ML20211H302

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Rev 2 to CR Dose for MSLB Accident
ML20211H302
Person / Time
Site: Byron  Constellation icon.png
Issue date: 09/30/1997
From: Launi C
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20211H271 List:
References
CON-9044-057, CON-9044-57 BYR97-332, BYR97-332-R02, BYR97-332-R2, NUDOCS 9710060319
Download: ML20211H302 (14)
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Exhibit C NEP 12-02 Revision 5 4

CALCULATION TITLE PAGE Page No.1 i

1 Calculation No: __BYR97 332 4 Project No.: 9044-057 Description Code: R02

Discipline Code: M BYRON STATION UNIT (S) 1&2 System Code: VC.Ms i

TrrLE: Control Room Dose for MSLB Accident X Safety Related Augmented Quality Non-Safety Related

REFERENCE NUMBERS Type Number Type Number DCP 9500394 COMPONENT EPN
DOCUMENT NUMBERS:

EPN Compt Type Doc Type /Sub Type Docmnent Number REMARKS:

REVISING APPROVED REV NO.

ORGAMMION PRINT / SIGN DATE O SBIL C.M. Launi/(See original for signature) 8/22/97 i S&L C.M. Launi/(See original for signature) 9/22/97 2 S&L C.M. Launi/ h//[Mg ' -

q 30-97

- tv 1

Exhibit C NEP 12-02 Revision 5 COMMONWEALTII EDISON COMPANY CALCULATION REVISION PAGE CALCULATION NO. BYR97 332 PROJECT NO. 9044-057 PAGE NO.: 2 REVISION SUMMARIES REV: 0 REVISION

SUMMARY

Originalissue, page I through 7, Al, A2, Bl Cl Electronic Calculation Data Files:

(Program Name, Vmion. File name en%iza/date.hourl: min)

None i

l Prepared by: W. L Johnson /(see oricinal for sienature) 8/22/97 Print / Sign Date Reviewed by: B. C. Schwartz /(see oricinal for sign.1ture) 8/22/97 Print / Sign Date Type of Review

[ X] Detailed [ ] Alternate [ ] Test DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION [ ] YES [ X ] NO Tracked by:

REV: 1 REVISION

SUMMARY

This calculation was updated to reflect changes in calculation ATD-410 and to make the control room dose comparison based on eight hour releases Electronic Calculation Data Files:

(Prognm Name, veien, File name en'aize'datehourl: min)

None Prepared by: W.1 Johnson /(See orieinal for signature) 9/22/97 Print / Sign Date Reviewed by: R. G. Chow /(See oricinal for sicnature) 9/22/97 Print / Sign Date Type of Review

[ X 1 Detailed [ ] Alternate [ ] Test DO ANY ASSUMFr!ONS IN THIS CALCULATION REQUIRE LATER VERIFICATION [ ] YES [ X ] NO Tracked by:

a l

Exhibit D NEP.12-02 Revision 5 COMMONWEALTH EDISON COMPANY

. CALCULATION REVISION PAGE CALCULATION NO. BYR97 332 PROJECT NO. 9044-057 PAGE NO.: 2.1 RF. VISION SUMMARIES REV: 2 REVISION

SUMMARY

l This calculation was updated to reflect a new revision of calculation ATD 410 and to clarify references and labels.

l

. Electronic Calculation Data Files:

(Program Name, Venian, File name enWe/date%urh min)

None Prepared by: W. J. Johnson / -

d', ,-

w 9/Io,lo.'7 Pri Si ate Reviewed by: R. G. Chow < 9D 9 r < '

v i Print / Sign Date Type of Review

[ X1 Detailed [ ] Alternate [ ] Test DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION [ ] YES [ X ] NO Tracked by:

l.

REV:

REVISION SUMhMRY:

Electronic Calculation Data Files:

(Program Name, Version, File name eu' size'datekurh min)

Prepared by:

Print / Sign Date Reviewed by:

Print / Sign Date Type of Review

[ ] Detailed [ ] Alternate [ ] Test _

DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION ! ] YES [ ] NO Tracked by-

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

Exhibit D NEP-12-02 Revision 5 COMMONWEALTE EDISON COMPANY CALCULATION TABLE OF CONTENTS PROJECT NO. 9044-057 CALCULATION NO. BYR97-332 REV. NO. 2 PAGE NO. 3 SECTION PAGE NO.

SUB-PAGE NO.

tilLE PAGE /

REVISION

SUMMARY

  1. 2*l TABLE OF CONTENTS y DURPOSE/ OBJECTIVE 4 l

METHODOLOGY AND ACCEPTANCE CRITERIA '

ASSUMPTIONS 4 DESIGN INPUT #

4 REFERENCES CALCULATIONS 5

SUMMARY

AND CONCLUSIONS 8

ATTACHMENTS A UFSARTable 6.4.1 jj,jy B UFSAR Figure 7.2-1 B1 C UFSAR Table 15.6.9 gj m

Exhibit E NEP 12-02 Revision 5 COMMONWEALTH EDISON COMPANY l CALCULATION NO. : BYR97 332 PROJECT NO. 9044-057 PAGE NO. 4 l PURPOSE / OBJECTIVE:

The purpose of this calculation is to assess the post accident radiological dose to control room occupants following a main steam line break (MSLB) accompanied by primary-to-secondary coolant leakage.

METHODOLOGY AND ACCEPTANCE CRITERIA:

The approach is to demonstrate that the consequences of the MSLB accident will be less than the design basis loss of coolant accident (LOCA) assessment and are, therefore, bounded by the rsessment included in the Updated Final Safety Analysis Report (UFSAR).

ASSUMPTIONS:

1 The control room ventilation is assumed to be in operation following the MSLB. The basis for this assumption is discussed in CALCULATIONS section.

DESIGN INPUT:

The iodine releases and the maximum acceptable steam generator leak rates are from caletdation ATD-0410, Rev. 4 (Reference 1). The releases from the containment and the resulting control room l dose are from the UFSAR (References 3 and 7).

REFERENCES:

. 1. Comed Calculation ATD-0410, Rev. 4," Allowable Leakrate Calculation for Steam Generator Interim Plugging Criteria," September 30,1997,

2. USNRC, Standard Review Plan, NUREG-0800, Section 15.6.3, " Radiological Consequences of Steam Generator Tube Failure (PWR),"Section II, Acceptance Criteria, Rev. 2, July 1981.
3. Byron UFSAR, Table 15.6-9 (copy attached)
4. USAEC Technical Ir'ormation Document TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites, March 1962.
5. Sargent & Lundy Calculation BY-VC-07, Rev. O, " Radiation Habitability for the Control Room -

Byron," October 3,1985.

6. Byron UFSAR, Figure 7.2-1 (Sheet 8)(copy attached)
7. Byron UFSAR, Table 6.4-1 (copy attached) l REVISION NO.: 2 l

Exhibit D NEPol2 02 Revision 5 COMMONWEALTII EDISON COMPANY l CALCULATION NO. : BYR97 332 PROJECT NO. 9044-057 PAGE NO. 5 l

8. Federal Guidance Report 11," Limiting Values of Radionuclide Intake and Air Concentration and Dose conversi on Factors for Inhalation, Submersion, and Ingestion, " 1988 CALCULATIONS:

Comparison ofReleases:

In order to determine control room doses for the MSLB case from doses calculated for the LOCA case, the radionuclide releases in each case must first be identified. Since the thyroid dose is the governing limit, releases of radioactive iodines will be compared.

  • MSLB Release Reference I considers three release sources:
a. Primary coolant with a pre-accident iodine spike
b. Primary coolant with a post-accident iodine spike
c. Secondary coolant with iodine concentrations at a predetermmed limit Reference 1, then, evaluates these to obtain a limiting primary to secoadary leak rate as follows. For a one gallon per minute primary to secondary leak, we have for the first two hours after the start of the accident:

Dose Equivalent Exclusion Area Source I 131 Release Boundary Dose a 15.9 Ci 3.40 rem b 10.6 Ci 2.25 rem c 5.20 Ci 1.11 rem NRC acceptance criteria considers the following combinations of sources and acceptance criteria:

I l REVISION NO.: 2 l

1

- Exhibit D NEP 12-02 Revision 5 COMMONWEALTH EDISON COMPANY

- l CALCULATION NO. : BYR97-332 PROJECT NO. 9044-057 PAGE NO. - 6 l Source Acceptable Dose Basis, Reference 2 at EAB a+c 300 rem 10CFR100 limit b+c 30 rem 10% of10CFR100 limit Using this criteria, Reference 1 calculates a limiting primary to secondary leak rate of 12.8 gallons per minute (Scenario b+c).

For the period 2-8 hours after the accident, the weighted activity released (E RiDCF) i due to a 12.8 gallons per minute primary to secondary leak rate can be calculated from the information from Tables 2.f.2 and 3.f.2 in Reference 1 as indicated below.

Weighted ActivityReleased I-131 Dose Conversion DE I-131 Source I Ri DCFi(rem) Factor (rem /Ci) Released (Reference 1) (Reference 8) (Ci) a 9.06E+8 1.08E+6 839 b 1.10E+9 1.08E+6 1019 Using this leak rate, the iodine releases for the different sources are as follows:

I Source Dose Equivalent I-131 Release a 12.8 x 15.9 + 839 = 1043 Ci b 12.8 x 10.6 + 1019 = 1155 Ci c 5.2 Ci Under these conditions, the worst case combination of(a+c) or (b+c) is (b+c), which results in an eight hour release of 1160 curies ofdose equivalent I-131.

-

The releases of radioactive iodines in the design LOCA case are given in Reference 3. These may be converted to dose equivalent I-131. In order to compare fairly with the control room dose assessment (because oflong term X/Q and other parameter variatiora), consider only the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of release (where all control room habitability parameters are constant).

l REVISION NO.: 2 j

b-Eahibit D l NEP-12-02 Revisloa 5 l COMMONWEALTH EDISON COMPANY j l CALCULATION NO. : BYR97 332 - PROJECT NO. 9044-057 - PAGE NO. 7 l' i~

j Release, Curies Rem per Curie Weighted Activity c 0-2 hr 2-8 Total Dose Conversion Release  !

hr Factor Total X DCFi ,

j- (Reference 4) (rem) l' I 131 214 545 759 1.48E6 ,

1.12 E9

-I-132 257 217 474 5.35E4 2.54E7 I.

I-133 -469 -1060 1529 4.00E5 6.12E8 i' I-134 320 62 382 2.50E4

~

9.56E6 I-135 401 684 1085 1.24E5 1.35E8 -

i Sum 1.90E9 i

I: The total dose equivalent I-131 release is then 1.90E9/1.48E6 or 1290 curies. Note that these are -

!- ICRP-2 dose conversion factors rather than the ICRP-30 dose conversion factors used for the

[ MSLB dose calculation. This is done to be consistent with the LOCA control room dose, which also

uses ICRP-2 dose conversion factors.

Evaluation of Control Room Ventilation Sysem Configuration-L .

F De proposed control room dose estiniation is valid only if the control room emergency filtration system (VC

- system) is in operation.' The VC system is n=M to be in operation for the LOCA assessment (Reference 5). A i review of applicable fuhl diagrams (Reference 6) shows that, in the event of a low steam line pressure, the r
' VC system is activated. 'Ihis assures that the proposed dose estimation is valid.

E=*im ^a of Control Room Dose:

i Reference 7 gives the' control room dose calculated for a LOCA. 'Ihe total 30 day dose is18.20 rem thyroid. ' Ibis

~1-1=+ian is h==ted in Reference 5. From intermediate results included in Reference 5, one can obtain the

cumulative dose for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in the LOCA case is 8.27 rem. His would be the resulting dose from the i _l,290 curies of dose equivalent I-131 released in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> as noted above 'A normalized dose for this penod caa be al~1=+H as

i 8.27 rem /1290 Ci = 6.41E 3 rem /Ci dose equivalent I-131

[ L Using the above LOCA resuhs, then, one can say that, all other things being equal, the control room dose for the MSLB is in proportional to the radioiodine release and would be:

? - 1160 Ci x 6,41E-3 rem /Ci = 7.4 rem J; -

I k

= l REVISION NO.: = 2 l f

Exhibit D NEP-12-02 Revision 5 COMMONWEALTH EDISON COMPANY ICALCULATION NO. BYR97 332 PROJECT NO. 9044-057 PAGE NO. 8 l 4

Since the ICRP-30 dose comersion factors are smaller than the ICRP-2 dose comersion factors, use of the normalized dose based on ICRP-2 is conservatin.

SUMMARY

AND CONCLUSION:

ne 0-8 hour 7.4 rem post-accident control room dose due to the MSLB accident is less than the 0-8 hour 8.27 rem due to the design basis LOCA.

FINAL I

l REVISION NO.: 2

l orpop-arsAR - .

TABL" -1 garag:IEn_sosE m - -y w- - F--- - ar ---

miarIgg EDE4GHIEi_&_laliE:QE:Ep24ELACCIDEELIIaral ra rerTE sWIELD ACD4EKATER_3R_D6Y DoSL_855 -

TMICENESS SE115EEN ~

SOURCE AND CONTROL y S and y Room. InggEs yuotz aoor _sgIg__

IgrygIn Direct Dose From Airborne Radio-activity in the Contaipment -

SidewgII- - 102 0.024 -- --

Ceiling -

50 pose from Post;-14CA Plume Eurroundipg~Coptrol Room 2d q.003 -

Dose Fror: Radioactivity Accumu-

  • lated on Control Room Makeup Air -

Filters 8 0.011 - -

Dose From Air Draeny into the Control Room From Containment Leakage M/A 2.17 23.38 From ESF Equipmept Leakage 18.20 N/A 1.00x10-5 -.65x10-5 *g,374 g { ,,

- - t7

~~

g 10 CFR 50, Appendix A, Criterion 19 limits g.

5 30 18 y gote:

Pripcipal assumptions are. listed IP Tab 37 f-1-la- k A

p.4-17

4 4 i

Cele No. BYR97 332, Rev. 2 BYisON-UFSAR Page A 2 (FINAL) 4

'l TABLE 6.4-la

, PRINCIPAL AERUMPTIONk UErp IN CONTROL RDOM

{

MARITABILITY CALCULATIONS j Core thermal power 3565 MW(t)

' Containment volumet sprayed volume 1.55 x 106 ft3 unspreyed volume 2.130 x;105 ft3 i

Flow rate, sprayed to unsprayed volume 1.80 x 105 ft /3 min Containment spray coefficientst '

i elemental iodine 29.9/hr particulate and organic iodine 0 containment

  • leak rate o-24 hr 0.1%/ day I 1-30 day 0.05%/ day ECCS leak rate 1. gal /hr.
Auxiliary b1dg filter efficiency 90%

Control room habitability methodology:

, Nurphy/Campe 13th air cleaning conference paper Single inlet configuration is assumed at a distance of 100 feet from the contair. ment surf ace.

X/Q (maximum 0-8 hour) in a-direction 94' gast of North from the Unit 2 containment = 4.05 x.10-3 sec/m3 -

v/O D1mucTION FACTOR

' WIND TOTAL X/Q WINDSPEED FACTOR OCCUPANCY REDUCTION TIME PERIOD FACTOR DIRECTIDM E TOR __ FACTOR i 0-8 hr 1.0 1.0 1.0 1.0 8-24 hr 0.549 0.856 1.0 0.470 24-96 hr 0.331 0.712 0.6 0.141 96-720 hr 0.199 0.424- 0.4 0.034

e. Control room HVAC envelope volume 405,164 ft 3' Actual control room volume used for finite cloud correction 230,837 ft3*
  • Control room air intake filter efficiency 99%

Control room recirc. filter efficiency 90%

Control room flow rates (see Figures 6.4-6 and 6.4-7)

Total unfiltered inleakage rate into the control room pressure boundary 78.75 ft 3/ min. ,

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TABLE 15.6-9 SCTIYITE REI2ASES 10 m FMME IASS OF (IMEAET ACCIM (Realistic Analysis Activity Release (Ci)). ,

IEDIQFE p-2 M 2-3 M A-24 M 1-4 MYS 4-30 MYS ,

I-131 6.21 (-5) 1.58 (-4) 4.06 (-4) 3.31-(-4) 1.19 (-3) 1-132 1.82 (-4) 1.54 (-4) 3.08 (-5) 6.71-(-8) 3.47 (-17) 1-133 1.58 (-4) 3.56 (-4) 6.66 (-4) 2.16-(-4) 2.20 (-5) 1-134 1.66 (-5) 3.24 (-6) 2.82 (-3) 2.21 (-4) 3.se (-39) 1-135 1.07 (-4) 1.84 (-4) 1.74 (-4) 1.03 (-5) 6.21 (-9)'

Xe-133 1.63 (-2) 4.77 (-2) 1.2e (-1) 1.07 (-1) 2.13 (-1)

Xe-1339 '1.86 (-3) 5.28 (-3) 1.22 (-2) 8.18 (-3) 5.35 (-3)

Ke-135 2.56 (-3) 6.38 (-3) 7.81 (-3) 8.28 (-4) 3.62 (-6)

Ke-135m 2.66 (-5) 1.29 (-7) 1.45 (-14) 1.06 (-33) NEGLIGIBLE Xe-138 9.86 (-5) 7.40 (-7) 3.05 (-13) 7.22 (-31) NEGLIGISLE Kr-85 7.58 (-3) 2.27 (-2) 6.06 (-2) 6.51-(-2) 5.88 (-1)

Kr-sse s.24 (-4) 1.3s (-3) 7.9s (-4) 1.70 (-5) 1.s1 (-10)

Kr-s7 3.71 (-4) 1.so (-4)_ 7.o1 (-6) 2.77 (-le) 2.1s (-27)

Kr-58 1.48 (-3) 1.78 (-3) 5.01 (-4) 2.34 (-6) 3.56 (-14)

(Regulatory Guide 1.4 Analysis Activity Re* sse (Ci))

I-131 2.14 (+2) 5.45 (+2) 1.40 (+3) 2.69 (t3) 8.12 (+3) _{ap ~-

I-132 2.57 (t2) 2.17 (+2) 4.35 (tl) 1.39 (+1) . WeGLIGIBLE I-133 4.69 (+2) 1.06 (+3) 1.98 (+3) 1.21 (+3)- 1.30'(+2) 2]E I-134 3.20 (+2) 6.22 (+1) 5.42 (+1) MSGLIGIBLE NSGLIGIBLE

~

I-135 4.01 (+2) 6.84 (t2) 6.46'(+2) 7.6s'(+1) 4.60'(-2) gWzy [

Xe-133 Df Ze-133a 1.69 ( 4 4.26 (+9 1 91 (94) 2 )) 1.21 (+3) 1.24 ( 2.21 (tS) 4 48 (t5) *

"y 2.81 (+t5)

3) 3.72 (+3). 2.45 (+3) -

Xe-135' 4.27 (+3) 9.53 (+3) 1.17 (44) '2.47 (43) 1.08 (+1) [

15.6-41 l --

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