response. For simplicity, it will be assumed that the containment temperature reaches its design value of I85 F, as a maximum, at the time of the debris quench. (In reality, continued application of spray for six hours after the accident, see Assumption 10, would keep the temperature below this maximum for some time, certainly as long as the sprays continued to operate). This maximum is shown on Exhibit 4, a mark-up ofFigure 3.7.1 ofReference 5. -

Also shown on Exhibit 4 are the maximum pressures as functions of time. The pressure at 10 seconds (part-way through the blowdown and prior to the start ofECCS for the case with ECCS) is taken from Figure 3.3.2.7 of Reference 5, and the value is 20 psia. Reference 14 states that the long-term containment response analysis (which constitutes the basis for Figure 3.3.2.7 of Reference 5) does not include the assumption of equilibrium between pool and containment atmosphere which is used in the short-term analysis. Rather, the thermodynamic states are calculated separately. This explains why Reference 5, Figure 3.3.2.6 begins at 10 seconds with a containment atmosphere temperature approximately 40 F higher than that of the pool.

From Reference 5, the pool begins at an assumed temperature of 95 F, 9 F less than the assumed containment atmosphere. (Maximum conditions are 95 F and 104 F, respectively). The initial containment pressure is expected to be 14.7 psia. By 10 seconds into the event, virtually all of the 2.8E5 ft' of drywell air has been purged into the 1.17E6 ft' containment, and given this rapid purge, one would expect, as a minimum, a polytropic compression of the containment air with an l n" of approximately 1.2. Using the expression:

T/f = (V /V )'*2 = [(1.17E6 + 2.8ES)/1.17E6]42 = 0.96 T = (104 + 460)/0.96 = 588 R = 128 F The corresponding pressure increase is about a factor of 1.3; i.e., to about 19 psia. However, the maximum containment pressure at 10 seconds taken from the Figure 3.3.2.7 ofReference 5 is 20 psia as noted above. This is because the containment temperature at 10 seconds from Figure 3.3.2.6 (about 145 F) is greater than the polytropic compression would account for. Even with an assumed initial drywell temperature of 145 F, the compression would raise the containment temperature to only 136 F. But an increase in containment temperature to 145 F would raise the

Attechment 6 PY-CEl/NRR-2076L Page 46 of 217 PSAT 04212H.02 Page: 26 of35 Rev:hl 2 3 4 pressure to 20 psia. Therefore, one can conclude that decreasing the temperature to 140 F (average following spray actuation) would reduce the pressure to essentially the same value.

Once the production of steam begins from the debris quench at 7333 seconds, the containment pressure will increase. Given that: (1) the beginning temperature is about the same as it was at 10 seconds, (2) the time for the pressure increase during the debris quench is less than it was during the 630 seconds between the start of the accident and the start ofcontainment sprays, and (3) the sprays are already operating, it is not likely that the containment pressure would be greate than that at the time of spray initiation,24 psia. This pressure exceeds the long-term containment pressure peak presented in Figure 3.3.2.7 of Reference 5, and may be regarded as an upper-bound containment pressure in the long-term as well as the short-term (see next section). As was the case forjust before spray initiation, the drywell pressure will not be more than 8 psid greater (i.e.,

32 psia - see Page 23) during the debris quench.

The maximum short-term values for containment pressure and temperature are shown on Exh 4, a mark-up ofFigure 3.7.1 ofReference 5. The same information is provided for the maximum drywell short-term pressures and temperatures on Exhibit 5, a mark-up of Figure 3.7.2 of Reference 5. Note that the maximum temperature in the drywell is assumed to be identical to design values. This is reasonable for a steamline break and conservative for a liquid line bre These maxima reflect suppression pool bypass and spray operation. Theonly remaini the three mentioned in connection with deviations from the Reference 5 thermal-hydraulic analyses) is zircaloy oxidation and hydrogen.

Zircaloy Oxidation Yielding Hydrogen and Energy

j

For a major pipe-break, hydrogen production tends to be limited until the core debris i quenched. This is because the core region empties rapidly of coolant, leaving residual water in i

lower vessel head without a significant heat source to produce the steam necessary for th zircaloy oxidation. For a small break, a stuck-open safety / relief valve, or a transient le i core damage, on the other hand, the production of hydrogen tends to be much greater, with potentially a greater impact on the containment thermal-hydraulics. However, for such events most, if not all, of the activity released from the core will be flushed out of the vessel anI j

} the safety / relief valve discharge to the pool where scrubbing will occur. Steam will b j

hydrogen on a mole-for-mole basis in-vessel; and therefore, the vessel sweep-out will be at lea

the same and, in reality, much greater because of the higher gas temperatures associated with zircaloy oxidation. Therefore, the impact of zircaloy oxidation on activity transport within the containment will be small and possibly even beneficial in the short-term, to the extent that l  !

j convection of activity to and through the suppression pool may be enhanced. The long-term impact is discussed in the next section.

4

l

Up to this point this section has concentrated on short-term maximum containment pressu l

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Anzchment O PY.CELKRR-2076L Page 49 0f 217 PSAT 04212H.02 Page: 29 of 35 Rev:@l<2 3 4 temperatures. For short-term minimum values ofdrywell and containment pressure, initially and during spray operation, it will simply be assumed that the containment pressure will not be less than 15.7 psia (1 psig) and that up until the time of the end ofsteaming from the debris quench (7484 seconds), the drywell is steam-filled and saturated at the temperature corresponding to that pressure (i.e.,215 F from Exhibit 1). Beyond that time the drywell and the containment are assumed to be at the same minimum temperature as the containment is assumed to be at immediately afier blowdown,100 F.

Long-Term Containment Resoonse In the long-term (beyond completion of steam production from the quenching of the core debris at 7484 seconds) the existing design basis maxima presented in Exhibits 4 and 5 will be assumed to hold with one exception and one comment. The exception is that the containment design pressure (15 psig or approximately 30 psia for one day) is much too high in light of the maximum long-term drywell pressure which is only about 30 psia (15 psig). The maximum drywell press is assumed to decrease immediately from 32 psia to 30 psia at 7484 seconds and then to follow the pressure shown on Exhibit 5. The maximum containment pressure is assumed to increase to 24 psia and to remain constant until approximately 6ES seconds when the pressure is then assumed to track that shown on Exhibit 4.

The comment pertains to the imponance ofhydrogen on long-term containment thermal-hydraulics. Exhibit 6 is Figure 3.3.2.8 ofReference 5 which compares the integrated decay p ,

vs. integrated heat removed from the containment for a large-break LOCA. Marked on this fig is the total heat released by the oxidation of approximately 50% of the zircaloy inventory in the core. This energy has been estimated from the zircaloy mass of 8.1E4 lbm (4E5 g-moles) from Reference 5, Section 3.2.1 and from the heat released by formation of one g-mole ofzirconium oxide (1106 KJ/g-mole from Reference 15 which represents, also, one g-mole ofzirconium). T release yields approximately 2E8 KJ or 2E8 BTU. The impact of this energy release is mitigated in the core by the need to decompose the steam to support the reaction; this decomposition requires 286 KJ per g-mole of 2 H O decomposed (from Reference 15), and since 4E5 g-moles of 2

H O must be decomposed to oxidize 2E5 g-moles ofzirconium, the energy needed to decompos the steam is about 1.1E8 KJ or 1.1E8 BTU. Therefore the net energy added to the core by 50%

zircaloy oxidation is about 9E7 BTU or 26 Mw-hrs or about 25 full-power-seconds. This energ will eventually show up in the containment as steam or heated water released during the quenching of the core debris and will be supplemented by hydrogen m recomb

• ation as the igniters operate to limit hydrogen concentrations. The total energy addition to the containment would be the 2E8 BTU.

This amount of energy is important only in the first day or so. Beyond that point it becomes increasingly overwhelmed by the decay heat (i.e., at the end of the first day it is only about seven percent of the integrated decay power). As can be seen from Exhibit 6, the rate ofheat removal by the RHR system becomes equal to the rate of heat addition at about four hours (slopes are l

1 i

PSAT 04212H.02 Page: 30of 35 Rev:hl 2 3 4 Exhibit 6 INTEGRATED DECAY POWER AND IIEAT REMOVED BY RIIR vs 50% ZIRC OXIDATION

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Attchment b PY.cE1/NRR-2076L Page51of217 PSAT 04212H.02 Page: 31 of 35 Rev:hl 2 3 4 equal). If more heat had been added early by zirconium oxidation (effectively, an increase in the

" decay power" over the first few hours of the accident), the point of" parallel slopes" would be reached sooner, indicating an earlier (but higher) maximum pool temperature than that from Reference 5. One way of estimating the impact of this energy is to assume that the steam resulting from it (either by cooling of core debris or by igniter-induced combustion) is condensed in the suppression pool (mass = 1.2E5 fl' from Reference 5, Section 3.2.2 x 62 lbm/ft' water density = 7.4E6 lbm). This would result in a temperature increase of the pool of about 27 F. If this were added to the peak suppression pool temperature given in Reference 5 of 185 F, the result would be 212 F. At this pool temperature, the associated spray temperature would be (using the expression on Page 24):

212 F(0.39) + 52 F = 135 F And assuming the atmosphere were at an average temperature corresponding to the average of the pool and spray temperatures, that temperature would be 174 F. For an expected initial containment temperature of 90 F the pressure increase due to the containment air heat-up would then be (460+174) R/(460+90) R or 1.15. Adding the saturated vapor pressure of steam at 174 F (approximately 6.6 psia from Exhibit 1), the corresponding containment peak pressure would be (1.15)(14.7) + 6.6 = 24 psia, and this peak would be expected within the first hour or two after quenching of the core debris. This is the same post-quench maximum containment pressure decided upon in the section on Short-Term Containment Response.

l l

POLESTAR PROPRIETARY l

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Attachment 6 PY-CEl/NRR-2076L Page 56 of 217 PSAT 04212H.02 Page:Al of A3 Rev:hl 2 3 4 APPENDIX A APPENDIX TITLE:

"Use of a Uniform Sweep-Out Rate During the Release Phase" SAFETY-RELATED APPENDIX: Yes i

CALCULATION NUMBER: PSAT 04212H.02 j CALCULATION TITLE:

i f "Drywell Sweep-Out Rate and Related Thermal-Hydraulic Conditions inside 1

Containment" Purpose The purpose of this appendix is tojustify a uniform sweep-out rate from the drywell to the torus during the release phase from essentially t=0 to t=120 minutes.

Approach The approach is to set up a spread-sheet wherein:

A release of 5% radioiodine is introduced over 30 minutes with no removal, and e

An additional 25% is added over 90 minutes using (1) no removal, (2) removal at a '

constant rate (" lambda") of one per hour, and (3) a linearly increasing removal rate beginning at zero and increasing to two per hour at the end of the 90 minutes.

The percent airborne is plotted and the integral under each of the curves is also calculated. The area under the curve (in %-minutes) is indicative of the release that would occur from the drywell for a constant leak rate and no decay. An assumption of no decay is acceptable since I-131 is the dominant radioiodine nuclide and it has a half-life of 8.1 days compared to the two-hour duration of this calculation. '

Results The results are shown on Figure A-1. The accuracy of the spread-sheet can be checked by

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Page 57 of 217 j i

i i PSAT 04212H.02 Page: ofA3 l

4 Rev: 012 3 4 observing the slope of the calculation for any percent airborne. For example, for the increasing lambda case the maximum airborne percent (about 13.1%) is reached at about 84 minutes. At 84 minutes the variable removal rate would be:

l 0 + 2 x (84 min -30 min)/ 90 min = 1.2 / hour The removal in terms ofYdhour would be:

1.2 x 13.1 = 15.7 %/ hour = 0.261 %-min This is almost exactly the addition rate (0.278 %-min) which explains the zero slope.

As another example, the constant removal rate case ends with an increasing slope of about 0.3 Yd 6 min or 0.05 Ydmin with an airborne percent of about 13.7%. The removal rate at this perce would be:

1/ hour x 13.7% x 1/60 hours / minute = 0.228 Ydmin The net increase would be:

0.278 %/ min (added) - 0.228 Ydmin (removed) = 0.05 %/ min The results in tenns of areas under the curves is shown on the figure. Note that the area under the constant removal curve is only 5% less than the area under the increasing removal curve. This shows that using a constant removal rate to approximate the increasing removal rate is acc at least for the case oflimited removal (i.e., about one per hour). The actual removal rate for Perry is calculated in the main body of the calculation to be 3.7E5 cfh/2.8E5orft3 about 1.3 per hour. A larger removal rate would increase this difference and make the constant removal rkte approximation increasingly non-conservative.

It is also of interest to note that either of the removal cases are about a factor of 1.

the no-removal case.

Attachment 0 PY.CE1/NRR.2076L Page 58 of 217 PSAT 04212H.d2 Page: ofA3 Rev: 012 3 4 l

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Atwnnwns u PY-CELWRR 2076L Page 99 of 217 l PSAT 04212H.02 / Page: B1 ofB11 l l l Rev:@l 2 3 4 APPENDIX B APPENDIX TITLE: i

          " Steam Generation Rate During Reflood" SAFETY-RELATED APPENDIX: Yes CALCULATION NUMBER:                 PSAT 04212H.02                                                          i CALCULATION TITLE:
         "Drywell Sweep-Out Rate and Related Thermal-Hydraulic Conditions inside Containment" I

I Purpose This appendix deals with steam generation during reflood when the core debris left in the core region (assumed to be 50% of the total)is quenched by the return to operation ofthe ECCS. The purpose of the appendix is to calculate (1) the steam produced and (2) the time required to reflood and quench the core debris. ~ i Approach POLESTAR l PROPRIETARY l

              .                                             Attachment 6 PY-CEl/NRR-2076L Pagc 60 of 217 PSAT 04212H.02   POLESTAR APPLIED TECHNOLOGY  Page: B2 ofB11 PROPRIETARY           Rev:@l 2 3 4 1

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ALWinfingill O PY CEl/NRR 2076L Page 62 of 217 PSAT 04212H.02 POLESTAR APPLIED TECHNOLOGY Page: B4 ofB11 3RO)R E~ARY l 0

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PSAT 04202H.12 NON-PROPRIETARY Page:1 of 6 Rev: 1234 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04202H.12 CALCULATION TITLE:

           " Calculation of Fraction of Containment Aerosol Deposited in Water" ORIGINATOR                  CHECKER                  IND REVIEWER Print /Sicn   Date          Print /Sicn  Date        Print /Sien  Date REVISION: 0J                   /g                                   aw ejcelfy/9 g                       9/p/pg 1       )                                           Y l

2 i 3 4 REASON FOR REVISION: l Nonconformance Ret 0 -InitialIssue N/A 1 2 3 l 4 l l \ l l

Attachment 6 PY CEl/NRR-2076L Page 63 of 217 PSAT 04212H.02 POLESTAR APPLIED TECHNOLOGY Page: B5 ofB11 Rev:hl 2 3 4 3RC)R E"ARY 1 1

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                                ,                                           Attacament o PY<EIMRR-2076L Page 65 of 217 PSAT 04212H.02  POLESTAR APPLIED TECHNOLOGY Page: B7 ofB11 Rev:hl 2 3 4
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Attachment 6 PY<ELWRR 2076L Page 67 of 217 PSAT 04212H.02 POLESTAR APPLIED TECHNOLOGY Pag 9 ofB11 Rev 1234 n 3Rv)R:...ARY 1 I i l l i 1

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Attachment 6 PY-CELHRR-2076L Page 70 of 217 POLESTAR PSAT 04212H.03 NON-PROPRIETARY Page: 1of7 l Rev:hl 2 3 4 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04212H.03 CALCULATION TITLE: 4

          " Ultimate Iodine Decontamination Factor for Perry DBA" ORIGINATOR                CHECKER                IND REVIEWER Pdnt/Sinn    Dan          Pdnt/ Sign     Dgg     Pdnt/Sinn   Dgg                   i REVISION: 0             -

eicztf D . E, 6 b, E. L-w i & Y & Mc ML alothc Mz _ +/uun 1 2 3 l ' 4 REASON FOR REVISION: l Nonconformance Rot 0 -InitialIssue N/A I 1 2 i 3 4

Attachment 6 PY-CEl/NRR 2076L Page 71 of 217 PSAT 04212H.03 Page: 2 of 7 1 Rev:@l 2 3 4 Table of Contents Section '1 East { Purpose 2 Methodology 2 Assumptions 2  ! References  : 3 Calculation 4 Results 7 Conclusions 7 Purpose i l The purpose of this calculation is to determine the maximum DF for iodine in containment that can be credited in the Perry drywell and containment for the purpose of applying the revised DBA source term ofReference 1 (assuming an adequate pH is maintained). I Methodology I The methodology of Referenceb is used to evaluate the maximum iodine DF tha (i.e., the minimum iodine DF that can be defended) assuming a pH of 7 is maintained. To confirm

                                                                                                                       )

the suppression pool pH, a separate calculation (Reference 3) has been performed. l Assumptions Assumption 1: i The suppression pool pH will be maintained at a value of 7 or above. Justification: The DF calculated herein is based on this minimum PH being maintained. According to Reference 4, Item 6.1, the initial suppression pool pH is not less than 6.0 at the start of the accident. The pH will rapidly increase as fission product cesium (the dominant fission product released by mass) in the form of CsOH (or other pH-basic chemical forms) is released to the containment and is deposited into

Attachment 6 PY-CEl/NRR.2076L Page 72 of 217 PSAT 04212H.03 Page: - 3 of 7 Rev:hl 2 3 4 the suppression pool concurrent with the radiciodine. Acids such as HNO 3 or hcl will be formed or deposited in the water later tending to lower the pH; but with operator action to add caustic and/or buffer, the pH will remain above 7. Reference 3 addresses pool pH during the course of the accident. Assumption 2: The water on the drywell floor and that in the suppression pool will mix , sufficiently to permit a uniform iodine concentration in the liquid phase to I be assumed. Justification: One approach evaluated in Reference 3 to maintaining an adequately high suppression pool pH is the injection of the SLCS sodium pentaborate as a buffer for any accident involving substantial core damage (such as the accidents identified in Reference 1 as the basis for the DBA source tenn). Mixing of this sodium pentaborate solution with all available water inside containment (which is a recognized necessity) would also provide mixing and a uniform distribution of the radioiodine between water on the floor of the drywell (or in the reactor vessel) and , that in the suppression pool. Even for pH-control options not involving SLCS I injection, uniform iodine distribution will result from spray operation, spillage of coolant from the break (and associated purge of water volumes in the drywell), and/or core steaming carrying any re-evolved iodine from drywell water volumes to the suppression pool or to the containment sprayed region. i References Reference 1: Soffer, L., et al., " Accident Source Terms for Light-Water Nuclear Power Plants", NUREG-1465, February 1995 Reference 2: Beahm, E. C., Lorenz, R. A., and Weber, C. F., " Iodine Evolution and pH Control", NUREG/CR-5950, November 1992 Reference 3: PSAT 04202H.11, " Suppression Pool pH for the Perry DBA", Revision 0 Reference 4: PSAT 04202U.03, " Design Data Base for Application of the Revised DBA Source Term to the CEI Perry Nuclear Power Plant", Revision 1 Reference 5: " Containment and NSSS Interface", General Electric Data Book 22A3759AL, Rev 2, March 29,1991 Reference 6: PSAT 04212H.02, "Drywell Sweep-Out Rate and Related Thermal Hydraulic Conditions inside Containment", Revision 0

                                                                                                                 ?

Anschment 6 PY-CEIMRR.2076L Page 73 of 217 l PSAT 04212H.03 Page: 4 of 7 Rev:@l 2 3 4  ! Calculation i From Reference 4, Item 6.6, the water volume which could ultimately dissolve the iodine released from the core is about 175000 ft' (suppression pool volume + RCS volume) = 175000 ft' x 28.3 liters /ft* = 4.95E6 liters. This volume ofwater corresponds to a mass of about 1.0E7 lbm at elevated temperatures. Of this water, about 6% comes from the reactor coolant (Reference 5, Section 3.2.1 gives vessel inventory as 5.6E5 !bm) and 19% from upper pool dump (Reference 4, Item 3.5) with a temperature of 110 F (Reference 5, Section 3.2.2). Assuming the remainder to be at the initial pool temperature of 95 F (Reference 5), we have the following estimate of post-  ! blowdown, post-upper pool dump suppression pool temperature (assuming also that the coolant is at saturation corresponding to the Reference 4, Item 8.4 pressure of 1060 psia) neglecting any i other heat addition: T,,i = (0.75)(95 F) + (0.06)(552 F) + (0.19)(110 F) = 125 F Reference 5, Table 3.3.1.3 indicates that the total stored energy of the steam, vessel, intemals, piping, and core is about 2E8 BTU at the start of the accident, and this energy would raise the pool temperature by about another 20 F if all of this were added prior to the peak pool temperature being reached. If hydrogen production / combustion adds another 2E8 BTU (see Reference 6) during core degradation and shortly after quench, that would raise the pool temperature by about another 20 F. It is reasonable to assume that all (or nearly all) of this energy would be added prior to the peak pool temperature being reached somewhere between two and four hours (the two hours is the approximate time of debris quench and the four hours is the time of the current peak taken from Reference 5, Figure 3.3.2.6). The difference between the decay power added and the heat removed by one RHR heat exchanger (assumed in Reference 6 to be in spray mode) up to this point in time (i.e., at two to four hours) can be estimated from Reference 5, Figure 3.3.2.8 as being about 4E8 BTU. This would raise the temperature an additional 40 F. The result would be a peak pool temperature of 205 F. In Reference 6, only thej pool water mass was considered and the peak pool temperature was estimated to be somewhat i higher;i.e.,212 F. This peak value will be assumed here as well, but only as a transient peak at two hours. This earlier time (over the range of two to four hours) is reasonable because the bulk of the hydrogen combustion (with igniters functioning) would be expected before this time. i It will be assumed that the pool temperature will begin to deviate from that of Reference 5, Figur 3.3.2.6 at the time of the start of S: = :f 9a significant fuel damage at about 1/2 hour (see R Reference 6) and that the peak (of 212 F) is reached at two hours. Beyond two hours, the rate at W which the temperature converges on the Reference 5, Figure 3.3.2.6 curve can be estimated by assuring that the product of the average temperature difference between the two curves times the mass of water in the pool times the heat capacity ofwater (i.e., the " excess" energy stored in the pool water over the convergence time) is equal to the average temperature difference between the two curves times the RHR heat exchanger removal constant times the time (i.e., the " excess" heat removal afforded by the higher temperature), or:

Atanment b . PY-CELWRR-2076L Page 74 of 217 l PSAT 04212H.03 Page: 5of7 i Rev:@l 2 3 4 j Time to converge = AT_/IE7 BTU /F) = 2.3E4 seconds j AT,(440 BTU /see-F) In actuality, this is a characteristic time, because this " excess" energy is removed exponentially. Assuming three characteristic times to converge, we have: j Time to converge = 69000 seconds When added to the assumed peak time of 7200 seconds, we have 76200 seconds or 0.9 days. For j simplicity, it will be assumed that the convergence occurs within one day. The assumed curve is ) presented as Exhibit 1, a mark-up of Figure 3.3.2.6 of Reference 5. From Reference 4, Item 1.3, i for the CEI high bum-up core, the core iodine mass is approximately 10.5 grams per Mw. From Reference 4, Item 1.1 the core power is 3758 Mw(t). This means the iodine mass is approximately 3.95E4 grams. The iodine core inventory (most ofwhich is stable or near-stable iodine) would be approximately SE-3 grams per liter if 100 percent were released. The Reference I source term, however, involves only a 30% release ofiodine for a BWR; and therefore, the iodine concentration (taken to be I-) is 2.4E-3 grams per liter or about 1.9E-5 gm-atoms per lit From Reference 2 ifH+ = 10 '" (i.e., pH = 7.0 - see Assumption 1), then for I = 1.9E-5: 12 = (H+)2(I')2/ [d + e(H')] where: d = 4.22E-14, and - e = 1.47E-9 12 in the liquid phase = 8.5E-11 gm-moles / liter I in the liquid phase = 1.7E-10 gm-atoms / liter Since l' in the liquid phase = 1.9E-5 gram-atoms / liter, then I/I = 9E-6 in the liquid phase. From Reference 2, the panition coefficient is: logia PC(I) = 6.29 - 0.0149T, where T is in K From Reference 4, item 8.5, the maximum pool temperature is 212 F = 373 K Then: PC(minimum) = 5.4 (i.e., the minimum concentration ofiodine, as tI in the liquid phase is 5.4 times that in the gas phase. A lower temperature would yield a higher PC) Since the gas phase volume = volume of drywell + volume of containment

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Attachment b , PY-CEl/NRR.2076L Page 76 of 217 i PSAT 04212H.03 Page 7 of 7  ; Rev: 1234

                                        ' = (2.8E5 + 1.165E6) ft'(from Reference 4, Items 3.1, 3.2, and 3.3)
                                          = 1.445E6 ft' And since the volume of the liquid phase is 175000 ft', the ratio of the gas phase volume to the liquid phase volume is 8.3:1. This means that once removed from the gas phase, the mass of                                      '

iodine, as2 1, in the liquid phase would never be less than (5.4/8.3 = 0.65) that in the gas phase. Since the maximum mass ratio ofI/1-in the liquid phase is 9E-6, the maximum mass ratio ofIin the gas phase to I in the liquid phase is 9E-6/0.65 = 1.4E-5. This means that the minimum ultimate DF ofiodine (i.e., ofmolecular 2 1 in the gas phase) for this system is approximately l 1/1.4E-5 = 70000 if the iodine can be removed from the gas phase initially. Reference 1 indicates that 0.0015 of the iodine released to containment must be conside organic. This fraction is 100 times gret.ter than the fraction of the iodine released which could re-evolve u 12as calculated above. Moreover, the suppression pool temperature would reach 212F as a post-accident peak for only a short time and only within the first few hours of the accident as a result of the additional energy from hydrogen production (see above and Reference 6). Therefore; as a practical matter, there is no need to limit the removal of inorganic iodine in the analysis of the revised DBA source term for Perry. The organic iodine (which is not removed by deposition or pool scrubbing) will always dominate. By Assumption 2 the water in the drywell ' and that in the suppression pool will have the same pH and radioiodine concentration; therefore, the concentration ratio 2(I in the gas phase to l'in the liquid phase) will be the same. This means a that the 21 concentration in the gas phase of the containment and the drywell will be the same, and a single control volume model of the lower containment /drywell is acceptable in the long-term from the standpoint of the potential for iodine re-evolution. Results The minimum justifiable long-term DF for elemental iodine in both the drywell and the containment is 70000. If this degree of decontamination can be achieved by removal mechanisms then the associated re-evolved 2 1 concentration will not exceed that of the organic iodine in the Reference I source term specification. Conclusions There is no need to limit elemental iodine removal in the analyses supporting application of the revised DBA source term to Perry.

Attachment b P%CElNRR-2076L ^ POLESTAR PSAT 04202H.05 NON-PROPRIETARY e: 1 of 7 Re 234 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04202H.05 CALCULATION TITLE:

      " Aerosol Decay Rates (Lambdas) in Containment with Spray" ORIGINATOR            CHECKER                    IND REVIEWER Print /Sien Dge       Print /Sien Dale           Print /Sien Dde Ruw     Sve 't[QIfL  *Tn *t    l~  ,

REVISION: 0g ,1 @h6 w Mekc4f l M 1 2 l I l

                                                            ~

3 4 REASON FOR REVISION: Nonconformance Ro, t 0 - Initial Issue N/A i 1 2 3 4

Anachmem 0

 .                                                                                    PY-CEl/NRR 2076L Page 78 of 217 PSAT 04202H.05                                                            P e: 2 of 7 Re    1234 Table of Contents Section Page Purpose                                                                       2 Methodology                                                                   2 Assumptions                                                                   3 Calculation                                                                   5 Results 6

References 7 Appendices: A "STARNAUA Input Files" (2 pages) POLESTAR PROPRIETARY B "STARNAUA Plot File" (6 pages) POLESTAR PROPRIETARY C "STARNAUA Output File" (33 pages) POLESTAR PROPRIETARY Purpose The purpose of this analysis is to calculate the aerosol decay (removal) rates in the containment due to sprays that remove fission and non-fission product aerosols from the containment atmosphere. Methodology The problem to be solved can be described as follows: During a design base accident (DBA), fission product aerosols are released from the damaged core into the drywell, together with significant amounts of steam and non-condensable gases. The steam and gases, as well as the heat transfer to the gases in the drywell, will cause an increase in drywell pressure and result in a significant sweeping flow into the unsprayed region of the containment through the pathways that connect the drywell and the unsprayed region, which will transport aerosol particles. Leakage flows into the main steam lines through the MSIVs are also expected. In addition, there will be introduction of aerosol into the sprayed portion of the containment as a result of the significant exchange flows between the sprayed i and unsprayed portions of the containment. The spray droplets will act to remove 1 l 1

Attachment 6

• PY-CELNRR-2076L Page 79 of 217 PSAT 04202H.05 P e: 3 of 7 Rev 1234 aerosol particles by means of several collection mechanisms, including impaction, interception and diffusion.

Based on the mass conservation law, the suspended aerosol mass in the containment is governed by the following equation: , 1 Suspended mass = Injected mass - Leaked mass - Removed mass The injected mass of aerosols into the containment include both fission and non-fission product aerosols from the drywell. The leaked mass accounts for the aerosols that leak from the containment to the environment through normal containment leakage pathways such as penetrations. Removal processes include sedimentation, diffusiophoresis and thermophoresis, and interactions between spray droplets and aerosol particles. All of the quantities in the equation can be functions of time. As will be seen, the leakage term is set equal to zero, The above equation is solved by the STARNAUA Rev.1 (STARNAUA Version 1.01) code [1] in which the aerosol removal processes mentioned above are modeled, and the suspended aerosol concentration is calculated for the specified timing and 3 rates of injected aerosols and the specified aerosol leakage rate to the environment. ' Removal by sprays is also explicitly modeled in STARNAUA Rev. I at the user's option. . j

                                                                                                             ?

Assumptions Assumption 1: The containment is well-mixed during the entire time period of the accident. Justification: Given the fact that steam, non-condensable gases (e.g., hydrogen)  ; and fission product gases and aerosols are entering the i containment atmosphere, while significant heat and mass transfers are going on in the containment, this assumption is reasonable. Assumption 2: Condensation and sensible heat transfer onto the containment walls are not considered. Justification: This assumption is conservative in the sense that it will result in a smaller aerosol decay rate. Assumption 3: Hygroscopicity of aerosols is ignored and relative humidity in the drywell is assumed to be 98% through-out the accident. Justification: The cesium and iodine species (mostly Csl and CsOH) released into the containment are likely to be soluble and the hygroscopic

maanam o PY-CEl/NRR-2076L Page 80 of 217 PSAT 04202H.05 P a: 4 of 7 i Re 1234 1 effect on the growth of the soluble aerosols is significant, which . j enhances the removal of such aerosols by increasing ' sedimentation. The assumption to ignore the hygroscopicity will thus be conservative. The relative humidity is immaterial, since l L both the hygroscopic effect on aerosol growth and diffusiophoresis (which is indirectly affected by the relative humidity) are not considered. Neglecting diffusiophoresis is also conservative. Assumption 4: The leakage aerosol from the drywell, which is the source to the containment, can be characterized as a single specie with an approximately average density and molecular weight of the l various species used in the drywell calculation, and geometric  ! mean radius and geometric standard deviation equal to 0.22 l micrometers and 1.81, respectively, (i.e., those of the aerosol source in the drywell calculation). Justification: The spray removal efficiency is not sensitive to properties of the aerosol such as density and molecular weight, and the calculation is conservative when the chosen values of geometric mean radius and standard deviation are used, as compared with the actual values for the leaked aerosol from the drywell. Assumption 5: Diffusiophoresis of aerosol to spray droplets due to condensation onto the droplets is neglected. Justification: It contributes little to the spray collection efficiency (2), and its neglect is conservative. Assumption 6: The temperature of the spray is input as 60 *C. Justification: Since condensation (or evaporation) onto the droplets is not considered (see assumption 5), the input value of the droplet temperature is immaterial. i Assumption 7: The leak rate from the containment to the environment is set equal to zero. Justification: The leak rate is less than 0.000083 hr-1 [3]; the spray lambdas are i 1-10 hr-1. Thus the leak rate can be ignored. l

Anacnment O , PY-CELNRR 2076L Page 81 of 217 PSAT 04202H.05 POLESTAR PROPRIETARY P e: 5 of 7 Rev 0 234 Calculation l l l l l

Attachment o P%CE1/NRR-2076L Page 82 of 217 I l PSAT 04202H.05 POLESTAR PROPRIETARY P ge: 6 of 7 l l Rev 0 1 2 3 4 l 1 l l l I 1 l l j 1 l l l l 0 l l

atasunon v PY{El/NRR-2076L Page 83 of 217 PSAT 04202H.05 POLESTAR PROPRIETARY Pagm 7 of 7 Resg1234 0 l l l l l l x

Attuunem o rY CEINRR-2076L [ l POLESTAR rue sor2n PSAT 04202H.04 NON-PROPRIETARY P e:1 of12 Rev: 1234 CALCULATION TITLE PAGE i l CALCULATION NUMBER: PSAT 04202H.04 CALCULATION TITLE:

           " Aerosol Decay Rates (Lambda) in Drywell" ORIGINATOR               CHECKER                   IND REVIEWER i

Print /Sien Date Print /Sicn Date Print /Sien Date

t. (2 u k tsL Si, 4l9{9 L  % Sk Yfl9L REVISION: 0 Y[9/9f l

1 2 l I l 3 - 4 l l REASON FOR REVISION: Nonconformance Rot l - l 0 -InitialIssue N/A j 1 t 1 2 3 4 i l

__ - -. . . - _ . - _ . - - _ . - - . _ _ _ ~ . Attachment 6

 ..                                                                                                 PY-CU!NRR.2076L 1                                                                                                    Pcge 85 of 217 PSAT 04202H.04 Pa e: 2 of12 Res . 0     234

Table of Contents Section ,

Eage Purpose 4 1 2 Methodology > 2 ,, , , Assumptions 3 a

References t:

7 a , Calculation a 8 1 Results si i 11 ct Appendices: A "Drywell Leakage Rates through MSIVs"(3 pages) m . P3i B "STARNAUA Input Files"(3 pages) er  ! POLESTAR PROPRIETARY rat J C "STARNAUA Plot File"(19 pages) ed POLESTAR. PROPRIETARY D "STARNAUA Output File"(45 pages) POLESTAR PROPRIETARY ,th Purpose (eC The purpose of this analysis is to calculate the aerosol decay e (removal) m, drywell due to natural removal mechanisms that remove fission and product aerosols from the drywell atmosphere, - no

s a fic Methodology The problem to be solved can be described as follows: ible damaged core into the drywell, together with sign -

sers condensable gases. The steam and gases, as well as the heat transfer to ate. flow into the unsprayed region of the containmen .soh the drywell and the unsprayed region. Leakage flows into rough the main steam 3e 9; lin the MSIVs is also expected. All these flows will dilute or remove n the the aerosols i l l 1

Attcchment 6 PY-CEl/NRR-2076L Paee 86 of 217 PSAT 04202H.04 Pa e: 3 of12 Res . 1234 drywell and, at the same time, the aerosols will experience other removal processes, such as sedimentation, diffusiophoresis, thermophoresis, etc., the rates of which are to be determined in this analysis. Based on the mass conservation law, the suspended aerosol mass in the drywell is governed by the following equation: Suspended mass = Injected mass - Leaked mass - Removed mass The injected mass of aerosols include both fission and non-fission product aerosols from the primary system. The leaked mass accounts for the aerosols entrained in the leak flows through several leakage pathways, such as the pathways that connect the drywell and the unsprayed region of the contamment and the MSIV leakage, and the removed mass represents the aerosols deposited on the surfaces in the drywell due to sedimentation, diffusiophoresis, thermophoresis, and other aerosol removal processes. All of the quantities in the equation can be functions of time. I The above equation is solved by the STARNAUA Rev.1 (STARNAUA Version 1.01) code [ reference 1] in which the aerosol removal processes mentioned above are modeled, and the suspended aerosol concentration is calculated for the specified tunmg and rates of injected aerosols and the specified aerosolleakage rates through different pathways. Assumptions Assumption 1: The drywell is well-mixed during the entire time period of the accident. Justification: Given the fact that steam, non-condensable gases (e.g., hydrogen) and fission product gases and aerosols are blowing into the drywell atmosphere, while significant heat and mass transfers are going on in the drywell, this assumption is reasonable. Assumption 2: Condensation and sensible heat transfer onto the drywell walls are not considered. l Justification: This assumption is conservative in the sense that it will result in a smaller aerosol decay rate. Assumption 3: Hygroscopicity of aerosols is ignored and relative humidity in the drywell is assumed to be 98% throughout the accident.

Auccnment 0 I PY-CELNRR-2076L ; Paac 87 of 217 ' PSAT 04202H.04 Pa e,: 4 of12 Re . 0 234 Justification: The cesium and iodine species (mostly Csl and CsOH) released into the drywell are likely to be soluble and the hygroscopic effect on I the growth of the soluble aerosols is significant, which enhances the j removal of such aerosols by increasing sedimentation. The s assumption to ignore the hygroscopicity will then be conservative.  ! A relative humidity of 98%, on the other hand, has no impact on  ! this analysis since both the hygroscopic effect on aerosol growth l and diffusiophoresis (that is indirectly affected by the relative humidity) are not considered. Neglecting diffusiophoresis is also conservative. Assumption 4: The release fractions of the fission products are obtained from NUREG-1465 [ reference 2] (see Tables 3.8 and 3.12) and the core l inventories are from reference 3, all of which are summarized in  ! Table 1 below. The timings are also obtained from NUREG-1465. Two phases of the fission product release are assumed. First, the gap release starts at 30 seconds after the initiation of the accident  ! and lasts 1800 seconds. It is then followed by the early in-vessel  ! release that lasts 1.5 hours. i According to NUREG-1465, the iodine specie released to the  ! containment is in the forms of particulate ahd gases (organic and elemental). 95% of the iodine released to the containment is aerosol,

                 - while 5% is gases. Of the iodine gases,97% are elemental and 3%

are organic. Organic iodine behaves like a noble gas, so it is l assumed to be non-removable. Elemental iodine, on the other hand, i tends to deposit on aerosols or other surfaces, and is assumed to be  ! removed similarly to the aerosols. Assumption 5: The amount of non-fission product aerosols released to the containment is the same as that of fission product aerosols (i.e., about 129 kg). They are released uniformly during the in-vessel release period, similar to the fission product aerosol release. The average density of the non-fission product aerosols is assumed to be 5.6 g/cm3, Justification: The assumption that the ratio of fission to non-fission in-vessel releases is 1:1 is obtained from reference 4. It should be pointed out that it was mentioned in NUREG-1465 that about 780 kg of in-vessel non-fission masses was calculated in NUREG-09% for one Peach Bottom sequence. Since the Peach Bottom reactor is not too different from the Perry reactor that is analyzed here, the same

Attachment 6 PY-CEl/NRR-2076L Page 88 of 217 PSAT 04202H.04 P e: 5 of12 Res 1234 order of magnitude of non-fission product release is expected. But, the non-fission product release that we assume is only 20% of what was calculated in NUREG-0956. Our assumption should then be conservative, since a larger amount of non-fission product release will enhance overall aerosol agglomeration and, therefore, increase aerosol sedimentation. As for the density, most of the non-fission product aerosols are Zr, Fe2O3 and UO2 species whose densities are 6.4, 5.24 and 10.09 g/cm3, respectively. So, a density of 5.6 g/cm3 for the non-fission product aerosols represents a conservative value, considering that the Zr inventory in the core is almost three times higher than that of the iron (table 4.5, reference 5). Table 1. Fission Product Releases into Containment 1 Gap Early Core Group Title Elementsin group releasel in-vessel inventory releasel (kg) 1 Noble Gases Xe,Kr 0.05 0.95 887 2 Halogens 1, Br 0.05 0.25 41.1 3 Alkali Metals Cs, Rb 0.05 0.20 531 4 Tellurium Group Te,Sb,Se 0 0.05 91.1 5 Barium, Strontium Ba,Sr 0 0.02 384 6 Noble Metals Ru, Rh, Mo, Tc 0 0.0025 1090 7 Lanthanides La, Zr, Nd, Eu, Nb, 0 0.0002 1830 Pm, Pr, Sm, Y 8 Cerium Group Ce 0 0.0005 436 1 Fractions of core inventories. Assumption 6: The flow exchange between the drywell and the unsprayed region of the containment is ignored after containment heat removal (or reflood)is over. Justification: According to PSAT 04202U.03 [ reference 3] (Items 3.9 and 3.10), l before 7484 seconds the flow exchange between the drywell and the unsprayed region of the containment is only in one direction, i.e., l from the drywell to the unsprayed region of the containment. So, , i I

_ _ . . . . , _ _ _ . . - - - - - - -~- Attachment b PY.CELHRR-20*l6L i Ptge 89 of 217 PSAT 04202H.04 Pa e: 6 of12 l Rev.0 1 2 3 4 the flow can be considered as a leakage flow out of the drywell. After 7484 seconds the flow from the drywell to the unsprayed region of the containment is balanced by the flow from the l unsprayed region of the containment to the drywell. To fully model the two-way flow exchange, the calculation of aerosol behavior in both the drywell and the unsprayed region of the containment

needs to be conducted in parallel, which will be very difficult. This assumption, evidently, simplifies the problem. The implication of the effect on the drywell aerosol decay rate calculation needs to be discussed when the result is used. Nevertheless, it should be pointed out that the suspended aerosol concentration in the l

unsprayed region of the containment is very likely to be less than that in the drywell because of the combination of the spray removal of aerosols in the sprayed region of the containment and the existence of large exchange flow rates between both the spraye.d and the unsprayed regions of the containment. Assumption 7: Aerosol size distribution is lognormal, with a geometric mean radius of 0.22 micron and a geometric standard deviation of 1.81. Justification: As discussed in Reference 6 (page 12-13), the overwhelming majority of aeror.ols are observed to have a lognormal size distribution. It is also a common practice to assume such a distribution for the fission product aerosols in nuclear safety . studis. A lognormal distribution is defined by the geometric mean radius and the geometric standard deviation. The values for them to be used in this calculation are based on an analysis of data from several degraded fuel expenments [ reference 7]. It should be { pointed out that the aerosols size distribution specified here yields a mass mean diameter of about 1.3 microns. For comparison, the mass mean diameters used in NUREG/CR-5966 [ reference 8) range from 1.5 to 5.5 microns and the geometric standard deviations range from 1.6 to 3.7 (see page 84). Thus, our assumption is evidently at the lower end of what were used in reference 8, and is  !

                                                  . thus conservative compared with reference 8.

l l t

Attachment b ' PY-CELHRR-2076L Page 90 of 217 PSAT 04202H.04 P e: 7 of12 Re 1234 Reference Reference 1: PSAT C101.02, "STARNAUA - A Code for Evaluating Severe Accident Aerosol Behavior in Nuclear Power Plant Containment: A Validation and Verification Report, Revision 1, February 1996 Reference 2: Soffer, L., et al., " Accident Source Terms for Light-Water Nuclear Power Plants", NUREG-1465, February 1995 Reference 3: PSAT 04202U.03, " Dose Calculation Data Base For Application of the Revised DBA Source Term to the CEI Perry Nuclear Power Plant", Revision 0 Reference 4: Letter from J. C. DeVine, Jr. to Leonard Soffer, " Additional ALWR Program comments on the NRC draft source term report, NUREG 1465", July 30,1993 Reference 5: Denning, R. S., et al., "Radionuclide Release Calculations for Selected Severe Accident Scenarios, BWR, Mark I Design", NUREG/CR-4624, BMI-2139, Vol.1, July 1986 Reference 6: Fuchs, N. A., "The Mechanics of Aerosols",' Dovers Publications, Inc., New York,1964 Reference 7: Polestar Memo from R. Sher to D. E.12 aver, " Aerosol Source Size Parameters", July 28,1995 Reference 8: Powers, D. A. and Burson, S. B., "A Simplified Model of Aerosol Removal by Containment Sprays", NUREG/CR-5966, SAND 92-2689, June 1993 i i i i 1 l i r- - - - - - . , - , - - ~ - - -

no........ PY-CEL'NRR-2076L Page 91 of 217 NAT 04202H.04 POLESTAR PROPRIETARY Pa e: 8 of12 Rev 0 234 Calculation l 6

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Attachment b

• PY-CEl/NRR-2076L Page 93 of 217 PSAT 04202H.04 POLESTAR PROPRIETARY Pa(e:10 of12 RevU012 3 4 I

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m aianuao PY-CEl/NRR-2076L Page 94 of 217 PSAT 04202H.04 POLESTAR PROPRIETARY Pa e:11 of12 Rev 0 1 2 3 4 4 5 l e

Attachment 6 j

 -                                                                                   PY-CEl/NRR-2076L Page 05 of 217 PSAT 04202H.04               POLESTAR PROPRIETARY                       Pa e:12 of12 Res 01 234 l

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Attachment 6 .. PY-CEIMRR-2076L Page 96 of 217 POLESTAR PSAT 04212H.06 NON-PROPRIETARY Page 1 of 8 Rev:@l 2 3 4 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04212H.06 CALCULATION TITLE:

        " Mixing between the Sprayed and Unsprayed Portions of the Perry Containment" QRIGINATOR                 CHECKER                      IND REVIEWER Print / Sign    Date       Print / Sign   Rats          Print /Sicn    Date REVISION: 0                ,defCelE        "' #     "
                                           &GW Wl%                                     9h1%

• JA{9fG 2

3 4 REASON FOR REVISION: Nonconformance Rqt 0 -InitialIssue N/A 1 2 3 4 1 I

Attachment 6 PY-CEIMRR-2076L Page 97 of 217 PSAT 04212H.06 Page 2 of 8 Rev:$12 3 4 Table of Contents Section Eage Purpose 2 Methodology 2 Assumptions 3 References 6 Calculation 6 Results 7 Conclusions 8 Purpose The purpose of this calculation is to determine time-dependent mixing rates betw and unsprayed portions of the Perry contamment. i Methodology i i Spraying of the upper containment atmosphere will cool that atmosphere relative to that o lower containment and wetwell. The lower containment /wetwell atmosphere is expo; suppression pool (which is hotter than the spray temperature) and is also more likely to rej any suppression pool bypass (due to greater exposure to the drywell pressure boundary). B on the cooling effects of the spray (even with the steam condensation effect conserva ' neglected - see Assumption 1), an expression will be developed which will relate the driven flow between the denser atmosphere of the sprayed region and the less den of the unsprayed region to the temperature of the suppression pool (used to characterize the temperature of the wetwell/ lower containment) and the temperature of the spray (used to characterize the temperature of the sprayed region). Suppression pool bypass is negle Assumption 2). The expression for mixing will be written in terms of a controlling " orifice" area that limits the flow between the sprayed and unsprayed regions. As applied to the Perry containment, this a is that of the equipment opening at the outer periphery of the refueling floor. As the spray

Attachment 6

 ..                                                                                                       PY-CEl/NRR-2076L Page 98 of 217 PSAT 04212H.06                                                                          Page 3 of 8 i

Rev:h 2 3 4 droplets transfer their momentum to the sprayed region atmosphere, this opening represents the longest, unimpeded vertical flowpath for sustained interaction between the falling spray droplets and the atmosphere, creating a natural downward flow (due to momentum exchange) to be supplemented by the density-driven component of the circulation potential. While the momentum exchange, itself, is conservatively neglected in quantifying the mixing rate (see Assumption 3), the geometry of the Perry containment will encourage downward flow through this control'ing flow area with the retum flow re-entering the sprayed region through multiple flowpaths in areas protected from direct spray impingement. Assumptions Assumption 1: Steam condensation in the sprayed region may be neglected in determining the mixing rate between the sprayed and unsprayed regions of the containment. Justification: The effect of steam in the unsprayed region (which then mixes with the sprayed region atmosphere and is condensed there) is to increase the density difference between the two regions, tending to increase the mixing rate. Assumption 2: Suppression pool bypass may be neglected in detennining the mixing rate between the sprayed and unsprayed regions of the containment. Justification: The effect of suppression pool bypass is to increase the heat load in the unsprayed { region. A large and positive dT/dt (rate of temperature change in the unsprayed region) or a large and negative dT/dt (rate of temperature change in the sprayed region) contributes to increased mixing. Assumption 3: Momentum exchange between the spray droplets and the containment atmosphere may be neglected in determining the mixing rate between the sprayed and unsprayed regions of the contamment. Justification: Momentum exchange can be appreciable in creating forces on the containment atmosphere that must be balanced by recirculation. Consider that the terminal velocity for a 1 mm droplet is about 20 fps (600 cm/sec at atmospheric pressure from Chapter 10, Figure 1 of Reference 2). For a spray flowrate of 5250 gpm and a minimum fall height of about 40 feet (Reference 3 Items 3.25 and 7.1), there would be about 2 seconds of spray flow or 175 gallons airborne at any time. The weight of this water is about 1450 lbf, and it is this force that would have to be reacted by air drag associated with the movement of the recirculating atmosphere. The average pressure created by this weight of water across the operating floor

Attachment 6

• PY-CEl/NRR-2076L Page 99 of 217 PSAT 04212H.06 Page 4 of 8 Rev:hl 2 3 4 would be about 1450 lbf/11310 ft2 (Item 7.4 of Reference 3) or roughly 0.13 psf or 0.001 psi. In certain areas where the fall height might be greater, the local pressure could be even higher.

The 0.001 psi may seem like a very small pressure, but it is equivalent to about 0.03" of water, and 0.03" ofwater is the velocity pressure corresponding to about seven MPH or 600 fpm (Reference 2, Chapter 19, Figure 1). With a mixing length of about 400 feet around the containment, a 600 fpm velocity would recirculate the containment atmosphere about once every 0.67 minutes or 90 volumes per hour. Although this is a simplistic assessment and does not take into account drag on the recirculating air due to obstacles in the path of the air flow or the fact that in some locations the downward pressure may act to resist flow created by an even greater downward pressure in other locations, it dose illustrate the magnitude of the effect that is being neglected. Assumption 4: Structural heat sinks in the containment may be neglected in determining the mixing rate between the sprayed and unsprayed regions of the containment. Justification: Most of the structural heat sinks in the containment are in the unsprayed region. Once sprays and the containment cooldown begins, these heat sinks will become heat sources low in the containment, tending to promote natural circulation. Assumption 5: Introduction of hydrogen through the vent system, through safety / relief valve discharge, or through pool bypass may be neg!ected in determining the mixing rate between the sprayed and unsprayed rep, ions of the containment. Justification: As noted in Reference 1, 50% cladding oxidation would result in the decomposition (and eventual recombination in containment) of about 4E5 g-moles of steam. The recombination would require about 2E5 g-moles or 6.4E3 kg of O 2 in the containment. At the start of the accident (after the purge of the drywell), the unsprayed region (about 6.8E5 ft' + 60% of the 2.8E5 drywell volume - Reference 3 Items 3.1,3.2, and 3.3) would contain about 64000 lbm of air or about 12800 lbm of oxygen.' This quantity of oxygen represents about 90% of that needed to recombine the hydrogen even without any exchange of atmosphere with the sprayed region. With igniters functioning in the wetwell/ lower containment, and the bulk of the hydrogen entering the wetwell/ lower containment prior to entering the upper containment, one would expect the bulk of the hydrogen combustion to occur in the lower region. This combustion would encourage even more rapid mixing between the sprayed and unsprayed regions.

                        .     --                               ~

Attachment 6 PY-CE!/NRR-2076L Page 100 of 217 PSAT 04212H.06 Page 5 of 8 Rev:@l 2 3 4 While bypassing steam could potentially inert the wetwell and lower containment (if steam generation were many times greater than the conservatively low values of Reference I and the bypass area were of the order of the design value) and force combustion in the upper containment, this introduction of steam into the wetwell and lower containment would encourage (and the associated transport of hydrogen would be indicative of) good containment mixing. Fission product aerosols would tend to follow the hydrogen-rich flow from the vessel /drywell to the upper containment. Assumption 6: The temperature of the wetwell/ lower containtnent is that of the suppression pool. Justification: Given that there is no bypass or hydrogen combustion considered, the temperature of the lower containment can reasonably be assumed to be that of the suppression pool once the effects of the initial compression (due to air purged from the drywell at the beginning of the accident) have abated. Assumption 7: The temperature of the upper containment is the average of the j temperature of the wetwell/ lower comainment and the inlet temperature of the spray. Justification: The exact temperature in the upper containment will be determined by the heat i load of the air being recirculated in from the wetwell/ lower containment and the inlet temperature of the spray. If the recirculation is very high, then the temperature of the upper containment will be closer to that of the wetwell/ lower containment. If the recirculation is very low, then the temperature of the upper containment will be closer to that of the spray inlet. Assuming an average temperature will lead to a moderate degree of recirculation which should be self-consistent with the temperature assumed. Assumption 8: A low containment temperature is conservative in determining the mixing rate between the sprayed and unsprayed regions of the containment. Justification: The higher the unsprayed region temperature (corresponding to the temperature of the suppression pool) the greater the temperature difference between the spray inlet temperature and the pool temperature and, therefore, between the sprayed and unsprayed regions and the greater the mixing. Also, consider that: r. T, (temperature of the unsprayed region) = T, (temperature of the pool) T, (temperature of the sprayed region) = (T, + T,)/2

Att chment 6 PY.CEl/NRR.2076L Page 101 of 217 j PSAT 04212H.06 Page 6 of 8 l Rev:@l 2 3 4  ! Then recalling that T,yy = T,- C(T,- To n,,m ) where C and T o no,m are I constants, dT/dt = dT,/dt and dT/dt = (1-C/2)dT,/dt i This means that the rate of change of the unsprayed region temperature will be greater than the rate of change of the sprayed region temperature. The two  ; temperatures will converge during the cooldown and will be the same when T, = 1 Toim, = 85 F (Reference 3, Item 9.4) l l References  ! Reference 1: PSAT 04212H.02, "Drywell Sweep-Out Rate and Related Thermal-Hydraulic l Conditions inside Containment", Revision 0 Reference 2: American Society of Heating, Refrigerating, and Air Conditioning Engmeers, Handbook of Fundamentals, New York,1972 Reference 3: PSAT 04202U.03. " Dose Calculation Data Base for Application of the Revised Source Term to the CEI Perry Nuclear Power Plant", Reyision 0 1 Calculation POLESTAR PROPRIETARY )

Atuchment 6 . PY<El/NRR-2076L Page 102 of 217 l PSAT 04212H.06 POLESTAR APPLIED TECHNOLOGY Page 7 of 8 l PROPRIETARY Rev:@l 2 3 4 i

Attachment b . PY-CEl/NRR-2076L Page 103 of 217 PSAT 04212H.06 POLESTAR APPLIED TECHNOLOGY Page 8 of 8 PROPRIETARY Rev:h12 3 4 Conclusions i l

Attachment 6 - PY-CEIMRR-2076L POLESTAR r .ma2n PSAT 04202H.07 NON-PROPRIETARY Pa :1 of15 Rev 1234 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04202H.07 CALCULATION TITLE:

       " Main Steam Line Heat Transfer Analysis" ORIGINATOR               CHECKER                IND REVIEWER Print / Sign Date        Print /Sicn Date       Print /Sinn  Date REVISION: 0 J""              N      b g                     kh                      k-                             l 1                                                                               .

1 2  ; 3 1 4 REASON FOR REVISION: Nonconformance Rot 0 -InitialIssue N/A 1 < 2 3 4

Attachment 6 5 PY-CEI/NRR 2076L l Page 105 of217 PSAT 04202H.07 Pa e: 2 of15  ; Rev.0 234 Table of Contents Section E!ULe Purpose 2 Introduction 2 Assumptions 4 Modeling 6 References 10

   - Calculation 11 Results 13 Exhibit 1 15 Purpose The object of this heat transfer analysis is to calculate the temperature profile along section of the process pipe of interest to us (i.e., between the inboard and outboard MSIVs). The results of this analysis will then be used to determine the axial natural circulation velocity induced by the axial temperature variation. Since the process pi insulated and its temperature is uniform at the start of the isolation, the temperature variation will only be significant if there exist significant localized heat losses.

Introduction In the section of the process pipe of interest to us, two locations at which significant hea losses are possible are identified. One is between the outboard MSIV and the shield building wall where the guard pipe is welded to the process. pipe. It is shown in Figu 1_at the point marked " Welding Location". The other is where the process clamp is . located. At this location six lugs that are physically connected to the process pipe an six lubrite plugs that are physically connected to the guard pipe are separated by a ve narrow gap (only about 0.%" according to Reference 1), as shown in Figure 2 (only one device is shown). Because most of the guard pipe is directly exposed to the atmosphe the guard pipe becomes a heat sink to the process pipe at those locations mentioned above. However, at the welding location, the guard pipe is insulated all the way to the  ; inner face of the shield building wall, the heat transferred from the process pipe to the i J

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PY.CEl/NRR-2076L Page 106 of 217 PSAT 04202H.07 Pa e: 3 of 15 i Rev 234 guard pipe will be CV SB Wall Insulated Guard Pipe i conducted ' Process Ciamp weldrig L cation through this Guard Pipe insulated section I before bemg

 " released" to the atmosphere.        At                      l                                                     os usiv the process clamp          Insulated Process Pipe                                                                   l i location, on the                                                              95 ft                                 1

other hand, the '

i heat transferred Figure 1. Process pipe Schematics i from the process pipe to the guard pipe has to go through the process clamp, the lug welded to the process clamp, the gap, the lubrite plug press fit into the bolt, and the bolt, as shown in Figure 2. Thermal resistance is expected at all the interfaces among them. Though, the process pipes are insulated, heat loss from the process pipe through the insulation rnaterial may not be negligible for the time frame in consideration (i.e., from 1 to 24 hours). l 1 Bot ) j l l Process Clamp

                                            \        j, l
                                                   ===

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4 Figure 2. Schematics of Joint of process pipe and guard pipe at process clamp Location 1

                                                                                             ~ . . . . . . . .

PY-CEl/NRR-2076L Page 107 of 217 PSAT 04202H.07 Pa e: 4 of15 j Rev 012 3 4 j Assumptions To analyze the heat transfer process, the following assumptions are made. ! Assumption 1: Heat loss through the insulation material from the process pipe is i uniform over the entire section of the pipe under analysis. The heat i transfer coefficient for the heat loss is assumed to be a constant and

is obtained from Reference 2 (see below).

Justification: The uniformity assumption for the heat loss through the insulation material is based on the fact that the pipe is uniformly insulated and, in addition, any small difference resulting from a possible inhomogeneous insulation will be smoothed out by the conduction in the pipe since the conduction resistance in a metal pipe is always l much smaller than the thermal resistance in the insulated material. A study on uniform cooling of the process pipe has been reported ' in Reference 2; as shown in Exhibit 1, the main steam line-temperature decreases as a function of time. The plot is used to derive a heat transfer coefficient through the insulation material in this analysis. Doing so is appropriate since, first of all, the main steam line insulation will not be too different from one nuclear plant to another in the US. Secondly, it is the temperature difference (between the temperature at any location of the process pipe and that at the hottest spot of the pipe) that is of interest to us, which will not be significantly affected by variations in a uniform cooling calculation. Assumption 2: The insulated portion of the guard pipe is treated as an extension of the process pipe at the welding location. Justification: The materials for the process pipe and the guard pipe are not different as far as the heat transfer is concerned. The difference between their cross-section areas is negligible, too. Assumption 3: Heat transfer from the outboard MSIV to the section of the process pipe at the welding location is ignored. Justification: This is for the simplicity and is conservative in the sense that it will cause the temperature variation along the section of the process pipe of interest to us to be overestimated. That is because the outboard MSIV has huge mass and heat capacity and therefore is a heat reservoir that tends to maintain the temperature of the process

bb-2076L I Page 108 of 217 PSAT 04202H.07 P  : 5 of15 i Res 234 pipe at the welding location against heat loss through the guard pipe. Assumption 4: The temperatures of the guard pipe at the end of insulation (which coincides with the inner surface of the shield building wall) and at the process clamp location are the ambient temperature of the environment. Justification: Evidently, this is also a conservative assumption since the guard pipe should be hotter than the environment in order to transfer heat to the environment. The ambient temperature is assumed to be 102 *F (as will be shown later in the calculation), which is believed to be conservative since the ambient temperature at that location should be higher than that. Assumption 5: On both sides of the process clamp, the temperature distributions along the process pipe in the vicinity of the process clamp are assumed to be symmetric. Justification: The process pipe is insulated on both sides of the process clamp and is at uniform temperature initially. Each side can be modeled as a semi-infinite body starting at the process clamp location. This is why only one side of the process pipe needs to be anslyzed. And it is also the reason why only three bolts out of the total six need to be considered in the heat transfer analysis. Assumption 6: Thermal contact resistance at all interfaces from the process pipe to the guard pipe is ignored, except for the gap resistance between the lug and the plug. Justification: This will greatly simplify the problem, and will be conservative. Assumption 7: The initial thermal hydraulic conditions in the process pipes are assumed to be 562 *K (552 *F) in temperature and 1 atm in pressure. Justification: The initial temperature in the process pipe is the same as that during normal operation, so it equals 562 *K (552 *F), which is the steara saturation temperature at the RCS pressure of 1060 psia (the pressure given in Reference 3 as Item 8.4). After the MSIV closes following a postulated severe accident, the pressure in the process pipe drops to about atmospheric pressure, while the wall

I ,, PY CEl/NRR-2076L Page 109 of 217 PSAT 04202H.07 POLESTAR PROPRIETARY Pa e: 6 of15 Rev 01 234 < l l I i l

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Attacnment o , PY-CEl/NRR-2076L NAT 04202H.07 POLFSTAR PROPRIETARY Pa e: 7 af Rev 01 234 0

Attacnment b 4 i PY-CE1/NRR-20761. Page 111 of 217

PSAT 04202H.07 POLESTAR PROPRIETARY Pa e: 8 of 15 i

Rev 0 234 I i a a 1 a t f l t I i i a i

ALLdwilillCinL 0 PY-CE!/NRR-2076L Pcge 112 or217 PSAT 04202H.07 POLESTAR PROPRIETARY Pa e: 9 of 15 Rev01234 I I l 1 i i I 1

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atanmem u l PY-CEl/NRR-2076L ' Page 113 of 217 PSAT 04202H.07 Pa 10 of15 l Re 1234 ' l l Reference Reference 1: Fax from J. Spano to J. Metcalf on Jan. 9,1996 Reference 2: J. Cline, "MSIV Leakage Iodine Transport Analysis," Prepared for 1 the U.S. Nuclear Regulatory Commission under contract NRC l 87-029, Task Order 75, March 26,1991. ' I Reference 3: PSAT 04202U.03, " Dose Calculation Data Base For Application of the Revised DBA Source Term to the CEI Perry Nuclear Power  ! Plant", Revision 0 i Reference 4: F. Kreith, " Principles of Heat Transfer", 3rd Edition, Intext Educational Publishers, New York,1973. Reference 5: W.M. Kays and M.E. Crawford, " Convective Heat and Mass  ! Transfer", 2nd Edition, McGraw Hill, NY ,1980. Reference 6: W.C Reynolds, H. C. Perkins " Engineering Thermodynamics", McGraw Hill, NY,1964

Attacnment o PY-CEl/NRR-2073L Page 114 of 217 PSAT 04202H.07 POLESTAR PROPRIETARY Pag :11 of15 Rev 0 1 2 3 4 Calculation O l

                                                'p[.dh'kk2076L Page 115 of 217 PSAT 04202H.07 POLESTAR PROPRIETARY    Pag 12 of15 Rev.0  234 O

kitacnmem o l PY-CEl/NRR 2076L i Page llG of 217 I PSAT 04202H.07 POLESTAR PROPRIETARY Pa :13 of15 Res . 0 234 Results 1 ( .i j i 1 i v d

1 Acachment o l

 ..                                                      PY-CEl/MRR-2076L I Page 117 of 217 PSAT 01202H.07   POLESTAR PROPRIETARY    Pag 14 of15 Rev 0  234 1

l 1 l l l 4 l i i a

Attachment 6 { PY-CELWRR-2076L l Page 118 of 217 PSAT 04202H.07 Page:15 of15 Rev 0 234 1 Exhibit 1 1 (Taken from Reference 2) ' 1 TEMPERATURES OF THE MSIV LEAKAGE LINES I J m ~ i m

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Attachment 6 POLESTAR 7 I. EIT32pm i PSAT 04202H.08 NON-PROPRIETARY Page 1 of 20 l Rev: 234 l

                                                                                                     /

l CALCULATION TITLE PAGE 1 CALCULATION NUMBER: PSAT 04202H.08 l CALCULATION TITLE:

         "Steamline: Particulate Decontamination Calculation" ORIGINATOR                CHECKER                    IND REVIEWER i

Print /Sicn Date Print /Sicn Date Print /Sicn Date  ! REVISION: 0 ' k/ffs 1 fu Q ff5/? 3rn)Debcah

                                                                        '    '         S 4                            7u%3fnlu              *           'f Y"l" 3

• 4 REASON FOR REVISION: Nonconformance Rpt 0 -Initial Issue N/A 1 - To correct mean free path of steam and associated Cun-N/A - error ningham slip factor (based on comparative DEPOSITION found in-calculation required by PSAT 042020. 02),to credit retention process.

in the intact steamlines inboard of the inboard MSIV, and to use time-dependent particle size distribution based on drywell STARNAUA computer runs. 2 3 4

Attachment 6 ,, PY-CEl/NRR-2076L Page 120 of 217 PSAT 04202H.08 - Psge: 2 of 20 Rev: 0@234 1 Table of Contents Section Eage Purpose 2 Introduction 2 Methodology 5 Assumptions 6 References 10 Mathematical Modeling 10 Calculation 13 Results 17 Appendices: A - I

                          " Aerosol Removal in the Drywell" (4 pages) POLESTAR PROPRIETARY B    -
                          " Aerosol Retention Efficiency in a Well-mixed 20LEST      S :eamme"AR                   PROPRIE (60 pages)

C- " Aerosol Retention Efficiency In A Steamline With Uniform Gas  : Flow"(6pages) POLESTAR PROPRIETARY D -

                          "NaturalCirculationin ASteamlineWith An AxialTemperature Variation"(7pages) POLESTAR PROPRIETARY

Attachment:

1

                      - Fax from Spano (CEI) to Leaver (Polestar) dated 8/17/95 (3 pages)

Purpose The purpose of this analysis is to model the behavior of the aerosols as they travel through the main steam lines and, thus, to calculate the removal efficiency of the aerosols in the main steam lines. 1 Introduction There is a total of 4 main steam lines in the Perry plant; each has an inboard MSIV, an c,utboard MSIV and a third isolation valve. Since the Design Basis Accident considered

Attachment 6 PY4TLNRR-2076L Page 121 of 217 , PSAT 04202H.08 Page: 3 of 20 l Rev:0(i)2 3 4 , 1 here is assumed to be initiated by a double guillotine pipe rupture in one of the four main steamlines (see Assumption 2 below), the fission products suspended in the  ; drywell atmosphere are assumed to leak to the environment through the MSIVs in the l broken line, as well as to be entrained in the gas flow back through the break and into ] the intact steam lines via the reactor vessel, and then to leak out to the environment l

through the MFT : ;n the intact lines. I I

The MSIVs in main steam lines are required to close when an accident occurs. Failure to close any of these valves will affect the retention of the p fission product aerosols in the P: P: { steamlines (and therefore the gpy __4} 4 [g [g fission product release to the  : I environment) as will the W location of the pipe rupture in the broken steam line and the p distribution of the 250 scfh x:

• 2"- "-

RPV total steam line leakage among the four lines. [y  ;' (b) Therefore,in order to assure that the most limiting (i.e., r g conservative) dose is RPV ._

                                                                                 ":            b evaluated for the DBA dose calculation,it is necessary to                               :g::            P           _p                ,

i M h determme the worst case single failure, break location, m and MSIV leakage Figure 1. MSIV leak path configurations distribution. Steam Line Single Failure Possibilities There are three single failure possibilities: (1) Failure of a single inboard MSIV to close (see Figure 1.a) (2) Failure of a single outboard MSIV to close (see Figure 1.b) (3) Failure of one or more third isolation valves (MOV 20 valves) to close (see Figure 1.c) D

P b h N 2076L Page 122 of 217 PSAT 04202H.08 Page: 4 of 20 Rev:0Q)2 3 4 l The aerosol retention is dependent on steam line length (i.e., fraction retained increases with the length of steam line available) and on the retention modeling assumptions for the steam line volume. With regard to retention, the reality is that for most steam line I configurations the gas and entrained aerosol from the leakage will flow with uniform velocity (determined by the volumetric flow from the MSIV leak rate) with a delay between the time of entry into the steam line and the time of arrival at the end of the steam line. Aerosol settles in the pipe as the gas and entrained aerosol flow down the pipe so that at the end of the pipe (i.e., the end of that portion of the pipe being credited as a retention volume), the concentration of aerosol in the leaking gas mixture is reduced (in effect, a filtering process). The time delay is not taken into account in making the determination of aerosol retention efficiency. l The retention has been modeled in one of two ways. For steam line sections which are completely isolated (i.e., where there is a closed isolation valve upstream and downstream of the volume comprising the steam line section) and where significant axial temperature variation does not exist along the steam line pipe wall, uniform velocity is assumed. For steam line sections where the upstream end is open to the drywell or reactor vessel, or where there is a significant axial temperature variation along the steam line pipe wall, some mixing can occur. In this situation a well-mixed model is assumed for conservatism; that is, aerosol settling is based on the aerosol mixing immediately as it enters the pipe. On the basis of the assumptions discussed below, the first and third of the single failure possibilities will be considered in the dose evaluation to determme the more limiting. These two configurations are as follows: (1) One line leaking at 100 scfh, with the break assumed to occur unmediately upstream of the failed open inboard MSIV in this line; credit for two retention volumes in series, one between the two MSIVs (a well-mixed volume with no uniform flow velocity due to the location of the break and the upstream MSIV having failed open) and one between the outboard MSIV and the third isolation valve (no retention prior to 20 minutes to effect closure of the third isolation valve, and uniform flow velocity after 20 minutes). A second line (intact) leaking at 100 scfh; credit for three retention volumes in series, one upstream of the inboard MSIV (a well-mixed volume due to the presence of the reactor vessel upstream), one between the two MSIVs (uniform flow velocity since both ends of the volume are isolated), and one between the outboard MSIV and the third isolation (again, uniform flow velocity after 20 minutes).

a %nmuao PY-CELTRR-2076L Page 123 of 217 PSAT 04202H.08 Page:5 of 20 i Rev:0@234 A third line (also intact) leaking at 50 scfh; credit for three retention volumes in series, one upstream of the inboard MSIV (a well-mixed volume due to the presence of the reactor vessel upstream), one between the two MSIVs (uniform flow velocity since both ends of the volume are isolated), and one between the outboard MSIV and the third isolation (again, uniform flow velocity after 20 minutes). (2) All four third isolation valves fail open (due to common power supply). l The broken line leaking at 100 scfh, with the break assumed to occur unmediately upstream of the inboard MSIV; credit for one retention volume between the two MSIVs (uniform flow velocity since both MSIVs are closed). A second line (intact) leaking at 100 scfh; credit for two retention volumes m l i series, one upstream of the inboard MSIV (a well-mixed volume due to the presence of the reactor vessel upstream), and one between the two MSIVs (uniform flow velocity since both ends of the volume are isolated). A third line (also intact) leaking at 50 scfh; credit for two retention volumes in series, one upstream of the inboard MSIV (a well-mixed volume with no uniform flow velocity due to the presence of the reactor vessel upstream), and one between the two MSIVs (uniform flow velocity since both' ends of the volume are i isolated). I Reference [1] establishes that because of the presence of the process clamp in the s! between the guard pipe and the steamline about mid-way between the inboard and outboard MSlVs, that portion of the steamline will cool down at a rate somewhat greater than the steamline, in general. Therefore, an internal circulation can be established over much of the steam line section between the inboard and outbo MSIVs after a certain period of time. This section will then be considered well-mixed. Methodology The problem to be solved can be described as follows: During a postulated DBA accident, the drywell pressure drives a small leakage flow to travel through the isolated main steamlines out to the environment. The fission products suspended in the drywell may be entrained in this leakage flow. As the fission product aerosols are traveling through the main steam lines, they will experience removal processes, such as sedimentation, Brownian diffusion, diffusiophoresis, '

m .. ...e l PLCEl/NRR-2076L Page 124 of 217 PSAT 04202H.08 Page: 6 of 20 Rev:0@2 3 4 thermophoresis, etc. The removal efficiency of the aerosols in a steam line depends on the condition and configuration in that steam line. When most of the steam line is at uniform temperature, the gas flow is driven by the steam line leakage only and is then expected to be uniform, so the steam line retention of aerosols is modeled as the aerosol sedimentation during the time interval when the aerosols traverse through the section of the steamline under consideration at the uniform flow velocity corresponding to the leak rate. The aerosols that are still  ; suspended (i.e., have not settled) when they arrive at the containment boundary (which is either the outboard MSIV or the third isolation valve) are considered to be released to the environment. The detailed modeling for this case is given below and the calculation is done in Appendix C. When a temperature variation prevails over some portion of the steam line, natural circulation flow may dominate over the flow induced by the leakage. Consequently, the steamline aerosols are better mixed than the case discussed above. In this case, the steam line section of interest is modeled as a well-mixed volume with an aerosol source rate and leak rate specified by the leakage rate. The computer code STARNAUA 1.01 is used to calculate the aerosol sedimentation. The discussion for this case and the calculation details are provided in Appendix B. Assumptions - Assumption 1: The single failure of outboard MSIV failure to close need not be considered further on the basis that it will have higher aerosol retention and thus is less limiting than the inboard MSIV failure to close. Justification: The outboard MSIV failure to close is identical to the inboard MSIV failure to close except that it would provide retention from uniform flow velocity over the steam line length from the inboard MSIV to the third isolation valve. The inboard MSIV failure to close, on the other hand, provides retention from a well-mixed volume over the steam line length from the inboard MSIV to the outboard MSIV, and uniform flow velocity from the outboard MSIV to the third isolation valve. Thus the outboard MSIV failure to close will have higher aerosol retention and is less limiting than the inboard MSIV failure to close. Assumption 2: For the remaining two single failure possibilities, the worst case break location is in a main steam line, immediately upstream of the inboard MSIV.

sutocnment b PY-cE!/NRR 2076L Page 125 of 217 PSAT 04202H.08 Page: 7 of 20 Rev:0(1)2 3 4 Justification: A main steam line break is more limiting than a recirculation line break since the drywell pressure for a main steam line break is somewhat higher than for a recirculation line break. This higher drywell pressure is conservative since it reduces the volumetric flow (and thus the fission product removal effect of drywell sweepout) from steam generation during and after core damage (with a fixed mass flow rate from steam generation as calculated in I Reference [2], a higher drywell pressure reduces volumetric flow from the drywell). A stuck open SRV is also not limiting since the SRV line will blow down into the suppression pool which would reduce airborne fission products significantly relative to what results from a main steam or recirculation line break. A break immediately upstream of the inboard MSIV is limiting since with this break location, there is no credit for retention in any portion of the broken line upstream of the inboard MSIV. Assumption 3: The worst case distribution of the 250 scfh total steam line leakage is to concentrate the leakage into three lines with the broken line and one other line at the 100 scfh per line maximum, and a third J line at 50 scfh. ~ Justification: The broken line will have less retention length, and thus less retention, than the intact lines as noted in Assumption 2 above. l Thus, assuming 100 scfh through the broken line is conservative. , l For the remaining 150 scfh, assummg one line at 100 scfh is conservative since increased leak rate decreases residence time in the steam line volume and thus decreases retention efficiency. Assumption 4: For the calcu'.aticn of the actual MSIV leak flow rate, thermal hydraulic conditions in the main steamlines are assumed to be 562

                   *K in temperature and I atm in pressure over the time period in the accident of interest, i.e., from 0 to about 28 hours to be consistent s

with other aerosol removal calculations (e.g., drywell aerosol calculation in Ref(rence [3]) Justification: The initial temperamre in the main steamlines is the same as that during normal operation, namely 562 'K, the steam saturation temperature at the RCS pressure of 1060 psia (the pressure is given

P ELhkk-2076L Page 126 of 217 PSAT 04202H.08 Page:8 of 20 Rev:0@2 3 4 in Reference [4] as Item 8.4). After the MSIV closes following a postulated core damage DBA, the pressure in the main steamlines drops to a reduced pressure (assumed conservatively to be atmospheric), while the wall temperature remains unchanged at least for a while. The temperature is expected to drop as time goes on, but ignoring the temperature drop leads to a higher MSIV leakage flow that, in turn, leads to a smaller decontammation factor, and is thus conservative. Assumption 5: The MSIV leakage flow becomes a uniform flow velocity after the i entrance into the main steam lines when the main steam line l temperature is uniform. Justification: If the leakage flow is jet-like, jet-induced vortices will occur in the l immediate vicinity of the leak pathway. It is expected that these  ! vortices will efficiently mix the incoming leakage flow with the bulk gas. If there are multiple leak paths, the leakage flow mixes with the bulk gas even more efficiently. Thus, the MSIV leakage is l considered to result in uniform flow velocity in the main steamline starting from the immediate vicinity of the MSIV. Assumption 6: In evaluating the average residence time that the aerosols spend in traversing the section of the main steamline of interest, only the part of this section where the gas flow is expected to be uniform is taken into account. The time that the aerosols spend in the part of the mam steamline where a natural circulation may exist due to the temperature variatian is ignored. 1 Justification: This assumption :mplies that the aerosols traverse the part of the main steamline where a natural circulation may exist from one side to the other instantuneously. This is evidently a very conservative assumption in the sense that the residence time will be underestimated so that the decontamination factor of the aerosols will underestimated. A detailed discussion on the actual aerosol behavior in the natural circulation to be encountered in this analysis is given in Appendix C below. Assumption 7: Aerosol sedimentation is considered to be the only removal mechanism for aerosols in the main steamlines. Only the horizontal sections of the main steamlines are credited for aerosol removal. 1

P[.CE kR.2076L Page 127 of 217 PSAT 04202H.08 Page: 9 of 20 Rev:0@2 3 4 Justification: The assumption is necessary for simplifying the problem. As a result of this assumption, main steamline decontammation factors will be underestimated and, therefore, the assumption is conservative. Assumption 8: In the calculation of aerosol removal, the aerosol source is assumed to be log normal, with a geometric mean radius, a geometric standard deviation and average aerosol density determined by the standard statistical analysis of the aerosol source. Justification: As discussed in Reference [5] (page 12-13), the overwhelming majority of aerosols are observed to have a lognormal size distribution. It is also a common practice to assume such a distribution for the fission product aerosols in nuclear safety studies. A lognormal distribution is defined by the geometric mean radius and the geometric standard deviation. Since the aerosols in the main steamlines are from the drywell, the aerosol size distribution for the suspended drywell aerosols is used (see Reference {3]). The average density calculated in Reference [3] is about 3.77 g/cm for the first 1800 seconds (i.e., from 30 to 1830 seconds in accident time) and the total leaked mass into steamlines is 7.36 grams for this time interval (sweeping flow is assumed to be zero during this time). The average density becomes about 4.7 g/cm3 after 1800 seconds and the total leaked mass into the steamlines is calculated to be 201.49 grams using the suspended aerosol mass concentration data given in Reference [3] and the MSIV leakage rates. Thus, the weighted average density for the aerosols that enter the steamlines is given by the following expression: 3.77 g/cm' x 736g + 4.7g/cm' x 201.49g

                                                              = 4.667g/cm' 736g + 201.49g The aerosol source rate into the main steam line is dependent on                 ,

the flow rate in that steam line (100 scfh or 50 scfh) and is derived l from the suspended aerosol concentration in the drywell as a function of time. To have a better suspended aerosol concentration  ; profile in the drywell over the time of interest, the drywell aerosol I calculation from Reference [3] has been repeated using more i frequent edits. The results are shown in Appendix A of this 1 1

P[-Cb5kkR-2076L Pcge 128 of217 i PSAT 04202H.08 i Page:10 of 20 Rev:06)2 3 4 i calculation. A comparison has been made in Appendix A to show  ! that the new calculation is identical to the original, except that the l results are printed out at better distributed time points in the new calculation.  ! i l References  ! Reference 1: PSAT 04202H.07, " Main Steam Line Heat Transfer Analysis ", Revision 0 . i Reference 2: PSAT 04212H.02, "Drywell Sweep-out and Related Thermal-Hydraulic Conditions Inside Containment", Revision 0 Reference 3: PSAT 04202H.04, " Aerosol Decay Rates (Lambda) in Drywell", Revision 0 Reference 4: PSAT 04202U.03, " Dose Calculation Data Base For Application of the Revised DBA Source Term to the CEI Perry Nuclear Power Plant", Revision 0 Reference 5: Fuchs, N. A., "The Mechanics of Aerosols", Dovers Publications, Inc., New York,1964 - Reference 6: S.K. Friedlander, " Smoke, Dust and Haze - Fundamentals of Aerosol Behavior", John Wiley & Sons, New York,1977 Reference 7: PSAT C101.02, "STARNAUA - A Code for Evaluating Severe Accident Aerosol Behavior in Nuclear Power Plant Containment: A Validation and Verification Report", Revision 1, February 1996 Reference 8: Fax from Spano (CEI) to Leaver (Polestar) dated 8/17/95 - Attachment I to this calculation. Mathematical Modeling POLESTAit PROPRIETARY

       -. .~    . -      __

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Attachtinctit o POLESTAR II:7III?rS#* PSAT 04202H.09 NON-PROPRIETARY Pa 1of9 Rev 1234 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04202H.09 CALCULATION TITLE:

      " Steam Line: Elemental Iodine Decontamination Calculation" ORIGINATOR             CHECKER                IND REVIEWE'l Print /Sicn Date       Print /Sicn Date       Print /Sicn Date
                    **'d L ~        7      )U{edcalf       Tar g elcetf REVISION: 0 W       syt%  C "y,,j4l     % Wi*Qnlgc.

1 2 3 4 i REASON FOR REVISION: . Nonconformance Rpt l 0 -Initial Issue N/A 1 2 3 4

nan.usm o PY-CEl/NRR-20761. Page 143 of 217 PSAT 04202H.09 Pa : 2 of 9 Rev: 234 Table of Contents Section Eage Purpose 2  ! Methodology 2 Assumptions 3 i References 3 Calculation 4 Results 7 Conclusions 8 Purpose The purpose of this calculation is to determine the elemental iodine released into the main steam lines and the ultimate decontamination factor (DF) of the iodine which deposits in the steam line. A fraction of the 1 2in the steam lines is assumed to resuspend as organic iodide and is then released to the environment. This calculation will estimate the fraction of 12 which resuspends as organic and convert i this resu.cpension fraction to an effective filter efficiency for 12 entering the steam i lines. The calculation will also consider the ultimate decontamination of iodine i aerosol which deposits in the steam line. Methodology To determine the 12 released into the steam lines, it will be assumed that the 12 released from the damaged core, as specified in NUREG 1465 [1], is assumed to plate out on the aerosol suspended in the drywell atmosphere and is transported with the aerosol. Thus the 12 leaks with the aerosol through the MSIVs and deposits on the steam line pipewall (with the aerosol). In order to determine the effective filter efficiency of the 12 entering the steam lines, a manual calculation will be performed which compares the resuspension rate of 1 2 with the fixation rate in order to determine the fraction of deposited 12 which resuspends over time. This resuspended fraction is then converted to a filter efficiency. l

l 1 b.2076L Page 144 of 217 PSAT 04202H.09 Page: 3 of 9 Rev:(0)12 3 4 l i Assumptions l Assumption 1: The I2 will tend to plate out on surfaces in the drywell. Justification: Elemental iodine is a gas at containment temperatures and is reactive with many materials [2]. It is well documented that it will tend to deposit on surfaces by chemical adsorption [3]. Since the 12 is released to the drywell where there are large surface areas of various types, a significant amount of the 21 will Pl ate out in the drywell. Assumption 2: The resuspended 12 in the steam line is converted to organic iodide. Justification: According to Reference [3], resuspended 12 can change its chemical form (conversion) to organic. For simplicity and conservatism, this conversion is assumed to be 100% References

1. L. Soffer et al, " Accident Source Terms for light-Water Reactor Nuclear Power Plants," NUREG 1465, February,1995. -

2. " Handbook of Chemistry and Physics," 73rd Edition, 1992-1993.

3. J. Cline, "MSIV Leakage Iodine Transport Analysis," Prepared for the U.S.

Nuclear Regulatory Commission under contract NRC-03-87-029, Task Order 75, March 26,1991.

4. N. A. Fuchs, "The Mechanics of Aerosols," Dover Publishing,1964.

5. " Aerosol Decay Rate (Lambda) in Drywell," Polestar QA Record PSAT 04202H.04.

6. " Dose Calculation Data Base for Application of the Revised DBA Source Term to the CEI Perry Nuclear Power Plant, " Polestar QA Record PSAT 04202U.03.

7. " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," U.S. NRC, NUREG 0800, Section 6.5.2, Revision 0.

8. " Steam Line: Particulate Decontamination Calculation," Polestar QA Record

 , PSAT 04202H.08.

PY-CEISJRR-2076L Page 145 of 217 i PSAT 04202H.09 Pa e: 4 of 9 Rev:6)1234 $ Calculation ! I Calculation of Plateout Area of Aerosol vs. Plateout Area of Drvwell Shell. ) Eauipment. and Structural Surfaces l Per the Assumption 1., the I2 will tend to plate out on surfaces. This calculation is to ] determine the relative magnitude areas of potential plate out surfaces in the drywell. , The aerosol particle surface area is estimated as follows. From Reference [4], the l mass fraction for aerosols of radius r is expressed by 2' 1 In r-(In r, + 31n2 y)' f(r)dr = exp< -

                                                                                                         > din r

, lao V2x 21n2 g i - ! = 6(r)dinr l The subtotal of the mass for aerosols of radius r to r + dr is

                                                                                                    -2' y               in r-(Inr + 31n2 y) 8 Am = Mf(r)dr =                          exp.     -
                                                                                                           > din r in aV2x                       21n2 y
                                                       = M6(r)dinr where the total mass of aerosols is M.

The subtotal of the volume is j Av = Am P where the volume per particle is 4 v = - xr 3 3 Thus the number of particles in r to r + dr is 1

                                                                          . ~. . - . - -

PY.CELNRR-2076L Page 146 of 217 PSAT 04202H.09 Page: 5 of 9 Rev:@l 2 3 4 N(r) = b v where the surface area per particle is A = 4xr' The subtotal of surface area for aerosols in r to r + dr is 3Av S = N(r).A =vb4xr2 = 0" 4xr' = g ,s r

                              = 34"'                          II)dr Pr 3M pr 6(r)dinr=

pr* Using a total aerosol mass of 27.1 kg and a particle density p of 3770 kg/m3, the total surface area of the aerosolis

                          -3M6(r)dr = 4.01E4 m2 for rg = 0.22 m and a = 1.81 a   pr 2 These values of aerosol mass, density, and size distribution are taken from Reference [5] for the conditions existing at the start of the fuel release. This is very conservative (i.e., lower than actually would be expected) with regard to aerosol mass and surface area since the peak aerosol suspended mass will be much larger after fuel release begins.

The drywell shell, equipment, and structural surface area is estimated by summing the following: (1) calculating the horizontal' surface area of the drywell shell (Ah ), (2) using a multiplicative factor based on a calculation by CEI to account for additional horizontal surface area (m), (3) calculating the vertical surface area of the drywell shell (Av), (4) applying the same multiplicative factor to the vertical surface area, and (5) calculating the downward facing surface area of the drywell shell (Ad). Using dimensional information from Reference (6), Item 7.1, Ah can be calculated as follows: A. = (x)(36.5)2 = 4186 ft2 The total horizontal surface area for sedimentation from Reference [6), Item 7.1, is 8712 ft2 . Thus the multiplicative factor is l

PY.Cbhkk-2076L Page 147 of 217 PSAT 04202H.09 Pa : 6 of 9 Rev: 1234 m = 8712/4186 = 2.08 Av can be calculated as follows: Av = Ai + A2 where At is the sidewall area of the cylinder (based on a height of 76.5 feet per Reference [6]), and A2 is the sidewall area of the upper ~ drywell head (based on a height of 16.5 feet and a radius of 16 feet per Reference [6]). From Reference [6], A, = (73r)(76.5) = 17544ft' and A2 = (32x)(16.5) = 1659p2 Thus, i Av = A 1+ A2 - 19200 ft2 The downward facing area A d can be calculated from Reference [6] as A, = x(16)2 = 804ft' { Thus, is the total plateout area of drywell surfaces including equipment and structures A tot = (Ah+ Av)(m) + Ad

                                          = (4186 + 19200) x 2.08 + 804 Thus,                                              -

2 i A tot = 49447 ft x 0.0929 m2/ft 2= 4594 m2 The minimum aerosol surface area during fuel release is 40100/4594 = -9 times that of the drywell surfaces. This would tend to make the 1 2 Pl ate out on the aerosol. A second consideration with regard to 1 2 Pl ateout on aerosol is the fact that the aerosol gradually is removed from the drywell and thus its effective plate out area decreases with time. However, the 1 l 2 P ateout rate constant from Reference [7] (= Sm/hr x Area / Volume where the Area / Volume is ~0.6)is significantly larger tha the sedimentation rate constant of the aerosol (0.6 hr-1 maximum from [5]). While the aerosol sweepout rate constant is somewhat larger, sweepout wi remove both aerosol and 12. Thus the 12 will tend to plateout much faster than the aerosol is removed from the drywell even if plateout were only on structures. In f

PY CELHRR-2076L Pcge 143 of 217 PSAT 04202H.09 Page: 7 of 9 Rev:@)12 3 4 fact, using the Reference [7] expression for plateout of elemental iodine gas on surfaces, lambda = (5 m/hr) x Area / Volume, for a BWR drywell, the lambda could be 1-2 per hour or even higher depending upon the fraction of surface area that is wetted. As calculated above, the total surface area of the aerosol pardcles is an order of magnitude larger than the total surface area of structures and equipment in the drywell. Therefore, one would expect aerosol plateout to dominate. Further, it is conservative to assume that the 12 Pl ates out on the aerosol rather than the drywell surfaces since the aerosol leaks to the steam line and the 2 1 can subsequently be released to the environment.12 Pl ated out on drywell surfaces will tend to remain in the drywell. Thus it will be assumed that the 1 l 2 P ates out on the aerosol and subsequently leaks with the aerosol to the steam lines on the basis that the aerosol particle area dominates and the fact that this assumption is conservative from the standpoint 12release to the environment. Fraction of b Resuspended from Steam Lines Based on Reference [8), essentially all of the aerosol which leaks through the MSIVs and into the steam lines will deposit on the pipewalls. Thus the 12 attached to this aerosol will also be deposited, and some fraction of this 21 will resuspend. This fraction is estimated by comparing the rate constant for fixation with the rate constant for resuspension. From Reference {3), the resuspension rate2 of1 (assumed to be resuspended as 100% organic per Assumption 2) as well as the fixation rate of1 2 varies with temperature of the steam line wall. Also from Reference [3), main steam line temperature varies from about 565 K to 400 K over the first few days after shutdown (see Exhibit 1). From Exhibit 1, it may also be seen that the average fixation rate over the first 3 days (260,000 seconds) is about 1E-5 sec-1, and the average resuspension rate is about 8E-6 sec-1. Thus the fraction which resuspends is something less than half of the total deposited. For conservatism,it is assumed that half of the 12 resuspends. This resuspension will occur over a period of several days (i.e., about 90% of the resuspension occurs in the first 72 hours). 3 Results Transporting the elemental iodine with the aerosol leaking into the steam line is consistent with the relative plateout areas in the drywell and is conservative from the standpoint of eventual 12release.  : I i

Ph2bk[NRk-2076L

• Page 149 of 217 PSAT 04202H.09 Page: 8 of 9 i Rev:h12 3 4 l Treating the resuspension of the 12 form the deposited aerosol in the steam line as a  ;

filtering process is conservative since the actual resuspension occurs over a several , day period, whereas the filtering process assumes that the release is instantaneous at j the time of deposition on the steam lines. The effective filter efficiency on the 12 entering the steam lines is conservatively _ taken as 0.5. The unfiltered 2I is then j assumed to be released as organic iodide per Assumption 2. Conclusions l It is concluded that treating the elemental iodine as aerosol up to the point that it is  ! deposited in the steam lines is reasonable (and conservative since plating the 12 out 1 in the drywell will release less 12 to the environment), and that the elemental iodine entering the steam lines may be conservatively modeled with an effective filter  ! efficiency of 50% Essentially none of the deposited aerosolis released from the  ! stream lines. . I i I I I ( i 1 I l i i l

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um-m o l POLESTAR E8EEE#* PS AT 04202H.11 NON-PROPRIETARY Page 1 of 11 Rev o l ou 1 CALCULATIONTITLE PAGE l J CALCULATION NUMBER: PSAT 04202H.11 CALCULATION TITLE:

       " Perry Containment Water Pool pH" ORIGINATOR               CHECKER              IND REVIEWER                l Print / Sign Date       Print / Sign Date       Print / Sign   Date REVISION: OT?rchand#eMAs               ) g.tm, q l gst          D, e. L        Ap4N     l N            09/'/9/%     b.Q.L =               bq. I o ..

1 l l 2 i 3 4 REASON FOR REVISION: Nonconformance Rot 0 - Initial Issue N/A l 2 1 3 4

_ - . . - . - - . .. - - . . - ~ ~ - - - . . . . . - . - Attachment 0

    ,                                                                                           PY-CEl/NRR-2076L Page 152 of 217 PSAT 04202H.11 Pa e 2 of 11 Rev. 1234 Table of Contents Section g

Purpose 2 Methodology 2 Assumptions 2 References 3 Calculation 4 Results and Conclusions 8 Purpose The purpose of this calculation is to determine the pH of the Perry containment water pool as a function of time following a severe accident out to 30 days. Methodology . Calculate the (OH-] or (H+] concentration in the water pool as a i function of time after reactor scram using the Radiolysis of Water model of the STARpH 1.02 code [1]. Calculate the [ hcl] concentration in the water pool as a function of time using the Radiolysis of Cable model of the STARpH 1.02 code [1]. Manually calcula' te the (H+] concentration added to the pool as a 't function of time from the results of the two previous calculations. Calculate the pH of the water pool considering the sodium pentaborate concentration in the pool and (H+] additions as a function of time using the Add Acid model of the STARpH 1.02 code [1]. Assumptions

1. Reactor power = 3758 MWt 2.

Containment water pool volume (including RCS) = 1.7E5 ft'

3. Volume of drywell = 276,500 ft 4.

Volume of wetwell/ lower containment = 684,226 ft'

P -Cb kR-2076L Page 153 of 217 PSAT 04202H.11 Page 3 of 11 Rev 012 3 4 l

5. Volume of upper containment = 481,174 ft'

6. Containment water pool initial pH = 6.0 l

7. Cable insulation 2.9E4 lbm Hypalon

8. Cable insulation jacket thickness .= 0.045 inch

9. Cable insulation outside diameter = 2.26 cm

10. Mass of sodium pentaborate available for injection is 5236 lbm

11. Chemical formula for sodium pentaborate is Na20 5B20310H 2O

12. The fission product inventory is 1.05 times the inventory in Item 1.3 of Ref. 2

13. Fraction of aerosol source term in water pool is 0.87

14. Density of Hypalon insulation jacket = 1.55 g/cm'

15. Containment water pool is in equilibrium with CO2 in the air in containment The first 12 assumptions are from the Dose Calculation Data Base for .

Application of the Revised DBA Source Term to the CEI Perry Nuclear Power Plant [2]. Assumption No.13 is from Ref. 3 and No.14 is from the Ref. 4. References

1. PSAT C107.02, STARpH Code Description and Validation and Verification Report, Revision 2, February 27,1996.

2. PSAT 04202U.03, Dose Calculation Data Base for Application of the' Revised DBA Source Term to the CEI Perry Nuclear Power Plant.

3. PSAT 04202H.12, Fraction of Containment Aerosol Deposited in Water.

4. J. Wing, Post-Accident Gas Generation from Radiolysis of Organic Materials, NUREG-1081, September 1984.

5. E. C. Beahm, R. A. Lorenz and C. F. Weber, Iodine Evolution and pH Control, NUREG/CR-5950, ORNL/TM-12242, December 1992.

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atanmem o ' PY CEl/NRR-2076L Page 163 of 217 PSAT 04202H.12 Pge: 2 of 6 Rev:gy12 3 4 l Table of Contents Section EiULe  ! Purpose  ! 2 J Terminology l 2 1 Methodology 3  :

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Assumptions f 3 { References 4 , Calculation 5  ; Results 6 Purpose This analysis calculates the fraction of the total aerosols eventually released into the  ; drywell that have either not yet been released (a factor prior to the end of the release period) or that will ultimately transport into water during a postulated severe reactor accident. This fraction includes the aerosols deposited in the water sump (or on the floor that is later flooded with water) in the drywell and the aerosols swept from the  ! drywell atmosphere into the containment where spray removal is quite rapid. l Terminology  ! Released aerosols:  ! Total aerosols released into the drywell from the damaged core i up to the end of the release period. i, Leaked aerosols:  : Aerosols leaked out of the drywell through the MSIV leakage i path. ' Swept aerosols: Aerosols swept from the drywell atmosphere into the j containment due to the sweeping flow from the drywell to the  ! wetwell. i Settled aerosols: Aerosols settled on all projected horizontal surfaces under i gravity. i Diffused aerosols: Aerosols deposited on walls in the drywell. l I

                                                                                           ,ull&lalltCIAL 0 PY.CEl/NRR.2076L P:ge 164 of 217 PSAT 04202H.12                                                                     Pr e: 3 of 6 Rev.0 234 Floor surface:             Projected horizontal surface at the bottom of the drywell that is either initially covered by water or flooded early in the accident.

It is also referred to as the water sump surface. Non-floor surfaces: Projected horizontal surfaces in the drywell that are above the water sump. They are assumed to be dry most of the time during the accident. Methodology Aerosol behavior in the drywell has been studied in Reference 1. The suspended aerosol concentration, the total settled aerosol mass, the diffused aerosol mass and the sum of the swept and the leaked aerosol masses as functions of time were calculated and provided in Appendices C and D. These results, together with some geometry i information and assumptions, will allow us to calculate the fraction of the released aerosols that are ultimately in water due to either sedimentation or pool scrubbing. Assumptions Assumption 1: Drywell is well-mixed during entire time period of the accident. Justification: Given the fact that steam, non-condensable gases (e.g., hydrogen) and fission product gases and aerosols are blowing into the drywell atmosphere, while significant heat and mass transfers are going on in the drywell, this assumption is reasonable. Assumption 2: Aerosol sedimemation flux (e.g., grams per square centimeter per second) does not change from one deposition surface to another in the drywell. _ Justification: Aerosol sedimentation flux to a surface is the product of the aerosol concentration at that surface and the termmal settling velocity of aerosol particles. In a well-mixed containment, the aerosol concentration and the termmal velocity are uniform everywhere, so the aerosol sedimentation flux is uniform, too. Assumption 3: Floor surface of the drywell is covered by water from the beginning of the accident to the end. Justification: Reflooding of the core has to occur in order to prevent vessel failure in the design base accident. So, the drywell floor is expected to be all covered by water most of the time during the accident.

PY-CEl/Nkk-2076L Page 165 of 217 PSAT 04202H.12 P, age: 4 of 6 Rev(0)12 3 4 i Assumption 4: Swept aerosols are assumed to be removed to water pool in the sprayed region of the containment. j Justification: No justification is needed. I \ Reference l , Reference 1: PSAT 04202H.04, " Aerosol Decay Rates (Lambda) in Drywell", Revision l 0  ; i i l . Reference 2: PSAT 04202U.03, " Dose Calculation Data Base for Application of the i Revised DBA Source Tenn to the CEI Perry Nuclear Power Plant",  ! t Revision 0 i l l l l 1 l 4 d i

                                                . . . . . . 1 PY CELNRR 2076L Page 166 of 217 PSAT 04202H.12 POI. ESTAR PROPRIETARY     P 3: 5of6 Rev 01 234 Calculation
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PY<E1/ NRM 0761. A 20 m .12 POLESTAR PROPRIETARY Pr e: 6 of Rev 0 234 l Results l 1 1 l l 1 l l I l 9

SIh5hi#* POLESTAR PSAT 04202H.13 NON-PROPRIETARY Page: 1 of 20 Rev: 0@23 4 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04202H.13 CALCULATION TITLE: i "Offsite and Control Room Dose Calculation" ORIGINATOR l CHECKER IND REVIEWER Print / Sign Date Print /Sien Date Print /Sinn Date REVISION: 0 g$Nld *llTl% h E. ww b. E. We g,_ _ qjg/qc jg 1 Juvt 1-l I/'9/# b . E. 6- D E 6-LfI4}sL t.lI4l94 2 4 3 4 REASON FOR REVISION: Nonconformance Ret ' 0-InitialIssue - N/A i 1 - To incorporate revision to PSAT 04202H.08 calculation, and CEI's requests (1) to increase containment bypass and ESF N/A leakages and (2) to decrease efficiency of charcoal filter in control room recirculation system. 2 3 4

PY-CE5'kk-2074L Page 169 of 217 PSAT 04202H.13 Page: 2 of 20 Rev: 0@23 4 Table of Contents Section .Page Purpose 2 l Methodology 2 l Assumptions 3 References 8 Calculation 8 l Results 15 Conclusion 16 Appendices: A -

                             " LIBRARY File"                                        (2 pages)

B -

                             "LOCATRAN Input Files"                                (26 pages)

C- "LOCADOSE Input File" (1 page) D -

                             " Dose Calculation Results"               (1 page & 2 diskettes)

Purpose The purpose of this calculation is to evaluate the doses for the Perry Nuclear Plant design basis accident (DBA) using the revised accident source term based on NUREG 1465 (Reference [1]) release parameters and on associated fission product removal phenomena. The dose evaluations are based on results generated in the Perry Plant PSAT calculation series prepared by Polestar Applied Technology, Inc. Key results from these calculations, as well as the Perry Plant design inputs, are contained in reference [2]. Methodology l The dose evaluations were performed using the LOCADOSE code developed by Bechtel j Corporation [3]. LOCADOSE was transmitted to Polestar for use on the Perry Plant revised source term application by reference [4]. i

Attachment b PY-CEl/NRR 2076L ' PaFe 170 of 217 PSAT 04202H.13 Page: 3 of 20 Rev: 0@23 4 LOCADOSE is a computer code for multi-region radiome transport and dose calculation for DBA evaluations. The LOCADOSE Program structure is illustrated in Exhibit 1. The LOCADOSE transport and dose calculation consists of three computer ' programs. The Activity Transport Program calculates activities, integrated activities, and releases ' over a time period using a multi-region model that can accommodate up to nine regions and unlimited time steps. Daughter isotope activities, spray removal, and LOCA during purge options can be performed by this program. Activities, integrated l activities, and releases are saved on a file for use by other programs, including the Dose Calculation and Filter Loading Programs, and printed as output as requested. The Dose f.alculation Procram uses the file generated by the Activity Transport Program, the isotope library file and a user generated data file to calculate dose rates and doses. Doses and dose rates can be obtained for all the regions used by the Activ Transport Program and for up to 20 offsite locations. The Filter Loadine Procram uses the file generated by the Activity Transport Program, the isotope library file and data supplied by the user interactively to calculate mass and l heat loadings on charcoal filters. This program can handle up to a maximum of 50 time l steps. In addition, the LOCADOSE CENTER program stores and manipulates data using database file structure. This program generates input data files and the isotope lib files for the above programs. Further details documentation. on LOCADOSE are contained in reference [3] and related Assumptions Assumption 1: The doses to be evaluated are the 10 CFR 100 exclusion area boundary and low population zone whole body and thyroid doses, and the 10 CFR 50, Appendix A, General Design Criterion (GDC) 19 control room doses. Justification: These are the regulatory requirements for DBA radiological j consequence evaluations. Assumption 7.: l The core damrge which leads to the DBA source term of reference ' {1] is arrested by the restoration of core cooling at about two hours j after the start of the accident.

PY CE kR-2076L

• Page 171 of 217 PSAT 04202H.13 Page: 4 of 20 Rev: 0@23 4 Justification: This is an extension to operating plants of a position presented by NRC in reference [5] for ALWRs and is discussed fully in reference

[6]. Assumption 3: The source terms of Reference [1] can be applied to Ferry without regard for fuel burn-up limitations.

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Justification: Since the reference [1] source term is specified in terms of fractions of core inventory and since core inventories are calculated for this application to Perry using an appropriate burn-up, the Section 3.6 statement is Nt related to core inventory. As noted in reference [1], the focus of the statement is the gap activity release, and because of the nature of this application to Ferry, the resc!ts would not be greatly sensitive to the exact gap release timing or magnitude in any case. Assumption 4: The MSIV leakage control system (LCS) is not credited in the revised source term evaluations and the main steam line leakage is assumed to be attenuated in the main steam line from the reactor vessel out to the outboard MSIV or to the third isolation valve, depending upon the break location and the single failure assumption. Justification: Not crediting the MSIV LCS is consistent with the approach taken by several BWRs which have applied for, and received NRC approval of, this change as part of the BWR Owners Group methodology. Crediting main steam line leakage attenuation for the main steam line out to the third isolation valve is based on the fact that for the Perry Plant, the main steam lines are seismically qualified out to and including the third isolation valves. While the BWR Owners Group methodology involves qualifying the main steam lines out to and including the drain line and main condenser, the existence of a qualified third isolation valve downstream of the 3 outboard MSIV, together with the characteristics of the revised source term (i.e., predominantly aerosol which is largely retained in the steam lines) creates the option of using only the main steam line itself forleakage attenuation. Assumption 5: The results of these analyses are sufficiently conservative to  ! constitute a basis for demonstrating compliance with the l requirements of 10CFR100 and with 10CFR50, Appendix A, GDC 19.

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Attachment 6

      .                                                                                                                                PY-CELHRR-2076L       i Page 172 of 217 PSAT 04202H.13                                                                                         Page: 5 of 20 Rev: 0@234 Justification:           The source terms of reference [1] are comparable in conservatism to the DBA source terms previously used on Perry as based on                                                    ;

10CFR100 (and reference [7]) and subsequent regulatory guidance. The noble gas and iodine release fractions (which are the main determinants of the whole body and thyroid dose evaluations specified in 10CFR100) are about the same. The reference [1] timing and chemical form, while different from the previous source terms, are nonetheless conservative compared to what is expected under actual accident conditions, (e.g., the 1979 accident at Three Mile i Island) and provide a more physically correct mpresentation of i activity release to containment. Moreover, in terms of activity  ; transport within and through the containment system and release to environment, there are many other conservatisms included in i the PSAT calculation series. These are as follows: l Conservatism 1 - Early Gao Release Start Time: In general, the PWR l gap release is expected to occur much mom rapidly than the BWR i gap release (refer to discussion in reference [1]). However, this l application has used a gap release start time of 30 seconds l (appropriate for a PWR) to represent the Perry BWR. See reference [8]. i Conservatism 2 - Underestunated Volumetric Flow from Drvwell i During Core Damage and Debris Ouench: Only gamma energy is considered in calculating the core power used to determine vent flow from the drywell to the containment during core degradation and the associated debris quench. Core debris sensible heat during the core degradation (and the formation of debris bed that would enhance heat transfer to the overlaying water), metal-water reactions, and beta heating are neglected. Noncondensible gas is also neglected. See reference [6]. Conservatism 3 - Nedected Pool Scrubbing: All of the leakage flow from the drywell is assumed to enter directly into the contamment via the pool bypass area, totally neglecting pool scrubbing. ' I Conservatism 4 - Neelected Natural Aerosol Removal in Unspraved Region: Natural aerosol removal in the unsprayed region of containment is neglected. Thus the only way aerosol is removed from the unsprayed region is by mixing with the sprayed ! region and subsequent removal by the sprays.

hkkk-2076L Page 173 of 217 PSAT 04202H.13 Page: 6 of 20 Rev: 0@23 4 Conservatism 5 - Underestimated Containment Sorav Effectiveness: The spray effectiveness has been conservatively underestimated in two ways. First, the mixing rate between the sprayed and unsprayed regions (which determines the rate at which unsprayed region aerosol is removed) has been underestimated since the only mixing mechanism considered was density difference due to temperature difference between the sprayed and unsprayed regions. Other mixmg mechanisms which would be effective include momentum transfer of the spray droplets to the unsprayed region, heat transfer from equipment in the unsprayed region, and flow from the unsprayed region due to steam condensation in the sprayed region. Second, the size distribution of the aerosol entrained in flow from the drywell to containment has been underestimated. A larger size distribution would result in faster aerosol removal in the sprayed region. Conservatism 6 - Most Conservative Break Location: A break location immediately upstream of the inboard MSIV in the main steam line is the most conservative. This is because a main steam line break results in maximum drywell pressure (and thus minimum volumetric flow from the drywell to the containment), and because a break immediately upstream of the inboard MSIV results in the steam line section between tlie reactor vessel and the inboard MSIV not being credited for aerosol retention. Conservatism 7 - Most Conservative Distribution of Total Main Steam Line Leakage: The worst case distribution of the 250 scfh total steam line leakage is to concentrate the leakage into three lines with the broken line and one other line at the 100 scfh per line maximum, and a third line at 50 scfh. Conservatism 8 - Most Conservative Main Steam Line Valve Single Failure: There are three single failure possibilities: (1) Failure of a single inboard MSIV to close (2) Failure of a single cutboard MSIV to close (3) Failure of one or more third isolation valves (MOV l 20 valves) to close As discussed in detail in reference [10], the last of these single i failures (i.e., all four third isolation valves failing to close since all

m .. PY-CEI/NRR-2076L

                                                                                                  . Page 174 of 217 PSAT 04202H.13                                                            Page: 7 of 20 Rev: 0@23 4 four depend on a common power supply) is the worst case and thus is the most conservative.

Conservatism 9 - Underestimated Natural Aerosol Removal in p Main Steam Lines: The steam line aerosol deposition is i ' conservatively modeled from a number of standpoints: (1) the aerosol agglomeration which will occur as the aerosol is transported down the steam line has been neglected which will result in steam line removal being underestimated, (2) aerosol removal macharusms other than sedimentation have been neglected, (3) for the most conservative steam line valve single l failure (i.e., all four third isolation valves fail open) no aerosol removal is credited downstream of the outboard MSIV even though it is expected that removal will occur up to the point of the failed open third isolation valve, (4) no credit is tiken for aerosol removal at the location of the pressure drop between the drywell and the steam lines (i.e., the MSIV leak path) even though the constricting streemlines will result in inertial impaction and probably even plugging, (5) the cold gas stratification which will exist in the main steam piping upstream of the inboard MSIV (due to the elevation drop of the piping as it exits the reactor vessel) and the resultant delay of the relatively hot fission product gas and aerosol release from the upper reactor vessel head out the MSIV has been neglected, and (6) the aerosol retention in steam line sections downstream of open isolation valves and the reactor vessel has been underestimated by assuming a well-mixed volume (vs. a plug flow which provides increased aerosol removal and is expected evenin this situation). Conservatism 10 - Underestimated Drywell Aerosol Natural Removal: The natural aerosol removal rate in the drywell is conservatively small due to use of a smaller sedimentation area than actually exists and neglecting hygroscopicity and natural aerosol removal mechanisms other than sedimentation. I' Conservatism 11 - Instantaneous 12 Relme in Main Steam Lines: The conversion of deposited elemental iodine (in the steam line) to , re-evolved organic iodine is assumed to be instantaneous as opposed to requiring several days. See reference [9]. .

asan ;us o PY-CEl/NRR-2076L Page 175 of 217 PSAT 04202H.13 Page: 8 of 20 Rev: 0@23 4 i References i

1. L Soffer et al, " Accident Source Terms for Light-Water Reactor Nuclear Power Plants," NUREG 1465, February,1995. l

2. I PSAT 04202U.03, " Dose Calculation Data Base for Application of the Revised DBA  :

Source Term to the Perry Nuclear Power Plant.", Rev 2. j t 1

3. LOCADOSE, NE319, "A Computer Code System for Multi-Region Radioactive I

Transport and Dose Calculation," User's Manual, Revision 4A, August,1995.

4. Bechtel Letter to Polestar, dated September 25,1995, Mercedes Dumlao to D.

I eaver, forwarding LOCADOSE, Bechtel ID Number 00126D.

5. Taylor, J., " Proposed Issuance of Final NUREG-1465, " Accident Somre Terms for Light-Water Nuclear Power Plants", SECY-94-300, December 15,1994.

6. PSAT 04212H.02, "Drywell Sweep-Out Rate and Related Thermal-Hydraulic Conditions inside Containment.", Rev 0.

7. DiNunno, L.L., et al., " Calculation of Distance Factors for Power and Test Reactor Sites", TID-14844, March 1%2.

8. PSAT 04212H.01, " Source Term for Use on Perry Application of NUREG 1465.", Rev0. 9. PSAT 04202H.09, " Steam Line: Elemental Iodine Decontamination Calculation.", Rev0.

10. PSAT 04202H.08, "Steamhne: Particulate becontamination Calculation.", Rev 1.

11. Perry QA Record No. 3.2.6.5, " Revised Post LOCA Offsite and Control Room Doses," 1993.

Calculation Perry Plant Revised DBA Source Term Dose Model 4 The LOCADOSE code was used in the Perry revised DBA source term dose calculations as described in the Methodology section above. Exhibit 2 describes the dose model which was used. The main clutnges from the existing licensing basis dose model are:

PY-CEl/NRR-2076L Page 176 of 217 i ! PSAT 04202H.13 Page: 9 of 20 i Rev: 0@23 4 Elimmation of the MSIV leakage control system MSN leak rate increased to 250 scfh total,100 scfh maximum per line Removal of airborne fission products from the drywell i Containment spray duration increased to 24 hours i Retention of fission product leakage in the steam line volume between the reactor vwsel and the third isolation valve, or the outboard MSN, depending upon the configuration (with no holdup credit for the main condenser) t l No credit for charcoal filtration in annulus exhaust gas treatment system i A 30 minute delay in actuation of control room recirculation mode

• i ESFleakageincreased by 50%

l t

• I Control room recirculation mode charcoal filter efficiency for elemental and organic iodine decreased to 50%  !

i Containment bypass leakage increased by 50% Control of pH so as to support use of mainly particulate iodine form Plant Confieurations Considered i In order to assure that the most limiting (i.e., conservative) dose was evaluated, it was necessary to determine the worst case single failure, break location, and MSN leakage distribution. Reference [10] discusses these worst cases in detail. Exhibits 3 and 4 describe the two configurations for which dose calculations are to be performed. ' Configuration (1) is for an inboard MSIV failed open. Configuration (2) is for all four third isolation valves failed open. The worst case break location is immediately upstream of the inboard MSN. Worst case leakage distribution is to assume 100 scfh in the broken line,100 scfh in one intact line, and 50 scfh in another intact line (with one intact line at zero scfh). , It should be noted that it would be possible to neglect further consideration of configuration (1) by inspection were it not for the fact that the third isolation valves are delayed in closing by 20 minutes. This can be seen by comparing configuration (1) with  ; configuration (2). Configuration (1), in which the third isolation valves are closed, credits retention in the entire steam line out to the third valve. Configuration (2) on the

PY-CELKRR-2076L Page 177 of 217 PSAT 04202H.13 Page: 10 of 20 Rev: 0@234 other hand, credits retention only out to the outboard MSIV and thus would be expected to have higher release than configuration (1), everything else being equal. However, it is necessary to perform a dose calculation to be certain that the 20 minute delay in closing the four third isolation valves does not significantly impact the release for configuration (1). Thus, a total of two LOCADOSE calculations were performed, one for configuration (1), and one for configuration (2). , Description of the LOCADOSE Input Files

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1. l The first LOCADOSE input file is a library file generated by LOCADOSE CENTER (see LIBRARY on Exhibit I and see Appendix A) that contains information about isotopes considered in the dose calculation. In this file the list of isotopes, the '

corresponding dose conversion factors, and the core inventories are specified in Item 1.2 of reference [2]. t i To confirm that the list of isotopes specified in reference [2] accurately represents the whole body, thyroid, and beta skin dose resulting from a more complete list of fission { products including those in the eight major groups of reference [1], an additional calculation was performed using configuration (2) with the isotopes from reference [2] plus the isotopes in Table 1. Table 1. Addition Isotopes Considered in Confirmation Dose Calculation Group title Elements in Group Release fraction

• Gap In-vessel Alkali Metals RB-87, RB-88, RB-89, CS-135, CS-138 0.05 0.20 .

Barium, strontium BA-140, SR-89 0.0 0.02 Noble Metals MO-99, RU-103, RU-105, RU-106, TC-99M, TC-99, RH103M, RH-105, 0.0 0.0025 RH-1% Lanthanides LA-140 NB-95 ZR-95 NB-95M 0.0 0.0002 Cerium group NP-239 PU-239 0.0 0.0005

• Fraction ofinitial coreinventory The confirmation calculation results show that the difference between the two cases with and without the additional isotopes is 1 to 2% maximum. The complete input and output files for the confirmation calculation are stored on a diskette as part of Appendix D.

n......... PY CElHRR.2076L Page 170 of 217 PSAT 04202H.13 Page: 11 of 20 , Rev: 0@ 23 4 l l l The core inventories for all isotopes in this library file are specified as coefficients in the units of curies per mega. watt thermal power. The total core inventories for the various isotopes in the library file are obtained by multiplying these coefficients by the total thermal power (i.e.,3758 mega-watt as specified in Item 1.1 of reference [2]). However, the values for the coefficients provided by the LIBRARY do not yield the same total core inventories as that specified in reference [2]. Thus, the LIBRARY coefficients were replaced by calculated values which are based on the following expression: Coefficient = total core inventory in item 1.2 of reference [2]/ 3758 Mwt

2. There are a total of two input files prepared to provide necessary information to

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calculate fission product transport for the two configurations discussed above. These  ! files are listed in Appendix B and are the input to the LOCATRAN program. As an example, the following is a detailed description of the Perry plant. specific portions of , one such input file for Configuration (2). l PERRY DOSE CALC. W/ REVISED SOURCE TERM, CFG 2, 24 HR SPRAY Problem title l JUN LI Originator PERRY DOSE CALC. Project name PSAT 04202H Project # 04202H.13 0 Calc W, Rev 1 l First page # of output The above specifies the header of the output file. 8 12 32 1 0 0 # Nodes, # Time steps, # Iso, ICR, CALCDA, LSPRAY The drywell, unsprayed region of the containment, sprayed regian, annulus and suppression pool comprise 5 nodes in this calculation model. Three additional volumes STLCV_1 (Node 7) , l 100 scfh ........ ...... 100_ scfh l Tl.i...............T :T: e l DRYWELL ................

                                                    'T'                      'T               :T:

150 sefh ' 'T' 'T' -T-

                               ......... ..... d .......              ......$ 150 scfh STL_CV_2 (Node 8)       ST(CV_3 (Node 9)

Figure 1. Model of Steam Lines in LOCADOSE Calculation for Configuration (2) I are considered for steamlines, which are labeled as STL_CV_1, STL_CV_2 and STL._CV_3. Figure I shows these three steamline volumes 'or configuration (2). The volumes are the same for configuration (1) between 0 to 20 anutes. After 20 minutes,

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PY.CE!/NRR.2076L Page 179 of 217 PSAT 04202H.13 Page: 12 of 20 Rev: 0@23 4 however, Nodes 7 and 9 are expanded to include the 29 foot section (= 86 ft3) between the outboard MSIV and the third isolation valve, so the new volume for Node 9 = 292 ft3 + 2 x 86 ft3 = 464 ft3, and that for Node 7 = 146 + 86 = 232 ft3 This volume change has been considered in the Configuration (1) calculation. The control room is also included when ICR is set equal to 1. It should be noted that LOCADOSE limits the user specified number of nodes to eight when the control room is considered, which is why we have to combine the 2 intact steam lines into 1 for both Configurations (1) and (2). Number of time steps is only a dummy, and is not used in the calculation. Number of isotopes is 32 since each iodine isotope is considered as 3 for elemental, organic and particulate forms. 1 0 3758 0 2 0 0 ITID, IPURGE, Power, SD time, NPF, # Spr nodes, # Delay cales CFM CUFT CURIES Flow unit, Volume unit, Activity unit 111111111111 Release frac for iso group 1-12 The release fractions (above) for all isotope groups are set to unity so that the actual release fractions to the drywell (see below) are based on the initial core inventories. 0.0485 0.0015 0.95 Elem, org, part iodine frac - DRYWELL 8.333E-3 UNSPRAYED 0.011111 1001 SPRAYED ANNULUS SUP POOL STL CV 1 STL CV 2 STL CV 3 Node name

                                                               -                  ~

From time, To time,~IPRTAC, ~IAACT,~IPACT, IPRINT The calculation block starts at 30 seconds and covers the 10 second time interval out to 40 seconds. I 011 IACTIN, LPTIN, LVOL 0.100000 0 0 0 0.6 0 0 0 Initial I-131 elem act frSc in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-131 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-131 part act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-132 elem act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-132 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-132 part act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-133 elem act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-133 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-133 part act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-134 elem act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-134 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-134 part act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-135 elem act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-135 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-135 part act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Kr-83m act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Kr-85 act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Kr-85m act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Kr-87 act frac in nodes 2-9 0.100000 0 0 0 0 000 0.100000 0 0 0 0 000 Initial Kr-88 act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Kr-89 act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Xe-131m act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Xe-133m act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Xe-133 act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Xe-135m act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Xe-135 act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Xe-137 act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial Xe-138 act frac in nodes 2-9 0.100000 0 0 0 0 000 Initial CS-134 act frac in nodes 2-9 00000 000 Initial CS-137 act frac in nodes 2-9 00000 000 Initial TE-132 act frac in nodes 2-9 Initial BA137M act frac in nodes 2-9

PY-CEI/NRk-2076L Page 180 of 217 l l PSAT 04202H.13 Page: 13 of 20 l Rev: 0@23 4 The gap release to the drywell (Node 2) is specified above at 10% core inventory per hour. To model ESF leakage, iodine is assumed to be released into the suppression pool (Node 6) at 60% core inventory per hour. (For conservatism and simplicity, this release to the suppression pool was assumed to occur in this first time interval even though the fuel release does not begin until 30 minutes). Since these two release rates will be changed or terminated after 30 minutes, the release to the drywell will be 5% of the core inventory and that to the suppression pool will be 30% of the core inventory. 276500. 684226. 481174. 1.96E+5 146952. 146. 440, 292. Volumes for nodes 2-9 The volume of the suppression pool (Node 6) includes the volume of the upper pool dump (i.e., the sum of Items 3.4 and 3.5 of reference [2]), so it equals 146952 fG. The volume of the STL_CV_1 (Node 7) is the volume in the broken line between the inb and outboard MSIVs, which is about 146 ft3 [10]. The volume of STL_CV_2 (Node 8) is for the combined spaces in both intact steamlines between the reactor vessel and the inboard ft3 MSIV (including the vertical portions of these lines), which is 440 ft3 total (220 each) [10]. The volume.of STL_CV_3 (Node 9) is for the combined spaces in both intact steamlines between the inboard and outboard MSIVs, which is then twice the volume of STL_CV_1, i.e.,292 ft3 [10]. 2 7 0 1.987 000000000000 From node, To node, Filt flow, Unfilt flow 2 8 0 2.98 Filt eff for iso groups 1-12 000000000000 From node, To node, Filt flow,.Unfilt flow 8 9 4.775 0 Filt eff for iso groups 1-12 From node, To node, Filt flow, Unfilt flow 501 03.183 7 74.6 00 74.6 74.6 74.6 74.6 74.6 74.6 74.6 74.6 Filt eff 4 iso grps 1-12 From node, To node, Filt flow, Unfilt flow 501 04.775 9 71.0 00 71.0 71.0 71.0 71.0 71.0 71.0 71.0 71.0 Filt eff 4 iso grps 1-12 From node, 50 0 74.0 0 74.0 74.0 74.0 74.0 74.0 74.0 74.0 74.0To node, Filt effFilt flow,grps 4 iso Unfilt flow 1-12 3 1 0 2.01 000000000000 From node, To node, Filt flow, Unfilt flow 34 0 71400. Filt eff for iso groups 1-12 000000000000 From node, To node, Filt flow, Unfilt flow 3 5 0 1.0E-5 Filt eff for iso groups 1-12 000000000000 From node, To node, Filt flow, Unfilt flow 4 1 0 1.005 Filt eff for iso From node, To node, Filt flow, groups 000000000000 Unfilt 1-12 flow 4 3 0 71400. Filt eff for iso groups 1-12 000000000000 From node, To node, Filt flow, Unfilt flow 4 5 0 1.0E-5 Filt eff for iso groups 1-12 000000000000 From node, To node, Filt flow, Unfilt flow 5 1 2000. O Filt eff for iso groups 1-12 From node, To node, Filt flow, Unfilt flow 0 61 0 1.0E-05 99 0 99 099 99 99 99 99 99 99 (Item 4.1) Filt eff for iso groups 1-12 99 99 99 99 99 99 99 99 99 99 99 99From node, To node, Filt flow, Unfilt flow

 -1,0,0,o                                            Filt eff for iso groups 1-12 End flow input The flow rates between the nodes and from nodes to the environment (i.e., Node 1 by default) are specified. It should be noted that 1.0E-5 was used for zero flow rate to avoid a singularity in the calculation. Flow from Node 2 to Node 8, from Node 8 to Node 9 and from Node 9 to Node 1 represent the main steam line leakage from the drywell through two intact lines out to the environment (i.e., Node 1). The Node 2 to l                .       ._ -__ _

mm.aunu.s o i PY-CEUNRR.2076L . Page 101 of 217  ! PSAT 04202H.13 Page: 14 of 20  ; Rev: 0@23 4  ; Node 9 flow is just the 150 scfh converted for steam line temperature (i.e.,150 scfh x 1.91 = 286.5 cfh = 4.775 cfm) sinular to the calculation in Appendix C of Reference [10]. Since the two intact steamlines are modeled one line, the combined aerosol removal efficiencies (W) for Nodes 8 and 9 are determined by the following expression:  ; 1 [Leakratein steamlinei x n, 3=' Leakrate in steamline i where n, is the aerosol removal efficiency for the corresponding space in steamline i (which can be obtained from Tables 2.a and 2.b on pages 17 and 18 of Reference [10]) and the leakrate is either 100 scfh or 50 scfh. To demonstrate the calculation, the removal efficiency in Node 8 (which is modeled as the filtration efficiency between Nodes 8 and 9) is calculated es follows: Since the input is for Configuration (2), the links between the steamline spaces and the removal efficiencies (labeled by Case numbers) are given in Tables 3.c and 3.d in Reference [10]. These two tables indicate that the aerosol removal efficiencies in the two volumes comprising Node 8 are given in Cases 2 and 4. From Table 2.b in Reference [10], we get: Removal efficiency in 100 scfh steamline (Case 2) = 0.711 Removal efficiency in 50 scfh steamline (Case 4) = 0.815 - Thus, the combined removal efficiency for Node 8 = (100 x 0.711+50 x 0.815)/150

                                                       = 0.746 Similarly, the combined removal efficiency for Node 9 (which is modeled as the                                        ,

filtration efficiency between Node 9 and the environment) is calculated to be 0.74. This i is the way the aerosol removal efficiencies for the flow from Node 8 to Node 9 and that l from Node 9 to Node 1 are calculated throughout the two dose calculations for Configurations (1) and (2). 1 2 0.084 Iso group, Node, Lambda 3 2 0.084 3 Iso group, Node, Lambda 5 2 0.084 Iso group, Node, Lambda 6 2 0.084 Iso group, Node, Lambda , 7 2 0.084 j Iso group, Mode, Lambda ' 8 2 0.084 Iso group, Node, Lambda 9 2 0.004 Iso group, Node, Lambda 10 2 0.004 Iso group, Node, Lambda I 11 2 0.084 Iso group, Node, Lambda 12 2 0.084 Iso group, Node, Lambda i

 -1,0,0,0 End lambda input Removal lambdas are specified for each isotope group in the drywell (Node 2).                                         l 1 7.0E-5                                                   LCHG, Control room X/Q 3.44E5 0 1375 2.7E4 1375       CR vol,Filt intake,Unfilt intake,Recire,Outleak

nana m u j PY-CE!/NRR-2076L l Page 182 of 217 l l PSAT 04202H.13 Page: 15 of 20 Rev: 0@23 4 000000000000 Intake filt eff for iso groups 1-12 000000000000 (Item 4.2) Recire filt eff for iso groups 1-12 Control room parameters are specified. 0.011111 0.018333 1 0 0 1 From time, To time, IPRTAC, IAACr, IPACr, IPRINT 000 IACrIN, LPTIN, Lv0L l Input for the next time interval (40 seconds to 66 seconds) begins. The input is repeated for each time interval until the end of the problem. In each interval, only those parameters that change from their previous values need be input. 4

3. The final input file is the input to LOCADOSE, which specifies the dose-related parameters. This file is listed as Appendix C.

Results The results of the two dose calculations are given in Table 2. The detailed output of the calculations is givenin Appendix D. i As is evident from Table 2, configuration (2) is limiting. This is not unexpected since ! the 20 minute delay in closing the third isolation valves for configuration (1) does not

add significantly to the fission product release since only the gap source term exists in containment during this interval. The additional retention due to the 29 foot main steam line section downstream of the outboard MSlV, which is credited in configuration

! (1), more than compensates for the effect of the 20 minute delay. i It should be noted that LOCADOSE calculates the control room immersion dose, and ) the control room personnel dose due to external exposure of the control room (from l direct gamma dose) has not been recalculated Ior the NUREG-1465 source term. The i } Table 2 Dose Results (Rem) Configuration Nodes Thyroid Whole Body Skin Configuration m ) CR 12.5 0.10* 4.68 ~ Single Failure- EAB 75.5 1.29 Inboard MSIV LPZ 93.9 1.60 4 Configuration (2) CR 16.2 0.11* 4.81 4 l Single Failure - EAB 157.9 1.88 4 ) Four 3rd Isolation Valves LPZ 130.3 1.73 j

• Immersion dose only i

I l 1 . i

mawat a PY-CE1/NRR-2076L Page 183 of 217 PSAT 04202H.13 Page: 16 of 20 Rev: 0@23 4 It should be noted that LOCADOSE calculates the control room immersion dose, and the control room personnel dose due to external exposure of the control room (from direct gamma dose) has not been recalculated for the NUREG-1465 source term. The combined containment direct gamma and cloud direct gamma doses are reported in CEI Calculation No. 3.2.6.5 as 0.13 rem and 0.002 rem, respectively, over 30 days. It is possible that the direct dose could increase slightly using NUREG-1465 source term (due to the increased radiocesium in liquid in the long term), but it is expected there would be a substantial corresponding decrease in the secondary containment airborne dose contribution. Moreover, with application of the revised DBA source term the whole body dose contribution from sources within the control room has remained low (4.12 mm) and therefore, there is no possibility that the 10CFR50, Appendix A, GDC-19 whole body dose acceptance value of 5 rem would be exceeded even in the unlikely event there were a small net increase in the contribution from external sources. Conclusions The main conclusions from the dose calculation are as follows: The failure of the four third isolation valves to close is the limiting single failum for the revised source term application to the Perry Plant. All doses for the limiting single failure meet regulatory limits with considerable  ; margin (roughly a factor of 2 margin). '

Attechment 6 PY-CELNRR-2076L Page 184 of 217 PSAT 04202H.13 Page: 17 of 20 Rev: 0@23 4 Windows / Graphical User interface y f 3 NEDG.MDB LOCADOSE CENTER 4 ( - 1.3 A 1.1 y gg LOCATRANS LOCADOSE input File input File 22 A 21 Question & 2 LT Answer ActivityTransport Session Program

            /   24                    \ 23 42 4

y 4.1 LF FitterLoading Output FIe LOCATRAN k " v 4.4 Output FIe 3.3 3 LD # Dose Calculation 32 31 p Program 4 y 3.4 Output FIe Exhibit 1 LOCADOSE Program Structure (taken from Reference [3])

n-> ,~m o l i PY-CEl/NRR-2076L ' l Page 185 of 217 l l PSAT 04202H.13 Page 18 of 20 Rev: 0@2 3 4 i l EXHIBn 2 i PERRY REVISED DBA SOURCE TERM DOSE McDEL l Third Isolar Vake

h l l l l

Outboari MSN Steam the l Rotenten M Aerosol pray Lambda

                                                                ~3 8 hr 1 (0-2 h)
                                                             -0.2 1.2 hr-1 (>2 hr)              HEPA Finer Efic=95%

Charcoal Fher O.625otm / Enic=50% 12. Org i inboard / (27,000 dm aber 30 rrdn (>40 eic) MSIV tocre delay) MSN Leak __

                                                             '"      ***I 100sd m                                               0.068 ct T=40 nee) 250 sdh total 7Ed d n                                                   Y N        %fahment
        @eg                                                                ypass y                               Leakage

• kg Lambda 6200 dm "*

4.4 hr-1 0.5-? hr) ' 2.0 dm (<40 see) A2 hr) 1E5 dm C'-2.03 hr) 0.14 dm f=40 sec) Region l 5(0 dm (>2.(8 h' O.033 dm 8.7 dm l - - (<24 hr. >24.5 hr) (24 24.5 hr) l 125 cfm g (>40 sec) Flashing Fker Effio=90% at lodne 2000 dm j

                                                     -                                      Suppression Annulus                           HEPA Fmer "I

Aerosol Removal Effc=99% ESF Lealage l l

l Main Steam Line Isolation Valve Configuration (1) g e i O ~ n  ! S I

                                                                                                                                                                                                                                          ?

8 i Drywell SB Wall CV Wall l l IB MSIV g g g OB MSIV 100 SCFH 3rd IV T  !! wm 41.5 feet 49 feet 29 feet $$

                                                                                                                                                                                                                                      - o e5 "R

w "s! i d U$ p

Main Steam Line Isolation Valve Configuration (2) gl 2 i E  ! l Y i 8 i Drywell SB  ! Wall CV Wall lB MSIV g g g OB MSIV 100 SCFH 3rd IV l RP

            ----===>                                                                      4======== > < =

o o 41.5 feet 49 feet 29 feet

['$ gg I: NO O si n P ,

Atannent o PY-CEl/NRR-2076L Page 188 of 217 PSAT 04202H.13 Page Al of A2 Rev. 0@2 3 4 Appendix A: " LIBRARY file" version 2.0 CEDE Thryoid Red MarrowBeta Skin Whole Body I--131 2.722E+04 9.976E-07 3.000E+04 2.000E+06 2.200E+02 1.120E-01 6.060E-02 01 1 22 00 00 00 00 00 1.100E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 01 1.817E-01 3.789E-01 1 22 002.722E+04 2--131 00 00 00 009.976E-07 3.000E+04 1.000E+06 2.200E+02 1.120E-01 6.060E-02 02 1.100E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 02 1.817E-01 3.789E-01 I--131 2.722E+04 9.976E-07 3.000E+04 1.000E+06 2.200E+02 1.120E-01 6.060E-02 03 1 22 00 00 00 00 00 1.100E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 03 1.817E-01 3.789E-01 I--132 00 003.922E+04 00 00 00 008.425E-05 3.600E+02 5.900E+03 4.800E+01 6.180E-01 3.770E-01 01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 29 4.824E-01 3.559E+00 I--132 00 003.922E+04 00 00 00 008.425E-05 3.600E+02 5.900E+03 4.800E+01 6.180E-01 3.770E-01 02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 30 4.824E-01 3.559E+00 I--132 00 003.922E+04 00 00 00 008.425E-05 3.600E+02 5.900E+03 4.800E+01 6.180E-01 3.770E-01 03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 31 4.824E-01 3.559E+00 I--133 2 24 23 5.495E+04 00 00 00 9.211E-06 00 5.800E+03 1.800E+05 9.600E+01 2.210E-01 9.730E-02 01 9.710E-01 2.900E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 04 4.067E-01 6.047E-01 I--133 2 24 23 5.495E+04 00 00 00 9.211E-06 00 5.000E+03 1.800E+05 9.600E+01 2.210E-01 9.730E-02 02 9.710E-01 2.900E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 05 4.067E-01 6.047E-01 I--133 2 5.495E+04 24 23 00 00 00 9.211E-06 00 5.800E+03 1.800E+05 9.600E+01 2.210E-01 9.730E-02 03 9.710E-01 2.900E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 06 4.067E-01 6.047E-01 I--134 00 006.022E+04 00 00 00 00 2.200E-04 1.300E+02 1.000E+03 2.200E+01 7.320E-01 4.380E-01 01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 07 6.052E-01 2.620E+00 . I--134 00 006.022E+04 00 00 00 002.200E-04 1.300E+02 1.000E+03 2.200E+01 7.320E-11 4.380E-01 02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 08 6.052E-01 2.620E+00 I--134 00 006.022E+04 00 00 00 00 2.200E-04 1.300E+02 1.000E+03 2.200E+01 7.320E-01 4.380E-01 03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 09 6.052E-01 2.620E+00 .I--135 2 26 25 5.149E+04 00 00 00 2.912E-05 00 1.200E+03 3.000E+04 7.800E+01 4.340E-01 2.640E-01 01 B.450E-01 1.550E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 10 3.691E-01 1.617E+00 I--135 5.149E+04 2.912E-05 1.200E+03 3.000E+04 7.800E+01 4.340E-01 2.640E-01 02 2262500000000

                                                                                                          \

8.450E-01 1.550E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 11 3.691E-01 1.617E+00 ' I--135 5.149E+04 2.912E-05 1.200E+03 3.000E+04 7.800E+01 4.340E-01 2.640E-01 03 2262500000000 8.450E-01 1.550E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 12 3.691E-01 1.617E+00 KR-83M 00 00 00 3.230E+03 00 00 001.052E-04 0.000E+00 0.000E+00 0.000E+00 1.360E-04 1.490E-05 04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 13 0.000E+00 4.610E-04 KR--85 4.25BE+02 00 00 00 00 00 002.054E-09 0.000E+00 0.000E+00 0.000E+00 5.010E-02 3.550E-04 04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 32 2.505E-01 2.236E-03 KR-85M 1 17 00 00 6.703E+03 00 00 004.297E-05 0.000E+00 0.000E+00 0.000E+00 0.310E-02 2.590E-02 04 2.100E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 14 2.902E-01 1.610E-01 KR--87 1 00 001.274E+04 00 00 00 001.514E-04 0.000E+00 0.000E+00 0.000E+00 5.230E-01 1.420E-01 04 1.000E+00 KR--88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 15 1.324E+00 8.032E-01 1.732E+04 1 00 00 00 00 00 00 6.731E-05 0.000E+00 0.000E+00 0.000E+00 5.490E-01 3.580E-01 04 1.000E+00 KR--89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 16 3.587E-01 1.981E+00 2.171E+04 1 00 00 00 00 00 00 3.632E-03 0.000E+00 0.000E+00 0.000E+00 7.710E-01 3.230E-01 04 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 17 1.363E+00 1.867E+00

Attesnment 6 PY-CEl/MRR-2076L Page 1890f 217 PSAT 04202H.13 Page A2of A2 Rev. 0@2 3 4 XE131M 00 00 003.060E+02 00 00 00 6.815E-07 0.000E+00 0.000E+00 0.000E+00 1.780E-02 1.360E-03 04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 18 0.000E+00 3.116E-03 XE133M 1 24 00 001.724E+03 00 00 00 3.663E-06 0.000E+00 0.000E+00 0.000E+00 3.840E-02 4.720E-03 04 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 19 0.000E+00 2.332E-02 XE-133 5.279E+04 00 00 00 00 00 00 1.528E-06 0.000E+00 0.000E+00 0.000E+00 1.840E-02 5.580E-03 04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 20 1.004E-01 2.997E-02 XE135M 1.093E+04 7.380E-04 0.000E+00 0.000E+00 0.000E+00 1.130E-01 6.820E-02 04 1260000000000 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 21 3.000E-01 4.266E-0 XE-135 1 00 00 001. 00 900E+04 00 00 2.115E-05 0.000E+00 0.000E+00 0.000E+00 1.150E-01 3. 960E-02 04 1.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 22 3.02BE-01 2.466 XE-137 1 30 00 004.792E+04 00 00 00 3.024E-03 0.000E+00 0.000E+00 0.000E+00 5.010E-01 3.030E-02 04 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 23 1.774E+00 1.895 XE-138 1 00 00 004.476E+04 00 00 00 8.151E-04 0.000E+00 0.000E+00 0.000E+00 4.090E-01 1.990E-01 04 1.000E+00 CS-134 0.000E+00 8.060E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.066E-08 4.300E+04 24 6.140E-01 1.241 00 00 00 00 00 00 4.000E+04 4.400E+04 3.710E-01 2.540E-01 05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 25 1.568E-01 1. CS-137 1 32 00 004.643E+03 00 00 00 7.284E-10 3.000E+04 2.900E+04 3.100E+04 2.770E-02 0.000E+00 05 9.460E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 26 1.708E-01 0.0 TE-132 3 04 05 063.856E+04 00 00 00 2.462E-06 8.600E+03 2.100E+05 1.300E+03 5.040E-02 3.460E-02 06 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 27 5.940E-02 2. BA137M 3.328E+03 00 00 00 00 00 00 4.529E-03 0.000E+00 0.000E+00 0.000E+00 1.460E-01 9.700E-02 07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 28 0.000E+00 5. s

PY-CEI!NRR-2076L Page 190 of 217 PSAT 04202H.13 Page B1 of B26 Rev. 0@2 3 4 Appendix B: "LOCATRAN Input Files" For Confieuration1 1 PERRY DOSE CALC. W/ REVISED SOURCE TERM, CFG 1, 24 HR SPRAY 2 JUN LI Problem title 3 Originator PERRY DOSE CALC. Project name 4 PSAT 04202H Project 8 0 04202H.13 0 6 Calc 9, Rev 1 First page 6 of output 7 8 12 32 1 0 0 0 Nodes, f Time steps, f Iso, ICR, CALCDA, LSPRAY 8 1 0 3758 0 2 0 0 ITID, IPURGE, Power, SD time, NPF, 4 Spr nodes, 4 Delay cales 9 CIM CUFT CURIES 10 111111111111 Flow unit, Volume unit, Activity unit 11 0.0485 0.0015 0.95 Release frac for iso group 1-12 12 Elem, org, part iodine frac 13 DRYWELL 8.333E-3 UNSPRAYED 0.011111 1001SPRAYED ANNULUS SUP POOL STL_CV_1 STL_CV_2 STL_CV_3 Node name 14 011 From time, To time, IFRTAC, IAACT, IPACT, IPRINT 15 LACTIN, LPTIN, LVOL 0.100000 0 0 0 0.6 0 0 0 Initial I-131 elem act frac in nodes 2-9 16 0.100000 0 0 0 0.6 0 0 0 1*/ Initial 2-131 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-131 part act frac in nodes 2-9 18 0.100000 0 0 0 0.6 0 0 0 89 0.100000 0 0 0 0.6 0 0 0 Initial I-132 elem act frac in nodes 2-9 20 Initial I-132 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-132 part act frac in nodes 2-9 21 0.100000 0 0 0 0.6 0 0 0 23 0.100000 0 0 0 0.6 0 0 0 Initial I-133 elem act frac in nodes 2-9 23 Initial I-133 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-133 part act frac in nodes 2-9 24 0.100000 0 0 0 0.6 0 0 0 25 0.100000 0 0 0 0.6 0 0 0 Initial I-134 ela act frac in nodes 2-9 36 Initial I-134 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-134 part act frac in nodes 2-9 37 0.100000 0 0 0 0.6 0 0 0 30 0.100000 0 0 0 0.6 0 0 0 Initial I-135 elem act frac in nodes 2-9 39 Initial I-135 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-135 part act frac in nodes 2-9 30 0.100000 0 0 0 0 000 3& 0.100000 0 0 0 0 000 Initial Kr-83m act frac in nodes 2-9 32 0.100000 0 0 0 0 000 Initial Kr-85 act frac in nodes 2-9 i 33 0.100000 0 0 0 0 000 Initial Kr-85m act frac in nodes 2-9 l 34 0.100000 0 0 0 0 000 Initial Kr-87 act frac in nodes 2-9 1 35 0.100000 0 0 0 0 000 Initial Kr-88 act frac in nodes 2-9 36 0.100000 0 0 0 0 000 Initial Kr-89 act frac in nodes 2-9 37 0.100000 0 0 0 0 000 Initial Xe-131m act frac in nodes 2-9 38 0.100000 0 0 0 0 000 Initial Xe-133m act frac in nodes 2-9 39 0.100000 0 0 0 0 000 Initial Xe-133 act frac in nodes 2-9 40 0.100000 0 0 0 0 000 Initial Xe-135m act frac in nodes 2-9 41 0.100000 0 0 0 0 000 Initial Xe-135 act frac in nodes 2-9 43 0.100000 0 0 0 0 000 Initial Xe-137 act frac in nodes 2-9 43 0.100000 0 0 0 0 000 Initial Xe-138 act frac in nodes 2-9 44 0.100000 0 0 0 0 000 Initial CS-134 act frac in nodes 2-9 45 00000 000 Initial CS-137 act frac in nodes 2-9 46 00000 000 Initial TE-132 act frac in nodes 2-9 47 Initial BA137M act frac in nodes 2-9 48 276500. 684226. 2 7 0 1.987 481174. 1.96E+5 146952. 146. 440. 292. Volumes for nodes 2-9 49 From node, To node, Filt flow, Unfilt flow 000000000000 Filt off for iso groups 1-12 50 2 8 0 2.98 From node, To node, Filt flow, Unfilt flow 91 000000000000 Filt off for iso groups 1-12 53 8 9 4.*J75 0 From node, To node, Filt flow, Unfilt flow 53 54 50074.6074.674.674.674.674.674.674.674.6 Filt off 4 iso grps 1-12 7 1 3.183 0 1 From node, To node, Filt flow, Unfilt flow ' 55 50 0 58.2 0 58.2 58.2 58.2 58.2 58.2 58.2 58.2 58.2 Filt off 4 iso grps 1-12 56 9 1 4.775 0 From node, To node, Filt flow, Unfilt flow 37 50 0 62.4 0 62.4 62.4 62.4 62.4 62.4 62.4 62.4 62.4 Filt off 4 iso grps 1-12 58 3 1 0 2.01 From node, To node, Filt flow, Unfilt flow 59 000000000000 Filt off for iso groups 1-12 60 3 4 0 11400. From node, To node, Filt flow, Unfilt flow 61 000000000000 Filt off for iso groups 1-12

Attachment b PY CE!!NRR 2076L Page 191 of217 PSAT 04202H.13 Page B2 of B26 Rev. 0@2 3 4 62 3 5 0 3.0E-5 From node, To node, Filt flow, Unfilt flow 63 000000000000 Filt eff for iso groups 1-12 64 4 1 0 1.005 From node, To node, Filt flow, Unfilt flow 65 000000000000 Filt eff for iso groups 1-12 66 4 3 0 71400. From node, To node, Filt flow, Unfilt flow 67 000000000000 Filt eff for iso groups 1-12 68 4 5 0 1.0E-5 From node, To node, Filt flow, Unfilt flow 69 000000000000 Filt eff for iso groups 1-12 70 5 1 2000. O From node, To node, Filt flow, Unfilt flow 71 0 0 99 0 99 99 99 99 99 99 99 99 (Item 4.1) Filt eff for iso groups 1-12 72 6 1 1.0E-05 0 From node, To node, Filt flow, Unfi~' flow 1 73 99 99 99 99 99 99 99 99 99 99 99 99 74 -1,0,0,0 Filt eff for iso groups 1-12 End flow input 75 1 2 0.084 Iso group, Node, Lambda 76 3 2 0.084 Iso group, Node, Lambda 77 5 2 0.084 Iso group, Node, Lambda 78 6 2 0.084 Iso group, Node, Lambda j 79 7 2 0.084 Iso group, Node, Lambda ) 80 8 2 0.084 Iso group, Node, Lambda 81 9 2 0.084 Iso group, Node, Lambda 82 10 2 0.084 Iso group, Node, Lambda 83 11 2 0.084 Iso group, Node, Lambda 84 12 2 0.004 Iso group, Node, Lambda 85 -1,0,0,0 86 1 7.0E-5 End lambda input 87 LCHG, Control room X/Q 3.44E5 0 1375 2.7E4 1375 CR vol, Filt intake,Unfilt intake,Recirc,Outleak 88 000000000000 89 000000000000 Intake filt eff for iso groups 1-12 90 (Item 4.2) Recirc filt eff for iso groups 1-12 0.011111 0.016333 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IFRINT 91 000 92 3 1 0 0.135 LACTIN, LPTIN, LVOL 93 From node, To node, Filt flow, Unfilt flow 000000000000 Filt eff for iso groups 1-12 94 3 5 0 1.205 From node, To node, Filt flow, Unfilt flow 95 000000000000 96 4 1 0 0.0675 Filt eff for iso groups 1-12 97 From node, To node, Filt flow, Unfilt flow 000000000000 Filt eff for iso groups 1-12 98 4 5 0 0.603 From node, To node, Filt flow, Unfilt flow 99 000000000000 100 -1,0,0,0 Filt eff for iso groups 1-12 101 -1,0,0,0 End flow input 102 0 7.0E-5 End lambda input 103 0.018333 0.175 1 0 0 1 LCHG, Control room X/O , i 104 000 From time, To time, IFRTAC, IAACT, IPACT, IFRINT l 105 -1,0,0,0 LACTIN, LPTIN, LVOL ' 106 12 0.184 End flow input 107 32 0.184 Iso group, Node, Lambda  ; 108 52 0.184 Iso group, Node, Lambda ~ 109 62 0.184 Iso group, Node, Lambda 110 72 0.184 Iso group, Node, Lambda all 82 0.184 Iso group, Hode, Lambda 212 92 0.184 Iso group, Node, Lambda l 113 10 2 0.184 Iso group, Node, Lambda 114 11 2 0.184 Iso group, Node, Lambda 115 12 2 0.184 Iso group, Node, Lambda 116 -1,0,0,0 Iso group, Node, Lambda 117 0 7.0E-5 End lambda input 118 0.175 0.19167 1 0 0 1 LCHG, Control room X/O 119 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 130 6 1 0.03342 0 LACTIN, LPTIN, LVOL 131 From node, To node, Filt flow, Unfilt flow 122 90 90 90 90 90 90 90 90 90 90 90 90 Filt eff for iso groups 1-12

     -1,0,0,0 133   -1,0,0,0                                                            End flow input 134   0 7.0E-5                                                          End lambda input 135                                                              LCHG, Control room X/Q 0.19167 0.20222 1 0 0 1      From time, To time, IFRTAC, IAACT, IPACT, IPRINT 136   000 137   -1,0,0,0                                                      LACTIN, LPTIN, LVOL 138   14    8.13                                                          End flow input 139   34 8.13                                                  Iso group, Node, Lambda Iso group, Node, Lambda

nu m. I PY CEVNRR-2076L Page 192 of 217 PSAT 04202H.13 Page B3 of B26 Rev. 0@2 3 4 130 54 8.13 131 64 8.13 Iso group, Node, Lambda , Iso group, Node, Lambda 133 74 8.13 133 Iso group, Node, Lambda 84 8.13 Iso group, Node, Lambda 134 94 8.13 135 10 4 0.13 Iso group, Node, Lambda Iso group, Node, Lambda 136 11 4 8.13 Iso group, Node, Lambda 137 12 4 8.13 Iso group, Node, Lambda 138 -1,0,0,0 139 0 7.0E-5 End lambda input 140 LCHG, Control room X/O 0.20222 0.25667 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT i 141 000 j 143 -1,0,0,0 LACTIN, LPTIN, LVOL 143 14 4.32 End flow input 144 34 4.32 Iso group, Node, Lambda 143 54 4.32 Iso group, Node, Lambda 146 64 Iso group, Node, Lambda 4.32 Iso group, Node, Lambda l 147 74 4.32 I 148 84 4.32 Iso group, Node, Lambda j 149 94 4.32 Iso group, Node, Lambda 150 10 4 4.32 Iso group, Node, Lambda 151- 11 4 4.32 Iso group, Node, Lambda 153 12 4 4.32 Iso group, Node, Lambda 153 -1,0,0,0 Iso group, Node, Lambda 154 0 7.0E-5 End lambda inpot 155 0.25667 0.33333 1 0 0 3 LCHG, Control room X/O 156 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 157 -1,0,0,0 LACTIN, LPTIN, LVOL 158 End flow input l 14 3.02 159 34 3.02 Iso group, Node, Lambda i 160 54 3.02 Iso group, Node, Lambda 161 64 3.02 Iso group, Node, Lambda ) 163 74 3.02 Iso group, Node, Lambda A63 84 3.02 Iso group, Node, Lambda 164 94 3.02 Iso group, Node, Lambda 165 10 4 3.02 Iso group, Node, Lambda 166 11 4 3.02 Iso group, Node, Lambda i l 167 12 4 3.02 Iso group, Node, Lambda 168 -1,0,0,0 Iso group, Node, Lambda 169 0 7.0E-5 End lambda input 170 0.33333 0.36583 1 0 0 1 LCHG, Control room X/O 171 001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 173 LACTIN, LPTIN, LVOL A73 276500. 7 1 3.183684226. 0 481174.1.96E+5146952. 232. 440. 464. Volumes for nodes 2-9 A74 From node, To node, Filt flow, Unfilt flow 175 50 9 1 04.775 92.9 00 92.9 92.9 92.9 92.9 92.9 92.9 92.9 92.9 Filt off 4 iso grps 1-12 A76 From node, To node, Filt flow, Unfilt flow 877 50 0 83.9 0 83.9 83.9 83.9 83.9 83.9 83.9 83.9 83.9 Filt eff 4 iso grps 1-12

       -1,0,0,0 A78   -1,0,0,0                                                          End flow input 179   0 7.0E-5                                                        End lambda input 180   0.36583 0.475     1001                                    LCHG, Control room X/Q ABA-  000                          From time, To time, IPRTAC, IAACT, IPACT, IPRINT 183   -1,0,0,0                                                     LACTIN, LPTIN, LVOL 183   1 4 2.52                                                          End flow input 184   34 2.52                                                Iso group, Node, Lambda 185   54 2.52                                                Iso group, Node, Lambda 186   64 2.52                                                Iso group, Node, Lambda 187   74 2.52                                                Iso group, Hode, Lambda 188   84 2.52                                                Iso group, Node, Lambda 189   94 2.52                                                Iso group, Node, Lambda 190   10 4 2.52                                              Iso group, Node, Lambda 191   11 4 2,52                                              Iso group, Node, Lambda 193   12 4 2.52                                              Iso group, Node, Lambda 193   -1,0,0,0                                               Iso group, Node, Lambda 194   0 7.0E-5                                                        End lambda input 195   0.475 0.500000 1001                                       LCHG, Control room X/O 196   000                          From time, To time, IPRTAC, IAACT, IPACT, IPRINT 197   -1,0,0,0                                                     LACTIN, LPTIN, LVOL End flow input

Attachment o PY-CE!!NRR-2076L Page 193 nf 217 PSAT 04202H.13 Page B4 of B26 Rev. 0@2 3 4 198 14 14.3 Iso group, Node, Lambda 199 34 14.3 Iso group, Node, Lambda 200 54 14.3 Ise group, Node, Lambda 201 64 14.3 Iso soup, Node, Lambda 202 74 14.3 Iso gssup, Node, Lambda 203 84 14.3 Iso group, Node, Lambda 204 94 14.3 Iso group, Node, Lambda 205 10 4 14.3 Iso group, Node, Lambda 206 11 4 14.3 Iso group, Node, Lambda 207 12 4 14.3 Iso group, Node, Lambda 208 -1,0,0,0 209 0 7.0E-5 End lambda input 210 LCHG, Control room X/Q 0.500 0.508333 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 211 000 LACTIN, LPTIN, LVOL 212 7 1 3.183 0 From node, To node, Filt flow, Unfilt flow 213 50 0 95.9 0 95.9 95.9 95.9 95.9 95.9 95.9 95.9 95.9 Filt eff 4 iso grps 1-12 214 9 1 4.775 0 From node, To node, Filt flow, Unfilt flow 215 216 50 0 91.4 0 91.4 91.4 91.4 91.4 91.4 91.4 91.4 91.4 Filt eff 4 iso grps 1-12

      -1,0,0,0 217   -1,0,0,0                                                           End flow input 318   0 7.0E-5                                                         End lambda input 219                                                             LCHG, Control room X/Q 0.50833 0.51861 1 0 0 1    From time, To time, IFRTAC, IAACT, IPACT, IPRINT 220   010 221                                                                LACTIN, LPTIN, LVOL 0.1666667 0 0 0 0 0 0 0             Initial I-131 elem act frac in nodes 2-9 222   0.1666667 0 0 0 0 0 0 0 223                                       Initial I-131 orgn act frac in nodes 2-9 0.16666670000000                    Initial I-131 part act frac in nodes 2-9 224   0.1666667 0 0 0 0 0 0 0                                                                   -

225 0.1666667 0 0 0 0 0 0 0 Initial I-132 elem act frac in nodes 2-9 236 Initial I-132 orgn act frac in nodes 2-9 0.1666667 0 0 0 0 0 0 0 Initial I-132 part act frac in nodes 2-9 227 0.1666667 0 0 0 0 0 0 0 228 0.1666667 0 0 0 0 0 0 0 Initial I-133 elem act frac in nodes 2-9 239 Initial I-133 orgn act frac in nodes 2-9 0.1666667 0 0 0 0 0 0 0 Initial I-133 part act frac in nodes 2-9 330 0.1666667 0 0 0 0 0 0 0 231 0.1666667 0 0 0 0 0 0 0 Initial I-134 elem act frac in nodes 2-9 332 Initial I-134 orgn act frac in nodes 2-9 0.1666667 0 0 0 0 0 0 0 Initial I-134 part act frac in nodes 2-9 233 0.1666667 0 0 0 0 0 0 0 234 0.1666667 0 0 0 0 0 0 0 Initial I-135 elem act frac in nodes 2-9 235 0.1666667 0 0 0 0 0 0 0 Initial I-135 orgn act frac in nodes 2-9 236 Initial I-135 part act frac in nodes 2-9 0.6333333 0 0 0 0 0 0 0 Initial Kr-83m act frac in nodes 2-9 237 0.6333333 0 0 0 0 0 0 0 338 0.6333333 0 0 0 0 0 0 0 Initial Kr-85 act frac in nodes 2-9 339 0.6333333 0 0 0 0 0 0 0 Initial Kr-85m act frac in nodes 2-9 240 0.6333333 0 0 0 0 0 0 0 Initial Kr-87 act frac in nodes 2-9 241 0.6333333 0 0 0 0 0 0 0 Initial Kr-88 act frac in nodes 2-9 242 0.6333333 0 0 0 0 0 0 0 Initial Kr-89 act frac in nodes 2-9 243 0.6333333 0 0 0 0 0 0 0 Initial Xe-131m act frac in nodes 2-9 244 0.6333333 0 0 0 0 0 0 0 Initial Xe-133m act frac in nodes 2-9 345 0.6333333 0 0 0 0 0 0 0 Initial Xe-133 act frac in nodes 2-9 346 0.6333333 0 0 0 0 0 0 0 Initial Xe-135m act frac in nodes 2-9 347 0.6333333 0 0 0 0 0 0 0 Initial Xe-135 act frac in nodes 2-9 348 0.6333333 0 0 0 0 0 0 0 Initial Xe-137 act frac in nodes 2-9 349 0.1333333 0 0 0 0 0 0 0 Initial Xe-138 act frac in nodes 2-9 250 0.1333333 0 0 0 0 0 0 0 Initial CS-134 act frac in nodes 2-9 351 0.0333333 0 0 0 0 0 0 0 Initial CS-137 act frac in nodes 2-9 252 0.0133333 0 0 0 0 0 0 0 Initial TE-132 act frac in nodes 2-9 353 2 3 0 6180.0 Initial BA137H act frac in nodes 2-9 254 000000000000 From node, To node, Filt flow, Unfilt flow 235 -1,0,0,0 Filt eff for iso groups 1-12 256 -1,0,0,0 ' End flow input 357 1 1.0E-5 End lambda input 258 LCHG, Control room X/O 3.44E5 0 1375 2.7E4 1375 CR vol,Filt intake,Unfilt intake,Recire,Outleak 259 000000000000 360 Intake filt eff for iso groups 1-12 261 50509509595959595959595(4.2) Recirc filt eff for iso groups 1-12 0.51861 0.52694 1001 262 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 263 -1,0,0,0 LACTIN, LPTIN, LVOL 364 12 0.25 End flow input 365 32 0.25 Iso group, Node, Lambda Iso group, Node, Lambda

                                                                                              <u w msm o                       ;

PY CEUNRR-2076L  ! Pqc 194 cf 217 I PSAT 04202H.13 Page B5 of B26 Rev. 0@2 3 4 266 52 0.25 Iso group, Node, Lambda 2 67 62 0.25 Iso group, Node, Lambda 268 72 0.25 Iso group, Node, Lambda 269 82 0.25 Iso group, Node, Lambda 270 92 0.25 Iso group, Node, Lambda 371 10 2 0.25 Iso group, Node, Lambda 273 11 2 0.25 Iso group, Node, Lambda 273 12 2 0.25 Iso group, Node, Lambda 2*14 -1,0,0,0' End lambda input 373 0 7.0E-5 LCHG, Control roam X/Q 276 0.52694 0.575 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 377 000 LACTIN, LPTIN, LVOL 378 -1,0,0,0 F,nd flow input 379 14 8.76 Iso group, Node, Lambda 280 34 8.76 Iso group, Node, Lambda 281 54 8.76 Iso group, Node, Lambda 282 64 8.76  ! Iso group, Node, Lambda 283 74 8.76 Iso group, Node, Lambda 284 84 8.76 Iso group, Node, Lambda 285 94 8.16 Iso group, Node, Lambda 286 10 4 8.16 287 Iso group, Node, Lambda 11 4 8.76 Iso group, Node, Lambda 288 12 4 8.76 289' Iso group, Node, Lambda

     -1,0,0,0 290                                                                      End lambda input 0 7.0E-5                                                    LCHG, Control room X/Q

,291 0.575 0.7025 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 292 000 393 -1,0,0,0 LACTIN, LPTIN, LVOL 294 End flow input 14 5.07 Iso group, Node, Lambda 395 34 5.07 296 Iso group, Node, Lambda 54 5.07 Iso group, Node, Lambda 297 64 5.07 398 Iso group, Node, Lambda 74 5.07 Iso group, Node, Lambda 399 84 5.07 300 94 5.07 Iso group, Node, Lambda 301 10 4 5.07 Iso group, Node, Lambda l 303 11 4 5.07 Iso group, Node, Lambda  ! 303 12 4 5.07 Iso group, Node, Lambda  ! 304 -1,0,0,O Iso group, Node, Lambda  ; 305 0 7.0E-5 End lambda input j 306 LCHG, Control room X/Q 307 0.7025 0.8725 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT l 000  ! 308 -1,0,0,0 . LACTIN, LPTIN, LVOL i 309 14 3.84 End flow input ' 310 34 Iso group, Node, IAmbda 3.84 311 Iso group, Node, Lambda 54 3.84 Iso group, Node, Lambda 313 64 3.84 1 313 Iso group, Node, Lambda 74 3.84 Iso group, Node, Lambda  ! 314 84 3.84 Iso group, Node, Lambda l 315 94 3.84 316 10 4 3.84 Iso group, Node, Lambda 317 11 4 3.84 Tso group, Node, Lambda Iso group, Node, Lambda 318 12 4 3.84 Iso group, Node, Lambda 319 -1,0,0,0 320 0 7.0E-5 End lambda input i 321 LCHG, Control room X/O ' 0.8725 0.88972 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 322 000 323 -1,0,0,0 1 ACTIN, LPTIN, LVOL , 334 14 3.25 End flow input i 335 Iso group, Node, Lambda 34 3.25 Iso group, Node, Lambda I 326 54 3.25 337 64 3.25 Iso group, Node, Lambda 338 74 3.25 Iso group, Node, Lambda j 329 84 3.25 Iso group, Node, Lambda I 330 94 3.25 Iso group, Node, Lambda  ! 331 10 4 3.25 Iso group, Node, Lambda 333 11 4 3.25 Iso group, Node, Lambda Iso group, Node, Lambda 333 12 4 3.25 Iso group, Node, Lambda

PY CE!/NRR-2076L

• Page 195 of 217 PSAT 04202H.13 Page B6 of B26 Itev. 06)2 3 4 ,

334 -1,0,0,0 End lambda input 335- 0 7.0E-5 LCHG, Control room X/Q l 336 0.88972 1.11944 1 0 0 1 From time, To time, IFRTAC, IAACT, IPACT, IPRINT  ! 331 000 LACTIN, LPTIN, LVOL 338 .-1,0,0,0 End flow input 339 12 0.35 Iso group, Node, Lambda , 340 32 0.35 Iso group, Node, Lambda 341 52 0.35 Iso group, Node, Lambda 342 62 0.35 Iso group, Node, Lambda 343 72 0.35 Iso group, Node, Lambda 344 82 0.35 Iso group, Node, Lambda 345 92 0.35 Iso group, Node, Lambda 346 10 2 0.35 Iso group, Node, Lambda 347 11 2 0.35 Iso group, Node, Lambda 348 12 2 0.35 Iso group, Node, Lambda 349 -1,0,0,0 End lambda input 350 0 7.0E-5 LCHG, Control room X/Q 351 1,11944 1.21778 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IFRINT ' 352 000 LACTIN, LPTIN, LVOL 353 -1,0,0,0 End flow input 354 14 3.22 Iso group, Node, Lambda 355 34 3.22 Iso group, Node, Lambda 356 54 3.22 Iso group, Node, Lambda 357 64 3.22 Iso group, Node, Lambda 358 74 3.22  ! Iso group, Node, Lambda j 359 84 3.22 Iso group, Node, Lambda 360 94 3.22 i Iso group, Node, Lambda 361 10 4 3.22 ] Iso group, Node, f==hda 362 11 4 3.22 Iso group, Node, Lambda i 363 12 4 3.22 j 364 Iso group, Node, Lambda

          -1,0,0,O                                                                                                         l 365                                                               End lambda input 0 7.0E-5                                             LCHG, Control room X/Q 366    1.21778 1.48306 1 0 0 1 367                              From time, To time, IFRTAC, IAACT, IPACT, IFRINT 000                                                     LACTIN, LPTIN, LVOL 368   -1,0,0,0 369

• End flow input 12 0.45 Iso group, Node, Lambda 370 32 0.45 371 Iso group, Node, Lambda 52 0.45 Iso group, Node, Lambda 372 62 0.45 373 Iso group, Node, Lambda 72 0.45 Iso group, Node, Lambda 374 82 0.45 375 Iso group, Node, Lambda 92 0.45 Iso group, Node, tambda 376 10 2 0.45 Iso group, Node, Lambda 377 11 2 0.45 Iso group, Node, Lambda 378 12 2 0.45 Iso group, Node, Lambda 379 -1,0,0,0 380 0 7.0E-5 End lambda input 381 LCHG, Control room X/Q 1.48306 1.50000 1 0 0 1 From time, To time, IPRTAC, iAACT, IPACT, IPRINT 382 000 383 -1,0,0,0 LACTIN, LPTIN, LVOL 384 End flow input 14 3.30 Iso group, Node, Lambda 385 34 3.30 386 Iso group, Node, Lambda 54 3.30 Iso group, Node, Lambda 387 64 3.30 388 74 3.30 Iso group, Node, Lambda 389 Iso group, Node, Lambda 84 3.30 Iso group, Node, Lambda 390 94 3.30 Iso group, Node, Lambda 391 10 4 3.30 Iso group, Node, fa=hda 392 11 4 3.30 Iso group, Node, Lambda 393 12 4 3.30 Iso group, Node, Lambda l

394 -1,0,0,0  ! 395 0 7.OE-5 End lambda input  ! 396 LCHG, Control room X/Q l 1.50000 1.62833 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 397 000  !

 - 398 LACTIN, LPTIN, LVOL 7 1 3.183 0                      From node, To node, Filt flow, Unfilt flow                                      j 399   50 0 96.6 0 96.6 96.6 96.6 96.6 96.6 96.6 96.6 96.6 Filt off 4 iso grps 1-12                                     ;

400 9 1 4.775 0 From node, To node, Filt flow, Untilt flow j 401 50 0 92.8 0 92.8 92.8 92.8 92.8 92.8 92.8 92.8 92.8 Filt eff 4 iso grps 1-12

Attacnment b PY-CEl/MRR-2076L Page 196 of 217 i PSAT 04202H.13 Page B7 of B26 l l Rev. 06)2 3 4 i 402 -1,0,0,0 ! 403 -1,0,0,0 End flow input End lambda input 404 0 7.0E-5 LCHG, Control room X/Q l 405 1.62833 1.86167 1 0 0 1 406 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 407 -1,0,0,0 LACTIN, LPTIN, LVOL 400 12 0.54 End flow input 409 Iso group, Node, Lambda 32 0.54 Iso group, Node, Lambda 410 52 0.54 411 Iso group, Node, Lambda 62 0.54 Iso group, Node, Lambda 412 72 0.54 413 Iso group, Node, Lambda 82 0.54 Iso group, Node, Lambda 414 92 0.54 415 10 2 0.54 Iso group, Node, Lambda 416 11 2 0.54 Iso group, Node, Lambda 417 12 2 0.54 Iso group, Node, Lambda 418 -1,0,0,0 Iso group, Node, Lambda 419 0 7.0E-5 End lambda input 420 LCHG, Control room X/Q 1.86167 2.00000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 421 000 422 -1,0,0,0 LACTIN, LPTIN, LVOL 423 14 6.55 End flow input 434 34 6.55 Iso group, Node, Lambda 425 54 6.55 Iso group, Node, Lambda 436 64 6.55 Iso group, Node, Lambda 437 74 6.55 Iso group, Node, Lambda 428 84 6.55 Iso group, Node, Lambda 429 94 6.55 Iso group, Node, Lambda 430 10 4 6.55 Iso group, Node, Lambda 431 11 4 6.55 Iso group, Node, Lambda 433 12 4 6.55 Iso group, Node, Lambda 433 -1,0,0,0 Iso group, Node, Lambda 434 0 7.0E-5 End lambda input 435 2.00000 2.00833 1 0 0 1 LCHG, control room X/Q 436 000 From time, To time, IPRTAC, IAACT, ITACT, IPRINT 437 -1,0,0,0 LACTIN, LPTIN, LVOL 438 -1,0,0,0 End flow input 439 0 7.0E-5 End lambda input 440 2.00833 2.03694 1 0 0 1 LCHG, Control room X/Q 441 010 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 443 00000000 LACTIN, LPTIN, LVOL 443 00000000 Initial I-131 elem act frac in nodes 2-9 444 00000000 Initial I-131 orgn act frac in nodes 2-9 445 00000000 Initial I-131 part act frac in nodes 2-9 446 00000000 Initial I-132 elem act frac in nodes 2-9 447 00000000 Initial I-132 orgn act frac in nodes 2-9 448 00000000 Initial I-132 part act frac in nodes 2-9 449 00000000 Initial I-133 elem act frac in nodes 2-9 450 00000000 Initial I-133 orgn act frac in nodes 2-9 451 00000000 Initial I-133 part act frac in nodes 2-9 433 00000000 Initial I-134 elem act frac in nodes 2-9 453 00000000 Initial I-134 orgn act frac in nodes 2-9 454 00000000 Initial I-134 part act frac in nodes 2-9 455 00000000 Initial I-135 elem act frac in nodes 2-9 456 00000000 Initial I-135 orgn act frac in nodes 2-9 457 00000000 Initial I-135 part act frac in nodes 2-9 450 00000000 Initial Kr-83m act frac in nodes 2-9 459 00000000 Initial Kr-85 act Irac in nodes 2-9 460 00000000 Initial Kr-85m act frac in nodes 2-9 461 00000000 Initial Kr-87 act frac in nodes 2-9 463 00000000 Initial Kr-88 act frac in nodes 2-9 463 00000000 Initial Kr-89 act frac in nodes 2-9 464 00000000 Initial Xe-131m act frac in nodes 2-9 465 00000000 Initial Xe-133m act frac in noder 2-9 466 00000000 Initial Xe-133 act frac in nodes 2-9 467 00000000 Initial Xe-135m act frac in nodes 2-9 468 00000000 Initial Xe-135 act frac in nodes 2-9 469 00000000 Initial Xe-137 act frac in nodes 2-9 Initial Xe-138 act frac in nodes 2-9

m .m..w.u PY-CEl/NRR-2076L Page 197 of 217 PSAT 04202H.13 Page B8 of B26 470 Rev. 0@2 3 4 00000000 471 00000000 Initial CS-134 act frac in nodes 2-9 472 00000000 Initial CS-137 act frac in nodes 2-9 473 00000000 Initial TE-132 act frac in nodes 2-9 474 2300 Initial BA137M act frac in nodes 2-9 475 000000000000 From node, To node, Filt flow, Unfilt flow 476 -1,0,0,0 Filt eff for iso groups 1-12 477 -1,0,0,0 End flow input 478 0 7.0E-5 End lambda input 479 2.03694 2.04000 1 0 0 1 LCHG, Control roam X/Q 480 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 481 2 3 0 5.4E+4 LACTIN, LPTIN, LVOL 482 000000000000 From node, To node, Filt flow, Unfilt flow 483 -1,0,0,0 Filt eff for iso groups 1-12 484 12 0.58 End flow input 485 32 0.58 Iso group, Node, Lambda 486 52 0.58 Iso group, Node, Lambda 487 62 0.58 Iso group, Node, Lambda 488 72 0.58 Iso group, Node, Lambda 489 82 0.58 Iso group, Node, Lambda 490 92 0.58 Iso group, Node, Lambda 491 10 2 0.58 Iso group, Node, Lambda 492 11 2 0.58 Iso group, Node, Lambda 493 12 2 0.59 Iso group, Node, Lambda 494 -1,0,0,0 Iso group, Node, Lambda 495 0 7.0E-5 End lambda input 496 LCHG, Control room X/O 497 2.04000 2.04333 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 000 498 2 3 0 1.3E+5 LACTIN, LPTIN, LVOL 499 000000000000 From node, To nede, Filt flow, Unfilt flow 500 -1,0,0,0 Filt eff for iso groups 1-12 501 -1,0,0,0 End flow input 502 0 7.0E-5 End lambda input 503 LCHG, Control room X/O 504 2.04333 2.04694 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 000 505 2 3 0 1.8E+5 LACT 1H, LPTIN, LVOL 506 000000000000 From node, To node, Filt flow, Unfilt flow 507 -1,0,0,0 Filt eff for iso grcups 1-12 508 -1,0,0,0 End flow input 509 0 7.0E-5 End lan"da input , 510 2.04694 2.04917 1 0 0 1 LCHG, Control raom X/Q 518 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 512 2 3 0 2.1E+5 LACTIN, LPTIN, LVOL 513 000000000000 From node, To node, Filt flow, Unfilt flow 314 -1,0,0,0 Filt eff for iso groups 1-12 515 -1,0,0,0 End flow input 516 0 7.0E-5 End lambda input 517 2.04917 2.05083 1 0 0 1 LCHG, Control room X/Q 518 000 From time, To time, IFRTAC, IAACT, IPACT, IPRINT 519 -1,0,0,0 LACTIN, LPTIN, LVOL 520 14 3.30 End flow input 531 34 3.30 Iso group, Node, Lambda Saa 54 3.30 Iso group, Node, Lambda 533 6 4. 3.30 Iso group, Node, Lambda 524 74 3.30 Iso group, Node, Lambda 535 84 3.30 Iso group, Node, Lambda 536 94 3.30 Iso group, Node, Lambda 537 10 4 3.30 Iso group, Node, Lambda 538 11 4 3.30 Iso group, Node, Lambda 539 12 4 3.30 Iso group, Node, Lambda

 $3G     -1,0,0,0                                               Iso group, Node, Lambda 531     0 7.0E-5                                                        End lambda input 532     2.05083 2.05472 1 0 0 1                                 LCHG, Control room X/O 533     000                       From time, To time, IPRTAC, IAACT, IPACT, IPRINT 534     2 3 0 2.3E+5                                                LACTIN, LPTIN, LVOL 535     000000000000                    From node, To node, Filt flow, Unfilt flow 536     -1,0,0,0                                        Filt eff for iso groups 1-12 537     -1,0,0,0                                                          End flow input End lambda input

                                                                                                            ^

! AnEnment b PY-CELHRR-2076L l Page 198 of 217 PSAT 04202H.13 Page B9 of B26 Rev. 0@2 3 4 538 0 7.0E-5 539 LCHG, Control room X/O 2.05472 2.05061 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 540 000 LACTIN, LPTIN, LVOL 541 2 3 0 2.5E+5 From node, To node, Filt flow, Unfilt flow 543 000000000000 543 -1,0,0,0 Filt eff for iso groups 1-12 544 -1,0,0,0 End flow input 1 545 0 7.0E-5 End lambda input 546 LCHG, Control room X/O 2.05861 2.06250 1 0 0 1 From time, To time, IFRTAC, IAACT, IPACT, IFRINT 547 000

  $48    2 3 0 2.6E+5                                              LACTIN, LPTIN, LVOL 549                                  From node, To node, Filt flow, Unfilt flow 550 000000000000                                   Filt eff for iso groups 1-12
         -1,0,0,0 551   -1,0,0,0                                                          End flow input 552   0 7.0E-5                                                      End lambda input 553   2.06250 2.06639 1 0 0 1                                 LCHG, Control room X/O 554   000                      From time, To time, IFRTAC, IAACT, IFACT, IPRINT                            l 553   2 3 0 2.1E+5                                               LACTIN, LPTIN, LVOL 556   000000000000                    From node, To node, Filt flow, Unfilt flow 557   - 1, 0, 0, 0                                   Filt eff for iso groups 1-12                          ;

558 -1, 0, 0, 0 End flow input 559 0 7.0E-5 End lambda input 560 2.06639 2.06972 1 0 0 1 LCHG, Control room X/O 561 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 562 2 3 0 1.6E+5 LACTIN, LPTIN, LVOL 563 000000000000 From node, To node, Filt flow, Unfilt flow l { 564 -1,0,0,0 Filt eff for iso groups 1-12 1 565 -1, 0, 0, 0 End flow input 566 0 7.0E-5 End lambda input 567 2.C6972 2.07306 1 0 0 1 LCHG, Control room X/O 568 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 569 2 3 0 1.0E+5 LACTIN, LPTIN, LVOL l 370 000000000000 From node, To node, Filt flow, Unfilt flow l 571 -1,0,0,0 Filt eff for iso groups 1-12 572 -1,0,0,0 ,End flow input 573 0 7.0E-5 End lambda input 574 2.07306 2.07611 1 0 0 1 LCHG, Control room X/O 575 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 576 2 3 0 55000. LACTIN, LPTIN, LVOL 977 000000000000 From node, To node, Filt flow, Unfilt flow 378 -1,0,0,0 Filt eff for iso groups 1-12 579 -1,0,0,0 End flow input 580 0 7.0E-5 End lambda input 581 2.07611 2.07890 1 0 0 1 LCHG, Control room X/O 582 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 583 2 3 0 12000. LACTIN, LPTIN, LVOL 584 000000000000 From node, To node, Filt flow, Unfilt flow 585 -1,0,0,0 Filt eff for iso groups 1-12 586 -1,0,0,0 End flow input 587 0 7.0E-5 End lambda input SBB 2.07890 2.15556 1 0 0 1 LCHG, Control room X/Q 589 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT l 590 2 7 0 1.65 LACTIN, LPTIN, LVOL 591 000000000000 From node, To node, Filt flow, Unfilt flow 592 2 8 0 2.47 Filt eff for iso groups 1-12 l 593 000000000000 From node, To node, Filt flow, Unfilt flow 594 2 3 0 500. Filt eff for iso groups 1-12 595 000000000000 From node, To node, Filt flow, Unfilt flow 596 3 2 0 500. Filt eff for iso groups 1-12 597 000000000000 From node, To node, Filt flow, Unfilt flow 598 -1,0,0,0 Filt eff for iso groups 1-12 599 12 0.54 End flow input 600 32 0.54 Iso group, Node, Lambda 601 52 0.54 Iso group, Node, Lambda , 602 62 0.54 Iso group, Node, Lambda 603 72 0.54 Iso group, Node, Lambda , 604 82 0.54 Iso group, Node, Lambda l 605 92 0.54 Iso group, Node, Lambda Iso group, Node, Lambda

Att3hment 6 PY-CEIHRR-2076L Page 199 of 217 PSAT 04202H.13 Page B10 of B26 Rev. 0@ 2 3 4 606 10 2 0.54  ! Iso group, Node, Lambda ' 607 11 2 0.54 Iso group, Node, Lambda 608 12 2 0.54 Iso group, Node, Lambda 609 -1,0,0,0 End lambda input 610 0 7.0E-5 LCHG, Control room X/O 611 2.15556 2.57056 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 612 000 LACTIN, LPTIN, LVOL l 613 -1,0,0,0 614 End flow input 14 1.19 Iso group, Node, Lambda 615 34 1.19 i 616 Iso group, Node, Lambda i 54 1.19 Iso group, Node, Lambda l 617 64 1.19 618 Iso group, Node, Lambda 74 1.19 Iso group, Node, Lambda 619 B4 1.19 Iso group, Node, Lambda 620 94 1.19 Iso group, Node, Lambda 621 10 4 1.19 Iso group, Node, Lambda 622 11 4 1.19 Iso group, Node, Lambda 623 12 4 1.19 Iso group, Node, Lambda 624 -1,0,0,0  ; 625 0 7.0E-5 End lambda input 636 LCHG, Control room X/Q 2.57056 3.00000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 637 000 LACTIN, LPTIN, LVOL 628 -1,0,0,0 629 12 0.45 End flow input 630 32 0.45 Iso group, Node, Lambda i i 631 52 0.45 Iso group, Node, Lambda 632 62 0.45 Iso group, Node, Lambda 633 72 0.45 Iso group, Node, Lambda 634 82 0.45 Iso group, Noue, Lambda 635 92 0.45 Iso group, Node, Lambda l 636 10 2 0.45 Iso group, Node, Lambda 637 11 2 0.45 Iso group, Noo?, Lambda l 638 12 2 0.45 Iso group, Node, Lambda l 639 -1,0,0,0 Iso group, Node, Lambda 640 0 7.0E-5 End lambda input 641 LCHG, Control room X/Q j 3.00000 3.25667 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 642 000 i 643 7 1 3.183 0 LACTIN, LPTIN, LVOL 644 From node, To node, Filt flow, Unfilt flow 50 0 97.2 0 97.2 97.2 97.2 97.2 97.2 97.2 97.2 97.2 Filt eff 4 iso grps 1-12 l 645 9 1 4.775 0 From node, To node, Filt flow, Unfilt flow 646 647 50 0 94.1 0 94.1 94.1 94.1 94.1 94.1 94.1 94.1 94.1 Filt eff 4 iso grps 1-12

      -1,0,0,0 l 640  -1,0,0,0                                                           End flow input                     ,

l 649 0 7.0E-5 End lambda input I 650 LCHG, Control room X/Q 3.25667 4.41139 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 651 000 652 -1,0,0,0 LACT:.'N, LPTIN, LVOL 653 14 0.50 End flow input 654 34 0.50 Ise group, Node, Lambda 655 54 0.50 Iso group, Node, Lambda 656 64 0.50 Iso group, Node, Lambda 657 74 0.50 Iso group, Node, Lambda 658 84 0.50 Iso group, Node, Lambda 659 94 0.50 Iso group, Node, Lambda 660 10 4 0.50 Iso group, Node, Lambda 661 11 4 0.50 Iso group, Node, Lambda 662 12 4 0.50 Iso group, Node, Lambda l 663 -1,0,0,0 Iso group, Node, Lambda l End lambda input i 664 0 7.0E-5 LCHG, Control room X/Q 665 4.41139 4.85250 1 0 0 1 666 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 667 -1,0,0,0 LACTIN, LPTIN, LVOL 660 End flow input 12 0.35 Iso group, Node, Lambda 669 32 0.35 670 Iso group, Node, Lambda 52 0.35 Iso group, Node, Lambda 671 62 0.35 672 72 Iso group, Node, Lambda 0.35 Iso group, Node, Lambda 673 82 0.35 Iso group, Node, Lambda

_ _ _ . . ._ __ . . - - - _ _ _ - -.____m._m_. _._ _ . . .

                                                                                                                     .._....v PY CEINRR-2076L   !

Page 200 0f 217  ! PSAT 04202H.13 Page B11 of B26  ! Rev. 0@2 3 4 , 674 92 0.35 Iso group, Node, Lambda 675 10 2 0.35 Iso group, Node, Lambda 676 11 2 0.35 ' Iso group, Node, Lambda 677 12 2 0.35 Iso group, Node, Lambda 678 -1, 0, 0, O 679 0 7.0E-5 End lambda input 680 LCHG, Control room X/Q 4.85250 5.00000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 681 000 662 -1,0,0,0 LACTIN, LPTIN, LVOL 683 14 0.27 End flow input 684 34 0.27 Iso group, Node, Lambda 685 54 0.27 Iso group, Node, Lambda 3 666 64 0.27 Iso group, Node, Lambda 687 74 0.27 Iso group, Node, Lambda 6E8- 84 0.27 Iso group, Node, Lambda 689 94 0.27 Iso group, Node, Lambda ' 690 10 4 0.27 Iso group, Node, Lambda 693 11 4 0.27 Iso group, Node, Lambda 692 12 4 0.27 Iso group, Node, Lambda 693 -1,0,0,O Iso group, Node, Lambda , 694 0 7.0E-5 End lambda input I 695 LCHG, Control room X/O 5.00000 6.00000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT  ; 696 000 697 7 1 3.183 0 LACTIN, LPTIN, LVOL 698 From node, To node, Filt flow, Unfilt flow 699 50 9 104.775 97.4 00 97.4 97.4 97.4 97.4 97.4 97.4 97.4 97.4 Filt eff 4 iso grps 1-12 700 From node, To node, Filt flow, Unfilt flow ~ 701 50 0 94.1 0 94.1 94.1 94.1 94.1 94.1 94.1 94.1 94.1 Filt off 4 iso grps 1-12

              -1,0,0,O 703     -1,0,0,O                                                                            End flow input 703     0 7.0E-5                                                                        End lambda input 704     6.00000 7.00000 1 0 0 1                                                   LCHG, Control room X/O 705     000                                   From time, To time, IPRTAC, IAACT, IPACT, IPRINT                                   ,

1 706 -1,0,0,0 LACTIN, LPTIN, LVOL 707 -1,0,0,O End flow input 708 0 7.0E-5 End lambda input 709 7.00000 B.00000 1 0 0 1 LCHG, Control room X/Q llo 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 711 7 1 3.183 0 LACTIN, LPTIN, LVOL 713 From node, To node, Filt flow, Unfilt flow 713 50 0 9 1 4.775 097.1 0 97.1 97.1 97.1 97.1 97.1 97.1 97.1 97.1 Filt off 4 iso grps 1-12 714 From node, To node, Filt flow, Unfilt flow 715 50 0 92.9 0 92.9 92.9 92.9 92.9 92.9 92.9 92.9 92.9 Filt off 4 iso grps 1-12

              -1,0,0,0 716     -1, 0, 0, O                                                                        End flow input 717     0 7.0E-5                                                                        End lambda input 718     B.00000 B.51917 1 0 0 1                                                   LCHG, Control room X/Q 719     000                                   From time, To time, IPRTAC, IAACT, IPACT, IPRINT 720     -1,0,0,0                                                                     IACTIN, LPTIN, LVOL 721     -1,0,0,O                                                                           End flow input 723     0 5.6E-5                                                                        End lambda input 733     B.51917 8.56194 1 0 0 1                                                   LCHG, Control room X/Q 734     000                                   From time, To time, IPRTAC, IAACT, IPACT, IPRINT i

735 -1,0,0,0 LACTIN, LPTIN, LVOL 726 12 0.25 End flow input 737 3 2- 0.25 Iso group, Node, Lambda 738 52 0.25 Iso group, Node, Lambda 739 62 0.25 Iso group, Node, Lambda 730 72 0.25 Iso group, Node, Lambda 731 B2 0.25 Iso group, Node, Lambda , 733 92 0.25 Iso group, Node, Lambda 733 10 2 0.25 Iso group, Node, Lambda 734 11 2 0.25 Iso group, Node, Lambda i 735 12 2 0.25 Iso group, Node, Lambda 736 -1,0,0,O Iso group, Node, Lambda 737 0 5.6E-5 End lambda input 738 8.56194 9.00000 1 0 0 1 LCHG, Control room X/Q 739 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 2 740 -1,0,0,0 IACTIN, LPTIN, LVOL 3 741 14 0.23 End flow input a Iso group, Node, Lambda

Ph2ELNRR-2076L

- Pyc 20l of 217 PSAT 04202H.13 Page B12 of B26 Rev. 0@2 3 4 742 34 0.23 Iso group, Node, Lambda 743 54 0.23 Iso group, Node, Lambda 744 64 0.23 Iso group, Node, Lambda ,

745- 74 0.23 Iso group, Node, Lambda l 746 84 0.23 Iso group, Node, Lambda 747 94 0.23 Iso group, Node, Lambda 748 10 4 0.23 Iso group, Node, Lambda 749 11 4 0.23 Iso group, Node, Lambda 750 10 4 0.23 Iso group, Node, Lambda 751 -1,0,0, O End lambda input

   -752  0 5.6E-5                                              LCHG, Control room X/Q 753  9.00000 11.0000 1 0 0 1    From time, To time, IFRTAC, IAACT, IPACT, IPRINT 754  000                                                      LACTIN, LPTIN, LVOL 755  7 1 3.183 0                      From node, To node, Filt flow, Unfilt flow 756  50 0 96.6 0 96.6 96.6 96.6 96.6 96.6 96.6 96.6 96.6 Filt eff 4 iso grps 1-12 757  9 1 4.775 0                      From node, To node, Filt flow, Unfilt flow 758  50 0 91.1 0 91.1 91.1 91.1 91.1 91.1 91.1 91.1 91.1 Filt eff 4 iso grps 1-12 759  -1,0,0,0                                                      End flow input 760  -1,0,0,0                                                    End lambda input 761  0 5.6E-5                                              LCHG, Control roam X/O 762  11.0000 11.1219 1 0 0 1    From time, To time, IPRTAC, IAACT, IPACT, IPRINT 763  000                                                      LACTIN, LPTIN, LVOL 764  7 1 3.183 0                      From node, To node, Filt flow, Unfilt flow 765  50 0 95.1 0 95.1 95.1 95.1 95.1 95.1 95.1 95.1 95.1 Filt eff 4 iso grps 1-12 766  9 1 4.775 0                      From node, To node, Filt flow, Unfilt flow 767  50 0 78.3 0 78.3 78.3 78.3 78.3 78.3 78.3 78.3 78.3 Filt eff 4 iso grps 1-12 768  -1,0,0,0                                                      End flow input 769  -1,0,0,O                                                    End lambda input 770  0 5.6E-5                                              LCHG, Control room X/O 771  11.1219 14.3442 1 0 0 1    From time, To time, IFRTAC, IAACT, IPACT, IPRINT 772  000                                                      LACTIN, LPTIN, LVOL l

173 -1,0,0,0 End flow input  ! 774 14 0.2 Iso group, Node, Lambda ' 775 34 0.2 Iso group, Node, Lambda 776 54 0.2 Iso grdup, Node, Lambda 777 64 0.2 Iso group, Node, Lambda 178 74 0.2 Iso group, Node, Lambda 779 84 0.2 Iso group, Node, Lambda 780 94 0.2 Iso group, Node, Lambda 181 10 4 0.2 Iso group, Node, Lambda 782 11 4 0.2 Iso group, Node, Lambda 783 12 4 0.2 Iso group, Node, Lambda 784 -1,0,0,O End lambda input 785 0 5.6E-5 LCHG, Control room X/O 786 14.3442 19.3092 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 787 000 LACTIN, LPTIN, LVOL 788 -1,0,0,0 End flow input 189 12 0.16 Iso group, Node, Lambda 790 32 0.16 Iso group, Node, Lambda 791 52 0.16 Iso group, Node, Lambda 792 62 0.16 Iso group, Node, Lambda 793 72 0.16 Iso group, Node, Lambda 794 82 0.16 Iso group, Node, Lambda 795 92 0.16 Iso group, Node, Lambda 796 10 2 0.16 Iso group, Node, Lambda 797 11 2 0.16 Iso group, Node, Lambda 798 12 2 0.16 Iso group, Node, Lambda 799 -1,0,0,O End lambda input 800 0 5.6E-5 LCHG, Control room X/Q 801 19.3092 21.0000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 802 000 LACTIN, LPTIN, LVOL 803 -1,0,0,0 End flow input 804 14 0.19 Iso group, Node, Lambda 805 34 0.19 Iso group, Hode, Lambda 806 54 0.19 Iso group, Node, Lambda ! 807 64 0.19 Iso group, Node, Lambda 808 74 0.19 Iso group, Node, Lambda 809 84 0.19 Iso group, Node, Lambda

i PLCEl/NRR-2076L i Page 202 of 217 PS/Cf 04202FI.13 Page B13 of B26 Rev. 0@2 3 4 810 94 0.19 Iso group, Node, Lambda i ' 811 10 4 0.19 Isc group, Node, Lambda 812 11 4 0.19 Iso group, Node, Lambda 813 12 4 0.19 Iso group, Node, Lambda 814 -1,0,0,0 End lambda input 815 0 5.6E-5 LCHG, Control room X/Q i 816 21.0000 24.0000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT l 817 000 LACTIN, LPTIN, LVOL 818 7 1 3.183 0 From node, To node, Filt flow, Unfilt flow 819 50 0 89.1 0 89.1 89.1 89.1 89.1 89.1 69.1 89.1 89.1 Filt eff 4 iso grps 1-12 820 -1,0,0,0 End flow input 821 -1,0,0,0 End lambda input 3 i 823 0 5.6E-5 LCHG, Control room X/O 833 24.0000 24.5000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 824 000 LACTIN, LPTIN, LVOL l 825 6 1 6.684 0 From node, To node, Filt flow, Unfilt flow 826 90 90 90 90 90 90 90 90 90 90 90 90 Filt eff for iso groups 1-12 837 -1,0,0,0 End flow input 838 14 0.0 Iso group, Node, Lambda 829 34 0.0 Iso group, Node, Lambda 830 54 0.0 Iso group, Node, Lambda 831 64 0.0 Iso group, Node, Lambda 833 74 0.0 Iso group, Node, Lambda 833 84 0.0 Iso group, Node, Lambda 834 94 0.0 Iso group, Node, Lambda 835 10 4 0.0 Iso group, Node, Lambda 836 11 4 0.0 Iso group, Node, Lambda 837 12 4 0.0 Iso group, Node, Lambda 838 -1,0,0,O End lambda input 839 0 4.3E-5 LCHG, Control room X/Q 840 24.5000 27.7778 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 841 000 842 LACTIN, LPTIN, LVOL 6 1 0.03342 0 From node, To node, Filt flow, Unfilt flow 843 90 90 90 90 90 90 90 90 90 90 90 90 844 -1,0,0,0 Filt eff for, iso groups 1-12 845 -1,0,0,0 End flow input End lambda input 846 0 4.3E-5 LCHG, Control room X/Q 847 27.7778 96.0000 1 0 0 1 848 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 000 LACTIN, LPTIN, LVOL 849 -1,0,0,0 850 12 0.0 End flow input Iso group, Node, Lambda 851 32 0.0 Iso group, Node, Lambda 853 52 0.0 853 Iso group, Node, Lambda 62 0.0 Iso group, Node, Lambda 854 72 0.0 855 Iso group, Node, Lambda 82 0.0 Iso group, Node, Lambda 856 92 0.0 Iso group, Hode, Lambda 857 10 2 0.0 Iso group, Node, Lambda 858 11 2 0.0 Iso group, Node, Lambda 859 12 2 0.0 Iso group, Node, Lambda 860 -1,0,0,0 End lambda input 861 0 4.3E-5 LCHG, Control room X/Q 8 63 96.0000 720.000 1 0 0 1 From time, To time, IFRTAC, IAACT, IPACT, IPRINT 863 000 864 -1,0,0,0 LACTIN, LPTIN, LVOL 865 -1,0,0,0 End flow input 866 0 1.5E-5 End lambda input LCHG, Control room X/Q i

rwamwa u PY-CElWRR 2073L Page 203 of 217 PSAT 04202H.13 Page B14 of B26 Rev. 0@ 2 3 4 For conficuration 2 1 PERRY DOSE CALC. W/ REVISED SOURCE TERN, CTG 2, 24 HR SPRAY Problem title 2 JUN LI Originator 3 PERRY DOSE CALC. Project name 4 PSAT 04202H Project i 5 04202H.13 0 Calc f, Rev 6 1 7 8 12 32 1 0 0 First page # of output

                                       # Nodes, f Time steps, # Iso, ICR, CALCDA, LSPRAY 8  1 0 3758 0 2 0 0     ITID, IPURGE, Power, SD time, NPF, # Spr nodes, 6 Delay cales 9  CFM CUFT CURIES 10  111111111111                                    Flow unit, Volume unit, Activity unit 11   0.0485 0.0015 0.95                                     Release frac for iso group 1-12 12                                                            Elem, org, part iodine frac DRYWELL UNSPRAYED SPRAYED 13   8.333E-3 0.011111 1001        ANNULUS SUP POOL STL_CV_1 STL_CV_2 STL_CV_3 Node name 14   011                                From time, To time, IPRTAC, IAACT, IPACT, IPRINT 85                                                                      LACTIN, LPTIN, LVOL 0.100000 0 0 0 0.6 0 0 0                   Initial I-131  elem  act  frac in nodes 2-9 16  0.100000 0 0 0 0.6 0 0 0

• 17 0.100000 0 0 0 0.6 0 0 0 Initial I-131 orgn act frac in nodes 2-9 18 0.100000 0 0 0 0.6 0 0 0 Initial I-131 part act frac in nodes 2-9 19 0.100000 0 0 0 0.6 0 0 0 Initial I-132 elem act frac in nodes 2-9 20 Initial I-132 orgn act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-132 part act frac in nodes 2-9 21 0.100000 0 0 0 0.6 0 0 0 82 0.100000 0 0 0 0.6 0 0 0 Initial I-133 elem act frac in nodes 2-9 23 0.100000 0 0 0 0.6 0 0 0 Initial I-133 orgn act frac in nodes 2-9 24 0.100000 0 0 0 0.6 0 0 0 Initial I-133 part act frac in nodes 2-9 25 0.100000 0 0 0 0.6 0 0 0 Initial I-134 elem act frac in nodes 2-9 36 0.100000 0 0 0 0.6 0 0 0 Initial I-134 orgn act frac in nodes 2-9 37 Initial I-134 part act frac in nodes 2-9 0.100000 0 0 0 0.6 0 0 0 Initial I-135 elem act frac in nodes 2-9 28 0.100000 0 0 0 0.6 0 0 0 29 Initial I-135 orgn act frac in nodes 2-9 30 0.100000 0 0 0 0.6 0 0 0 Initial I-135 part act frac in nodes 2-9 0.100000 0 0 0 0 000 31 0.100000 0 0 0 0 000 Initial Kr-83m act frac in nodes 2-9 32 0.100000 0 0 0 0 000 Initial Kr-85 act frac in nodes 2-9 33 0.100000 0 0 0 0 000 Initial Kr-85m act frac in nodes 2-9 34 0.100000 0 0 0 0 000 Initial Kr-87 act frac in nodes 2-9 35 0.100000 0 0 0 0 000 Initial Kr-88 act frac in nodes 2-9 36 0.100000 0 0 0 0 000 Initial Kr-89 act frac in nodes 2-9 37 0.100000 0 0 0 0 000 Initial Xe-130m act frac in nodes 2-9 38 0.100000 0 0 0 0 000 Initial Xe-133m act frac in nodes 2-9 39 0.100000 0 0 0 0 000 Initial Xe-133 act frac in nodes 2-9 40 0.100000 0 0 0 0 000 Initial Xe-135m act frac in nodes 2-9 41 0.100000 0 0 0 0 000 Initial Xe-135 act frac in nodes 2-9 42 0.100000 0 0 0 0 000 Initial Xe-137 act frac in nodes 2-9 43 0.100000 0 0 0 0 000 Initial Xe-138 act frac in nodes 2-9 44 0.100000 0 0 0 0 000 Initial CS-134 act frac in nodes 2-9 45 00000 000 Initial CS-137 act frac in nodes 2-9 i 46 00000 000 Initial TE-132 act frac in nodes 2-9 1 47 Initial BA137M act frac in nodes 2-9 48 276500. 684226. 481174. 1.96E+5 146952, 146. 440. 292. Volumes for nodes 2-9 2 7 0 1.987 j

49 From node, To node, Filt flow, Unfilt flow  ; 50 000000000000 Filt eff for iso groups 1-12 2 8 0 2.98 51 000000000000 From node, To node, Filt flow, Unfilt flow 52 8 9 4.775 0 Filt eff for iso groups 1-12 53 From node, To node, Filt flow, Unfilt flow 1 54 50074.6074.674.674.674.674.674.674.674.6 7 1 3.183 0 Filt eff 4 iso grps 1-12 55 From node, To node, Filt flow, Unfilt flow 56 50 0 71.0 9 1 4.775 0 0 71.0 71.0 71.0 71.0 71.0 71.0 71.0 71.0 Filt eff 4 iso grps 1-12 57 From node, To node, Filt flow, Unfilt flow 58 501 00 74.0 3 2.01 0 74.0 74.0 74.0 74.0 74.0 74.0 74.0 74.0 Filt eff 4 iso grps 1-12 59 From node, To node, Filt flow, Unfilt flow 60 000000000000 Filt eff for iso groups 1-12 3 4 0 71400. From node, To node, Filt flow, Unfilt flow 61 000000000000 Filt eff for iso groups 1-12 i 62 3 5 0 1.0E-5 From node, To node, Filt flow, Unfilt flow 63 000000000000 Filt eff for iso groups 1-12

Anachment b PY-CEl/NRR-2076L Page 204 of 217 PSAT 04202H.13 Page B15 of B26 Itev. 0@)2 3 4 65 000000000000 Filt eff for iso groups 1-12 66 4 3 0 71400. From node, To node, Filt flow, Unfilt flow 67 000000000000 Filt eff for iso groups 1-12 68 4 5 0 1.0E-5 From node, To node, Filt flow, Unfilt flow 69 000000000000 Filt eff for iso groups 1-12 70 5 1 2000. O From node, To node, Filt flow, Unfilt flow 71 0 0 99 0 99 99 99 99 99 99 99 99 (Item 4.1) Filt eff for iso groups 1-12 73 6 1 1.0E-05 0 From node, To node, Filt flow, Unfilt flow 73 99 99 99 99 99 99 99 99 99 99 99 99 Filt eff for iso groups 1-12 74 -1,0,0,0 End flow input 75 1 2 0.084 Iso group, Node, Lambda 76 3 2 0.084 Iso group, Node, Lambda 77 5 2 0.084 Iso group, Node, Lambda 18 6 2 0.084 Iso group, Node, Lambda 79 7 2 0.004 Iso group, Node, Lambda SO 8 2 0.084 Iso group, Node, Lambda 81 9 2 0.084 Iso group, Node, Lambda B2 10 2 0.084 Iso group, Node, Lambda 83 11 2 0.004 Iso group, Node, Lambda 84 12 2 0.084 Iso group, Node, Lambda 85 -1,0,0,0 86 1 7.0E-5 End lambda input B7 LCHG, Control room X/O 3.44E5 0 1375 2.7E4 1375 CR vol,Filt intake,Unfilt intake,Recire,Outleak BB 000000000000 Intake filt eff for iso groups 1-12 89 000000000000 90 (Item 4.2) Recire filt eff for iso groups 1-12 0.011111 0.018333 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 91 000 93 3 1 0 0.135 LACTIN, LPTIN, LVOL 93 From node, To node, Filt flow, Unfilt flow 000000000000 Filt eff for iso groups 1-12 94 3 5 0 1.205 From node, To node, Filt flow, Unfilt flow 95 000000000000 Filt eff for iso groups 1-12 96 4 1 0 0.0675 From node, To node, Filt flow, Unfilt flow 97 000000000000 Filt eff for iso groups 1-12 98 4 5 0 0.603 From node, To node, Filt flow, Unfilt flow 99 000000000000 100 -1,0,0,0 Filt eff for ' iso groups 1-12 .01 -1,0,0,O End flow input 103 0 7.0E-5 End lambda input 103 0.018333 0.175 1 0 0 1 LCHG, Control room X/O 104 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 105 -1,0,0,0 LACTIN, LPTIN, LVOL 106 12 0.184 End flow input 107 32 0.184 Iso group, Node, Lambda 100 Iso group, Node, Lambda 52 0.184 Iso group, Node, Lambda 109 62 0.184 120 72 0.184 Iso group, Node, Lambda 111 82 0.184 Iso group, Node, Lambda 183 Iso group, Node, Lambda 92 0.184 Iso group, Node, Lambda 113 10 2 0.184 Iso group, Node, Lambda 184 11 2 0.184 Iso group, Node, Lambda 115 12 2 0.184 Iso group, Node, Lambda 116 -1,0,0,0 l 117 0 7.0E-5 End lambda input 110 0.175 0.19167 1 0 0 1 LCHG, Control room X/Q i 119 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT I 130 6 1 0.03342 0 LACTIN, LPTIN, LVOL Sal From node, To node, Filt flow, Unfilt flow 90 90 90 90 90 90 90 90 90 90 90 90 Filt eff for iso groups 1-12 133 -1,0,0,0 133 -1,0,0,0 End flow input 134 0 7.0E-5 End lambda input 135 LCHG, Control room X/O 0.19167 0.20222 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 126 000 137 - 1, 0, 0, 0 LACTIN, LPTIN, LVOL 138 14 B.13 End flow input 129 Iso group, Node, Lambda 34 0.13 Iso group, Node, Lambda 130 54 B.13 Iso group, Node, Lambda 131 64 B.13

                                                          , Iso   group, Node, Lambda

                                                                                           /unnmem o P%CEL%RR 2076L Pagc 205 0f 217 PSAT 04202H.13                                                     Page B16 of B26                !

Rev. 0(D2 3 4 131 64 8.13 i 132 Iso group, Node, Lambda 74 8.13 Iso group, Node, Lambda i 133 84 8.13 j 134 Iso group, Node, Lambda l 94 8.13 Iso group, Node, Lambda j 135 10 4 8.13 Iso group, Node, Lambda j 136 11 4 8.13 i Iso group, Node, Lambda 137 12 4 8.13 Iso group, Node, Lambda 138 -1,0,0,0 139 0 7.0E-5 End lambda input 140 0.20222 0.25667 1 0 0 1 LCHG, Control room X/O 141 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 142 -1,0,0,0 LACTIN, LPTIN, LVOL 143 14 4.32 End flow input 144 34 4.32 Iso group, Node, Lambda 1 145 54 4.32 Iso group, Node, Lambda 146 64 4.32 Iso group, Node, Lambda 147 74 4.32 Iso group, Node, Lambda , 148 84 4.32 Iso group, Node, Lambda l 149 94 4.32 Iso group, Node, Lambda 150 10 4 4.32 Iso group, Node, Lambda j 151 11 4 4.32 Iso group, Node, Lambda  ; j 152 12 4 4.32 Iso group, Node, Lambda Iso group, Node, Lambda j 133 -1,0,0,0 j 154 0 7.0E-5 End lambda input { 155 0.25667 0.36583 1 0 0 1 LCHG, Control room X/Q 156 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT i 157 -1,0,0,0 LACTIN, LPTIN, LVOL l 158 14 3.02 End flow input { l 199 34 3.02 Iso group, Node, Lambda l 160 54 3.02 Iso group, Node, Lambda l 161 64 3.02 Iso group, Node, Lambda j 162 74 3.02 Iso group, Node, Lambda l 163 84 3.02 Iso group, Node, Lambda 164 94 3.02 Iso group, Node, Lambda 165 10 4 3.02 so group, Node, Lambda 166 11 4 3.02 Iso gro6p, Node, Lambda 167 12 4 3.02 Iso group, Node, Lambda 168 -1,0,0,O Iso group, Node, Lambda ) l 169 0 7.0E-5 End lambda input i ! 170 0.36583 0.475 1001 LCHG, Control room X/O I 171 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT l 172 -1,0,0,0 LACTIN, LPTIN, LVOL l 173 14 2.52 End flow input A74 34 2.52 Iso group, Node, Lambda i i 175 54 2.52 Iso group, Hode, Lambda ' l 176 64 2.52 Iso group, Node, Lambda 177 74 2.52 Iso group, Node, Lambda 178 84 2.52 Iso group, Node, Lambda , 879 94 2.52 Iso group, Node, Lambda l 100 10 4 2.52 Iso group, Node, Lambda 181 11 4 2.52 Iso group, Node, Lambda 182 12 4 2.52 Iso group, Node, Lambda

183 -1,0,0,0 Iso group, Node, Lambda

184 0 7.0E-5 End lambda input l 185 0.475 0.500000 1001 LCHG, Control room X/Q 4 l

' 186 000 from time, To time, IPRTAC, IAACT, IPACT, IPRINT 187 -1, 0, 0, 0 LACTIN, LPTIN, LVOL l 188 14 14.3 End flow input 189 34 14.3 Iso group, Node, Lambda A90 54 14.3 Iso group, Node, Lambda 191 64 14.3 Iso group, Node, Lambda 192 74 14.3 Iso group, Node, Lambda 193 84 14.3 Iso group, Node, Lambda 194 94 14.3 Iso group, Node, Lambda 195 10 4 14.3 Iso group, Node, Lambda 196 11 4 14.3 Iso group, Node, Lambda 197 12 4 14.3 Iso group, Node, Lambda Iso group, Node, Lambda l l

Antenmemb PY-CEI!NRR-2076L Page 206 of 217 PSAT 04202H.13 Page B17 of B26 Rev. 0@2 3 4 198 -1,0,0,0 End lambda input 199 0 7.0E-5 LCHG, Control room X/Q 200 0.500 0.508333 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 301 000 LACTIN, LPTIN, LVOL 203 7 1 3.183 0 From node, To node, Filt flow, Unfilt flow 203 50 0 85.0 0 85.0 85.0 85.0 85.0 85.0 85.0 85.0 85.0 Filt eff 4 iso grps 1-12 304 9 1 4.775 0 From node, To node, Filt flow, Unfilt flow 205 50 0 83.0 0 83.0 83.0 83.0 83.0 83.0 83.0 83.0 83.0 Filt eff 4 iso grps 1-12 206 -1,0,0,0 307 -1,0,0,0 End flow input 308 End lambda input 0 7.0E-5 LCHG, Control room X/Q 209 0.50833 0.51861 1 0 0 1 210 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 010 LACTIN, LPTIN, LVOL 211 0.1666667 0 0 0 0 0 0 0 283 0.1666667 0 0 0 0 0 0 0 Initial I-131 elem act frac in nodes 2-9 Initial I-131 orgn act frac in nodes 2-9 213 0.1666667 0 0 0 0 0 0 0 Initial I-131 part act frac in nodes 2-9 214 0.1666667 0 0 0 0 0 0 0 315 0.1666667 0 0 0 0 0 0 0 Initial I-132 elem act frac in nodes 2-9 216 Initial I-132 orgn act frac in nodes 2-9 0.1666667 0 0 0 0 0 0 0 Initial I-132 part act frac in nodes 2-9 387 0.1666667 0 0 0 0 0 0 0 318 0.1666667 0 0 0 0 0 0 0 Initial I-133 elam act frac in nodes 2-9 219 Initial I-133 orgn act frac in nodes 2-9 0.1666667 0 0 0 0 0 0 0 Initial I-133 part act frac in nodes 2-9 330 0.16666670000000 231 0.1666667 0 0 0 0 0 0 0 Initial I-134 elem act frac in nodes 2-9 223 Initial I-134 orgn act frac in nodes 2-9 0.1666667 0 0 0 0 0 0 0 Initial I-134 part act frac in nodes 2-9 233 0.1666667 0 0 0 0 0 0 0 234 0.1666667 0 0 0 0 0 0 0 Initial I-135 elam act frac in nodes 2-9 225 0.1666667 0 0 0 0 0 0 0 Initial I-135 orgn act frac in nodes 2-9 236 0.6333333 0 0 0 0 0 0 0 Initial I-135 part act frac in nodes 2-9 227 0.6333333 0 0 0 0 0 0 0 Initial Kr-83m act frac in nodes 2-9 238 0.6333333 0 0 0 0 0 0 0 Initial Kr-85 act frac in nodes 2-9 339 0.6333333 0 0 0 0 0 0 0 Initial Kr-85m act frac in nodes 2-9 330 0.6333333 0 0 0 0 0 0 0 Initial Kr-87 act frac in nodes 2-9 331 0.6333333 0 0 0 0 0 0 0 Initial Kr-88 act frac in nodes 2-9 333 0.6333333 0 0 0 0 0 0 0 Initial Kr-89 act frac in nodes 2-9 333 0.6333333 0 0 0 0 0 0 0 Initial Xe-131m act frac in nodes 2-9 234 0.6333333 0 0 0 0 0 0 0 Initial Xe-133m act frac in nodes 2-9 335 0.6333333 0 0 0 0 0 0 0 Initial Xe-133 act frac in nodes 2-9 336 0.6333333 0 0 0 0 0 0 0 Initial Xe-135m act frac in nodes 2-9 337 0.6333333 0 0 0 0 0 0 0 Initial Xe-135 act frac in nodes 2-9 338 0.6333333 0 0 0 0 0 0 0 Initial Xe-137 act frac in nodes 2-9 239 0.1333333 0 0 0 0 0 0 0 Initial Xe-138 act frac in nodes 2-9 340 0.1333333 0 0 0 0 0 0 0 Initial CS-134 act frac in nodes c.9 241 0.0333333 0 0 0 0 0 0 0 Initial CS-137 act frac in neo a 2-9 343 0.0133333 0 0 0 0 0 0 0 Initial TE-132 act frac in neues 2-9 , 243 2 3 0 6180.0 Initial BA137M act free in nodes 2-9 344 000000000000 From node, To node, Filt flow, Unfilt flow l I 245 -1,0,0,0 Filt eff for iso groups 1-12 346 -1,0,0,0 End flow input i 347 1 7. 0E-5 End lambda input 248 3.44E5 0 1375 2.7E4 1375 LCHG, Control room X/Q 249 000000000000 CR vol,Filt intake,Unfilt intake,Recire,Outleak l I 250 Intake filt eff for iso groups 1-12 251 50 50 95 0 95 95 95 95 0.51861 0.52694 1 0 0 1 95 95 95 95 (4.2) Recirc filt eff for iso groups 1-12 353 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT l 353 -1,0,0,0 LACTIN, LPTIN, LVOL 354 12 0.25 End flow input 255 32 0.25 Iso group, Node, Lambda 256 52 0.25 Iso group, Node, Lambda 257 62 0.25 Iso group, Node, Lambda 258 72 0.25 Iso group, Node, Lambda 359 82 0.25 Iso group, Node, Lambda 360 92 0.25 Iso group, Node, Lambda 361 10 2 0.25 Iso group, Node, Lambda 263 11 2 0.25 Iso group, Node, Lambda 363 12 2 0.25 Iso group, Node, Lambda 264 -1,0,0,0 Iso group, Node, Lambda End lambda input

                                                                                               ,u.....,

f PY-CEI/NRR-2076L Page 207 of 217  ! PSAT 04202H.13 Psg3 B18 of B26 l l Rev. 0$2 3 4 ) i 265 0 7.0E-5 LCHG, Control room X/Q  ! 266 0.52694 0.575 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 267 000 LACTIN, LPTIN, LVOL  ; 268 -1,0,0,O End flow input

• 269 14 8.76 Iso group, Hode,' Lambda 270 34 8.76 Iso group, Node, Lambda 271 54 8.76 Iso group, Node, Lambda I 272 64 8.76 Iso group, Node, Lambda 273 74 8.76 Iso group, Node, Lambda 274 84 8.76 Iso group, Node, Lambda 275 94 8.76 Iso group, Node, Lambda

! 276 10 4 8.76 Iso group, Node, Lambda 277 11 4 8.76 Iso group, Node, Lambda i 278 12 4 8.76 Iso group, Node, Lambda 1 279 -1, 0,0, O End lambda input l 280 0 1.0E-5 LCHG, Control room X/Q I 281 0.575 0.7025 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 282 000

                                                                                                                 )

LACTIN, LPTIN, LVOL 283 -1,0,0,0 End flow input 284 14 5.07 Iso group, Node, Lambda 285 34 5.07 Iso group, Node, Lambda 206 54 5.07 Iso group, Node, Lambda 287 64 5.07 Iso group, Node, Lambda l 288 74 5.07 Iso group, Node, Lambda

   -289  84   5.07                                           Iso group, Node, Lambda 290  94   5.07                                           Iso group, Node, Lambda 291  10 4 5.07                                           Iso group, Node, Lambda 292  11 4 5.01                                           Iso group, Node, Lambda l    293  12 4 5.07                                           Iso group, Node, Lambda 294  -1,0,0,O                                                      End lambda input 295  0 7.0E-5                                             LCHG, Control room X/Q 296  0.7025 0.8725 1001        From time, To time, IPRTAC, IAACT, IPACT, IPRINT 297  000                                                     LACTIN, LPTIN, LVOL 298  -1,0,0,0                                                        End flow input

• 299 14 3.84 Iso group, Node, Lambda 300 34 3.84 Iso group, Node, Lambda 301 54 3.84 Iso group, Node, Lembda 302 64 3.84 Iso group, Node, f==h'ia 303 74 3.84 Iso group, Node, Lambda 304 84 3.84 l Iso group, Node, Lambda 305 94 3.84 1so group, Node, Lambda 306 10 4 3.84 Iso group, Node, Lambda 307 11 4 3.84 Iso group, Node, Lambda 308 12 4 3.84 Iso group, Node, Lambda 309 -1,0,0,0 End lambda input j

310 0 7.0E-5 LCHG, Control room X/Q  ! 311 0.8725 0.88972 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 312 000 LACTIN, LPTIN, LVOL 313 -1,0,0,0 End flow input 314 14 3.25 Iso group, Node, Lambda i i 315 34 3.25 Iso group, Node, Lambda 316 54 3.25 Iso group, Node, Lambda 317 64 3.25 Iso group, Node, Lambda 318 74 3.25 Iso group, Node, Lambda 319 84 3.25 Iso group, Node, Lambda 320 94 3.25 Iso group, Node, Lambda 321 10 4 3.25 Iso group, Node, Lambda 322 11 4 3.25 Iso group, Node, Lambda

323 12 4 3.25 Iso group, Node, Lambda l 324 -1,0,0,0 End lambda input 325 0 7.0E-5 LCHG, Control room X/Q 326 0.88972 1.11944 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 327 000 LACTIN, LPTIN, LVOL 328 -1,0,0,0 End flow input i i

329 12 0.35 Iso group, Hode, Lambda  ! 330 32 0.35 Iso group, Node, Lambda 331 52 0.35 Iso group, Node, Lambda

_ _ . - _ _ _ _ _ ~- Anacnment o PY-CELERR-2076L Pagc 208 cf 217 PSAT 04202H.13 Page B19 of B26 Rev. 0@2 3 4 333 62 0.35 Iso group, Node, Lambda 333 72 0.35 Iso group, Node, Lambda 334 82 0.35 Iso group, Node, Lambda 335 92 0.35 Iso group, Node, Lambda 336 10 2 0.35 Iso group, Node, Lambda 337 11 2 0.35 Iso group, Node, Lambda 338 12 2 0.35 Iso group, Node, Lambda 339 -1,0,0,0 End lambda input 340 0 7.0E-5 LCHG, Control room X/O 341 1.11944 1.21778 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 343 000 LACTIN, LPTIN, LVOL 343 -1,0,0,0 344 End flow input 14 3.22 Iso group, Node, Lambda 345 34 3.22 Iso group, Node, Lambda 346 54 3.22 347 Iso group, Node, Lambda 64 3.22 Iso group, Node, Lambda 348 74 3.22 349 Iso group, Hode, Lambda 84 3.22 Iso group, Node, Lambda 350 94 3.22 331 Iso group, Node, Lambda 10 4 3.22 Iso group, Node, Lambda 353 11 4 3.22 353 Iso group, Node, Lambda 12 4 3.22 Iso group, Node, Lambda 354 -1,0, 0, O 355 0 7.0E-5 End lambda input 356 LCHG, Control room X/Q 1.21778 1.48306 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 357 000 358 -1,0,0,0 LACTIN, LPTIN, LVOL 359 12 0.45 End flow input 360 32 0.45 Iso group, Node, Lambda 361 52 0.45 Iso group, Node, Lambda 363 62 0.45 Iso group, Node, Lambda 363 72 0.45 Iso group, Node, Lambda 364 82 0.45 Iso group,, Node, Lambda 365 92 0.45 Iso group, Node, Lambda 366 10 2 0.45 Iso group, Node, Lambda 367 11 2 0.45 Iso group, Node, Lambda l 1 368 12 2 0.45 Iso group, Node, Lambda 369 -1,0,0,O Iso group, Node, Lambda 370 0 7.0E-5 End lambda input 371 1.48306 1.50000 1 0 0 1 LCHG, Control roam X/O 372 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 373 -1,0,0,0 LACTIN, LPTIN, LVOL i 374 14 3.30 End flow input 375 34 3.30 Iso group, Node, Lambda l 376 54 3.30 Iso group, Node, Lambda Iso group, Node, Lambda 377 64 3.30 l 378 74 3.30 Iso group, Node, Lambda  ! 379 84 3.30 Iso group, Node, Lambda I 380 94 3.30 Iso group, Node, Lambda 381 10 4 3.30 Iso group, Node, Lambda 383 11 4 3.30 Iso group, Node, Lambda 383 12 4 3.30 Iso group, Node, Lambda 384 -1,0,0,0 Iso group, Node, Lambda l 385 0 7.0E-5 End lambda input 386 1.50000 1.62833 1 0 0 1 LCHG, Control room X/O 387 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 388 7 1 3.183 0 LACTIN, LPTIN, LVOL 389 From node, To node, Filt flow, Unfilt flow 390 50 0 88.5 9 1 4.775 0 0 88.5 88.5 88.5 88.5 88.5 88.5 88.5 88.5 Filt eff 4 iso grps 1-12 391 From node, To none, illt flow, Unfilt flow 393 50 0 85.1 0 85.1 85.1 85.1 85.1 85.1 85.1 85.1 85.1 Filt eff 4 iso grps 1-12

      -1,0,0,0 393  -1,0,0,0                                                            End flow input End lambda input 4

394 0 7.0E-5 LCHG, Control room X/Q 395 1.62833 1.86167 1001 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 396 000 397 -1,0,0,0 LACTIN, LPTIN, LVOL l 398 12 0.54 End flow input l Iso group, Hode, Lambda

I hwun.:m o I PY-CEl/NRR-2076L t . P:ge 209 of 217 PSAT 04202H.13 Page B20 of B26 l Rev. 0@2 3 4 399 32 0.54 400 Iso group, Node, Lambda 52 0.54 Iso group, Node, Lambda 401 62 0.54 402 72 0.54 Isc group, Node, Lambda 403 82 0.54 Iso group, Node, Lambda 404 92 0.54 Iso group, Node, Lambda 405 10 2 0.54 Iso group, Node, Lambda 406 11 2 0.54 Iso group, Node, Lambda l 407 12 2 0.54 Iso group, Node, Lambda 408 -1,0,0,0 Iso group, Node, Lambda End lambda input 409 0 7.0E-5 410 LCHG, Control room X/O 1.86167 2.00000 1 0 0 1 Fram time, To time, IPRTAC, IAACT, IPACT, IPRINT 411' OOO 412 -1,0,0,0 LACTIN, LPTIN, LVOL 413 14 6.55 End flow input 414 34 6.55 Iso group, Node, Lambda ,

415 54 6.55 Iso group, Node, Lambda 416 64 6.55 Iso group, Node, Lambda 417 74 6.55 Iso group, Node, Lambda 418 84 6.55 Iso group, Node, Lambda 419 94 6.55 Iso group, Node, Lambda 420 10 4 6.55 Iso group, Node, Lambda 421 11 4 6.55 Iso group, Node, Lambda 422 12 4 6.55 Iso group, Node, Lambda 423 -1,0,0,0 Iso group, Node, Lambda 424 0 7.0E-5 End lambda input 425 2.00000 2.00833 1 0 0 1 LCHG, Control room X/Q 426 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 427 -1,0,0,0 LACTIN, LPTIN, LVOL 428 -1,0,0,0 End flow input 429 0 7.0E-5 End lambda input r 430 2.00833 2.03694 1 0 0 1 LCHG, Control room X/Q 431 010 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 432 00000000 LACTIN, LPTIN, LVOL 433 00000000 Initial I-131 elem act frac in nodes 2-9 434 00000000 Initial I-131 orgn act frac in nodes 2-S 435 00000000 Initial I-131 part act frac in nodes 2-9 436 00000000 Initial I-132 elem act frac in nodes 2-9 437 00000000 Initial 2-132 orgn act frac in nodes 2-9 438 00000000 Initial I-132 part act frac in nodes 2-9 439 00000000 Initial 2-133 elem act frac in nodes 2-9 440 00000000 Initial I-133 orgn act frac in nodes 2-9 441 00000000 Initial I-133 part act frac in nodes 2-9 442 00000000 Initial I-134 elem act frac in nodes 2-9 443 00000000 Initial I-134 orgn act frac in nodes 2-9 444 00000000 Initial I-134 part act frac in nodes 2 9 445 00000000 Initial I-135 elem act frac in nodes 2-9 446 00000000 Initial I-135 orgn act frac in nodes 2-9 447 00000000 Initial I-135 part act frac in nodes 2-9 448 00000000 Initial Kr-83m act frac in nodes 2-9 449 00000000 Initial Kr-85 act frac in nodes 2-9

450 00000000 Initial Kr-85m act frac in nodes 2-9 451 00000000 Initial Kr-87 act frac in nodes 2-9 452 00000000 Initial Kr-8B act frac in nodes 2-9 453 00000000 Initial Kr-89 act frac in nodes 2-9 454 00000000 Initial Xe-131m act frac in nodes 2-9 455 00000000 Initial Xe-133m act frac in nodes 2-9 456 00000000 Initial Xe-133 act frac in nodes 2-9 l 457 00000000 Initial Xe-135m act frac in nodes 2-9 458 00000000 Initial Xe-135 act frac in nodes 2-9 is9 00000000 Initial Xe-137 act frac in nodes 2-9 460 00000000 Initial Xe-138 act frac in nodes 2-9 461 00000000 Initial CS-134 act frac in nodes 2-9 i 462 00000000 Initial CS-137 act frac in nodes 2-9 463 00000000 Initial TE-132 act frac in nodes 2-9 464 2300 Initial BA137M act frac in nodes 2-9 I 465 000000000000 From node, To node, Filt flow, Unfilt flow i Filt eff for iso groups 1-12 l l

mmm,nm u PY-CElWRR-2075L Pcge 210 of 217 PSAT 04202H.13 Page B21 of B26  ! Rev. 0@ 2 3 4 i 466 -1,0,0,0 467 -1,0,0,0 End flow input End lambda input 468 0 7.0E-5 LCHG, Control room X/Q 469 2.03694 2.04000 1 0 0 1 470 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 000 LACTIN, LPTIN, LVOL 471 2 3 0 5.4E+4 From node, To node,' Filt flow, Unfilt flow 4 T3 000000000000 Filt eff for iso groups 1-12 73 1,0,0,O 474 12 0.58 End flow input l 475 31 0.58 Iso group, Node, Lambda l 476 5 .' O.58 Iso group, Node, Lambda  ! 477 62 0.58 Iso group, Node, Lambda 1 478 72 0.58 Iso group, Node, Lambda  ! 479 82 0.58 Iso group, node, Lambda l 480 02 0.58 Iso group, Node, Lambda  ! 481 10 2 0.58 Iso group, Node, Lambda i 483 11 2 0.58 Iso group, Node, Lambda  ; 483 12 2 0.58 Iso group, Node, Lambda I 484 -1,0,0,O Iso group, Node, Lambda ' 485 0 7.0E-5 End lambda input 486 2.04000 2.04333 1 0 0 1 LCHG, Control room X/Q 487 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 488 2 3 0 1.3E+5 LACTIN, LPTIN, LVOL 489 000000000000 From node, To node, Filt flow,'Jnfilt flow 490 -1,0,0,0 Filt eff for irs groups 1-12 491 -1,0,0,O End flow input 492 0 7.0E-5 End lambda input 493 2.04333 2.04 ti94 1 0 0 1 LCHG, Control room X/O 494 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 495 2 3 0 1.BE+5 LACTIN, LPTIN, LVOL 496 000000000000 From node, To node, Filt flow, Unfilt flow  ! 497 -1,0,0,0 Filt eff for iso groups 1-12 498 -1,0,0,O End flow input 499 0 7.0E-5 End lambda input 500 2.04694 2.04917 1 0 0 1 LCHG, Control room X/Q 501 000 From time, To time, IPRTAC, IAACT/ IPACT, IPRINT 503 2 3 0 2.1E+5 LACTIN, LPTIN, LVOL 503 000000000000 From node, To node, Filt flow, Unfilt flow 504 -1,0,0,0 Filt eff for iso groups 1-12 505 -1,0,0,O End flow input 306 0 7.OE-5 End 1ambda input j i 507 2.04917 2.05083 1 0 0 1 LCHG, Control room X/O 500 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT I 509 -1,0,0,0 LACTIN, LPTIN, LVOL 510 14 3.30 End flow input 511 34 3.30 - Iso group, Node, Lambda 513 54 3.30 Iso group, Node, Lambda $13 64 3.30 Iso group, Node, Lambda 514 74 3.30 Iso group, Node, Lambda 515 84 3.30 Iso group, Node, Lambda 516 94 3.30 Iso group, Node, Lambda $17 10 4 3.30 Iso group, Node, Lambda SIB 11 4 3.30 Iso group, Node, Lambda 519 12 4 3.30 Iso group, Node, Lambda 530 -1,0,0,O Iso group, Node, Lambda 538 0 7.OE-5 End Iambda input 532 2.05083 2.05472 1 0 0 1 LCHG, Control room X/Q 533 000 From time, To time, IFhiAC, IAACT, IPACT, IPRINT 534 2 3 0 2.3E+5 LACTIN, LPTIN, LVOL 523 000000000000 From node, To node, Filt flow, Unfilt flow 536 -1,0,0,0 Filt eff for iso groups 1-12 537 -1, 0, 0, O End flow input 528 0 7.0E-5 End lambda input 539 2.05472 2.05861 1 0 0 1 LCHG, Control room X/Q 530 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 531 2 3 0 2.5E+5 LACTIN, LPTIN, LVOL 533 000000000000 From node, To node, Filt flow, Unfilt flow Filt eff for iso groups 1-12

m .uu.u. - PY-CEIMRR-2076L Pcge 211 of 217 PSAT 04202H.13 Page B22 of B26 Rev. 0@2 3 4 533 -1,0,0,0 End flow input 534 -1,0,0,0 End lambda input 535 0 7.0E-5 LCHG, Control room X/Q 536 2.05861 2.06250 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 537 000 LACTIN, LPTIN, LVOL 538 2 3 0 2.6E+5 From node, To node, Filt flow, Unfilt flow 539 000000000000 Filt eff for iso groups 1-12 540 -1,0,0,0 End flow input 541 -1,0,0,0 . End lambda input 542 0 7.0E-5 LCHG, Control room X/Q 543 2.06250 2.06639 1 0 0 1 From time, To time, IPRTAC, LAACT, IPACT, IPRINT 544 000 545 LACTIN, LPTIN, LVOL 2 3 0 2.1E+5 From node, To node, Filt flow, Unfilt flow 546 000000000000 547 Filt eff for iso groups 1-12

     -1,0,0,0 540                                                                    End flow input
     -1,0,0,0
                                                                    'End 1ambda input 549  0 7.0E-5                                                LCHG, Control room X/Q 550  2.06639 2.06972 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 551  000 552                                                             LACTIN, LPTIN, LVOL 2 3 0 1.6E+5                  From node, To node, Filt flow, Unfilt flow 553  000000000000 954                                                  Filt off for iso groups 1-12
     -1,0,0,0 555  -1,0,0,0                                                          End flow' input 556  0 7.0E-5                                                        End lambda input 557                                                          LCHG, Control room X/Q 2.06972 2.07306 1 0 0 1 From time, To time, IFRTAC, IAACT, IPACT, IPRINT 558  000 559                                                             LACTIN, LPTIN, LVOL 2 3 0 1.OE+5                  From node, To node, Filt flow, Unfilt flow 560  000000000000 561  -1,0,0,0                                        Filt eff for iso groups 1-12
$62  -1,0,0,O                                                          End flow input 563  0 7.0E-5                                                        End lambda input 564                                                          LCHG, Control room X/Q 2.07306 2.07611 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 565  000 566  2 3 0 55000. .                                             LACTIN, LPTIN, LVOL-567                                From node, To node, Filt flow, Unfilt flow 568 000000000000                                    Filt off for. iso groups 1-12
     -1,0,0,0 569  -1,0,0,O                                                          End flow input 570  0 7.0E-5                                                        End lambda input 571                                                          LCHG, Control room X/Q 2.07611 2.07890 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 572  000

.573 2 3 0 12000. LACTIN, LPTIN, LVOL From node, To node, Filt flow, Unfilt flow 574 575 0000000'OOOOO Filt eff for iso groups 1-12

     -1,0,0,0 576  -1,0,0,O                                                          End flow input 577  0 7.0E-5                                                        End 1ambda input 578                                                          LCHG, Control room X/Q 2.07890 2.15556 1 0 0 1 579 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 000                                                        LACTIN, LPTIN, LVOL j

580 2 7 0 1.65 Fran node, To node, Filt flow, Unfilt flow 581 000000000000 l Filt eff for iso groups 1-12 582 2 8 0 2.47 From node, To node, Filt flow, Unfilt flow l 503 000000000000 Filt eff for iso groups 1-12 584 2 3 0 500. From node,. To node, Filt flow, Unfilt flow 585 000000000000 Filt eff for iso groups 1-12 586 3 2 0 500. From node, To node, Filt flow, Unfilt flow 587 000000000000 . 588 -1,0,0,0 Filt eff for iso groups 1-12 l 589 12 0.54 End flow input 590 Iso group, Node, Lambda 32 0.54 Iso group, Node, Lambda 591 52 0.54 592 62 0.54 Iso group, Node, Lambda Iso group, Node, Lambda l' 593 72 0.54 594 Iso group, Node, Lambda 82 0.54 Iso group, Node, Lambda 595 92 0.54 Iso group, Node, Lambda 596 10 2 0.54 Iso group, Node, Lambda 597 11 2 0.54 Iso group, Node, Lambda 598 12 2 0.54 Iso group, Node, Lambda 599 -1,0,0,0 End lambda input

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

h Anachment 6  ; PY.CELHRR-2076L l Pge 212 of 217 l l PSAT 04202H.13 4 Page B23 of B26 l Rev. 0@2 3 4 600 0 7.OE-5 LCHG, Control room X/Q I

       . 601               2.15556 2.57056 1 0 0 1 602               000                                        From time, To time, IFRTAC, IAACT, IPACT, IPRINT 603               -1,0,0,0                                                                         LACTIN, LPTIN, LVOL                       1 1

604 14 1.19 End flow input 605 Iso group, Node, Lambda l 34 1.19 j j 606 54 1.19 Iso group, Node, Lambda - 607 64 1.19 Iso group, Node, Lambda 608 Iso group, Hode, Lambda { 4 74 1.19

,        609              84 1.19                                                                 Iso group, Node, Lambda                             !

! 610 94- 1.19 Iso group, Node, Lambda 611 10 4 1.19 Iso group, Node, Lambda < 613 11 4 1.19 Iso group, Node, Lambda 613 12 4 1.19 Iso group, Node, Lambda 6A4 -1,0,0,0 Iso group, Node, Lambda 615 0 7.0E-5 End lambda input 616 2.57056 3.00000 1 0 0 1 LCHG, Control room X/Q + 617 000 From time, To time, IFRTAC, IAACT, IPACT, IPRINT 3 618 -1,0,0,0 LACTIN, LPTIN, LVOL j 619 12 0.45 End flow input

620 32 0.45 Iso group, Node, Lambda 631 52 0.45 Iso group, Node, Lambda

, 622 62 0.45 Iso group, Node, Lambda i 623 72 0.45 Iso group, Node, Lambda 624 82 0.45 Iso group, Node, Lambda 635 92 0.45 Iso group, Node, Lambda 636 10 2 0.45 Iso group, Node, Lambda 627 11 2 0.45 Iso group, Node, Lambda 638 12 2 0.45 Iso group, Node, Lambda 629 -1,0,0,0 Iso group, Hode, Lambda 630 0 7.0E-5 End lambda input { 631 LCHG, Control room X/O 3.00000 3.25667 1 0 0 1 4 j 633 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT j 633 713.1830 LACTIN, LPTIN, LVOL j 634 From node, To node, Filt flow, Unfilt flow 635 50 9 104.775 90.0 00 90.0 90.0 90.0 90.0 90.0 90.0 90.0 90.0 Filt eff 4 iso grps 1-12 j 636 From node, To node, Filt flow, Unfilt flow 637 50 0 85.9 0 85.9 85.9 85.9 85.9 85.9 85.9 85.9 85.9 Filt eff 4 iso grps 1-12

                         -1,0,0,0 638              -1,0,0,0                                                                               End flow input i       639               0 7.0E-5                                                                             End lambda input j       640              3.25667 4.41139 1 0 0 1                                                    LCHG, Control room X/Q l       641              000                                          From time, To time, IPRTAC, IAACT, IPACT, IPRINT 642              -1,0,0,0                                                                          LACTIN, LPTIN, LVOL 643              14 0.50                                                                                 End flow input j       644              34 0.50                                                                 Iso group, Node, Lambda 645              54 0.50                                                                 Iso group, Node, Lambda 646              64 0.50                                                                 Iso group, Node, Lambda i       647              74 0.50                                                                 Iso group, Node, Lambda Iso group, Node, Lambda

648 84 0.50

;      649              94 0.50                                                                 Iso group, Node, Lambda

! 650 10 4 0.50 Iso group, Node, Lambda

651 11 4 0.50 Iso group, Node, Lambda j 653 12 4 0.50 Iso group, Node, Lambda a 653 -1,0,0,0 Iso group, Node, Lambda 1

654 0 7.0E-5 End lambda input ! 655 4.41139 4.85250 1 0 0 1 LCHG, Control room X/Q 656 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 4 657 -1,0,0,0 LACTIN, LPTIN, LVOL 4 658 12 0.35 End flow input , 659 32 0.35 Iso group, Node, Lambda 1 660 52 0.35 Iso group, Node, Lambda

 !     661              62 0.35                                                                 Iso group, Node, Lambda 663              72 0.35                                                                 Iso group, Node, Lambda 1

663 82 0.35 Iso group, Node, Lambda j 664 92 0.35 Iso group, Node, Lambda 665 10 2 0.35 Iso group, Hode, Lambda 666 11 2 0.35 Iso group, Node, Lambda Iso group, Node, Lambda I i

munau PY-CE!/NRR-2076L Pqe 213 of 217 PSAT 04202H.13 Page B24 of B26 Rev. 0@2 3 4 667 12 2 0.35 Iso group, Mode, Lambda 668 -1,0,0,0 End Ismbda input 669 0 7.0E-5 LCHG, Cor.crol room X/O 670 4.85250 5.00000 1 0 0 1 From time, To time, IFRTAC, IAACT, IPACT, IPRINT 671 000 L%CTIN, LPTIN, LVOL 672 -1,0,0,0 End flow input 673 14 0.27 Iso group, Node, Lambda 674 34 0.27 Iso group, Node, Lambda 675 54 0.27 Iso group, Node, Lambda 676 64 0.27 Iso group, Node, Lambda 677 74 0.27 Iso group, Node, Lambda 678 84 0.27 Iso group, Node, Lambda 679 94 0.27 Iso group, Node, Lambda 680 10 4 0.27 Iso group, Node, Lambda 681 11 4 0.27 Iso group, Node, Lambda 682 12 4 0.27 Iso group, Node, Lambda 683 -1,0,0,0 End lambda input 684 0 7.0E-5 LCHG, Control room X/Q 685 5.00000 6.00000 1 0 0 1 686 From time, To time, IFRTAC, IAACT, IPACT, IFRINT 000 LACTIN, LPTIN, LVOL 687 7 1 3.183 0 From node, To node, Filt flow, Unfilt flow 688 s 50 0 87.4 0 87.4 87.4 87.4 87.4 87.4 87.4 87.4 87.4 Filt eff 4 iso grps 1-12 s 689 9 1 4.775 0 From node, Te r. ode, Filt flow, Unfilt flow 690 691 50084.9084.984.984.984.984.984.984.984.9 Fi.t eff 4 iso grps 1-12

      -1,0,0,0 692  -1,0,0,O                                                              End flow input 693  0 7.0E-5                                                           End lambda input 694                                                             LCHG, Control room X/Q 6.00000 7.00000 1 0 0 1        From time, To time, IPRTAC, IAACT, IPACT, IPRINT 695  000 696  -1,0,0,0                                                       LACTIN, LPTIN, LVOL 697  -1,0,0,O                                                             End flow input 698  0 7.0E-5                                                           End lambda input 699                                                             LCHG, Control room X/O 7.00000 8.00000 1 0 0 1       From time, To time, IPRTAC, IAACT, IPACT, IFRINT 700  000 LACTIN, LPTIN, LVOL 701  7 1 3.183 0                          From node, To node, Filt flow, Unfilt flow 702 103  50   0  83.5 9 1 4.775 0  0 83.5 83.5 83.5 83.5 83.5  83.5 83.5 83.5 Filt eff 4 iso grps 1-12 704                                       From node, To node, Filt flow, Unfilt flow 705  50081.8081.881.881.881.881.881.881.881.8
      -1,0,0,0                                               Filt eff 4 iso grps 1-12 706  -1,0,0,0                                                             End flow input 707  0 7.0E-5                                                          End lambda input 708                                                             LCHG, Control room X/Q 8.00000 8.51917 1 0 0 1       From time, To time, IPRTAC, IAACT, IPACT, IPRINT 709  000 710  -1,0,0,0                                                       LACTIN, LPTIN, LVOL 711  -1, 0, 0, O                                                          End flow input 712  0 5.6E-5                                                          End lambda input 713                                                             LCHG, Control room X/Q 8.51917 8.56194 1 0 0 1       From time, To time, IPRTAC, IAACT, IPACT, IPRINT 714  000 715  -1,0,0,0                                                       LACTIN, LPTIN, LVOL 716  12 0.25                                                              End flow input 787  32 0.25                                                 Iso group, Node, Lambda 718  52 0.25                                                 Iso group, Node, Lambda 719  62 0.25                                                 Iso group, Node, Lambda 730  72 0.25                                                  Iso group, Node, Lambda 721  82 0.25                                                 Iso group, Node, Lambda 732  92 0.25                                                 Iso group, Node, Lambda 723  10 2 0.25                                               Iso group, Node, Lambda 734  11 2 0.25                                               Iso group, Node, Lambda 735  12 2 0.25                                               Iso group, Node, Lambda 736  -1,0,0,O                                                Iso group, Node, Lambda 737  0 5.6E-5                                                          End lambda input 728                                                             LCHG, Control room X/Q 8.56194 9.00000 1 0 0 1       From time, To time, IFRTAC, IAACT, IPACT, IFRINT 739  000 730  -1,0,0,0                                                       LACTIN, LPTIN, LVOL 731  14 0.23                                                              End flow input 732  34 0.23                                                  Iso group, Node, Lambda 733  54 0.23                                                 Iso group, Node, Lambda Iso group, Node, Lambda

muiwouunu PY-CEl/NRR-2076L Page 214 of 217 PSAT 04202H.13 Page B25 of B26 Itev. 06)23 4 734 64 0.23 Iso group, Node, Lambda 735 74 0.23 Iso group, Node, Lambda 736 84 0.23 Ise group, Node, Lambda 737 94 0.23 Iso group, Node, Lambda 738 10 4 0.23 Iso group, Node, Lambda 739 11 4 0.23 Iso group, Node, Lambda 140 12 4 0.23 Iso group, Node, Lambda 741 -1,0,0,0 End lambda input 742 0 5.6E-5 LCHG, Control room X/Q 743 9.00000 11.0000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 744 000 LACTIN, LPTIN, LVOL 145 7 1 3.183 0 From node, To node, Filt flow, Unfilt flow 746 50 0 79.0 0 79.0 79.0 79.0 79.0 79.0 79.0 79.0 79.0 Filt off 4 iso grps 1-12 747 9 1 4.775 0 . From node, To node, Filt flow, Unfilt flow 748 749 50 0 77.8 0 77.8 77.8 77.8 77.8 77.8 77.8 77.8 77.8 Filt eff 4 iso grps 1-12

      -1,0,0,0 150                                                                       End flow input
      -1,0,0,0                                                                                                   {

751 0 5.6E-5 End lambda input j

 '752                                                          LCHG, Control room X/Q 11.0000 11.1219 1 0 0 1      From time, To time, IPRTAC, IAACT, IPACT, IFRINT 753  000                                                          LACTIN, LPTIN, LVOL 754  7 1 3.183 0                         From node, To node, Filt flow, Unfilt flow 755 156  50  0 42.3 9 1 4.775 0 0 42.3 42.3  42.3 42.3 42.3  42.3 42.3 42.3 Filt off 4 iso grps 1-12 737                                     From node, To node, Filt flow, Unfilt flow 758  50 0 43.7 0 43.7 43.7 43.7 43.7 43.7 43.7 43.7 43.7 Filt eff 4 iso grps 1-12
      -1,0,0,0 759  -1,0,0,O                                                            End flow input 760  0 5.6E-5                                                        End 1ambda input             -

761 LCHG, Control room X/Q 11.1219 14.3442 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 762 000 763 -1,0,0,0- LACTIN, LPTIN, LVOL 764 14 0.2 End flow input 165 34 0.2 Iso group, Node, Lambda 766 54 0.2 Iso group, Node, Lambda 767 64 0.2 Iso group, Node, Lambda 768 74 0.2 Iso group, Node, Lambda 769 84 0.2 Iso group, Node, Lambda 770 94 0.2 Iso group, Node, Lambda 771 10 4 0.2 Iso group, Node, Lambda 778 11 4 0.2 Iso group, Node, Lambda 773 12 4 0.2 Iso group, Node, Lambda 774 -1,0,0,0 Iso group, Node, fm=hda 775 0 5.6E-5 End lambda input 776 14.3442 19.3092 1 0 0 1 LCHG, Control room X/Q

• 777 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 778 -1,0,0,0 LACTIN, LPTIN, LVOL 779 12 0.16 End flow input 780 32 0.16 Iso group, Node, Lambda 781 52 0.16 Iso group, Node, Lambda 783 62 0.16 Iso group, Node, Lambda 783 72 0.16 Iso group, Node, Lambda 784 82 0.16 Iso group, Node, Lambda 785 92 0.16 Iso group, Node, Lambda 786 10 2 0.16 Iso group, Node, Lambda 787 11 2 0.16 Iso group, Node, Lambda 788 12 2 0.16 Iso group, Node, Lambda 789 -1,0,0,0 Iso group, Node, Lambda 790 0 5.6E-5 End lambda input 791 19.3092 21.0000 1 0 0 1 LCHG, Control room X/Q 792 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 193 -1,0,0,0 LACTIN, LPTIN, LVOL 794 14 0.19 End flow input 795 34 0.19 Iso . group, Node, Lambda 796 54 0.19 Iso group, Node, Lambda 797 64 0.19 Iso group, Node, Lambda 798 74 0.19 Iso group, Node, Lambda 799 84 0.19 Iso group, Node, Lambda 800 94 0.19 Iso group, Hode, Lambda 1so group, Node, Lambda

PY-CEl/NRR-2076L Page 215 of 217 PSAT 04202H.13 Page B26 of B26 Rev. 0@ 2 3 4 801 10 4 0.19 Iso group, Node, Lambda 802 11 4 0.19 Iso group, Node, Lambda 803 12 4 0.19 Isc group, Node, Lambda 954 -1,0,0,0 805 0 5.6E-5 End lambda input 806 LCHG, Control room X/Q 21.0000 24.0000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 807 000 808 -1,0,0,0 LACTIN, LPTIN, LVOL 809 -1, 0, 0, O End flow input 810 0 5.6E-5 End lambda input 811 LCHG, Control room X/O 24.0000 24.5000 1 0 0 1 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 812 000 LACTIN, LPTIN, LVOL 813 6 1 6.684 0 From node, To node, Filt flow, Unfilt flow 814 90 90 90 90 90 90 90 90 90 90 90 90 815 -1,0,0,0 Filt eff for iso groups 1-12 816 14 0.0 End flow input 817 34 0.0 Iso group, Node, Lambda 818 Iso group, Node, Lambda 54 0.0 Iso group, Node, Lambda B19 64 0.0 820 74 0.0 Iso group, Node, Lambda 821 84 0.0 Iso group, Node, Lambda 822 94 0.0 Iso group, Node, Lambda Iso group, Node, Lambda 823 10 4 0.0 Iso group, Node, Lambda 824 11 4 0.0 Iso group, Node, Lambda 825 12 4 0.0 Iso group, Node, Lambda 826 -1,0,0, O 827 0 4.3E-5 End lambda input 828 24.5000 27.7778 1 0 0 1 LCHG, Control room X/Q 829 000 From time, To time, IFRTAC, IAACT, IPACT, IPRINT 830 6 1 0.03342 O LACTIN, LPTIN, LVOL 831' From node, To node, Filt flow, Unfilt flow 832 90 90 90 90 90 90 90 90 90 90 90 90

        -1,0,0,0                                           Filt eff for iso groups 1-12 833    -1,0,0,0                                                            End flow input 834    0 4.3E-5                                                          End lambda input 835    27.7778 96.0000 1 0 0 1                                    LCHG, Control room X/Q 836    000                          From time, To time, IFRTAC, IAACT, IPACT, IPRINT 837   -1,0,0,0                                                       LACTIN, LPTIN, LVOL 838   12 0.0                                                               End flow input 839   32       0.0                                              Iso group, Node, Lambda 840   52       0.0                                              Iso group, Node, Lambda 841   62       0.0                                              Iso group, Node, Lambda 842   72       0.0                                              Iso group, Node, Lambda 843   82       0.0                                              Iso group, Node, Lambda 844   92       0.0                                              Iso group, Node, Lambda 845   10 2 0.0                                                  Iso  group,  Node, Lambda 846   11 2 0.0                                                  Iso  group,  Node, Lambda 847   12 2 0.0                                                  Iso  group,  Node, lambda 848   -1,0,0,0                                                  Iso  group,  Node, Lambda 849   0 4.3E-5                                            '

End lambda input 850 96.0000 720.000 1 0 0 1 LCHG, Control room X/Q 851 000 From time, To time, IPRTAC, IAACT, IPACT, IPRINT 852 -1,0,0,0 LACTIN, LPTIN, LVOL 853 -1, 0, 0, O End flow input 854 0 1.5E-5 End lambda input LCHG, Control room X/Q I

anaanaao i PY-CITNRR 2076L I Page 216 of 217 l

                                                                                                        \

PSAT 04202H.13 Page C1 of C1 Rev. 0@2 3 4 Appendix C: "LOCADOSE input file" l PERRY CR, EAB & LPZ DOSES (BASE) W/ REVISED SOURCE TERM JUN LI Problem title { PERRY PHASE II Originator l PSAT 04202H Project name Project # l PSAT 04202H.13 0 Calc 6, Rev l 1 l DORDOF First page 6 of output I 2533100 Output flag NXQ, NXQT, NBRT, NOCT, NRBRT, EVACDO, OUTFIL REM REM /HR Dose unit, Dose rate unit 4.3E-4 0 0 0 0 SB X/O during time step 1-5 (NXQT entries) 3.47E-4 1.75E-4 2.32E-4 SB breath rate during time step 1-3 (NBRT entries) 4.8E-5 4.BE-5 3.3E-5 1.4E-5 4.1E-6 LPZ X/Q for time step 1-5 (NXQT entries) 3.47E-4 1.75E-4 2.32E-4 LPZ breath rate during time step 1-3 (NBRT entries) 282496720 Time step end points for X/O values (NXQT entries) 8 24 720' 11 Time step end pts for offsite breath rate (NBRT entries) 111 Gamma cloud correct fac for SB, LPZ  ! 3.47E-4 Occup fac for node 2 (NOCT entries) l 111 Breath rates for node 2 (NRBRT entries) 3.47E-4 Occup fac for node 3 (NOCT entries) 111 Breath rates for node 3 (NRBRT entries) 3.47E-4 Occup fac for node 4 (NOCT entries) 111 Breath rates for node 4 (NRBRT entries) 3.47E-4 Occup fac for node 5 (NOCT entries) 11* Breath rates for node 5 (NRBRT entries) 3.47E-4 Occup fac for node 6 (NOCT entries) 111 Breath rates for node 6 (NRBRT entries) 3.47E-4 Occup fac for node 7 (NOCT entries) 111 Breath rates for node 7 (NRBRT entries) 3.47E-4 Occup fac for node 8 (NOCT entries) 111 Breath rates for node 8 (NRBRT entries) 3.47E-4 Occup fac for node 9 (NOCT entries) 1 .6 .4 Breath rates for node 9 (NRBRT entries) 3.47E-4 Occup fac for node 0 (NOCT entries) 24 96 720 Breath rates for node 0 (NRBRT entries) 720 Time step end pts for occup fac (NOCT entries) 111111111 Time step end pts for onsite breath rates (NRBRT entries) Gamma cloud correct factor for nodes 2-10

PY-CElHRR-2076L e Page 217 0f 217 , PSAT 04202H.13 P g2 D1 of D1 Rev. 0@2 3 4 Appendix D: " Dose calculation results for the two cases and the confirmation on 1

   - additionalisotopes from Table 1."

This appendix contains three 3.5" high density IBM formatted diskettes. , l l l l I I e l L l i 1 i l i 1 i j}}