18
From: Sent: To: Subject: Attachments: RST01 Ho c Monday, April 18, 2011 1:26 PM (b)(6) FW: Answers for the questions on Fukushima Daiich NPS Attachment_2 DWpressure after N2).pdf; Attachment_l pressure).pdf; Attachment 6 water injection).pdf; Attachment_5 Survey map).pdf; AttachmentA(transfer line).pdf; Attachrrient _3 PCVcooling).pdf; Requests for assistance from the DOE.doc; Fukushima questions Apr 15 Answer) .docx DOE documents attached. Boron/seawater evaluation included. Larry Criscione Reactor Safety Team From: Versluis, Rob [mailto: [email protected]] Sent: Thursday, April 14, 2011 10:17 AM To: RSTO1 Hoc Subject: Fw: Answers for the questions on Fukushima Daiich NPS Fy i Rob Versluis +1-301-903-1890 o) b) 6) 3m) From: Kelly, John E NE) To: DL-NERT-AII Sent: Thu Apr 14 10:00:31 2011 Subject: FW: Answers for the questions on Fukushima Daiich NPS From: A, -T- [mailto:[email protected]] Sent: Thursday, April 14, 2011 9:04 AM To: Kelly, John E NE) Cc: [email protected]; [email protected]; [email protected]; [email protected]; [email protected]; [email protected]; N = ; [email protected]; [email protected]; [email protected]; [email protected]; [email protected]; )z *_Q; ll A; [email protected]; [email protected]; Onishi, Yasuo; [email protected]; [email protected]; hirohide.oikawa@toshiba .co.jp Subject: Answers for the questions on Fukushima Daiich NPS Dear Mr. Kelly, This is Kumano from TEPCO. DK 344 of 1892

Exhibit 4 – Answers from DOE in response to TEPCO

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From:

Sent:

To:

Subject:

Attachments:

RST01 Ho c

Monday, April 18, 2011 1:26 PM

(b)(6)

FW: Answers for the questions on Fukushima Daiich NPS

Attachment_2 DWpressure after N2).pdf; Attachment_l pressure).pdf; Attachment

6 water injection).pdf; Attachment_5 Survey map).pdf; AttachmentA(transfer line).pdf;

Attachrrient_3 PCVcooling).pdf; Requests for assistance from the DOE.doc; Fukushima

questions Apr 15 Answer) .docx

DOE documents attached. Boron/seawater evaluation included.

Larry Criscione

NRC Reactor Safety Team

From: Versluis, Rob [mailto: [email protected]]

Sent: Thursday, April 14, 2011 10:17 AM

To: RSTO1 Hoc

Subject: Fw: Answers for the questions on Fukushima Daiich NPS

Fyi

Rob Versluis +1-301-903-1890 o) b) 6) 3m)

From: Kelly, John E NE)

To: DL-NERT-AII

Sent: Thu Apr 14 10:00:31 2011Subject: FW: Answers for the questions on Fukushima Daiich NPS

From: A, -T- [mailto:[email protected]]

Sent: Thursday, April 14, 2011 9:04 AMTo: Kelly, John E NE)

Cc: [email protected]; [email protected]; [email protected]; [email protected];[email protected]; [email protected]; N = ; [email protected];

[email protected]; [email protected]; [email protected]; [email protected]; )z*_Q; ll A; [email protected]; [email protected]; Onishi, Yasuo; [email protected];

[email protected]; hirohide.oikawa@toshiba .co.jp

Subject: Answers for the questions on Fukushima Daiich NPS

Dear Mr. Kelly,

This is Kumano from TEPCO.

DK 344 of 1892

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In advance to the telephone meeting with you and TEPCO for today at 8pm EDT 9am JST Fri 4/15), I d like to send you

answers and some additional information about our plant status.

Also,a list of technical questions is attached which TEPCO would like to have assistance from the DOE.

Could you please distribute attached files to your colleagues who would join the meeting?I hope we will have good discussion on the meeting.

Best regards,

Yumiko Kumano

Yumiko KumanoTransport Engineering Group,

Nuclear Fuel Cycle Department,Tokyo Electric Power Company TEPCO)

TEL: +81-3-6373-5446

FAX: +81-3-3596-8545

(Text data is attached below.)

4/14/2011 TEPCO

Answers for the questions on Fukushima Daiichi Plants from DOE

Any information on the questions below will be used to refine analysis and options studies. These questions are motivated to

help improve analysis in four key areas: reactor status, long-term passive cooling options, spent-fuel pool analysis, and

wastewater treatment.

(b)(5)

2

DK 345 of 1892

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(b)(5)

3

DK 346 of 1892

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 b) 5)

4

DK 347 of 1892

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 b) 5)

5

DK 348 of 1892

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 b) 5)

 b) 5)

6

DK 349 of 1892

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(b)(5)

7

DK 350 of 1892

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Enhancement of Reactor Injection Reliability

April 12, 2011

L ong Term Cool ing Team

The Injection into reactors of Fukushima I U nit 1- 3 is presently continued with use of temporary

pumps driven by the power supplied via the Tohoku EPCs power grid. The followings are being

evaluated and implemented for enhancement of reactor injection reliability; (7 Multiplexing of

Pumps.

(2) Multiplexing of Power Supply and ®MDiversification of Injection Points. (9 Countermeasures for

Tsunami were also evaluated.

(D Multiplexing of Pumps

Current Status:

* Injection is carried out with use of one temporary pump (non-safety) for each plant

respectively.

Measures for Reliabil i ty Enhancement:

* A backup pump for non-safety temporary pump is being prepared. It was Installed on

April 12 and its test operation is planned on April 13 and 14.

* The header is attached to the outlet of the temporary pump w hich forms the line

configuration enabling water delivery using other pump when the pump fails => (Done).

injection by the fire engine is feasible as further backup => (Done).

(2) Multiplexing of Power Supply

Current Status:

* The power is supplied via the Tohoku EPC's power grid.

Reliabil i ty Enhancements:

a, * The temporary pump (non-safety) is powered by the temporary DG If the power from theTohoku EPC's grid is lost => (Done).

* The bus cable connecting the power supply system for Units 1 and 2 (from Tohoku grid)

with that for Units S and 6 (from T E P C O grid) is being installed => (Under Preparation).  Two dedicated power supply cars are deployed to supply the power to 6.9kV M/C of Unit

1/2 and Unit 3/4 power supply systems => (From Today)

(M Diversification of Injection Points

Current Status:

f injection for Unit 1 via F / W line is carried out by a temporary pump (Non-safety)

* Injection for Unit 2 and 3 is carried out via fire fire line - low head Injection l ine using a

temporary pump (non-safety).

Reliabil i ty Enhancements:

* Installation of one Injection l ine from F/W line and Increase of F1W l ine injection points

are being prepared. However, there is a concern that about 10 of injection water flow

into the condenser because sufficient boundary configuration is difficult in the high

radiation area.

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(FO Countermeasures for TsunamiCurrent Status:

- A temporary pump (non-safety) and a temporary DG are Installed near the deionized

water tank (low elevation). They cannot be accessed dur ing there occurs the Tsunami

warning.Y here Is a possibility that the large scale Tsunami could damage the t empora ry pump,

temporary DG, existing hose, etc.

Reliability Enhancements:

* Relocate Pump Control Panel and temporary DG to higher elevation to enable switchingover to pump star tup ope rat ion and temporary DG even w h e n the Tsunami warning Is

issued.Y he hose reinstallation will be necessary due the damage to the existing hose when th elarge scale Tsunami hits. Thus, the following material and equipment must be procured

and deployed.Fire hose - The 20m x 250 spools already ordered in addit ion to spares present ly

available3- Fire Engines - 10 fire engines are already deployed at higher elevation (by the

seismically Isolated emergency building

3 W ater Source - Headers and others which would facilitate connection of f ire hose

with pipe branch flange between filtered water , pure water tank and filtered water

tankTemporary Pump (non-safety) andTemporary G --Spare units are being preparedto enable existing equivalent facility after securing the power

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-7

 b) 5)

DK 353 o 1892

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DK 354 of 1892

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11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17

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11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1 2 3 4 5 6 7 8 9 10 12 13 14 15 16 17

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Attachment 2

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AttachmenExternal PCV Cooling example for 1F 01

b) 5)

DK 358 of 1892

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Assessment of External PCV Water Cooling

for Long-term Cooling: Achieve stable core cooling while mitigating release

radioactivity to the environment (atmosphere and ocean)

for 1F-1 (1F-3 would be similar)

* Current assumption: 6ton/hr of water injected in the core is evaporated; some portion ofwhich is released to the atmosphere or T/B with radioactivity.

* Due to external PCV cooling, steam released to the atmosphere accompanying

radioactivity will decrease in 3 months, but will not become zero. (PCV temp.: 112 °C)

* On the other hand, water cooling requires 40ton/hr of injection compared to the current

injection rate of 6ton/hr, leading to increased leakage to T/B.

* Access to R/B is necessary in order to conduct work on injection line for external PCV

cooling.

* Thus, we will increase water level up to TAF, maintain current water injection and, if

possible, prevent external released by early construction of upper roof. U Target externaPCV water cooling in 6 to 7 months when PCV temperature can be maintained below 100

°OC by injection rate of 10ton/hr.

for 1F-2

on closure of suppression pool leakage location by grout or alternativematerial.

*After closure of leakage location, basically same as for 1F-1, 3.

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 b) 4), b) 5)

DK 360 of 1892

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l~tcment

  b 4 , b 5