ML20236T793

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Non-proprietary Rev 1 to Psat 08410T.03, Pnpp Rast Calculation Using Tede/'Worst Two Hour' Sliding Window
ML20236T793
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 05/29/1998
From: Leaver D, Metcalf J
POLESTAR APPLIED TECHNOLOGY, INC.
To:
Shared Package
ML20138K431 List:
References
PSAT-08401T.03, PSAT-08401T.03-R01, PSAT-8401T.3, PSAT-8401T.3-R1, NUDOCS 9807290019
Download: ML20236T793 (11)
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Text

Attachmsnt 6

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+ Attachment 6 +

Non-Proprietary PNPP RAST Calculations using TEDE/" worst two hour" sliding window '

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9907290019 DR 980722 ADOCK 05000440 PDR-

' PSAT 08401T.03 POLESTAR NON-PROPRIETARY Page 1 of 10 Rev. 0@ 3 4 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 0840lT.03 CALCULATION TITLE:

" Perry Plant Total Effective Dose Equivalent (TEDE) Calculation" ORIGINATOR CHECKER IND REVIEWER Print / Sign Date Print / Sign Date Print / Sign Date jyjgy qqe s/ftfra

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REASON FOR REVISION: Nonconformance Rpt 0 -InitialIssue N/A 1 - Revise to incorporate definition of TEDE (p.2), incorporate refs.[10], N/A

[11), and [12], incorporate more detail on the basis for completeness of the additional isotopes considered for the TEDE calculation (p. 6),

and to make minor editorial changes 2

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PSAT 0840lT.03 POLESTAR NON-PROPRIETARY Pege 2 of 10 Rev. 012 3 4 Table of Contents Section Py Purpose 2 Methodology 2 Assumptions 4 References 5 Calculation 6 Results 8 Conclusions 9 Attachment 1 LIBFILEl File (proprietary)

Attachment 2 STARDOSE Input File (proprietary)

Attachment 3 Partial STARDOSE Output File (4 pages)

Attachment 4 Complete STARDOSE Output File (proprietary)

Purpose The purpose of this calculation is to evaluate the total effective dose equivalent (TEDE) for the Perry Nuclear Plant radiological design basis accident (DBA) using the revised accident source term based on NUREG 1465 [1] release parameters and on associated fission product removal phenomena. CEI has requested the TEDE calculations as a supplement to the whole body (WB) and thyroid dose calculations noted below.

The PSAT 04202 calculation set prepared by Polestar Applied Technology,Inc. for the Perry Plant [2,3] utilized the revised DBA source term and evaluated WB and thyroid doses [4] in accordance with existing NRC requirements (10 CFR 100). This calculation set was submitted by CEI to NRC in 1996. Key results from these calculations, as well as the Perry Plant design inputs, are contained in reference [5] and are used as design inputs for the TEDE calculation.

Methodology l g . ~ -

l The TEDEWaluations were performed using the STARDOSE code [6,7,8] developed and maintained by Polestar under Polestar's Appendix B QA Program. STARDOSE is a DBA dose code that is designed for applications of the revised accident source term [1] as well as the existing accident source term [9]. TEDE is defined per reference [10] as the sum of the deep-I

PSAT 0840lT.03 POLESTAR NON-PROPRIETARY Page 3 of10 Rev. 012 3 4 dose equivalent (for external exposure) and the committed efTective dose equivalent (for intemal exposure). Per reference [10), deep-dose equivalent is the dose equivalent at a tissue depth of I l em and applies to whole body exposure. .

The overall dose calculation model consists of ten control volumes. These control volumes and l their names in the STARDOSE input file INPUT.DAT (Attachment 2) are as follows: 1.

j damaged core and RCS (core),2. drywell portion of the primary containment (Dry _.Well),3.

! unsprayed portion of the containment (Unsprayed Cont),4. sprayed portion of the containment (Sprayed Cont), S. suppression pool (Suppression Pool), 6. containment annulus (Annulus),7.

space between the inboard and outboard MSIVs in the broken steamline wherein the inboard and l outboard MSIVs are assumed to successfully close but the third MSIV fails to close (Steamline2), 8. space in the horizontal portion of the steam pipe from the reactor vessel out to the inboard MSIV in the 2 intact steamlines in which 100 scfh and 50 scfh leakage, respectively, are assumed to occur (Pipe 2steamlinel), 9. the space between the inboard and outboard MSIVs 1

( in these two intact steamlines wherein the inboard and outboard MSIVs are assumed to successfully close but the third MSIV fails to close (Steamlinel), and 10. the control room (Control _ Room). These control volumes are arranged as shown on Exhibits 2 and 4 of reference i [4], with the variousjunctions that connect them. Thesejunctions are associated with volumetric flows which determine the rate at which radioactivity is exchanged between the control volumes.

( In addition removal processes such as spray impaction, sedimentation, adsorption, pool scrubbing, filtration and other are modeled within and between the control volumes, as l

I appropriate. These junctions are also identified in INPUT.DAT.

The junctions related to containment transport and environmental release include:

. Drywell-to-unsprayed containment, e Unsprayed containment-to-drywell vacuum breaker flow, l * - Annulus exhaust flow to environment I

. Leakage flow to the annulus from the sprayed containment and unsprayed containment

. Ilypass pathways (MSIV leakage into steamlines, steamline flow to environment, annulus bypass) e Suppression pool (ESP) leakage to environment l

  • Exchange between sprayed and unsprayed containment regions L e Control room exchange with environment e Core (and RCS) release of fission products to drywell and suppression pool L

i The corejunctions effect the release of radioactivity to both the drywell and the  !

suppression pool in parallel. The drywell and suppression pool release are an example of conservative " double-counting" in that the same amount of activity is assumed to be in ,

both places at the same time. In fact, the release of radioactivity to the suppression pool  !

is conservatively assumed in the analysis to be complete within the first half hour of the accident, even though it actually takes many hours for the sprays and other mechanisms to remove the radioactivity from the containment atmosphere and get it into the water of i the suppression pool.  !

PSAT 0840lT.03 POLESTAR NON-PROPRIETARY Page 4 of 10 Rev. 012 3 4 Control room junctions exist in the model to take activity out of the environment (after it has been diluted by the appropriate X/Q) and bring it into the control room.

Assumptions Assumptions 2,3,4, and 5 from reference [4] apply to the TEDE calculation. Additional assumptions are as follows:

Assumption 1:The doses to be evaluated are the exclusion area boundary (EAB) and low population zone (LPZ) TEDE, and the 10 CFR 50, Appendix A, General Design Criterion (GDC) 19 control room TEDE.

Justification: The regulatory requirements for operating plants are the 10 CFR 100 EAB and LPZ WB and thyroid dose, and the 10 CRF 50, Appendix A, General Design Criterion (GDC) 19 control room WB dose or its equivalent. These doses were calculated by Polestar for the Perry Plant revised source term application in 1996. CEI now desires to determine TEDE for the Perry revised source term application. NRC recently put in place a requirement for advanced plants to meet TEDE limits including EAB (maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and LPZ limits of 25 rem TEDE [11], and it is anticipated that NRC will eventually require that similar limits be met for operating plants which apply the revised source term.

Assumption 2:'Ihe design inputs of reference [5] apply to the Perry TEDE calculation.

Justification: The radiological DBA source term release magnitude, timing, and chemical fonn for the TEDE calculation are based on NUREG 1465 as was the case for calculation set PSAT 04202. Similarly, the fission product transport parameters to be used for TEDE are evaluated based on the NUREG 1465 source term characteristics and the Perry design, and thus are identical to that used in the calculation set PSAT 04202. The only difference in design inputs for TEDE vs. the earlier WB and thyroid dose calculation is that additional input data is required, ,

i.e., the TEDE requires additional isotopes to be considered, requires initial core inventories for these additional isotopes, requires release fractions for these additionai isotopes, requires WB ]

and committed effective dose equivalent (CEDE) dose conversion factors (DCFs) for these additional isotopes, and requires CEDE DCFs for the original set ofisotopes used in the calculation set PSAT 04202.

Assumption 3: Configuration 2 from calculation set PSAT 04202 will be used in calculating TEDE.

I Justification: Configuration 1 from calculation set PSAT 04202 is for a single failure of an inboard main steam isolation valve (MSIV), and configuration 2 is for simultaneous failure of all four third steam line isolation valves (see Exhibits 3 and 4 from reference [4]). From Table 2 of i -

. reference [4], it-is evident that configuration 2 is controlling for dose. Configuration 2 resulted in significant higher WB and thyroid doses, for both EAB and LPZ as well as for control room, than configuration 1. Since TEDE is closely approximated as the sum of WB and a weighting factor times thyroid dose, configuration 2 will also be controlling for TEDE.

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PSAT 0840lT.03' POLESTAR NON-PROPRIETARY Page 5 of10 Rev. 012 3 4 References ,

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

NUREG 1465, February,1995.

2. PSAT 04202U.01," Project QA Plan for Application of the Revised DBA Source Term to the CEI Perry Nuclear Power Plant," March 4,1996. '
3. PSAT 04202U.02," Implementing Procedure for Design Control for Application of the Revised DBA Source Term to the CEI Perry Nuclear Power Plant," March 4,1996.
4. PSAT 04202H.13, "Offsite and Control Room Dose Calculation," June 14,1996.
5. PSAT 04202U.03, " Dose Calculation Data Base for Application of the Revised DBA Source Term to the Perry Nuclear Power Plant," June 14,1996. i
6. PSAT C109.03,"STARDOSE Model Report," January 31,1997.
7. PSAT C109.04, "STARDOSE Programming Report," January 31,1997.
8. PSAT CIO9.05,"STARDOSE Validation Report," March 12,1998.
9. DiNunno, L.L., et al., " Calculation of Distance Factors for Power and Test Reactor Sites",

TID-14844, March 1%2.

10. Code of Federal Regulations, Title 10, Part 20.1003, January 1,1997.

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11. Code of Federal Regulations, Title 10, Part 50.34(a), January 1,1997. J
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13. DRF A41-00054," Fission Product Inventories for Perry High Energy Cycles," Revised March 14,1996.

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15. NUREG/CR-5106, " User's Guide for the TACT 5 Computer Code," June,1988.

I 16. Federal Guide 11, " Limiting Values of Radionuclides Intake and Air Concentration and Dose

- Conversation Factors for Inhalation, Submersion, and Ingestion," 1988.

17. PSAT 04202H.08,"Steamline: Particulate Decontamination Calculation," June 14,1996. I l

PSAT 08401T.03 POLESTAR NON-PROPRIETARY Page 6 of10 Rev. 012 3 4 Calculation Perry Plant Revised DBA Source Term Dose Model As stated in Assumption 1, TEDE is to be calculated. Based on Assumption 2, the dose model used in the STARDOSE code evaluation of TEDE is the same as that used in calculation set PSAT 04202. This dose model had a number of changes from the existing Perry licensing basis dose model. These changes, which are listed in reference [4], are repeated here:

Elimination of the MSIV leakage control system MSIV leak rate increased to 250 scfh total,100 scfh maximum per line Removal of airborne fission products from the drywell Containment spray duration increased to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Retention of fission product leakage in the steam line volume between the reactor vessel and the third isolation valve, or the outboard MSIV, depending upon the configuration (with no holdup credit for the main condenser)

No credit for charcoal filtration of annulus leakage A 30 minute delay in actuation of control room recirculation ESF leakage increased by 50%

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Control room recirculation 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 Configuration Considered Based on Assumption 3, configuration 2 from reference [4] is to be used.

Description of the STARDOSE Input Files See proprietary version I

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PSAT 0840lT.03 POLESTAR NON-PROPRIETARY Page 7 of 10 Rev. 012 3 4 1

i The top of the Attachment I library file states the number ofisotopes (76) and the number of isotope groups (11). There are 18 columns which are as follows:

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1. Isotope Name (e.g.,1131)
2. Isotope Group Name (may be N_ Gas, Org_I, Elm _l, Prt_I, CsGrp, TeGrp, BaGrp, Nmtis, LaGrp, CeGrp, or SrGrp)
3. Name ofParent Isotope or NONE
4. Name ofDaughterIsotope orNONE
5. Initial Core Inventory ofIsotope in Ci/Mw(t)
6. Decay Constantin seca
7. Dose Conversion Factorfor Thyroid Dose in rem /Ci inhaled (not used)
8. Dose Conversion Factorfor External Exposure Whole Body Dose in rem-m3 /Ci-sec
9. Dummy
10. Dummy
11. Dose Conversion Factorfor External Exposure Skin Dose in rem-m 3/Ci-sec (not used)
12. Dose Conversion Factorfor CEDE in rem /Ciinhaled 13-18. Dummy The core inventories (column 5) for all isotopes in this library file are specified as coefficients in the units of curies per mega-watt thermal power and are taken from reference [13]. For the 22 isotopes in reference [5], Item 1.2, these core inventories are the same as that provided in Item 1.2 except for very minor adjustments on some of the isotopes to reflect a revision to reference

[13]. 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 ofreference [5]).

The decay rates and WB DCFs for the 22 isotopes in reference [5], Item 1.2 are taken from Item 1.2. The remaining 44 isotope decay rates are taken from reference [15]. The remaining 44 isotope WB DCFs and the 76 CEDE DCFs are taken from reference [16].

The second STARDOSE input file is the data necessary to calculate fission product transport and, together with the library fib, calculate TEDE. The input file, INPUT.DAT, is contained in Attachment 2, and is annotated by hand to show the correspondence of various sections of the {

file with the input data contained in reference [5] and with some clarifications and additions as i follows:

l e l The additional isotopes which are discussed above

  • The core release fractions (in units of fraction of core inventory per unit time) over the 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period'from 1830 seconds to 7230 seconds (i.e., the fuel release); the 11 STARDOSE l isotope groups are listed above in the description of the Attachment I library file; the release

- fractiods for the first 6 groups are taken from reference [5], and the release fractions for the remaining 5 groups, based on reference [1], are as follows:

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PSAT 08401T.03 POLE' STAR NON-PROPRIETARY Page 8 of 10 Rev. 012 3 4

+ BaGrp: 0.02/1.5 = 0.0133 hf'

+ NMtis: 0.0025/1.5 = 1.677E-3 hf'

+ LaGrp: 0.0002/1.5 = 1.333E-4 hf'

+ CeGrp: 0.0005/1.5 = 3.333E-4 hf'

+ SrGrp: 0.02/1.5 = 0.0133 hf'

. The Pipe 2steamlinel volume which is based on Attachment 1 of reference [17]

e The control room recirculation tilter efficiency for elemental and organic iodine which is 50% according to the assumption documented in reference [4] and repeated above

. The filter efficiency of the junction downstream of Pipe 2steamlinel which is obtained fram a weighted average of the Case 2 (100 scfh) and Case 4 (50 scfh) efficiencies of Table 2.b of reference [17]

e The filter efficiency of thejunction downstream of Steamlinel which is obtained from a weighted average of the Case 3 (100 scfh) and Case 5 (50 scfh) efficiencies of Table 2.a of reference [17]

e The filter efficiency of the junction downstream of Steamline2 which is equal to the Case 1 efficiencies of Table 2.a of reference [17]

. The containment bypass leakage (i.e., sprayed and unsprayed containment leakage to environment) was increased by 50% per assumption documented in reference [4] and I repeated above The input file also specifies the edit times (the first four lines of the file) for the code output. .

These edits are used to compute the two hour TEDE as a function of time. This is because the .

TEDE requirement for advanced plants (and the requirement that is expected for operating plants) specifies that the dose over the maximum two hour interval be calculated. This maximum two hour interval calculation was performed as follows:

D, = cumulative dose up to time ti hours Da2 = cumulative dose up to time ti + 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Max 2 hr TEDE = maxi (Da2- D) i The results of this calculation have been plotted vs time, to the nearest 0.1 hr of the beginning of the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> interval, to show the interval with maximum dose.

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Results i

j. Selected portions of the STARDOSE output are included as Attachment 3, and the TEDE results I

are summarized in the table below for EAB (maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose), LPZ (30 day), and control room (30 day). Detailed output is provided in Attachment 4. The TEDE results are for the STARDOSEruh identified as 1:00:45 PM April 11,1998. TEDE is the sum of CEDE for the 10  ;

non-noble gas isotope groups plus the WB dose due to the plume._

Figure 1 is a plot of the two hour interval EAB dose vs. time of start of the interval. As is evident from the figure, the maximum TEDE interval for the EAB is 1.1 to 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

PSAT 0840lT.03 POLESTAR NON-PROPRIETARY Page 9 of 10 Rev. 012 3 4 EAB dose is included in the table for perspective. In the case of the control room, the WB dose includes the 30 day contribution from plume inside the control room (calculated as 0.12 rem from STARDOSE), the 30 day contribution from containment direct gamma (0.13 per reference

[4]), and the 30 day contribution from cloud direct gamma (0.002 per reference [4)).

CEDE (rem) WB (rem) TEDE (rem)

EAB (0 to 2 hr) 7.47 1.95 9.4

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l EAB (max 2 hr) 12.1 3.7 15.8 i LPZ (30 day) 6.43 1.82 8.3 Control Room (30 day) 0.78 0.25 1.0 A breakdown of the CEDE by isotope group for the EAB, LPZ, and control room is as follows:

EAB LPZ CR CEDE due to inhalation of organic iodide 0.12 .23 .05 CEDE due to inhalation of elemental iodine 1.44 .60 .11 CEDE due to inhalation of particulate iodine 6.5 3.41 .38 CEDE due to inhalation of cesium / rubidium 2.3 1.23 .13 CEDE due to inhalation of tellurium / antimony 0.35 .12 .013 CEDE due to inhalation of barium 0.06 .03 .003 CEDE due to inhalation of noble metals 0.37 .22 .02 CEDE due to inhalation oflanthanum group 0.1 .12 .02 CEDE due to inhalation cerium group 0.46 .28 .03 CEDE due to inhalation of strontium 0.31 .18 .019 Whole body due to plume 3.73 1.82 .12 CR WB due to cloud direct gamma - -

.002 CR WB due to containment direct gamma - -

13 TEDFs 15.76 8.3 1.03 Conclusions The dose analysis contained in this report demonstrates that the Perry Plant radiological DBA revised source term TEDE is below the limits discussed in Assumption 1. The EAB maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose for the Perry Plant is 15.8 rem TEDE. The maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> exposure interval is 1.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (This EAB maximum 2 hr TEDE is a 68% increase over the 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> TEDE.) The LPZ 30' day dose is 8.3 rem TEDE. The control room 30 day dose is 1.0 rem TEDE.

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PSAT 08401T.03 Page 10 of 10 l l Rev6)12 3 4 Figure 1 Two Hr TEDE vs. Time of Start of Two Hr Inteval 17 i 16 -

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0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 1.3 1.4 1.5 Time of start of two hour exposure interval (hr)

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