10
CIbTthre~+ Group DT (Records Withheld In Part)

FOIA/PA-2012-0170 - Resp 1 - Final - Group DR. Part 1 of 1. · eiio S 1%/daykt F ý3 M FP 'eisandift IIN/a 7.8I kF Md o ItIA 9*/ft&S%~wO-WDWUTC i OS (MWI M~M1~wdgmmuem~ffi~ Title:

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  • CIbTthre~+

    Group DT

    (Records WithheldIn Part)

  • SUMMARY OF SOURCE TERM INFORMATION SENT TO NARAC

    1-v 17Va 8h 224Aa 23-Ma 74_&_ 244s

    C~ Oleit01 0 5%JrdnRASCAL BVWRCore :iwentof

    •Power10%kiny

    -.

    • (l0/ayI 4~8I:

    Legend - I% FuelIDamage 100o 70 1 0 1 133 I -Iom:125 MArdi ffts/rvutrixRASCAL_rUns ulsx

  • __ I, __ *111~1 __ __ __ __ __ __ I __ __I- I I I- I -t t I I

    4. 4 4- 4 + + 4- 4 F + 4 4

    Legend

    % CoreDamage

    100 90 80 70 60 50 40 30 20 10 0

    m:\25 March files\matrix_RASCAL runs.xlsx

  • SUMMARY OF SOURCE TERV )RMATION SENT TO NARAC(16 RASCAL ant IELCOR RUN)

    I

    **~

    Wi-

    I

    MELCOR

    100 70 40 33 10 0 * * BWR Core Inventory Only

  • 100 90 80 rn CA An'-I

    7-7-7 4

  • Dose calculations that supported the March 16 press release and calculations sent to NARACData as of 03/25/2011

    Fule Melt (FM) and containment Fuel Pool Inventory released NARACDate sent Name of case release (%/Day) assumed Summary Note

    I I Ul Core U2 Core U3 Core U1 SFP U2 SFP U3 SFP U4 SFP

    Attachment 1 to March 16 Protective Action 100% FM RASCAL run, not sentPress Release 100%/day to NARAC.

    RASCAL run, not sentto NARAC. Adjusted

    3/16/2011 Attachment 2 to March 16 Protective Action 33% FM 33% FM, 100% N/A U2 power toPress Release 100%/day 100%/day released approximate source

    term from assumed

    damage.3 fresh

    batches + NARAC to use this

    4 old source term to-3/18/201 "Super Core" Trans- Pacific 33% FM release in batches N/A determine impacts to

    14 days 100%/14 U.S. west coastdays

    1/2 hour release duration based on mix of 100 "Worst-Case"

    3/19/2011 MELCOR Assessment - Long Term Station a containment failure shortly after S00 day off loaded fuel & 500 day scenario using best

    Blackout (LTSBO) Reactor Pressure Vessel (RPV) 16-hour release duration fuel 8- N/A estimate accident

    breach hour progressionrelease assumptions

    >1 rem TEDE Source Term from

    33% FM 33% FM 33% FM No Fuel Pool release assessed in this 7.8 km conference call withPlausible Realistic Scenaro 0.5%/Day 0.5%/Day 0.5%/Day scenario 14:33 UTC OSTP (Japan), DOE,

    March 24, 2011 NARAC and NRC

    33% FM >1 rem TEDE

    70% FM S inz hole 33% FM No Fuel Pool release assessed in this 12.6 km Source term Info from

    3/24/2011 Plausible Realistic Case PRC-V3 10%/day 60 psi 100%/day scenario 16:00 UTC Japan 3/21/2011internal March 25, 2011 Analysis Team

    pressure

    3 freshbatches +

    50% bDOE was directed by33% FM release in 4 old N/A the White House to33% M rleas inbatches

    3/26/2011 Intermediate Phase Supercore 100%/day 14 days 100%/14 generate report

    days

    M:\PMT\Major dose assessment matrlx.xlsx

  • (

    Dose calculations that supported the March 16 press release and calculations sent to NARACData as of 03/25/2011

    Fule Melt (FM) and containment Fuel Pool inventory released NARAC Note

    \:ýD-' --- " Name of case release (%/Day) assumed US 3S U4SFP SummaryUlCore I U2Core u3Core U1SFP U2_SFP U3SFP IU

    31S/2011 Attachment Ito March 16 Protective Action 100% FM N/A RASCAL run, not sentPress Release 100%/day to NARAC.

    RASCAL run, not sentto NARAC. Adjusted

    Attachment 2 to March 16 Protective Action 33% FM 33% FM, 100% U2 power to

    Press Release 100%/day 100%/day released approximate sourceterm from assumed

    damage.

    3 fresh

    batches + NARAC to use this33 M5% 4 old source term to3/17 - 3/18/2011 "Super Core" Trans- Pacific 33 Mrelease In 4odN/Aso ctemo33% FM daIn batches determine Impacts to

    100%/14 U.S. west coastI _days

    1/2 hour release duration based on mix of 100 "Worst-Case"

    3/19/2011 MELCOR Assessment - Long Term Station a containment failure shortly after 500 day off loaded fuel & 500 day scenarioes ingdbest

    Blackout (LTSBO) Reactor Pressure Vessel (RPV) 16-hour release duration fuel 8- N/A estimate accident

    breach hour progressionrelease assumptions

    >1 rem TEDE Source Term from

    Plausible Realistic Scenario 33% FM 33% FM 33% FM No Fuel Pool release assessed in this 7.8 km conference call with

    0.5%/Day 0.5%/Day 0.5%/Day scenario 14:33 UTC OSTP (Japan), DOE,March 24, 2011 NARAC and NRC

    33% FM

    S in2 hole >1 rem TEDE Source term info from70% FM 5 i 33% FM No Fuel Pool release assessed in this 12.6 km

    3/24/2011 Plausible Realistic Case PRC V3 10%/day 60 psi 100%/day scenario 16:00 UTC Analysis Team

    internal March 25, 2011pressure

    3 freshvt•T• •2z•"•"•' ' •";*"•"/'•"•batches + Ewadietdb

    Intermediate Phase Supercore NollIis 33% batches DOE was directed by3/26/2011 sou(r( terit irh nt to be used going forward doe 33% FM release in 4aold N/A the White House to

    to error in offload tirnn fu SPt #4 14 days 100%/14 generate report

    ___days

    / - 4-.-

    M:\PMT7\Copy of Major dose assessment matrix_03272011 .xlsx

  • g 01 Er Dose calculations that supported the March 16 press release and calculations sent to NARACData as of 04/03/2011Dose calculations that supported the Mairch 16 press release and calculations sent to NARAC

    Data as of 04/03/2011

    I/

    Fuel Melt (FM) and containment Fuel Pool Inventory released NARACDate sent Name of case release (%/Day) assumed Summary Note

    U l Core U2 Core I U3 Core U1 SFP U2 SFP I13 SFP U4 SFP S u4marAttachment I to March 16 Protective Action 100% FM RASCAL run, not sent

    Press Release 100%/day N/A to NARAC.

    RASCAL run, not sent

    to NARAC. Adjusted3/16/2011 Attachment 2 to March 16 Protective Action 33% FM 33% FM, 100% N/A U2 power to

    Press Release 100%/day 100%/day released approximate sourceterm from assumed

    I _damage.

    3 fresh

    "SuperCore" Trans- Pacific NO I w htsofi 50% batches + NARAC to use this

    3/17 3/18/2011 toIIis ,'o to he used going fo waid due to 33% FM release in 4 old N/A source term toiiI' t, offload t ,img fol 'ýP1 #4 ma1 l ,'t 100%/day 14 days batches determine impacts to

    31.1001 1 (6)) 1, .4 In NARIA( 100%/14 U.S. west coastI days

    1/2 hour release duration based on mix of 100 "Worst-Case"

    MELCOR Assessment - Long Term Station a containment failure shortly after 500 day off loaded fuel & 500 day scenario using best3/19/20 11 Blackout (LTSSO) Reactor Pressure Vessel (RPV) 16-hour release duration fuel 8- N/A estimate accident

    breach hour progressionrelease assumptions

    >1 rem TEDE Source Term from

    33% FM 33% FM 33% FM No Fuel Pool release assessed in this 7.8 km conference call with0.5%/Day 0.S%/Day 0.5%/Day scenario 14:33 UTC OSTP (Japan), DOE,

    March 24, 2011 NARAC and NRC

    33% FM3 F>1 rem TEDE

    70% FM 5 in2 hole 33% FM No Fuel Pool release assessed in this 12.6 km Source term Info from

    3i24r2011 Plausible Realistic Case PRC-V3 10%/day 60 psi lO0%/day scenario 16:00 UTC Japan 3/21/2011Internal March 25, 2011 Analysis Teampressure

    3 fresh

    Intermediate Phase Supercore Nof ) II h50% batches + DOE was directed by50% DOE was directedd by frwrddu 33 F 4ol

    3/26/2011 %0W fef, WMI 1i not to he tood *o.og f. ? ~due t 33% FM release in batches N/A the White House toto error n oload Ifing foi SPI, 114 f madi fent 100%/day 14 days 100%/14 generate report1 days er redayspr

    312, 11/ -1,01/jf RL • (w•/-•,' M-:\PMT\Major dose assessment matrix_04032011.xlsx

  • Dose calculations that supported the March 16 press release and calculations sent to NARACData as of 04/03/2011

    Dose calculations that supported the March 16 press release and calculations sent to NARACData as of 04/03/2011

    Fuel Melt (FM) and containment Fuel Pool inventory released NARACDate sent Name of case release (%/Day) assumed Summary Note

    U I Core U2 Core U3 Core Ul SFP U2 SFP U3 SFP U4 SFP

    3 fresh O ted tha

    70% FM, batches

    some ex- offloaded

    3/30/2011 Pessimistic Source Term for US Embassy in vessel, on plume Request from Japan

    Tokyo drywell 12/01/10, ,loellg Team

    venting 7 old b

    batches 'Previous runshive, bomiuded

    33% FM5 in holee l i

    3/31/2011 MELCOR version of "Plausible Realistic Case" 70% FM 60 i 33% FM No Fuel Pool release assessed in this mi/e " vi(futei ail

    (Ref OMT09 email to C. Tinkler & J. Shaperow) lO%/day 60 psi 100l/day scenario N/A Vahdite , i / 1 t1internal V3 r of RAY('ALpressure

    M:\PMT\Major dose assessment matrix_04032011.xlsx

  • oeftwe I

    3AWMIi i

    via/nil AnsdmmMISo Ma 6P om 3WFM 13MFK

    3NCKtbv 200*/day MA I

    3/17 - 3/16201 -Awwe ms Ptc&i 33% FMIWNA*l50k

    5*0bb@Wm+

    46MboOm10WA4

    dim

    dmweml

    NOJ fa andfN/A

    112 how rdumndwus bond an ISd Wr cmsftWELCOR Amussuisi - Lohw Term Sion a ScOMMLM11W*M*ES*fttr m0 aw Off mm"de tielI modd

    Obdw" (LYS PvmwqVWdjW 1640w rdeeme N

    mm~00 rsl

    3/24/2011 tauw eacCm.PC33%Mo ~ /211%/daykt eiio S F ý3 M FP IIN/a 'eisandift 7.8I kF Md o

    ItIA 9*/ft&S%~wO-WDWUTC OS (MWI i

    M~M1~wdgmmuem~ffi~