Text

Fuel Handling Accident Inside Containment CR & Offsite Doses
	ML20078F576
Person / Time
Site:	San Onofre
Issue date:	03/14/1994
From:	Nakano R, Remick T; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20078F543	List: ML20078F541; ML20078F557; ML20078F576;
References
	N-4072-003, N-4072-3, NUDOCS 9502020161
	Download: ML20078F576 (89)
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l 1 To sesolve ODts 92 019,92470 and 92 071 which state that data given la Revision 0 of this calculatice is inconsissent with design data. ' Ibis analysis will supersede Revision O.

2 Phges added - curristly ainnbered pages 1 tiuough 89

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NES&L DEPARTMENT

. CALCULATION SHEET ICCN No/

PRELIM. CCN No. PAGE_ oF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CoNVER$ ton:

CCN No. CCN -

. Subject Fuel Handfino Accident (FHA) InsMe Containment . Control Room and Offsite Doses Sheet No. 4 MV ORIGNAToR DATE flE DATE REV ORIGNAToR DATE WlE DATE R j E

1 R. Nakano 02 24 94 T. Remick 02 28 94 y 4

4 TABLE OF CONTENTS Section Description Ents CALCULATION COVER SHEET ....................... 1 Calf ULATION CROSS INDEX . . . . . . . . . . . . . . . . . . . . . . . . 2 F

TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1.0 PURPOSE ....................................... 6 1.1 Task Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 1.2 Criteria, Codes and Standards . . . . . . . . . . . . . . . . . . . . . . . 6 2.0 RESULTS/ CONCLUSIONS AND RECOMMENDATIONS ........ 8 2.1 Results/ Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 2.2 Recommendations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 3.0 ASS UMPTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 3.1 Reactor Shutdown Time . . . . . . . . . . . . . . . . . . . . . . . . . 10 3.2 Containment Dome Air Circulators ..................10 3.3 Containment Purge Isolation Valve Closure Time . . . . . . . . . . 10 3.4 Concrete Shielding Density . . . . . . . . . . . . . . . . . . . . . . . 10 3.5 Air Density For Shielding . . . . . . . . . . . . . . . . . . . . . . . . 11 3.6 Daughter Product Isotopes . . . . . . . . . . . . . . . . . . . . . . ; . 11 3.7 Control Room Emergency Filtration Damper Stroke Times . . . . 12 3.8 Unfiltered Control Room inkakage ..................12 3.9 Configuration Symmetry Between Units . . . . . . . . . . . . . . . . 12 3.10 Release Duration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.11 Number of Failed Fuel Pins . . . . . . . . . . . . . . . . . . . . . . . 12 !

4.0 DESIGN INPUTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4.1 Fuel Handling Accident Activity Release Characteristics ...... 13 4.2 Refueling Water Clean-up of Isotopes . . . . . . . . . . . . . . . . . 14 4.3 Containment Characteristics . . . . . . . . . . . . . . . . . . . . . . . 14 4.4 Control Room Characteristics . . . . . . . . . . . . . . . . . . .... 16 4.5 Number of Fuel Rods Per Fuel Assembly ..............21 4.6 Occupancy Factors ............................21 i 4.7 Breathing Rates ..............................21 l 4.8 . Atmospheric Dispersion Factors ....................22 4.9 Dose Conversion Factors . . . . . . . . . . . . . . . . . . . . . . . . . 23 4.10 SOURCE 2 Code Source Strength Spectrum Energy Structure ... 23 l

l

NES8d. DEPARTMENT CALCULATION SHEET 'cc"

rREuu. eCN No. raoE_ or_

Preiset or DCPAIMP SONGS 2&2 Calc. No. N-4072-003 CCN CONVERSloN:

CCN No. CCN -

Subioet Fuel Handlina Accident FHA) Inside Containment . Control Room and Offsite th=== Sheet No. 5 IEV ONGMaTOR DaTE N DaTE IWV ONGedaTOR DaTE 5tf DaTE R E

1 R. Nakano 02 24 94 T. Remick 02-28-94 y 4

5.0 METHODOLOGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 5.1 General Methodology . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 i 5.2 Computer Code Descriptions . . . . . . . . . . . . . . . . . . . . . . 26 5.3 EAB and LPZ and Control Room Inside Cloud Doses . . . . . . . 27 5.4 Control Room Outside Cloud Shine Doses . . . . . . . . . . . . . . 30 5.5 Control Room Filter Shine Doses ...................30 5.6 Containment Direct Shine Doses . . . . . . . . . . . . . . . . . . . . 31

6.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 7.0 NOMENCLATURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. 36 8.0 COMPUTATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 8.1 Refueling Wa.ter Iodine Removal . . . . . . . . . . . . . . . . . . . . 37 8.2 Control Room Intake and Recirculation Effi&Mn . . . . . . . . 37 8.3 CR Rae. tion Monitor Trip Initiation Time . . . . . . . . . . . . . . 38 ;

8.4 Control Room Isolation Tune . . . . . . . . . . . . . . . . . . . . . . 39 8.5 LOCADOSE Code Tune Steps . . . . . . . . . . . . . . . . . . . . . 40 i 8.6 CR HVAC Intake Filter Direct Flowrate From Containment . . . 40 8.7 Integrated Activity Release .......................41 8.8 SOURCE-2 Code Multiplier For Outside Cloud Dose . . . . . . . 42 8.9 SOURCE.2 Code Multiplier For CR HVAC Filter Shine Dose .. 43 8.10 SHIELD SG Model For Outside Cloud Dose ............43 8.11 CR HVAC Filter Shine Dose . . . . . . . . . . . . . . . . . . . . . . 48 8.12 Doses Due to Release From One Pin . . . . . . . . . . . . . . . . . 50 8.13 Design Basis Case Doses . . . . . . . . . . . . . . . . . . . . . . . . . 52 R0 COMPUTER PROGRAM INPUT AND OUTPUT FILES . . . . . . . . . 53 9.1 Files Created During 'Ihis Analysis . . . . . . . . . . . . . . . . . . 53 9.2 LOCADOSE Code Input Files . . . . . . . . . . . . . . . . . . . . . 54 9.3 SOURCE 2 Code Input Files . . . . . . . . . . . . . . . . . . . . . . . 58 9.4 SHIELD-SG Code Input Files . . . . . . . . . . . . . . . . . . . . . . 60 9.5 LOCADOSE Code Output Files . . . . . . . . . . . . . . . . . . . . 64 9.6 SOURCE 2 Code Output File . . . . . . . . . . . . . . . . . . . . . . 76 9.7 SHIELD SG Code Output File . . . . . . . . . . . . . . . . . . . . . 79 10.0 COPIES OF MISCELLANEOUS REFERENCES . . . . . . . . . . . . . . 83

NES&L DEPARTMENT I CALCULATION SHEET ICCN W PREUM. CCN No. PAGE_ oF_ l Reject or DCP/MMP SONGS 28:3 Calc. No. N 4072-003 CcN CotNERsioN:

cCN No. CCN - l

. Subject Fuel Handlino Accident (FHA) Inside Containment - Control Room and Offsite Daa== Sheet No. 6 ;

REW omosuToR DaTE IRE DaTE REV oM0fuToR DaTE plE DaTE R l 1 R. Nakano 02 24 94 T. Remick 02-28-94 h 4

l 1.0 PURPOSE 1.1 Task Description i Dis revision will determine the control room and offsite doses due to a design basis fuel handling accident inside the containmer,t building. Revision 0 of the calculation modeled '

a containment building purge isolation valve response time of 0 acconds, which caused i containment isolation completely before radioactivity was released to the eavironment, and therefore elimina'ad the need to calculate control room and offsite doses.

The design basis FHA in Containment is being revised to resolve concerns identified in the following Open Item Reports:

92-019 Revision 0 to this Calculation does not account for two containment exhaust ducts that may give a higher flow rate from the containment and therefore the containment isolation time may be greater than that calculated. :

92-070 Revision 0 to this Calculation does not justify the assumption that an isolation of the containment purge will occur on a high radiation signal !92-071 UFSAR Section 15.7.3.4 incorrectly reported the results of Revision 0. !

1.2 Criteria, Codes and Standards The control room operator dose criteria governing a fuel handling accident (FHA) event !

are defined in the General resign Criteria of Appendix A to 10 CFR 50 (Reference 6.4.g). Genern Design Criterion 19 states that the control room personnel must be able to occupy the control room during accident conditions without receiving ,

radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the !

body, for the duration of the accident.

]

Seedon H 6 of Standard Review Plan 6.4 (Reference 6.4.d), clarifies the dose guidelines for evaluating the protection afforded by the control room by indicating that the dose to the control room personnel during the entire period of the postulated accident should not exceed:

Control Room (accident duration dose): Whole body gamma dose of 5 rem Dyroid dose of 30 rem Beta skin dose of 30 rem

NES&L DEPARTMENT

' ' CALCULATION SHEET ICCN No./

PRELIM. CcN No. PAGE_ OF_

Project or DCP/MMP SONGS 2&3 Calc. No. N 4072 003 CCN CONVERSloN:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) Inside Containment Control Room and OEsite Doses Sheet No. 7 MV ORIGNAToR DATE flE DATE HEV oR10NAToR DATE NIE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h 4

The offsite dose criteria governing a FHA event are dermed in 10 CFR 100 (Reference 6.4.h). Per Section H.1 of Standard Review Plan 15.7.4 (Reference 6.4.e),

the plant site and the dose mitigating engineered safety features are acceptable with respect to the radiological consequences of a postulated FHA if the calculated whole-body and thyroid doses at the exclusion area boundary and at the low population zone are well within the 10 CFR 100, Section 100.11 exposure guidelines. SRP 15.7.4 dermes "well within" as meaning 25 percent or less of the 10 CFR 100 exposure guidelines as follows:

x posure guidelines of 10 CFR 100, Section 100.11(a)(1), the dose at the Per the e~

exclusion area boundary is for the two hours immediately following onset of the postu ated accident. Therefore, the EAB dose should not exceed:

EAB (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months dose): Whole body gamma dose of 6 rem Thyroid dose of 75 rem Per the exposure guidelines of 10 CFR 100, Section 100.11(a)(2), the dose at the outer boundary of the low population zone is for the entire period of the postulated accident.

'Iberefore, the LPZ dose should not exceed:

LPZ (accident duration dose): Whole body gamma dose of 6 rem Thyroid dose of 75 rem

NES&L DEPARTMEhT CALCULATION SHEET 'cc=

l PREUM. CCN No. PAGE_ oF_

Project or DCP/MMP SONGS 2&S Calc. No N 4072-003 CcN CoNVERsloN:

CCN No. CCN -

. Subject Fuel Handlina Accident FHA) Inside Cont.;saent - Control Room and Offsite Doses Sheet No. 8 REV onlG5dAToR DATE WIE DATE REV oNGedAToR DATE WlE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h 4

2.0 RESULTS/ CONCLUSIONS AND RECOMMENDATIONS 2.1 Results/ Conclusions Based on the criteria presented in Section 1.2 and the calculations presented in Computation Section 8. Table 2.1-1 presents the Control Room, EAB and LPZ doses following a design basis fuel handling accident inside containment. 'Ihe design basis case ,

is the failure of 236 fuel pins with a Control Room Isolation at 3 minutes after the start of l the accident.

'Ihe following conclusions were made from the results presented in Table 21 .-1 and Section 8.13.

l e When the CR is isolated at 3 minutes, all the doses meet the criteria listed in Section 1.2 (see Table 2.1-1).

e *Ihe CR isolation on high radiation is required to meet General Design Criterion 19 Appendix A to 10 CFR 50 (Refemnce 6.4.g) (see Section 8.12.2).

Table 2.1 1 Design Basis Cases Control Room Isolates at High Radiation Signal Location Criteria Dose (Rem)

CR:

D yroid 30 19.5 Beta Skin 30 13.5 Whole Body 5 0.2 EAB:

Dyroid 75 72.7 Beta Skin NA 1.2 Whole Body 6 C.a 11Z:

D yroid 75 2.1 Beta Skin NA <0.1 Whole Body 6 <0.1 i

w- -

-,,-ew- - ~

NES&L DEPARTMENT CALCULATION SHEET &c"CCN

,u No. Aor_ or_

Project or DCP/MMP SONGS 2&3 Calc. No. N.4072-003 CCN CONVERSION:

CCN NO:CCN -

. Subject Fuel Handlino Accident (FHA) In_ aide Containment - Control Room and Offsite Doses Sheet No.1 REV ORNMNATOR DATE ME DATE REV OfuCINATOR DATA utE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h

4 2.2 Recommendations

1. 'Ihis analysis no longer credits the high radiation isolation of the Containment Purge System for offsite radiological doses. However, there may be other commitments requiring high radiation isolation of the enntniament. Therefore, the Technical Specifications related for the Containment Purge Isolation System should be reviewed to dete:mine if changes are necessary.

2. This analysis credits a 3 minute isolation time for the Control Room. A review should be performed to determine if a Technical Specification response time should be established for the Control Room isolation time.

3. The LOCADOSE whole body immersion Dose Conversion Factors used in this analysis differ slightly from those listed in UFSAR Appendix 15.B Table 15.B-6.

Due to the fact that several analyses have been perfonned with the LOCADOSE DCFs, Table 15.B-6 should be updated with the actual DCFs used.

CALCULATION SHEET 'cc" '*

PRELIM. ccN No.

'T l l PAGE_ oF_

Prefect or DCP/MMP BONGS 2ais Cole. No. N-4072 003 CcN CoNVERstoN:

CcN No'. CCN -

e Sulifect Fuel Ham % Aaamnit (FHA) Iraw containment - Control Room and Offsite D===s Sheet No._1g_

MW ofuGNaToR DATE WIE DATE MV oRIGNAToR DATE flE DATE R 1 R. Nakano 02 24-94 T. Remick 02 28 94 h 4

3.0 ASSUMFFIONS 3.1 Reactor Shutdown Thne It is assumed that the reactor has been suberitical for at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to movement ofirradiated fuel in the reactor pressure vessel. 'Ihis shutdown time is based on the Units 2 and 3 Technical Specification 140 3.9.3 (References 6.3.a & b). Regulatory !

Guide 1.25 states that the accident will be assumed to occur at a time after shutdown !

identified by the Technical Speincadons as the earliest time fuel handling operations may begin.

3.2 Containment Dome Air Circulators Tachniemi Specification 140s 3.6.2.3 and 3.6.4.3 (References 6.3.a & b) state that the Contsiament Cooling Fans should be operable in MODES 1, 2, 3 and 4 and the Containment Dome Circulators should be operable in for MODES I and 2. Since there is no 'IS requirement to have any air circulation units operable in MODE 6 (Refueling), it is maanmed that the units will not be operating during the FHA.

Because there is no air circulation in the containment, this analysis does not take credit for activity dilution within the air of the containment dome space for the calculation of control room and offsite doses. A smaller dilution volume would yield a higher containment activity concentration which would in turn yield higher and therefore, conservative offsite and control room doses.

3.3 Containment Purge Isolation Valve Cicoure ilme In this calculation it is nasumed that the containmant purge valve closure time is infinite.

. Consequently, credit is not taken for Containment Purge Isolation Signal [CPIS) actions, and therefore it is not neceaanry to model any instrument delays or uncertainties. This assumption is conservative because it mari=I=1 the activity released to the environment.

3.4 Concrete Shielding Density The dose consequences in the Control Room are mitigated by radiation shielding provided by the concrete walls, flooring and ceiling of the Auxiliary Building. These concrete barriers are assumed to be constructed of ordinary concrete. Per Section 4 of l

tiy -

-y

NES&L DEPARTMENT i CALCULATION SHEET 'CCN No./

PREUM. CCN No. PAoE_ oF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CoNVERsloN:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 11 LEV OIWGNaToR DATE ME DATE REV ORIGNAToR DATE ME DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 "

l 8 ANSI /ANS-6.4-1977 (Reference 6.10), ordm' ary concrete is " Type 04" concrete, which has a theoretical density of 2.35 g/cc (148 lb/ft').

3.5 Air Density For Shielding

'Ibe Control Room air temperature is assumed to be 71*F, since at least one of the two I independent trains of CR HVAC will be in operation to maintain the Control Room temperature. 'Ihe outside air temperature is assumed to be 100 *F, which is conservatively greater than the normal temperature, per UFSAR Section 2.3.2.1.2 (Reference 6.3.c). 100*F will also be used for the air in the remainder of the Auxiliary Building. Per the Handbook of Physical Pronerties of Liouids and Gases (Reference 6.8, page 588), the air densities are:

Temperature (*F/*K) Specific Volume (dm8 /kg or cm8 /3) Density (g/cm')

71*F / 295'K 846.6 1.18e 03 l 100'F / 311*K 892.7 1.12e-03 The air densities modeled in this analysis will not have a significant impact om the analysis )

insults. The gamma radiation attenuation properties of the air are minor in comparison with the geometric attenuation. '

3.6 Daughter Product Isotopes .

The effects of daughter products are considered in this analysis. 'Ibe daughter products generated by the radioactive decay of the Iodine isotopes are noble gas isotopes. 'Ibe daughter products generated by the radioactive decay of the noble gases are Rubidium, Cesium, Strontium and Barium. 'Ihe Bechtel IACADOSE computer program (Reference 6.5.a) places isotopes into groups. Rubidium and Cesium are in IDCADOSE isotope group 5, and Strontium and Barium are in IDCADOSE group 7. Per Table 2-17

" Particulate Release Rates from Gaseous Effluents", of NUREG-0017 (Reference 6.4.f) these isotopes are particulates. Additionally, the isotopes in LOCADOSE groups 6 (Te, Sb),8 (noble metals), and 9 (rare earths) are also listed as pa& lata =. 'Iberefore for this analysis, IhCADOSE Groups 5 to 9 are considered to consist of pardmlatas and will be subject to High Efficiency Particulate Air (HEPA) filtration.

I

NES&L DEPARTMENT CALCULATION SHEET ICCN No/

PREUM. cCN No. PAGE_ oF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVER$10N:

CCN No. CCN -

. Subject Fuel Handlino Accident FHA) Inside Cont L r. erit - Control Room and Offsite Doses Sheet No. 12_

IEV oRIGNaToR DaTE WIE DATE REV oRIQWaTOR DATE WlE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h 4

3.7 Control Room Emergency Mitration Damper Stroke Times Stroke time of the HVAC isolation dampers in the CR HVAC system will be assumed to be 6 seconds, based on E-Mail from F. Santa Ana to T. Remick (Reference 6.2.e).

l 3.8 Unnitered Control Room Inleakage When the Control Room is isolated, an unfiltered Control Room inleakage of 10 cfm is assumed to account for door opening, per SRP 6.4 Section II.3.d.3 (Reference 6.4.d).

l l

3.9 Con 5guration Symmetry Between Units '

This calculation is based on the Unit 2 configuration. Due to the symmetry between units, the results are assumed to apply to Unit 3 also.

3,10 Release Duration In accordance with Regulatory Guide 1.25 Section C.I.i (Reference 6.4.a), the all of the '

radioactive material in the Containment atmosphere is assumed to be released over a two hour interval.

3.11 Number of Failed Fuel Pins If an irradiated fuel assembly being reloaded into the core is dropped into an empty reactor vessel, there is the possibility that the drop distance will be larger than would occur in the Fuel HandiMg Building (254" per CE Iztter S-CE-2666, Reference 6.2.a).

'Iberefore, for the FHA inside containment, all 236 fuel pins in the dropped ammbly will be paamlad to fail. CE concurrence with this assumption is given in Reference 6.2.g.

'Ibe structural elements surrounding fuel in the Reactor Vessel are different than those assumed in CE letter S-CE-2666. When a fuel assembly is dropped onto irradiated fuel in the Reactor Vessel, it is pos4ble that the fuel pins in the impacted assembly could break. However, per S-CE-2666, a fuel assembly can withstand the landing impact of a drop from about 21' without breaking any pins. 'Ibe maximum drop beight onto fuel in the Reactor Vessel will be approximately 13', lowering the impact energy. Therefore, it is assumed that no damage will occur to the impacted bundles. CE concurrence with this assumption is given in Reference 6.2.g.

NES8d. DEPARTMENT CALCULATION SHEET -t PREUM. CcN No. PAGE oF_,,,,

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CcN No. CCN -

. Subject fuel,,tir dlino Accident (FHA) Inside Containment - Contro( Room and Offsite Doses Sheet No. 12.,,,,,

MV om0fdaToR DATE WE DATE REV ofBGedAToR DATE WE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h 4

l 4.0 DESIGN INPUTS 4.1 1%el Handling Acddent Activity Release Charactedstics W Gap Inventory CE letters S-CE-2666 (Reference 6.2.a) and S-CE 3068 (Reference 6.2.b) provide the activity released from ,one fuel pin during an FHA (with a pealdng factor of 1.65 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of decay after reactor shutdown). The assumptions used in generating the fuel rod gap inventories are consistent with Regulatory Guide 1.25 (Reference 6.4.a). To account for operating with fuel discharge burnup extended from 33,000 MWD /MTU to 60,000 MWD /MTU, calculation N-4097-013 (Reference 6.1.h) determined an activity change factor to be used to account for the change in burnup. In the Table 4.1-1 below, the CE activities are adjusted by the N-4097-013 Table 8.1-1 change factor. Where the change factor is less than 1.0, no changes were made to the CE inventory. In accordance with N-4097-013 page 8, a change factor of I was used for Xe-133m (with its 2.19 day halflife). 'Ibe daughter isotopes that the LOCADOSE Code library file created are listed l with a zero initial activity. I Table 4.11 Gap Inventory Per Peak Rod for an FHA ,

ISOTOPE N-4097-013 S-CE 3068 Inventory Adjusted Change Factor (Ci/ Peak Rod) Inventory ;

(Ci/ Peak Rod) '

I-131 1.00 2.10e+02 2.10e+02 I-133 0.98 5.56e+01 5.56e+01 1-135 0.98 3.47e 01 3.47e41 KR-85 2.00 1.46e+01 2.92e+01 l XE131M 1.00 ?.m +00 3.58e+00 XE 133 0.98 5.12e+02 5.12e+02 XE133M 1.00 1.07e +01 1.07e+01 XE 135 1.10 6.63e+00 7.29e+00 ;

XE135M 1.00 0.00e+00 0.00e+00 CS-135 2.00 0.00e+00 0.00e+00 i

i 1

NES&L DEPARTMENT CALCULATION SHEET ICCN No./

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CcN No. CCN -

. Subject Fuel Handlino Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 14 MV oR10HaTOR DaTE WIE DaTE REV oRIGNAToR DaTE WIE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h Per Section C.I.f of Regulatory Guide 1.25, the iodine gap inventory is composed of 99.75 percent inorganic species (i.e., elemental and particulate iodine), and 0.25 percent organic species (i.e., organic iodide).

l 4.2 Refueling Water Clean-up of Isotopes ill Refueling Canal Iodine Removal Per Section C.I.g of Regulatory Guide 1.25, the iodine gap activity released to the water is subject to clean-up due to pool sembbing. Regulatory Guide 1.25 gives pool decontamination factors for situations where there is at least 23 feet of water above the ~

rods. Per Technical Specification ILO 3.9.8.1 (References 6.3.a & b), in MODE 6 the water level above the reactor pressure flange is greater than or equal to 23 feet.

The pool decontamination factors for the inorganic iodine and organic iodide species are 133 and 1, respectively.

1 112 Refuelinn Canal Noble Gas Removal

Per Section C.I.h of Regulatory Guide 1.25, the noble gas activity released to the pool is t

not subject to clean-up due to pool scrubbing. 'Ihe retention of noble gases in the pool is l negligible (i.e., a decontamination factor of one). ;

1 4.3 Containment Characteristks The containment will be Node 2 in the LOCADOSE model. LOCADOSE implicitly models the environment as Node 1.

111 Containment Concrete Wall'Ihickness Per Drawing 23000 (Reference 6.6.c, Note 3), the minimum containment wall thickness shall be d'0" and the minimum containment dome thickness shall be 3'9". 'Ibe elevation of interest is the elevation of the Control Room (30 feet to 50 feet). The containment at elevation 30' to 50' will have a minimum wall thickness of 4'0".

I

NES&L DEPARTMENT l . -

CALCULATION SHEET KCN W PREUM. CCN No. PAGE_, OF__

Project or DCP/MMP SONGS 2&2 Calc. No. N-4072 003 cCN CoNVERSloN:

CCN No'. CCN -

Subject Fuel Handlina AaeWent (FHA) In*Me Cente'ement - Control Room and Offsite Da**s Sheet No._.lft._

MV OfuGNAToR DATE stE DATE REV ORIGNATOR DATE stE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h S

G Containment Net Free Volnma

Ihe activity r*1*anad from the refueling canal is diluted by the containment air volume.

Per Aasumption 3.2, the dome circulators are not operating 'Iberefore, no credit will be taken for activity dilution within the air of the hemispherical containment dome space for .

the calculation of the offsite doses. 'Ibe effective volume that will be used in calculating l the Control Room and offsite doses is' 1

V4 = V- Yw V, = V-(f)(*)xRi.,

where, V, = effective containment free volume in which activity is mixed (ft 8)

V = containment free volume = 2.305e6 ft3(Calc C-257-1.06.01, Reference 6.1.b)

Vw = containment dome volume R% = containment dome radius = 74' 113/4" (Per Sections B and E of Drawing 23060, 75'0" (radius) minus 1/4" (steel liner), Reference 6.6.d)

'Iherefore, V, = 2.We6AS - ( )( )x(74.98A 8)

V, = 2.305e6A 8- 0.883e6As = 1.422e6As

@ Containment Relamaa Flow Rate Per Assumption 3.10, the activity is released from the containment building over a two hour period. In this calculation this requirement will be met by modeling a containment telease rate large enough to ensure that at the end of two hours, about 99.9 percent of the activity will have been released. Therefore, at the end of two hours, the activity in the containment (A,) will be 0.1% of the initial activity (A) in the containment. For a volume of 1.422e6 ft', the containment release flow rate that will need to be modeled is given by the following general equation for activity:

NES&L DEPARTMENT

CALCULATION SHEET ICcN No/

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Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN coNVERSloN:

cCN No. CCN -

Subject Fuel Handfina AaaWant FHA) in*Wa containment - Control Room and Offsite Doses Sheet No. 16 REV oRIGNaToR DATE 5tE DATE REV ORIGNATon DATE WIE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h

4 h

A, = A,e *** = A,e " am.

8""" n=,

0.001 = a *=

h(0.001) = - x lisse = - x 120 ada Fehsmie S 1.42246 A 1.422e6

.. Mowrare - -h(0.001) x Mawraer = 81857 din = 32000qin

Ihe release rrte from the containment to the outside environment will be modeled as 82,000 cfm.

As can be seen from Section 9.5.1 (LOCADOSE output), the activity at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months is less than 0.1% of the initial activity. 'Iherefore, the equation used above is valid.

t 4.4 Control Room Characteristics

'Ihe Control Room will be Node 4 in the LOCADOSE model and the Control Room filter (for filter shine doses) will be Node 3 in the LOCADOSE model.

W Control Room Net Free Volume The Control Room net free volume is 244,398 cubic feet per Calculation M-73-41 (Reference 6.1.c, page 7).

M Control Room Charcoal and HEPA Filter Efficiancies Control Room filter efficiaarian are as follows. Per UFSAR Appendix 15B, no credit is taken for the CR Emergency Ventilation Supply filter (A206 or A207). 'Ibe Emergency Air Conditioner (EAC) iodine filter efficiency is based on the charcoal filter depth of 2 inches (E-Mail from D. Higgins to F. Santa Ana (Reference 6.2.d)) and the corresponding Gercoal filter efficiency values given in Regulatory Guide 1.52 Table 2 (Reference 6.4.c).

'Ibe EAC particulate efficiency is based on the HEPA efficiencies given in Regulatory Guide 1.52 section C.5.c. Regulaary Guide 1.52 efficiencies are applicable since

i NES&L DEPARTMENT CALCULATION SHEET

'CCN No./

l PREUM. ccN No. PAGE._ oF_

l Project or DCP/MMP SONGS 28 2 Calc. No N-4072 003 CCN CoNVERSloN:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) in*14 containment - Control Room and Offsite Doses Sheet No. 17 REV oRIONAToR DATE WIE DATE REV ORIONAToR DATE WlE DaTE R 1 R. Nakano 02 24 94 T. Remick 02-28 94 i

Technical Specification 4.7.5.c (References 6.3.a and b) tests the EAC filters to this Regulatory Guide.

Imm king Filmred CR Emergency Vaa'ileiaa Supply CR Emergency Air Conditioner 1

(A206/7) Filter F&iaan (E418/9) Filter Efficiency Elemeral Iodine 0% 95 %

Organic Iodide 0% 95 %

Particulates 0% 99 %

W Control Room HVAC Ooeration Characteristics The Control Room HVAC parameters during normal and emergency operation are as follows. For conservatism, the emergency mode outside air intake flowrate was increased to the Technical Specification upper tolerance, and the recirculation flowrate decreased to the lower tolerance.

Parameter CR Normal Operation CR Emergency Operation per Train Value Reference Value Reference Filtered Intake Ocfm 40096 (Ref. 6.6.i) 2050 + 150 = 2200 cfm TS 4.7.5a (Refs. 6.3.a & b)

Unfiltered 5820 cfm 40096 (Ref. 6.6.i) O cfm + 10 cfm Intake 40090 (Ref. 6.6 i) 40098 (Ref. 6.6.j)

A-aatian 3.8 Filtered 0 cfm 40096 (Ref. 6.6.1) (35,485-10%)-2200 = TS 4.7.5a Recirculation 29,737 cfm (Refs. 6.3.a & b)

Unfiltered 29,885 cfm 40096 (Ref. 6.6.1) Ocfm Recirculation 40096 (Ref. 6.6.1) 40098 (Ref 6.6.j)

W Control Room Dimensions The modeling of the Control Room dimensions for the determination of the doses due to the outside cloud shine will be used for the SHIELD-SG model. For modeling purposes, the Z-axis will be with elevation of the plant. The X axis runs North and South and the Y-axis runs East and West. The origin of the co-ordinate system used is at the plant elevation rero and at the North-West comer of the control room outer wall. The control F

NES&L DEPARTMENT CALCULATION SHEET ICCN W PREUM. CCN No. PAGE _ oF _

Project or DCP/MMP SONGS 28:3 Calc. No. N-4072 003 CcN CONVERSION:

CcN No. CCN -

, Subject Fuel Handfine Accident FHA) Inside Cooteli.crerit - Control Room and Offsite Doses Sheet No. 18 MV ORIGedATOR DATE WlE DATE REV ORIGedAToR DATE WlE DATE R 1 R.Nakano 02 24 94 T. Remick 02 28 94 h 4

room is rectangular, and therefore, the North and South walls have the same dimensions and the East and West walls have the same dimensions.

North and South Walic:

Per Drawing 10101 (Reference 6.6.a), the inner surfaces of the Control Ram North and South walls have a length of 120'6" - 2'6" - l'3" = 116'9".

Fict and West Walls:

Per Drawing 10101 (Reference 6.6.a), inner surfaces of the Control Room East and West walls have a length of 219'0" - l'3" - l'3" = 216'6".

flDDE

Ibe floor of the control room is at plant elevation 30' 0" per Drawing 10115 (Reference 6.6.b) and is 1 foot thick per drawing 25112 (Reference 6.6.e).

Ceiling:

Per Drawing 10115 (Reference 6.6.b), the top of the Control Room ceiling is at plant elevation 50' 0". 'Ihis includes a l' thick ceiling per Drawing 25115 (Reference 6.6.f).

1 W Atuiliary Buildine Several concrete walls and floors / ceilings are important for the purposes of modelling the various direct shine doses:

Control Room East Wall (2*6" thick per 10101, Reference 6.6.a)

Control Room West Wall (2'6" thick per 10101, Reference 6.6.a)

Control Room North Wall (2'6" thick per 10101, Reference 6.6.a)

Control Room South Wall (2'6" thick per 10101, Reference 6.6.a)

Elevation 70 Floor (l' thick per 25120, Reference 6.6.g)

Building Roof Elevation 85 (l' thick per 25123, Reference 6.6.h)

NES&L DEPARTMENT l CALCULATION SHEET ICCN NW ;

PREUM. CCN No. PAGE_ oF ,

Project or DCP/MMP SONGS 2&3 Calc. No. N.4072 003 CCN Co,NVERsioN:

CCN No. CCN -

. Subject Fuel Handlino Acekfent (FHA) le=Ma C66teMment . Control Room and Offsite Da=== Sheet No. 19 IEV ORIGhaToR DaTE WIE DaTE IWV OR10NaToR DATE WIE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28 94 y 4

fjj Control Room RMindon Monitor 'haracteried" r At a background level of 100 cpm and a setpoint of 480 cpm, the trip initiation time of the CR HVAC radiation monitore M initiate the CRIS (RE.7824-1 and RE.7825 2 per P&ID 40173A, Reference 6.6.k) is as follows per Maintenance Order #93080083 (Reference 6.7).

Steo Increase Above Backrround (com) Trio Initiation Time (sec) le3 33.25 le4 2.625 le5 0.360 le6 0.0815 le7 0.0250 1E+07 in;3n,' y nu suu: tuuv

..:.:.:::., ::::::::, .::.::!u u u u u u;n uj:ununuinusui ininannuinsuu

......y.........

'P 1E+O6 m u

a.; 3. . ; p; m, n. .g: i.n . s.. .m<<.

3,3

. 3.p::;: . ; p:$ : .t.: ::: : . ; . .p:: . . : : -. s

.4 . >

.n. 3 p n: :

i

. .....i n.s .u. .". >1t,: :::....,...."...:.

[ ..

l t

...... ...;.4..:.4.;;4 ...... . : . .; . : .; i 4.-, . . . . . . (. . 4. . : . i . ; 4.; ; . . . . . .; . . .:. 4 4. i.; : :,

1E+05 ;;;;;;:;;;3 ppg;;;;; ;;;;;;;;;;gg.;gg;;;;;g;;gj;;p;;.;;; ;;;j;;jj;g;p;.;p;;;

. . . . . . > . . .) . 4. .:. 4. H < < .................

. . . l . . 3 . .) . 3 .) ( .; .,

s ..... .

. . . . < .. .4.. .. .g...4. 3.:.3

...,3

. . .. . . . . . . . .:. 4. .:. g .) ; (

. )

. . . . . . > . . . > ......H... ... o g.o..g. o. ).3

. ...4. p . go . g.o .g ..p .g .:4.. 3 o n oy.. .o:.. p . +. p>. .n. ,

1E+04 uinu na nna su u! unnan. ,

gf} :*::*: :::: ::::::::' an up:u j:uuusisu : ::::::::::...su"sui n u na u su su au n

. . . . . .y . . .y . g. .y g. g , . .'. : .: .: . : . :* :::* * :

. g . . . g . .y . g .y g .:.y , . . . . , . . . g. . g . g . g .:. , , . . . .y . . .:. . <. g. g .y g .

. . . . . .. . . .; . .. .; g. ; g g < . . . . . ; . . . g . .y . ; .. g .;.y. . . . . . g. . . g . . . . g . g g. . g ..

.. . . .y . g. .;. g.. g ;,

+ 1E+03 : : : en -

n -

:::en : .: : -

gj..!g;3g;3;g;3.g!!g;;ggg;;; gg;gggg; 3.;g;ggg;ggggg; ;;g;;;gg.;ggg3g j ................ .. . . . . . . . . . . . . . .

0.01 0.10 1.00 10.00 100.0 Trip initiation Time (sec)

Per calculations A.92.NF.003 page 9 (Reference 6.1.a) and N-4060-014 page 8 (Reference 6.1.f), the sample transit time for the CR HVAC radiation monitors is 5.6 seconds. Per N-4060-014 page 9, the reported value of 5.6 seconds should actually be increased by 10% to account for an additional 18 feet of duct not explicitly included in the analysis, for a total time of 6.2 seconds.

l NES&L DEPARTMENT CALCULATION SHEET ICCN No./

PREUM. CCN No. PAGE_ 0F_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CONVERSloN: I j cCN No'. CCN -

. Sulliset Fuel Handlina Accident FHA) Inside Centeininent - Control Room and Offsite Doses Sheet No.1 IWV OIWGNaTOR DATE WIE DaTE REV ORIGNaToR DaTE WIE DATE R 1 R. Nekano 02 24 94 T. Remick 02 28-94 h 4

Per E.' fail from J. Beebe to T. Remick (Reference 6.2.f), the efficiency of the radiation 3

monitors for Kr-85 is such that I cpm is equivalent to the following pCi/cm . De least i 3

efGcient (largest pCi/cm per cpm) of the CR radiation monitors will be used for the ,

calantations, Rad Monitor (mci /cm 3)/com CR 7824 2.33e-8 CR 7825 3,56e-8 De allowable limits for the CR HVAC radiation monitors is equal to the setpoint divided by 0.871 per E-Mail from J. Beebe to T. Remick (Reference 6.2.f). He highest values will be used in the calculations. His results in the following:

Esd_ Monitor Setpoint Allowable Limit 7824 464.5 cpm 533.3 cpm 7825 495.2 cpm 568.5 cpm

.4dl CR Intake Filter Characteristics De CR HVAC Intake filter shine SHIELD-SG dose model and resulting post-LOCA dose rates developed for calculation N-4060-016 revision 1 (Reference 6.1.g Sections 9.5 and 9.7) will be used as a basis for the filter shine analysis for this calculation. Per this model, the volume of each CR intake filter (A206/7)is 7.32 ft3 with a corresponding volume scaling factor of 4.8225e-6 cm-3 (1/V). Use of this model, and the N-4060-016 LOCA soume term, resulted in a 30 day operator dose of 0.65 Rem, with the following dose rates at Dose Point 10 (N-4060-016, page 47). Per N-4060-016, dose point 10 has the largest post accident operator dose in the Control Room operating area:

.Tamt Dose Rate (Rem /hr) 0.2 hr 8.18e-03 0.5 hr 9.64e-03 1 hr -

9.76e-03 2 hr 9.48e-03 3 hr 9.20e-03 4 hr 9.08e-03

~ _ _

NES&L DEPARTMENT CALCULATION SHEET ICcN W PREUM. CCN No. PAGE _ oF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

ccN No'. CCN -

, Subject Fuel Handfino Accident FHA) Inside Containment - Control Room and Offsite h Sheet No. ,2]__

MV ofuGN aToR DaTE WlE DATE MV ofuGMaToR DaTE WlE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h i

4.5 Number of Fuel Rods Per Fuel Amm-hly This calculation will model 236 fuel rods in an assembly (Reference 6.6.m), which is the maximum number of fuel rods per assembly allowed by Technical Specifications Section 5.3.1 (References 6.3.a and b).

4.6 Occupancy Factors Table 6.4-1 of Standard Review Plan 6.4 (Reference 6.4.d), gives the Control Room egmacy factors. There are no occupancy factor changes in the CR for the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Section 100.11 of 10 CFR 100 states that the post-accident offsite doses are to be calculated for an individual who is exposed for the entire interval of interest (i.e., an

-:-:-:=-=cy factor of 1.0). Table 4.6-1 presents the CR and offsite occupancy factors for ,

the time interval of interest. :

Table 4.61 Occupancy Factors l

Time Interval Control Room EAB IEZ (unitiess) (unitiess) (unitiess) j 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.0 1.0 1.0 l 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.0 0.0 (not < W) 1.0 4.7 Breathing Rates l

Standard Review Plan 6.4 (Reference 6.4.d) and Regulatory Guide 1.25 (Reference 6.4.a), do not provide guidance on breathing rates. The only breathing rate guidance that can be found is present in Regulatory Guide 1.4 (Reference 6.4.b), which i addresses the breathing rates ofindividuals present at offsite locations during a LOCA. l The Regulatory Guide 1.4 (Section C.2.c) breathing rate guidance varies as a function of time as it addresses the offsite individuals at work and at rest.1be IX)CA at-work breathing rate will be assumed to apply to the operators during a FHA. The LOCA offsite breathing rates will be assumed to apply to individuals at the EAB and LPZ during a FHA. These breathing rates are given in Table 4.7-1.

1 l

CALCULATlON SHEET ICcN W PREUM. CcN No. PAGE_ oF_

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ccN No. CCN -

Subject Fuel Handlino AaaMam (FMA) le=Ma Containment - Control Room and Offsite W Sheet No. 21_ l MV OfuGNaToR DaTE WIE DaTE REV ORIGNaToR DaTE WIE DaTE 5 1 R. Nekano 02 24 94 T. Remick 02-28 94 5

Table 4.71 Breathing Rates Time Interval CR EAB LPZ (m'/sec) (m'/sec) (m'/sec)

O to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.47 x 104 3.47 x 10d 3.47 x 10d 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.47 x 104 Not Applicable 3.47 x 10d f 4.8 Atrnospheric Dispersion Factors The atmospheric dispersion factors (i.e., x/Q values) between the Containment Building l and the offsite EAB and LPZ locations are determined in Calculation N-4010-002 i (Reference 6.1.e, Revision I page 3). As required by Standard Review Plan 15.7.4 i (Section H.3), the atmospheric dispersion factors used in this analysis are the five percentile x/Q values.

l l

l The atmospheric dispersion factors between the Containment Building and the Control Room are determined in Calculation N-4010-001 (Reference 6.1.d page 39) for dispersion. As required by Standard Review Plan 15.7.4 (Reference 6.4.e,Section II.3),

i i the atmospheric dispersion factors used in this analysis are the five percentile X/Q values.

l The control room occupancy factors (per Design Input 4.6) are included in the x/Q values l given in Calculation N-4010001 and will be removed and considered separately by this i

analysis. However, for the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , the Control Room c-xsp= y factor is 1 and therefore the atmospheric dispersion factors presented here will be the same as those in i Calculation N-4010001. l In this calculation no credit is taken for cloud depletion by ground deposition and :

radioactive decay during transport from the Containment Building to the Control room and offsite locations. 'Ihus, this calculation assumes instantaneous dispersion and transport once the material is released to the environment.

(

[ 1he atmospheric dispersion factors are listed in Table 4.8-1: 1 i

l l l

l l

1

NES&L DEPARTMENT CALCULATION SHEET 'cc"

PREUM. CCN No. PAGE_ oF_

Pro lact or DCP/MMP SONGS 2&2 Calc. No N-4072 003 CCN CONVERsloN:

CcN No. CCN - 1 o Subject Fuel Handlina Accident (FHA) In*W= Containment - Control Room and Offsite Da*** Sheet No. 23 l Rev opeWNAToR DATE stE DATE ptE

' REV oRONATOR DATE DATE R l 1 R. Nakano 02 24 94 T. Remick 02 28 94 h )

l Table 4.81 Atmospheric Dispersion Facton Ahric Dispersion Factors (sec/m')

Time Interval ",

toCR to EAB to LPZ 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3. le-03* 2.72e-04 7.72e-06 ;

2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3. le-03* Not Applicable 7.72e 06 3.le-3 from N 4010401 + occupancy factor of 1.0 from Design input 4.6 = 3.le-3 l

l 4.9 l Dose Convenion Factors The default dose conversion factors (DCFs) present in the Bechtel LOCADOSE computer program (Reference 6.5.a) will be used in this analysis.

4.10 SOURCE 2 Code Source Stangth Spectrum Energy Structure The gamma energy source strengths from the SOURCE 2 output will be grouped into a

" BASE 10" energy structure. The " BASE 10" gamma energy structure is shown in Table 4.101. This energy structure is part of the SOURCE 2 Code (Reference 6.5.b) library.

l

- - - - - - - -i

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. Sutiisct Fuel Handfina Accident (FHA) Inside containment - Control Room and Offsite Doses Sheet No. 21._,,, !

REV OfuGSGATOR DATE 5tE DATE REV OfuodNATOR DATE WIE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h l

\

TABLE 4.101

" Base 10" Gamma Energy Structure Energy Group Energy Ranges Effective Energy Number (Mev/y-dantegration (Mev/y<ksintegration) l

) i 1 0.0 s E s 0.1 0.1 1 2 0.1 < E s 0.4 0.4 l 3 0.4 < E s 0.9 0.8 4 0.9 < E s 1.35 1.3 5 1.35 < E s 1.80 1.7 6 1.80 < E s 2.20 2.18 7 2.20 < E s 2.60 2.5 8 2.60 < E 5 3.00 2.8 9 3.00 < E s 5.00 4.0 '

10 5.00 < E 515.00 6.2

)

l

NES&L DEPARTMENT !

4

CALCULATION SHEET 'cc"

PREUM. CcN No. PAGE_ oF_

Project er DCP/MMP SONGS 2&3 Cak:. No. N 4072 003 CCN CONVERSION:

CCN No'. CCN -

, Subject Fuel Handlina Accident FHA) leam containment Control Room and Offsite Doses Sheet No.1 IWV CWWGfdaToR DaTE plE DaTE REV olWGedaToR DATE plE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 4

5.0 METHODOLOGY ;

5.1 General Methodology

'Ihis Section presents a discussian of the methodology employed in the evaluation of control room and offsite doses after a design basis FHA.

Following an FHA, core activity is dispersed into the containment atmosphere, and from there, to the Control Room and the Offsite locations of the EAB and the LPZ.

'Ibe doses will be evaluated as follows:

1. Control Room doses

a. Immersion and inhalation doses from the cloud inside the control room

b. Shine from the cloud outside the control room

c. Shine from the emergency control room charcoal filter

d. Shine from contaminated air in the Containment Building

2. EAB and IJZ immersion and inhalation doses from the airborne cloud An analysis will also be made for the case where no credit for the CR emergency HVAC system is taken. Therefore, two separate LOCADOSE computer runs will be made:

a. CR is in normal operation, and then isolates when high radiation is sensed by the HVAC radiation monitor.

b. No CR isolation occurs.

Rinm the impact of the direct shine doses on the Control Room whole body dose are expected to be small, these direct doses will only be determined for the LOCADOSE run where the CR isolates when high radiation is sensed by the HVAC radiation monitor. 'Ihe dose from this case will also be used for the case where no CR isolation occurs.

I

'Ihis calculation will make use of three computer codes to evaluate the doses of interest:

LOCADOSE, SOURCE 2, and SHIELD SG (References 6.5.a. b, & c). These computer codes are described in Section 5.2. 1

NES8d. DEPARTMENT CALCULATION SHEET ==

PREUM. CCN No. PAGE ,_ oF_

Project or DCP/MMP SONGS 23:3 Calc. No tL(.072-003 CCN CoNVERslON:

ccN No. CCN -

. Subject Fuel Handlina W (FHA) Ir=W Containment - Control Room aripffsite Doses Sheet No. 23,,,_

u-MV ORIGelaToR Dalt WIE DaTE REV oRIGedaToR DATE WIE DaTE R 1 R. Nakano 02 24 94 T. Momick 02 28 94 h

4 5.2 Computer Code Descriptions 12J LOCADOSE Code Descriptions ne dose due to the FHA activity release mechanism will be evaluated through use of Release 3 of Bechtel Standard Computer Program NE-319, "LOCADOSE". He LOCADOSE Code consists of three modules: an activity transport program, a dose calculation program and a filter loading program. De first two modules are used in this calculation.

I De activity transport module calculates activities, integrated activities and releases over a i time period using a multi region model that can accommodate up to nine regions and fifty I time steps. Daughter isotope activities, spray removal and LOCA during purge option can !

be performed by this program. Activities, integrated activities and releases are saved on a !

file for use by the other modules. I De dose calculation module 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 activity transport program l and for up to twenty offsite locations. i he LOCADOSE Code will be executed on a personal computer. The Validation Calculation Test Cases supplied with the program have been run and compared with the i test case output supplied with the software. De LOCADOSE Code output was found to l be no different from the test case output. Derefore, the software and hardware utilized in l

the preparation of this calculation are considered validated.

12J SOURCE 2 Code Descriptions !

l De SOURCE 2 Code determines the source strength spectrum from a User specified energy grouping arrangement and a User specified activity pmfile. De activity profile represents the total number of curies of each isotope that are present.

To calculate doses in units of Rem requires SHIELD-SG Code input in the form of an integrated source strength spectrum in units of Mev-hr/cc-sec. To calculate an integrated source stiength spectrum in units of Mev-hr/cc-see requires SOURCE 2 Code input in the form of an integrated activity concentration in units of Ci hr/cc.

i his program will be executed on a personal computer. De Validation Calculation Test Cases have been run and canpared with the test case output supplied with the software.

NES&L DEPARTMENT

, . CALCULATION SHEET 'ec"

PREUM. CCN No. PAGE_ oF_

Proinct or DCP/MMP SONGS 2sas

Calc. No. N-4072-003 CCN conversion:

cCN No. CCN -

Subjoet Fuel Handlina W FHA) Ira Co.,;_;. T c.; - Control Ree. T. and Offsite Doses Sheet No._22_

Amf olWG5daToR DaTE WE DaTE MV olW0sdaToR DaTE WE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 De SOURCE 2 source strength spectra generated for the current test cases were found to be no different from the test case output supplied with the software. Therefore, the software and hardware utilized in the preparation of this calculation are considered to be validated. '

l i

W SHmrD-SG Code Descrintions i Bechtel Standard Computer Program NE-650, " SHIELD-SG" will be utilized in this calculation. SHmtD-SG is an interactive program designed to solve gamma ray transport i problems using the point kernel method (i.e., given an input energy si;e.Eviii and l source / shield geometry, it calculates the gamma dose rate through the shield). He ,

source / shielding geometry can be any combination of up to fifty geometrical bodies, l including orthogonal alabs, right parallelepipeds, and/or right cylinders. Multiple dose points can be specified in a single run. !

De SHIELD-SG Code determines the doses in the control room as a function of geometry !

and a energy source strength spectrum. Dese source strength spectrums are calculated I with the SOURCE 2 Code as detailed in Section 5.2.2.

' i His program will be executed on a personal computer. De Validation Calculation Test Cases supplied with the software have been run and compared with the test case output l

, supplied with the software. De SHIELD SG output generated for these test cases was l l found to be no different from the test case output supplied with the software. Derefore, '

the software and hardware utilized in Om preparation of tins calculation are considered to t be validated. '

5.3 EAB and LPZ and Control Room Inside Cloud Domes Dese are the immersion and inhalation doses due to the airtiorne cloud at the EAB and LPZ and the cloud inside the Control room. De LOCADOSE dose calculation program will be run using the appropriate assumptions and design inputs from Sections 3 and 4 to calculate the Imrnersion doses in the CR and at the EAB and LPZ. Fim.s 5.3-1 and 5.3-2 show the LOCADOSE models used.

1

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

NES&L DEPARTMENT CALCULATION SHEET KCN W PREUM. CCN NO.

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CCN No. CCN -

. Subject Fuel Handlina Accident FHA) Inside Cerd.;, T ra - Control Room and Offsite Doses Sheet No. 28 MV OluGNATOR DATE plE DATE REV ORIGNATOR DATE plE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h

4 Mgure 5.31 LOCADOSE Model CR HVAC In Normal Mode (No CR Isoladon)

NODE 2 Contelrnent Building 1.422e6 cf 0 cfm NODE 3 --g t cfm 9 e6 A206/7 Control 1001 Isobte Gas Room Inteke Filter 01 Other 82000 cfm e 7.32 cf A l y/OEAB y/OCR y/O LPZ l

y 0 cfm DE 1(elem)

DE f(org) 01 Partic l 01 Noble Gas " 5820 cfm I

IIODE 4 control noon

---* 5820 cfm 244,396 cf 01 I(elen) 01 2(org) < 29685 cfm DE Partic 05 Noble Gas

NES&L DEPARTMENT l

. . CALCULATION SHEET ICCN W PREUM. CCN NO. PAGE _ 0F _

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CCN No. CCN -

1 Subject Fuel HandEno Accident (FHA) In*W Cent-lrs r. - Control Room and Offsite Domes Sheet No. 23_

W CleGNATOR DATE flE DATE LEV OfDONATOR DATE WlE DATE R 1 R. Nakano 02 24-94 T. Remick 02-28-94 h 4

Mgure 5.3 2 LOCADOSE Model 2 Trains of CE HVAC In Emergency Mode (CR Isoladon on High Radiadon Signal) l I

l NODE 2 Centeiruient building 1.422e6 cf 264 cfm Is00E 5 m t cfm 9 e6 A206/7 Control 1001 Imble Gas Room Intelte Filter 01 Other l 81T36 cfm

7.52 cf d y/OEAB y/OCR y/O LPZ l

T 4400 efo (totet for 2 trains) m !(elem) m !(org) ,

991 Partic l !

DE Imble Gas " 10 cfm N00E 4 -

l control anon 1

* 4410 cfm l M4,596 cf l

1 1

951 I(elen) 951 Itorg) o 59474 cfm (totet for 2 trains) 991 Portic OE leable Gas

NES&L DEPARTMENT CALCULATION SHEET 'cc"" lcy , ,,,,_

Project or DCP/MMP SONGS 28:2 Calc. No, N-4072 003 CCN coNVERsloN:

CcN No'. CCN -

. Sutliect Fuel Handlina Accident (FHA) inside Containment Control Room and Offsite Doses Sheet No._2G_

MV oNGStafoR DaTE WE DaTE MV oNOMaToR DaTE WIE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h 5.4 Control Room Outside Cloud Rhine Doses

'Ibe integrated activity released from the Containment Building (base,i on the LOCADOSE transport activity program) for the 0 to 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months time period will be used as input to the SOURCE 2 Code to determine an integrated source strength wuurs representing the l l outside cloud. SOURCE 2 will determine the gamma energy source strength spectrum l l using the SOURCE 2 BASE 10 energy structure (per Design Input 4.10). 'Ihc source l

! strength spe.hwu will then be used as input to the SHIELD-SG code to calculate the

! doses in the Control Room. 'Ibe O to 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months integrated release will be used to ensure all l of the activity released is included in the analysis.

'Ihe output of the LOCADOSE run made for Section 5.3 will give the activity leaving the Containment Building for the specified time steps. 'Ibe integrated activity will then be calculated by adding up the time intervals ofinterest.

A SOURCE 2 Code Multiplier will be determined by using the 0-8 hour Control Room atmospheric dispersion (x/Q) values, and the appropriate unit conversion factors. The 0-8 hour x/Q values will be used since this is the x/Q used for the release period.

Using the above input parameters, the output of the SOURCE-2 Code will be in units of Mev-hr/cc-sec. Use of these values as an input into SHIELD-SG will determine the integrated dose at various locations within the Control Room envelope due to gamma radiation shine from the cloud outside.

5.5 Control Room FUter Shine Doses

'Ibe atmospheric dispersion of the release means that only a portion of the activity present in the Containnunt release becomes entrained in the CR HVAC Intake flow. Another way to analyze this dispersion would be to model a direct flowpath between the Contalanet Building and the CR Intake Filter node. 'Ibe flowrate used would account for the dispersion of the Contalan=t release, and the intake flow rate of the CR intake filter. A IDCADOSE recirculation filter will be used (with an arbitrary flowrate of 1,000,000 cfm) on Node 3 (CR Intake filter) to remo.ve the noble gases, since the CR

HVAC Intake Filters do not retain noble gases.

Once this modeling is done, the IDCADOSE computer run will then determine the time Q=E t filter activity. 'Ihe filter activity will be converted to a source strength through the use of the SOURCE 2 code. A SOURCE-2 Code Multiplier will be determined by l

I

NES&L DEPARTMENT CALCULATION SHEET 'cc" No '

PREUM. CcN No. PAoE__, oF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CoNVERsloN:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) Inside Containment - Control Room and Offsite na==s Sheet No. 11__

MV OIDGodaTOR DaTE WIE DaTE IWV OR10fdaToR DaTE plE DaTE R 1 R. Nakam 02 24 94 T. Remick 02 28 94 h j 4

using the filter volume (per Design Input 4.4.7), to determine a source strength in units of Mev/sec-cc.

Using the above input parameters, the output of the SOURCE 2 Code will be in units of Mev-sec/cc. Use of these values as an input into SHIELD-SG will determine the dose rate at various locations within the Cetrol Room envelope due to gamma radiation shine from the HVAC intake filter shine. 'ib SHIELD-SG model from calculation N-4060-016 revision 1 (Reference 6.13) will be ux.d (with the deletion of those dose points not in the Control Board area).

5.6 Contalmnent Direct Shine Doses De contaminated air inside the Containment Building could cause it to serve as a shine source for the Control Room he radiation must pass through the following walls in order to reach the operators:

Containment Wall (4'0" thick per Design Input 4.3.1)

Control Room North Wall (2'6" thick per design Input 4.4.4)

Additionally, any potential contribution from this source stops at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , since all of the activity has been released from the Containment per Assumption 3.10. Based on engineering judgement of the large amount of concrete, and the geometric attenuation due to the distance between the Containment and the CR, the direct shine dose from the Containment is negligible.

4 e

NES&L DEPARTMENT l CALCULATION SHEET

"" No '

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CCN No. CCN -

o Subloct Fuel Handhna Accident FHA) Inside Containment - Control Room and Offshe_Datas Sheet No.._32_

MV OfuGnaTOR DaTE WE DATE MV OluGMaTOR DaTE 5tE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h i

6.0 REFERENCES

l 6.1 Calculations

a. Units 2&3 Calculation A-92-NF 003, Revision 0, CR Dose Evaluation For Deletion CR Monitor Iodine / Particulate Channels.

1

b. Units 2&3 Calculation C-257-1.06.01, Revision 1, " Containment Shell Analysis- )

Containment Passive Heat Sink", dated 07/28/77.

c. Units 2&3 Calculation M-73-41, Revision 7, " Auxiliary Building - Control Area l El-30' Control Room Complex - Heat Load Calculation Spec # SO23-4101". I a d. Units 2&3 Calculation N-4010-001, Revision 4 " Control Room x/Q values", dated 07/07/92.

c. Units 2&3 Calculation N-4010 002, Revision 1, "EAB and LPZ x/Q values",

dated 08/13/76.

f. Units 2&3 Calculation N-4060-014, Revision 0, Dose Due to Control Room Isolation Delay.

3. Unns 2&3 Calculation N-4060-016, Revision 1 Post LOCA Charcoal Filter Doses j

- Control Building. !

h. Units 2&3 Calculation N-4097-013, Revision 0, Spent Fuel Pool Rcrack Activities and Source Strength Spectruras. i 6.2 Comsoondence

a. CE letter S-CE-2666, "FSAR Accident Analysis for San Onofre 2 and 3", dated March 18,1976 (CDM # C760318G-41-7-3)

b. CE letter S-CE-3068 " San Onofre 2 and 3 FSAR - Sections 7.3 and 15.7.4", dated July 19,1976 (CDM # C760719G-47-3-4) 3

c. Deleted

d. E Mail from D. Higgins (SCE) to F. Santa Ana (Bechtel) et. al., dated 5/13/93, "CR HVAC Intake Filter Housing" (a copy is included in Section 10.1).

I

NES&L DEPARTMENT CALCULATION SHEET ICCN NoJ PREUM. CCN No. PAGE__ oF__,

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CCN No. CCN -

. Subject Fuel Handline Accident FHA) Inside Containment - Control Room and Offsite Doses Sheet No. _3L_,

REV oNGWAToM DaTE WlE DATE REV om0NaToR DATE WIE DATE R 1 R. Nekano 02 24 94 T. Remick 02 28-94 h 1

I

e. E Mail from F. Santa Ana (SCE) to T. Remick (Bechtel), dated 9/16/93, " Control Room HVAC Information" (a copy is included in Section 10.2). l

f. E-Mail from J. Beebe (SCE) to T. Remick (Bechtel), dated 10/8/93, "CR and FHB HVAC Rad Monitor Information" (a copy is included in Sxtion 10.3). l

3. E-Mail from A. Bardia (SCE) to T. Remick (Bechtel), dated 1/19/94, "OIR 92-019, 070, 071 Information Request - RESPONSE TO" (a copy is included in Section 10.4).

6.3 Licensine Documents

a. San Onofre Unit 2 Technical Specifications, up to and including Amendment 101.

b. San Onofre Unit 3 Technical Specifications, up to and including Amendment 90.

c. SONGS 2&3 Updated Final Safety Analysis Report, up to and including Amendment 9.

6.4 Rerulatory Documents

a. Regulatory Guide 1.25 (Safety Guide 25), " Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors", dated March 23,1972, . -

b. Regulatory Guide 1.4, Revision 2, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors", dated June 1974.

c. Regulatory Guide 1.52, Revision 2, " Design, Testing and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Ilght Water-Cooled Nuclear Power Plants", I dated March 1978.

l I

I 1

-a4- .1- - aa-- a _ . s --, - . , , - . m NES&L DEPARTMENT CALCULATION SHEET ==

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CCN No. CCN -

Subject Fuel Hardina Accident (FHA) Inside C661 ; rises; - Control Room and Offsite Daa*=

Sheet No.1 REV ONGMaToR DaTE WIE DaTE REV ORIGNaToR DATE WE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h 4

d. NUREG-0800, Standard Review Plan SRP Section 6.4, Revision 2, " Control Room Habitability System", dated July 1981.

c. NUREG 0800, Standard Review Plan (SRP) Section 15.7.4, Revision 1,

" Radiological Consequences of Fuel Handling Accidents", dated July 1981.

1

f. NUREG-0017, Revision 1, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE '

Code)", published April 1985.

l

g. 10 CFR Part 50, " Domestic Licensing of Production & Utilization Facilit!:s", l revised as of January 1,1993. j

h. 10 CFR Part 100, " Reactor Site Criteria", revised es of January 1,1992.

6.5 Bechtel C0mDuter Programs

a. LOCADOSE Code, Bechtel Standard Computer Program NE-319, Release 3, dated l October 19, 1990.

b. SOURCE 2 Code, Bechtel Standard Computer Program NE-602, Release D2-5, l dated December 11,1991.

c. SHIELD-SG Code, Bechtel Standard Computer Program NE-650, Release D1-9, dated December 11, 1991. .

l 6.6 Drawines

a. Units 2&3 Drawing 10101, Revision 28, Aux Building Floor Plan El 30'0" (Control Area).

b. Units 2&3 Drawing 10115, Revision 19, Aniliary Building Transverse Section.

l

c. Units 2&3 Drawing 23000, Revision 5, Containment Structure - General Arrangement.

d. Units 2&3 Drawing 23060 Revision 6, Containment Structure - Dome liner &

Inserts - Sections & Details Sh 1. '

l

NES&L DEPARTMENT CALCULATION SHEET ICCN No./

PRELIM cCN No. PAGE of Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CCNVER$1oN:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No.._2L_

IEV ORIGWaTOR DATE 5tE DATE REV ORIGNaTOR DATE 5tE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h

e. Units 2&3 Drawing 25112, Revision 9. Auxiliary Building Control Area Interior Concrete Walls E 9'0" to E 30'0" - Sheet 3.

f. Units 2&3 Drawing 25115, Revision 11. Auxiliary Building Control Area Interior ,

Concrete Walls E 30'0" to 50'0" Sheet 1. 1 1

g. Units 2&3 Drawing 25120, Revision 5, Auxiliary Building Control Area Interior Concrete Walls E 50'0" to 70'0" Sheet 1.

l l

h. Units 2&3 Drawing 25123, Revision 6, Auxiliary Building Control Area, Exterior l Concrete Walls El. 70'0" to E 98'8".

i. Air Flow Diagram 40096, Revision 12, Train B Control Building - El. 30'-0". I J. Air Flow Diagram 40098, Revision 6, A Control Building - El. 30'-0".

k. Units 2 & Common Drawing 40173A, Revision 11, P&I Diagram, Control Room l Complex HVAC (Normal A.C.)- System No.1510. '

l. Drawing SO23-410-1-1-13, Revision 13, Control Room Emergency HV Unit (American Air Filter drawing R107D-160325-K).

! m. Drawing SO23-910-10-0, Revision 0, Fuel Bundle Assembly.

I 6.7 Maintenance Order #93080083.

l 6.8 Vargaftik, N.B., Handbook of Physical Pronerties of rinuids and Gawe., Second '

Edition, published by Hemisphere Publishing Corporation, Washington DC, dated l 1983.

6.9 J.R. Lamarsh, Introduction to Nuclear Eneineerine. 2nd Edition, published by Addison-Wesley Publishing Company, Inc., of Reading Massachusetts, dated 1983. l 6.10 American National Standard ANSUANS-6.4-1977 (N403), approved August 8, 1977, " Guidelines en the Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants".

i

NES&L DEPARTMENT CALCULATION SHEET ICCN No./

PREUM. CCN NO. PAGE_ oF_

Prefect or DCP/MMP SONGS 2&S Calc. No. N-4072 003 CCN CoNVERSloN:

cCN No. CCN -

. Subject Fuel Handlina Accident FHA) Inside Containment - Control Room and Offsite Domes Sheet No. ,16._

IWV ORIGNAToR DATE WIE DATE REV OIDGNAToR DATE plE DATE R 1 R.Nakano 02 24 94 T. Remick 02 28 94 h S

7.0 NOMENCLATURE CE Combustion Engineering CPIS Containment Purge Isolation Signal Cpm Counts Per Minute for a radiation monitor CR Control Room CRIS Control Room Isolation Signal .

DCF Dose Conversion Factor l EAB Exclusion Area Boundary EAC Emergency Air Conditioning '

EVS Emergency Ventilation Supply )

FHA Fuel Handling Accident !

HVAC Heating, Ventilating and Air Conditioning '

LCO Technical Specification Ilmiting Condition for Operation !

LOCA IAss of Coolant Accident LPZ Low Population Zone SRP Standard Review Plan (NUREG-0800)

'IS Technical Specifications UFSAR Updated Final Safety Analysis Report x/Q Atmospheric Dispersion Factor i

J

NES8tL DEPARTMENT CALCULATION SHEET ICcN No./

PREUM. ccN No. PAGE _ oF _

Prefect or DCP/MMP SONGS 2&2 Calc. No. N-4072 Op[ cCN CoNVERSloN:

CcN No. CCN -

, Subject Fust Handlino AceW=nt IFMA) Ir**Wa Containment - Control Room and Offsite Da=== Sheet No. 27 IEV OluG5daTOR DaTE WE DaTE REV oRIGfdaToR DaTE WE DaTE R 1 R. Nakano 02 24 94 lT. Remick 02 28-94 h 1

S.0 COMPUTATIONS 8.1 Refueling Water Iodine Removal As discussed in Design Input 4.2.1, the iodine gap activity released to the water is subject to clean-up due to pool scrubbing. Regulatory Guide 1.25 gives pool decontamination factors for situations where there is at least 23 feet of water above the rods. Per Technical Specification ILO 3.9.11 (References 6.3.a and b), in MODE 6 the water level above the reactor pressure flange is greater than or equal to 23 feet. Except for the case where the damaged bundle is lying on the reactor pressure flange, there will be greater than 23 feet of water above the damaged bundle. For the bundle lying on the flange, at

~.

least 22'3" of water (23' - 8.1" bundle width per Reference 6.6.m) will be above the damaged fuel pin. Based on Reference 6.2.g, the use of the Regulatory Guide 1.25 dacantamination factors is acccotable for 22'3" of water.

Per Design Input 4.1.1, the activity profile modeled assumes that the iodine gap inventory is composed of 99.75 percent inorganic species (i.e., elemental and particulate iodme),

and 0.25 percent organic species (i.e., organic iodide). Per Design Input 4.2.1, the pool decontamination factors for the inorganic iodine and organic iodide species are 133 and 1, respectively. ' Ibis results in the following iodine activity inventories becoming airborne in the Containment:

lodine Species A B C AxB+C ,

Initial Pin Gap Fraction of rharaminatinn Airbome Activity Inventory (Ci) TotalIodine Factor (Ci)

I 131 elemental 210 0.9975 133 1.575 I 131 organic 210 0.0025 1 0.525 I-133 elemental 55.6 0.9975 133 0.417 I-133 organic 55.6 0.0025 1 0.139 I 135 elemental 0.347 0.9975 133 0.0026025

~

I-135 organic 0.347 0.0025 1 0.0008675 S.2 Contrd Room Intake and Redmdation Ef5dendes Design Input 4.4.2 lists the removal efficiencies for the Control Room EVS and EAC filter units. Per drawings 40096 (Reference 6.6.1) and 40098 (Reference 6.6.j), the makeup air entering the Control Room passes through both the EVS and EAC filter trains.

However, per Design Input 4.4.2 credit is only taken for the EAC charcoal filter, which

NES&L DEPARTMENT CALCULATION SHEET ICCN No./

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l

. Sulliect Fuel Handfino Aaewnt FHA) Inside Centebswi,61 - Control Room and Offsite Doses Sheet No. 38 :

MV oRIGMaToR DaTE WIE DaTE REV ORIGNaTom DATE plE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h contains a total of 2 inches of charcoal. De recirculation air passes only through the EAC filter train, which contains a total of 2 inches of charcoal. Per Regulatory Guide 1.52 (Reference 6.4.c) this results in the following elemental and organic iodine removal efficiencies for the LOCADOSE intake and recirculation filters.

Item Being EVS Removal EAC Filter LOCADOSE LOCADOSE Removed Efficiency Efficiency Retawal M d adon Efficiency Removal Efficancy Elemmtal Iodine 0% 95 % 95 % 95 %

Organic Iodide 0% 95 % 95 % 95 %

Particulates 0% 99 % 99 % 99 %

8.3 CR Radiation Monitor Trip Initiation Ttrne l

To ensure that the trip initiation time remains valid for assemblies which have significant '

decay (such a fuel assembly being reloaded after being stored in the SFP for a cycle), this analysis will be based only on the Kr-85 activity present. The ContaPanent activity concentration leaking from the Containment is taken as the Kr-85 acuvity diluted in the Containment volume. De activity concentration at the Control Room outside air intake is l I

the Containment concentration reduced by the effect of atmospheric dispersion. The Kr-S5 activity (per Design Input 4.1.1) and the d' sign basis x/Q (per Design Input 4.8) and the Containment characteristics (per Design Input 4.3) will be used: l AesM%mu,,,, = AesMry Jteleased hem Cont u dQcam er a

^**M%m , Kr-85 C%drin , y , gq

)6siedpin Cent Volume AesM a n, 29.2 Ci $

, , 32000A , 3.1x10-'aec , min ,10' pCyc

3sdpin 1A22x10 As 8 min as 60 esc s 10'em'/m C' " . S.1x104 *O MindPin em' Raennae the sample points for the CR radiation monitors are downstresn of where the outside air and recirculation air combine, the activity concentration in the duct will be less than the activity in the outside air line. The nominal normal HVAC flowrates (per Design

.y -

NES&L DEPARTMENT CALCULATION SHEET M No/

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CCN No. CCN -

. Subject Fuel "ead;as Accident (FHA) Inside Cc61 ;rinent - Control Room and Offsite Doses Sheet No. . 39 MV ORIGodaToM DATE flE DATE REV ORIOedAToR DATE flE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28 94 , y s l I Input 4.4.3) will be used to model this dilution effect. 'Dds results in the following Kr-85 concentration at the radiation monitor sample location:

5820efn 8.7x10-s pegf,,s g,4gg,jg., pCyd p W , (5520& + 29885&) Miedp n piedpin Using the number of failed pins (per Assumption 3.11) and the detector Kr-85 efficiency (per Design Input 4.4.6) results in the following detector reading:

1.418x10-s pcgfe,s ##"

236 Mied A x pied pin x = 94@ ep 3.ssx10 a pCilem' Per Design Input 4.4.6, the trip initiation time corresponding to a step change of 94,000 cpm is about 0.4 seconds.

8.4 Control Room Isolation Time Due to the location of the radiation monitors and isolation dampers, contaminated air will enter the Control Room via the normal HVAC system for some period of time at the beginning of the FHA. 'Ihe time period is equal to the following:

time needed to travel to the radiation monitor time needed for the radiation monitor to initiate the isolation signal time needed for the isolation dampers to close Further detail on each of these cose contributo s are:

a. The time needed to travel to the radiation monit. r is 6.2 seconds (per Design Input 4.4.6),

b. Per Section 8.3, radiation monitor trip initiation time is 0.4 second.

c.1he damper closure time is 6 seconds per Assumption 3.7.

Therefore, the total isolation time is 6.2 + 0.4 + 6 = 12.6 seconds. To provide margin f in this analysis, and to not require a restrictive CRIS response time, a value of 3 minutes (0.05 hrs) will be conservatively modeled in the IDCADOSE runs.

NES&L DEPARTMENT !

CALCULATION SHEET ICCN No./

PREUM. ccN No.

i PAGli_ oF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-005 CCN CONVERSION:

ccN No. CCN ~

. Subject Fuel Handlina Accident (FHA) In*W Cc61.'rir.er,; - Control Room and Offsite Doses Sheet No. 40 !

REV ORONaTOR DATE IRE DATE REV ORO NATOR DATE 1RE DATE R j 1 R. Nakano 02 24 94 T. Remick 02 28 94 h ;

S l

1

)

8.5 LOCADOSE Code Time Steps "Ibe time steps entered into the LOCADOSE Code were chosen to model the times at which parameters important to the analysis are changed (e.g., HVAC changes). While the l accident ends at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per Regulatory Guide 1.25, the analysis will go until 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to !

ensure that all of the activity is removed from the Containment (due to the exponential l equation used in determining the Containment exhaust flowrate in Design Input 4.3.3). l This also ensures that the activity entering the Control Room has had sufficient time to j 4

either be exhausted back to the environment, decay, or be removed by the recirculation filters.

l l

Time Step Significance of the Time Step event) 1 0 hrs

Begmmng of FHA event 0.05 hr Control Room HVAC transfers from Normal to Emergency Mode l 0 minutes)

I hr Time step for CR HVAC shine dose analysis 1 2 hrs End of EAB analysis 8 hrs End of analysis

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of decay occur prior to the start of the accident (per Assumption 3.1) .

l 8.6 CR HVAC Intake filter Direct flowrote From Containment !

As discussed in Section 5.5, an equivalent unfiltered flow rate from the Containment (LOCADOSE Node 2) to the CR HVAC Intake Filter (Node 3) can be determined as .

follows: .

1 Orferc , = Ac Mry ConeatCAOussideAirAsante x CAfass&cF&mnase Curierm,m = Ac:Mry rh From Cost x yJQ%a x CR Aurake F&mnase Cur % . w , % = x Cent Edomst Flowrase x g/Q x CR fasske Fkunsre i

p

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

NES&L DEPARTMENT e .

CALCULATION SHEET 'c=l ,

Project or DCP/Mh1P SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSloN:

ccN No. CCN -

. Subiect Fuel Handhna Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 41 REV ONG8daToR DaTE N DaTE REV ONOWaToR DaTE WIE DaTE R 1 R.Nakano 02 24 94 T. Remick 02 28-94 4

Since IDCADOSE determines the Pin Activity / Containment volume, the direct Containment to CR Intake filter (Node 3) flowrate would be as follows:

Mowreare,,,,m = Coat E.rhaast Mowrare x g/Q x CA IsraAe Meweste Beanne the purpose of this flowrate is to determine the activity buildup in one EVS filter, a flowrate of 2200 cfm (per Design Input 4.4.3) will be used for the CR intake flow.

Based on the 0 to 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months CR x/Q of 3.le-3 sec/m3(Design Input 4.8), the equivalent unfiltered flowrate with a Containment exhaust flowrate of 82000 cfm (Design Input j 4.3.3) is as follows:

8 s 8

)

see

% , 82000A ,(3.1x10-s min , 0.02832 m ) x 2200 A )

min as 60 see A 8 min M*"'88'c.= a, me s = 264 cfn Modelling the flow into Node 3 in this manner slightly reduces the flow from the Containment (LOCADOSE node 2) into the environment, and thus the resulting doses.

This reduction is equivalent to the reduction in flow, or (264 cfm + 82000 cfm) x 100%

= 0.3%. Based on ecgineering judgement, this impact is negligible.

8.7 Integrated Activity Release The integrated activity released from the Containment following the damage of one fuel pin is the sum of the activity released in each time interval. The LOCADOSE output for the case whett the CR HVAC system is in the Normal mode at the beginning of the accident, and then isolates on high radiation, will be used as the source of the activity.

'Ihis IDCADOSE run was used since this represents the normal configuration. However, since this analysis is only concerned with what activity is released from the Containmaat, CR isolation is not of concern. 'Ibe activity released in each time interval is:

NES&L DEPARTMENT j CALCULATION SHEET ICcN W PREUM. CCN No. PAGE_ of_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CcN CONVERSION:

CCN No'. CCN -

Subject Fuel Handlina AceAnt FHA) Inside Cc6ter,rr rit - Control Room and Offsite Doses Sheet No. 42 REV OMONaToR DaH RE DaTE REV ORIONaToR DATE IRE DATE R {

1 R. Nakano 02 24 94 T. Remick 02 28 94 4

l 38080Pc Contamment Curies Released For Interval (LOCADOSE File fha cont.to):

O to 3 minutes 3 minnteeto 1 bour 1 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Total I-131 3.336e 01 1.693e+00 6.344e-02 2.051e-03 2.092e+00 I- 133 8.825e 02 4.443e 01 1.618e-02 5.076e-04 5.492e-01 l I-135 5.498e-04 2.714e 03 9.233e-05 2.689e-06 3.359e-03 !

KR-85 4.639e+ 00 2.357e+01 8.861e-01 2.876e-02 2.912e+01 XE131M 5.687e-01 2.887e +00 1.083e-01 3.506e-03 3.568e +00 XE133M 8.131e +01 4.116e +02 1.528e + 01 4.892e-01 5.087e +02 XE-133 1.710e+00 9.30le+00 4.332e-01 1.695e-02 1.146e+01 XE-135 1.156e+00 5.751e+00 2.011e 01 6.033e-03 7.114e+00 XE135M 5.261e-06 2.053e-04 1.504e 05 4.619e-07 2.261e-04 CS-135 7.518e-13 4.653e-11 7.407e-12 4.255e-13 5.511e-11 Total 8.981e +01 4.552e+02 1.699e +01 5.470e-01 5.625e+02

8.8 SOURCE 2 Code Multiplier For Outside Cloud Dose To simplify the mathematics and future interpretation of this calculation, use will be made of the SOURCE 2 scaling factor input parameter. Specifically, the time integrated activity releases per Section 8 7 will be scaled by the atmospheric dispersion factor (expressed in ;

consistent units) to determine the integrated activity atmospheric concentration at the Control Room location. With the SOURCE 2 input parameters established in this manner, use of the SOURCE 2 output in the SHIELD-SG code will result in integrated outside cloud shine doses for the Control Room. 'Ihe atmospheric dispersion factor used will be the 0 to 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Containment to CR x/Q per Design Input 4.8.

l

= Ac:Mrymono (CD x Mdqpher ( ,)

- j Melqpuer = 1 ("') x I x I"

Qms woo see 1x10' cm8 g , , 3.1x10-8sec , 1 Ar , 1m8

= 8.6111x10'18 8

m 3600 see 1x108 cm8 cm 8 l

l

NES&L DEPARTMENT CALCULATlON SHEET ICCN W rReuw. eCN No. race _ or_

, Project or DCPMMP SONGS 2&2 Calc. No. N 4072 003 CCN CoNVERSloN:

CCN No'. CCN -

0 Subject Fuel ;; dias Accident FHA) Insh Centehmen; - Control Room and Offsite Doses Shoot No. ,_L),,_,

MV oRIGedaToR DaTE WIE DaTE MV oRIGedaToR DaTE WIE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94

'Ibe SOURCE 2 input file is shown in Section 9.3.1, and the SOURCE 2 output file is shown in Section 9.6.1.

8.9 SOURCE 2 Code Multiplier For CR HVAC F11ter Shine Dose To simplify the mathematics and future interpretation of this calculation, use will be made of the SOURCE 2 scaling factor input parameter. Specifically, the filter activity will be directly entered into the SOURCE 2 Code, and a conversion factor of 1/ filter volume (expressed in cm-3) will be entered separately as a scaling factor. To determine the source strength on a per unit volume basis, a scaling factor equal to 4.8225e-6 cm 3 (per Design !

Input 4.4,6) was used.

'Ibe SOURCE 2 input file is shown in Section 0.3.2, and the SOURCE 2 output file is shown in Section 9.6.2.

8.10 SMF1D-SG Model For Outside Cloud Dose Body I will represent the box of contaminated air surrounding the Control Room. Based on engineering judgement, the gamma rays emitted from locations that are farther than approximately five mean free paths from the Control Room will not significantly contribute to the Control Room dose. This is due to the attenuation that occurs in five mean free paths.

Per Table II.4 of the textbook Introduction to Nuclear Enrineerine (Reference 6.9), a 2

one MeV gamma ray has a mass attenuation coefficient (p/p) of 0.0636 cm /g in air of 3

density (p) 1.293e 3 g/cm . Therefore, the mean free path of a one MeV gamma ray is approximately:

M a aarr ,

E-xp i 9

, 0.01 m/cm 0.0636 cm*/g x 1.293E-3 g/cm 3

= 122 aukrz 122 meters x 3.28 ft/m = 400 ft. 'Iberefore, five mean free paths will be 2000 ft. To

{

mnservatively encompass all the activity that will contribute to the Control Room dose, Body I will be a box that will extend approximately 3000 feet from the sides of the 1 1

i

NES&L DEPARTMENT CALCULATION SHEET ICCN Nol PRELIM. CCN No. PAGE ,_ oF,,_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CoNVERStoN.

CcN No. CCN -

, Subject Fuel Handlino Acekfent FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 44 REV ORIONaToR DaTE WIE DaTE REV ORIONaToR DaTE RE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h 4

Control Room walls and the Control Room ceiling. His surrounding air volume will only go 21 feet below the Control Room, since the lowest level of the plant is at elevation 9 feet per Drawing 10115 (Reference 6.6.b) and the Control Room is at elevation 30 feet (Design Input 4.4.4). His contaminated air will also be modeled as filling the rooms on elevations 9,50 and 70, since these areas are not served by the Control Room HVAC system.

Dr. source strengths entered into the SHIELD-SG model are from the SOL'RCE2 output given in Section 9.6.1. For modeling purposes, the Z-axis will be plant elevation. The X-axis runs North and South and the Y-axis runs East and West. De origin of the co-ordinate system used is at the plant elevation zero and at the outside surface of the North-West corner of the Control Room.

Body h Air Surroundinn ne Control Room his is the region containing the contaminated air. His body has the following characteristics:

Geometry: Box X-Coordinate: -3000 feet (Section 8.10)

X-Distance: 6300 feet (Section 8.10 and Design Input 4.4.4)

Y-Coordinate: -3000 feet (Section 8.10)

Y-Distance: 6200 feet (Section 8.10 and Design Input 4.4.4)

Z-Coordinate: 9 feet (Section 8.10)

Z-Distance: 3100 feet (Section 8.10 and Design Input 4.4.4)

Material: SOURCE Density 1.12e-03 gm/cm3 (Assumption 3.5) 4

NES&L DEPARTMENT CALCULATION SHEET ICCN NCU PREUM. CCN No. PAGE_ oF_

Projett or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CoNVERsCN; cCN No. CCN -

. Subject Fuel Handfina Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. _45 __

REV ORIGedATOR DATE stE DATE REV ORIGedAToR DATE stE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 4

Body 2: Contaminated Air Inside Elevation 9 This is the region representing the inside of the rooms on elevation 9, which are filled with contaminated air, since these rooms are not served by the CR HVAC system.

' Ibis body has the following characteristics:

Geometry: Box X-Coordinate: 2 feet, 6 inches (Design Input 4.4.5 and Section 8.10)

X-Distance: 216 feet, 6 inches (Design Input 4.4.4)

Y-Coordinate: 2 feet,6 inches (Design Input 4.4.5 and Section 8.10)

Y-Distance: 116 feet, 9 inches (Design Input 4.4.4)

LCoordinate: 9 feet (Reference 6.6.b and Section 8.10)

LDistance: 20 feet (Design Input 4.4.4)

Material: SOURCE Density 1.12e-03 gm/cm3 (Assumption 3.5)

Body 3: Contaminated Air Inside Elevation 50 This is the region representing the inside of the rooms on elevation 50, which are filled with contaminated air, since these rooms are not served by the CR HVAC system. This body has the following characteristics:

Geometry: Box X-Coordinate: 2 feet,6 inches (Design Input 4.4.5 and Section 8.10)

X-Distance: 216 feet, 6 inches (Design Input 4.4.4) )

Y-Coordinate: 2 feet, 6 inches (Design Input 4.4.5 and Section 8.10) l Y-Distance: 116 feet, 9 inches (Design Input 4.4.4)

LCoordinate: 50 feet (Reference 6.6.b and Section 8.10)

LDistance: 19 feet (Reference 6.6.b and Design Input 4.4.4)

Material: SOURCE Density 1.12e-03 gm/cm3 (Assumption 3.5) 1 4

NES&L DEPARTMENT CALCULATION SHEET ICCN No./

PREUM. CCN No.

PAGE_ oF_

Preiset or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN No'. CCN -

Sutlioct Fuel Handlina Acehnt (FHA) Inside Containment - Control Room and Offsite Danes Sheet No. 46 IWV OfuGNAToR DATE 5lE DaTE fEV OfuGNATOR DATE flE DATE R 1 R. Nakeno 02 24 94 T. Remick 02 28 94 h i

Body 4: ContaminataA Air Inside Elevation 70 This is the region representing the inside of the rooms on elevation 70, which are filled with contaminated air, since these rooms are not served ley the CR HVAC system. 'Ihis body has the following characteristics:

Geometry: Box X-Coordinate: 2 feet,6 inches (Design Input 4.4.5 and Section 8.10)

X Distance: 216 feet, 6 inches (Design Input 4.4.4)

Y-Coordinate: - 2 feet, 6 inches (Design Input 4.4.5 and Section 8.10)

Y-Distance: 116 feet, 9 inches (Design Input 4.4.4) l Z-Coordinate: 70 feet (Reference 6.6.b and Section 8.10) l Z-Distance: 14 feet (Reference 6.6.b and Design Input 4.4.4)

Material: SOURCE Density 1.12e-03 gm/cm3 (Assumption 3.5)

Body 5: Air In Ide The Control Room

Ihis is the region representing the inside of the Control Room. ' Ibis body has the l following characteristics: l Geometry: Box X-Coordinate: 2 feet, 6 inches (Design Input 4.4.5 and Section 8.10)

X-Distance: 216 feet, 6 inches (Design Input 4.4.4)

Y-Coordinate: 2 feet,6 inches (Design Input 4.4.5 and Section 8.10) -

Y-Distance: 116 feet, 9 inches (Design Input 4.4.4)

Z-Coordinate: 30 feet (Design Input 4.20 and Section 8.10)

Z-Distance: 19 feet (Design Input 4.4.4)

! Material: Air Density: 1.18e-03 g/cm3 (Assumption 3.5) l i

l

NES&L DEPARTMENT CALCULATION SHEET lCCN No./

PREUM. CCN No.

1 PAGE_ oF_ l Project or DCP/MMPJONGS 2&3 Calc. No. N-4072-003 CCN CoNVERsloN:

CCN No'. CCN -

. Subject Fuel Handrino Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 47 _

MV OfuGNAToR DATE stE DATE REV OfuGNAToR DATE NtE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h i

Body 6: Auxillary Buildine Concrete Wam This is the region representing the walls of the Auxiliary Building. This body has the following characteristics:

Geometry: Box X-Coordinate: 0 feet (Design Input 4.4.5 and Section 8.10)

X-Distance: 221 feet, 6 inches (Design Input 4.4.4 and 4.4.5)

Y-Coordinate: 0 feet (Design Input 4.4.5 and Section 8.10)

Y-Distance: 121 feet,9 inches (Design Input 4.4.4 and 4.4.5)

Z-Coordinate: 9 feet (Design Input 4.4.4 and Section 8.10)

Z-Distance: 76 feet (Reference 6.6.b)

Material: Concrete Density: 2.35 g/cm' (Assumption 3.4)

Dose Points Due to geometry considerations, the dose to a Control Room Operator will vary as a function of the location within the Control Room. Therefore, dose points will be located in center of the control room and adjacent to (6 inches away from the wall surface) the center of each Control room inner surface (i.e., walls, floor, and ceiling).

The dose present anywhere else within the Control Room should not exceed the most severe dose realized at one of these seven locations. The six inch separation distance is arbitrary, and reflects an assumption that an operator will rarely be in actual contact with the surface.

Ihe coordinal 4 for each dose point are shown in the following table. Concrete is used as the buildup factor for each dose point, since that is the last material that significantly attenuates the gamma rays prior to the dose points.

NES&L DEPARTMENT CALCULATION SHEET 'ccN Nos PREUM. CCN No. PAGE_ oF_

Praiset or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERStoN:

CCN No. CCN -

. Subject Fuel Handlina Aceldent (FMA) Insh Containment - Control Room and Offsite Doses Sheet No.._(R_

REV ORIGMATOR DATE WIE DATE REV ORIONATOR DaTE ftE DATE R 1 R.Nakano 02 24-94 T. Remick 02 28-94 h Deee Poim X Coordame Y Coordane Z Coor&ame Descripdoe

, 1 110'9" 60'10.5" 39'6" Control Room Center 2 3'0" 60'10.5" 39'6" Center of Control Room North Wall 3 218'6" 60'10.5" 39'6" Center of Control Room South Wall 1

4 110'9" 118'9" 39'6" Center of Control Room East Wall 5 110'9" 3'0" 39'6" Center of Control Room West Wall 6 110'9" 60'10.5" 48'6" Just Below Control Room Ceiling 7 110'9" 60'10.5" 30'6" Just Above Control Room Floor 8.11 CR HVAC Miter Shine Dose Per Design Input 4.4.7, the CR HVAC Intake filter shine SHIELD-SG dose model )

developed for calculation N-4060-016 revision 1 (Reference 6.1.g) is used as the basis for the filter shine analysis for this calculation. As shown in section 9.7.2, use of this model and the FHA source tenn results in the highest dose rate being 2.26e-06 Rem /hr (per failed pin) at Dose Point 2 (which is the same location as N-4060-016 Dose Point 10).

The N-4060-016 dose rates for this same location (Dose Point 10) are as follows per Design Input 4.4.7:

.Ilgte Dose Rate (Rem /hr) 0.2 hr 8.18e-03 0.5 hr 9.64e-03 1 hr 9.76e-03 2 hr 9.48e-03 3 hr 9.20e-03 4 hr 9.08e-03 The 30 day operator dose is equal to spending some period of time at the 1 bour dose rate. In calculation N-406(M)16, this duration is:

Equtualent durnston =

= 66.6 kr 9.76x10 Jtem/kr i

Since the Calculation N-4060-016 release occurs for 30 days, using the equivalent duration l detennined above is conservative for the FHA. 'Ihis is hennae after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months the FHA release ends, resulting in no " fresh" radioactive material being added to the filter. Note l

NES&L DEPARTMENT CALCULATION SHEET 'cc"

rRau. CcN No. raae_ ov_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CoNVERSloN:

CCN No. CCN -

, Subject Fuel Handlina Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 49 MV OIDGMAToR DATE WIE DATE IEEV OfuGNAToR DATE 5tE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h that the filtc: shine dose period for the FHA exceeds the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months release duration, since material trapped on the filter Continues to serve as a shine source after the release ends.

'Ihus, the FHA filter shine dose is estimated to be:

ca svAc shine pose . 2M0* ^= , sg.s y ,1Mo* M Ar-Mi*drin pied rin i

e l

l l NES&L DEPARTMENT i ICCN NO./

CALCULATION SHEET L

PREUM. CCN No. PAGE oF _

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CoNVERSloN:

CCN NCI. CCN -

. Subloct Fuel Hand'ina Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. ._50_

my omoseafoR DaTE WIE DATE REV cRMNaToR DaTE WIE DaTE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h 8.12 Doses Due to Release From One Pin NO'IE: These doses, while listed for one pin, are based on trip initiation times that were determined for the design basis Case with 236 failed pins. 'Ihese results may not be vdd for any FHAs that result in less than 236 failed i

Pns.

8.12.1 With Control Room Isolation on High Radiation When Control Room isolation occurs, the doses due to the release from one damaged fuel pin are as follows, based on the computer output given in Sections 9.5,9.6 and 9.7. The outaide Cloud shine dose for the dose points 1 and 7 (CR Center and just above the CR floor)is given, as those are the locations of the highest dose.

CR HVAC in Normal at Start, Isolates on High Radiation

)

Dose Contributor (Palentation Secuan) CR Done (Rem) EAB Dose (Rem) LPZ Dose 3 (Rem)

THYROID DOSE:

Immersion / Inhalation Dose (9.5.2) 8.28e-2 3.08e-1 8.75e-3 BETA-SKIN DOSE:

homersion/Inhalariou Dose (9.5.2) 5.74e-2 4.88e-3 1.39e4 WHOLE BODY DOSE:

hamersion/ Inhalation Dose (9.5.2) 8.34e-4 1.32e-3 3.75e-5 Omide Cloud Shine Dose (9.7.1) 2.40e-6 NA NA CR HVAC Fiher Shine Dose (8.11) 1.51e-4 NA NA cantaiarnear Shine Dose (5.6) 0 NA NA Total Whole Body Dose 9.87c-4 1.32c-3 3.75e-5 i

NES&L DEPARTMENT CALCULATION SHEET IcCN No./

PREUM. CCN No. PAGE__, oF ,,,,,

Project or DCP/MMP SONGS 2&3 Calc. No. N 4072 003 CCN CoNVERalON:

CCN No'. CCN -

. Subject Fuel Handlino Accident FHA) Inside Costeinment Control Room and Offsite Dames Sheet No. j,1,_

MV oftGelaToR DaTE WlE DaTE REV ORIGStaToR DaTE flE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 i

8.12.2 Without Control Room Isolation No isolation of the Control Room HVAC system occurs, resulting in no operation of the CR Intake or Recirculation filters. De lack of operation of the CR Intake filter means that it is not a shine dose contributor in this case. He doses due to the release from one pin are as follows, based on the computer output given in Sections 9.5,9.6 and 9.7. He outside cloud shine dose for the dose points 1 and 7 (CR center and just above the CR floor) is given, as that is the location of the highest dose.

CR HVAC in Normal at Start, No Isolation Occur Dose Contributor (Calculation Section) CR Dose (Rem) EAB Dose (Rem) LPZ Dose (Rem)

THYROID DOSE:

Immersion / Inhalation Dose (9.5.3) 3.51 3.09e-1 8.77e 3 BETA SKIN DOSE:

Immersion / Inhalation Dose (9.5.3) 5.53e-2 4.89e-3 1.39e-4 WHOLE BODY' DOSE: !

Immermon/ Inhalation Dose (9.5.3) 8.45e-4 1.32e 3 3.76e 5 Outside Cloud Shine Dose (9.7.1) 2.40e-6 NA NA CR MVAC Fiher Shine Dose (8.11) 1.51e 4 NA NA -

re' he Shine Dose (5.6) 0 NA NA Total Whole Body Dose 9.98e-4 1.32e 3 3.76e-5 Note that the CR thyroid dose for the failure of one pin is 3.5 Rem. This will give a design basis (failure of 236 pins) dose of 826 Rem. His egceeds the 30 Rem CR thyroid dose criterion, and thus means that a Control Room isolation on high radiation is required for this accident.

NES&L DEPARTMENT CALCULATION SHEET ICCN W PRELIM. CCN NO. PAGE_ 0F_

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CCN No. CCN -

, Sutiject Fuel Handlina Accident FHA) Inside Containment - Control Room and Offsite hes Sheet No. ft2_.

MV oRio9dAToR DATE WIE DATE REV oRIGs4AToR DATE 5tE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h 4

S.13 Design Basis Case Doses NOTE: Dese doses are based on trip initiation times that were determined for the design basis Case with 236 failed pins. Dese results may not be valid for any FHAs that result in less than 236 failed pins.

De following accidents use the design basis parameters, and have the resulting doses, he number of fuel pins that fall are given in Assumption 3.11. The single pin doses are from Section 8.12.1.

Table 8.131 Design Basis Cases - Control Room Isolates at High Radiation Signal Location Single Pin Dose Design Basis Case (Rem)

Pins Failed Dose (Rem)

CR:

Thyroid 8.28e-02 236 19.5 Beta Skin 5.74e 02 236 13.5 h ic Body 9.87e-04 236 0.2 EAB:

Thyroid 3.08e 01 236 72.7 Beta Skin 4.88e-03 236 1.2 h ie Body 1.32e 03 236 0.3 IEZ:

7hyroid 8.75e-03 236 2.1

Beta Skin 1.39e-04 236 <0.1 Whole Body 3.75e-05 236 <0.1 l

l l

l

l NES&L DEPARTMENT CALCULATION SHEET ICCN NN PREUM. CCN No. PAGE_ oF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CoNVERSloN:

CCN No'. CCN -

Subject Fuel Handlina Acendent (FHA) In=W Cerit-lr.cr w, Control Room and Offsite Doses Sheet No. .,,,,52 ,,,,,,

MV ONOMATOR DATE WlE DATE REV ONONATOR DATE WlE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h

4 9.0 COMPUTER PROGRAM INPUT AND OUTPUT FILES Dis Section presents the Computer Code input files. Section 9.2 presents the LOCADOSE files, Section 9.3 presents the SOURCE 2 files and Section 9.4 presents the SHIELD-SG files.

i 9.1 Mies Created During This Analysis LOCADOSE FILES i I

Library File FMA, CONT LIB 3056 09-06-93 2:13p CR HVAC Starts in Normal Mode. Isohten on Hinh Radiation FNA CONT Tl 1542 12-23-93 9:34a M CONT DI 506 12 13-93 3:40p M CONT 70 19935 12-23-93 1:47p M CONT D0 15601 12 23-93 1:47p CR HVAC Starts in Normal Mode and Never Isolates FMA CONI DI 496 12-13-93 3:41p M CON 1 Tl 1106 12-13-93 3:40p M CONI 00 14931 12-13 93 3:50p FMA] CON 1TO 14361 12-13-93 3:50p SOURCE 2 FILES Control Room Outside Cloud Shine Dose FMA CLD $1 555 12-23 93 2:27p I M ,CLD $0 3474 12-23 93 2:29p l

Control Room HVAC Filter Shine Dose FMA A206 $1 2231 12-23-93 2:27p M ,A206 So 13696 12-23-93 2:29p I

SHIELD.SG FILES Control Room Outside Cloud Shine Dose SM CLD IN 3192 12-23 93 2:350 SH[CLD OUT 7314 12-23-93 2:37p Control Room HVAC Filter Shine Dose SH

~ A206 IN 3564 12-27-93 10:23a SM,A206 0UT 6896 12-27-93 10:26e

NES&L DEPARTMENT CALCULATION SHEET ICCN W PRELIM. CCN No. PAGE _ OF_

Project or DCP/MMP_ SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION: l CCN No'. CCN -

Subject Fuel Handlina Accident FHA) In=Me Containment - Control Room and Offsite Dames Sheet No._Iti_

MV OfBGs4ATOR DATE BIE DATE REV OR1054ATOR DATE 5tE DATE R 1 R. Nakano 02-24 94 T. Remick 02-28 94 4

l 9.2 LOCADOSE Code Input FUes l l

MJ IACADOSE Library File Vocalon 1.0 Thyroid Lung tone tota Skin lAote body I--1312.508E+04 9.976E-071.490E46 2.073E+04 3.150E43 3.170E42 8.720E-02 1 1 11 0 000 0 1.100E42 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1 1.81TE-01 3.789E-01 I-1312.508E+04 9.976E-071.490E+06 2.OT3E+04 3.150E+03 3.170E42 8.T20E-02 2 1 11 00 00 0 1.100E-02 0.000E40 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2 1.81TE-01 3.789E-01 1-1312.508E+04 9.976E-071.490E+06 2.073E+04 3.150E+03 3.170E-02 8.720E-02 3 1 11 0 00 0 0 1.100E-02 0.000E40 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3 1.81TE-01 3.789E-01 !

1--133 5.622E+04 9.211E-06 2.690E45 5.064E+031.080E+03 T.350E-021.550E-01 1 -

21312 0 00 0 9.710E-012.900E-02 0.000E+00 0.000E40 0.000E+00 0.000E+00 4 4.06TE-01 6.04TE-01 I-133 5.622E+04 9.211E-06 2.690E+05 5.064E+031.000E+03 7.350E-021.550E 01 2 21312 0 0 0 0 9.710E41 2.900E-02 0.000000 0.000E+00 0.000E+00 0.000E+00 5 4.06TE-01 6.X TE-01 1--133 5.622E+04 9.211E 06 2.490E+05 5.064E+031.000E+03 T.350E-021.550E 01 3 21312 0 0 0 0 9.710E-012.900E-02 0.000E+00 0.000E+00 0.000E40 0.000E+00 6 4.06TE-01 6.04TE-01 1-135 5.103E44 2.912E-05 5.600E441.971E+03 3.350E+021.290E-014.210E-01 1 21415 0 00 0 8.450E-01 1.550E-010.000E+00 0.000E40 0.000E+00 0.000E+00 7 3.691E-01 1.61TE40 I-135 5.103E+04 2.912E-05 5.600E441.971E+03 3.350E421.290E-014.210E-01 2 2 14 15 0 00 0 4.450E-01 1.550E-010.000E+00 0.000E+00 0.000E+00 0.000E40 8 3.691E-01 1.61TE+00 1-135 5.103E+04 2.912E-05 5.600E+041.971E+03 3.350E+021.290E-014.210E-01 3 2 14 15 0 0 0 0 4.450E-01 1.550E-010.000E+00 0.000E40 0.000E+00 0.000E+00 9 3.691E-01 1.61TE+00 10t-45 4.102E42 2.054E-09 0.000E+00 2.410E+00 0.000E+00 4.246E-02 5.102E-04 4 000 0 000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0010 2.505E-01 2.236E-03 IE131M 2.595E+02 6.815E-07 0.000E+001.400E+00 0.000E+001.508E-02 2.899E-03 4 000 0 0 0 0 0.OODE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 11 0.000E+00 3.116E-03 IE133M 1.384E+03 3.663E-06 0.000E+001.890E+00 0.000E+00 3.150E-02 T.954E-03 4 1 13 0 00 0 0 1.WDE+00 0.000E+00 0.000E+00 0.000E40 0.000E+00 0.000E+0012 0.000E+00 2.332E-02 IE-133 5.622E441.528E-06 0.000E+001.570E+00 0.000E40 9.697E43 9.316E-03 4 l

00000 00 0.000E+00 0.000E+00 0.000E+00 0.OODE+00 0.OODE+00 0.000E40131.004E-012.997E-02 IE-135 5.563E44 2.115E-05 0.000E+00 4.050E40 0.000E40 5.894E-02 5.736E-02 4 1 14 0 0 0 0 0 1.000E+00 0.000E40 0.000E+00 0.000E+00 0.000E+00 0.000E+0015 3.028E-01 2.466E-01 RE135m 0.000E+00 T.380E-04 0.000E+00 2.220E+00 0.000E+00 2.253E-02 9.487E-02 4 1 14 0 00 00 1.000E+00 0.000E40 0.000E+00 0.000E+00 0.000E+00 0.000E+0014 3.000E-014.266E-01 CS-135 0.000E+00 7.449E-15 T.480E+031.57DE+031.440E+04 2.750E-03 0.000E+00 5 00000 0 0 0.000E40 0.000E+00 0.000E+00 0.000E40 0.000E+00 0.000E+0016 5.630E-02 0.000E+00 l

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN No.

l PAGE,,,,,, OF_

{

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CONVER$10N:

CCN No. CCN -

. Sutlject Fuel Handlina Accident FHA) Inside Containment - Control Room and Offsite Doses Sheet No. Jti IWV ORIGNATOR DATE WIE DATE REV ORIGMATOR DATE 5tE DATE R E i 1 R. Nakano 02-24 94 T. Remick 02 28-94 y ,

l 4 i I

W Activity Transoort - CR HVAC Isolata= on Hieh Radiation (fha Cont.ti) _

i FMA In Guntelnment, OL lealetes en High Rad (fhe

~

cent.tc)

RITA ledAND SONGS UNITS 2,5 18740-475 se472-005 1 1

2 4 16 1 1 0 )

1 00 0.00000E+00 0.00000E+00 2 0 0 l CFM CUFT CURIES 1 1 1 1 1 1 1 1 1 1 1 l 1 1 0 EImp3INNT A206/7 i

0. **WE+00 5.00000E-02 1 1 1 1

O 1 '

1.575 0 1 0.525 0 l 0 0 0.41T C 0.139 0 0 0 0.0026025 0 0.0008675 0 0 0 29.2 0

. 3.58 0 512 0 10.7 0 7.29 0 0 0 i 0 0 '

1.42200E+06 7.32 2 1 0 82000 0 0 0 0 0 0 0 0 0 0 0 33 1.0E+06 0 0 0 0 100 0 0 0 0 0 0 0 .

-1,0,0,0 '

-1,0,0,0 1 s.100000E-03 l 24439s 0 5a20 29ee5 5a20 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.00000E-02 1.00000E+00 1 1 1 1 00 0 21 0 81736 4 0 0 0 0 0 0 0 0 0 0 0 I 230 264 0 0 0 0 0 0 0 0 0 0 0 3 3 1.0E+06 0 0 0 0 100 0 0 0 0 0 0 0

-1,0,0,0

-1,0,0,0 1 3.100000E-03 744396 4400 to 59474 4410 M 95 99 0 99 99 99 99 99 0 0 M M M 0 M M M M M 0 0 1.00000E+00 2.00000E+00 1 1 1 0 0 0 0

-1,0,0,0

'L 7.100000E-03

l NES&L DEPARTMENT l CALCULATION SHEET ICCN NO./

PREUM. CCN No. PAGE_ OF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN No'. CCN -

Subject Fuel Handline Accident FHA) Inside Containment - Control Room and Offsite Doses Sheet No. _gg_,

i MV Of0GNATOR DATE flE DATE REV ORIG 0dATOR DATE WIE DATE R l 1 R. Nekano 02 24 94 T. Remick 02 28 94 h 1 l

2.00000E*00 8.00000E+00 1 1 1 0 000

-1,0.0,0 I

~1,0,0,0 0 3.100000E-03 W Dose Pronram - CR HVAC Isolates on Hieh Radiation (fha cont.di)

FNA In Contalement, Dt factates on High Rad (fha cent.do)

RITA h4KANO SONGS 181175 2,5 1t?40-475 h4072-005 1 1 !

00R*3F i

2 2 1 1 1 O O REM REN/MR

' 2.T200E-04 0.0000E+00 '

3.4700E-04 T.7200E-06 T.7200E-06 3.4700E-04 2.0000E+00 8.0000E+00 A.0000E+00 1.0000E+00 1.0000E+00 1.0000E+00 l 3.4700E-04 1.0000E+00 3.4700E-04 l 1.0000E+00 3.4700E-04 8.0000E+00 8.0000E+00 1.0000E+00 1.0000E+00 1.0000E+00 l

W Activity Tranmort - CR HVAC Does Not Isolate (fhn con 1.ti) _

FNA In cantainment, No Ot !aolation (fha, cont.tol RITA h4KAND SONOS 1811T5 2,3 18740-475 e6072-003 1 1

2 3 in 1 1 0 00 0.00000E+00 0.00000E+00 200 CFM Curf Cast!ES 1 1 1 1 1 1 1 1 1 1 1 1 1 0 CENTA!19ff A206/T 0.00000E+00 1.00000E+00 1 1 1 1 l 1 0 1 '

1.575 0 0.525 0 0 0 0.41T 0 1 0.139 0 i 0 0 l 0.0026025 0 0.0000675 0 I

NES&L DEPARTMENT CALCULATION SHEET 'cc"

PREUM. CCN No. PAGE_ 0F_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN No. CCN -

c Sutdeet Fuel Handfino Accident FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 12_

IEV ORIONATOR DATE BIE DATE MV OR10MATOR DATE 5tE DATE R l 1 R. Nakano 02 24 94 T. Remick 02 28-94 h I l

S l

0 0 29.2 0 3.58 0 512 0 10.7 0 T.29 0 0 0 0 0 j 1.42200E+06 T.32 <

21 0 82"J 0 0 's 0 0 0 0 0 0 0 0 33 1.0E+06 0 0 0 0 100 0 0 0 0 0 0 0

-1,0,0,0

-1,0,0,0 1 3.100000E-03 1 244396 0 5820 29685 5820 l 0 0 0 0 0 0 0 0 0 0 0 l 0 0 0 0 0 0 0 0 0 0 0 1.00000E+00 2.00000E+00 1 1 1 0 I O O O I l -1,0.0,0

-1,0,0,0 ;

0 3.100000E-03 1 2.00000E+00 8.00000E+00 1 1 1 0 0 0 0

-1,0,0,0

-1,0,0,0 0 3.100000E-03 i

W Dose Pronram - CR HVAC Does Not Isolate (fha Con 1.di)

FMA In Contaltunent, Ito CR ! solation (fhe,, con 1.do)

RITA leMAfs0 SONGS IAtITS 2.5 18740-475

4072-005 1 1

DDRODr 4 2 2 1 1 1 0 0 l REM REM /NR 2.T200E-04 0.0000E+00 3.4700E-04 7.T200E-06 7.T200E-06 3.4700E-04 2.0000E+00 8.0000E+00 8.0000E+00 1.0000E+00 1.0000E+00 1.0000E+00 3.4700E-04 1.0000E+00 3.4700E-04 1.0000E+00 3.4700E-04 8.0000E+00 8.0000E+00 1.0000E+00 1.0000E+00 1.0000E+00 l

i

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN NO. PAGE.,_ OF._,

Project or DCP/MMP SONGS 2&1 Calc. No. N 4072 003 CCN CONVERSION:

CCN NO. CCN -

Subject Fuel Handlina Accident (FHA) Inside Cent.1 T ,.nt - Control Room and Offsite Doses Sheet No. _,ftg_,,,

IEV ORIGNATOR DATE WIE DATE IWV ORIGNATOR DATE 51E DATE R 1 R. Nekano 02 24 94 T. Remick 02 28 94 h 4

4 9.3 SOURCE 2 Code Input Mies l

111 Oitside Cloud Shine Ir. nut File (fha cid.si) l SOUR h4072-03 1 RITA NAKAN0 SONG $ UNITS 2,5 18740-475 FMA In Contairment - CR Gutside Shine Dose INTESAATED ACTIVITY AT 8 MRS AFTER START OF ACCIDENT l 10 11 0 1 0 1 4.6111E-13 .00000E+00 .00000E+00 l

I--131 2.092E+00 I--133 5.492E-01 1-135 3.359E-03 10t--85 2.912E+01 IE131M 3.568E+00 l IE133M 5.06TE+02 RE-135 1.146E+01 IE-135 7.114 E+00 IE135M 2.261E-04 CS-135 5.511E-11 112 Control Room HVAC Intue Filter Shine Inout File (fha a206.si) _

Solst h4072-03 1 RITA NAKAN0 SONGS UNITS 2,5 18740-475 FMA in Cont-A206/7 Source Strength From FMA CONT.70 Activity at 5.0000E-02 hours for node 3 (A256/T) 10 11 0 0 0 0 48225E-05 .00000E+00 .00000E+00 I--131 5.320E-30 i 1--133 4.485E-32 '

I--135 9.188E-35 l KR--85 0.000 IE131M 0.000 .

IE133M 0.000 IE-135 0.000 l

IE-135 0.000 IE135M 0.000 CS-135 3.920E-19 l Sour e6072-03 1 RITA h4KAND SONGS UNITS 2,5 18740-475 ;

FNA in Cent-A206/T Source Strength From FMA CONT.T0 '

Activity at 1.000 cars for node 3 (A206/7)~

10 11 0 0 0 0 48225E-05 .00000E+00 .00000E+00 I - 131 5.455E-03 I--133 1.402E-03 I--135 8.144E-06 KR--85 1.247E-09 IE131M 1.526E-10 IE133M 2.158E-08 IE-133 5.813E 10 IE-135 2.886E-10 IE135M 4.274E-13 Cs-135 1.503E-13 ScuR e6072-03 1 RITA h4KAND SONGS Lei!TS 2.3 18740-475 FMA in Cent-A206/7 Source Stragth From FMA CDNT.TO Activity at 2.000 hours0 days 0 hours 0 weeks 0 months for node 3 (A206/71-10 11 0 0 0 0 .48225E-05 .00000E+00 .00000E+00

NES&L DEPARTMENT

. . CALCULATION SHEET ICCN MJ rREuu. CCN No. r4:E _. or_

Project or DCPAIMP SONGS 2&3 Colc. No. N-4072 003 CCN CONVERSm:

CCN NCI. CCN -

. Sutliset Fuel Handfino Accident FHA) Inskle Containment - Control Room and Offsite Doses Sheet No.,,,,Li W ORIGNATOR DATE NIE DATE REV ORIGNATOR DATE ptE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h i

1-131 5.640E-03 I--153 1.407E-03 1--135 7.611E-06 IR--85 3.921E-11

IE131M 4.802E-12 IE133M 6.696E-10 IE-133 2.500E-11 IE-135 8.467E-12 It135M 3.878E-13 CS-135 1.742E-13 IOuR e4072-03 1 RITA swrAND $0NGS UNITS 2,5 18740-475 FMA in Cent-A206/7 Source Strength From FMA CONT.TD Activity at 8.000 hours0 days 0 hours 0 weeks 0 months for nt4e 3 (A206/7F 10 11 0 0 0 1 48225E-05 .00000E+00 .00000E+00 I--131 5.526E-03 I--133 1.155E-03 I--135 4.062E-06 IR--85 3.781E-20 IE131M 1.823 E-14 IE133N 5.478E-14 IE-133 7.652E-13 IE-135 3.362E-14 '

IE135N 2.152E-15 CS-135 1.756E-13 I

t l

l l

l

NES&L DEPARTMENT CALCULATION SHEET ICCN W PRELIM. CCN NO. PAGE_ _ OF_

Project or DCP/MMP SONGS 2&S Calc. No. N-4072-003 CCN CONVER$10N:

CCN NO. CCN -

. Subject Fuel Handlino Acehnt (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. f.p,.

nEv omeNATOR DATE WIE DATE REV ORiaNATOR DATE IRE DATM [

1 R. Nakano 02 24 94 T. Remick 02 28-94 4

9.4 SmErASG Code Input Mies til Outside Cloud Shine Innut File (sh cid.in) 1 (JOEY ah ctd.0UT 1~ (JSCR 1 (JOPT 1 (J$UN 1 (JENT h-4072-005 1

RITA NMAND <!OR -

SONGS UNITS 2/3 18740-475 FHA IN CONT, Control Room - Outside Cloud Shine Oose 10 (NUM

.10 40 .80 1.30 1.70 2.18 2.50 2.60 4.00 6.20 1 (!UN 1 (ICO 1.00E-02 (EPs 0 (NENT 0 (N8FE T (NslG 1 (00$E SEGMENT # 1 110. 9.000 60. 10.50 39. 6.000 CONCRETE controt ibam Center 1 400$E SEGMENT # 2

3. .000 60. 10.50 39. 6.000 CDNCRETE CR morth Watt 1 (DOSE SEGMENT # 3 '

218 6.000 60. 10.5 39. 6.000

! CONCRETE l

CR south Watt 1 (DOSE SEGMENT # 4 110 9.000 118 f.000 39. 6.000 CDNCRETE

CR East Welt i

1 (DOSE SEGMENT # 5 110 9.000 3. .000 39. 6.000 CDNutETE C3t Wast Wei1 1 (00$E SEEMENT # 6 110 9.000 do. 10.50 48. 6.000 CONOtETE Just teled CR Collint 1 (005E SEGMENT # T 110 9.000 60. 10.50 30. 6.000 CDNCACTE Just Above Ot Floor (CASE # 1 0 to 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ccmtrot noon outside Cloud Shine Dose 1.11E-02 4.51E-01 2.04E-02 1.08E-03 1.04E-04 4.12E-06 4.18E-06 0.00E+00 0.00E+00 0.00E+00 1.00E+00 (C2 6 (Nag thstside Air (300Y # 1 1 3 INT l l

l t <

l

NES&L DEPARTMENT CALCULATION SHEET lCCN N0J PRELIM. CCN NO. PAGE ,_ OF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CONVERSION:

CCN No. CCN -

. Subject Fuel Handlino Ace &nt (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 61 IEV ORIGBdATOR DATE WIE DATE REV ORIGINATOR DATE WIE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28-94 y 4

00s

-3000. -0.000 -3000. -0.000 9. .000 6300. 0.000 6200. 0.000 3100. .000 A!R 1.12E-03 El 9 Conte Air (BODY # 2 2

INT SDX

1. 6.000 2. 6.000 9. .000 216. 6.000 116. 9.000 20. .000 SOL #tCE El 50 conte Air (800Y # 3 3

INT BOX

2. 6.C00 2. 6.000 50. .000 216. 6.000 116. 9.000 19. .000 ScuRCE El TO contam Air (900Y # 4 4

INT toX

2. 6.000 2. 6.000 70. .000 216. 6.000 116. 9.000 14 .000 SOURCE CA Clean Air (800Y # 5 5

INT BOX

2. 6.000 2. 6.000 30. .000 216. 6.000 116. 9.000 19. .000 A!R 1.18E-03 Aux BL Concrete (BODY # 6 6

INT toX

0. .000 0. .000 9. .000 221 6.000 121. 9.000 76. .000 CDNCRETE 2.35E+00 l

l l

NES&L DEPARTMENT CALCULATION SHEET ICCN W PRELIM. CCN NO. PAGE _ OF _

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CQNVERSION:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) Inalda Containment - Control Room and Offsite Doses Sheet No. _jl.,,,

~

Rev omoseATOR DATE WIE DATE REV ONGINATOR DATE WIE l DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 h

S jdj Control Room HVAC Int ** Filter Shine Inout File (sh _a206.in) 1 (JOEV SN A206." JUT 1~ (JSCR 1 (J0PT 1 (JSUM 1 (JENT

-4072-003 1

RITA NAKAND (10R SONGS UNITS 2/3 18740-475 CR Intake Fitter Shine OR th,sring en FMA in the Cont Shine Dose 10 (NUM

.10 40 .90 1.35 1.80 2.20 2.60 3.00 5.00 10.00 1 <!UN ,

1 (ICO 1.00E-02 (EPS O (NENT C (NSFE 5 (NSEG 1 <00$E SEGMENT f 9 109. 6.000 47 6.000 31. 10.000 CDmCRETE Col 19: N-4060-16 #9 1 (00$t SEGMENT f 10

94. .000 47. 6.000 31, 10.000 temCRETE Col 18.4: N-4060-16#10 1 (DOSE SLGMENT # 14 T2. .000 59. 3.000 31. 10.000 tonCRETE Col N: N-4060-16 #14 1 (00$E SEGMENT # 15 94 .000 59 3.000 31. 10.000 !

caCRnE '

Ost h/18.4:h4060-16#15 1 (00$E SEGMENT # 16 109. 6.000 59 3.000 31. 10.000 tauCRETE Col m/19: N-4060-16#16 (CASE # 1 Est WAC Intake Filter Shine Dose Rete At 1 Nour 2.04E+00 3.0TE*02 1.97E+02 1.52E+01 1.45E+00 5.60E-02 5.68E-02 0.00E+00 0.00!+00 0.00E+00 1.00E+00 (C2 9 (NBB stastCE 80x (800Y # 1 1

INT eOE

45. .000 -4. .000 30. .000 120. .000 6. .000 20. .000 CARBON 1.01E+00 A206 CHARCOAL (BODY f 2 2

INT l EM 49 8.000 -4 -8.000 30. 8.000

0. 24.000 C. 27.750 0. 19.000

NES&L DEPARTMENT CALCULATION SHEET KCN W PREUM. CCN NO. PAGE_ 0F_

Praiect er DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN No. CCN -

Subject Fuel Handlino Accident FHA) In=W Containment - Control Room and Offsite Doses Sheet No. 12_

IWV OIDONATOR DATE 5tE DATE REV OluGNATOR DATE 5tE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28 94 y 4

slutCE A2DT DIAltCD4L <go0Y # 3 3

Ivi SOE 161. .000 -3. -8.000 30. 8.000 C. 24.000 0. 27.750 C. 19.000 SoutCE A206 FILTER CASE (800Y # 4 4

INT SOE

49. 7.900 -4. -8.100 30. 7.900 C. 24.200 C. 27.950 0. 19.200 STEEL T.86t+00 A207 FILTER CASE <e00Y # 5 5

ENT BCE 160. 11.900 -3. -8.100 30. 7.900 C. 24.200 C. 27.950 0. 19.200 ETEEL T.NE+00 SOURCE AIR BOX (BODY # 6 6

INT EDE

45. .000 -6. .000 30. .000 120. .000 6. .000 20. .000 AIR 1.18E-03 FIRE 6MLLS < BODY # 7 1

EIT EDE

40. .000 0. .000 30. .000 130. .000 0. 1.50 20. .000 -

c mCRETE 1.00b00 FIREsnLLS (900Y # 8 S

EIT Ret

40. .000 34 .000 30. .000 130. .000 0. 1.50 20. .000 asiatETE 1.00E+00 mastoute!IeG AIR 4300Y # 9 9

EIT Est O. .000 -20. 000 C. .000 200. .000 180. .000 100. .000 AIR 1.18E-03 l

+-. -

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN NO. PAGE_ OF_

Project or DCPA4MP SONGS 2&3 Calc. No. N 4072 003 CCN CONVERSION:

CCN No. CCN -

. Subject Fuel ll J;na Accident (FHA) In*W CerdairTent - Control Room and Offsite Doses Sheet No. 64

, MV ORIGMATOR DATE 5tE DATE REV ORIONATOR DATE WIE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h

4 9.5 LOCADOSE Code Output Mies M Activity Trans - CR HVAC Isolates on Hieh Radiation (fha Cont.to) ,

Calc No. fe4072-003 Aev No. 1 crigiriator RITA NAKANO Date 23 Dec 1993 Checked Date Project SONCS UNITS 2,3 !

Job No.18740-475 sheet Iso. 1 l St&Jact FitA In Contalrnent, CR !solates on High Rad (fha, cont.to) i e

Standard Computer Program NE319 LfA.ADOSE Version 3.0 for the IBM PC/XT/AT or Compatible e

This is the Activity Transport Progren. This program calculates activities, integrated activ' 'ss and releases for each node per time-step and stores them on a file for use by the Dose Calculation Programs.

This progran contains proprietary and confidential infcrimetion be1ongIng to Bechtel Power Corporation.

This program is also en taipublished work protected by the copyright lads of the thited States. Any reprinksction ir futt or in part or use or disclosure of the infonnetton contained in this program is strictly prohibited without the express prior written pensission of techtet Power comoration, 50 Seele Street San Francisco, Califomis 94105, U.S.A.

f

NES&L DEPARTMENT CALCULATION SHEET ICCN W PREUM. CCN NO. PAGE ,,,, OF ,,_

Preiset or DCP/MMP SONGS 2&1 Calc. No. N-4072 003 CCN CQNVERSION:

CCN No. CCN -

Sutiject Fuel Handfina Accident (FHA) In=1de Containment - Control Room and Offsite Doses Sneet No._A}__

REV ORIGNATOR DATE 5lE DATE REV ORIGNATOR DATE 5lE DATE -

R E

1 R. Nakano 02 24 94 T. Remick 02-28-94 y S

Bechtel Standard Computer Program LOCA00$E, N O19 version 3.0 (c) 1989 Calc ho. E 072-003 Rev No. 1 Originator RITA NAKANO Cate 23 Dec 1995 Project SONGS UNITS 2,5 Job No.18740-475 sheet No. 2 Sdject FNA In Contalrunent, CR !solates on High Rad (fhe, cont.to)

Nodes = 2 Time stape = 4 Ikaber of lectopos= 16 Power = 0. Et shutd m time = .00 hrs (if negative, no decay prior to start of accident is considered helease fractions Elemental todine= 1.0 organic lodtrw= 1.0 Particulate Iodine = .00 mobte Gases = 1.0 Co, Rb= 1.0 Te, se, $s= 1.0 Sr, Be= 1.0 Nob le Metats= 1.0 mare Earths = 1.0 Other lectopes= 1.0 Helogens (except todines)= 1.0 Ce trol room activities will be calculated for this case skrtput file LOCATRAM ms created on 23 Dec 1993 at 13:47:23 NOI3 version 1.0 ms used to generate isotopo date for this rm tochtet Standerd Computer Program LOCA00$E, NE319 Version 3.0 (el 1969 Cetc No. 884072-003 Rev ho. 1 Originator RITA N C uso Date 23 Dec 1993 Project SONGS UNITS 2,5 Job ho. 18740-475 sheet Ie. 3 Subject FHA In Contaltunent, CR !solates on High Rad (fhe, cont.to)

Ties latervet = 0.000E40 - 5.000E-02 hrs Inittet Activity in CURIES CONTA!NMT A206/7 I - 131 2.100E+00 0.000E+00 1 - 133 5.560E-01 0.000E+00 1-135 3.470E-03 0.000E+00 IR--85 2.920E+01 0.000E+00 IE131M 3.580E+00 0.000E+00 IE133M 5.120E+02 0.000E+00 IE-133 1.070E41 0.000E+00 IE 135 T.290E40 0.000E+00 IE135M 0.000E+00 0.000E+00 CS-135 0.000E40 0.000f+00 Total 5.654E42 0.000E+00 l

NES&L DEPARTMENT CALCULATION SHEET ICCN N0J PREUM. CCN NO. PAGE_ OF_

Pfeisct or DCP/MMP SONGS 2&3 Calc. No,.&4072 003 CCN CONVERSION.

CCN No. CCN -

1

. Subject Fuel Handlina Accident FHA) Inside Conteirir-ra - Control Room and Offsite Doses Sheet No. Ag_ l l

MV ORiefdATOR DATE 5tE DATE REV ORIONATOR DATE 5tE DATE R l 1 R. Nakano 02-24 94 T. Remick 02 28 94 h '

4 Sechtet Standefti Onuputer Progree LOCA00$E, NE319 version 3.0 Ec) 1969 Cole no. h4072-003 Rev ho. 1 Originator RITA RAKANO Date 23 Dec 1993 Project SONGS tm!TS 2,3 Job ho. 18740-475 sheetsu. 4 Subject FMA In Contaltment, CR !solates on High Rad (fhe_ cont.to)

- - Time intervel = 0.000E+00 - 5.000E-02 hrs volumes of nodes in f t"3 mode volume 2 1.422E+06 3 7.320E+00 Renoval Rates (1/ hrs)

Group CONTAINMT A206/7 Elem lod 0.000E+00 0.000E+00

Org lod 0.000E+00 0.000E+00 Port lod 0.000E+00 0.000E+00 et Gas 0.000E+00 0.000E+00 Cs, Ab 0.000E+00 0.000E+00 Filtered Transfer Rates in cfm from to Mode morie 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 1.000E+06 teftttered Transfer Rates in efe f;tus to Node mode 1 2 3 2 8.200E+04 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 ritter Efficiencies (U For Elem !ad f.*an to Node tode 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 1 0.000E+00 0.000E+00 0.000!+00 F1tter Efficiencies (U For Org lod )

from to am.% l made 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 Fitter Efficiercies (U For Port !ad from to mode made 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 Fitter Efficiencies (S) For It>l Gas from to Node mode 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+001.000E+02

NES&L DEPARTMENT CALCULATION SHEET ICCN W PREUM. CCN NO. PAGE_ OF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN COWASION:

CCN NO. CCN -

Subject Fuel Handlina Accident FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 11._

IEV ofuGedATOR DATE WIE DATE HEV ORIG 8dATOR DATE WlE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h ;

Bechtel Stenderif Computer Progree LOCA00$E, NO19 version 3.0 Ic) 1989 Calc ho. h4072-003 new ho. 1 Originator RITA NAKANO Date Z3 Dec 1993 Project SONGS LMITs 2.3 . lob mo. 18740-475 sheet No. 5 Subject FMA In Contairement, CR !soletes on High Red (fhe_ cont.to)

" Time intervet = 0.000E+00 - 5.000E-02 hrs filter Efficiencies (U For Cs, Rb from to mode hode 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 Controf Room Parameters

.110 = 3.100E-03 W use= 2.444E+05 f t"3

'Antrol lham NVAC Systm Filtered Intete = 0.000E+00 cfm thfittered Inteke = 5.820E+03 cfm Recirculation Flow = 2.989E+04 cfm Lefitts N inteskoge = 5.820E+03 cfm Fitter Efficiencies (U Inteke Recirculation Elam Iod .00 .00 Org lod .00 .00 Port lod .00 .00 abt Gas .00 .00 Cs, it .00 .00 l

1

NES&i. LEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN NO. PAGE_ 0F_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSHXt CCN NO. CCN -

. Subject Fuel Handlina Accident (FHA) Inside Cs61 i.a r.: - Control Room and Offsite Doses Sheet No..JB_

IEV OfEGNATOR DATE 51E DATE REV ORIGNATOR DATE WlE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28-94 y a 5

_1 Dechtet Standard Computer Program LOCA00$E, N O19 weaston 3.0 (c) 1999 Cate No. 24072-003 nov ho. 1 Orieinator RITA NAKANO Onte 23 Dec 1993 Project SouGS LMITS 2,3 Job ha.18740-475 sheet No. 6 Se& ject FNA IL Contaltsuant, CR !solates on High Red (fhe_ cont.to)

- nseutts for Activity Camputation at the end of 5.0000E-02 hours Olstribution of Instantaneous Activity in CURIES CDWTA!NMT A206/7 Cont Room I - 131 1.766E+00 5.320E-30 2.738E-03 1 - 133 4.669E-01 4.485E-32 7.239E-04 I - 135 2.904E-03 9.188E-35 4.502E-06 ER--85 2.456E+01 0.000E+00 3.808E 02 IE131M 3.011E+00 0.000E+00 4.668E 03 IE133M 4.304E+02 0.000E+00 6.673E-01 IE-133 9.116E+00 0.000E+00 1.413E-02 j RE-135 6.109E+00 0.000E+00 9.471E-03 XE135M 5.614E-05 0.000E+00 8.686E-08 CS-135 8.207E-12 3.920E-19 1.2 TIE-14 )

Total 4.754E+02 3.920E-19 7.371E-01 Anchtet Standerd Computer Program LOCA00$E, N O19 version 3.0 (c) 1989 Calc ho. h4072-003 Rev ho. 1 originator RITA NAKANO Oste 23 Dec 1993 Project 50hCS L*ITS 2,3 Job No.18740-475 Sheet No. T l Sihject FMA In Containment, CR Isolates on High Red (fhe_ cont.to) l

- ensults for Activity Computation at the and of 5.0000E-02 hours Activity heteesed from Each hode in CURIES Since Last Printout CONTAINMT A206/7 Totet I - 131 3.336E-01 0.000E+00 3.336E-01 1 - 133 8.825E-02 0.000E+00 8.825E-02 1 - 135 5.498E-04 0.000E+00 5.498E-04 IGt--85 4.639E+00 0.000E+00 4.639E+00 EE131M 5.687E-01 0.000E+00 5.687E-01 IE133M 8.131E+01 0.000E+00 8.131E+01 IE-133 1.710E+00 0.000E+00 1.710E+00 RE-E5 1.156E+00 0.000E+001.156E+00 IE1F M 5.261E-06 0.000E+00 5.261E-06 CS-145 T.518E-13 0.000E+00 7.514E-13 l Totat 8.981E+01 0.000E+00 8.981E+01 !

l 1

2

NES&L DEPARTMENT

' ' l CALCULATION SHEET ICCN NO./

PRELIM. CCN NO. PAGE_ OF _,

Project or DCPA4MP SONGS 2&2 Calc. No. N-4072-003 CCN CQNVERSION:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) InsWe Containment - Control Room and Offsite Doses Sheet No._it._, .

IEV ORIGWATOR DATE WIE DATE REV ORIONATOR DATE ptE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 h j I

Originator RITA hAKAND Date 23 Dec 1993 Project SONGS tlNITs 2,5 Job No. 18740-475 sheet ho. 8 Subject FMA In Contalruent, CR laolates on High Rad (fha _ cont.tol l

- - Time intervet = 5.000E 1.000E+00 hrs Asmoval Rates (1/ hrs)

Group CONTA!NMT A206/7 i Elem !ad 0.000E+00 0.000E+00 I Org lod 0.000E+00 0.000E+00 Port lod 0.000E+00 0.000E+00 att Gas 0.000E+00 0.000E+00 Cs, Itb 0.000E+00 0.000E+00 Filtered Transfer Itates in efs from to Node -

mode 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 1.000E+06 thfittered Transfer states in cfm from to mode mode 1 2 3 2 8.174E+04 0.000E+00 2.640E+02 3 0.000E+00 0.000E+00 0.000E+00 Filter Efficiencies (1) For Elan lod from to mode hode 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 Fittar Efficiencies (1) For org lod from to Nose made 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 Filter Efficierstes (1) For Part led from to leode made 1 2 3 2 0.000E+00 0.000E400 0.J00E+00 3 0.000E+40 0.000E+00 0.000E+00 Filter Efficiencies (1) For tel Gas from to fede ande 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 1.000E+02

NES&L DEPARTMENT CALCULATION SHEET 'c='

PRELIM. CCN NO. PAGE_ OF_ '

Project or DCP/MMP SONGS 2&3 Calc. No. N 4072 003 CCN CONVERSION:

CCN No. CCN -

Subject Fuel Handlina AaeWent (FHA) Inside Containment - Control Room and Offsite Doses Sheet No. 70 REY ORIGNATOR DAlli WIE DATE REV ORIGNATOR DATE 5tE DATE R 1 R. Nekano 02 24-94 T. Remick 02 28 94 i

I l

Dechtel Stenderd Computer Program LOCA00$t, NE319 version 3.0 (c) 1969 Cole ho. h4C72-003 Rev ho. 1 Originator RITA h4KAmo Date 23 Dec 1993 Project SONGS LMITS 2,3 Job ho. 18740-475 Sheet No. 9 Subject rhA In Contelnment, CR !soletes on High Rad (fhe_ cont.to)

Tlee intervel = 5.000E 1.000E+00 hrs Filter Efficiencies (U For Cs, Rb from to hode hade 1 2 3 2 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 Control Room Parameters A/O = 3.100E-03 Wolume = 2.444E+05 f t"3 Control lhom HVAC SFstem Filtered Intake = 4.400E+03 cfm f imfiltered Intake = 1.000E+01 cfm Recirculation Flow = 5.94TE+04 cfm I Imfiltered intestage = 4.410E4 5 cfm Filter Effict mcies (U Inteke Recirculation Elem Iod 95.00 95.00 org lod 95.00 95.00 Port Icd 99.00 99.00 abt Gas .00 .00 Cs, ab 99.00 99.00

NES&L DEPARTMENT i CALCULATION SHEET ICCN W PREUM. CCN NO. PAGE_ OF ,_.

Preiset er DCP/MMP SONGS 2&3 Calc. No. N 4072-003 CCN CONVERSION:

CCN No. CCN - i Sulliset Fuel Handlino Accident (FHA) Inside Conterir rit - Control Room and ONsite Doses Sheet o 71 REV OIWG36ATOR DATE flE DATE REV CIDGNATOR DATE WIE DATE R i E

1 R. Nakano 02 24-94 T. Remick 02 28 94 y )

4 tochtet Standard Computer Progren LOCADOSE, N U19 version 3.0 ft) 1999 Cate No. N4072-003 Aev No. 1 eriginator RITA NerAno Date 23 Dec 1993 Project SONGS tm!TS 2,3 . lob No. 18740-475 sheet No. 10 34 ject FMA In Contalrunent, CR !solates on High Red ((he_ cont.to)

""Aeoutts Por Activity Computation at the end of 1.000 hours Distribution of Instantaneous Activity in CURIO CDNTAINMT A206/7 Cent Room I - 131 6.577E-02 5.455E-03 6.643E-06 I - 133 1.691 E-02 1.402E-03 1.707E-06 I - 135 9.821E-05 8.146E-06 9.919E-09 NR--45 9.178E-01 1.24TE-09 8.722E-02 IE131M 1.123 E-01 1.526 E-10 1.067E-02 IE133m 1.588E+01 2.158E-08 1.509E+00 IE-153 4.271 E-01 5.813E-10 4.013E-02 IE-135 2.123E-012.886E-10 2.018E-02 IE135N 1.615E-05 4.274E-13 2.284E-07 CS-135 6.247E-121.503E-13 3.896E-14 Total 1.763E+01 6.865E-03 1.668E+00 Bochtet starderd Oceputer Program LOCA00SE, N U19 version 3.0 (c) 1989 Cate No. N4072-003 Rev No. 1 Originator RITA NAKAN0 Date 23 Dec 1993 Project 50NGS LA!TS 2,3 Job No. 18740-475 Sheet No. 11 seject FMA In Contalrument, CR !solates on High Red (fhe_ cont.to)

==nesults for Activity Computation at the end of 1.000 hours !

Activity heteesed free Each Mode in CURIES '

Since Last Printout CDNTAINNT A206/7 Total I - 131 1.693E+00 0.000E+001.693E+00 I - 133 4.443E-010.000E+00 4.443E-01 ,

I - 135 2.714E-03 0.000E+00 2.714E-03 '

NR--45 2.357E+010.000E+00 2.357E+01 IE131M 2.887E+00 0.000E+00 2.887E+00 IE133N 4.116E+02 0.000E+00 4.116E+02 RE-133 9.301E+00 0.000E+00 9.301E+00 AE-135 5.751E+00 0.000E+00 5.751E+00 RE135N 2.053E-06 0.000E+00 2.053E-04 i CS-135 4.653E-11 0.000E+00 4.653E-11 1 Total 4.552E+02 0.000E+00 4.552E+02 i

l I

l

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN NO. PAGE_ 0F_

Project er DCP/MMP SONGS 2&3 Calc. No. N 4072-003 CCN CofWER$10N:

CCN No. CCN -

I Sulliset Fuel Handlino Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No._22_

MV OluGNATOR DATE WIE DATE MV ORIG 56ATOR DATE WIE DATE R g

1 R. Nakano 02 24 94 T. Remick 02-28-94 y 4

tochtet Stenderd Caputer Program LOCA00SE, NE319 version 3.0 (c) 1989 Cole No. h4072-003 Aev ho. 1 Origlvater RITA M4KAND Date 23 Dec 1993 Project SONGS UNITS 2,3 Job No.18740-475 Sheet No. 12 S4 ject FNA In Contalruent, CR !solates on Nigh Red (fhe_ cont.tol

- - - Results for Activity Computation et the end of 2.000 hours Olstribution of Instantaneous Activity in CURIES CDNTAINNT A206/7 Cont Room I - 131 2.060E-03 5.640E-03 2.000E-07 i 1 - 133 5.141E-04 1.407E-03 5.191E-08 1-135 2.780E-06 7.611E-06 2.OO7E-10 ER-85 2.885E-02 3.921E-11 3.218E-02 IE1314 3.520E-03 4.802E-12 3.926E-03 IE133N 4.927E-01 6.696E-10 5.496E-01 IE-153 1.625E-02 2.300E-11 1.TT9E-02 IE-135 6.186E-03 8.467E-12 6.899E-03 IE135N 4.981E-07 3.878E-13 1.501E-08 CS-135 3.800E-13 1.742E-13 1.387E-14 Total 5.501E-01 7.055E-03 6.104E-01 Dechtet Standard Caputer Program LOCA005E, NE319 version 3.0 (c) 1909 Cole No. N4072-003 Rev No. 1 Originator RITA NAKANO Date 23 Dec 1993 Project SONGS UNITS 2,5 Job No.18740-475 sheet No. 13 Seject FMA In Contalruent, CR !solates on Nigh Red (fhe, cont.tol

"*Results for Activity teneutation at the md of 2.000 hours Activity Released from Each hade in CURIES Since Last Printout CONTAINMT A206/7 Total I - 131 6.344E-02 0.000E+00 6.344E-02 1 - 153 1.618E-02 0.000E+00 1.618E-02 I--135 9.233E-05 0.000E+00 9.233E-05 ER--85 8.861E-01 0.000E+00 8.861E-01 IE131n 1.083E-01 0.000E+00 1.083E-01 IE1334 1.528E+01 0.000E+00 1.528E+01 IE-133 4.332E-01 0.000E+00 4.332E-01 NE-135 2.011E-01 0.000E+00 2.011E-01 IE135N 1.504E-05 0.000E+001.504E-05 CS-135 7.407E-12 0.000E+00 7.407E-12 Tekt 1.699E41 0.000E+00 1.699E+01

~

NES&L DEPARTMENT CALCULATION SHEET 'ec=

PREUM. CCN NO. PAGE___ OF_

Project or DCP/MMP SONGS 2&2 Calc. No. N-4072 003 CCN CONVERS60N:

CCN No. CCN -

o Subject Fuel Handlina Wt FHM InaMe Cent.;aT a - Control Room and Offsite De Sheet No. 73 i

IEV oNGHATOR DATE BIE DATE MV ORIONATOR DATE BtE DATE R 1 R. Nekano 02 24 94 T. Remick 02 28 94 E y

{

Criginator RITA llARAND Oste 23 Dec 1993 !

Project SONGS 18t!TS 2.5 Job ho. 18740-475 Wiset No. *t4 Subject FNA In Containment, CR !aolates en High Red (fhe, cont.to) l mesma

- - - Anaults for Activity Computation at the end of 8.000 hours Distribution of Instantaneous Activity in CURIES CONTA!NNT A206/7 Cont Room I--131 1.944E-12 5.526E-031.963E-16 I--133 4.063E-13 1.155E-03 4.103E-17 i I--135 1.429E-15 4.062E-061.443E-19 I RR--85 2.782E-113.781E-20 4.898E-05 j IE131M 3.346E-12 1.823E-14 5.889E-06 IE133M 4.390E-10 5.478E-14 7.729E-04 IE-133 5.234E-117.652E-13 5.501E-05 i

RE-135 3.780E-12 3.362E-14 6.651E-06 !

I EE135m 1.003E-15 2.152E-13 5.088E-17 ts 135 2.324E-21 1.756E-13 2.165E-17 )

Total 5.286E-10 6.685E-03 8.894E-04 i

{

Originator RITA NARAho Cole No. m4072-003 Rev No. 1 l

Cate 23 Dec 1993 '

Project SONC$ UNITS 2,3 Job No. 18740-475 Sheet No. 15 I Subject FHA In Containment, CR !soletes on High had (fhe, cont.to)

- - - Ameults for Activity Computation at the end of 8.000 hours

)

Activity Released from Each hade in CURIES Since Last Printout CnNTAlloff A206/7 Total I--131 2.051E-03 0.f100E40 2.051E43 1--153 5.076E-04 0.000E40 5.076E-04 I - 135 2.689E-06 0.000E40 2.689E-06 RR--85 2.876E-02 0.000E+00 2.876E-02 IE131M 3.506E-03 0.000E40 3.506E-03 IE1334 4.892E-010.00nE<:0 4.892L-01 IE-133 1.695E-02 0.000t+00 1.695E-02 RE-135 6.035E-03 0.000E+00 6.033E-03 IE1354 4.619E-07 0.000E40 4.619E47 CS-135 4.255E-13 0.000E+00 4.255E-13 i Total 5.470E-010.000E40 5.470E-01

1 NES8d. DEPARTMENT CALCULATION SHEET ICCN W PRELIM. CCN NO. PAGE._ OF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CONVERSION:

CCN NO. CCN -

Subitct Fuel Handlino Aceldent FHA) Inside Containment - Contrdoom and Offelte Doses Sheet No. 74 MV ONGedATOR DATE WIE DATI REV ON086ATOR DATE WIE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28-94 y S

M2 Dose Protram - CR HVAC Isolates on Hinh Radiation (fha cont.do) tochtet Standard Computer Progree LOCA00st. W O19 version 3.0 (c) 1989 Cate No. m4072-003 Aev ho. 1 Originster RITA NAEANO Date 23 Dec 1993 Project SONGS UN!fS 2.3 Job No. 18740-475 Sheet ho. 2 3 4Joct FHA In Containment, CR !soletes on High Red (fhe_ cont.do) 3019 Dose Irgut Sumnery File LOCATRAN generated on 23 Dec 1993 at 13:47:23 is used by this run The follcwing options and calculottons are performed:

Doses within regions will be calculated 1 Offsite Doses will be calculated Control Room doses will be calculated l This run evoluetes 16 isotopes ustrg 4 regions and 4 time-steps Offsita doses for 2 dose points w1LL be calculated i h013 version 1.tes used to generate the isotope sta for this rm !

lectopes Considered in this Run l 1

I--131 I--131 I--131 I--133 I--133 I--133 I--135 I--135 l 1--135 KR--85 IE131M AE133M XE 133 XE-135 RE135M CS-135 NE319 Doses Within Regions suonary Doses in REM for region 4 Cont Room Time Intervet (hr) Thyroid Lung tone tota skin teole body From to

.0000 -5.0000E-02 2.010E-02 2.908E-04 4.424 E-05 3.190E-04 4.874 E-06 5.0000E 1.000 6.219E-02 1.516 E-03 1.369E-04 3.021E-02 4.392E-04 1

i 1.000 - 2.000 5.226E-04 3.801E-04 1.149E-06 1.765E-02 2.560E-04 .

2.000 - 8.000 1.687E-05 1.957E-04 3.705E-06 9.220E-03 1.337E-04 !

Total 8.283E-02 2.383 E-03 1.823E-04 5.740E-02 8.338E-04 l 8019 Offatte Does Sumnery Doses in REM for distance 1 Tien Interval (hr) Thyroid Lung tone teta Skin teole tody From to

.0000 -5.0000E-02 4.915E-02 7.113 E-04 1.082 E-0=, 7.803E-04 2.111 E-04 5.0000E 1.000 2.494 E-01 3.608E-03 5.487E-04 3.951E-03 1.067E-03 1 1.000 - 2.000 9.333E-03 1.350E-04 2.051E-05 1.469E-04 3.970E-05 2.000 - 8.000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000 E+00 Total 3.079E-01 4.454E-03 6.774 E-04 4.878E-03 1.319E-03 g NO19 Offstte cose Summary Doses in REM for dl:tance 2 I Ties Interval thr) Thyroid tmg Scne tota Skin thole body From to

.0000 -5.0000E-02 1.395E-03 2.019E-05 3.071E-06 2.215E-05 5.991E-06 5.0000E 1.000 7.078E-03 l

1.024 E-04 1.557E-05 1.121E-04 3.033E-05 1.000 - 2,000 2.649E-04 3.831E-06 5.822E-07 4.168E-06 1.127E-06 1 2.000 - 8.000 8.553E-06 1.236E-07 1.878E-08 1.336E-07 3.612E-06 l Total 8.747E-03 1.266E-04 1.925E-05 1.386E-04 3.748E-05 l l

)

NES&L DEPARTMENT CALCULATION SHEET ICCN NW PREUM. CCN NO. PAGE __ OF_

Project or DCP/MMP SONGS 2&3 Colc. No. N-4072-003 CCN CONVERSION:

CCN No. CCN -

Subject Fuel Handlina Accident (FHA) Inside Containment - Control Room and Offsite Doses Sheet No._.ZE_,_

g ORONATOR DATE WIE DATE REV ORGNATOR DATE ME DATE R 1 R. Nakano 02 24 94 T. Remick 02 28 94 y 4

112 Dose Prorram - CR HVAC Does Not Isolate (fha Coni. dol tachtet Standerd Cassiuter Progran LOCADOSE ND19 version 3.0 (c) 1969 Cale no. m4072-003 Rev 2o. 1 Originetor RITA NAKANO Dete 13 Dec 1993 Project SONGS UN!TS 2.5 . lob No.18740-475 Shoet No. 2 Subject FMA In Containment, ho CR Isolation (fhe_ con 1.do) k ulf Dose input Summary File LOCATRAN generated on 13 Dec 1993 at 15:50:36 is used by this run The following options and calculations are performed:

Doses within regions will be calculated Offsite Ooses will be calculated Control Room doses will be calculated This run evoluetes 16 isotopes using 4 regions and 3 ties-steps Offsite doses for 2 dose points will be calculated ND13 version 1.tes used to generate the isotope data for this rm

Isotopes Considered in this Run l

I--131 !--131 I--131 I--133 1--133 1--133 1--135 I--135 l I--135 KR--85 IE131M RE153M XE-133 XE-135 IE135M CS-135 I NO19 Doses 4tithin Regions Suenary Doses in REM for region 4 Cont fWom flee Interval thr) Thyroid Lung tone tota Skin lAote Body From to

.0000 - 1.000 2.160E+00 3.124E-02 4.751E-03 3.416E-02 5.21TE-04 1.000 - 2.000 1.012E+00 1.463E-02 2.224E-03 1.591E-02 2.429E-04 2.000 - 8.000 3.379E-01 4.862E-03 T.415E-04 5.262E-03 8.031E-05 Total 3.510E+00 5.076E-02 T.71TE-03 5.533E 02 8.449E-04 IE319 Offsite thee Suseery Doses in REM for distance 1 flee Interval (hr) Thyrold Lung tone tota skin lAote body From to

.0000 - 1.000 2.994E-01 4.331E-03 6.587E-04 4.744 E-03 1.263E-03 1.000 - 2.000 9. 563 E-03 1.354 E-04 2.056E-05 1.473 E-04 3.963E-05 2.000 - 8.000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

Total 3.067E-01 4.467E-03 6.793E-04 4.891E-03 1.323E-03 i

ut319 Offsite Oose Suenary Ooses in REM for distance 2 Ties Interval (hr) Thyroid Luig tone tota skin thole body From to l .0000 - 1.000 8.496E-03 1.229E-04 1.87DE-05 1.346E-04 3.642E-05 i 1.000 - 2.000 2.656E-04 3.443E-06 5.841E-07 4.182E-06 1.131E-06 2.000 - 8.000 8.561E-06 1. 240E-07 1.864E-06 1.540E-07 3.624E-06 Total 8.TT1E-03 1.269E-04 1.930E-05 1.390E-04 3.756E-05

NES&L DEPARTMENT CALCULATION SHEET ICCN W PREUM. CCN No. PAGE.,_ OF_,,

Prefect Or DCP/MMP SONGS 2&2 Calc. No. N-4072-003 CCN CQNVERSloN:

CCN NO. CCN -

. Subject Fumi Handfino Ace &nt (FHM inside Cant.;66,ent . Control Room and Offsite Doses Sheet No. 76 REV OIWGNATOR DAT*i WlE DATE REV ORIONATOR DATE NtE DATE R E <

1 R. Nakano 02 24 94 T. Remick 02 28-94 y )

S 9.6 SOURCE 2 Code Output File 211 Outside Cloud Shine Outout File (fhn cid.so) _

NO1E: As discussed in Section 5.2.2, an integrated activity (Ci) and a scaling factor based on dispersion (hr/cmS ) is input to SOURCE 2. 'Ihus, the output units for this SOURCE 2 run are actually (Mev-hr)/(cm 8-sec),

rather than the Mev/sec listed in the printout.

CASE TITLE: INTEGRATED ACTIVITY AT 8 HR$ AFTER START OF ACCIDENT MULTIPLICATION FACTOR = 8.6111E-13 ISOTOPE INPUT ACTIVITY ( CURIES I I--131 2.09200E+00 I--133 5.49200E-01 1--135 3.35900E-03 KR--85 2.91200E+01 IE131M 3.56800 E+00 IE133M 5.06700E+02 NE-133 1.14600E+01 RE-135 T.11400E+0C IE135N 2.26100 E-04 CS-135 5.51100E-11 TOTAL 5.62607E+02 CASE TITLE: INTEGRATED ACTIVITY AT 8 HRS AFTER START OF ACCIDENT EMMA SOURCE STRENGTH AS A FUCTION OF DECAY TIME ( MEV/SEC 1 WERGY GROUP .000 SEC .000 - 100 MEV 1.10823E-02 i

.100 - 400 MEV 4.50571E-01 l

.400 - .900 MEV 2.03941 E-02 '

.900 - 1.350 MEV 1.00014 E-03 '

1.350 - 1.800 MEV 1.04474E-04 '

1.800 - 2.200 MEV 4.12302E-06 l 2.200 - 2.600 MEV 4.18428E-06 '

2.600 - 3.000 MEV 0.00000E+00 3.000 - 5.000 MEV 0.00000E+00 5.000 -15.000 MEV 0.00000E+00 TOTAL 4.83240E-01 l

I l

NES&L DEPARTMENT CALCULATION SHEET 'CCN No.i PRELIM. CCN NO. PAGE_ 0F_

Project or DCP/MMP SONGS 28t3 Calc. No. N.4072-003 CCN CONVERSION:

CCN NO. CCN -

. Subject Fuel Handlino Accident (FHA) Inside Cente:n. Gent . Control Room and Offsite Doses Sheet No. 77 REV ORIONATOR DATE WlE DATE HEV ORIGNATOR DATE 5tE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28-94 y S

W Control Room HVAC Int ** Filter Shine Outnut File (fha _a206.so)

Cast TITLE: Activity at 5.0000E-02 hours for node 3 (A206/7)

GAMMA SOURCE STRENGTH AS A FUCTION OF DECAY TIME (MEV/CC-SEC I ENERGY GROUP 000 $EC

.000 - .100 MEV 1.96556E-27

.100 - 400 MEV 2.96316 E-25 400 - .900 MEV 6.37556E-26

.900 - 1.350 Mtv 4.62294 E-28 1.350 - 1.800 MEV 2.97397E-29 1.800 - 2.200 MEV 6. 31596E-31 2.200 - 2.600 MEV 6.40962E-31 2.600 - 3.000 MEV O.00000E+00 3.000 - 5.000 MEV 0.00000 E*00 5.000 -15.000 MEV 0.00000E+00 TOTAL 3.64550E-25 CASE TITLE: Activity at 1.000 hours0 days 0 hours 0 weeks 0 months for node 3 (A206/7)

EAfen SoutCE STRENGTH AS A FUCTION OF DECAY TIME (MEV/CC-SEC )

ENERGY E40VP .000 SEC .000 - .100 MEV 2.03595E+00

.100 - 400 MEV 3.06543E+02 400 - .900 MEV 1.97036L+02

.900 - 1.350 MEV 1.52386E+01 1.350 - 1.800 MEV 1.45121E+00 1.800 - 2.200 MEV 5.59968E-02 2.200 - 2.600 MEV 5.68286E-02 2.600 - 3.000 MEV 0.00000E+00 3.000 - 5.000 MEV 0.00000E+00 5.000 -15.000 MEV 0.00000E+00 TOTAL 5.22438t+02 CASE TITLE: Activity at 2.000 hours0 days 0 hours 0 weeks 0 months for node 3 (A206/7) 4

. GApen SOURCE STRENGTH AS A FUCTION OF DECAY TIME (MEV/CC-5EC 1 ENDIGY EROUP .000 SEC .000 - .100 MEV 2.10499E+00

.100 - 400 MEV 3.16937E+02 400 - .900 MEV 1.99574 E+02

.900 - 1.350 MEV 1.52009E+01 1.350 - 1.800 MEV 1.40060 E+00 1.800 - 2.200 MEV 5.23191E-02 2.200 - 2.600 MEV 5.30965E-02 2.600 - 3.000 MEV 0.00000E+00 3.000 - 5.000 MEV 0.00000E+00 5.000 -15.000 MEV 0.00000E+00 TOTAL 5.35330E+02

NES&L DEPARTMENT CALCULATION SHEET @uEcN No. PAGE_ O L_

Project or DCPMMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) Inside CeniJr.rr.er,t Control Room and Offsite Doses Sheet No._ZB_,

REV OfuGNAT0ft DATE WIE DATE IIEV OIWGMATOR DATE 5tE DATE R E

1 R. Nakano 02 24 94 T. Ramick 02 28 94 y 8

CASE TITLE: Activity at 8.000 hours0 days 0 hours 0 weeks 0 months for node 3 (A206/7)

GAMPH SOLAtCE STRENGTM As A FUCTION OF DECAY TIME (MEVICC-SEC 1 ENDICY G110VP .000 SEC .000 - 100 MEV 2.06245E+00

.100 400 MEV 3.10413E+02 400 - .900 MEV 1.73784E+02

.900 - 1.350 MEV 1.21585E+01 1.350 - 1.800 MEV 9.33583E-01 1.800 - 2.200 MEV 2.79228E-02 2.200 - 2.600 MEV 2.833TTE-02 2.600 - 3.000 MEV 0.00000E+00 3.000 - 5.000 MEV 0.00000E+00 l 5.000 -15.000 MEV 0.00000E+00 TOTAL 4.99408E+02 i

i i

l I

l l

I 1

I

NES&L DEPARTMENT l CALCULATION SHEET =c= / I PRELIM. CCN No. PAGE OF_ J Calc. No. N 4072 003 CCN CQNVERSON: j Probet or DCP/MMP SONGS 2&S cCN No. ccN - l

. Subiect EuaWandHrMI_AccideftlEHAl_1naldefontainmart-Inntrol Roommd Offalta_Danta Sheet No. 23,,,,,,

IWV ORIGSdATOR DATE WE DATE MV OR105dATOR DATE 5lE DATE R 1 E l 1 R. Nakano 02 24-94 T. Remick 02 28-94 y '

S l

l 9.7 SHIF1D-SG Code Output Mie

),J.J ,Outside Cloud Shine Outnut File (sh cid.out)

NO'IE: As discussed in Section 5.2.2, the input source strength %bwu is in units of (Mev-hr)/(cm 8-sec), rather than the Mev/(cm3-sec) listed in the printout.

This means that the output units for this SHIELD-SG run is Rem, instead of the Rem /hr listed in the program output.

CALC StaJECT: FMA IN CONT. Control Room - Outside Cloud Smne Dose PAGE:~ ~ "T CASE TITLE: 0 to 8 Nour Control Room Outside Cloud Shine Oose

SOURCE ENERGY GROUPS AND EM!$$10N RATES * [ SOURCE MULTIPLIER = 1.000E+00)

CROUP # 1 2 3 4 5 MEV/ GAMMA .100 .400 .800 1.500 1.700 MEv/06 S 1.11E-02 4.51E-01 2.04E-021.06E-031.04E-04 GROUP # 6 T & 9 10 ,

MEv/GA8en 2.180 2.500 2.800 4.000 6.200 MEv/CM5 S 4.12E-06 4.18E-06 0.00E+00 0.00E+00 0.00E+00

OG)Y DATA

900Y EDORDIMTES X Y Z gony gooy Ag pauRHO DENSITY -------------- -------------- --------------

TYPE LOC !$ puTERIAL [G/CM3) [FT 10 [FT 10 [FT 10 1 00R SRC ~ A!R 1.12E-03 -[3000 .000) -[3000 .000) +[ 9 .0003 2 tot SRC -- AIR 1.12E-03 +[ 2 6.000) +[ 2 6.000] +[ 9 .000) 3 30 SRC - AIR 1.12E-03 +[ 2 6.000) +[ 2 6.000] +[ 50 .000) 4 80E SRC -- AIR 1.12E-03 +[ 2 6.000] +[ 2 6.000) +[ 70 .000) 5 00K lNT - AIR 1.18E-03 +[ 2 6.000) +I 2 6.000) +[ 30 .000) 6 BOK INT - CONCRITE 2.35E+00 [ 0 .000) [ 0 .000) +[ 9 '.000)

OODY O!MENSIONS

. _._._..~. ~

OX Of QZ R 300f - ----------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

SODY

[FT 10 [FT 10 [FT 10 [FT 10 DESCRIPTION 1 [6300 .001) [6200 .001) [3100 .000) - -

Outside Air 2 [ 216 6.000) I 196 9.0003 [ 20 .000) - -

El 9 Contam Air 3 [ 216 6.0003 [ 116 9.000] [ 19 .000) - -

El 50 Contam Air 4 [ 216 6.0003 [ 116 9.000) I 14 .000) - -

El 70 contam Air 5 [ 216 6.0003 [ 116 9.000) I 19 .000) - - CR Clean Air 6 [ 221 6.000) [ 121 9.0003 [ 76 .000) - - Aux BL Concrete

{

NES&L DEPARTMENT CALCULATION SHEET 'CCN NO.i PRELIM. CCN NO. PAGE._ 0F_,

Pruisct or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CQNVERSION:

CCN NO. CCN -

l . Subiect Fuel Handlina Accident FHA) Inside Containment - Control Room and Offsite Doses Sheet No._ AIL _

IEV OWIBdATOR DATE Wit DATE REV ONGedATOR DATE 5tE DATE R E

1 R.Nakano 02 24 94 T. Remick 02 28 94 y S

Rost POINT DATA

DOSE POINT COORDINATES IP YP 2P ggg gUiLDUP . . ~ . . . - - . - - . . - . - . .

005E PO!NT POINT NATERIAL [FT IN3 [FT 1R1 [FT IN] SET DESCRIPfl0N 1 CONCRETE +[ 110 9.0003 +[ 6010.500) +[ 39 6.000) Centrol Room Center 2 CONCRETE +[ 3 .000) +[ 60 10.5001 +[ 39 6.0003 CR North Wett 3 CONCRETE +[ 218 6.000] +[ 6010.500] +[ 39 6.000) CR South Well 4 CONCRETE +[ 110 9.000) +[ 118 9.000] +[ 39 6.000) CR East WmLL NE650 SHIELD-SGt02-10) [(C) 1983,1992 SECNTEL ALL RIGHTS RESERVED] sh cld.0UT

. CRIGINATOR: RITA NAKANO (10R DATE: 12/23/93 CALC: N-4072-003Riv: 1 PatutCT: SONGS UNITS 2/3 J08: 18740-475 CHECK: DATE: / /

CALC SLEJECT: FMA IN CONT. Control Room - Outside Cloud Shtne Dose PAGE:- ~ "I CASE TITLE: 0 to 8 Hour Control Room Outside Cloud Shine Oose 00$E POINT C00RDINATES IP YP 2P INSE tu! LOUP ~ ~ - . - - - - - - - - - . - - . - ~ ~ - - . - - - - . - . 00$E Po!NT PolNT M4TERIAL [FT IN) [FT IN] [FT IN3 SET DESCRIPTION 5 CONCRETE +[ 110 9.0001 +[ 3 .000) +[ 39 6.000) CR West Well 6 CONCRETE +[ 110 9.0003 +[ 6010.500] +[ 48 6.000) Just tetow CR Celling 7 CONCRETE +[ 110 9.000) +[ 6010.500] +[ 30 6.0003 Just Above CR Floor

- - BCEE EC11! VALENT RATES [REN/NRJ " [ CONVERGENCE CRITERION = .010)

GRP 00$E POINT iADSERS

1 2 3 4 5 6 7 1 2.37E 101.29E-101.29E-101.28E-101.27E-10 2.37E-10 2.37E 10 2 2.05E-061.10E-061.10E-061.09E-061.09E-06 2.05E-06 2.06E-06 3 3.01E 071.60E-071.60E-071.60E 071.60E-07 3.00E-07 3.02E-07 4 3.29E-08 1.79E-08 1.79E-08 1.78E-08 1.79E-08 3.24E-08 3.30E-08 5 4.35E-09 2.46E-09 2.46E-09 2.45E-09 2.45E-09 4.22E-09 4.39E-09 6 2.37E-101.42E-101.43E-101.42E 101.42E-10 2.25E-10 2.42E-10 7 2.86E-101.79E-101.79E-101.78E-101.78E-10 2.66E-10 2.ME-10 8 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 TUTAL 2.39E-061.3SE-061.26E-061.!TE-061.27E-06 2.39E-06 2.40E-06 i

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN NO. PAGE._ 0F__

Project or DCP/MMP SONGS 2&2 Calc. No. N-4072 003 CCN CCNVERSION:

CCN No. CCN -

. Subject Fuel Handlina Accident (FHA) inside Centeinrnent . Control Room and Offsite NMs Sheet No. 81 MV Oft m ATOR DATE 5tE DATE MV ORIGW6ATOR DATE stE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28 94 y 4

SL2 Control Roorn HVAC Intaa Filter Shine Outout File (sh a206.out)

NOTE: The units listed in the output are Correct.

CALC SLBJECT: CR Intake Fitter Shi e OR Ouring an FMA in the cent PAGE:- ~ "T CASE TITLE: CR NVAC Intake Fitter Shine Oose Rate At 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

- - SOURCE ENERGY GROUPS AND EMISSION RATES *** [ SOURCE PRJLTIPLIER = 1.000E+00)

Emour # 1 2 3 4 5

.. .. .. ~ . .... .... ........ ........

MEV/G4MMA .100 400 .900 1.350 1.800 MEV/06-s 2.04E+00 3.07E+021.97E+021.52E+01 1.45E+00

~

smour # 6 7 8 9 10 MEV/ GAM A 2.200 2.600 3.000 5.000 10.000 MEVIOG-s 5.60E-02 5.68E-02 0.00E+00 0.00E+00 0.00E+00

- - 800Y QATA ***

900Y COORDINATES X Y Z 300y 300y As pRJ/ RHO DENSITY - ~ ~ ~ - - - - - - - - - - - - - - - - - - - - - - - - - ~ ~

TYPE LOC IS MTERIAL [G/CM3] [FT IN) [FT IN) [FT IN) 1 00X SRC ~ CAR 80N 1.01E+00 +[ 45 .000) -[ 6 .000) +[ 30 .000) 2 BM SRC -- CARE 0N 1.01E+00 +[ 49 8.000) -[ 4 8.000) +[ 30 8.000) 3 a0x SRC -- CARS 0N 1.01E+00 +[ 161 .000) -[ 3 8.000) +[ 30 8.0003 4 BOX INT -- STEEL 7.86E+00 +[ 49 T.900) -[ 4 8.100] +[ 30 T.9001 5 00X INT -- STEEL T.86t+00 +[ 160 11.900) -[ 3 8.100] +[ 30 7.900) 6 BOX INT -- AIR 1.18E-03 +[ 45 .000) -[ 6 .000) +[ 30 .000)

T t0K EXT -- CONCRETE 1.00E+00 +[ 40 .000) [ 0 .0001 +[ 30 .000]

4 tot EXT ~ CONCRETE 1.00E+00 +[ 40 .000] +[ 34 .000) +[ 30 .000) 9 set EXT ~ AIR 1.18E-03 [ 0 .000) -[ 20 .000] [ 0 .000]

, 000T DIMENSIONS DR DY OZ R 3007 -------------- -------------- -- - ---------- - ----.---.-- 300Y

[FT 110 [FT IN) [FT 180 [FT 110 DESCRIPTION 1

[ 120 .000) [ 6 .000) [ 20 .000) - -

SOURCE sot 2 [ 2 .000] [ 2 3.750) [ 1 T.000) - -

A206 CHARCmL 3 [ 2 .000) [ 2 3.750) [ 1 T.000) - -

A207 CHARcnAL 4 [ 2 .200] [ 2 3.950) [ 1 T.200) - -

A206 FILTER CASE 5 [ 2 .200) [ 2 3.950) [ 1 T.2003 - -

A207 FILTER CASE 6 [ 120 .0003 [ 6 .000) [ 20 .000) - .

SOURCE AIR 30x T [ 130 .0003 [ 0 1.500) [ 20 .000) - -

FIRE mLLs 8 [ 130 .0003 [ 0 1.500) [ 20 .000) . -

FIRE m LLs 9 [ 200 .0003 [ ISO .000] [ 100 .000) - -

SURROUNDING AIR l

~ _

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN No. PAGE_ 0F_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN No. CCN -

Subject Fuel Handlina Accident FHA) Inside Cc6te;6,T.ent Control Room and Offsite Doses Sheet No. 32_

IEV ofuGe6ATOR DATE stE DATE fEV ORIGedATOR DATE stE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28 94 y I

NE650 SHIELO-$Gl02-10) [(C) 1983,1992 BECHTEL ALL RIGNTS RESERVED) SH A206.0UT ORIGINAT'A: RITA NAKANO <!OR DATE: 12/27/93 CALC: N-4072-003RYY: 1 PRCUECT: SONGS UNITS 2/3 J08: 18740-475 CHECK: DATE: / /

CALC SLELJECT: CR Intake Filter Shine OR During en FMA in the Cont PAGE:~ ~ "7 CASE TITLE: CR NVAC Intake filter Shine Oose Rete At 1 Nour

- - DDSE PO!NT DATA ***

00$E POINT CDORDINATES XP YP 2P DOSE BUILOUP -------------- -------------- -------------- 00$E POINT Po!NT MATERIAL [FT IN) (FT IN) (FT IN) SET DESCRIPTION 1 CONCRETE +I 109 6.000] +[ 47 6.000) +[ 31 10.000) col 19: N-4060-16 #9 2 CONCRETE +I 94 .000) +C 47 6.000) +[ 31 10.000) Col 18.4: N-4060-16t10 3 CONCRETE +I 72 .000) +t 59 3.000] +[ 31 10.000) Col N: N-4060-16 814 4 CDNCRETE +[ 94 .000) +I 59 3.000] +C 31 10.000) Col N/18.4:N4060-16#15 5 CONCRETE +I 109 6.000) +t 59 3.000) +I 31 10.000) Col N/19: N-4060-16Gi6

" DOSE EQUIVALENT RATES [REN/MR) " (CONVERGENCE CRITERION = .010]

GRP 00$E POINT NUMBERS

1 2 3 4 5 1 1.76 E-09 1.87 E-09 1. 83 E-09 1. 60 E-09 1. 56 E-09 2 1.26E-061.30E-061.13E-061.07E 061.0$E-06 3 8.59E-07 8.84E-07 7.61E-07 7.18E-07 T.10E-07 4 6.55E-08 6.74E-08 5.79E-08 5.45E-08 5.38E-08 5 6.09E-09 6.26E-09 5.38E-09 5.05E-09 4.99E-09 4 2.32E-10 2.38E-10 2.05E-101.92E-101.90E-10 7 2.30E-10 2.36E-10 2.03E-10 1.90E-10 1.88E-10 8 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 2.19E-06 2.26E-061.96E-061.85E-061.83E-06

NES&L DEPARTMENT CALCULATION SHEET ICCN NN PREUM. CCN NO. PAG (__ 0F__

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN No. CCN -

. Cubject Fuel Handlina Accident (FHA) InsWe Containment - Control Room and Offsite Dmul Sheet No. ,0.3_.,,,,

MV OfuGedATOR DATE WIE DATE REV OpuGedATOR DATE 5tE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28 94 , y 1 8 10.0 COPIES OF MISCELLANEOUS REFERENCES 10.1 E Mail from D. Higgins (SCE) to F. Santa Ana (SCE)

(6) From: DAN HIGGINS at ANS3 5/13/93 9:25AM (30" bytes: 53 in)

To FABIAN SANTA ANA at NESL5, THOMAS REMICK ** ;L2, MARK DRUCKER at NESL2 cc: KEVIN FLYNN, DALE WICKMAN, DAN MIGGINS,. W LE, MARK RERSCHTHAL

Subject:

CR MVAC Intake Filter Housing

. . . . . . . . - - . . . . . . . . . . . . . . . . . . . . - Me 8 88 2 e Cen t . A s . - . . . . . . . . . . . . . . . - - . - . - - . . - - - -

Fabian....Thank you for the vote of confidencel .

Tom... Dale Wickman is your man for this system. He has taken over resportsibility for the smargency NVAC systems formerly handled by Kevin. Kevin now has Radweste systems.

However I will answer your questions on this one and give D11e a break. Firstly, you have the right drawing. The 3 3

arbon trays you see are TSS Standard CS-ST carbon trays for t/pe II adeo.ber cells. The cells are built of type 304 SS with 26 gauge perforated plate (0.045 holes) and flanged reinforced 24 gauge 24 gauge facoplates. There are (2) 2*

deep beds per charcoal cell. Cell dimensions are 24'W x 27-3/4'D x 6-9/32'H. Details of this cell with a cutaway can be found in the Nuclear Air Cleaning Handbook 'sy C. A.

Durchsted, ERDA 76-21 on page 58. Secondly. I believe the drawing you have is the only one we have svallable. Based on observation and notes on other AAF drawings, the steel housing is $11 GA (.1011 min.). Same for all housings.

Dale (FAX e6152) will be able to help you with any other questions you may have, uave a good days . .

j.f7,9f Dan Miggins 5-13 93 -

Tom, I have not come seroes any document regarding the deatails of the Control Room Emergency ventilation Unit (MA206/207).

Your best bet would be Station Technical who have hands on knowledge of these unite.

I suggest you get in touch with either Dan Higgins (PAX 89211) or Kevin Flynn (FAX 892121.

I em confident that they have the documents you need to complete your analysis.

Fabian 5/13/93 Fabian, we are doing a reanalysis of the filter shine radiological i

' dose from the Control Room NVAC Intake filters (SA1510MA20s and SA1510MA207). As of now, I have not been able to find a drawing of the filter unit that has the following dimensions:

a. Omarcoal filter tray (length a width x height per tray) ( I g

Thickness of steel housing, at the charcoal filter location

b. i The only drawing I have been able to find is 3023-410-1 1 (American Air wilter drawing R107D-160325). If you can suggest any other documents (such as a vendor manuali that might have the information I am looking for, I would appreciate it.

Thank you

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM. CCN NO. PAGE _ OF,_,,

ProjoCt or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CQNVERSION:

CCN No. CCN -

Subject Fuel Handfino Accident (FHA) in*Me Containment - Control Room and Offsite Doses Sheet No. 84 _

REV 08uGNATOR DATE 5tE DATI REV OIDG8dA10R DATE WIE DATE R E

1 R. Nakano 02 24-94 T. Remick 02 28 94 y 4

10.2 E.Ma!! From F. Santa Ana (SCE) to T. Remick (Bechtel)

(104) From: FELICIA UDREA 2/17/94 7:59AM (4957 bytest 99 In)

To: FABIAN SANTA ANA subjects control Room MVAC Information .

... . . . ... ...--. . . . . . .-.. .-..... Fo rwa rd ed ------------~~ - --

Frost FABIAN SANTA ANA at NESLS 9/16/93 10:1L7AM (4782 bytes 99 In)

Tot TNOMAS REMICK at NTJL6 oct FABIAN SANTA ANA, VINCENT BARONE at NESL4, FELICIA UDREA, PATRICIA YEACLEY at NEsL3, GOPAL PATEL at NESL2 Subjects Control Boon NVAC Information

Me s sa g e Conte nt s ----- ~~-- ~~----~~~ -----

Felicle, Flease research and provide the required information.

Please patch the input to m. prior to issue. Thanks Fabian 8/27/93 Fs CHARGE THIS TO CIR 92-086, 1.E. DBD.

PKY Pat, Please provide the charge number on this task. Thanks Fabian Fabian, We are in the process of doing a raanalysis of the ruel Mandling Accident radiologi:::a1 consequences. As a part of the analysis, control Room doses will be calculated. Can you suggest any goooa e r arences for the following Control Roos KVAC information? I have indicated the ,urrent values used in some analyses, or the value from current references. Also please let me know if you disagree with any of the values I have listed. Thanks!

Tom .

1. MV-9702 stroke time closed (Normal fan 1295 Train A discharge) - 6 seconds per N-4060-014 page 9 Calc. N-4060-014 dated 1980 uses UFSAR 6,4.2.2.2f as reference which indicated 6 seconds closure time. (Items 1 through 7)

2. NV-9703 stroke time closed (Normal fan E295 Train 3 discharge) -- 4 seconds per N-4060-014 page 9 3.

NV-9711 seconds perstroke time closed N-4060-014 page 9(Normal fan E295 Train 3 suction) -- 4 4.

NY-9712 seconds perstroke time closed N-4')40-014 page 9(Normal fan E295 Train A suction) - 6

5. NV-9778 stroke time open (Recisc 3 E419 suction) -- 6 seccada per N-4060-014 page 9

6. TV-9742 stroke time open (Emergency supply B A206 suction) == 6 seconds per N-4060-014 page 9

, 7. FV-9761 stroke time open (Emergency supply A A207 suction) -- 6 seconde per N-4060-014 page 9

8. Tacirc A E418 time to clear low flow condition - unknown, needed to I

I NES&L DEPARTMENT CALCULATION SHEET *e"

i PREUM. CCN NO.

Project or DCP/MMP_ SONGS 28d PAGE_0F_

Calc. No. N-4072-Q CCN CONVERSION:

CCN No. CCN -

Sutiloct Fuel Handfino AnMant (FHA) Inalde Cs.t. r.ri.ent - Ca.:ro: Ra.rn and Offsite Sheet D-r==sNo. 85 IWV OfuGNATOR DATE WIE DATE REV ORIGNATOR DATE WIE DATE R 1 R. Nakano 02 24 94 T. Remick 02 28-94 E y

4 determine A207 start time Need controls input.

9.

Recire B E419 time to c16er low flow condition -- unknown, needed to determine A204 start time poed Controls input.

11.

A304/7 intake filter efficiencies (based on 6 inch charocal depth):

l i Elemental lodine -- 994 (TS 4.7.5.c.3, RG 1.52 c.6.a, 8023-410-1-1-13)

Organic lodine -- 994 (TS 4.7.5.c.3, RG 1.t2 C.S.a. 8023-410-1-1-13)

Particulate iodine -- 994 (TS 4.7.5.c.2, RG 1.52 C.S.c) i Other Particulates ~~ 996 (TS 4.7.5.c.2, RG 1.52 c.5.c)

12. ; ,

E41s/9 recirculation filter efficiencies -- '

Activated carbon bed depth is 2 inch per Den Higgine as indicated on Drawing 5023-410-1-7, revision 11.

For ef ficiency use RG 1.52, paragraph C.6.a.

Elemental iodine -- unknown charcoal depth, need filter drawing organic iodine -- unknown charcoal depth, need filter drawing Particulate lodine -- 994 (TS 4.7.5.c.2, RG 1.52 C.S.c)

Other Particulates -- 994 (TS 4.7.5.c.2, RG 1.52 C.5.c) '

13.

A206/7 flowrote -- 2,050 cfm + 150 cfm = 2,200 cfm (Tech spec 4.7.5.a)

Two trains in service equals 4,400 cfm 14.

E41s/9 recircul.stion flowrote -- (35,485 cfm - 10%) - 2,200 cfm =

29,737 cfm (Tech spec 4.7.5.a)

Two trains in service equals 59,474 cra

15. Normal ventilation E295 flowrotes Rectro -- 29,s85 cfm per 40006 - 10% = 26,s97 cfm r Outside Air -- 5,820 cfm per 40096 + 104 = s,402 cfm -

16. Control Room untiltered air inleakage -- 10 cfm pet Standard Review Plan 6.4, Section. (II.3.d.3) III 3.2.11 .

17. Control Room volume - 244,398 ft3 per M-073-041, Revision 7 Control Room volume was changed to 244,398 ft3 in the Revision 5 of calculation is in the review M-073-041 datedPatel) cycle. (Gopal 1985. A volume recalculation 18.

Transit time from NVAC duct to RE-7524/25 -- 5.4 seconds per calculation A-92-NT-003 section 4 5 Weed controls input.

19.

Time when 'one intake train is secured -- e hours post-IACA per 30!

S023-12-3, Revision s Floating step FS-15 gG WO WYM p A# NAP MMIIs#'*dE D&

ys 29 W.

F) L" W hh l

, . NES&L DEPARTMENT CALCULATION SHEET ICCN W PREUM. CCN NO. PAGE.__ OF_

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072 003 CCN CONVERSION:

CCN NO. CCN -

, Subject Fuel Handlina Accident FHA) Inside Containment - Control Room and Offsite Doses Sheet No._11_

REY OfuGWATOR DATE WIE DATE IEV OfuGRATOR DATE flE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28-94 y 4

l 10.3 E MaII From J. Beebe (SCE) to T. Remick (Bechtel) l

sAwM (13] From IW at WEST 6 10/0/S3 9:18AM (3983 bytes: 47 In) l To: TWOMAS I et NES!J ecs MARK DRU t NEsL3, DAVE SNUCSS et WEST 7, PattICIA YEA 412Y at WasL3 Subjects Ret CR and FIIS NVAC Red Monitor Information j Nessage contente -.

Jin to support the new ruel mandling Accident in the Fuel sendling l Building analysis (per DSD Open Item Deport 93-085), I as leotting for some radiation monitor information. Per Dave Snugge, you can provide some of the ]

information I am looking for. If possible, could you Reall the following information to myself and Mark Drucker?

CR NVAC med Monitore RI-7834 & 7835

1. The detector setpoint.

For both gae abannels, we ta>= the Tech Spec alloweble limit (400 Cret) add background and multiply the reeg1 tant alewable limit by 0.871 (14 ZES drift l I

allowance) to get the trip value (400 CPM N 0.871 = 348 CPM le more eeneervative then the Tech Spec given Trip value of See Cppt + Bachpround).

Channel Trip setpointes 70 34 = [ 400 + 13 3. 3 ] x 8. 871 = 4 64. 5 CPN 7838 = [400 + 168.9) s 0.871 = 498.3 CPvt

3. The onlibration eenetante for the monitors for Er-SS, in (uC1/cc)/cym.

I enouse you have this eve 11able from the latest performance of procedure 8033-XIV-9.343 for each detector.

Kr-es Calibration Constante (uC1/oc/Cret) from the latest so33-Erv-9.343 Cs11brationes 7e34 3.33 m 1er-s and 3.33 x los-es civen by svf e710311e on 1/39/es.

7ess - 3.s6 x 1st-a and 3.13 x les-as elven by eve e30s07ss en s/1s/s2.

FEB NVAC Red monitore HE-7833 4 7823

3. De detector setpoints (for Unit 3 and Unit 3).

The Trip value for the FNIS See channele le 8700 Cptt Given by SEEBIO to FILE en 3/8/08 from Gerry Imer to Doug eregory. STEC assessed ma allowable limit of 10,000 CFut. We take 0.871 of this to get the 8700 Cptt Trip Value.

3. he salabration annetants for the monitore for Er-es, in (aci/ec)/ syn.

I saouse you have this available from the latest performanoe of procedure 8033-?.JT-9.343 for each detector.

3 assume you have this available from the latest performanoe of preeeu e 3033-IIv-9.343 for each detector (for Unit 3 and Unit 3).

Mr.85 Calibretion Constanta (uci/oc/CFIt) from the latest 9033=Erv-S.343 Calibretiens:

53 7823 3.13 x 10f-8 and 3.06 x 103-0 81ven by svs 88133175 on 4/30/09. - i

1 NES&L DEPARTMENT c .

CALCULATION SHEET M NO./

PREUM. CCN NO. PAGE_ OF_

Project or DCP/MMP SONGS 2&3 Colc. No. N-4072 003 CCN CONVERSON:

CCN No'. CCN -

. Subiect Fuel Handfino Accident (FHA) Inside Containment - Control Rcom and Offslie Doses Sheet No.1 fEV OfuGMATOR DATE NIE DATE REV OfuGNATOR DATE NIE DATE R E

1 R. Nakano 02 24 94 T. Remick 02 28 94 y 5

7833 - 3.14 m les-s one 3.es a 10s-es elven by evs 90013s00 on 3/3s/so.

93 7833 - 3.46 m 103-83 Siven by syf 90030304 en 3/17/90.

Taas - 3.34 m los-s and 3.30 m los-as siven by svf po1131st en 3/12/91.

Jim seene lo/a/s3 l i

7maaks for your assistanoe, Tom Basick l

l l

i

NES&L DEPARTMENT CALCULATION SHEET ICCN NO./

PREUM CCN NO. PAGE._. OF_

Project or DCP/MMP SONGS 2&3 Calc. No. N 4072-003 CCN CONVERSION:

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. Subject Fuel Handrina Accident (FHA) Inside Conteinment . Control Room and Offsite Doses Sheet No. _88 REV ORIG #dATOR DATE RE DATE REV ORIGINATOR DATE 1RE DATE IR 1 R. Nakano 02 24 94 T. Remick 02 28 94 E y

5 10.4 E-Mail from A. Bardia (SCE) to T. Remick (Bechtel)

$Q5%

1210) Fron ALEX BAADIA at WEST 7 1/20/94 10:49AN (4(91 bytess 05 in) ,

To: THOMAS REMICK at 1ESL2 ces MARE DRUCKER at ptSL2, PATRICIA YEACLEY at NESL3, CEARLES RAAMER, ALEK BARDIA subjects See CIR g2 019, 070, 071 Information seguest . Resp 0NSE To

.. - . . . - .. .. .. . .. ... ..... ... .. Me s s a g e Con t e n t s ... .. .... -. .. . .. . .- . .. . .- -- ..

Tom...

During my last trip to Aas-CE, I met with phil Rotondo (Mgr.

Fuel Mechanical Design). He indicated that the information contained in 5.CE-2666 was the result of a generic calculation that evaluated the mechanical integrity of the fuel rods in the event of a fuel handling accident with two impact modes, i.e.

vertical and horizontal.

When I asked Phil about the calculation issue date being over a year latter than the date of 5-CE-2666, he indicated thats a) ta his knowledge this is the only calculation that evaluated the fuel handling accident, and b) the results were probably known and circulated prior to formally designating the calculation as a QA record.

Also, see below for response to your questions.

Alexander He are in the process of preparing a new analysis for a Fuel Wandling Accident occurring in the Containment. We attempted to directly apply the guidance contain<d in letter 8.CE.2666, which is for an Fila that occurs in the fuel sandling Building, but were precluded by the following input assumptions:

1. 14tter 8-CE.2666 discusses a maaimum drop height of 254 f aches (21.11 feet).

2. Letter S.CE.2646 postulates that the damage occurs as the dropped bundle falls onto its side, striking a postulated protruding structure.

3. Retter 5-CE-2666 postulates no damage to the any bundles impacted by the dropped bundle.

tse have the following guestion regarding this accidents

' 1. To there specific CE guidance on the number of fuel pins that fail during an FuA in Containment?

seo, the only calculation that evaluated the mechaalcal integrity of feel rods in the event of a feel handling accident is the

,generic calculation 6370-610 66.

If the answer to question 1 is 30, we would like to see the following logic to apply the guidaene of s-CE-2666 to the ruA in containment.

a. The assumption of the dropped assembly impacting on a ,

postulated protruding structure (in letter 5.CE.26663 bounds the geometry present in the reactor cavity.

phil Rotondo le in s.greement with this assumption

b. Desed on our review of the Contalament drawings, it appears

' ^

NES&L' DEPARTMENT c

CALCULATION SHEET ECN W PREUM. CCN NO. PAGE _0F__

Project or DCP/MMP SONGS 2&3 Calc. No. N-4072-003 CCN CONVERSION:

CCN No. CCN -

Subject Fuel Hendrina Acendent FHA) Inside Containment - Control Room and Offsite Doses Sheet No. ._B.R._,

REV OfuGMATOR DATI ME DATE REV OfuGNATOR DATE RE DATE R R. Nakano 02-24 94 T. Remick E 1 02 28 94 y 4

9 that there to the possibility of a larger drop in containment, when a irradiated fuel sesembly being reloaded could be i dropped into an empty reactor vessel.' For this scenario, all 236 fuel pins will be postulated to fail (we calculate a drop height of no larger than 27.8 feet, with the actual value approximately 25 feet).

phil Aotondo also agrees that this is a conservative bounding assumption

c. If a fuel assembly is dropped onto irradiated fuel in the reactor vessel, no eted assemblies will be postulated to be damaged. This is ause the drop beight is reduced to

' approximately 13 feet (27.0 feet - 14.13 feet height of the assemblies in the core), reducing the impact energy.

phil Rotondo also agrees that this assusytton is valid given both the reduced impact energy and the energy absorbed by the assemblies being impacted

d. If a dropped bundle lande such that it is laying on the reactor flange, the t,-ight of water above the damaged pins would be less than 23 feet (by up to the 8.1 inch width of the bundie). It will be assumed that this decrease in the water depth will mot significantly affect the iodine removal by the pect water, since it represents only a 34 decrease in water depth.

phil motondo is in agreement with this assumption The mein item requiring cs input is the validity of item e above, since the structural elements surrounding a fuel assembly la the reactor are significantly different than for an assembly in the storage rocks. 2 imput on the overall approach would also be

epprecisted.

e

)

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