Exhibit 11 – Redacted Presentation from Nuclear Energy System Safety Division of JNES

8/12/2019 Exhibit 11 Redacted Presentation from Nuclear Energy System Safety Division of JNES

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Rev. 12011.4.21RESTRICTED

Plant Status Evaluation of IF-1, 2and 3from 25th March 0:00 to 8th April 0:00

April 212011Nuclear Energy System Safety Division

JNES

* The evaluation of the plant status are based on the available technical information till 8th April 0:00. W e acknowledge that theevaluation is ubject to change and refinement.

DK 1690 of 1892


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Plant Status of IF-1 from 25th March 0:00 to 8th April 0:00P: Reactor Pressure Vessel (RPV)

* Although there is small size rupture at the bottom head (e.g., instrumental penetrations or CRDhousings), most damaged / molten core remiains in RPV at the reactor core or vessel bottom(*1,*2).However, small part of damaged / molten core may be accumulated on D/W flpor (inside the lowerpedestal) through the breach.

* Cooling water is injected into RPV through FPN nozzles. Cooling water flows into inside of the shroudafter filling up the downcommer outside the shroud. The reactor water level has been around TAF -1,650 mm" at the flow rate of -10 m3/h ("2011/3/25).

*1:Total amount of injected water into RPV was; -4,700 m3 on 27th March. Total amount of steam couldbe generated by decay heat was estimated to be 2,800 M 3 . If the steam of -2,800 m3 was releasedfrom RPV to S/C through SRVs (i.e., SRVs were assumed to be stuck open), injected water of '1,900m3 still remained in RPV. However, it is unreasonable because the volume of RPV is around '280 M 3 .This implies that there are leak paths through RPV bottom.

*2: After the temperature of surface of RPV bottom increased over v400'0(2011/3/23), the flow rate wasincreased and maintained around -7,-8 m 3/h. This decreased the RPV surface temperature to120-150 0C(2011/3/24 or later). The increased flow rate made water ingression to hot damaged /molten core on the lower head, and then the cooling of damaged / molten core was promoted.

1


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wPrimary Containment Vessel (PCV)* Since D/W pressure (as well as S/C pressure) increased to -0.84 MPa (2011/3/12) and thetemperature of D/W atmosphere increased to -400C (2011/3/23), small leak paths are inferred.However, the leak tightness of PCV is kept to some extent.

The water through the vessel bottom breach flows into S/C through the vent pipes between D/W andS/C, after filling up D/W floor up to the lowest level of vent pipes(*3). This means water isaccumulated on D/W floor. The gaseous part is enough remain in the upper part of S/C, to functionthe vent pipes and the vacuum breakers between D/W and S/C (before ,-2011/4/7) (*4).

*3: This inference is based on that there are leak paths through the RPV bottom head, and that waterare continuously injected into RPV.

*4: The fact that D/W pressure is nearly same as S/C pressure, implies that vent pipes and vacuumbreakers are not flooded and can fulfill their functions.

2


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r PCV Pressurei The steam generated by decay heat is released through leak paths of D/W. However, the leaktightness of PCV is kept to some extent, D/W pressure is slightly higher than atmospheric pressure.r S/C pressure is 0.160 MPa. S/P temperature is 55C of which saturation pressure is 0.016MPa(2011/4/2 or later). Therefore, the gaseous part of S/C is filled with not only saturated steam butalso considerable amount of non-condensable gases (e.g., nitrogen, hydrogen, oxygen, noble gasesetc.)

D/W pressure (0.155 MPa) and S/C pressure (0.160 MPa) are almost same, since vacuum breakerscan perform their functions (2011/3/24 or later). In addition, the partial pressure of saturated steammay become higher than 0.016 MPa, if the thermal stratification is considered at the upper regionabove the lower end of the downcomer in S/P.*1: PCV pressure (DW pressure:0.155 MPa, S/C pressure:0.160 MPa) at the onset of nitrogenpurge(2011/4/7), slightly increased by the nitrogen purge to D/W Pressure of 0.175 MPa, and S/Cpressure of 0.170 MPa at 2011/4/17.

r RPV Pressurew Most of damaged / molten core remains in reactor core or in vessel bottom. The damaged core

uncovered by water heats up RPV (e.g., flange, vessel middle, lower head etc.), shroud, FW nozzlesand so on. The steam generated by molten core accumulated in the vessel bottom makes RPVpressure higher than D/W pressure (*2). The water and steam flow out through the breach of thebottom head(*3).*2: The reason why the indication of a channel A (0.190 MPa-g) defers from that of channel B (0.542

MPa-g) (2011/4/8) is hard to understand. However, the indication of cannel Bseems to be incorrect,because RPV pressure indicated by a cannel B has not followed D/W pressure at 2011/3/26 or later.*3: During the nitrogen purge period, where D/VV was pressurized, RPV pressure (0.464 MPa (absolutepressure)) deferred from D/W pressure (0.155 MPa) (2011/4/7). Therefore, it is inferred that thegaseous part of RPV does not open into the D/W atmosphere. 3


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r- RPV Temperature* The water flow rate into RPV was increased and maintained around 7-8 m3 when the temperatureof FW nozzles became higher than "400c(2011/3/23). Then, the temperature of FW nozzlesdecreased to r200 0C(2011/3/25). After that, the flow rate was slightly increased when thetemperature of FW nozzles became s300 oC(2011/3/28). Then, the temperature of FW nozzlesdecreased to ,,,250OC(V2011/4/1). This infers that the increase of the flow rate decreased the coreand shroud temperature, and indirectly decreased the temperature of FW nozzles.. The flow rate into RPV was increased and maintained around r,78,8 m3 when the temperature of thelower head of RPV became higher than -,400C(2011/3/23).Then the temperature of the lower headdecreased to ev120OCev150C(2011/3/25 or later). This infers that injected water reached the heatedvessel bottom due to the increase of the flow rate, and cooled the core debris on the vessel bottom.

4


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(b)(5)

Fig.1-1 Plant Status of IF-M around 3/31/2011 5DK 1695 of 1892


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Recommendations of Accident Managements for 1F=4F. Water Injection into RPVw The injection rate should be kept as minimum as required corresponding to decay heat in order tokeep the efficiency of venting from W W and to prevent a venting line inW/W from submerging.

The stable cooling for damaged / molten core in RPV has been kept for long days. Therefore; coolingwater injection to RPV via FW nozzle to outside of shroud should be kept in order to keep the stablecooling.; It is not recommended to inject cooling water to inside of shroud via CS lines because cooling waterinjection to inside of shroud could generate large amount of hydrogen and could progress thedegradation of core due to the heat generated by M-W reaction.

The further progression of degradation of core should be prevented by carrying out continual coolingwater injection since the upper part of RPV contains oxygen gas, hydrogen gas and noble gas. Thedepressurization of RPV can not be recommended. Non-condensable gases contained in RPV can flowinto D/W via S/C ifSRV or ADS are activated..P Accident Management for D/Ww It is not recommended to activate containment spray system since the containment spray watercauses reverse flow of air by steam condensation of steam in D/W.a It is not recommended to activate venting from D/W. If venting from D/W are activated, accumulatedwater on D/W floor and fission products contained inS/C pool as well as atmosphere of D/W can bereleased from PCV.

r Accident Management for S/C* The gaseous part of S/C contains hydrogen gas and oxygen gas by water radiolysis as well as steam.However, the possibility of hydrogen explosibn is small since the gaseous part is filled with saturatedsteam.* PCV venting from S/C with pool scrubbing is efficient for depressurization of S/C. It is necessary toconstantly monitor with pressure equalization between D/W and S/C so that vent pipes are not filledup with water and vacuum breakers are available. 6


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[kPa]9000

800 -

700 -

600

500 -

IFI ~t-flTiE5~3111 i4.46 Jm+9N-lAnL3/111 2:42 3IZ3,1-A 93/12 14:30 ".-I" .1j112 15:36 2k-.~3/112 20:20 }j_

Imm]0

-500

-1000I 4/7,1:30 N2r.NrJ42,I

;400

300

200

f*1l (MR,*4tOA) (mm)2lTh~A(kpag)

I - ?XItJ nuk1-

100 f .1

3/15 0:00 3/17 0:00 3/19 -DWWIIJ tJ [kPag]

S. . - rS/WJEtkWpag)IS/C1ii+t(kpag)

.nr4K.. __= ik..,.I.,:."n..

...- .i]' ~:,- rA.,.. ..-,,r7. .*ar:r

-1500

-2000

-i -25008 0:00:00 3/21 0:00 3/23 0:00

[kPagl

i3/25 0;00 3/27 0.00[kPagj

3/29 0:00 3/31 0:00 4/2 0:00t.'-S/C tb[kPagJ 4/4 0:00 4/6 0.00 4/

[mm]

/

Fig.i-2 Reactor pressure, water level, D/W pressure, S/C pressure (IF-1) 7


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-lil t '- --. --- .-W1/15tuvnJI- *I~:~~~ ft~i9ta3~p_If.4Cu4 , d ~ -f0Jl'~1%Sf?~2 S ~ A~-1 6

.flthi. 'ir a--~ l~tL,llF--Atu

VI II AM~ffITC~BOu.AOi 2,*, a)-

*4 W9 . .11W~I l c~...0*~1 .1&ROL

Patt~' r-~

a I WuI U2Z I

a/li VT/ -Via 0/14 v/ia ?f)4 v1 -Sln, 01 712n J/:1 V22 3fl3 3/Z4 01'245 4,111 V 7 41 28 J/1~9 V30 tIJI42 /a-ex. Gio 01M 0 oo1 1icimO QVn) aD 0,01 Q: Q DtO .0%Dn 0:03 0:00 goj floa OsXJ (X00 ThOO 4 3 0;.W 0%0 OOCcc~I W 5Z FRVttOtV~~Pt dk A lTYEi kFCttL ;7Pi

Fig.1-3 The amount of injected water into RPV (1F-1,2 and 3)8


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IF-i RPV 18:00

I I I I I I I I * I I : I I

400 _-(. L _.L L . J-- I - J .L.. . . .- -, . {40~T-rf

m LI I I I I I I I I I I:1 I I it b I I I I I I I I I

275 i .- -Il l ' ' r~4n 1 ~r:3, ,,zIA

I I I JAR

2 I :-- I I I

I I I / I I I 1 I

20 r---- -"T: " .. .. .. .. .

l, [ I I t I I_ _ _ _

125- L -

75 7 I I I I r I I , I

50 PI I I I I IT

25 1.----..... . .--- l ..T - --- ' ... "

3123/24 3 25 23/26/27 3/28 3 29 3/M0/31 1 4/2 4/3 4/4 4/5 4/6 417US84/9a.0 Mvftamaoaoa 0% 0.000 noa Mv0%aMv OsGeoa

t~ l tI I

Fig.1-4 The temperatures of some points around RPV IF-i)9

DK 1699 of 1892


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Plant Status of 1F-2 from 21th March 0:00 to 8th April 0:00r Reactor Pressure Vessel (RPV)

' There is the rupture at the bottom head (e.g., instrumental penetrations or CRD housings) (*1). Mostdamaged / molten core drops to the lower pedestal. Small amount of damaged / molten core remainsin RPV(*2).

F The water flows into the inside of the shroud via PLR exit nozzles and jet pump diffusers. The reactorwater level has been around TAF -1,500 mrm" at the flow rate of -10 m3/h.

*1:Total amount of injected water into RPV was '8,00 m3 on 27th March. Total amount of steam couldbe generated by decay heat was estimated to be -4,000 m 3 . If the steam of r4,000 m3 was releasedfrom RPV to S/C through SRVs (i.e., SRVs were assumed to be stuck open), injected water of ,-1,900m3 still remained in RPV. However, it is unreasonable because the volume of RPV is around ,-200 m3.This implies that there are leak paths through RPV bottom.

*2: It is inferred that the steam is dominantly generated in D/W based on the fact that D/W pressure ishigher than RPV pressure. The RPV surface temperature of 1F-2 is lower than that of 1F-1.

F. Primary Containment Vessel (PCV)v S/C is filled up with water, there is water level in D/W and bottom of RPV is flooded. The water levelin D/W is communicated with RPV via the rupture at the bottom head of RPV. The water level in RPVis higher than that in D/W because D/W pressure is higher than RPV pressure.w It is inferred that there are leak paths in S/C based on the fact that hydrogen explosion occured inS/C (or Torus Room) and there is a large amount of water which may leak from S/C pool.r Since D/W pressure increased to -0.75 MPa (from late at night of 14th to twilight of 15th March),leak paths are inferred in D/W. 10


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PCV Pressurer Since the steam generated by decay heat has been released through large leak paths of D/W, thepressure is around atmospheric pressure (v0.1MPa).r Since S/C pressure is rO.1MPa (the saturation temperature is 100'C) and S/P temperature is 100 0C,the gaseous part of S/C is almost filled up with the saturated steam, and very small amount of non-condensable gases (e.g., hydrogen, oxygen etc.) exist (*1).P There can be the gaseous part of S/C depending on the location of leak paths in S/C. S/P watercontinuously flows out through leak paths in S/C, since injected sub-cooled water into RPV flowsdown to S/C.*1: S/C temperature is 100c, of which the saturation pressure is -0.1 MPa. This infers that the breachand/or leak path exist at the upper part of S/C, and that S/C is almost flooded completely. Strictlyspeaking, S/C pressure is somewhat higher than D/W pressure, because D/W water level is higherthan S/C water level.

r RPV Pressurea Although a small amount of damaged / molten core remains in RPV, water is injected via PLR exitnozzles and jet pump diffusers. The water injection rate is .10m 3/h at room temperature(r2011/3/31). Therefore, the pressure of RPV is around 85kPa (slightly lower than the pressure ofD/W) because damaged / molten core in RPV is covered with water. The saturation temperaturecorresponding to 85kPa is 95CC. However, the shroud is heated by the heat conduction from thedamaged / molten core stuck to the shroud.F RPV Temperature* The temperature of FW nozzles was 10000 at the water injection rate of -20m 3/h (the water level inRPV was -TAF -1,200). When the cooling water injection rate was decreased to around 10 m3/h(thewater level in RPV was around TAF -1,500), the temperature of FW nozzles increased to 150-200C.

The temperature of FW nozzle is high, because of the radiation heat transfer / heat conduction fromthe damaged / molten core distributed around the shroud. The temperature of the leakage detectorof SRV is also increased in the same manner of FW nozzles.* RPV skirt temperature becomes high, because the gaseous part (air pocket) exists surrounded by RPVbottom head and the skirt. 11


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(b)(5)

Fig.2-1 Plant Status of 1F2 around 3/31/2011 12

DK 1702 of 1892


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Recommendations for Accident Managements 1F-2r Water Injection into R PV

(b)(5)

v Accident Management for D/W

(b)(5)

Accident Management for SIC

(b)(5)

13

DK 1703 of 1892


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[kPa] 1F2 [mml900

80 0

700

60 0

50 0

40 0

300

200

(100

I D/WF)j(2Pd)S54k.Pagi 3/1 1,4:46 --

3/14 6:342 ,,RCC13/15 0:0OW -4i 3/1Sho SPJ-,-~fi-CWS3/15 9:25 RI135Mf-idc.-J YO 1

I(mm)

5000

4000

3000

A 2000

1000

-100.0

-2000

-3000;

-4000

-5000

J_

umm mm.D/\&E-t(kPag)

0oT

-1003/15 0:00 3/17 0:00 3/19 0:00

KAc

3/21 0:00 3/23 0:00"1"

3/25 0:00 3/:27 0:00 3/29 0:00 3/31 0:00 4/2 0:00 4/4 0:00 4/6 0:00 4/8 0:00[KPsg3 --M -D/WlEt[KPaffj - S/CE t~aIJ r.* tt i

Fig.2-2 Reactor pressure, water level, D/W pressure, S/C pressure (1F-21 4


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250

20 0

150M

ID0

50

3/20 0.00 3/1 QOO/22 0:00 3/23 Moo/24 000 3/25 0:00 3/226O Z M 31 2a00 3/29 W1

Fig.23-1 The temperatures of some points around RPV (1F-2)15

DK 1705 of 1892


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1F-2 RPV L 114/7 19:40)I ItIFF ti ll l i I iI iI Ii ti-'- 111112 IF I Fi i I I I I F I I III F : II it Ft F ti ll F FI I , til IF ti I t

24. . I I I I . I I . . .. I 6I1 t I I I

F I Fllt til Fit Fl-I Iit Fl .it tSIFF iiFFF I FI FFI I PF t I [I.'Ii I lit lF F F t F F F F I I F I F t I * I F t

260 L_,,IF r F F IF I Fli i T i I rT I FI I 4 liF I I F240 t. LlitI t FtI 1FIt F F 1FFI i I I F F F F I IF I "F F F I I t i F

I i I F F F F I IF t F I F t I F F i i t F; t i iF 1FF I ,, Fi F tt.,ik Ft 1:i 1 t F

it 1 FIIF IF 1n v l~lll.P' IF I t F.JL It Il iFFi F81Ii .6 II ' I I F " I I t i "{)5

200-r-TJrUr------- -

Ft I: F il j i i Ii FtI',.i~i Ft It i ll' F I ;.'%fI I I '^IIo I l I

F F *F "I'F I Fat i I I I I 1 F- - I 1 F ' ' ' ' l/ itt P a-.;-JZ t FI130 rT7 F- t' l I [Iji ll I '| * I I 4tn I t l il l l

0 1- I I I I0I I I

3/2 Y ,/27/2 /2 3/3 33/3 41 1 4/ 4/ 4/ / 43 M 41 4/9It 160- 4-F--Ii t~ 16oK 170 of189

110 i.q Fi t it I~ F t F F i lI i F I ' I I I. t F t I F F.t&1 FjlIi F i F F I |I t I' . I. IF FI ( FII F F F F I i I.. t I

S I I I ? I lt t t F F t I I F F I I I t i FfI i t " I I t r i I t i l lI i lI F F v i tit F~Iii i I { ii ii ii iliII IFF Ii I ti F t| I tIII I II iF F I t il Fi t

t lt lI I iil| IJ I i Ii 1111II t FFi t F, ti i F I Fti I l Il 1FF F t F

3/25 3/26 3/21 3/2,8 3/29 3/30 3/31 4/1 4 2 4/3 4 4 4/5 4/ 4/-/ 4/8 4/9

Fig,2-3-2 The temperatures of some points around RPV (1F-Q)16

DK 1706 of 1892


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Plant Status of 1F-3 from 25th March 0:00 to 8th April 0:00F Reactor Pressure Vessel (RPV)

a There is the breach at the bottom head (e.g., instrumental penetrations or CRD housings) (*1). Mostof damaged / molten core drops into the lower pedestal. Small amount of damaged / molten coreremains in RPV (*2). The water flows into the inside of the shroud via PLR exit nozzles and jet pump diffusers. The reactorwater is around TAF -2,000 mm at the flow rate of -7 m3/h (-2011/3/29).*1:Total amount of injected water into RPV was -7,500 m3 on 27th March. Total amount of steam couldbe generated by the decay heat was estimated to be -4,000 M3. If the steam of -4,500 m3 wastransferred from RPV to S/C through SRVs (i.e., SRVs were assumed to be stuck open), injectedwater of 3'3,000 m3 still remained in RPV. However, it is unreasonable because the volume of RPV isaround -330 M3 . This implies that there is the breach at the bottom head of RPV.*2: It is inferred that the steam was dominantly generated by the damaged / molten core in the waterinside the RPV pedestal, because D/W pressure was higher than RPV pressure(r2011/3/21). The RPVsurface temperature of 1F-3 was lower than that of IF-.

E Primary Containment Vessel (PCV)S/C is almost filled up with water, and there is the water level in D/W(*3). Since D/W pressure ishigher than RPV pressure, the bottom of RPV may be submerged, and the water level of D/W may becommunicated with RPV via the rupture at the bottom head of RPV. It is implied that the significantsteam explosion and/or the MCCI did not occurred, because the damaged / molten core alreadyexisted in the water inside the RPV pedestal.

*3:The water level of D/W reached the level of level switch which was located at the OP 8,300 mm(2011/3/29), and this means vent pipes are submerged. 17


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r Primary Containment Vessel (PCV) continuedVent pipes between D/W and S/C were fully flooded, and there was the water level in D/W. D/Wpressure (0.107 MPa(0.006 MPag)) was almost same as RPV pressure (0.OlMPag) (2011/3/31).The water level inside the RPV pedestal is higher than that of D/W outside the pedestal, because ofthe steam voids generated by the damaged / molten core inside the RPV pedestal. (i.e., The voidcollapsed water levels are same for the inside and outside the RPV pedestal.) The bottom of RPV maybe submerged, and the water level of D/W may be communicated with RPV via the breach at thebottom head of RPV (2011/3/31).Leak paths may exist in D/W, based on the facts that D/W pressure (and S/C pressure as well)increased to ,-0.64 MPa ( -,2011/3/13), that the temperature of the D/W atmosphere increased to,-400C (r2011/3/23), and that the hydrogen explosion occurred in thle R/B (2011/3/14) (*1).

*1 Total amount of injected water was up to -7,500 m3, which exceeded the free volume of PCV(-2011/3/27). Therefore, it is obvious that the steam generated by the decay heat was released fromD/W. In fact, D/W pressure already became around atmospheric pressure.r The shield plug on PCV may be covered by the water, which was injected to the spent fuel poolregion after hydrogen explosion. The water flowed into the space above the PCV top head throughthe clearance of the shield plug (*2). When the temperature of D/W atmosphere increased to

300r400C(r,2011/3/23), the gasket of PCV flange might ruptured by the over heating.These facts infer that RPV was cooled by thle water in the space above the PCV leaked into D/Wthrough the ruptured gasket, during the period where the large amount of water was injected intoSFP.

*2 Even if the condition of the shield plug is normal, water leaks/flows into the region around the top ofPCV through the gap of the shield plug (i.e., the shield plug is composed of 9 pieces of concreteplates). It is likely that the shield plug was damaged, because of the hydrogen explosion in R/B. Inthat case, water flows more easily.

18


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PCV Pressurei Since amount of steam generated by decay heat has been released through leak paths of D/W, th e

pressure of D/W ismaintained around the atmospheric pressure (NO.1MPa) N2011/3/21).v The leak tightness of S/C is aintained at a ertain extent, and D/W is looded by the water up to acertain level. The gaseous part of S/C is ompressed and ismaintained at higher pressure than th eatmospheric pressure.

Because the temperature of the water flowed from D/W floor to S/C is bout 100 C, the partialpressure of non-condensable gases shares the pressure over 40.1 MPa (N2011/3/25).

RPV PressureSmall amount of damaged / molten core remains in PV. The water isnjected into RPV via PLR exitnozzles and jet pump diffusers. The water injection rate is 7 m/h t room temperature (2011/3/31).The RPV pressure (0.01 MPag) is lmost same as D/W pressure (0.107 MPa (0.006 MPag)), becausethe damaged / molten core in PV is ubmerged inhe water. The saturation temperaturecorresponding to the RPV pressure isN103'C. However, the shroud is eated by the heat conductionfrom damaged /molten core which stuck to the shroud (2011/3/31).

*1 he RPV pressure was measured by channels And C,ince a hannel Bailed (N2011/3/21), Thereason of the difference between a hannel A0.01 MPag) and a hannel B-0.09 PMag) is ot clear.However, the indication of a hannel A s robably reliable, because the indication of a hannel C s ,0MPa (absolute).

19

DK 1709 of 1892


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F RPV TemperatureF The temperature of FW nozzles became around 300 0C (v2011/3/23), Around this moment, RPV wasconsidered to be cooled by the water flowed via the degraded gasket from the space above PCV tophead where the water is accumulated. Another possibility is the effect of the water increased injectioninto RPV at the flow rate of 30 m3/h (The start timing is unknown).r The temperature of the lower head became -2500C on March 23th 0:00. At this moment, RPV wascooled by the injected water at the flow rate of 30 m3/h, and the temperature decreased to ,-,1000C(,,s2011/3/26).

20


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(b)(5)

Fig.3-1 Plant Status of 1F-3 around 3/31/2011 21DK 1711 of 1892


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Recommendations for Accident Managements for IF3Water InjectionI

into RPV

(b)(5)

Accident Management for D/WI

(b)(5)

F.:Accident Management for SICI

(b)(5)

22

DK 1712 of 1892


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*[kPa]900

700

1F3i D/WffIJS54kPag(2kd)i

[mm]0

S-500*1- .1. I r...

600

5GO

400

300

200

100

3/15 0:00

Ip -

_1 o

-1500

-2000i ft.rXA,_0,* JJB) (mm) I .k i,,,, _0

. -fr.- r. e . . . _,, p.W .r0 1 V.99,- a"i . )/W LBE (kPag) M'1MT1i1 -2500

3/17 0:00 3/19 0:00[KPag]

" ; M I, a.(k Pg) I i-3000

3/21 0:00 3/23 0:00 3/25 0:00 3/27 0:00 3/29 0:00 3/31 0:00 4/2 0:00 4/4 0:00 4/6 0:00MD/WJh[Kpag] I-SaCfft[KpegJ 0-#iEA m I ){[KPagl [KPag) MAW11t) [mm]

Fig.3-2 Reactor pressure, water level, D/W pressure, SI pressure (1F-3) 3


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0:30 15:30 18:02 10:10

550 i i-- * -3 /2222:35

405 -- --.- - .9k,

(b)(5)250 . .

ITI I0

3 19 3/20 3/21 3/22 3/23 3 24 3 25 3/26 3 27 a/28 3/29

Fig.3-3-I. The relationship between the timing of SFP injection and thetemperatures of some points around RPV 1F-3) 24DK 1714 of 1892


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600II I I I Ia a I a a

aI a]I a* *a a

S. a.. I I - a aaI a a a al a aI IJ I I a a I a

3w .. .... i ,--.--4---)(,---,I-----

I5 a *a a a i a " a a aa: a a a a a a a a i ia a i

I :I

4a I Ia[ al I a I I

1 a I a.iaa a a a I i a i a a I I

Q' i a a p a a(b)(5)jaa a a I I t I a a a a a a aa l 1 a I a a a a a a a a a a a aa a[ a a a a a a a a i a a a a a

50 -i.- r*- --- -------- r----I--a----------- ------'T --''''----'-'--- -

mou % 0 am a.1 aO aG aO aw a a a0 a ao .0A

mPAAAMAIAIA wh 9 a t ~ i a

1 T t oI a

50II 25iL* I1 of 1892

P am a a a a arLI I

DK 115Io 189

Exhibit 11 – Redacted Presentation from Nuclear Energy System Safety Division of JNES

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Transcript of Exhibit 11 – Redacted Presentation from Nuclear Energy System Safety Division of JNES