ML13140A210.pdf - Nuclear Regulatory Commission

From:Sent:To:Cc:Subject:Attachments:

RST06 HocSunday, April 10, 2011 4:54 AMHoc, PMT12RST01 HocPARs for Deputies Meeting Revll.docxPARs for Deputies Meeting Revll.docx

Revised items 1 through 10 under Phase 1 technical stability section to reflect most recent changes.

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From:Sent:To:Subject:Attachments:

Hoc, PMT12Sunday, April 10, 2011 1:40 AM

RST06 HocPARs for Deputies Meeting Rev11PARs for Deputies Meeting Rev11.docx

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From:SentTo:SubjectAttachments:

UA06 HocSunday, April 10, 2011 6:18 PM

UA08 HocFW: Latest Composite PaperPARs for Deputies Meeting Revl4 Trish Milligan and RST input 04-10-11.docx

Liaison Team DirectorU.S. Nuclear Regulatory CommissionOperations Center

From: Hoc, PMT12Sent: Sunday, April 10, 2011 6:17 PMTo: LIA06 HocCc: LIA06 HocSubject: Latest Composite Paper

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From:Sent:To:Subject,Attachments:

Hoc, PMT12Sunday, April 10. 2011 1:39 AMRST06 HocFW: Integrated document from Trish MilliganPARs for Deputies Meeting Rev0 (3).docx

From: PMT01 HocSent: Sunday, April 10, 2011 12:43 AMTo: Hoc, PMT12Subject: FW: Integrated document from Trish Milligan

From: McDermott, BrianSent: Friday, April 08, 2011 4:02 PMTo: PMT09 Hoc; PMT01 Hoc; Cool, Donald; Zimmerman, Roy; Blount, Tom; Hiland, PatrickSubject: Integrated document from Trish Milligan

Attached is the document that Trish was working to integrate today, based on direction from last night.(b)(5)/

Once clarity is gained regarding the desired product, I recommend using the Task Tracker to document the conclusionssuch that subsequent shifts will be able to clearly understand the deliverables. I also recommend that all parties presentfor the alignment discussion review the Task Tracker language, to ensure the best possible description of thedeliverables is provided for the oncoming shift.

Brian

Contact Group Name: Industry Consortium

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From:SentTo:Subject:Attachments:

Hoc, PMT12Monday, April 11, 2011 12:46 AM

RST06 HocRed line and clean copies of the Permanent Re-Entry latest rev.

PARs for Deputies Meeting Rev14 clean copy Trish Milligan and RST input

04-10-11.docx; PARs for Deputies Meeting Rev14 Trish Milligan and RST input

04-10-11.docx

Attached. This is located in M/Fukushima/Papers. Tx greg

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Formatted: Font (DeWt) Arlat 11 pt, Do notcheck spelling or grammar

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ak3PaperskPARs fGr DopUtiBS Meoting ReVI 3 TrFish MiHligan and RST iqput 04 00 11 ldocx Page 5

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Wittick, Brian

From: Wittick, BrianSent: Tuesday, April 12, 2011 9:42 AMTo: Emche, DanielleSubject: Re: Read out from 4/11 and 4/12

If it is OUO it should not be shared outside US channels.

Sent from NRC BlackBerryBrian Wittick

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From: Emche, DanielleTo: Wittick, Brian; Doane, Margaret; Mamish, Nader; Foggie, KirkCc: Abrams, Charlotte; Bloom, StevenSent: Tue Apr 12 09:38:15 2011Subject: Re: Read out from 4/11 and 4/12

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DanielleSent from an NRC BlackBerry.

From: Wittick, BrianTo: Doane, Margaret; Emche, Danielle; Mamish, Nader; Foggie, KirkCc: Abrams, Charlotte; Bloom, StevenSent: Tue Apr 12 09:03:59 2011Subject: Re: Read out from 4/11 and 4/12

It should probably be marked OUO and controlled accordingly.

VR


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From: Doane, MargaretTo: Emche, Danielle; Mamish, Nader; Foggie, KirkCc: Abrams, Charlotte; Bloom, Steven; Wittick, BrianSent: Tue Apr 12 08:28:56 2011Subject: Re: Read out from 4/11 and 4/12

Daniel•ie and BrianThere is going to be a meeting at the IAEA with the US, on Japan invoking the assistance convention. Any concern withme sending this note to them. The assistance discussion would help.Margie

Sent from an NRC BlackberryMargaret Doane

From: Emche, DanielleTo: Doane, Margaret; Mamish, Nader; Foggie, KirkCc: Abrams, Charlotte; Bloom, Steven; Wittick, BrianSent: Tue Apr 12 07:15:30 2011Subject: Read out from 4/11 and 4/12

Email your questions. It is 8:15 and we haven't had dinner or lunch! You better read the whole thing ©

Danielle

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To:

Subject:Date:

Harrinnton. HollyMcIntyre. David Brenner. Eliot

RE: U.S. Nudear-Disaster Preparedness Hobbled by Uncertain Chain of CommandTuesday, April 12, 2011 8:42:29 AM

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Eliot - I can send to Brian McDermott and ask them to review. We may want to come up with a

blog post to address the general issue.

Holly

From: McIntyre, DavidSent: Tuesday, April 12, 2011 8:24 AMTo: Brenner, Eliot; Harrington, HollySubject: FW: U.S. Nuclear-Disaster Preparedness Hobbled. by Uncertain Chain of Command

Not sure this ProPublica piece would make it into our clips. Discusses potential chaos as

locals, fcds do power struggles during an emergency.

From: Dave McIntyre [mailt (b)(6)

Sent: Tuesday, April 12, 2011 6:42 AMTo: McIntyre, DavidSubject: U.S. Nuclear-Disaster Preparedness Hobbled by Uncertain Chain of Command

I would like to share this link with you:

Http://www.propublica.or,/arti ce/u.s.-nuclear-disaster- preparedness-hobbled- by-uncertain-chain-of-command

From ProPublica - journalism in the public interest. Sent using the ProPublica iOSapp.

Dave

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RSTO1 HocWednesday, April 13, 2011 3:23 PM

ET02 HocFW: Daiichi Electrical Injection Status.docxDaiichi Electrical Injection Status.docx

From: DiRito, Paul J (WANO) [mailto:[email protected]]Sent: Wednesday, April 13, 2011 12:38 PMTo: RSTO1 HocSubject: Daiichi Electrical Injection Status.docx

Res•ricLd O•risbulion: Copyright C 2011 by the Institute of Nuclear Power Operlorts. Not for sale or for commercial u.e. Reproduction of this report withot mheprior writ!an consent of INPO is exprelssly orolhibite-d.. Unauthortzed reproductlin is a violation of appicable Law. The person or peerso's trial are tumiP.ed ccpies ofthis reoc-rt should not deliver or transfer this rekort to any third party, or make tnis report or its contents public. withoul the prior agre.emnent of INPO. AlD other ,ightsreserved.

DISCLAIMER:This e-mail ard any of its attachments may contain proprietary INPO or WANO nforrnriaon t'hat.Is pnvifleea, confidential, or protected by copyright belonging toINPO or WANO. This e-mail is intended solely for the use of the individual or entity for which It is intended. if you are not the intended recipient of ihis e-mail. anydisseminaiton. distdribu'in, oapyino. or action taken in relation to te .ontenLt of and attachments to this a-mail is contrar to the rghts of PNPO orWANO and isprohibited. It you are not the Intended recipient of this e-mail, please notify th•e sender immediately by return e-mail and aerrnanenaly delete te anginal and anycopy or printout of this e-mail and any .tL•snmen-ir.Thank you.

&I/1e

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April 10, 2011

From: LIA0i HocSent Wednesday, April 13, 2011 5:47 PMTo: Aaron Leong; Al Hochevar; Aleshia Duncan; Alice Caponitii (b)(6)

Blake Crowe; Blarney, Alan; Blount, Tom; Boger, Bruce; Bruce Howard; Casto, Chuck;

Christensen, Harold; Christopher Green; Claire Berger, Craig Gaddis; Daniel Piccuta;

Daniel Piccuta; Daniel Russel; DORLCAL Resource; Dorman, Dan; DprNrrCal Resource;Emche, Danielle; ET05 Hoc; ET07 Hoc; FOIA Response.hoc Resource; Geoffrey Wiggin;

Giitter, Joseph; Glenn Southern; Heather Dresser; Holahan, Vincent; HOO Hoc; INPO;

INPO: INPO: INPQ: INPO; INPO; INPO; INPO; James White; James Zumwalt;(b)(4) I Jay Tilden; Jeffrey Bader; Jeffrey Miller; Jeremy Mears; John

Peters; Joseph Donovan; Joseph Young;.[ (b)(4) IJustin Cooper; Kenneth

Spurlockf (b)(4) [ LCDR Daryn Moorman (USN); Lee A Gard, (INPO);

LIA01 Hoc; LIA06 Hoc; LIA08 Hoc; LIAll Hoc; Lt Trevor Conger (USN); Mark Wall;

McDermott, Brian; McGinty, Tim; Michael Schiffer, Miller, Chris; Monninger, John;

Morris, Scott; NRC Liaison at USAID; OST02 HOC; PACOM Watch Officer; PentagonJapan Crisis Team J-4 Desk; Peter Lyons; Hoc, PMT12; Raymond Greene; Riaz Awan;

(b)(4) t Rick Nielsen; Robert Gambone; Robert Luke; Robert Mercer;

Ron Cherry, DOE-Japan Embassy; Ross-Lee, MaryJane; RSTO1 Hoc; RSTO1B Hoc; Russell

Morales: Rust Deming; Sal Golub; Sal Golub; Samuel Young; Simon Schuchat; Stahl,

Eric; Stephen Gabri; Stephen Town; Steve Aoki; Suzanne Basalla; Tim Cipullo; Tom

(b)(4) Virgilio, Martin; Weber, Michael; Wiggins, Jim; WilliamSBerger, Wiam Webster, Wittick, Brian; Zimmerman, Roy

Cc: Blarney, Alan; Wittick, Brian; OST01 HOCSubject. CANCELLED: Consortium Call for Wednesday April 13th

The next Consortium Call will be held on THURSDAY April 1 4th at 2000hrs. to better align with the new schedule of

Cabinet meetings in Japan.

Thank you

Lisa

Lisa Gibney WrightLiaison Team Coordinator

US Nuclear Regulatory CommissionEmail to: [email protected]

Desk Ph: 301-816-5185

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ET02 HocWednesday, April 13, 2011 3:36 PMOST01 HOCRST01 HocFW: Daiichi Electrical Injection Status.docx

Daiichi Electrical Injection Status.docx

EST Support (OST01.hoc):Here's something that I assume is for the ET Director.

RST01:Please send all e-mails to OST01.hoc if you want information to be given to the ET Director.

Thanks....karen Jackson, est response ops sys mgr

From: RST01 HocSent: Wednesday, April 13, 2011 3:23 PMTo: ET02 HocSubject: FW: Daiichi Electrical Injection Status.docx

From: DiRito, Paul 3 (WANO) [mailto:[email protected]]Sent: Wednesday, April 13, 2011 12:38 PMTo: RST01 HocSubject: Daiichi Electrical Injection Status.docx

Rest"xted Dstribution: Copynght Q? 2D1 1 by the insitute of Nuclear Power Oper-abons. Not for saie or for ccmniierctai Lse. Reproduction ef this renor wi!hout theprior written consent of INPO -is expressly prohibited Unauthorized reprodubt•ic is a violation cf apolicatie law, The le!on or permcns that are fumisrned cories oftis reporl snhbuld not deliver, tracl_,_ this remr, tc, Irany ttrira party, or mnaie, !iis report or if r.,ccn!rnts pubiir. withc.;j Irre Lior aqreemenl of INPO. All other rihts

reserved

.D!SCLAiMER:This e-mail and any of i!s attachments may contain propnre!ary lltO or WANO intcrnatrcn that is prrvil. ctdertIuI, o; protected by copyrryht beoriging toINPO or WANO. This e-mail ;s Intended solely for the use of the indjvidtial or enrity for vwhich it is intended..If you are not the intended recipieni of dris e-melt anycissemination. distribution. copying. or act.on taken in retalion Io rhe contents i4 and 3aach menls, to thIs .-moil !S contrar, to 0he right.' of INPO or WANO end isprohibited. If you are not :tie inýendecl recipient of lltis e-mail. pleo7 notify the sender inmediately by return e,-m-rl and I3PfmanenlIV delete the cr.,inal and rarcopy or printo.t of this e-rnal and apny n.tachmenLsThank you.

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April 10, 2011

From: OST01 HOCSent: Wednesday, April 13, 2011 7:49 AM

To: Weber, MichaelSubject: RE: RESPONSE - IAEA Technical Briefing Summary for April 12, 2011

Mr. Weber,

You are correct about the round-about way that this gets to the EST Coordinator. I have added you to the DistributionList for the IAEA documents we receive.

V/r,Rebecca Stone

EST Coordinator

From: Weber, MichaelSent: Wednesday, April 13, 2011 7:41 AMTo: OSTO1 HOCSubject: RESPONSE - TAEA Technical Briefing Summary for April 12, 2011

Thanks, Rebecca. From the email string below, it appears that LIA02 is on Mark Shaffer's distribution list. Note thp /document we are discussing is not a product of the State Department and the HOO is not on Mark's distribution.would like to receive Mark's daily report.

From: OST01 HOCSent: Wednesday, April 13, 2011 7:21 AMTo: Weber, MichaelSubject: RE: RESPONSE - IAEA Technical Briefing Summary for April 12, 2011

Mr. Weber,

The HOOs are on State's distribution list for the IAEA documents. Any emails sent to the HOOs get forwarded to the EST'Coordinator. From there, we forward them to the current ET Director. If you would like to be added to our distributionlist or have any additional questions, please notify the EST Coordinator on shift at [email protected].

V/r,Rebecca StoneEST Coordinator

From: Wiggins, JimSent: Wednesday, April 13, 2011 7:02 AMTo: Weber, MichaelCc: OST01 HOCSubject: RE: RESPONSE - IAEA Technical Briefing Summary for April 12, 2011

Don't know the author. It's a report that supported a press opportunity that occurred 4/12. NHK ran a story onit overnight. I got it from OST01. OST01 - do you have a source for the IAEA report?

From: Weber, MichaelSent: Wednesday, April 13, 2011 6:54 AM

To: Wiggins, JimCc: Virgilio, Martin; Doane, Margaret; Mamish, Nader; Golder, Jennifer; Shaffer, Mark R; ET05 Hoc; ET01 Hoc; OST02HOC; Dyer, JimSubject: RESPONSE - IAEA Technical Briefing Summary for April 12, 2011

Thanks, Jim. Is the document that you attached from the IAEA Technical Briefing a productprepared by Mark in Vienn/based on the Technical Briefing? I found the summary to be useful and informative.

From: Wiggins, JimSent: Wednesday, April 13, 2011 5:32 AMTo: Virgilio, Martin; Weber, Michael; Dyer, Jim; Carpenter, Cynthia; Boger, Bruce; Johnson, Michael; Zimmerman, RoySubject: FW: IAEA Technical Briefing Summary for April 12, 2011

Se the attached FYI

, heard overnight that a remote visual check of the U4 SFR indicated water over the top of the fuel bundles '

%5-10 ft) -

From: LIA08 HocSent: Wednesday, April 13, 2011 5:23 AMTo: RST07 Hoc; Hoc, PMT12; Wiggins, JimSubject: FW: IAEA Technical Briefing Summary for April 12, 2011

For your info. Jeff Temple

From: LIA02 HocSent: Wednesday, April 13, 2011 4:19 AMTo: LIA08 HocSubject: FW: IAEA Technical Briefing Summary for April 12, 2011

From: Shaffer, Mark R [mailto:[email protected]]Sent: Wednesday, April 13, 2011 4:19 AM

- To: Shaffer, Mark R; Scheland, Mark DL; IAEA Vienna; Davies, Glyn TCc (b)(6)

(b)(6)

Subject: IAEA Technical Briefing Summary for April 12, 2011

IAEA Technical Briefing on Fukushima Accident - April 12, 2011

The IAEA Technical Briefing on April 12 was led by Deputy Director General Denis Flory, and supported by Mr.Miro Lipar, from the Division of Nuclear Installation Safety; Ms. Elena Buglova, Acting Director for the Incident& Emergency Center: and Ms. Maria Betti, Director of IAEA's Marine Environmental Laboratories in Monaco.

Current SituationOverall, the situation at the Fukushima Daiichi plant remains very serious, but there are early signs of recoveryin some functions such as electrical power and instrumentation.

Provisional INES Level 7 Rating

IAEA confirmed that the Nuclear and Industrial Safety Agency (NISA) has submitted a provisional InternationalNuclear and Radiological Event Scale (INES) Level 7 rating for the accident at the Fukushima Daiichi nuclear

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power plant. This new provisional rating considers the accidents that occurred at Units 1, 2 and 3 as a singleevent on INES and uses estimated total release to the atmosphere as a justification.Previously, separate provisional INES Level 5 ratings had been applied for Units 1, 2 and 3.The provisional rating was determined by NISA after it received the results of the analysis conducted by theJapan Nuclear Energy Safety Organization (JNES). NISA then applied the INES assessment methodology tocalculate the total estimated release in terms of radiological equivalence to 1-131.

Based on this provisional assessment, NISA concluded that the accident would be provisionally rated INESLevel 7 as per the definition in the 2008 Edition of the INES Manual, which identifies a level & accident as "Anevent resulting in an environmental release corresponding to a quantity of radioactivity radiologically equivalentto a release to the.atmosphere of more than several tens of thousands of terabequerels of 1-131."NISA estimates that the release of radioactive material to the atmosphere is approximately 10% of theChernobyl accident, which is the only other accident to have an INES Level 7 rating.

Protective Measures

"On April 11, the Government of Japan announced that they had concluded to establish 'Planned EvacuationAreas' and 'Evacuation prepared Area' in the areas beyond the 20km radius from the Fukushima Daiichinuclear power plant. The review was conducted because the Government considered the safety of residentsits first priority. The Government of Japan considered the standards recommended by the InternationalCommission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA) as part ofthe review.

With regard to the 'Planned Evacuation Areas', the Japanese authorities have found that the areas beyond 20km radius could be exposed to over 20mSv during the course of the next one year, approximately until nextMarch. Therefore the Government of Japan will be consulting with the local communities in terms of plannedevacuations, ant at this juncture they are hoping that this planned evacuation will be carried out during the nextmonth to come. The Planned Evacuation Areas that have been newly designated for evacuation includeKutsurao Village, Namie town, litate village, a part of Kawamata town and a part of Minami Souma City.

The Government also defined a second new area called the 'Evacuation Prepared Area'. This area includesthe area previously defined as the 'Indoor Evacuation Area' between 20 and 30 km from Fukushima Daiichi,but excludes those areas designated above as 'Planned Evacuation Areas'.Within the 'Evacuation Prepared Area' people living in this area should be prepared for indoor evacuation orevacuation (outside of this area) in case of emergency. Voluntary evacuation is recommended within this area.Children, pregnant women, people who require nursing care and those who are hospitalized should not enterthis area. Kindergartens, pre-schools, elementary schools, junior-high schools and high school will be closedwithin this area."

Earthquake of 11 AprilWith regard to earthquake that occurred in Japan at 08:16 UTC, on April11, the IAEA International SeismicSafety Centre rated it as a 6.6 magnitude, revised from an initial 7.1 magnitude. The epicenter of theearthquake was in Fukushima Prefecture, 68 km from the Daiichi nuclear power plant. The epicenter wasinland at a depth of 13.1 km. The IAEA contacted NISA who confirmed the following regarding the status of theFukushima Daiichi nuclear power plant:

" No changes were observed on the readings at the on-site radiation monitoring posts;* Workers were temporarily evacuated to the seismic evacuation shelter;" Off-site power was lost and water injection pumps for Units 1, 2 and 3 stopped but were restarted 50

minutes after the earthquake; and" The injection of nitrogen into Unit 1 stopped and resumed later.

Fukushima Daiichi Plant Status

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In Unit I fresh water is being continuously injected into the RPV through the feed-water line at an indicatedflow rate of 6 m3/h using a temporary electric pump with off-site power. In Units 2 and 3 fresh water is beingcontinuously injected through the fire extinguisher lines at an indicated rate of 7 m3/h using temporary electricpumps with off-site power.

Nitrogen gas is being injected into the Unit 1 containment vessel to reduce the possibility of hydrogencombustion within the containment vessel. The pressure in this containment vessel is increasing due to theaddition of nitrogen. The pressure in the RPV is increasing as indicated on both channels of instrumentation. InUnits 2 and 3 Reactor Pressure Vessel and Drywell pressures remain at atmospheric pressure.

RPV temperatures remain above cold shutdown conditions in all Units, (typically less than 95 °C). In Unit Itemperature at the feed water nozzle of the RPV is 221 'C and at the bottom of the RPV is 120 *C. In Unit 2the temperature at the feed water nozzle of the RPV is 155 *C. The temperature at the bottom of the RPV wasnot reported. In Unit 3 the temperature at the feed water nozzle of the RPV is 97 OC and at the bottom of theRPV is 111 'C.

There has been no change in status in Units 4, 5 and 6 and the Common Spent Fuel Storage Facility.

Radiation MonitoringOn April 11, deposition of both iodine-131 and cesium-137 was detected in 6 and 8 prefectures respectively.The values reported for iodine-131 ranged from 2.1 to 35 Bq/m 2 and for cesium-1 37 from 5.2 to 41 Bqim 2.

Gamma dose rates are measured daily in all 47 prefectures, the values tend to decrease. For Fukushima, onApril 11 a dose rate of 2.1 pSv/h, for the ibaraki prefecture a gamma dose rate of 0.15 pSv/h was reported.The gamma dose rates in all other prefectures were below 0.1 pSv/h.Dose rates are also reported specifically for the Eastern part of the Fukushima prefecture, for distances ofmore than 30 km to Fukushima-Daiichi. On April 11, the values in this area ranged from 0.2 to 25 pSv/h.

In an additional MEXT monitoring program, on April 11 measurements were reported for 25 cities in 13prefectures. In Fukushima City, a value of 0.42 pSv/h was observed. In all other cities, gamma dose ratesranged from 0.04 to 0.13 pSv/h. Typical normal background levels are in the range of 0.05 to 0.10 pSv/h. Alsoon April 11, the IAEA Team made measurements at 9 different locations in the Fukushima area at distances of30 to 58 km, West to Northwest from the Fukushima nuclear power plant. At these locations, the dose ratesranged from 0.1 to 2.2 pSv/h. At the same locations, results of beta-gamma contamination measurementsranged from 0.01 to 0.28 Megabecquerel/m 2.

Analytical results related to food contamination were reported by the Japanese Ministry of Health, Labor andWelfare on 11 April, and covered a total of 21 samples taken on 8 April and 10 to 11 April. Analytical results forall of the samples of various vegetables, spinach and other leafy vegetables, fruit (strawberries), various meats(chicken, beef and pork), seafood and unprocessed raw milk in eight prefectures (Fukushima, Gunma, Hyogo,Ibaraki, Miyagi, Niigata, Saitama and Yamagata) indicated that 1-131, Cs-1 34 and/or Cs-1 37 were either notdetected or were below the regulation values set by the Japanese authorities.

Marine MonitoringTEPCO is conducting a program for seawater (surface sampling) at a number of near-shore and off-shoremonitoring locations. Up until April 3, a general decreasing trend was observed at the sampling points TEPCO1 to TEPCO 4. After the discharge of contaminated water on April 4, a temporary increase has been reported.As of April 12, no new data for TEPCO 1 - 10 sampling points have been reported.

MEXT Off-shore Monitoring ProgramAs reported in previous briefings, MEXT initiated the off-shore monitoring program on March 23 andsubsequently points 9 and 10 were added to the off-shore sampling scheme. On April 4, MEXT added twosampling points to the north and west of sampling point 1. These are referred to as points A and B. As of April12, no new data for all ME)(T sampling points have been reported.

Questions from Member States4

Member States asking questions today included Japan, Singapore, Korea, Russia and France.Nearly all questions centered on more detail regarding the INES 7 rating. Singapore and Korea in particularwanted to know what member states "should be doing differently in response to the new rating." Despite DDGFlory's best efforts to explain that INES is meant to relay information based on scientific findings, not todescribe conditions on the ground or real effects on human health or the environment, the member statescontinued to probe for what actions they should take in response to this "new" decision. Russia was also vocalin this discussion, stating that it is "not appropriate to compare accidents like Chemobyl and others, becausethis is not what the INES system is for." Russia also (correctly) pointed out that the accident at Fukushima isstill ongoing and it is premature to speculate how much radioactivity will be released, in compassion to otheraccidents. Seemly, Russia was concerned with Japan's announced that the radioactive releases fromFukushima so far are only 10% of what Chernobyl released.Russia also asked several questions about Japan's plans for "storing and/or containing" the massive amount ofcontaminated water that continues to be accumulated on site. DDG reminded member states that storagetanks, trenches and other means of containment are currently being completed on site, in hope that there willbe adequate storage capacity to meet this need.

Closing RemarksDDG Flory closed the meeting by stating that Philippines and the Republic of Korea have also now providedIAEA with monitoring data and/or links to their websites. Although not specifically mentioned by DDG Flory, theUSG provided IAEA with monitoring data (from the Environmental Protection Agency) on April 9.Lastly, DDG Flory stated that the next technical briefing will be conducted on April19.

This email is UNCLASSIFIED.

5

Merzke, Daniel

From:Sent:To:

Cc:Subject:Attachments:

Merzke, DanielWednesday, April 13, 2011 8:43 AMBradford, Anna; Warren, Roberta; Thoma, John: Baggett, Steven; Tadesse, Rebecca; Kock,AndreaVietti-Cook, Annette; Muessle, Mary; Andersen, JamesFW: FYI - PARs for Deputies Meeting Rev 19a (2).docxPARs for Deputies Meeting Rev 19a (2).docx

Please find attached the latest draft document with the criteria for short-term re-entry of U.S. citizens inside the50 mile zone around Fukushima, and the long-term re-entry criteria. I would like to stress this is still a draftdocument at this time. I'm still working on locating a copy of the Global Assessment, and will forward thatwhen I find it.

Dan

"rom: Dudek, MichaelSent: Wednesday, April 13, 2011 7:42 AMTo: Merzke,. DanielSubject: FYI - PARs for Deputies Meeting Rev 19a (2).docx

Dan,

Here is one of the documents for distribution, as appropriate. OUO at this time.

Michael I. Dudek

Michael Dudek I Technical Assistant I NSIR/Division of Preparedness & Response I U.S. NRC11555 Rockville Pike, Rockville, MD 20852 I •I (301) 415-6500 1 CI Michael.Dudek."hnrc.ov

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From: RST01 HocSent: N Thursday. April 14. 2011 1:57 PMTo:

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Subject: FW: 1100 am call notes/ questions

1100 Call Notes

Decision made to change the format of the meeting from being run by INPO to being run by the RST. Callchanging from discussing RST Assessment to discussing plant conditions and items of concern amongconsortium members. ¶

On Tuesdays and Thursday s, call will also address changes to the RST Assessment document.

INPO and EPRI indicated that they will still support the Tuesday and Thursday calls but will not listen in on theother calls.

Questions/Comments from the 1100 Call

1. What size Tsunami was the plant designed to withstand?a. What size earthquake was the plant designed to withstand.b. GEH indicated that design of earthquake was in ground motion and not on Richter scale

2. Does anybody have a copy of the paper that was previously generated on potential interactionsbetween boron and seawater?

3. Any thoughts on how high radiation levels should be in SFP with water level 2.5 m aboveTAF? Currently reading 8 rem/hr

4. Any thoughts on having TEPCO getting a better flow path that could handle higherpressures? Recommendations

5. Any word on when they might stop inerting Unit 1?6. Any concerns that may have more instrument failures due to operating in a high radiation / high

temperature environment?7. Received report today that TEPCO thinks they have 4' of water in DW, I thought we believed they had

10-12' any effort to reconcile differences?

Comments

1. Concern about Alternate Vent methods of venting Unit 1 RPVa. Method of venting all RPV'sb. Concern about covering up the SRV's if they flood up DW

i. Do we have that concern?ii. SRV may close and lose all injection and vent capability

2. Appears no damage to #4 SFP fuel - may not have had a firea. Radiation levels appear to be high 8 rem/hr for level of 2.5 m over top of stored fuel

3. RST Assessment is being farmed out to NRR, all comments and changes will still go through RST1

9

4. Unit 2 trench pumped down - refilled again5. DOE indicated that they would send out information copies of documents that they had been working

on.a n ed baclcomments by Close of business on Monday

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From:Sent:To:Cc:

Subject:

Aoki, Steven [[email protected]]Thursday, April 14, 2011 9:33 AMGauntt, Randal; Kelly, John E (NE); Binkley, SteveLee, Richard; Orrell, Stanley A; Pickering, Susan Y; Bums, Shawr• kelwdycoda.ccqm;.Tinkler, Charles.RE: Unit 4 Spent Fuel Pool. Isotopic Analysis

From: Gauntt, RandalSent: Thursday, April 14, 2011 4:53 AMTo: Kelly, John E (NE); Aoki, StevenCc: Lee, Richard (NRC); Orrell, Stanley A; Pickering, Susan Y; Burns, ShawntSubject. FW: Unit 4 Spent Fuel Pool Isotopic Analysis r

.kcw~adVtdda--ct-. -hiarles~tinkler~dnrc.govr 0

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From: Gard, Lee A (INPO) [[email protected]]Sent: Thursday, April 14, 2011 2:35 AMTo: alan.blameyvanrc.qov Brian Wittick; Carl Moore; Chuck Casto; elmo.collinsanrc.gov; Gauntt, Randall 0; Jeff Mitman;.michael.calI(nrc.gov; michael.hayvnrc.gov; Miller, Mari!hard-kondogtibad. ;rudolph.bernhard~cnrc.qov; Salay,Michael; Steve Garchow; Steve ReynoldsSubject: FW: Unit 4 Spent Fuel Pool Isotopic Analysis

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gardla(Winpo.org U

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale or for commerciat-•-use. Reproduction of this report without the prior written consent of INPO is expressly prohibited. Unauthorized

134

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repV ,n is a violation of applicable law. The persons and organizations that are furnished copies of this report shouldnot deliver or transfer this report to any third party, or make this report or its contents public, without the prior agreementof INPO. All other rights reserved.

DISCLAIMER:This e-mail and any of its attachments may contain proprietary INPO or WANO information that is privileged. confidential, or protected by copyright belonging toINPO or WAND. This e-mail is intended solely for the use of the individual or entity for ,hicti it is intended. If you are not the intended recipient of this e-mail, anydissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mail is contrary to the rights of INPO or WANO and isprohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete the original and anycopy or printout of this e-mail and any attachments.Thank you.

135

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Lee, Richard

From:Sent:To:Cc:

Subject:

Gauntt, Randall 0 [[email protected]]Thursday, April 14, 2011 10:31 AMAoki, Steven; Kelly, John .E (NE); Binkley, SteveLee, Richard; Orrell, Stanley A: Pickering, Susan Y; Burns, [email protected];Tinkler, CharlesRE: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(5)

'Randy

From: Gauntt, Randall 0Sent: Thursday, April 14, 2011 8:09 AMTo: Aoki, Steven; Kelly, John E (NE); Binkley, SteveCc: Lee, Richard (NRC); Orrell, Stanley A; Pickering, Susan Y; Burns, Shawn ;kcw@cdycodaxcom; kharles.tinkleronrc.govSubject: RE: Unit 4 Spent Fuel Pool Isotopic Analysis f

4,ood suggestion.

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randy

From: Aoki, Steven [[email protected]]Sent: Thursday, April 14, 2011 7:32 AMTo: Gauntt, Randall 0; Kelly, John E (NE); Binkley, SteveCc: Lee, Richard (NRC); Orrell, Stanley A; Pickering, Susan Y; Burns, Shawn k da~comcharles.tinkleronrc.qovSubject: RE: Unit 4 Spent Fuel Pool Isotopic Analysis

From: Gauntt, RandalSent: Thursday, April 14, 2011 4:53 AMTo: Kelly, John E (NE); Aoki, StevenCc: Lee, Richard (NRC); Orrell, Stanley A; Pickering, Susan Y; Burns, Sha(n; [email protected], chlarles.tinkler@nrc. ovSubject: FW: Unit 4 Spent Fuel Pool Isotopic Analysis I

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From: Gard, Lee A (INPO) [[email protected]]Sent: Thursday, April 14, 2011 2:35 AMTo: alan.blarneyvnrc.gov; Brian Wittick; Carl Moore; Chuc&Gasto; elmo.collins nrc.qov; Gauntt, Randall 0; Jeff Mitman;michael.callianrc.qov; michael.hayvcnrc.gov; Miller, Mari richard.kondo&crbard.com; ýudolph.bemhard nrc.qov; Salay,Michael; Steve Garchow; Steve ReynoldsSubject: FW: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(4)

,Lee GardINP9

rceý (b)(6)

7-ard•a(amuDo.ord

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale or for commercialuse. Reproduction of this report without the prior written consent of INPO is expressly prohibited. Unauthorizedreproduction is a violation of applicable law. The persons and organizations that are furnished copies of this report shouldnot deliver or transfer this report to any third party, or make this report or its contents public, without the prior agreementof INPO. All other rights reserved.

DISCLAIMER:This e-mai and any of its attachments may contain proprietary tiNPO or WANO information that is privileged, confidential, or protected by copyright belonging toINPO or WANO. This e-mail is intended solely for the use of the individual or entity for which it is intended. If you are not the intended recipient of this e-mail, anydisseminalion, distribution, copying, or action laken in relation to the contents of and attachments to this e-mail is contrary to the rights of INPO or WVa,',N and isprohibited. if you are not the intended recipient of this e-mail, please notily the sender ;mrediately by return e-mai; and permanently delete the original and anycopy or printout of this e-mail and any attachments.Thank you.

142

Lee, Richard

From:Sent:To:Cc:

Subject:

Gauntt, Randall 0 [[email protected]]Thursday, April 14, 2011 8:58 AM'Joh nE. Kelly@N uclear. Energy. Gov; Lee, RichardOrrell, Stanley A; Pickering, Susan Y; Burns, Shawn; '[email protected]'; Tinkler, Charles;'[email protected]'Re: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(5)

4

From:. Kelly, John E (NE) [mailto:JohnE.Kelly@)Nuclear.Enerqy.Gov]Sent: Thursday, April 14, 2011 06:32 AMTo: Lee, Richard (NRC) <[email protected]>; Gauntt, a O10Cc: Orrell, Stanley A; Pickering, Susan Y; Burns, Shawn ,w.Lcoda:trn < [email protected]'cdnoms;. Vnkler, Charles<Chartes.TinkIer&nrc:.qov>; Aoki, Steven <Steven.Aokiý npsa.doe.gov>Subject: RE: Unit 4 Spent Fuel Pool Isotopic. Analysis

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From: Lee, Richard (NRC)Sent: Thursday, April 14, 2011 8:04 AMTo: Gauntt, RandalCc: Orrell, Stanley A; Pickering, Susan Y; Kelly, John E (NE); Burns, Shav-kcwg dycoda.66n6i,'Tinkler, Charles; Aoki,StevenSubject: RE: Unit 4 Spent Fuel Pool Isotopic Analysis

Randy:

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Richard

From: Gauntt, Randall 0 [mailto:roqauntasandia.govlSent: Thursday, April 14, 2011 4:53 AMTo: Kelly, John E(NE); Aoki, StevenCc: Lee, Richard; Orrell, Stanley A; Pickering, Susan Y; Burns, Shavn;.kcwvdycoda~com; 11inkler, CharlesSubject: FW: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(5)

Randy

132

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From: Gard, Lee A (INPO) [[email protected]]Sent: Thursday, April 14, 2011 2:35 AMTo: alan.blameyCnrc.oov; Brian Wittick; Carl Moore; Chuck Casto; elmo.collins~nrc.aov; Gauntt, Randall 0; Jeff Mitman;[email protected]; [email protected]; Miller, Marie; richard.kondoecbcrbard.com; rudolph.bernhardanrc.qov; Salay,Michael; Steve Garchow; Steve ReynoldsSubject: FW: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(4)

Lee Gard-_INPO

IL"111(b)(6)gardla(Winpo.orq

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale or for commercialuse. Reproduction of this report without the prior written consent of INPO is expressly prohibited. Unauthorizedreproduction is a violation of applicable law. The persons and organizations that are furnished copies of this report shouldnot deliver or transfer this report to any third party, or make this report or its contents public, without the prior agreementof INPO. All other rights reserved.

.DISCLAIMER:This e-mail and any of its attachments may contain proprietary INPO or WAND information that is prvileged, confidential, cr protected by copyright belong;ng toINPO or WANO. This e-mail is intended solely for the use of the individual or entity for which it is intended. If you are not the intended recipient of this e-mail. anydissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mail is contrary to the rights of INPO or WANO and isprohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete the original and anycopy or printout of this e-mail and any attachments.Thank you.

133

Lee, Richard

From: Lee, RichardSent: Thursday, April 14, 2011 8:43 AMTo: 'Gauntt, Randall 0'Subject: RE: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(5)

From: Gauntt, Randall 0 rmailto:[email protected]: Thursday, April 14, 2011 8:29 AMTo: Lee, RichardSubject: Re: Unit 4 Spent Fuel Pool Isotopic Analysis

Well,

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From: Lee, Richard rmailto:Richard.Lee(nrc.qov1Sent: Thursday, April 14, 2011 06:04 AMTo: Gauntt, Randall 0C(: Orrell, Stanley.A; Pickering, Susan<YA Kelly, John E (NE) <JohnE.Kelly(@Nuclear.Energy.Gov>; Burns, Shawn;k .. I .1,k cw.-od--,cDm-; Ifnkler, Charles <Charles.Tinkler(nrc.qov>; Aoki, Steven

].Steven.Aoki@ nnsa.doe.qov> -•

Subject: RE: Unit 4 Spent Fuel Pool Isotopic Analysis

Randy:

(b)(5)

Richard

From: Gauntt, Randall 0 [mailto:roMauntasandia.cov1Sent: Thursday, April 14, 2011 4:53 AMTo: Kelly, John E (NE); Aoki, StevenCc: Lee, Richard; Orrell, Stanley A; Pickering, Susan Y; Burns, Sh ~ n;*kw&d inkier, CharlesSubject: FW: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(5)

*Randy

57

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From: Gard, Lee A (INPO) [[email protected]]Sent: Thursday, April 14, 2011 2:35 AMTo: alan.blamehy~nrc.gov; Brian Wittick; Carl Moore; Chuck Casto; elmo.collinsa)nrc.qov; Gauntt, Randall 0; Jeff Mitman;michael.callknrc.oOV; michael.hayvnrc.qov; Miller, Marie; richard.kondo(crbard.com; rudolph.bern hard@ nrc.qov; Salay,Michael; Steve Garchow; Steve ReynoldsSubject: FW: Unit 4 Spent Fuel Pool Isotopic Analysis

(b)(4)

Lee Gard

'-gardiagijnto.orq

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale or for commercialuse. Reproduction of this report without the prior written consent of INPO is expressly prohibited. Unauthorizedreproduction is a violation of applicable law. The persons and organizations that are furnished copies of'this report shouldnot deliver or transfer this report to any third party, or make this report or its contents public, without the prior agreementof INPO. All other rights reserved.

DISCLAIMIER:This e-mail and any of its attachments may contain proprietary INPO or WANO information that is privileged. confidential, or protected by copyright belonging toINPO or WAND. This e-mail is intended solely for the use of the individual or entity for which it is intended. if you are not the intended recipient of this e-mail, anydissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mail is contrry to the rights of INPO orWANO and isprohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete zhe original and anycopy or printout of this e-mail and any attachments.Thank you.

58


HOO HocThursday, April 14, 2011 8:28 PM

LLA07 Hoc; LIA08 Hoc; OST01 HOCFW: Official notice (14/04/2011) Documents of the briefingimage001.jpg

Headquarters Operations OfficerU.S. Nuclear Regulatory CommissionPhone: 301-816-5100Fax: 301-816-5151email: hoo.hocgnrc.govsecure e-mail: hool•nrc.sgov.gov

SU.S.NRC

From: Hinds, Lynda I [mailto:[email protected]] On Behalf Of Tokyo Staff Assistant-.•nt! Tht~r~dav. Anril 14.2fl11 R:25 PM

-Sent: Thursda April 14 20118:25 PMTol (b)(6) I

(b)(6)

Subject: FW: Official notice (14/04/2011) Documents of the briefing

Lynda HindsStaff Assistant(03) 3224- 5370

From: PROTOCOLOFFICE-EM [mailto:[email protected]]Sent: Friday, April 15, 2011 4:49 AM

To: PROTOCOLOFFICE-EMSubject: Official notice (14/04/2011) Documents of the briefing

-Urgent-

Official Notice(15th April 2011 04:00 revised)

To All Missions (Embassies, Consular posts and International Organizations inJapan)

The Ministry of Foreign Affairs has the honour to send for the perusal of Missionsdocuments which were distributed at the briefing on 14th April, 2011 at 16:00 foryour reference.< p class-MsoNormal style='text-indent:7.Opt'>

Also, the Ministry would like to inform the missions that the Chief CabinetSecretary announced at the press conference the removal of shipment restriction ofkakina, leafy vegetable, originated from Tochigi Prefecture.

Furthermore, the Ministry would like to correct the data provided by NISAcolleague at the briefing regarding sampling data of water from the Unit4 spentfuel pool. The corrected data is the following:

131 1 2.2 x 102 Bq/cm 3 (=220 Bq/cm3)

(note: the usual data is less than 0.01Bq/cm3)34 Cs 8.8 xlO Bq/cm 3 (=88 Bq/cm3)

(note: the usual data is less than 0.01Bq/cm3)137 Cs 9.3 xlO Bq/cm 3 (=93 Bq/cm3)

(note: the usual data is the order of 0. 1Bq/cm3)

List of attachments

1. List of briefers from Ministries other than the MOFA (14th April)2. Levels of radioactive contaminants in foods (data reported on 13 April 2011) (Ministry of

Health, Labour and Welfare)3. Current situation for water supply works(14th April 2011)and Press release on detection of

radioactive materials in tap water(33th announcement)(Ministry of Health, Labour andWelfare)

4. Results of the inspection on radioactive materials in fisheries products (Ministry ofAgriculture, Forestry and Fisheries)

2

5. Reading of Environmental Radiation Level by emergency monitoring (Ministry of Education,Culture, Sports, Science and Technology)

6. Press Release (Evaluation of Environmental Radiation Monitoring Results (16:45 on April 13,2011) (Nuclear Safety Commission, Cabinet Office)

7. District-based Assessment of Vulnerability to Earthquake Disaster (2008), issued by TokyoMetropolitan Government (MOFA)

8. Tokyo Metropolitan Government Disaster Prevention Homepage (MOFA)9. Information for those who are interested in the volunteer work for the Great East Japan

Earthquake) (MOFA)10. Excerpts from the press conference by Executive Vice President Muto (TEPCO)11. Seismic Damage Information (the 91st and 92nd Release) (Nuclear and Industrial Safety

Agency)12. Conditions of Fukushima Dai-ichi Nuclear Power Station Unitl-6 (As of 6:00 April 14th,

2011 ) (Nuclear and Industrial Safety Agency)

(END)

3

r

From:Sent:To:

OST01 HOCThursday, April 14, 2011 2:59 PMFranovich, Mike; Hipschman, Thomas; Snodderly, Michael; Orders, William; Castleman,

Patrick; Weber, Michael; Virgilio. Martin; Boger, Bruce; Zimmerman, Roy; Bowman,

GregoryDraft Chuc'k Casto SlidesJapanGlobalAssessment.pptx

Subject-Attachments:

Please see attached DRAFT slides from Chuck Casto, as requested. Staff comments have not

been incorporated yet. After receipt of planned final, we can resend that version tomorrow,

hopefully.

Executive Support Team

(for the ET Director, Roy Z.)

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Westreich, Barry

From: Holahan, PatriciaSent: Friday, April 15, 2011 11 : 10 AMTo: Westreich, Barry; Holahan, VincentSubject: Fw: OUO- Japan

FYI.

From: Zimmerman, RoyTo: Monninger, John; Virgilio, MartinCc: Merzke, Daniel; Wiggins, Jim; Holahan, Patricia; Evans, Michele; Weber, MichaelSent: Fri Apr 15 10:17:32 2011Subject: OUO- Japan

Just got off the phone call briefing with Chuck Casto and the Chairman. Chuck indicated that based on theTEPCO isotopic analysis of the Unit 4 SFP, TEPCO currently believes the spent fuel is undamaged. This is amore positive view than yesterday's statement that damage occurred to some fuel rods.l!1

(b)(5)

Regarding the composite assessment, NSIR has the lead and it is being worked by Trish Milligan We arecontacting Trish and will get back to you.

SoS briefing slides: Received from Chuck and provided to various folk, including you and I

1g 67/ qtý


Hoc, PMT12Friday, April 15, 2011 9:23 AMPMT1O HocLatest version of Composite documentPARs for Deputies Meeting Rev 21with tracked changes (3).docx

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Wittick, Brian

From: Wittick, BrianSent: Saturday, April 16, 2011 2:03 AMTo: Huffert, Anthony; Gepford, Heather; Meighan, SeanSubject: FW: April 15 briefing notes, excel spreadsheet and radiation survey mapAttachments: April 14 1600 Facility Area Survey Data[1].pdf; April 15 Ryan 6 pm briefing notes.doc; TEPCO

Summary Rev.87 Final April 15.xls

FYI

From, Gard, Lee A (INPO) rmailto:[email protected]: Friday, April 15, 2011 5:21 AMTo: Blamey, Alan; Wittick, Brian; Moore, Carl; Casto, Chuck; Collins, Elmo; Gauntt, Randall 0; Mitman, Jeffrey;michael.callanrc.gov; Hay, Michael; Miller, Marie; richard.kondoacrbard.com; Bernhard, Rudolph; Salay, Michael;Garchow, Steve; Steve ReynoldsSubject: FW: April 15 briefing notes, excel spreadsheet and radiation survey map

.D:SCLAIMER:This e-mail and any of its attachments may contain proprietary INPO or WANO information that is privileged, confidential, or protected by copyright belonging toINPO or WANO. This e-mail is intended solely for the use of the individual or entity for which it is intended. If you are not the intended recipient of this e-mail, anydissemination, distribution; copying. or action taken in relation to the contents of and attachments to this e-mail is contrary to the rights of INPO or WANO and isprohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete the original and anycopy or printout of this e-mail and any attachments.Thank you.

('RI2344ý 1 4 16:00I*£)

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FUKUSHIMA DAIICHI

Status as of 6pm (JST) April 15, 2011- TC Briefing. (All times JST)

All information may be shared

The priorities remain as follows:

" Ensuring fresh water injection and cooling capabilities to the reactorsand spent fuel pools. Goal is to reduce and maintain temperature inthe reactors and spent fuel pools below 100 degrees centigrade.

" Draining water from the turbine buildings and trenches to reduce theradiation levels sothat work can continue.

" Containing the spread of radioactive materials.

Highlights for today include the following:

• N2 purging of Unit 1 continues. Drywell pressure has been steady orslightly decreasing over the past several days.

* The transfer of radioactive water from the Unit 2 trench to the Unit 2hotwell was completed last night. After an initial decrease, trench levelhas been increasing.

* Leak checks and seal inspections / repairs are in progress in theRadioactive Waste building in preparation for water transfers from theunits.

0 To support waste water cleanup TEPCO announced they will installmultiple temporary tanks of 27,000 tons capacity by the end of May.They will also deploy a megafloat of 10,000 tons capacity by mid-May.

* 25 tons of water was added to the Unit 3 SFP. Spray of 140 tons intothe Unit 4 pool is planned for today.

* Silt screens are in the process of being installed around intake Idischarge areas. They are also placing sandbags filled with zeolite inthe water around the intake structures to aid in the absorption ofcesium.

* The unmanned helicopter is scheduled to fly again today. Videos fromprevious test flights have not yet been released.

* Debris removal and dust / particle scatter preventive actions arecontinuing.

* To strengthen electrical power reliability the Tohoku transmission lineused as the Unit 1 & 2 power source and the TEPCO power source forUnit 3 & 4 will be cross connected and switchable. The emergencydiesel generators for powering injection will be relocated to higherground (April 15).

I

Unit Status

" In Unit 1, non-borated fresh water injection into the main feedwater linecontinues at 6 cubic meters/hr. Comments on parameters:

- Reactor pressure indicator A increased slightly to .428 MPa g, (62psig). Indicator B is considered to be unreliable.

- Feedwater nozzle temperature continues to decrease and isreading 197 C (387F). This parameter remains suspect.

- Reactor vessel lower temperature has remained steady at 119 C(246 F)

- Drywell and torus pressure remains relatively steady at .185 MPaabs (27.6 psia) and .165 MPa abs (23 psia) respectively.

- Dose rates in the Torus continue to decrease slightly to 9.7 Svlhr(970 Rem/hr.)

* In Unit 2, injection of non-borated fresh water using the low pressurecoolant injection continues at 7 cubic meters/hr, (= to the goal andequivalent to the decay heat rate 14 days after shutdown.) Commentson parameters:

- Unit 2 reactor pressures remain fairly stable. TEPCO nowconsiders these measurements to be suspect.

- Feedwater nozzle temperature continues to decrease slowly to150 C (302 F)

- Reactor vessel lower temperature is believed unreliable.

- Drywell pressure is stable at .090 MPa abs (13.8 psi)

- Dose rates in the U2 Drywell and Torus continue to decrease.The drywell dose rates are at 27.1 Sv/hr or (2,710 Rem/hr) andthe dose rate in the Torus has decreased to .629 Sv/hr or (62.9Rem/hr.)

" In Unit 3, injection of non-borated fresh water using the low pressurecoolant injection line continues at 7 cubic meters/hr (= to the goal andequivalent to the decay heat rate 14 days after shutdown.). Commentson parameters:

- Unit 3 reactor pressures indicate stable but are consideredsuspect.

- Feedwater nozzle temperature is fluctuating day-to-day and isconsidered to be unreliable.

- Reactor vessel lower temperature has been steady two days at at121 C (248 F)

- Drywell pressure was steady at .104 MPa abs (15 psi). Toruspressure decreased slightly to .166 MPa abs (24 psi).

- Dose rates in the U3 Drywell and Torus continue to decrease.The drywell is at 16.5 Sv/hr (1,650 Rem/hr) and the dose rate inthe Torus is .634 Sv/hr or (63.4 Rem/hr.)

2

Dose and Dose Rates

" Radioactivity level in underground water around Unit 1 and 2 hasincreased compared to samples taken last week. Increases observedranged from 6 to 38 times higher depending on the isotope.Radioactivity levels of groundwater around Units 3 and 4 remained thesame or decreased slightly.

• The number of workers who have received greater that 100 mSv (10Rem) has increased to 28. The highest received was 198 mSv (19.8Rem). The maximum emergency dose is temporarily set at 250 mSv.

" Overall site dose rates are decreasing. For example:

> The last reading reported at the main gate was 72 pSv /hr or(7.2 millirem/hour).

> The side of the administration building facing the units is at 545pSv/hr or 55 mrem/hr.

> The dose rate at the west gate is reported to be 37 pSv /hr or(3.7 millirem/hour).

3

rent Status and Planned Work

15 April at 08:00 (Rev-87)

*nix cues essemuIles are SaoveQ in 3rrlEGate between IFP & reactor cavity

closed (For core shroud replacement

workduring outage)

start of the next operation cycleERPV bolted up

(Earthquake occurred aftercompletion of

RPV hydrauric test just before thestartup)EMaintaining cold shutdown

re

KOrdinary operation in SHC mode of RHR NOrdinary operation in SHC mode of(14 April 18:57- )

14 April 18:19- 1

ow

en

1) RIRPY Dome Pressure (at U6:00 on 15 NRPV Dome Pressure (at 06:00 on 15April) April)

0.003 MPa-g 0.010 Ma-gUReactor Water Level (at 06:00 on 15 EReactor Water Level (at 06:00 onApril) 15 April)

TAF+1701 am (Shut Down Range Gauge) TAF+2315amOCoolant Temprature (at 06:00 on 15 ECoolant Temprature (at 06:00 on 15April) April)

nr. 9, 47.19C

_____________________________________________________ _________________________________________________ ______________________________________________ _______________________________________________

ENegative pressure kept by SGTS ENegative pressure kept by SGTS

ine

USFP water level Uncertain Ulnventory securing Hlnventory securing USFP water temperatureUSFP water temperature; gauge out of * CST -> MUWC -) FPC -) SFP * CST -> MIUWC -> FPC -) SFP 28 C at 07:20 on 14 April

order EHeat removal EHeat removal ECooling function achieved by airof (at 11:10 on 24 March * FPC (Surge Tank) -> RHR -> S/C * FPC (Surge Tank) -> RHIR -> S/C fin coolers

and later) * Heat removal in S/C cooling mode * Heat removal in S/C cooling mode (at 16:26 on 24th March)mSkimmer suge tank level of RHR of RIl EWater supply to the common

4350 mm ( at 06:00 on 15 April) USFP Water level; uncertain (Water NSF? Water level; uncertain(Water SFP by MUl systemon ENo roof due to explosion at the level alarms were not activated.) level alarms were not activated.) ( 24 March 16:15-18:04

operational floor USFP Water temp; USF? Water temp; UFPC(A) started at 18:05mInstailation alternation pump for RIlS 3n. t (at 06:00 on 1I 24. 5C at 06:00 on on 24th MarchmWatering by concrete pumping vehicle April) 15 April)

( called as Giraffe) USecondary containment is intact with USecondary containment is intact-30 March 14:04-18:33 (Fresh water) roof with

1 April 08:28-14:15 (Fresh of R/B roof of R/BWater) . UFresh water was transferred to fresh UFresh water was transferred to

* 3 April .17:14-22:16 (Fresh water tank 83 by tank lorry I - I fresh water tank 83 by tank lorry ( -Water) April) I April)U Check the condition of FPC lines

* No abnormal condition on thestrainer

- Piping seems to be stuffed (on 4April)UThe Elephant was moved from Unit I toUnit 4mWatering with the Elephant

5 5 April 17:35-18:22* 7 April 18:23-19:40* 9 April 17:07-19:24" 13 April 0:30- 6:57 (195 ton)

1) mUreparation for water feeding withelectric

motor numns was comnleted. (on 9Cliater spray with the Elephmnt 92 (15April 14:00 - 19:00

0480V P/C 4D powered throughrr&nsmission

line (at 10:35 on 22nd March)i120V I & C main bus powered at 01:40

on 23 MarchlIllumination of MCR restored at 11:50

on 29 March

er

ETemporary power supply achievedutilising the

non-damaged part of 66kV off-sitepower

transmission line (Yono-Mori lineIL. 2L)ENon-safety grade buses of SA and 5Bare

unavailableOTemporary pump (RHRS) was installedand

connected to the water supply lineon 24th March

KEmergency administration building waspowered on 24th March

EWater Purification Facility waspowered

at 9:10 on 24th MarchKInvestigating cable laying work formonitoring

posts (MP-1/2/3/4) on 26 March.UT/B MCC 5D-2 has been powered on 31

March

ETemporary power supply achievedutilising

the non-damaged part of 66kV off-site

power transmission line (Yono-Moar line

IL, 2L)NNon-safety grade buses of 6A and 6Bare

unavailableOTemporary pump (works as asubsutitute

of RHRS) was installed and putin-service

(Powered by P/C)mTest run od installed cable was

conductedon 20 March

1Monitoring posts (MPI-4) wererestored.

ETemporary power for commonpool was restored at 15:30

on 24th March

OLaying temporary power cable for SLC Olnvestigating cable laying work for -lnvestigating the power(B) monitoring restoration work

/B posts for I & C and illumination

F Part of I & C equipments were powered EPart of I & C equipments were powered lPart of I & C equipments wereby by powered by

temporary battety to monitor plant temporary battery to monitor plant temporary battety to monitorstatus status plant status

mDC 24 Charger 5B-lhas been poweredon 31 March

S3 holes(3-7.5 cm) were drilled on 03 holes(3-7.5 cm) were drilled onthe the

ceiling panel (250 mm thick) of the ceiling panel (250 m= thick) ofrector the rector

building on 18 March to relieve building on 18 March to relievehydrogen hydrogen

gas and to avoid explosion gas and to avoid explosion

ODrainiio water-.Water level in T/B

OP +2800a (at 07:00 on IS April); sae as 14 Ap-il 11:00

- Water transfer (Concentrated RWT/B)

(2 April 14:25 - 4 April 09:22;suspended)

-Water transfer pumps were added( 1 - 5 pumps; 3 Apr. 10:00 - 4 Apr.

09:22.suspended due to high water levelin the trench)

0 Work for shutting off the leak in pit

- Concrete was poured ( 25m2) to clogcracks

IMDraining water

Water transferRHO pump area 9 CS pump area

S/C(4 April)

MDischarging water in sub-drainof Unit 5 to the sea; 950 m3

(4 April 21:00 - 8 April 12:14)

EDraining water- Water transfer (RW base floor

-. H/W)(I April 13:40 - 2 April 10:00)

* Suspended by large amount ofwater;

considering draining waterMDischarging water in sub-drain

of Unit 6 to the sea; 372.6 m3(4 April 21:00 - 9 April 18:52)

mDraining water. -Concentrated RW - sea: 9070m3

(4 April 19:03 - 10 April 17:40)UDraining water from main processbuilding

was completed.[Draining water from incinerator

buildingwas started (on 6 April)

UBeing repaired of boundary /Prevention of leaks from boundary ofbuildings before storing

highly contaminated water inconcentrated

RW

in

OlWork for shutting off the leak in pit:r 0 Camera for level monitcring is

planned.

RCIC :Reactor Core Isolation Cooling

RHR :Residual Heat Removal

RPV :Reactor Pressure Vessel

S/C :Suppression Chamber

SDF :Self Defense Force

SFP ;Spent Fuel Pool

SGTS :Stabd by Gas Treatment System

SHC :Shut Do'n Cooling

(TV2344,25E 1

FUKUSHIMA DAIICHI

Status as of 6pm (JST) April 26, 2011- TC Briefing.

Information that is in italics should not be shared as it has not yet beenreleased by TEPCO.



* Draining water from the turbine buildings and trenches to reduce theradiation levels so that work can continue.



* N2 purging of the Unit 1 Drywell was stopped yesterday forapproximately five hours while power supply lines from Unit 5/6 wereconnected to a Unit 1/2 load center to improve reliability of Units 1 and2. During that time, Drywell pressure decay and decay rate wasmonitored and used to estimate free space and water level in theDrywell. It is now believed that Drywell water level is .5 m below thebottom of the reactor vessel.

* The robot entered the Unit 1 reactor building on Tuesday to check forpossible leakage from an electrical penetration or other areas on thereactor building first floor. No leakage was observed. TEPCO isconsidering increasing injection flow up to 14 m3/hr to increase theflooding rate of the Drywell.

* Transfer of highly radioactive water from Unit 2 to the CentralizedRadioactive Waste Treatment Facility continues at a rate of 250tons/day. Level in the Radioactive Waste Facility has risen 840 mmsince the start of transfer.

* Unit 2 trench level decrease has slowed dropping only 10 mm sinceyesterday. It is now 890 mm below the trench top. Unit 3 trench levelhas increased an additional 20 mm and is now 980 mm from the top.

" After four days of stability, Unit 4 turbine building water level increased50 mm and is now 3050 mm (1.5 m above floor level) which is slightlyhigher than the Unit 3 turbine building water level of 3000 mm.

* Two hundred ten tons of water were added to the Unit 4 Spent FuelPool (SFP) yesterday. Another 160 ton addition is scheduled for todayto fill the pool. The structural integrity of the Unit 4 SFP is consideredsufficient to support a full SFP. Calculations and observations indicatethat approximately 82 tons of water is needed to be added to the Unit 4SFP daily to maintain level.

* Thirty-eight tons of water was added Unit 2 SFP yesterday. Fifty tonsof water is scheduled to be added to the Unit 3 SFP today. Boil offrates are 21 tons/day and 17 tons/day respectively.

I

Unit Status

* In Unit 1, non-borated fresh water injection into the main feedwater linecontinues at 6.1 m3/hr. Comments on parameters:

- Reactor pressure indicator A is increased slightly to .450 MPa abs(65 psig). Indicator B continues to be suspect.

- Feedwater nozzle temperature continues to be suspect.

- Reactor vessel lower temperature decreased slightly to 111 C(232 F)

- Drywell and Torus pressure remained at .150 MPa abs (22 psia).

- Drywell and Torus dose rates are considered to be suspect.

* In Unit 2, injection of non-borated fresh water using the low pressurecoolant injection continues at 7 m3/hr. Comments on parameters:

- Unit 2 reactor pressures remain suspect.

- Feedwater nozzle temperature decreased slightly to 122 C (252F)


- Drywell pressure was stable near atmospheric.

- Dose rate in the U2 Drywell continues to decrease. The drywelldose rate is 2.31 Sv/hr or (2,310 Rem/hr). The Torus dose ratereading is considered suspect.

" In Unit 3, of non-borated fresh water using the low pressure coolantinjection continues at 6.8 m3/hr. Comments on parameters:

- Unit 3 reactor pressures are considered suspect.

- Feedwater nozzle temperature is considered to be suspect.


- Drywell pressure was steady at .104 MPa abs (15 psi). Toruspressure is also steady at .178 MPa abs (26 psi).

- Dose rate in the U3 Drywell continues to decrease and is at 14.6Sv/hr (1,460 Rem/hr). Dose rate in the Torus is considered tobe suspect.

Dose Rates

Overall site dose rates are stabilizing or only varying slightly. Forexample:

> The last reading reported at the main gate was 52 pSv /hr (5.2mrem/hour) and be 23 pSv /hr (2.3 mrem/hour) at the west gate.

, The side of the administration building facing the unitsdecreased slightly to .450 pSv/hr or 45 mrem/hr. The same asyesterday.

2

Not for Release

Fukushima-Daiichi Current Status and Planned Work

26 April at 01:00 1 09:00 (Rov-iO0)

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Importance:

Iluffert, AnthonySunday, April 17, 2011 10:54 PM'[email protected]'

FW: GEH Nuclear Response Team ResponseQ466 NRCPostulatedCorebreach_1 F2 - FINAL.pdf

High

From: Mitman, JeffreySent: Sunday, April 17, 2011 5:45 AMTo: Liaison JapanSubject: FW: GEH Nuclear Response Team ResponseImportance: High

From: RST01 HocSent: Saturday, April 16, 2011 9:22 AMTo: Mitman, JeffreySubject, FW: GEH Nuclear Response Team Response

From: RST09 HocSent: Friday, April 15, 2011 8:20 PMTo: RSTO1 HocSubject: FW: GEH Nuclear Response Team Response

Please forward to site team.

From: RST01 Hoc rmailto:RSTO1,Hoc(rnrc.aov]Sent: Friday, April 15, 2011 6:51 PMTo: RST09 Hoc; RST07 Hoc; RST08 HocSubject: FW: GEH Nuclear Response Team Response

From: GE Hitachi Nuclear Response Team (GE Power &Water)[SMTP:GE.HITACHINUCLEARRESPONSETEAM(,GE.COMISent: Friday, April 15, 2011 6:50:50 PMTo: RST01 HocSubject: GEH Nuclear Response Team ResponseAuto forwarded by a Rule

1 P)Oý

9",

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April 15, 2011Confidential - GE Hitachi Nuclear Energy LLCWithhold Pursuant to FOIA Exemption 4Information is Unverified

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(b)(4)

April 15, 2011Confidential - GE Hitachi Nuclear Energy LLCWithhold Pursuant to FOIA Exemption 4Information is Unverified

(b)(4)

Attached please find our NRC Postulated Core Breach 1F2 Review.

<<Q466 NRCPostulatedCore breach_1F2 - FINAL.pdf>>

Rich Rusin

Technical Services

GE Hitachi Nuclear Response Team

2


OST01 HOCSunday, April 17, 2011 1:51 PMRST01 HocFW: ACTION - New Ticket for Japanese Event Task Tracking (JETT) Processguideline comments.docx

Doug sent this to Trish already.

From: Weaver, DougSent: Sunday, April 17, 2011 1:46 PMTo: OST01 HOC; Deegan, George; Lewis, Robert; Hiland, Patrick; Skeen, David; Dudek, Michael; Milligan, Patricia;Gibson, Kathy; Case, Michael; Anderson, James; Tracy, GlennCc: Rahimi, Meraj; Kinneman, John; Haney, Catherine; Ordaz, VonnaSubject: RE: ACTION - NewTicket for Japanese Event Task Tracking (JETT) Process

Trish,

Please see attached comments for you consideration.

Doug

From: OSTO1 HOCSent: Sunday, April 17, 2011 3:54 AMTo: Deegan, George; Lewis, Robert; Weaver, Doug; Hiland, Patrick; Skeen, David; Dudek, Michael; Milligan, Patricia;Gibson, Kathy; Case, Michael; Anderson, James; Tracy, GlennSubject: ACTION - New Ticket for Japanese Event Task Tracking (JETT) Process

The Operations Center has identified a task that falls in the purview of the Line Organization. You were provided as a

POC for NRR/NSIR/RES/FSME/NMSS.

NSIR: Please provide the latest version of the composite document to Marty Virgilio by 0900 Monday morning 4/18.

NRR/FSME/NMSS/RES: Please review and provide comments to Trish Milligan, NSIR and OST 01 HOC by 4/17/2011,1500 EDT

This ticket is being tracked in the Japan SharePoint page (http://nsir-oos.nrc.gov/Lists/HOC%2ORed%20Tickets/AlIltems.aspx) under ticket number 4771.

Please provide a response to this email to confirm receipt. Thank you,


******Please note: All attachments are Official Use Only**********

p19

&

(b)(5)


Larry and Casper,

PMT10 Hoc

Sunday, April 17, 2011 9:29 AMRST01 Hoc; [email protected]

Composite document comments on definitions and a reentry parameterComposite Document Rev 1 - formerly called PARs for Dep Mtg V21.docx

(b)(5)

Sam KeithCDC Liaison

From: PMT10 HocSent: Friday, April 15, 2011 10:14 PMTo: Hoc, PMT12Cc: PMT10 HocSubject: FW:

(b)(5)

Thanks,Sam KeithCDC Liaison404-277-0016

From: Hoc, PMT12Sent: Friday, April 15, 2011 11:43 AMTo: PMT10 HocSubject:

Sam

Here's the latest draft.

Sandi

1 (

Andersen, James

From: Andersen, JamesSent: Sunday, April 17, 2011 12:22.PMTo: OST01 HOCSubject: Re: ACTION - New Ticket for Japanese Event Task Tracking (JETT) Process

No that is okay. Just let me know if you need assistance fron the EDO's office. Thanks.

Sent from an NRC BlackberryJames Andersen

I (b)(6)

From: OST01 HOCTo: Andersen, JamesSent: Sun Apr 17 11:53:34 2011Subject: RE: ACTION - New Ticket for Japanese Event Task Tracking (JEFF) Process

Do you want me to send and make sure your name is listed? I have only gotten 1 reply so far.

From: Andersen, JamesSent: Sunday, April 17, 2011 11:52 AMTo: OST01 HOCSubject: Re: ACTION - New Ticket for Japanese Event Task Tracking (JETT) Process

I probably will not see the responses for reply to all, please let me know if you do not hear back from the lead offices.Thanks.

Sent from an NRC BlackberryJames Andersn

S (b)(6) I

From: OST01 HOCTo: Andersen, JamesSent: Sun Apr 17 09:44:03 2011Subject: FW: ACTION - New Ticket for Japanese Event Task Tracking (JETT) Process

Here you go.

From: OST01 HOCSent: Sunday, April 17, 2011 3:54 AMTo: Deegan, George; Lewis, Robert; Weaver, Doug; Hiland, Patrick; Skeen, David; Dudek, Michael; Milligan, Patricia;Gibson, Kathy; Case, Michael; Anderson, James; Tracy, GlennSubject: ACTION - New Ticket for Japanese Event Task Tracking (JETT) Process

* * ****Please note: All attachments are (,f4cial ** *****


POC for NRR/NSIR/RES/FSME/NMSS.

NSIR: Please provide the latest version of the composite document to Marty Virgilio by 0900 Monday morning 4/18.

1

161

NRR/FSME/NMSS/RES: Please review and provide comments to Trish Milligan, NSIR and OST 01 HOC by 4/17/2011,1500 EDT

This ticket is being tracked in the Japan SharePoint page (http://nsir-ops.nrc.gov/Lists/HOC%2ORed%2OTickets/AII Items.aspx) under ticket number 4771.



******Please note: All attachments are -OffiriaI I I I * *********

2

Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subject tochange and refinement. "

(b)(5)

Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subject to

change and refinement.

OFFICIAL USE ONLY

I

Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subject tochange and rcfinement.

(b)(5)

Our assessments and recommendations are based on the best available technical information- We acknowledge that the information is subject tochange and refinement.

(b)(5)

Our assessments and recommendations are based on the best available technical informalion. We acknowledge that the information is subject tochange and refinement.

(b)(5)

Our assessments and recommendations are based on the bcst available technical information. We acknowledge that the information is subject tochange and refinement.

(b)(5)

Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subject tochange and refinement.

(b)(5)

N


(b)(5)

Our assessments and recommendations are based on the best available technical inlformation. We acknowledge that the information is subject tochange and refinement.

(b)(5)

Our assessments and recommendations are based on the best available technical information- We acknowledge that the information is subject tochange and refinement.

(b)(5)

Our assessments and recommendations are based on the best available technical information, We. acknowledge that the information is subject to


(b)(5)

From:Sent:To:Subject:

Tracy, GlennSunday, April 17, 2011 5:20 AMOST01 HOCFW: Composite document rev 2

From: RST08 HocSent: Sunday, April 17, 2011 3:51 AMTo: Hiland, Patrick; Ruland, William; Collins, Timothy; Skeen, DavidCc- RSTO1 Hoc; Norton, Charles; FOIA Response.hoc Resource; Garchow, Steve; Hoc, PMT12; Tracy, GlennSubject: RE: Composite document rev 2

All,

A thought related to the Composite Document:

(b)(5)

Eva Brown, BWR Systems and Ops AnalystReactor Safety Team

Nuclear Regulatory Commission

1

From: RST01 HocSent: Saturday, April 16, 2011 9:58 PMTo: RST08 HocSubject: FW: Composite document rev 2

From: RST01 HocSent: Saturday, April 16, 2011 7:04 PMTo: Hiland, Patrick; Ruland, William; Collins, Timothy; Skeen, DavidCc: RST07 HocSubject, FW: Composite document rev 2

All,

Attached is the Composite Document. The purpose of this document is to provide guidance forreturn and re-entry of US citizens to areas around Fukushima Daiichi NPP.

The RST is responsible for enclosure 2.

(b)(5)

(b)(5)

Chuck NortonRST BWR Analyst

2

From: Hoc, PMT12Sent: Saturday, April 16, 2011 5:50 PMTo: RST01 HocSubject: Composite document rev 2

3

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Hoc, PMT12Sunday, April 17, 2011 10:02 AMPMT10 Hoc

rev2Composite document rev 2.docx

.Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subject tochange and refinement.

kulkol,



OFFICIAL USE ONLY

2-

-7 r

/

•y

/.."....•


(b)(5)



(b)(5)

N

Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subject tochange and rcfinement.

(b)(5)


(b)(5)

Our assessments and recommendations are based on the best available technical information. We acknowledge thai the information is subject tochange and refinencnt.

(b)(5)

ij

* I

: •'\.-?

4


c ange an ., nement.

(b)(5)

Our assessments and recommendations are based on the best available technical information. We acknowledge tbaE the information is subject tochange and refinement

(b)(5)



(b)(5)

Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subject tochange and refinement

(b)(5)


(b)(5)


OFFICIAL USE ONLY

Our assessments and recommendations are based on the best available technical information. We acknowledge that the information is subjLct to


OFFICIAL USE ONLY

I's

Mk4

Wittick, Brian

From: Wittick, BrianSent: Monday, April 18, 2011 5:01 PMTo: Schwartzman, JenniferSubject: Re: Japan Nuclear Assistance Meeting (04/15)

Thanks


h(b)(6)

From: Schwartzman, JenniferTo: Wittick, BrianSent: Mon Apr 18 16:57:30 2011Subject: FW: Japan Nudear Assistance Meeting (04/15)

Item 2 of 2

From: Suttenberg, JeremySent: Monday, April 18, 2011 4:17 PMTo: Schwartzman, JenniferSubject: FW: Japan Nuclear Assistance Meeting (04/15)

Here's my write-up. Let me know if you have any other questions.

- Jeremy.

From: Burns, StephenSent: Monday, April 18, 2011 9:55 AMTo: Clark, Lisa; Bupp, Margaret; Reddick, Darani; Davis, Roger; Zorn, Jason; Coggins, AngelaCc: Hirsch, Patricia; Suttenberg, JeremySubject: FW: Japan Nuclear Assistance Meeting (04/15)

Below is FYI regarding a meeting we covered Friday.

From: Suttenberg, JeremySent: Friday, April 15, 2011 5:08 PMTo: Rothschild, Trip; Hirsch, Patricia; Kim, Grace; Burns, Stephen; Dyer, Jim; Virgilio, Martin; Weber, Michael; Doane,MargaretSubject: Japan Nuclear Assistance Meeting (04/15)

Attorney-Client Information

Today, I participated in an inter-agency meeting to discuss some legal issues involved with U.S. government assistance to

Japan. Attorneys from State and DOE are flying to Tokyo on Tuesday to meet with their Japanese counterparts, and this

was sort of a pre-meeting briefing. In attendance were lawyers from State, DOD, DOE, DOJ, and the NSC (a full

attendance list is attached).

(b)(5)

2

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- Jeremy

Jeremy SuttenbergAttorneyOffice of the General CounselU.S. Nuclear Regulatory Commission(301) [email protected]

3


Hoc, PMT12Monday, April 18, 2011 7:16 AMPMT10 HocFW:

Composite rev 3.docx; Composite rev 3 clean copy.docx; composite alternativerecommendations.docx

From: Milligan, PatriciaSent: Monday, April 18, 2011 3:05 AMTo: Hoc, PMT12; Wiggins, Jim; McDermott, Brian; [email protected]; Zimmerman, RoySubject:

I have attached three versions of the composite document.. one with tracked changes, one that is "clean" and onethat is a bit of a departure from the others.

I have several concerns about the composite document that were shared by some reviewers of the document in thecomments provided to me.

(b)(5)

I can be reached at1 (b)(6) or discussion. I am currently on travel - feel free to call anytime

Patricia Milligan, CHP, RPhSenior Technical Advisor for Preparedness & ResponseOffice of Nuclear Security and Incident ResponseUS NRC

1 ý1&1/ 16D

MS T B46MWashington, DC 20555301-415-2223

c berrT (b)(6)

2

Our ascssements and rcommendations •ae based on be b.st availble technical infotenatioo. We acktowledge tha the information is subject toichange and refitoerntt.

(b)(5)

Our assessments and recommcndations are bah d wn the best available technical information. We aclkmwledge that the informraion is subjc tochange and refinement.

(b)(5)

N

Our assessments and mcorunendadions ar= based on te bet available tecbnical information. We acknowledge that the iaformasion is subject tochooge and sfrmcmcnn.

(b)(5)

Our aSftsmnTs and recomencndations are based on the bct available etehnical informbation. We acknowledge that ibe information is subjecc tochange and refinement.

(b)(5)

Our usur~wwuts and recommenodations are based on the bocs available technical infonruaion. We acknowledge that the infortoation is subject tochange and refitenettnt.

(b)(5)

Our assesmmnti and recoimiendatiorts are based m the bost available techni,:al information. We akowimoologe that the inforrmolton is subject tochoasg and refinemento.

(b)(5)

Our assesssonens and emwmnd~tions are based on, the be~st available technical infonnaiion. We mcknowkcdge that the infonmatioa is subject tochange and refinement.

(b)(5)

Osm assessments and rnvommendwan u c bse an the best available tudmcniW infoxmaxio We ackto'utudV tha tdu information, is subita tocbaogc and refinemnt.n

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Our asesuments and recominendatiocs are based on the best available tcehnical ntwmuiion. WVe sknovvlcdgc tha.t the info-taion is subject tochange and rtfinemcnt-

(b)(5)

0Chu assssmcnut and rccomrnzndations are based on the best ,s'ailabic technical infromiion. We acknowledge that the infotmutin is subjeccto1chanoge and refmcsneot.

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Our assessr•ns and recommendations a=e based on the best available technical informntion. We acknowledge bat the infonraion is subject to

change and trinenseet.

(b)(5)

Our assostmcnts and mo uenaidons are based on the best avoilabku ec~hnicad itornarion. we acmo'nledge that the infonntion is subject tochange and refinement.

(b)(5)

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Our assasmtnt and r.ncomctndations are basd on the ba.t available technical inflornation. Wc acknowlcdgc hat the information is subject tochagc and efrnemert.

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From:SentTo:

Subject.Attachments:

RSTO1 HocTuesday, April 19, 2011 3:39 PM

(b)(6)

11:00am Technical Consortium SummaryApril 19 1100 Summary.docx

All,

Attached is the 11:00am Technical Consortium Summary.

RST

,*F6//(;>/

Summary of Technical Consortium 11:00 a.m. Call of 4/19/2011

NRC - D. Skeen, L. Criscione, L. Vick

Consortium - Representatives from GEH, INPO, EPRI, AFRI, BETIS, and Naval Reactors

Regarding N2 iniection into a containment with a high steam generation rate

It was pointed out by one Consortium member that Unit 1 is generating approximately 266 cubicfeet of 02 per day which would take some time to build up a significant concentration. Overall,TEPCO's Unit 1 approach appears to mitigate any H2 concerns at this time. However, source

of coolant leak remain unknown to-date and is contributing to uncertainties for re-flooding thevessel/containment.

Recommendations/comments regarding N2 strategy/discussion for Unit 2 and 3 continues.

TEPCO Road Map

Overall, Consortium is reviewing the roadmap for comment feedback. Generally, the time lineshould be shorter rather than longer. More detail is needed for practical implementation.

Site Team Feedback (Casto)

Site team reported that TEPCO is transferring about 480 TONS per day of water to Radwaste -it will take about 26 days to complete the task.

Robot information regarding Unit 2 indicates that Unit 2 reactor building is full of steam, 40

Degrees C. TEPCO is looking for a way to entomb the reactor building basement. Site teamsuspects that bellows may be ruptured/failed.

Mr. Casto mentioned 4 long term issues: 1) Stopping the leak from the suppression pool; 2)water getting into turbine building trenches may be coming from Unit cross-connect pipingassociated with the radioactive waste system; 3) TEPCO need help with high level wasteprocessing - Maybe DOE labs has suggestions; 4) Unit 3 reactor building is inaccessible due alot of debris and equipment damage in the N2 piping area plus very high radiation areas -TEPCO is looking for alternate ways of injecting Nitrogen; 5) Unit 2 precludes N2 due to inabilityto maintain pressure in the drywell.

The following was sent to the Japan Site Team:

1. Ask TEPCO what is the strategy once unit 1 is at TAF. Is there a way to recirc and coolcontainment/torus? Are they going to continue to inject at a low rate to make up forboiling and vent steam? What affect will this have on salt/boron etc.?

2. What is the current pump head/max RPV injection rate for all units (1, 2, 3)?

3. Send basis as to why TEPCO believes unit 1 is only at 4 ft in containment?4. Please see email concerning data which used to be supplied from TEPCO

-. Kock, Andrea

From:Sent:To:Cc:Subject:

Kock, AndreaTuesday, April 19, 2011 5:36 PMBubar, Patrice; Merzke, Daniel; Milligan, PatriciaTadesse, RebeccaRE: EPA guidance on reentry and return

Thanks, Patty for framing those questions! It would be helpful to discuss those. The only other questions Ivini rid hnita wrn dri ha=-

(b)(5)

Thanks to all for meeting with us if you can!

Andrea KockUnited States Nuclear Regulatory CommissionTechnical Assistant for MaterialsOffice of Commissioner Ostendorff301-415-2896

From: Bubar, PatriceSent: Tuesday, April 19, 2011 4:55 PMTo: Merzke, Daniel; Milligan, Patricia; Kock, AndreaCc: Tadesse, RebeccaSubject: RE: EPA guidance on reentry and return

f

(b)(5)

Trish - I know you are just getting back into the country so you may not even know what time zone you are in. But if wecould find some time tomorrow for me and Andrea Kock to meet with you - that would be quite helpful.

I was trying to arrange time through Sandra Cianci to have us meet with Marty but that is not going to be possibletomorrow. I have asked Sandra to find some time with Marty early Thursday - if possible - before the meeting with theother federal agencies on the PAGs.

If we can find some time to meet - here is a sampling of the topics I would like to discuss:

(b)(5)

1

(b)(5)

Andrea may have other questions to discuss.

Thank you for your consideration. Dan - thank you for assisting us with this also.

Patty BubarChief of StaffOffice of Commissioner William D. MagwoodU.S. Nuclear Regulatory Commission301-415-1895

4

From: Merzke, DanielSent: Tuesday, April 19, 2011 3:40 PMTo: Batkin, Joshua; Bradford, Anna; Sharkey, Jeffry; Castleman, Patrick; Thoma, John; Monninger, John; Sosa, Belkys;Baggett, Steven; Bubar, Patrice; Tadesse, Rebecca; Nieh, Ho; Kock, AndreaCc: Virgilio, Martin; Weber, Michael; Milligan, Patricia; Vietti-Cook, AnnetteSubject: RE: EPA guidance on reentry and return

(b)(5)

I hope this clears up the question. If you have further questions, please let me know.

Dan

From: Kock, AndreaSent: Tuesday, April 19, 2011 2:59 PMTo: Milligan, Patricia; Merzke, DanielSubject: FW: EPA guidance on reentry and returnImportance: High

(b)(5)

Thanks

2

Andrea Kock

United States Nuclear Regulatory Commission

Technical Assistant for Materials

,Office of Commissioner Ostendorff

301-415-2896

From: Vietti-Cook, AnnetteSent: Tuesday, April 19, 2011 12:37 PMTo: Kock, AndreaSubject: FW: EPA guidance on reentry and returnImportance: High

From: Vietti-Cook, AnnetteSent: Tuesday, April 19, 2011 12:34 PMTo: Batkin, Joshua; Monninger, John; Sharkey, Jeffry; Castleman, Patrick; Sosa, Belkys; Snodderly, Michael; Bubar,Patrice; Orders, William; Nieh, Ho; Franovich, MikeSubject: FW: EPA guidance on reentry and returnImportance: High

(b)(5)

From: Zimmerman, Roy -Sent: Tuesday, April 19, 2011 12:23 PMTo: Virgilio, Martin; Vietti-Cook, Annette; Milligan, PatriciaCc: Hoc, PMT12Subject: FW: EPA guidance on reentry and returnImportance: High

(b)(5)

From: Keith, Sam (ATSDR/DTEM/ATB) [mailto:[email protected]]Sent: Tuesday, April 19, 2011 12:05 PMTo: Hoc, PMT12; RST01 HocCc: Zimmerman, Roy; LIA08 HocSubject: EPA guidance on reentry and returnImportance: High

Sandy,

I would appreciate you sharing this message and attachment with Trish at the earliest. I am copying ET and UA on this.

Thanks,Sam .KeithCDC Liaison

3

From: OST01 HOCSent: Tuesday, April 19, 2011 2:40 PM

To: RST01 HocSubject: RE: Task No 4847 "ASSIGN A ITEM JOINTLY TO NSIR AND NRR"

Please advise OST01 if this e-mail effectively closes task 4847.

Thank you,

EST Support

From: Hiland, PatrickSent: Tuesday, April 19, 2011 2:33 PMTo; Dudek, Michael; RST01 Hoc; OST01 HOCCc: Skeen, David; Brown, FrederickSubject: Task No 4847 "ASSIGN A ITEM JOINTLY TO NSIR AND NRR"Importance: High

The below was sent to ET yesterday. NRR assumes that this closes Task No. 4847.

From: Brown, FrederickSent: Monday, April 18, 2011 4:45 PMTo: Virgilio, Martin; Zimmerman, Roy; Wiggins, Jim; Uhle, Jennifer; Boger, Bruce; Dyer, JimCc: Skeen, David; Hiland, Patrick; Milligan, Patrida; Reynolds, Steven; Casto, Chuck; OST01 HOC; RST01 HocSubject: RE: ACTION: ASSIGN A ITEM JOINTLY TO NSIR AND NRRImportance: High

(b)(5)

Fred

.-k

Our assessments and recommendations are based on the best available technical information.. We acknowledge that the information is subject tochange and refinement.

(b)(5)


(b)(5)

From:Sent:To:SubjectAttachments:

PMT10 HocTuesday, April 19, 2011 6:58 [email protected]: composite paper OFFICIAL USE ONLY

Composite rev 5.doc; composite rev 5 with tracked changes.doc

For ability to work remotely with NRC on this document

From: Hoc, PMT12Sent: Tuesday, April 19, 2011 8:36 AMTo: PMT10 HocSubject: FW: composite paper

From: Milligan, PatridaSent: Tuesday, April 19, 2011 8:27AMTo: Hoc, PMT12Subject:

Here is the paper, the internet was down at the hotel this am until now. who does upgrades at 6 am??Patricia Milligan, CHP, RPh

Senior Technical Advisor for Preparedness & ResponseOffice of Nuclear Security and Incident Response

US NRC

MS T B46M

Washington, DC 20555

AB01-415-2223Blackberry (b)(6)

I

S69116) ý

A

From: Dudek, MichaelSent: Tuesday, April 19, 2011 3:55 PMTo: OST01 HOC; Hoc, PMT12Cc: Milligan, Patricia; Williams, Kevin; Holahan, Patricia; McDermott, Brian; Norris, MichaelSubject: CLOSURE OF ACTION #4906. - Review of EPA vs. NRC re-entry guidance documentsAttachments: EPAs Version Reentry-Return_4-13-2011.docx; Composite rev 6.doc

Operations Center,

(b)(5)

Please close action #4906 for NSIR.

Thanks,Michael I. Dudek

Michael Dudek I Technical Assistant I NSIR/Division of Preparedness & Response I U.S. NRC11555 Rockville Pike, Rockville, MD 20852 I2 (301) 415-6500 1 S: Michael.DUdckdnC._ov

From: Dudek, MichaelSent: Tuesday, April 19, 2011 2:50 PMTo: OST01 HOC; Hoc, PMT12Cc: Merzke, Daniel; Milligan, Patricia; Williams, KevinSubject. RE: ACTION: Review of EPA vs. NRC re-entry guidance documents

Operations Center,

Please advise.

Michael Dudek I Technical Assistant I NSIR/Division of Preparedness & Response I U.S. NRC11555 Rockville Pike, Rockville, MD 20852 I W (301) 415-6500 I 2;: hMich.-I.Dudek(i:nrc.qv

From: OST0i HOCSent: Tuesday, April 19, 2011 2:00 PMTo: Hoc, PMT12; Dudek, MichaelSubject: RE: ACTION: Review of EPA vs. NRC re-entry guidance documents

This ticket was sent out of process. Please refer all questions to PMT. Due date is ASAP for meeting at the White House

tomorrow:


POC for NRR

Question to be answered by NSIR:

1

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(b)(5)

This ticket is being tracked in the Japan SharePoint page (http://nsir-

ops.nrc.gov/Lists/HOC%20Red%2OTickets/AIlItems.aspx) under ticket number 4906.



******Please note: All attachments are Official Use Only**********

From: Dudek, MichaelSent: Tuesday, April 19, 2011 1:41 PMTo: Hoc, PMT12Subject: RE: ACTION: Review of EPA vs. NRC re-entry guidance documents

When is this due? What is the Tasking? Concurrence?

Michael Dudek I Technical Assistant I NSIR/Division of Preparedness & Response I U.S. NRC11555 Rockville Pike, Rockville, MD 20852 I V (301) 415-6500 1 2T: MichaeV.Dudck6F'nrc.gov

From: Hoc, PMT12Sent: Tuesday, April 19, 2011 1:10 PMTo: Dudek, MichaelSubject: ACTION: Review of EPA vs. NRC re-entry guidance documentsImportance: High

Michael,

Please be diligent in assigning this task.

V/r,

Kimberly GambonePMT12

2


Hoc, PMT12Tuesday, April 19, 2011 8:37 AM

LIA08 Hoc; OST01 HOC; RST01 Hoc; Zimmerman, Roy

FW:Composite rev 5.doc; composite rev 5 with tracked changes.doc

From: Milligan, PatriciaSent: Tuesday, April 19, 2011 8:27 AMTo: Hoc, PMT12Subject:

Here is the paper. the internet was down at the hotel this am until now. who does upgrades at 6 am??Patricia Milligan, CHP, RPh

Senior Technical Advisor for Preparedness & ResponseOffice of Nuclear Security and Incident ResponseUS NRCMS T 846MWashington, DC 20555

-301-415-2223Blackber b

Lee, Richard

From: Salay, MichaelSent: Wednesday, April 20, 2011 7:50 AMTo: Lee, RichardCc: Marksberry, Don; Esmaili, HosseinSubject: RE: NRR ANSWER ON NITROGEN PURGE

Richard,

We did not send this writeup. HQ RST had already provided their comments to the Japan Team(Jeff Mitman is on the RST in Japan). What we were saying was mostly consistent with whatcontributed by NRR. The two sentences that I sent Jeff more concisely state the differences.

-Mike----- Original Message -----

From: Lee, RichardSent: Tuesday, April 19, 2011 8:39 PMTo: Salay, Michael; Marksberry, Don; Esmaili, HosseinSubject: RE: NRR ANSWER ON NITROGEN PURGE

Mike:

Have RES provided the writeup you sent yesterday on nitrogen inerting to RST?

Richard

From: Salay, MichaelSent: Tuesday, April 19, 2011 12:11 PMTo: Marksberry, Don; Esmaili, HosseinCc: Lee, RichardSubject: FW: NRR ANSWER ON NITROGEN PURGE

From: Salay, MichaelSent: Tuesday, April 19, 2011 8:20 AMTo: Mitman, JeffreySubject: RE: NRR ANSWER ON NITROGEN PURGE

Jeff,

It seemed to me that the argument that was being made that they are steam purging (flushingcombustible gases out of DW with steam), not that they are steam inerting (making acombustible mixture non-combustible by increasing the steam concentration). Do we know forsure, however, that they are flushing through leaks in the DW and not through the SP thuspotentially leaving the DW atmosphere mostly unchanged?

-Mike

From: Mitman, JeffreySent: Tuesday, April 19, 2011 12:01 AMTo: Liaison JapanSubject: FW: NRR ANSWER ON NITROGEN PURGE

From: RST01 Hoc

Sent: Tuesday, April 19, 2011 9:44 AMTO: Mitman, Jeffrey; PMTjapan ResourceSubject: FW: NRR ANSWER ON NITROGEN PURGE

From: Harrison, DonnieSent: Monday, April 18, 2011 4:25 PMTo: Hiland, Patrick; RSTO1 Hoc; OST01 HOCCc: Skeen, David; Ruland, William; Brown, FrederickSubject: RE: NRR ANSWER ON NITROGEN PURGE

(b)(5)

From: Hiland, PatrickSent: Monday, April 18, 2011 3:57 PMTo: RSTO1 Hoc; OSTO1 HOCCc: Skeen, David; Ruland, William; Brown, Frederick; Harrison, DonnieSubject: NRR ANSWER ON NITROGEN PURGEImportance: High

The evaluation of Nitrogen purge vs. steam has been reviewed by NRR. The comments below

incorporates GEH's review and our own assessment. FYI, the contributors are noted in parens.

(Fred Brown)"I believe that GEH has discussed this on our calls.

I

(b)(4),(b)(5)

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---

76

....

From: RSTO1 HocSent: Monday, April 18, 2011 4:59 AMTo: Hiland, Patrick; OSTOl HOCCc: RSTO1 Hoc; Skeen, David; Ruland, WilliamSubject: ACTION: ASSIGN A ITEM TO NRR

Please assign the following action thru task tracker:

As a result of discussion with the Site team at the 0300, 18 April 2011 call the issuesassociated with the nitrogen inerting were clarified. - , (b)(5)

If possible provide input to RST before 1100 18 April 2011. If this is not possible pleaseprovide RST with estimated completion time.

77

V.

From: Gambone. KimberlySent Friday. April 22, 2011 7:40 PMTo: Milligan, PatriciaCc: Kokajko, Lawrence; Hoc, PMT12; RST01 Hoc; LIA08 Hoc; OST01 HOCSubject: RE: revised guidelines

Thanks Trish. I'll get this routed for review.

Kimberly

From: Milligan, PatriciaSent: Friday, April 22, 2011 6:54 PMTo: Gambone, KimberlySubject: Fw: revised guidelines

Sent from my NRC BlackberryPatricia A Milligan, CHP RPh

(b)(6 Io M 1

From: Milligan, PatriciaTo: Hoc, PMT12Sent: Fri Apr 22 18:18:30 2011Subject: revised guidelines

(b)(5)

I am home all night.. if you need to talk. have the HOOs patch you thru.

Thanks

1 ý 67//e," ý

Patricia Milligan, CHP, RPhSenior Technical Advisor for Preparedness & Response

Office of Nuclear Security and Incident ResponseUS NRCMS T B46MWashington, DC 20555301-415-2223Blackberry (b)(6)

2

From: OST01 HOCSent: Friday, April 22, 2011 2:54 PMTo: FOIA Response.hoc ResourceSubject: FW: Response to Letter from Rep. Markey to Sec. ChuAttachments: NA-40 Markey Letter Draft Response 4-21.docx

----- Original Message----From: LIA08 HocSent: Friday, April 22, 2011 2:49 PMTo: McGinty, Tim; Giitter, JosephCc: Kokajko, Lawrence; Droggitis, Spiros; RST01 Hoc; Hoc, PMT12; OST01 HOCSubject: FW: Response to Letter from Rep. Markey to Sec. Chu

Mr. McGinty and Mr. Gitter:

NRC has been asked to review and comment on the attached draft letter from DOE to Rep Markey. Per ET Directordirection, I am sending it to DORP and DPR for review. Please send any comments back to Spiros Droggitis and to LIA08.Thank you.

V/R,

Clyde Ragland

Liaison Team CoordinatorUS Nuclear Regulatory Commissionemail: [email protected]

Desk Ph: 301-816-5185

---- Original Message----From: LIA08 HocSent: Friday, April 22, 2011 1:51 PMTo: RST01 Hoc; Hoc, PMT12; OST01 HOC; Kokajko, LawrenceSubject: FW: Response to Letter from Rep. Markey to Sec. Chu

I have reviewed the attached, and do not see any problems with this draft, but I assume others will need to reviewbefore getting back to Spiros. Does anyone else need to review/have comments? Does anyone k now if this differs fromwhat we have told Rep. Markey?

Please respond before end of shift. Thanks!

Clyde Ragland

Liaison Team Coordinator

US Nuclear Regulatory Commission

email: [email protected]

Desk Ph: 301-816-5185

----- Original Message -----From: Stransky, RobertSent: Friday, April 22,2011 1:38 PMTo: LIA08 HocSubject: FW: Response to Letter from Rep. Markey to. Sec. Chu

----- Original Message -----From: Droggitis, Spiros

Sent: Friday, April 22, 2011 8:41 AMTo: Stransky, RobertSubject: FW: Response to Letter from Rep. Markey to Sec. Chu

Robert: FYI, in Bill and Scott's absence. Could you please have someone take a look at this draft DOE response andprovide comments to DOE? Thanks, Spiros

----- Original Message----From: Droggitis, SpirosSent: Friday, April 22, 2011 8:38 AMTo: Gott, WilliamSubject: FW: Response to Letter from Rep. Markey to Sec. Chu

Bill: FYI in Scott's absence. Could you have someone take a look at this draft DOE response and provide comments toDOE? Thanks, Spiros

---- Original Message -----From: Droggitis, SpirosSent: Friday, April 22, 2011 8:36 AMTo: Morris, Scott; Benowitz, Howard

Subject: FW: Response to Letter from Rep. Markey to Sec. Chu

Scott/Howard: I am out today. I received this proposed response from DOEto Congressman Markey's March 13 letter to the President. Would you mind taking a look at it and getting back to CarlPavetto, as appropriate?Thanks, Spiros

----- Original Message -----From: Pavetto, Carl [mailto:[email protected]]

Sent: Friday, April 22, 2011 8:21 AMTo: Droggitis, SpirosSubject: Response to Letter from Rep. Markey to Sec. Chu

Hi Spiros

The Secretary received a letter from Congressman Markey asking questions

about the federal government's response to a crisis like the crisis in

Japan.

2

The letter was originally sent to the President and it was referred to DOEeven though the substantive answers to most of the questions would not be a

DOE lead.

We have prepared a response that I attach. If you could be.so kind as to

review the draft response or forward it to whomever else in NRC might have

input, I would appreciate it.

Thanks!

CSP

3

4

(b)(5)

Sincerely,

Steven Chu


RST01 HocFriday, April 22, 2011 10:35 AMRST01A HocFW: Some layout drawings and P&IDs for 1F1

1F1, RWCU (729E466).pdf; 1F1, Shutdown reactor Cooling System (729E484).pdf; IF1,SLC (161F259).pdf 1F4 RFF Laydown.pdf; 1F4_FPCPID.pdf; 1FX, CRD Hydraulic

(104R944).pdf; 1FX, Reactor Internal Data (729E257_0).pdf 1FX, Reactor Vessel andReculation Loop Data (729E523).pdf; 730E427C STD Plant Containment Drawing IF1Type[1].pdf; 1F1, 1F2, 1F3, Assorted Reactor Building Elevations.pdf; 1F1, AtmosphericControl System (161F278 ).pdf 1F1, Containment Spray Cooling System (148F709).pdf1F1, Core Spray System (919D677).pdf; 1F1, Fuel Pool Cooling (729E483r5).pdf, 1F1,HPQ (729E465 shl).pdf; 1F1, HPCI (729E465 sh2).pdf; 1F1, Isolation Condenser System(729E503).pdf

From: Marksberry, DonSent: Thursday, April 21, 2011 1:42 PMTo: RST01 HocSubject: Some layout drawings and P&IDs for IFI

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RST02 HocFriday, April 22, 2011 3:43 PMOST01 HOCApril 22 roadmap assessmentRev.l.docxApril 22 roadmap assessmentRev.l.docx

Avlqltt (1

April 22, 2011

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From:Sent:To:Cc:

Subject:Attachments:

Follow Up Flag:

Flag Status:

For your review.

Norwood

Norwood, DonaldSunday, April 24, 2011 2:31 AMRST01 HocMitman, Jeffrey; Garchow, Steve; Lupold, Timothy, '[email protected]'; Norwood,

DonaldFukushima Plant Drawings

Rx Bldg a.pdf; Rx Bldg b.pdf; Rx Bldg c.pdf Rx Bldg d.pdf; Atmosphere Control.pdf;

Cntmt Data.pdf; Core Spray.pdf HPCLpdf& Iso Condenser.pdf; RPV Internals.pdf

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Follow Up Flag:Flag Status:

Garchow, SteveMonday, April 25, 2011 2:18 AMMitman, Jeffrey; Moore, Carl; Lupold, Timothy; Norwood, DonaldRST01 HocFW: Bellows drawing for Reactor well seal and vent line.NX-7831-3 Reactor bellows.pdf, NX-7865-2 Reactor well seal.pdf; NX-8291-97[ 89'bellow for vent line.pdf

Follow upFlagged

fyi

--- Original Message -----From: Reynolds, Steven

Sent: Monday, April 25, 2011 2:16 AMTo: Garchow, SteveSubject: Fw: Bellows drawing for Reactor well seal and vent line.

---- Original Message ----

From: Foster, Dirk L CAPT USN (b)(6)

To: Reynolds, Steven; Casto, Chuck; Gard, Lee A (INPO) <[email protected]>

Sent: Mon Apr 25 02:12:26 2011Subject: FW: Bellows drawing for Reactor well seal and vent line.

Attached are unsolicited engineering drawings forwarded to me by the Monticello PC system engineer. He thoughtthese might be useful. I have no idea if they are similar to Fukushima or not.

Let me know if there is any other information from Monticello that you might be interested in.

Dirk

-- Original Message-----From: Foster, Dirk L. [mailto:[email protected]]

Sent: Monday, April 25, 2011 11:49 AMTo: Foster, Dirk L CAPT USNSubject: FW: Bellows drawing for Reactor well seal and vent line.

From: Bush, Devin

Sent: Friday, April 22, 2011 2:34 PM

To: Wojchouski, Alan V.aCc (b)(6) Foster, Dirk L.Subject: FW.: Bellows drawing for Reactor well seal and vent line.

I

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Thanks AlM

I'll forward these to Dirk also. He is in Japan assisting with theFukushima crisis.

From: Wojchouski, Alan V.Sent: Wednesday, April 20,2011 11:19 PMTo: Bush, DevinSubject: Bellows drawing for Reactor well seal and vent line.

Devin

Attached are the drawing for the reactor seal bellow and it'sarrangement.Also the drawing for the vent line bellows.

Hope these help.

Alan W.

2

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From:Sent:To:Attachments:

Hoc, PMT12Monday, April 25, 2011 6:52 PMPMT1O Hoc

Composite rev 8.docx

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Our assessments and recommendations are based on the best availabletechnical information. We acknowledge that the information is subject to


(b)(5)

(b)(5)

Our assessments and recommendalions are based on the best available technical information. We acknowledge that the information is subject to

change and refimement.

(b)(5)


(b)(5)

*2

f


PMT10 HocMonday, April 25, 2011 8:39 PMHoc, PMT12CDC comments on Composite document rev 8Composite document rev 8 CDC cmts 2011-04-25.docx

Stacy, my comments on the Composite document are attached for Trish's consideration. Please let me know if you haveany questions.

Thanks,Sam KeithCDC Liaison

From: Hoc, PMT12Sent: Monday, April 25, 2011 6:52 PMTo: PMT1O HocSubject:

1

Our asessmc'ns and rccommendnatons a= based on the best available technical inafomnation. We aclaowledge that the infonnation is subject tochange and refinement.

(b)(5)

Our assessmcats and rmcotntnedations are based on the best available technical information. We acloowledge that the infonnasio is subjcti to

(b)(5)

2-.

Owr asscssmcnts and r comdatijo,, = based axtth best available, techicalI infonmrion We acknowledge that the info~tm~o is subject tocbeogc and rtfnci~mtr.

(b)(5)

Our ascssntents and recom mendations are based on the besýt available technical inroetnotion. We acknowleJge that the infontttarion is subject tochange and refinement.

(b)(5)

Our ssessments and recornmmendations ae. based on the best available tcchnical is•fonnation. We acknowledge that the infoarnasion is subjct tochange and rtfintmet.

(b)(5)

N.N,


OST01 HOCMonday, April 25, 2011 5:13 PMFOIA Response.hoc Resource

FW: REPLY: revised guidelines - CJ commentsComposite rev 8 cj edits.docx

From: Jones, CynthiaSent: Monday, April 25, 2011 4:16 PMTo: Milligan, Patricia; McDermott, Brian; Williams, KevinCc: Merzke, Daniel; Bush-Goddard, Stephanie; Andersen, James; Bowman, Gregory; Virgilio, Martin; Gambone, Kimberly;Dudek, Michael; MorganButler, Kimyata; Jackson, Deborah; Weaver, Doug; Hiland, Patrick; Skeen, David; Ciocco, Jeff;Kevern, Thomas; Wiggins, Jim; Evans, Michele; Holahan, Patricia; Tracy, Glenn; Uhle, Jennifer; Carpenter, Cynthia;Johnson, Michael; Kokajko, Lawrence; Weber, Michael; RST01 Hoc; LIA08 Hoc; OST01 HOC; Reynolds, Steven; Holonich,Joseph; Casto, Chuck; PMTjapan Resource; Holahan, Vincent; Zimmerman, Roy; Boger, Bruce; Layton, Michael; Lewis,RobertSubject: RE: REPLY: revised guidelines - C comments

My comments to Trish's revised edits from this PM are attached.

(b)(5)

Thank for the opportunity to commentCyndi

Sent: Monday, April 25, 2011 9:25 AMTo: Virgilio, Martin; Gambone, Kimberly; Dudek, Michael; MorganButler, Kimyata; Jackson, Deborah; Weaver, Doug;Hiland, Patrick; Skeen, David; Ciocco, Jeff; Kevem, Thomas; Wiggins, Jim; Evans, Michele; Holahan, Patricia; Tracy,Glenn; Uhle, Jennifer; Carpenter, Cynthia; Johnson, Michael; Kokajko, Lawrence; Weber, Michael; RSTO1 Hoc; LIA08 Hoc;OST01 HOC; Reynolds, Steven; Holonich, Joseph; Casto, Chuck; PMTjapan Resource; Holahan, Vincent; Zimmerman,Roy; Jones, Cynthia; Boger, Bruce; Layton, Michael; Lewis, Robert; McDermott, Brian; Williams, Kevin

Cc: Merzke, Daniel; Bush-Goddard, Stephanie; Andersen, James; Bowman, GregorySubject: RE: REPLY: revised guidelines

Please review and comment.

thank you.Trish

Patricia Milligan, CHP, RPhSenior Technical Advisor for Preparedness & Response

Office of Nuclear Security and Incident Response

US NRC

MS T B46M

Washington, DC 20555301-415-2223

BlackberryI (b)(6)

From: Virgilio, MartinSent: Sunday, April 24, 2011 12:24 PMTo: Gambone, Kimberly; Dudek, Michael; MorganButler, Kimyata; Jackson, Deborah; Weaver, Doug; Hiland, Patrick;Skeen, David; Ciocco, Jeff; Kevern, Thomas; Wiggins, Jim; Evans, Michele; Holahan, Patricia; Tracy, Glenn; Uhle,Jennifer; Carpenter, Cynthia; Johnson, Michael; Kokajko, Lawrence; Weber, Michael; Holahan, Patricia; RST01 Hoc; LIA08Hoc; OST01 HOC; Skeen, David; Hiland, Patrick; Reynolds, Steven; Holonich, Joseph; Casto, Chuck; PMT japanResource; Holahan, Vincent; Tracy, Glenn; Zimmerman, Roy; Holahan, Patricia; Jones, Cynthia; Boger, Bruce; Wiggins,Jim; Kokajko, Lawrence; Uhle, Jennifer; Layton, Michael; Carpenter, Cynthia; Johnson, Michael; Lewis, Robert; Milligan,PatriciaCc: Me~rzke, Daniel; Bush-Goddard, Stephanie; Andersen, James; Bowman, GregorySubject: REPLY: revised guidelines

All

Please set of goal at COB Monday for resolving these differences. NSIR lead.

Marty

2

From: Gambone, KimberlySent: Friday, April 22, 2011 8:02 PMTo: Virgilio, Martin; Dudek, Michael; MorganButler, Kimyata; Jackson, Deborah; Weaver, Doug; Hiland, Patrick; Skeen,David; Ciocco, Jeff; Kevern, ThomasCc: Holahan, Vincent; PMTjapan Resource; Tracy, Glenn; Zimmerman, Roy; Boger, Bruce; Wiggins, Jim; Uhle, Jennifer;Layton, Michael; Holonich, Joseph; Kokajko, Lawrence; Carpenter, Cynthia; Johnson, Michael; Lewis, Robert; Holahan,Patricia; Jones, CynthiaSubject: FW: revised guidelines

All,

Attached is the latest revision of the Composite Paper, i.e., "Recommendations for US citizens on relaxation ofthe 50 mile evacuation recommendation and re-entry to evacuate areas around Fukushima Daiichi NPP."NRC Operations Center PMT requests that all line organizations review and provide comment. We strive torelease the document to the federal family middle of next week.

Provide comments by COB Tuesday, April 2 6 th to PMT12.hocdnrc.Qov, Cc: Patricia Milligan.

Task Tracker #4969.

Please contact me if you have questions.

Thank you.

V/r,

Kimberly Gambone

PMT/PAAD

3

Ow a cmsmcrns and rrcovntlzdtions am~ based mw the ieti available technical infonntion. We aclaoinoledge that the inforention is suh~ut tochmgce and vefinemet.

(b)(5)

Our assessments and reomncneoaros are based on the bes available technical information. We acksohsdge that the information is subject tocbangc and refasemcot

(b)(5)

Our as~srmnenu and recommtendtricos an: based on the best available technical inforoastimr We acknowledge that the intonm~tor, issbn t.change and refinemenot.

(b)(5)

Our asusswerns and recomtmendations are based on the best available technical information. We aclknowledge that rci information is subject tochange and refinemcnt.

(b)(5)

Our asmsssrns and recommendations are based on the best availabi tecbhnical iefortnation. We aknowedgc tha the infoationo- is subject tocbange and refincrbent.

(b)(5)

Meighan, Sean

From:Sent:To:


Gard, Lee A (INPO) [[email protected]]Tuesday, April 26, 2011 1:14 AMHuffert, Anthony; Moore, Carl; Casto, Chuck; Gepford, Heather, Mitman, Jeffrey; Hay,Michael Sala Michael; Meighan, Sean; Garchow, Steve; Reynolds, Steven; Foster, Dirk LCAPT USN; (b)(6)

FW: April 26 plant Updates20110426 0100 Plant Parameters[1].pdf; 20110426 0500 Unit 1 Drywell Pressure[1].pdf;20110426 0700 Water Levels.pdf

Attached is the latest information on N2 purge, building water levels and temperature /pressure graphs.

.DISCLAIMER:This e-mail and any of its attachments may contain proprietary INPO or WANO information thatis privileged, confidential, or protected by copyright belonging to INPO or WANO. This e-mailis intended solely for the use of the individual or entity for which it is intended. If youare not the intended recipient of this e-mail, any dissemination, distribution, copying, oraction taken in relation to the contents of and attachments to this e-mail is contrary to therights of INPO or WANO and is prohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete theoriginal and any copy or printout of this e-mail and any attachments.Thank you.

)5Ij:/ v'lj-9 (a -Eb U ev9IUN5.lafffffto[•MitMAN

A Q 9R P *UhJ-

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4/24 12.00 -1500 -2050 -0.018 -0.025 0.080 23,6 26.5 0.497 115.0 0.084/24 1N00 -1500 -2050 -0.020 -0.025 0.080 23.5 26,4 0.496 107.0 0.07

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Hoc, PMT12Tuesday, April 26, 2011 3:07 PMPMT1O Hoc

FW: Update to paperComposite rev 9.docx

From: Milligan, PatriciaSent: Tuesday, April 26, 2011 3:01 PMTo: Uhle, Jennifer; Foster, Jack; Hoc, PMT12Subject: Update to paper

Comments?

Thanks.

1 ep)l I I I

Our assessments and mcommcndations arm bdwd on the b•st available technical infoenation. We acknowledge that the information is subject tochange and refinement.

(b)(5)

Our asscssr~nis and mccoumnntndmaons we bawd on the best available technical innorptation. We acknowledge dtha the infttotmaon is subject tochange and efitntent.

(b)(5)

' I

Owu ses~stniens and rerommnundation zre based on dhe best avadable techntint infomsaion. We acknosoledge tha the inforesaiin is subject tochange and mitenteasto.

(b)(5)

Our assessmrunts and rccoommaadarious arc bawd on the best available ech~nical infortmation. We xonowledge that the nformnaion is subject tochange and mraLacmtal.

(b)(5)

V ~"

Ow assessments and rvconmmendations are based on thn best available tchnical information. We aclmowledge that the inforenation is subject ancbange and reincment.

(b)(5)

Ouw asewmnt and racomiacndatious =rn based on dhr best available technical infoanrtian. We ackmoraledge that the information is subject toclhnagr and refinement.

(b)(5)

, . 2.. "

Meighan, Sean

From:Sent:To:

Gard, Lee A (INPO) [[email protected]]Wednesday, April 27, 2011 5:54 AMHuffert, Anthony; Moore, Carl; Casto, Chuck; Gepford, Heather; Mitman, Jeffrey; Hay,Michael; Salay Michael Mei'han, Sean; Garchow, Steve; Reynolds, Steven; Foster, Dirk LCAPT USN; (b)(6) I Wittick, Brian; Gregg Schneider; Lovell, Russ; Hochevar,Albert R. (INPO); Gakuto Nakamura; Gard, Lee A (INPO); Hiroyuki Matsuura; Junji Tanaka;[email protected]; Keith Moser; Michio Matsuda; Richard Rossi; Bob Holland;[email protected]; [email protected]; Shigeo Hattori; Shinya Fujii; ShujiFuruya; Yoneo Suzumegano; Tom StevensFW: April 27 briefing notes and excel spreadsheetTEPCO Sumarry Rev.101 Final April 27.xls; April.27 Ryan 6 pm briefing notes.doc


Attached are the briefing notes and parameter spread sheet. The radiation survey map was notavailable today.


F

Meighan, Sean

From:Sent:To:


Gard, Lee A (INPO) [[email protected]]Tuesday, April 26, 2011 9:37 AMHuffert, Anthony; Moore, Carl; Casto, Chuck; Gepford, Heather, Mitman, Jeffrey; Hay,Michael; Sala, M'hael; Meighan, Sean; Garchow, Steve; Reynolds, Steven; Foster, Dirk LCAPT USN;I (b)(6) ý ittick, BrianFW: April 26 briefing notes, excel spreadsheet and radiation survey map20110425 1640 Facility Area Survey Data[l].pdf; TEPCO Sumarry Rev.100 Final April 26.xls;April 26 Ryan 6 pm briefing notes.doc

Attached are the briefing notes, parameter spread sheet and survey map.


1°

Meighan, Sean

From:Sent:To:


Gard, Lee A (INPO) [[email protected]]Tuesday, April 26, 2011 1:07 AMHuffert, Anthony; Moore, Carl; Casto, Chuck; Gepford, Heather; Mitman, Jeffrey; Hay,Michael; Salay Mithnl. Mainhn aean; Garchow, Steve; Reynolds, Steven; Foster, Dirk LCAPT USN 1(b)(6)IFW: Drywell and SFP in o26 April Drywell Info.pdf; 26 April SFP lnfo.pdf

We have been told that the plan is to fill Unit 4 SFP between today and tomorrow and thenkeep adding to keep it full. They will both strengthen the Unit 4 RB and also "shore up"from underneath the Unit 4 SFP. We are trying to get the plan.


Water may be leaking from No. 4 reactor fuel pool

The operator of the troubled Fukushima Daiichi nuclear power plant says water may beleaking from the spent fuel pool of the No. 4 reactor.

More than 1,500 spent fuel rods are stored in the pool, the largest number at the site.

Tokyo Electric Power Company, or TEPCO, has been injecting water daily into the poolto make up for the loss of cooling function and prevent the fuel rods from being exposedand further damaged.

TEPCO has poured in 140 to 210 tons of water over each of the last few days. Thecompany found that water levels in the pool were 10 to 40 centimeters lower thanexpected despite the water injections.

The walls of the reactor building supporting the pool were severely damaged by ahydrogen explosion last month. TEPCO says the pool may have been damaged by theblast as well.

According to a schedule announced earlier on containing the ongoing emergency,TEPCO plans to install concrete pillars to support the fuel pool by around July to increaseits earthquake resistance.Wednesday, April 27, 2011 09:05 +0900 (JST)

Not for

27April at 06:00 A 09:00 (Rev-lIOl)


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FUKUSHIMA DAIICHI




* Ensuring fresh water injection and cooling capabilities to the reactorsand spent fuel pools. Goal is to reduce and maintain temperature inthe reactors and spent fuel pools below 100 degrees centigrade.

" Draining water from the turbine buildings and trenches to reduce theradiation levels so that work can continue.



" N2 purging of the Unit 1 Drywell was stopped yesterday forapproximately five hours while power supply lines from Unit 5/6 wereconnected to a Unit 1/2 load center to improve reliability of Units 1 and2. During that time, Drywell pressure decay and decay rate wasmonitored and used to estimate free space and water level in theDrywell. It is now believed that Drywell water level is .5 m below thebottom of the reactor vessel.

" The robot entered the Unit 1 reactor building on Tuesday to check forpossible leakage from an electrical penetration or other areas on thereactor building first floor. No leakage was observed. TEPCO isconsidering increasing injection flow up to 14 m3/hr to increase theflooding rate of the Drywell.


* Unit 2 trench level decrease has slowed dropping only 10 mm sinceyesterday. It is now 890 mm below the trench top. Unit 3 trench levelhas increased an additional 20 mm and is now 980 mm from the top.

" After four days of stability, Unit 4 turbine building water level increased50 mm and is now 3050 mm (1.5 m above floor level) which is slightlyhigher than the Unit 3 turbine building water level of 3000 mm.

" Two hundred ten tons of water were added to the Unit 4 Spent FuelPool (SFP) yesterday. Another 160 ton addition is scheduled for todayto fill the pool. The structural integrity of the Unit 4 SFP is consideredsufficient to support a full SFP. Calculations and observations indicatethat approximately 82 tons of water is needed to be added to the Unit 4SFP daily to maintain level.

" Thirty-eight tons of water was added Unit 2 SFP yesterday. Fifty tonsof water is scheduled to be added to the Unit 3 SFP today. Boil offrates are 21 tons/day and 17 tons/day respectively.

I

Unit Status

* In Unit 1, non-borated fresh water injection into the main feedwater linecontinues at 6.1 m3/hr. Comments on parameters:

- Reactor pressure indicator A is increased slightly to .450 MPa abs(65 psig). Indicator B continues to be suspect.



- Drywell and Torus pressure remained at .150 MPa abs (22 psia).- Drywell and Torus dose rates are considered to be suspect.

" In Unit 2, injection of non-borated fresh water using the low pressurecoolant injection continues at 7 m3/hr. Comments on parameters:

- Unit 2 reactor pressures remain suspect.- Feedwater nozzle temperature decreased slightly to 122 C (252

F)- Reactor vessel lower temperature is believed unreliable.- Drywell pressure was stable near atmospheric.- Dose rate in the U2 Drywell continues to decrease. The drywell

dose rate is 2.31 Sv/hr or (2,310 Rem/hr). The Torus dose ratereading is considered suspect.

" In Unit 3, of non-borated fresh water using the low pressure coolantinjection continues at 6.8 m3/hr. Comments on parameters:






Dose Rates

Overall site dose rates are stabilizing or only varying slightly. Forexample:

The last reading reported at the main gate was 52 pISv /hr (5.2mrem/hour) and be 23 pSv /hr (2.3 mrem/hour) at the west gate.

> The side of the administration building facing the unitsdecreased slightly to .450 pSv/hr or 45 mrem/hr. The same asyesterday.

2

Meighan, Sean

From:Sent:To:


Gard, Lee A (INPO) [[email protected]]Wednesday, April 27, 2011 3:07 AMHuffert, Anthony; Moore, Carl; Casto, Chuck; Gepford, Heather, Mitman, Jeffrey; Hay,Michael; Sal haelS Meiahan Sean; Garchow, Steve; Reynolds, Steven; Foster, Dirk LCAPT USN;I (b)(6) fittick, BrianFW: Unit 4 RB support planPlan for Unit 4 RB support.pdf

Attached is an overview of the support being considered for Unit 4 RB.still saying additional support is not need so this is "just in case".July.

Presently TEPCO isSchedule runs until

Drawing details in Japanese, we will work to translate.

-Lee

Restricted Distribution: Copyright @ 2011 by the Institute of Nuclear Power Operations. Notfor sale or for commercial use. Reproduction of this report without the prior written consentof INPO is expressly prohibited. Unauthorized reproduction is a violation of applicable law.The person or persons that are furnished copies of this report should not deliver or transferthis report to any third party, or make this report or its contents public, without the prioragreement of INPO. All other rights reserved.


IF4 R/B I*SIfttUX

Gý in, A'0'0

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_______ i i' I I•1, , ' I a II

(32*(16PX2MOU) *ý9(RIM).

oilI" Roo" RXd% IY

Meighan, Sean

From:Sent:To:


Gard, Lee A (INPO) [[email protected]]Wednesday, April 27, 2011 4:46 AMHuffert, Anthony; Moore, Carl; Casto, Chuck; Gepford, Heather, Mitman, Jeffrey; Hay,Michael; Salay, Michael; Meighan, Sean; Garchow, Steve; Reynolds, Steven; Foster, DirkCAPT USN;[ (b)(6) ]Wittick, BrianFW: unit 4 RB support plan1F4 RB SFP Reinforcement Plan (Draft).pdf

English translation now of the Unit 4 R/B Spent Fuel Pool Reinforcement Plan (Draft)

.DISCLAIMER:This e-mail and any of its attachments may contain proprietary INPO or WANO information thatis privileged, confidential, or protected by copyright belonging to INPO or WANO. This e-mail

is intended solely for the use of the individual or entity for which it is intended. If youare not the intended recipient of this e-mail, any dissemination, distribution, copying, oraction taken in relation to the contents of and attachments to this e-mail is contrary to therights of INPO or WANO and is prohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete theoriginal and any copy or printout of this e-mail and any attachments.Thank you.

I4 R/B Spent Fuel Pool Reinforcement Plan (draf)

I F4R/B 'JS ItL )

\L.4

a I

(~) *1 ~

71914J

allvt.winisI

Wittick, Brian

From:Sent:To:


Gard, Lee A (INPO) [[email protected]]Wednesday, April 27, 2011 5:54 AMHuffert, Anthony; Moore, Carl; Casto, Chuck; Gepford, Heather; Mitman, Jeffrey; Hay,Michael; Salay. Michael; Meiqhan Sean; Garchow, Steve; Reynolds, Steven; Foster, Dirk LCAPT USN; (b)(6) ittick, Brian; Gregg Schneider; Lovell, Russ; Hochevar,Albert R. (INW); Uau•uO Na amura; Gard, Lee A (INPO); Hiroyuki Matsuura; Junji Tanaka;[email protected]; Keith Moser; Michio Matsuda; Richard Rossi; Bob Holland;[email protected]; [email protected]; Shigeo Hattori; Shinya Fujii; ShujiFuruya; Yoneo Suzumegano; Tom StevensFW: April 27 briefing notes and excel spreadsheetTEPCO Sumarry Rev.101 Final April 27.xls; April 27 Ryan 6 pm briefing notes.doc

Attached are the briefing notes and parameter spread sheet. The radiation survey map was not availabletoday.

.DISCLAIMER:This e-mail and any of its attachments may contain proprietary INPO or WANO information that is privileged,confidential, or protected by copyright belonging to INPO or WANO. This e-mail is intended solely for the useof the individual or entity for which it is intended. If you are not the intended recipient of this e-mail, anydissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mailis contrary to the rights of INPO or WANO and is prohibited. If you are not the intended recipient of this e-mail,please notify the sender immediately by return e-mail and permanently delete the original and any copy orprintout of this e-mail and any attachments.Thank you.

eplll"ý1

Not for Release


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FUKUSHIMA DAIICHI




* Ensuring fresh water injection and cooling capabilities to the reactorsand spent fuel pools. Goal is to reduce and maintain temperature inthe reactors and spent fuel pools below 100 degrees centigrade.




* Percent of fuel damage estimates has been revised for all three reactorcores. Current estimates are 55 % damage of Unit 1 fuel, 35 % of Unit2 fuel and 30 % damage of Unit 3 fuel. A calculation error contributedto inaccuracies in the previous estimates of 70 %, 30 %, and 25 %respectively.

" N2 purging of the Unit 1 Dryweil continues. It is now believed thatDrywell water level is .5 m below the bottom of the reactor vessel.TEPCO increased injection flow to the primary containment vessel to10 m3/hr Wednesday morning. After verifying leak tightness injectionflow will be increased to 14 m3/hr later today.

* The robot will entered the Unit 1 reactor building on Thursday to checkfor possible leakage following the increase in vessel injection rate.

" Transfer of highly radioactive water from Unit 2 to the CentralizedRadioactive Waste Treatment Facility continues at a rate of 250tons/day. Level in the Radioactive Waste Facility has risen 946 mmsince the start of transfer.

* Unit 2 trench level has not changed since late Monday. Unit 3 trenchlevel has increased an additional 10 mm and is now 970 mm from thetop.

" After increasing 50 mm yesterday, Unit 4 turbine building water levelremained steady at 3050 mm (1.15 m above floor level). Unit 3 turbinebuilding water level also remained steady at 3000 mm.

* One hundred thirty tons of water was added to the Unit 4 Spent FuelPool (SFP) yesterday. Another 70 ton addition is scheduled for today.Forty seven tons of water was added to the Unit 3 SFP yesterday.The fuel pool cooling line is now being used for injection into the Unit 3SFP and the elephant has been moved to Unit 1.

* Based on recent differences between observed water level increaseand calculated water level increase following water additions to the Unit4 SFP, TEPCO now believes the Unit 4 SFP pool may be leaking.

I

Previously it was reported that observed water level increase followingwater addition was as expected.

Although TEPCO considers that the Unit 4 reactor building structuralintegrity is sufficient to support the SFP, plans have been developed toadd supports in the compartments under the Unit 4 SFP. Constructionis expected to start in May and completed in July.

Unit Status

• In Unit 1, non-borated fresh water injection into the main feedwater linewill be increased in steps up to 14 m3/hr today until at least tomorrowmorning. Comments on parameters:

- Reactor pressure indicator A is steady at .450 MPa abs (65 psig).Indicator B continues to be suspect.


- Reactor vessel lower temperature is steady at 111 C (232 F)

- Drywell and Torus pressure remained at .150 MPa abs (22 psia).


* In Unit 2, injection of non-borated fresh water using the low pressurecoolant injection continues at approximately 7 m3/hr. Comments onparameters:


- Feedwater nozzle temperature decreased slightly to 120 C(248 F)



- Dose rate in the U2 Drywell continues to decrease. The drywelldose rate is 2.27Sv/hr or (2,270 Rem/hr). The Torus dose ratereading is considered suspect.

* In Unit 3, of non-borated fresh water using the low pressure coolantinjection continues at 6.9 m3/hr. Comments on parameters:






2

Dose and Dose Rates

" A female employee received a cumulative radiation dose of 18 mSvduring the first quarter of 2011. This exceeds the maximum, allowabledose for a female of 5 mSv/3 months. Quarterly dose for all 19 femaleemployees of the station is under review.

" Overall site dose rates are stabilizing or decreasing slightly. Forexample:

> The last reading reported at the main gate was 51 pSv /hr (5.1mrem/hour) and be 23 pSv /hr (2.3 mrem/hour) at the west gate.

> The side of the administration building facing the unitsdecreased slightly to .440 pSv/hr or 44 mrem/hr. The same asyesterday.

3

I .

Valentine, Nicholee


Philpott, StephenThursday, April 28, 2011 9:15 AMValentine, NicholeeFW: Mark 1 Containment Issues (Q372)Report-BWRMarklContainment_03212011 .pdf; 0372 Request.pdf

Hi Nikki,

This is a response I received from GE related to the other chain of e-mails I sent you yesterday in response toFOIA 2011-0189. The attached report is not marked as Proprietary, so I imagine it's OK to release. Plus Ihave another e-mail that indicates this report was available on GE's website, so I think it has been availablefor a while (and it's a bit dated now).

Steve

From: Hren, Jeff (GE Power & Water) [mi (b)(6)Sent: Monday, April 04, 2011 11:13 PMTo: Philpott, StephenCc: Harrison, James F. (GE Power & Water); GE Hitachi Nuclear Response Team (GE Power & Water)Subject: Mark 1 Containment Issues (Q372)

Mr. Philpott,

It has been several days since you have issued your request. I am sending you a white paper that we prepared hoping itwill satisfy your curiosity. Please reply with specifics if you desire more information.

Thanks,Jeff

Jeff A. HrenTechnical Project ManagerGE Hitachi Nuclear Energy

k!T 910 819 4729MI (b)(6)F 910 362 4729

El (b)(6)

3901 Castle Hayne Road, M/C F-12P.O. Box 780Wilmington, NC 28402, USA

$ (,// 7" ý'1

Mark I Containment Report

March 19, 2011

Revision 1

I

PURPOSE

This paper describes the Mark I containment design in use in the 23 U.S. reactors and its abilityto fulfill its safety function in containing fission product releases under design basis conditions.It also offers, as an initial matter, some observations about the performance of the Mark Icontainment under many beyond-design-basis events experienced at Fukushima Daiichi inMarch 2011.

PERFORMANCE OF MARK I CONTAINMENTS AT FUKUSHIMA DAIICHI

Fukushima Daiichi Units 1-4 are boiling water reactors ("BWRs") equipped with Mark Icontainments. Units 1-3 were operating; Unit 4 was in shutdown with fuel offloaded when theearthquake and tsunami occurred, which resulted in the loss all offsite and on-site power to allfour units.

Early reports regarding Units 1-3 stated plant operators used safety relief valves to relievepressure in the reactor pressure vessel. In addition, when the fuel rods became uncovered,hydrogen formed in the core (due to zirconium/water reaction) and was also transported into thewetwell when the reactor vessel safety relief valves opened. The combination of steam andhydrogen flowing into the wetwell increased the wetwell temperature and pressure. Since therewas no on-site or off-site power available, there was no means available to cool the wetwellwater. Over time, the pressure in the primary containment rose over the design pressure. Toavoid containment breach, venting became necessary. Upon venting, it is believed that ventedhydrogen gas caused explosions at these units.

The following should be noted:

Coincident long-term loss of both on-site and off-site power for an extended period of timeis a beyond-design-basis event for the primary containment on any operating nuclearpower plant.The Mark I containment vessels appeared to have held pressure to well above the designpressure.The response of the reactor pressure vessel and reactor in general agree with severeaccident management studies performed in the 1980s and early 1990s.

BACKGROUND

Description of the Mark I Containment System

Figure 1 shows a cutaway view of a typical Mark I Containment system. The major componentsshown in the figure include:

The drywell, which surrounds the reactor pressure vessel (RPV) and recirculation loops.The drywell is light-bulb shaped steel-lined pressure vessel backed over most of its surfacewith reinforced concrete.

2 Revision 1

" A wetwell is situated beneath the drywell and connected to the drywell by a system of ventpipes. The wetwell is a toroidal-shaped (donut shaped) pressure vessel which is filled toabout half of its height with water. The wetwell is often referred to as a torus (donut shape)or as a suppression pool (due to its function) and is made from either steel or concrete.

" An interconnecting vent network exists between the drywell and the wetwell. The vents areopen on one end to the drywell and on the other end open into a header in the wetwell thathas additional downcomer vents below the water level in the suppression pool.

The drywell, wetwell and vent system form the primary containment around the reactor pressurevessel and recirculation loops. The function of the containment system is to contain the energyreleased during a postulated design-basis loss-of-coolant accident of any size reactor coolant pipeand to protect the reactor from external events. The design-basis break is the largest reactorrecirculation system pipe. The primary containment system is designed to withstand thecombined seismic, pressure and temperature loads for this event and maintain integrity. Thecontainment system accommodates this accident without exceeding the design leakage rate; inthis way, the containment system limits the release of fission products during that event to offsitedose to levels significantly below the guideline values specified by regulation (10 CFR 100).

The primary containment is one of the three main barriers limiting release of fission productsfrom the BWR nuclear fuel into the environment. Other barriers include the fuel rod claddingand the reactor pressure vessel together with its piping, which form the reactor coolant pressureboundary and the primary containment. In addition to the three fission product barriers, thesecondary containment surrounds the primary containment and houses emergency core coolingsystems and the spent fuel pool.

Note: Secondary Containment may vary from site to site

3 Revision 1

Secondary Containment

Dryweil -- ,

Figure 1 - Typical Mark I Containment System

1% wetwell

4 Revision 1

CONTAINMENT OPERATION DURING A Loss OF COOLANT ACCIDENT

During normal operation, the drywell atmosphere and the wetwell atmosphere is inerted (filledwith nitrogen), and the wetwell water is at ambient temperature. In the event of a pipe break inthe reactor coolant systeminside the drywell, pressurized coolant escaping from inside thereactor coolant system will flash to steam and begin to pressurize and heat the drywellatmosphere. The reactor is automatically shut down. As the pressure rises in the drywell, the ventsystem will also pressurize, eventually forcing the steam into the wetwell below the water level.The steam contacting the water condenses in the wetwell. This reduces (suppresses) the pressurein primary containment following the loss of coolant accident by turning steam back into water.

Steam condensing in the wetwell gradually increases the wetwell temperature and pressure. Asthe accident progresses, plant instrumentation will sense the change in conditions in containmentand in the reactor coolant system, and emergency systems will activate to cool the shut downreactor. Systems will also be activated to cool the water in the wetwell. These active emergencysystems can be powered by off-site power or by on-site emergency diesel generators in the eventof a loss of off-site power. With these emergency systems available, the Mark I containmentsystem is designed to contain reactor water (and any fission products if present) without releaseduring a range of pipe break scenarios, up to and including a full guillotine rupture of the largestpipe connected to the reactor vessel, such that the primary containment pressure does not exceedits design value (50 to 60 PSIG at expected accident temperature). This prevents discharge of anyreleased water (and fission products if present) during the loss of coolant accident from escapingcontainment into the atmosphere.

Use of a wetwell for pressure suppression in primary containment is a feature of the GeneralElectric BWR design.

DESIGN BASIS

Appendix A to 10 CFR 50 lists current general design criteria for nuclear power plants. FourGeneral Design Criteria-2, 16, 50, and 51-are used for any reactor vendor containmentdesign. Each of the criteria are provided below:

Criterion 2 - Design bases for protection against natural phenomena. Structures, systemsand components important to safety shall be designed to withstand the effects of naturalphenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami and seicheswithout loss of capability to perform their safety functions. The design bases for thesestructures, systems; and components shall reflect: (1) Appropriate consideration of themost severe of the natural phenomena that have been historically reported for the site andsurrounding area, with sufficient margin for the limited accuracy, quantity, and period oftime in which the historical data have been accumulated, (2) appropriate combinations ofthe effects of normal and accident conditions with the effects of the natural phenomenaand (3) the importance of the safety functions to be performed.

Criterion 3 - Reactor containment and associated systems shall be provided to establishan essentially leak-tight barrier against the uncontrolled release of radioactivity to the

5 Revision I

environment and to assure that the containment design conditions important to safety arenot exceeded for as long as postulated accident conditions require.

Criterion 50 - Containment design basis. The reactor containment structure, includingaccess openings, penetrations, and the containment heat removal system shall bedesigned so that the containment structure and its internal compartments canaccommodate, without exceeding the design leakage rate and with sufficient margin, thecalculated pressure and temperature conditions resulting from any loss-of-coolantaccident. This margin shall reflect consideration of(l) the effects of potential energysources which have not been included in the determination of the peak conditions, suchas energy in steam generators and as required by § 50.44 energy from metal-water andother chemical reactions that may result from degradation but not total failure ofemergency core cooling functioning, (2) the limited experience and experimental dataavailable for defining accident phenomena and containment responses, and (3) theconservatism of the calculational model and input parameters.

Criterion 51 - Fracture prevention of containment pressure boundary. The reactorcontainment boundary shall be designed with sufficient margin to assure that underoperating, maintenance, testing, and postulated accident conditions (1) its ferriticmaterials behave in a nonbrittle manner and (2) the probability of rapidly propagatingfracture is minimized. The design shall reflect consideration of service temperatures andother conditions of the containment boundary material during operation, maintenance,testing, and postulated accident conditions, and the uncertainties in determining (1)material properties, (2) residual, steady state, and transient stresses, and (3) size of flaws.

The Mark I containment system has undergone extensive testing and analysis and in some caseshas been modified to ensure that these criterion are satisfied, as described in the followingsections.

ORIGINAL DESIGN OF THE MARK I CONTAINMENT

The original design of the Mark I containment system considered postulated accident loadsassociated with containment design. These included pressure and temperature loads associatedwith a loss-of-coolant accident (LOCA), seismic loads, dead loads, jet-impingement loads, andhydrostatic loads due to water in the suppression chamber.

The original design loads for the containment were based on large-scale tests performed by GEand other institutions. The purpose of these initial tests, performed from 1958 through 1962, wasto demonstrate the viability of the pressure-suppression concept for reactor containment design.The tests were designed to simulate LOCAs with breaks in piping sized up to approximatelytwice the cross-sectional break area of the design-basis LOCA.

The tests were instrumented to obtain quantitative information associated with containmentdesign pressures during these events. The data from these tests were the bases for the design andthe initial NRC approval of the Mark I containment system.

6 Revision 1

EVOLUTION OF THE DESIGN

After the establishment of the original design criteria, additional loading conditions wereidentified which arise in the functioning of the pressure-suppression concept used in the Mark Icontainment system design. These conditions were noted in the course of performing large-scaletesting of an advanced design pressure-suppression containment (Mark III). Specifically, duringthe large-scale testing of the Mark III containment system design in the period 1972 through1974, new suppression pool hydrodynamic loads were identified for the postulated LOCAs. GEtested the Mark III containment concept in its Pressure Suppression Test Facility (PSTF). Thesetests were initiated for the Mark III concept because of configuration differences between theprevious containment concept and the Mark III design. More sophisticated instrumentation wasavailable for the Mark III tests, as were computerized methods for data analysis. It was from thePSTF testing that the short-term dynamic effects of drywell air being forced into the pool in theinitial stage of the postulated LOCA were first identified. This air injection into the suppressionpool water results in a pool swell event of short duration. In this event, a slug of water rises andimpacts the underside of structural components within the suppression chamber.

In addition to the information obtained from the PSTF data, other LOCA-related dynamic loadinformation were obtained from foreign testing programs for similar pressure-suppressioncontainments. In these foreign tests, oscillatory condensation loads which occur during the laterstages of a postulated LOCA were identified.

Also, experience at operating plants indicated that Safety Relief Valve (SRV) discharges to thesuppression pool would cause oscillatory hydrodynamic loads within the suppression chamber.Both the LOCA and SRV discharge are characterized by an initial short period injection of airinto the suppression pool, followed by a longer period of steam discharge into the suppressionpool.

Further, during in-plant testing of Mark I containments, new suppression pool hydrodynamicloads which had not explicitly been included in the original Mark I containment design basiswere identified. These additional loads result from dynamic effects of drywell air and steambeing rapidly forced into the suppression pool (torus) during a postulated LOCA and fromsuppression pool response to safety relief valve (SRV) operation generally associated with planttransient conditions.

These hydrodynamic loads had not been considered in the original design of the Mark Icontainment, the NRC required that a detailed reevaluation of the Mark I containment system bemade.

In February and April 1975, the NRC transmitted letters to all U.S. utilities owning BWRfacilities with the Mark I containment system design, requesting that the owners quantify thehydrodynamic loads and assess the effect of these loads on the containment structure. TheFebruary 1975 letters reflected NRC concerns about the dynamic loads from SRV discharges,while the April 1975 letters indicated the need to evaluate the containment response to the newlyidentified dynamic loads associated with a postulated design basis LOCA.

7 Revision I

As a result of these letters from the NRC, and recognizing that the additional evaluation effortwould be very similar for all Mark I BWR plants, the affected utilities formed a Mark I OwnersGroup, and GE was designated as the Group's lead technical organization. The objectives of thegroup were to determine the magnitude and significance of these dynamic loads as quickly aspossible and to identify courses of action needed to resolve any outstanding safety concerns. TheMark I Owners Group divided this task into two programs: A Short-Term Program and a Long-Term Program.

The objectives of the Short-Term Program (STP) were to verify that each Mark I containmentsystem original configuration would maintain its integrity and functional capability whensubjected to the most probable loads induced by a postulated design basis LOCA, and to verifythat the licensed Mark I BWR facilities could continue to operate safely without endangering thehealth and safety of the public while a methodical, comprehensive Long-Term Program (LTP)was being conducted.

The STP structural acceptance criteria used to evaluate the design of the torus and relatedstructures were based on providing adequate margins of safety; i.e., a safety-to-failure factor of2, for continued operation of the plant's original configuration before the more detailed results ofthe LTP were available.

The NRC concluded that a sufficient margin of safety had been demonstrated in the STP toensure the functional performance of the containment system and, therefore, any undue risk tothe health and safety of the public was precluded. These conclusions were documented in the"Mark I Containment Short-Term Program Safety Evaluation Report," NUREG-0408, datedDecember 1977. The NRC granted the operating Mark I facilities an exemption relating to thestructural factor of safety requirements of 10 CFR 50.55(a) for an interim period while the morecomprehensive LTP was being conducted.

The objectives of the LTP were to establish conservative design basis loads that are appropriatefor the anticipated life of each Mark I BWR facility, and to restore the originally intended designsafety margins for each Mark I containment system. The plans for the LTP and the progress andresults of the program were reviewed with the NRC throughout the performance of the program.

The LTP consisted of:

" The definition of loads for suppression pool hydrodynamic events" The definition of structural assessment techniques* The performance of a plant-unique analysis (PUA) for each Mark I facility in the U.S.

The generic aspects of the Mark I Owners Group effort were completed with the submittal of the"Mark I Containment Program Load Definition Report" (LDR) and the "Mark I ContainmentProgram Structural Acceptance Criteria, Plant Unique Analysis Application Guide" (PUAAG).The NRC concluded that load definitions and structural acceptance criteria documented in thesetwo reports were acceptable for use in the plant-unique analysis of each plant. The NRCconclusions and comments were presented in the "Mark I Containment Long-Term Program

8 Revision 1

Safety Evaluation Report, NUREG-0661," dated July 1980 and Supplement Number I toNUREG-0661.

GE provided reports to each Mark I BWR facility with plant unique LOCA hydrodynamic loads.GE also prepared and provided a supplementary generic load definition report and supportingapplication guides which provided the load definition procedures for the postulated LOCA andSRV actuation events for use in the structural re-evaluation of the pressure suppression chamber,vent system, SRV discharge piping, and other Mark I containment components.

The NRC reviewed the generic criteria and analysis techniques developed for the LTP for re-assessment of the Mark I containment. The NRC provided an acceptance criteria for applicationof the LTP loads assessment process in US NRC NUREG-0661, "Safety Evaluation Report,Mark I Containment Long-Term Program," July 1980 and NUREG-0661, Supplement 1, issuedAugust 1982 (Refer to Attachment 4 for additional information regarding NUREG-0661)

Each BWR Mark I plant performed a plant-unique re-assessment of the Mark I containment,applying the load definition process developed by the LTP and implementing the NRCacceptance criteria ofNUREG-0661. The objective of this reassessment was to eitherdemonstrate that the existing plant design has the required safety margin or to identify anyadditional plant modifications that were necessary to restore the intended margins of safety in thecontainment design. The reports included, as appropriate, documentation of evaluationperformed for modifications to the original design (the plant-unique assessments led to structuralmodifications to the torus and vent system at most US BWR's with Mark I containments toensure compliance with the applicable criteria). The plant-unique analyses documented theefforts to address each of the applicable NUREG-0661 requirements and demonstrated with theNUREG-0661 acceptance criteria that the design of the containment is adequate and that theoriginal design safety margins are either confirmed with the original design or restored with themodifications. Each Mark I BWR facility submitted its plant-unique analysis report to the NRCfor approval, since each plant has an individual license with the NRC.

CONTAINMENT OPERATION DURING A STATION BLACKOUT

In the late 1980s and early 1990s, BWR operators made procedure changes and modifications tocope with events which involved the loss of the normal offsite power and normally availableemergency diesel generators as discussed in NRC Regulatory Guide 1.155 (Station Blackout).

To support safe operation in a variety of circumstances, the plants have been designed and havedeveloped procedures to address a wide range of potential events. The Emergency OperatingProcedures provide instructions for maintaining adequate core cooling and protection of thereactor vessel and containment under a variety of prescribed emergency conditions. If adequatecore cooling cannot be maintained, radiological emergency response procedures provideinstructions for plant staff to take actions to mitigate the consequences of an event that could leadto radioactive material release to the public and provides for making recommendations to stateand local agencies to take action to protect the health of the public such as evacuation orsheltering. The industry has also implemented Severe Accident Management Guidelines(SAMG) to diagnose and mitigate severe accidents. These operating guidelines include steps for

9 Revision 1

dealing with challenges to containment integrity and reactor coolant loss beyond the originalplant design basis. This includes methodology to use auxiliary equipment that is not driven bynormal plant power sources to provide makeup water to the reactor vessel/containment. Theseguidelines interface with Emergency Operating Procedures to mitigate a loss of large areas of theplant and with state and local radiological emergency response procedures.

As a result of the September 11, 2001 terrorist attacks, additional actions and equipment wereput in place at certain U.S. plants to allow water makeup to the reactor and the fuel pools shouldsignificant damage occur to the reactor buildings. These changes include pre-staged diesel-drivenpumps, piping, and procedures that would support water makeup from various water supplieswithout the need for electrical power.

Also, as a result of the Industry Degraded Core Rulemaking (IDCOR) and NRC programs forSevere Accident Closure, recommended that all Mark I U.S. nuclear power plants add acontainment venting capability. This containment vent was designed as a hard pipe that woulddischarge from the containment in the case of a BWR from the wetwell or drywell, and dischargeto an elevated release, such as the plant stack. All U.S. Mark I nuclear reactors have installed thiscontainment venting modification.

In summary, this vent allows operators to protect the integrity of the primary containment as wellas preventing a ground-level release for the severe accident scenarios beyond the design andlicensing basis (Refer to Attachment 5 for additional modification information specific to BWRMark I containment).

CONCLUSION

The Mark I containments in currently operating BWRs have been designed to meet the specificprovisions of 10 CFR 50 Appendix A, General Design Criteria 2, 16, 50 and 51 for containmentdesign or the applicable equivalent regulation at the time of licensing.

The GE Mark I containment systems in U.S. BWRs have undergone extensive testing andanalysis and have been modified to meet NRC regulations. The Mark I pressure suppressioncontainment is a proven technology that has been enhanced with confirmatory testing, enhancedknowledge and advanced analysis over time. It meets all regulations and has been certified byreview of the NRC through a Safety Evaluation Report (SER) at each Mark I plant undercomprehensive, NRC-mandated Mark I Containment Program re-analyses performed to addressthe evolving design loading conditions.

The Mark I containment also has many features inherent in its design that make the probabilityof a severe accident extremely low. They have been modified throughout their operation toprovide additional features and response capabilities to further reduce this probability.

Also, to ensure containment integrity, the drywell or primary containment, as called, is tested atestablished intervals (every 10 to 15 years) in accordance with 10 CFR 50 Appendix J Program(Primary Reactor Containment Leakage Testing). This test is used to demonstrate containmentintegrity and to demonstrate it will perform its safety function by verifying that leakage through

10 Revision I

the containment, and systems and components penetrating the primary.containment, shall notexceed established limits. The containment and associated systems and components penetratingcontainment are designed to provide the final barrier in preventing the release of quantities ofradioactive material that would have a significant radiological effect on the health of the public.This program also uses periodic surveillance testing to demonstrate the leak tightness.

Additional procedures, hardware and resources have been planned and prepared for the beyond-design-basis scenarios to assure protection of the safety and health of the public. In addition, 10CFR 50, Appendix B, also assures that any conditions adverse to quality be identified andresolved. It requires assuring that the cause of the condition is determined and corrective actionstaken to preclude repetition.

I1I Revision I

Attachments

12 Revision 1

ATTACHMENT 1Page 1 of 1

U.S. Nuclear Plants WithMark I Containment

Reactor NameBrowns Ferry 1

Browns Ferry 2

Browns Ferry 3

Brunswick 1

Brunswick 2

Cooper

Dresden 2

Dresden 3

Duane Arnold

Edwin I. Hatch 1

Edwin I. Hatch 2

Fermi 2

Hope Creek 1

James A. Fitzpatrick

MonticelloNine Mile Point 1

Oyster Creek 1Peach Bottom 2

Peach Bottom 3Pilgrim 1

Quad Cities 1

Quad Cities 2

Vermont Yankee 1

StateAlabamaAlabamaAlabamaNorth CarolinaNorth CarolinaNebraskaIllinoisIllinoisIowaGeorgiaGeorgiaMichiganNew JerseyNew YorkMinnesotaNew YorkNew JerseyPennsylvaniaPennsylvaniaMassachusettsIllinoisIllinoisVermont

13 Revision 1


Analyzed Loading ConditionsFor Mark I Containments

Hydrodynamic Loads evaluated a spectrum of postulated pipe breaks to determine the worstloading condition for each structural element. For the long-term program, an intermediate liquidbreak accident (IBA) and a small steam break accident (SBA) were specified in addition to theDesign Basis Accident DBA. All LOCA and seismic loads are added together as appropriate forthe load combination scenario. Not all of the suppression pool hydrodynamic loads can occur atthe same time. In addition, the load magnitudes and timing will vary, depending on the accidentscenario under consideration. Therefore, combinations of loading conditions have beendetermined from typical plant primary system and containment response analyses, withconsiderations for automatic actuation, manual actuation, and single active failures of the varioussystems in each event. The typical new loads analyzed were:

Pressure and temperature time histories for the suppression chamber wetwell and drywell

Vent system pressurization and thrust loads

Net vertical pool swell loads and average submerged pressures on the suppressionchamber

Pool swell impact and drag loads on the vent system

Pool swell froth impingement loads

Pool fallback loads

Vent header deflector loads

Condensation oscillation loads and chugging loads

Fluid structure interaction

Safety-relief valve discharge loads

Submerged structure drag loads

Secondary effects loads

Seismic slosh/loads, which occurs due to horizontal seismic motion on the pool

Post-pool-swell waves/loads, due to the wave action associated with continued flowthrough the downcomers

Asymmetric vent system flow, resulting from asymmetric flowrates due to vent blockage

Downcomer gas-clearing loads, resulting from the rapid clearing of gas from the vent

system causing lateral loads as bubbles are being formed in the pool

Sonic and compression wave loads, due to the shock wave propagating from the breaklocation

Safety-relief valve steam discharge loads

14 Revision I

ATTACHIMENT 2Page 2 of 2

Original loads included pressure and temperature loads associated with a LOCA, seismic loads,dead weight loads, jet impingement loads, hydrostatic loads due to water in the suppressionchamber, overload pressure test loads, and construction loads.

The generic aspects of the Mark I Owners Group LTP were completed with the submittal of theMark I Containment Program Load Definition Report (LDR), and the Mark I ContainmentProgram Structural Acceptance Guide (PUAAG), as well as supporting reports on the LTPexperimental and analytical tasks. The generic analysis techniques were used to perform a plantunique analysis to confirm the adequacy of the modifications made to the containment structuresand related piping. This analysis was documented in the Plant Unique Analysis Report (PUAR),which shows that the original margins of safety in the containment design have been restored.

15 Revision 1


Recommended ModificationsFor Mark I Containments

The Mark I containment was originally designed based on large-scale experimental tests in 1958through 1962. More advanced large-scale tests in 1972 through 1974 and actual plant operationsidentified some new phenomena and issues needing resolution. The Mark I containment programbegan in 1975 when NRC sent letters to Mark I owners requiring Reevaluation of ContainmentResponse to Hydrodynamic Loads. The BWR Owners Group embarked on a program to resolvethe issues. The issues were highly scrutinized and reviewed for plant-specific applicability onoperations and structural capability. In summary, dynamic effects of drywell air and steam beingrapidly forced into the suppression pool (torus) during a postulated LOCA and from suppressionpool response to SRV operation generally associated with plant transient operating conditionswere addressed for:

* Loss-of-Coolant-Accident-Related Hydrodynamic Loads including Pool SwellPhenomena

* Loss-of-Coolant-Accident Steam Condensation Phenomena* Safety-Relief Valve Discharge-Related Hydrodynamic Loads

The new experimental data and new analytical models extensively studied the issues. Immediateoperability of the existing structures was demonstrated for the short-term then more robuststructural improvements were implemented. Operational changes and strengthened structuralsupports at specific locations were implemented to meet ASME and other industry acceptancecriteria. A typical list of hardware changes made:

o Torus: Additional ring girder reinforcement, Miter joint support saddles and saddleextension plates, Additional ring-girder-to-torus weld, Torus Temperature monitoringinstrumentation, Torus tie-downs, Dynamic restraint snubbers

o Vent System: Downcomer/vent header stiffeners, Downcomer lateral bracingDowncomer longitudinal bracing, Vent header deflector, Vent line drain reinforcement,Torus-to-drywell vacuum breakers, and Vacuum breaker header support

o Internal Structures: Catwalk midbay supports, Catwalk lateral bracing, Catwalk supportsat ring girders, Conduit rerouted

o Wetwell Piping Modifications (Internal): Spray header supports, HPCI turbine drain potsupport, HPCI turbine exhaust line support, ECCS suction strainer reinforcement, LPCIfull-flow test line supports, modify external supports

o Relief Valve Discharge Line Piping: Reinforced vent line penetration, Added T-quenchers, Added T-quencher supports, Added SRV line support, SRVDL vacuumbreaker

16 Revision 1


o Torus Hardened Vent

o Torus Vacuum Breaker orientation changes

o SRV operating - recommendations to minimize loading, discharge piping pressureswitch, instrumentation to allow SRV position monitoring

17 Revision I


NUREG - 0661 ABSTRACT July 1980

"This Safety Evaluation Report prepared by the staff of the Office of Nuclear Reactor Regulationdiscusses suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities withthe Mark I pressure-suppression containment design. The report finishes the NRC's GenericTechnical Activity A-7 (Mark I Containment Long-Term Program), which has been designatedan "Unresolved Safety Issue." The report describes the generic techniques fo r the definition ofsuppression pool hydrodynamic loads in a Mark I system and the related structural acceptancecriteria.

On the basis of a review of the experimental and analytical programs conducted by the Mark IOwners Group, the staff has concluded that, with one exception, the proposed suppression poolhydrodynamic load definition procedures (as modified by the staff' s requirements in AppendixA of this report) will provide conservative estimates of these loading conditions. The exceptionis the lack of an acceptable specification for the downcomer "condensation oscillation" loads. In

addition, requirements for confirmatory analyses and testing have been identified. The resolutiono f these issues will be described in a supplement to this report.

The staff also has concluded that the proposed structural acceptance criteria are consistent withthe requirements of the applicable codes and standards. In conjunction with the general structuralanalysis techniques, these criteria will provide an acceptable basis for establishing the margins of safety in the Mark I containment design."

NUREG-0661 SUPPLEMENT 1 ABSTRACT August 1982

"When the NRC staff published "Safety Evaluation Report, Mark I Containment Long-TermProgram" (NUREG-0661) .in July 1980 four areas were identified where the technical issues hadnot been fully resolved. These were:

1. Specification for condensation oscillation loads acting on the down comers2. Adequacy o f the data base for specifying torus wall pressures during condensation

oscillations,3. Possibility of asymmetric torus loading during condensation oscillations, and4. Effect of fluid compressibility in the vent system on pool swell loads.

The first item, downcomer condensation oscillation loads, lacked an acceptable load definition.The remaining three items had acceptable specifications; however, the NRC requested additionalconfirmatory information to justify the adequacy of the load specifications.

This supplement addresses the resolution of the four issues listed above. In response to NRC

concerns expressed in NUREG-066 1, the Mark I Owners Group conducted additionalexperimental and analytical studies. The experimental studies consisted basically of twoadditional condensation oscillation tests in the Full-Test Facility (Norco, California). The staff

has reviewed these efforts and has concluded that all technical issues connected with the genericMark I Long-Term Program have been resolved."

18 Revision I


Summary:

NUREG 661 Contains a safety evaluation of loading determination methods and acceptancecriteria for the evaluations that resulted in the modifications made as part of the Long TermProgram.

NUREG 661 Supplement 1 contains a safety evaluation of the four unresolved issues describedin NUREG 0661.

19 Revision I


Summary of Critical Modifications

The following modifications are the more significant examples of improvements to the Mark Icontainment design as enhancements to design margins or increased capability to address"beyond design basis conditions."

Hardened Vent

In the 1980s, the NRC staff reviewed the potential for accidents more severe than those theplants were licensed and designed to mitigate. In order to enhance the ability of all containmentsto prevent and mitigate the consequences of severe accidents beyond the design basis accidents,the NRC requested that all plants install a hardened vent. In the event of a core damage accident,the hardened vent would allow reduction in containment post-accident pressure. Hardened meantthat the vent would transport hydrogen, steam and other accident products and release themoutside the reactor building. This would preclude damage to the reactor building and equipmentfrom steam and the possible hydrogen explosions.

In response to the GL 89-16 and the results of their Individual Plant Examinations (IPEs), all ofthe nuclear power plants installed a hardened vent. This hardened vent capability would allowBWR plant operators to vent post-accident airborne materials by passing them through the waterin the wetwell, thereby removing a large amount of the radioactive material contained in the ventstream before venting. This added capability increases the ability of the Mark I containment tomitigate the consequences of design-basis and beyond-design-basis accidents.

SRV Modifications

Mark I containments were designed for hydrostatic loads as part of the original design basis ofthe plants. During subsequent testing of the Mark III containment design, additionalhydrodynamic loads were identified. The industry established a Mark I Owners' Group anddeveloped test regimes to define the hydrodynamic loads and establish design criteria forevaluation of the Mark I containment.

The hydrodynamic loads are defined in Plant Unique Load Definition Reports and each Mark Icontainment was evaluated against its own report. As a result of this effort, Mark I plantsmodified their piping and/or pipe supports inside containment to reduce the loads an SRVdischarge would impose on the torus and to withstand post-LOCA loads on SRV dischargepiping. These modifications included pipe supports, discharge line vacuum breakers, "ramshead" discharge pipe fittings and T-quenchers. The modifications provide additional margin toensure that SRV actuation will not damage the wetwell pressure boundary, any of the wetwellinternal components or piping, and also ensure that the SRV piping will remain functional duringpostulated transients and accidents.

20 Revision 1


Torus Attached Piping

In addition to the SRV piping modifications discussed above, the plant-unique analysis identifiednew loads on torus attached piping (TAP). In order to ensure the structural integrity of the torusfor all postulated loads, all TAP was re-evaluated and either removed or modified as necessary.The piping was evaluated, and upgrades were made to torus attachments and pipe supports toensure that they would withstand all postulated loads with a significant factor of safety betweenthe design load and the actual load. These modifications ensure that the Mark I containment willcontinue to perform its safety function during plant transients and postulated accidents as well asimprove the capability to mitigate beyond-design-basis events.

ECCS Suction Strainers

NRC Bulletin 96-03 identified NRC concerns with the potential for debris plugging ofEmergency Core Cooling System (ECCS) suction strainers inside the containment wetwell.These concerns resulted from an event in Sweden and two events in the U. S. that indicated thepossibility that fibrous insulation material dislodged by a design-basis accident and particulatematerial suspended in the wetwell water could be entrained on strainer surfaces causing loss ofthe ECCS pumps. These pumps are used for normal reactor shutdown and to inject cooling waterinto the reactor following an accident that depressurizes it.

The plant owners employed the BWR Owners' Group (BWROG) and the Electric PowerResearch Institute (EPRI) to conduct testing to determine criteria for designing and, particularly,sizing the strainers to ensure ECCS pumps capability if needed. Each plant owner then designedand installed new larger strainers. These strainers provide additional assurance that ECCS pumpswill perform their intended function in the unlikely event of an accident.

21 Revision I

Meighan, Sean

From:Sent:To:


FYI,Al

Hochevar, Albert R. (INPO) [[email protected]]Thursday, April 28, 2011 5:44 AMHuffert, Anthony; Wittick, Brian; Moore, Carl; Chuck Casto; Norwood, Donald; Gepford,Heather; Mitman, Jeffrey; Salay, Michael; Hay, Michael; Meighan, Sean; Garchow, Steve;Reynolds, Steven; CAPT Dirk L Foster; Reid TanakaApril 28 briefing notes, excel spreadsheet and radiation survey mapApril 28 Ryan 6 pm briefing notes.doc; TEPCO Sumarry Rev.102 final April 28(1).xls;20110427 0850 Facility Area Survey Data[1].pdf

Al HochevarInstitute of Nuclear Power OperationsCel• (b)(6)

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale or forcommercial use. Reproduction of this report without the prior written consent of INPO is expressly prohibitedUnauthorized reproduction is a violation of applicable law. The persons and organizations that are furnishedcopies of this report should not deliver or transfer this report to any third party, or make this report or itscontents public, without the prior agreement of INPO. All other rights reserved

.DISCLAIMER:This e-ma'l and any of its attachments may contain proprietary INPO or WANO information that is privileged, confidential, or protected by copyright belonging toINPO or WANO. This e-mail is intended solely for the use of the individual or entity for which it is intended. If you are not the intended recipient of this e-mail, anydissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mail is contrary to the rights of INPO or WANO and isprohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete the original and anycopy or printout of this e-mail and any attachments.Thank you.

I .

FUKUSHIMA DAIICHI




• Ensuring fresh water injection and cooling capabilities to the reactorsand spent fuel pools. Goal is to reduce and maintain temperature inthe reactors and spent fuel pools below 100 degrees centigrade.

* Draining water from the turbine buildings and trenches to reduce theradiation levels so that work can continue.

* Containing the spread of radioactive materials.


* N2 purging of the Unit 1 Drywell continues. TEPCO increased injectionflow to the primary containment vessel to 10 m3/hr at approximately10:00 am Wednesday morning. Reactor vessel temperature, drywelltemperature and pressure were observed to decrease after the start ofthe injection increase. The rate of change of these parameters slowedthis morning. TEPCO intends to stop the increased injection ratebefore drywell pressure reaches atmospheric.

* The robot is scheduled to enter the Unit 1 reactor building today tocheck for possible leakage following the increase in vessel injectionrate.


" Unit 2 trench level has decreased only slightly since Monday and isnow 900 mm from the top of the trench. Unit 3 trench level hasincreased an additional 20 mm and is now 950 mm from the top.

" Unit 4 turbine building water level increased 50 mm and is at 3050 mm(1.2 m above floor level). Unit 3 turbine building water level remainedsteady at 3000 mm.

* Eighty five tons of water was added to the Unit 4 Spent Fuel Pool(SFP) yesterday. No addition to the Unit 4 SFP is scheduled for today.Sixty tons of water is scheduled to be added to Unit 2 SFP today.

" After reexamining the recent differences between observed water levelincrease and calculated water level increase following water additionsto the Unit 4 SFP, TEPCO now believes the Unit 4 SFP pool may notbe leaking. The condition of the Unit 4 SFP will continue to beevaluated closely by TEPCO.

" A water sample for radionuclide analysis is scheduled to be taken fromthe Unit 4 SFP today.

I

TEPCO released their plan for radioactive water treatment today.Ultimately it will have a capacity of 1,200 m3/day. A reservoir capacityof 31, 400 m3 will be installed by early June. Additional capacity will beadded later. Currently there is an accumulation of 87,500 m3 ofradioactive waste water at the station. Injection into the reactorpressure vessels is adding to this total daily.

Unit Status

" In Unit 1, non-borated fresh water injection into the main feedwater linewas increased in steps up to 10 m3/hr yesterday on a temporary basis.Future injection flow will be determined following analysis of dataobtained during the injection flow increase. Comments on parameters:

- Reactor pressure decreased to .415 MPa abs (60 psig).

- Feedwater nozzle temperature is considered to be suspect butdid show a decrease of approximately 25 C (77F).

- Reactor vessel lower decreased approximately 12 C to 98.5 C(209 F)

- Drywell and Torus pressure decreased to .125 MPa abs (18 psia).


" In Unit 2, injection of non-borated fresh water using the low pressurecoolant injection continues at approximately 7 m3/hr. Comments onparameters:


- Feedwater nozzle temperature was steady at 120 C(248 F)




* In Unit 3, of non-borated fresh water using the low pressure coolantinjection continues at approximately 6.8 m3/hr. Comments onparameters:



- Reactor vessel lower temperature was steady at 110 C (230 F)



2

Dose and Dose Rates

" As reported yesterday, a female employee received a cumulativeradiation dose of approximately 18 mSv during the first quarter of 2011.This exceeds the maximum allowable dose for a female of 5 mSv/3months. Upon examination it was determined that the woman received13.6 mSv internal exposure. The woman was working in a building thatwas contaminated by the hydrogen explosion on March 1 21h and wasnot wearing a protective mask. Two other females working in the samebuilding may have also exceeded their exposure limits.

* Overall site dose rates are stabilizing or decreasing slightly. Forexample:

> The last reading reported at the main gate was 48 pSv /hr (4.8mrem/hour) and 22 pSv /hr (2.2 mrem/hour) at the west gate.

>, The side of the administration building facing the unitsdecreased slightly to 430 pSv/hr or 43 mrem/hr.

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11 V 111111MK x4: cool 0LI10 wtoh gailO o-

ntllio*t)0

1111kiootry opltiotb io X so,6 of MI N biril VA- I

lb,, out of too qP:w? M1 smallUrpped I ?S April l84D1 -26 lptif

Will1

fl1011 $0011

... .... .. ......... .tlii 6 f .'+'Il I I I. I.

c oolest 40l

roolkTf .1

Ih4suto Oolo Lotil lo'Att 15i . 111

TAF-165f0 a (fool 10161; &koao 6)ITl -16M as U01 Rain: (41g. 81IVY Ow. Clonoooi lot 05:l011 a ul0.115 61fta I(cGw Q

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Irv lfw lat.IT0W0n4iI

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corotlottfo-0. OM ii'-g tros, 0 loolohiltg trotal

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trodcooot IYool bot itcoptlgo

loliutito proobloB.LD4Otb ff fP ! to6I

lIhct low fml lot 0., C-1 I, 1.

1;rill

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lItb 1147. 1c

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entire, coliditsl.

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lootorlig ofl-oslte ootr I tolatfd

v.Cimc f ocof011dto r

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. ig

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111103 (t Wo1 0:$ tal 0ol

* faserlime:81'. belle nil: hIRS8101 1.14b; UI t

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IDNI lot Will on 43fotWOPoioamp it 0 11rabs

11Sol Inell l; 1A =MillerAll oIoif: lIIIt

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(0 rmpronocr 2834 1h

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April)

!%po, missal, kroat 8l bo 4:021810 stil W0.0 rtoo ra forlopitalif 'weryr M1 foot 20

itoill)

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(it/il "r 4oor) irrisoo Fa vtsýwt Int W : 4.17 I I I

41L 0b

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- Fill 040 ci, tontltibonlo flre withhitroOis

* Itaifoorced oeoitoori of 040 piomo.ii Coetian to teulcourtoialonlia i,

(Aftl wis W00r1 Off-lit Powncloororitg P~v Sp0.1 00pit/eo

IL* qhfi ifoo 51300

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Iskimin roE " ookI'030 ( At W0.0OW n 5 totI)

Eloooro'iq bo ocoirrym pits odoirt(frtsh hinr-r

fIH r~she tEo -Sooo.05 Iooch 1101:3-111i31 lkot) WM14:60:0102b/ Ap i :8l00

The njkoaao of awrio,i oMie~rl~ forWo I 4I a cloroo lror 'lop Giraffe, to'44L,tot 10e nc ofl, rt a oIbIe 00 1.ri

Pfrepoa re i s:, fal~r 'al iatilt !l'le00110 mi.0

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-PAII Ipi) 5850)0

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Ils1h

M 'mrlati lf, otbrSoirElf? i t Oep tlill or tpl eltlso

leth of Ponr upoppy

'Al. 40011 11:06- 20.0 (0.

01pr5 02-19:15 (Fro.ltorofElooprolirs NYfotr 00:3 ot): with'lertrio

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L-A N f Mew[.11 -o miod; W20 fit M i

(on 11 Aprl)Dlyalor ospay .!I thEephan*t 1i

-10A1pr11I 14:18 -15:02 fifoal'0N fool F14:1 - 15:40 (BrO'l-20 April 10:20 - 12:0, Idoob of

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-!22 pill 01:43 - 04:2800:.lo)

3320ut Io n tol : knuorao1040 wet imr oo410 50040 or: of

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Ior Im1 Apill)

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is btrlsoo teo I r.odN40 Oohi..4 llu0000 1'05 1NZt 1r1 0 -00 les

ora tf6 fEoroost 12 nd oeorrlintispt stur.

5 3 CAd 21Aprill

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L11rair of the Elepant II Oral,., 4:0,1/O~ '1- o'' Itot)l

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Not for

IM PIC X COI' mtrdos local

mtwkit of tI.h FPtat 15:46 "o !D Itrch)

*lilogentst of SE i~tmd rot thinl circuitCAt troord but fn till an 21 Tellr

1120 I a C life boau PaIttle 04:40

Il IuuWWI Ito or ER mtrneo at 11:30tai ll ich

*Straitleir b-ll, pour-I!, Iire b~it o. 116it 12 un4l1o0011 Wass

fgoh.ho Stalvor ]i, - (Vias line has

Mtilablol (cotI9ffil)-Tie flor tto t~i% 1 i 0E usuob so

i1ma40lt.l(c 5Aa 1fi)

I a0 PiT XC oreelectd to loualIlistribtljo.

01101ib of T"bl 11C111 15:I4w in0 beoh

1111C !kI it the outibo bulldlj MIspourad .015:42,0 an this

II falotoloru Is ritstoad I min contrtol

.116:45 rOt 21 XboIftmoo~a wi lt@ perr

*tit firs brwog 11602l and 014100

intotllit (T Wlo l f li ne ir-

ba ai ou levif~lab ito 6194il)

Itm 60 April

LLPttatt Stais

3I0= PIC ID poured &Wrs LoatIC oltiCfire 6ao10:15 on IN1 Sooof

*.Ter;OMt PAT Fa~ll Maiwod91ilielo1f tie

waisolfcal pito of 6610 off-sits flrrOtanalssiall line

-Trl~l Ilacorfo baltg of fthe rtorCenter

oullol for Will6 mad fkitl alatoqlsoed

at 14:28 to 16 Marth*Ititalatliont aaof I 140411 bIVOpIa

aid OdFIS t cbfs art eq a M o TO bshSisspotlitio of cable, for mtlto ccaba

21 lbelfiiore DOWJy us stopped dix, to

,,zit m "a of hit 064 Iwo,:w MI0

1206 April l0:2)15:27k* ,1 13it~ 60i ll, 5 64 fly)

1600l Ec X-2 II ow benal poao ?,2lar4kIII6III MIX IN li beer aopo toi V6I. tooo1120411 C aais too petered mr V2 Vota

I M0 PIC 40 rooundi throo4

lrooo (At l o I~O ~ r

-Pour n49b5 ts s topped Je to

craoiom. p7 of hbit 664 Itpervto:

?5 .April l0:23-!rbf

MoItohla cf 21-4 Ay,1101120Y 11 C uniit oo P~sirde At 01:40

an 23 111r1tlilbooliaitito Of El trwmta It 11;50

ton 21ooathItTI. fine betiatv NMIo andl Urit24LIPfootAlIo q"o W etir linei'

Kata fir.his bra aoilebld for IfIrill

Ifasgcoirit poinopt MIT liordaoiliai.4 16

wardoLwmi poorit of000r ott-sltePITr

Irltsoftion fire, lfTW*l fir.2.60Efo-Weof var gr aofe Uoo SaidOv59 Ott

wtrif lableBingertry W~ l Im a id r lledadl

rrrtd u thbe witer aelfil I110,

oArimd m, 24th laitchMasta Perifiatllo failIlly mas

-16.1:10 M 24th larthElorritipiOn cable Imlire "Ai firsmtootrkir

171/ 1 AT -2 lois ias pruirif tovarch

ESrtion0 ht wr~ite peopo- im line to Uhi ILI Pio I., War

ioioalloaiUIxtill

Itro lry potr iwooy ohiradutilisinq

the, dool. pooL Of My of tsit,

posi+ I t•iri ire (flr-hiIri-lit.

"llasatt grad. lait of 6A Wdh51art

ecapallibliIfopcoir w Nito is i otbostlta~t

of REm) nsi h.ittaldad -A t tiservice

Uneaatd bit PAIBrfs art otod total Id talla u;

to 20 WelallItitioriot poll T(V-IA ar,rt~tortal.Iltomootlor ot-ot,i P-ta

ITie lirem to-sh I U2 ga few aiotlP!io,

m Api~pll

Mowery poora tot cimVol w rstoread it 11:

Iltlwisr "lir fat (aPool rs tnrped dia toL-4 rll tomla it dlocooowai llets (f Apoil 14:2:oostota at 17:44 01ffT

It/C roo iow pmoItalifqy oojtl gandat

mqitat ir 01 f Wit MI4(AV -4f•f 1I 260 Avil fi:56-16:34)

figh Vol [ag,IC 6-oar*iY%•l•

Wioo~ itomt tOf IILasfiop Will hariotortot

32.antrAoit Of Pete fe Ira motutatO1,af-oter l-u -torh+la1 I.tl, I ,

al'tar otifltiP4 atitr triott tro tl

L'Fois If A, to Peri at 04 itlahdineaytistmtttrRjo 1J fr~~i2 . IT 12£ ,11

orar;F Tel U a 41t1p litotlotto

11404r tcxriry patr cablle for SLCM6plittol atrk

ktihltli of[Ekin, PioPSIW'II real

-tut ollot I ft Etlairro od by li t M f I I cirAa m, PM14 IT Fitt o 1C qotormt we pirc4 by Ulato of I6 C isk wfoiaot.it, posorod INatI mif I( C -t rt atop 4 1f C Cr1l/ atr, o Tt l•Orriftatioti I.tttr t. raoiotr plot tmpta Wi Ittyj t ittr pact tooet'tit boto 1, to tor/t r pliot by roaoO bypby

scto tatustoll Otalt iOtW e0 liallmt to Mile) plat trail.oar Ly lotlIn to oriotow plot t~ov~ra ballet? to KOrorw electEfouity ff12.1 Is beet poagred - Ulil'iafa [oatt Tw iicelfatrge statas SOWao sttuts

C urrentt 0 Srs It :3 as 21 bpo tre IIC 20 CalotWiIlas hear porsrDCPotsr~latol' frn~ e 12:1 lacb

Mr flat latobllifiattrti oIf D 121 Clarge t; rit M

•20 Baotrlt •or,

•ltltfo ofEf1otri,. Plato

INNIMMI~ tay EIphrcm oaw Itcoidtfing the itjaotitr of IC pAI into Itotidariog hi iritotia of V2 gas oto 0f leailosi-I. 5 mi Piiri drilled o1 13 lotlrts(3-.5 4o wti dillted OR 1awntolaltir..ir R tR lRt My hi ] ofing r, Uo;0 ' a irk) of har

toatiaifretLgcAP ij~iotm 0f0.12 E&sr ato fOAI bydos tao so oh. atp L6llo NOre (.01 -&I0 thi/h .f 0est0r*lkKimt of, IN gts is io. progrs plot the, or. WWtlliIg 0 18 Il6Lo t, r,]i-.

* Ils mt.o UlAW d lootf pily: of the trator blwltoý i, of UwoAts loildtigan 10 hioth to rtfinta hbytiotoaThbitsah aol. olrod M 21st bofth hyofoo ias v4 to avoid aiplwaip

I Aifi 01:31- 9 April 22:n Daotl to and vo id asplosio INhlow anm it* k1l6uiltri mor(oompttMo~sp•-ear to , t.. frb e lhls roth. r tmll BiA 61om otaatol to otat,,t t1Il ialilfetioM

lituilliogaa NMt Sutats 6. 1. switoh to high dra. .4 purity tAWt mleaoa (tt 32 kuoolX! to) It'losh alli tthhe iirhioiri'wg to paaeo rmta iwtorfato Ito 32

booooflttoita ofbfilh drjVa if Vgoitoll 4A5 I. taoth)asis pa It is cld that thiv.itligtrofo~~~otsi(n lfowrt: a" *M dof Piitrit: LI ftitootto,4 e kthogn gas,

* lr~ifiont of A2 itoou mat~c dtopa hi

01. jtt M is rMo at off-sitrkstoi

PI•At•itta l• " ]Ifuar "bit. iskidtt to)ilf

Not for

IlDiuirima ato m ii uT/B

III 'fSOi 6161: tit2 Is ill)* i1 morea 1 Aril 11440NoSlr MoifttAi - CST a April :51.* to )Fri

IlDrlbinli ariea in Trmoilh-Radiation mmlbfl Of1 AIv Suirfc mIn

0,46111b ii27tirh-later [.o(Irisup Wa iof galin to.0 letter

ourfacmlI3111 No ,Ii M0 III 'I tPill)

asm No2;Asiri1 1t600-lomi. sonitcilr mmiirturei ofover [vmd 15 16 tumru inemsliliishemd (ca April)

11NWIi viii In fig

le '316ON (it avol M 1 April)MR mill Atiril 01:00

(2 April 17:10 - 9 April 13:10)'bibom nitt cars mour Intel Ivo a

binitirr mNer in Triour- ilhili mlotI. al Slm mlate mullc Ii

Ir~inhl hlivr iiv lowlkl it IMr 2Wr.)

-bieri 0ij In l gii Ai

mm sen 13 AprIl 11:0111-Rout. wiLosits almirioni Ar Now

in iii, irmfir veo nIidilid (Mm 2

1(110pral rvl

,A rullir board 4) Plamid Near 14v

it IJSl .r 6 Aprjtl- locitts f1 Aliqld Ilnkl in

lMIrtestsIoAvi Amd Ii ?Apoili

I lAite IrouAIn ltii 11 170 w

*iiin !iiir in fti

- fier Int Api l 17

-fau i~ler h WNW T - S. rural mmmilt

M1 *Aii~ 17:45 - 31 Itrmh 06:31)

6Ak tim nonv kreolu ni corfirsod

(Mr I A prtmil)T Tii

RaiahliAi Immi AT Ltm later surfice Ii

Niiii/L*rcirme dom to di fficulit in(0rii lib rkismii

Wartr iail(Ifrre t" mli of gratini to ente

sturil'um9y) 0 (it. 01.01 on H1 Am ill:iLl la imo [in /It Art.Ilo

-futuremrsiti(ai imi ofmrA"iti I-mm in lii trotch ourisiarilishad I. 2 Aprill

111min t .,tir-hlate trial in 1/t

: am . 7ali 11i~ DOC

-filerioel (onol~o

If kpill 14:2 - 4 *il 01:21:

ht~illIt rmfmr tulare "il* AddPAP 3 A. 11:6011-44pAnt

sanmprowled due to highi mlate Intito thi liscre) ,

Park fAr iltt~ini off 160 (Ink ii, pii-Ccustimi ins PEWri I W to CIA I

rock

Elmrtin ing sale?filer transfer

5(6 Iiv mIn CS FM Arm

(I Axi P11DRIAmrmin enter 1i ftdrii

atWt6 olItoim;in %G N11Aul21:600- ItApril Mill6

E~Minimaata mmi it ,0-C smfm ort on 19 Anihi ll,

Iraial E.~i mk~u

- r tlol l tl

rorm501,ln141 iliit mmiii

AletIllinsfer le I1Intl

(I April 13:4D -9 A4ijl 16:220

!Dtiroitl 'trmot-i

(I 4-ril 19:03 - 1)II Jl

Wiodler

.A 6, mm mit ~iig~roium lAri igt i irI

It April)Ilifrk for Ak-irii off ihe (It

Miifji,4 6i IS5pr11)NO litair~uatlrd mairlistrm

-Acosui if Inreasem mit Iit Anill

ASS a Wllm OiAR lii

Turbine, Build

water lb.lain

U[rajicu iiltl ii Ill bijmrsii-Naing rar li nfir /Jitinir sure! in

fillhiiiknlt Isas laimliflli

EU.Nairl~ imii ini T/I Iisaiimni- touicaji fr Iyrmiul mmii in V11

hisionn401 o. rhiitoh An lroilifmil

JliOk for thalint of! t10 lei in oil

10iiii tmm, ii u A ' 1 -rut IA TiOum i i

Ii %iitii immm 4imvi

Morali* Imitr trunilrr. ouili Al. I -~ Flmm' Autir lost (on I a 2 1pr111-filei imstili Pairs %.2 - Piiart. ~or 1.1n 3 kiri)'at, W ifo.1ivi -1m &tim (ar4 46011

ll air Oin Cow sinuor CATmurLI- In tentless iCwAo-ctl in .1. S, 12,1, It.2 13. 14. 16. 16. 1&. 20. 21. X a. ?26 A A qrf di))

Ilimmmm ml darirnA-Inprogiom ifr(Cnilumedan 18,1. 'A1 11.22. 23. X4.iS.2 Wto 7i )pill)

Ulibitiiomu start .1i pwnld (IAz It Aili. iia into miwlu pan r~i il~li'121(1 frnii; icr it it Ari foin s aior, mmi nm I tod MuIiii . .(Mr 13 VIril WL SIC: i. tmu rl rfirt, fmiiiiiiisi (i11 14 lril Uniit Itll I-i.l AS l ofmuinn 1`4111161. CJIl 1-4: inoth of Ifiauu(el lo t, pinm IA I 1,0 o ir states fimiltium.Gitinfo air Molir.( i Filei tmil lrLadk (IS sprlit11-ladm project mimi biIn lm .liotou)ii 10 I, 14. IS rod liciuliSPaini~m i~i of m*X m4ittt ii v Inali hu miwuhrm (ml 3 1tiomim se 15 April. atiI ulocii on 11 April. pulled 2 o4P for radivm i R rvmi ý mo uco 19 I Anril)gifimiri lInnimL111 mill, tidl JitiI 1: Mo IS. 6 Aullt /AIL 1: GeI W/ Il~r li 2m : to I1 Aprall111M gli t im m am ed mi fri. Fnkoukm (Sirrid In Fm~iuliiim Dmihi ( for "Wito 2 WI/ for Il-i:)Ilionir Drill (lialiiiiii M~isrn mi liiiag -'Pilrfstual Nobelm uilrin)r iou 21 April)111Wllulicn if fliso Milieuoi SLW 11427 April)

51t.11

I-. . - .UlmimI or I'lln whlmt,~~ 14 C AtlillOutir korre Natnenoirmim Contr iuodl Id or IN ri/liW1IN W"OImitiijer with idn: I- bitll ImiWorhluI cr 27 Wpillfkimi t

adMatlIlio:

(040 (munuirei AiM T.Wim 1ii o jlA Stomli

MCS?(olmcnomi $limpr TOS

Ill :ittitol tolter (1 lIl 1; rAyItz)

0/4 :ky fill

I? :Fir, ProIxim.ii

1S %im sters

VC( :br Fimit Cmomrt

IR6 rluto 16 Ttour Coooroit f(mite]

PIC :1141 biiiribolitie (001mm

111C :lim SUri mluoliie Coclimi

me :613"1Ami imi rml

O em lon Pitcnoim TMIi

SKC $A,;IiprM i14CT~i

2F 01'St DfmmiForce

SFP :*_n, Apl fail

ErS o Ln (Wming

SIX :5lmid br liquid Cralnial

From:To:

Subject:Date:Attachments

Gard. Lee A (TPO'hHufr.Aton ~rCr Castp Cud~ Genfrd.eathe Mmn. Jeffrey Hay, Mihe aa ihe

Meihan Sen Grchw S ev;Rygks tee Foger. Diric LCAPT USN refd lrnaka~usfl mUMW: Drywelt and SFP lnfo

Tuesday, April 26, 2011 1: 11:10 AM26 Acnil Dnrvwe Into.odf26 April SFP Infb odf

(b)(4)

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you./i

Meighan, Sean

From: Hochevar, Albert R. (INPO) [[email protected]]Sent: Friday, April29, 2011 10:08 PMTo: Huffert, Anthony; Wittick, Brian; Moore, Carl; Chuck Casto; Norwood, Donald; Gepford,

Heather; Mitman, Jeffrey; Salay, Michael; Hay, Michael; Meighan, Sean; Garchow, Steve:Reynolds, Steven; CAPT Dirk L Foster; Reid Tanaka

Subject: 1 F Plant DATA (4/30/2011)Attachments: A--7 -' I• p -3r0430_06*005.pdf; f%-T - -W0430_800F i x .pdf

All,Plant data as of today.

Al

Al HochevarInstitute of Nuclear Power OperationsCellI (b)(W) I

Restricted Distribution: Copyright @ 2011 by the Institute of Nuclear Power Operations. Notfor sale or for commercial use. Reproduction of this report without the prior writtenconsent of INPO is expressly prohibited. Unauthorized reproduction is a violation ofapplicable law. The persons and organizations that are furnished copies of this reportshould not deliver or transfer this report to any third party, or make this report or itscontents public, without the prior agreement of INPO. All other rights reserved.


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4/22 12:00 -1500 -2050 -0.023 -0.027 0.085 24.2 .27.5 0.519 136.0 0.084/22 1800. -1500 -2050 -0,027 -0.034 0.085 24.1 27.4 0.517 135.0 0.06

4/23 000 -1500 -2100, 0.023 -0.027 0.085 24.1 27.3 0.516 132.0 0.084/23 6:00 -1500 2100 0.023 -0.027 0.080 .... 24.0 27.0 0.512 135.0 0.07

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4/24 12.00 -1500 -2050 -0.018 -0.025 0,080 23.6 26.5 0.497 115.0 0.084/24 18.00 -1500 -2050 -0.020 -0.025 --0-080 --- 23.5 26.4 0,496 107.0 0.014/25 0:00 -1500 -2100 -0,020 -0.021 0.080 23.4 26.3 0,493 119.0 0.064/25 6:00 -1450 -2100 -0.020 -0.027 0,080 23.3 26.2 0.490 103.0 0.06

4/25 11:00 -1500 -2100 -0.020 -0.025 0.080 23.2 26,1 0.489 94.1 0.054/2517.0 -1500 -2100 -0,018 -0.025 0,080 23.2 26.0 0.486 98.6 0.074/25 23.00 -1500 -2100 -0.020 -0.025 0.080 23.1 26.0 0.483 105.0 0.054/265%t -1500 -2100 -0.020 -0,025 0,080 23.0 25.9 0.480 104.0 0.08

4/2611.00 -1500 -2050 -0.016 -0.025 0.080 22.9 25.8 0.4771 76.4 0.074/26 17:00 -1500 -2100 -0.018 -0.025 0.080 22.8 25.7 0.476 106.0 0.084/26 23.0 -1500 -2100 -0.020 -0.027 0,075 22.7 25.6 0.474 57.7 0.084/275:00 -1500 -2100 -0.018 -0.023 0.080 - 22.7 25.6 0.472 4 3S 0,08

4/27 11:00 -1500 -2100 -0.018 -0.025 0.075 22.6 25.5 0.470 45.9 0.064/27 1700 -1500 -2100 -0,020 -0.023 0.075 22.5 25.4 0.467 43.3 0,054/27 23,00 -1500 -2100 -0.018 -0.020 0.075 22,5 25.3 0.465, 41.9 0.084/28 500 -100 -2100 -0.016 -0,020 0.075 22.4 25.2 0.463 40.8 0.08

4/28 11.%00 -1500 -2100 -0.020 -0.023 0.075 22.3 25.2 0.461 39.7 0.044/28 1700 -1500 -2100 -0.020 -0.020 0,075 22.3 25.1 0.460 38.3 0.074/28 2300 -1500 -2100 -0.020 -0.023 0,0751 22.2 25.0 0.456 37.4 0.064/29 500 -1500 -2100 -0.023 -0,023 0.075 22.i 24.9 0.454 35.9 0,08

4/29 1100 -1500 -2100 -0.020 -0.023 0.075 22.1 24.8 0.452 37.1 0.084/29 17.00 -1500 -2100 -0.025 -0.025 0,075 220 24.8 0.449 36.1 0.074/29 2300 -1500 -2100 -0,025 -0.023 0.075 22.0 24.7 0.447 38.5 0.074/305:00 1 50 15 _ -21001 -0.025 -0025 0.075 21.9 24.6 0.444 452 0.07

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ALM 190*"m 11110 1A M*&I, N-4B I RII5 "TI _ffi]OIAN EJIONK',, D/W HVNIL)j2 RPV'I.D- ITFO8 NI $/Cj-nX S/ -RV-20.1A 111182-86A -- M 1113# if Ah-UN. 1112 • l g'l (H*IW-6. ý'--& 9"X'.1 J.,IAM AilMR4/20 0:.00 147.5 65,1 133.4 137.1 126.2 124 O.S 93 74.3 74.64/20.'00 151 65.2 133.6 136.9 125.8 122 O.S 93 74 74.34/20 12.00 153.9 05.2 134.7 137.6 126.2 123 O.S 92 73.7 744/20 18:00 155.3 85.4 135.5 138.5 126.9 124 O.S 93 73.4 73.74/21 0:00 156.2 65.3 130 138.7 127.2 126 0. 93 73.2 73.54/21 6.I 155.9 65.2 136.1 139.8 121.4 126 O.S 93 72.9 73.24/21 12.00 150.2 65.3 136 131.7 128.4 126 O.S 93 72.8 734/21 18.00 153.8 65.5 134.1 137.2 127.6 125 O.S 94 72.6 72.94/22 N:00 151.2 65.5 133.1 135.9 126.7 124 Os 94 72.6 72.94/226.00 146.1 65.7 131.2 134.4 125.5 122 O.S 93 72.5 72.84/22 12100 141.8 65.7 129.2 .... 132.4 124.4 120 O.S 93 72.4 72.74/22 18:00 140.7 65.7 128.8 131.7 120.4 116 O'S 93 72.3 72.64/23 000 140.1 65.1 128.4 131 INA4 17 O.S 93 72.2 72.54/23.600 140 65.9 i28 131.6 108.5 119 O.S 93 72.1 72.34/2312.00 139.6 65.8 127.7 133.4 III 116 O.S 93 72 72.24/2318.00 138.7 65.8 127.2 "130.1 112.5 116 O.S 93 71.9 72.14/24 0:00 136.6 65.6 126.3 129.1 118.1 ..... 115 O.S 93 71,8 72.14/240.6 134 65.8 125.2 129.1 119.6 114 O.S 92 71.1 71.94/24 12:00 140.2 65.8 124.2 128.5 118.9 114 O.S 92 71.5 71.84/24 18:00 139.9 65.8 123.4 123.3 117.2 114 O.S 92 11.4 71.64/25 0:00 138.1 65.8 i22.9 123.2 114.4 113 O.S 92 71.3 71.64/25D.00 137.6 65.7 122.5 122 115.5 114 0.S 93 11.2 71.44/2511.00 137.2 65.7 122.3 122.9 116.3 114 OS 92 71,1 71.34/25 17% 13714. 65.7 122.5 1221 115.6 114 O.S 92 71 71.34/2523'00 137.1 65.7 121.9 _ 120.5 116.4 114 Os 92 70.9 71.14/265.00... 136.4 65.6 121.2 120 117.5 113 O.S 92 -70.6 70.94/2611:00 135.4 65.7 120.5 120.1 116.2 112 O.S 92 70.7 714/2617.00 135.4 65.8 120.2 _111.3 115 112 0.5 92 70.7 70.04/26 23:00 135 65.7 120.4 1I17 l115.7 112 O.S 92 70.6 70.94/27 500 134.9 65.7 120.4 117.6 114 112 O. 922 70.5 70.94/271.'00 134.4 65.7 120.3 116 1141 III O.S 92 70.5 70.84/2717.00 134 65.8 120.1 116.5 113.4 Ill O.S 92 70.5 70.74/2723.'00 134.4 65.9 120.1 117.6 116.1 ill O.S 02 70.4 70.74/285:00 133.8 85.7 119.9 117.1 113.3 III O.S 92 70.4 10.74/2811:00 133.4 65.7 119.8 116.2 113.1 110 O.S 92 70.3 70.64/28171:00 133.2 65.6 119.6 117 116.3 110 O.S 92 70.3 70.54/282300 133 65.6 119.4 116.2 116.1 110 O.S 02 7- 70.34/29 5.00 132.9 05.6 119.2 116.5 115.9 110 O.S 92 69.7 704/29 1100 132.6 65.7 119.2 118.3 115.8. 110 O.S 92 69.6 69.84/291700 128 65.8 119.3 11697 113 108 O.S 92 69.3 69.94/2923.00 132.9 65.7 119.3 117.5 115.8 108 O.S 92 691 69.34/30500 129.6 65.6 119.1 .... 116.9 115.3 109 O.S 92 68.9 69.1

I/1

1F3 * RJfiJIZtA5.-95000

4000

3000

2000

1OOO

30

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(IffmUNICIAIT13, IROVANHIONNOT, agog

mitnuToz. ljmmmurcm, cmm

A DIWffJt (MPe abs)

X S/CE t(MPa abs)

0.8

0.7

0.6

0.5

0.4 70.

0.-3

0,3 I•

0.2

0.1

0

-2000

xxx x x x X. xxxx

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1 F- U Al ,P HIfff3 BE POE D/WE• 1)(MPaS/CEFt (MPe CAMS CAMS CAMS CAMS O laf20 (•JIN A) (201tB) (MPs) •(MPa) abs) abs) D)/W(A) D/W(B) SlCY) S/C(B) (mSv/h)

(mm) (mm) (Sv/h) (Sv/h) (Sv/h) (Sv/h)

4/201200 -1850 -2250 -0.089 -0.043 0.1045 0.1748 15.5 11.0 0.585 0.541 0.0654/20 18:10 -1850 -2250 -0.087 -0.043 0.10471 0.1754. 15.5 11.6 0.582 0.540 010854/20 23:50 -1850 -2250 -0.087 -0.045 0.1054 0.1781 15.4 11.5 0.580 0,539 0.0654/21 6:00 -1850 -2250 -0.085 -0.043 0.1061 0.1768 15,4 11.5 0.579 0.538 0.065

4/21 12.0 -1850 -2250 -0.081 -0.043 0.1050 0.1769 15.4 11.5 0.577 0.537 0.0654/21 18.00 -1850 -2250 -0.085 -0.043 0.1052 0.1715 15,3 11,4 0.575 0.535 0.0654/22000 -1850 -2250 -0.089 -0.047 0.1055 0.1776 15.1 11.4 0.573 0,534 0.0654/228.00 -1850 -2250 -0,087 -0.047 0,1055 0.1780 152 11.4 0.570 0.532 0.070

4/22 11;50 -1850 -2250 -0.089 -0,049 0,1048 0.1780 15.2 11.4 0.569 0.531 0.0704/22 17:50 -1850 -2250 -0.089 -0.049 0.1047 0.1783 15.2 11.3 0.568 0.530 0.0804/230. -1850 -2250 -0.087 -0.053 0.1047 0.1785 15.2 11.3 0.560 0.528 0.0504/236:15 -1850 -2250 -0.087 -0,049 0.1045 0.1782 15.1 11.3 0.564 0.527 0.070

4/23 11:55 -1850 -2250 -0.087 -0.049 0.1038 0.1778 15.1 11.3 0.563 0.526 0.0604/23 18%0 -1850 -2250 -0.089 -0.051 0.1033 0.1771 15.0 11.2 0.562 0.525 0.0604/24 000 -1850 -2250 -0.091 -0.055 0.1027 0.1776 15.0 11.2 0.561 0.523 0.0704/24 5:50 -1850 -2250 -0.089 -04053 0.1031 0.1778 15.0 11.2 0.560 0.522 0.060

4/24 12.00 -1850 -2250 -0.091 -0.051 0.1031 0.1780 14.9 11.1 0.558 0.521 0.070 i4/24 1800 -1850 -2250 -0.091 -0.051 0,1034 0.1785 14.9 11.1 0.557 0.520 0.070!4/25 0. -1850 -2250 -0.089 -0.055 0.1038 0.1787 14.8 11.1 0.556 0.519 0.070!4/25 8:00 -1850 -2250 -0,089 -0.053 0,1041 0.1789 14.8 11.1 0.554 0.518 0,070

4/251100 -1800 -2250 -0,091 -0,055 0.1029 0.1787 14.7 11.0 0.553 0.517 0,0504/25 1700 -1850 -2250 -0.089 -0.055 0,1034 0,1187 14,7 11.0 0,552 0.516 0,0504/25 23.00 -1800 -2250 -0.091 -0.055 0.1041 0.1792 14.6 11.0 0.55i- 0,515 0.050'4/26 500 -1850 -2250 -0.087 -0.055 0.1043 0.1794 14.6 11.0 0.550 0.514 0.040 '4/26 9:00 -1850 -2250 -0.099 -0.055 0,1041 0,1794 14.5 10.9 0.549 0.513 0.040

4/28 17:00 -1850 -2250 -0.089 -0,051 0.1033 0.1790 13.9 10.9 0.517 0.511 0.0504/26 23.00 -1850 -2250 -0.089 -0.049 0.1034 0.1792 14.2 10.9 0.530 0.5101 0.050_4/27 5:00 -1850 -2250 -0,089 -0,053 0.1031 0.1787 14.3 10.9 0.532 0.508 0,050

4/2711.' -1850 -225_0 0.09 -0.053 0.1029 0.1792 14,3 10.8 0.534 0.5017 0.040!4/27 17:00 -1850 -2250 -0.089 -0,053 0.1022 0.1789 14.3 10.8 0D534 0.505 0.0504/27 23. -1850 -2250 -0.007 -0.055 0.1022 0.1789 14.3 10.8 0.534 0.504 0.0454/285,0 -1850 -2250 -0,089 -0.055 0.1017 0.1783 14.2 10.8 0,533 0.502 0.050

4/28 11.% -1850 -2250 -0.089 -0.055 0.1017 0,1785 14,2 10.7 0.532 0.501 0.0504/28 17:10 -1850 -22501 -0.05 -0.055 0.1017 0.1790 14.2 10.7 0.532 0.500 0.0504/28 2300 -1850 -2250 -0.089 -0.060 0.1027 0.1792 14.1 10.7 0.530 0.499 0.0404/29 5:00 -1850 -22501 -0,091 -0082 0.1036 0.1799 14.1 10.6 0.529 0.496 0.050

4/29 11:00 -1850 -2250 -0.091 -0.060 0.1033 1 0.1796 17.0 10.8 0.527 0,495 0.0504/29 17:00 -1850 -2250 -0.009 -0.080 0.1038 0,1799 14.0 10.6 0.526 0,494 0.0504/2923:00 1850 -2250 -0.089 -0.084 0.1040 0.1804 14.0 10.5 0.525 0,492 0,0504/30 501 -1850 -2250 -0.091 -0.088 0.1043 0.1803 13.9 10,5 0.524 0.491 0.040

1/I

73/22 22:38triFi23i1

300g

275

250 a

225

200

175¶

150 ju

125 AL

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75

50

25

(Noll]

0 5/ * '53/11 2/2l 3/23 3/1J3/2173/213131 4/2 4/4 4/6 4/8 4/tO 4/I? 4/14 4/1l 4/11 4/30 4/22 4/2442 4/210U 4/30 5/2 1/4

IF-3,19I.-NUAW-il

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ng~om~u~ utum~.

MdJXA 98 Rp m i±WD46 122 WvAMItW WY11175W &P 2-710 AL9t0o-hIF 1110 I W WoiiM~tz~ sV4's-',-l V~- Si -&ail .. 039 _. l 2 1 M -86A,,f .. .. *ZIA 1ore- III_____ *II *I 1

4/22 11:50 92.4 1488s 11159 116.1 14.3 17.2 102.5 51.8 82. 137.9 42.2 42.2

4122 17:50 80.8 149.9 110.1 113,3 146.2 81.7 102.3 58.5 57.3- 130.6 42,1 421

4/23000 81.7 150 109.2 110.8 148.1 71.8 102.2 58.6 58.1 135.2 42.1 42.1

4/238:15 85,9 154.9 109,4 101.5 1089 85.2 101,4 58.9 56.2 134.2 42 42

4/23 11:55 65.7 152.1 108. 104.3 129.5 72.4 100.6 59,2 55.1 132.9 41.9 41.9

4/23 U8'0 81.1 153 110.1 10.g 144.4 80.5 100.6 59.4 51.3 130.8 41.9 41.9

4/240% O 1 71 155.7 109.6 102.7 150.4 81,9 99.5 598 84.4 129,8 41.8 41.8

4/24 5:50 81.1 160.7 109.1 104.3 151.9 79.4 99.5 593 63.5 128.3 41.8 41.8

4/24 12:00 65.5 183.2 110.8 102.9 140.5 74.9 988.6 59.4 65.2 126.6 41.7 41.1

4/24 1901 71.5 15.5 110.2 102.8 142.7 68 98.3 594 65.3 126.6 41.7 41.7

4/25 000 74.8 189 110.8 103.4 129.9 804 98.4 59.2 687 124,3 41.6 41.6

4/256.00 72.5 165.9 109.3 99.3 130 53 98.5 58.9 70.2 122.5 41.6 41.6

4/25 1 I0 8.8 104.8 Ila 99.5 145. 43.2 97.8 59.6 69.5 120 41.6 41.5

4/2517.00 7717 163.8 110 98 153 53.. 97.3 59.5 61.4 117.6 41.5 41.5

4/25 23.0 84.9 155.7 1091 98.8 158.4 628 96.7 59.2 84.5 103.1 41C4 41.4

4/21500 87.9 151 110.4 94.1 1568 68.7 97 59 87.3 111.9 41.4 41.4

4/26 W00 82.5 149.4 110.7 97 158 43.4 98.7 59.1 89 121.5 41.4 41.4

4/28 17,00 882 154.8 110.5 94.3 180.7 82.4 98 59.6 711 122.2 41.3 41.3

4/2823.00 85.5 158.6 110.7 92 158.7 83.2 96.1 59.7 96.7 122.2 41.2 4112

4/27 5.00 12 153.1 110.7 943 157 51.7 98.3 59,9 101.9 121.7 41.2 41.2

4/21 I11 82.3 150.4 110.3 95.3 1517 50 97.3 59.9 103.8 1214 41.1 41.1

4/27 17%00 83.2 143.2 109.9 92.4 156.8 36 98.7 90.6 104 124.8 41.1 41.1

4/2723.00 84.6 137.1 110,2 90,5 152.1 56.6 97.2 80.7 102.9 124.1 411. 41.1

4/285:00 88 129,5 109.8 92.7 150.9 57.8 98.2 609 102.1 124.7 41 41

4/2811,00 85.1 1271.2 109.4 91.3 154.4 54.7 856 80.7 9a9 125.4 41 41

4/28 17:10 8315 124.1 110 94.9 150.1 54.1 96 60.8 95.5 128 41 41

4/28 23.00 82.4 120.8 112.1 92.2 149.7 90.3 95.8 50,5 98.1 129.1 40.9 40.9

4/295,00 81.3 114.7 112. 91.6 150.8 85.1 98.7 60.2 98.6 1283 40.9 40.9

4/2911.00 80., 111 112. 64 1517 84 9U.7 603 971.2 127.4 40.9 40.9

4/2917,00 90.9 100.1 1117 al.1 151.2 845 96.3 M4 97.8 127.6 40.8 40.8

4/29 23.00 81.6 108.2 113.3 83.2 147.1 84.8 95.1 608? 97.9 128.0 40.8 4098

4/305.00 83g 1009 1131 848 150 81,0 97 60 101,2 125.3 40.7 4017

11hJk1.LL

1/1

1 F576 ~~~

100.0I 1F5 * I

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40.0

20.0

0.04/24 4/25 4/26 4/27 4/28 4/29 4/30 5/1

1 F5/6 * -i-

___ F5Wl F~*MJ 1F50fi,%V-J-L,.8A fF6 5+Tr*A9( S ~ -)4/27 10,00 37.5 41.3 54.3 27.04/27 11:00 40.4 41.1 44.3 27.04/27 12.00 42.8 40.8 40.9 27.54/27 13:00 45.8 39.5 37.6 28.54/27 14:00 48.1 39.1 35.5 29.04/27 15:00 50.4 38.8 33.6 29.04/27 16:00 52.7 38.3 32.1 29.54/27 17:00 55.0 37.8 30.9 30.04/27 18.00 58-2 37.5 29.8 30.04/27 19:00 59.4 37.1 29.2 30.04/27 20:00 53.4 37.0 28.6 30.54/27 21:00 50.5 37.4 32.6 30.54/27 22.00 48.2 37.6 34.1 30.04/27 23:00 47.5 37.9 35.9 29.54/28 0:00 45.7 38.3 37.5 29.04/28 1.00 43.3 38.6 39.0 29.04/28 2:00 41.9 39.0 40.7 28.54/28 3:00 41.0 39.2 42.1 28.04/28 4:00 40.1 39.6 43.9 27.04/28 5:00 39.4 39.9 45.6 27.04/28 6:00 38.7 40.4 47.5 27.04/28 7:00 38.1 40.7 49.3 26.54/28 8.00 37.6 41.0 50.9 26.54/28 9:00 37.1 41.3 52.5 26.0

4/28 10:00 38.7 41.6 46.2 26.04/28 11:00 41.3 41.4 43.2 26.54/28 12:00 43.9 41.1 40.3 27.04/28 13:00 46.4 40.1 37.7 27.54/28 14.:00 48.9 39.5 35.6 28.04/28 15:00 51.4 39.1 33.7 28.04/28 16:00 53.8 38.7 32.2 28.54/28 17.00 55.8 38.3 31.2 29.04/28 18:00 58.0 37.9 30.2 29.54/28 19:00 60.5 37.5 29.3 30.04/28 20:00 57.7 37.1 28.7 30.04/28 21.00 54.2 37.2 28.2 30.04/28 22:00 51.3 37.5 27.7 30.54/28 23:00 48.7 37.9 27.2 30.54/29 0:00 46.6 38.2 26.8 31.0

4/29 1:00 45.1 38.5 26.6 31.04/29 2:00 43.3 38.9 26.2 32.04/29 3.00 42.0 39.2 26.0 3254/29 400 41.0 39.5 25.7 33.04/29 5.00 40.0 39.9 25.5 33.04/29 6:00 39.1 40.3 25.3 33.54/29 7:00 38.4 40.6 25.2 34.04/29 8:00 37.9 41.1 25.1 34.04/29 9:00 37.3 41.4 25.0 34.5

4/29 10:00 38.2 41.6 24.9 35.04/2911:00 41.2 41.4 24.9 35.54/29 12:00 43.7 41.2 24.8 36.04/29 13:00 47.0 40.1 24.8 36.54/29 14:00 48.9 39.6 24.8 36.54/29 15:00 51.3 39.2 24.9 37.04/29 16:00 53.7 38.9 24.9 37.04/29 17-00 55.9 38.4 24.9 37.54/29 18.00 58.4 38.0 24.9 38.04/29 19:00 60.8 37.7 28.6 37.54/29 20:00 62.7 37.3 30.1 37.54/29 21.00 64.9 37.0 31.9 35.04/29 22.00 57.1 36.9 33.8 35.04/29 23.00 53.7 37.1 36.0 34.04/30 0:00 50.7 37.4 37.6 33.04/30 1.00 48.4 37.8 39.2 32.04/30 2.00 46.3 38.1 40.8 31.0

4/30 3:00 44.8 38.4 42.1 30.54/30 4.00 42.7 38.9 44.6 30.04/30 500 42.0 39.1 45.6 29.5

4/30 600 40.7 39.6 47.7 29.0

I/I

2 F - 1 -;T

7 --

2

8000

6000

5000 E

4000 :e

3000w

2000

1000

0 e- -. 0*-0-0* 44 *0-4 * v- w * & b *- -W & * * # * • * 04/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6:00 12:00 18:00 0:00 6:00 12:00 18:00 0:00 6:00 12.00 18.00 0:00 6:00 12:00 18-00 0.00

160

140120 .. . . '1

280 ---6I0-

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20 .. . ..... 4' w 0

0-.............. ......

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6:00 12.00 18:00 0:00 6:00 12:00 18.00 0:00 6-00 12.00 18:00 0:00 6-00 12.00 18:00 0:00

300

6200 -

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A D/WZEE 2002x S/CZI i

0

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/I 5/1 5/20:00 6:00 12:00 18:00 0-00 6:00 12:00 18:00 0:00 6.00 12:00 18:00 0:00 6.00 12.00 18:00 0:00

7000 , .. .......

6m000--

-5000

EE4000

23000 w-- 40-- - -*- 6__

S/C*a

1000 -- -

04/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/I 5/20:00 6:00 12:00 18:00 0:00 6:00 12:00 18:00 0:00 6:00 12:00 18:00 0.00 6.00 12:.00 18.00 0.00

2 F - 2

8

7

2

8000

7000

6000

. 4000 E

3000

2000

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0 6.- 4. -*..*-4-* * # * * , * * * , * * * * * #, # * * -...... 04/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6-00 12:00 18:00 0:00 6:00 12:00 18:00 0:00 6:00 12:00 18.00 0:00 6:00 12-00 18:00 0:00

160 .. .....140 . . . . . .. . .. . . .

120- .--1. 00 ...... .

~80

40.

20 f . 't. - .• _ .. e .40

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6:00 12:00 18:00 0:00 6:00 12:00 18:00 0.00 6-00 12:00 18:00 0:00 6:00 12:00 18:00 0:00

300 . . . .. . . . .. - [gage] 3

250 . - S/CEh [abs] 250

A 200 xs/C- -- 200

150 ...-...... .... .. ... 515

o 100 -a.MIm aLa aI' II n l '.LMs a . .... .. ..... 00

50 -. 50

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6:00 12:00 18.00 0:00 6:00 12:00 18:00 0:00 6.00 12:00 18:00 0:00 6:00 12.00 18.00 0:00

6000 .............. .......................

5000 --•,S/C*,f

E 4000E3000. ..-- -

20012000 .

1000 -- +.+4 , ,+ _ - _-. ._, __+_ _._+ - - .-

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6:00 12-00 18.00 0:00 6:00 12:00 18:00 0:00 6:00 12-00 18-00 0-00 6,00 12-00 18:00 0:00

2 F - 3 -'iy

8

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wi~ 0 -asU U UU U~m U UU S

80007000

. .. - - 6000

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I .- - . - .--- - ---. ----- -.. 1000

0 .,&.-'"-' -4 ' • ' 4-b 40--. --- 0---&b &.. 0

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/I 5/1 5/I 5/1 5/20:00 6:00 12.00 18:00 0:00 6:00 12:00 18:00 0:00 6:00 12:00 18.00 0:00 8:00 12-00 18.'00 0:00

160

140

120.

40 .. . .. .....

20

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6:00 12:00 18:00 0:00 6:00 12.00 18:00 0-00 6-00 12:00 18.00 0:00 6:00 12.00 18.00 0M00

300 -. . . . . . . . . . . . . . . . . . .. . . . . . 300* D/WE t [gpge]

250 .... .. .. mS/CIE[abs] . 250A AD/WE!"

~200 .xCA -200

442000.. . . . .. b*bb .... .. ..- ,- •200 ,,

-R ~x s/cl• 2i

0•'e• e'• e'•''e'• •-...........................................------------............ .04/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 511 5/1 5/I 5/1 512

0-00 6:00 12'00 18:00 0.00 6:00 12.00 18:00 0:00 6:00 12.-00 18.'00 0.00 6.00 12:00 18.00 0:00

6000 . . • -. . . . . . . . . . . ..--- ------ *_.-

*.S/C*1u- 4000

A 3000-* 2 0 0 0 Sbb.b••_.bbbbbbbbbbbbbbbb•e •• <•• o bb0"' 1000 --. - ...-- - - - - - .... -

0 -.. ...... . . .. . .

-1000 .. . . . ...4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20:00 6:00 12.00 18M00 0:00 6-00 12:00 18:00 0:00 6:00 12-00 18.00 0:.00 6:00 12.00 18.'00 0:00

2 F - 4.5 3

7

6

5.

04

2

7000

6000

.. 5000,-,E

4000 .

3000 -

2000

1000

0o * 0 'v 0 *-*., 0- # 0 * * a ' 4 * # 0 * . 0 * * * 0 0

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/2

0:00 :0.0 12-00 18-00 0:00 6:00 12:00 18.00 0-00 6:00 12.00 18:00 0:00 6-00 12.00 18.00 000

160

140

120

N 80

" 60--

40 .

2 0 .

0 . ..4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30' 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20.00 6:00 12.00 18-00 0.00 6.00 12:00 18:00 0.00 6-00 12:00 18:00 0:00 6:00 12.00 18:00 0:00

300 3000 D/Wa±g[pgeJ

250 .... . ..... ..-. .. • S/CEEa [bs] ... 250

6 200 . . .... . . . ..- 200x S/C=.

150o 1......... ,50

100 vt-A re-&. CS-.M.-.M. a ma 0 0 •..s Wi n a 0 9.- a a a •...... . .. 100•

S 0 , -.. . .... . . . . . . . . . .. . . . .. . . . ....... ...... . .. .. . . ..* * . .. . .. .. . . . . ..- . 0

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/I 5/1 5/20:00 6:00 12:00 18,00 0:00 6:00 12:00 18-00 0-00 6:00 12:00 18:00 0:00 6:00 12-00 18:00 0:00

6000...........

0

4000E

Eo 3000 ... . . ."* 2000 ,-*--o--.4•-o-,-.4.-.4.. a *, ao.o. o.-o-o 0--o 4.o.a.o-o*. 4. ........... . ... .....

00ooo -...... ....................

-1000----------------------...

4/28 4/28 4/28 4/28 4/29 4/29 4/29 4/29 4/30 4/30 4/30 4/30 5/1 5/1 5/1 5/1 5/20-00 6:00 12:00 18:00 0:00 6-00 12:00 18:00 0:00 6:00 12:00 18:00 0:00 6.00 12:00 18.00 0.:00

_________2F- 1 G TAF)b'*0)1f= *1 +4200[mm]0~ ~• F;• (M;,[mm[OM c] D/WE~h D/W'sl s/Cf±-t SOc10 S/cl•

Mga[e) ] 4i */ M 'iill [kPa(gage)] [0C] [kPa(abs)] [mm] [OC]

2011/4/280:00 0.05 5200 23.9 7 27.5 108 2003 232011/4/282:00 0.05 5200 23.9 8 27.5 108 2002 232011/4/28 400 0.05 5200 23.9 8 27.5 108 2003 232011/4/28 6:00 0.05 5200 23.9 8 27.5 108 2003 232011/4/288:00 0.05 5200 23.9 7 27.5 108 2003 23

2011/4/28 10.00 0.05 5200 23.9 7 27.5 108 2002 232011/4/28 12. 0.05 5200 23.9 71 27.5 108 2002 232011/4/28 14:00 0.05 5200 23.9 7 27.5 108 2002 232011/4/28 16:00 0.05 5200 23.9 7 27.5 108 , 2002 232011/4/28 18:00 0.05 5200 24.0 7 27.5 108 2002 232011/4/28 2000 0.05 5200 24.0 7 27.4 108 2002 232011/4/28 22:00 0.05 5200 24.0 6 27.4 108 2003 23

2011/4/29 0:00 0.05 5200 24.0 6 27.5 108 2003 232011/4/29 2:00 0.05 5200 24.0 6 27.5 108 2004 232011/4/29 4:00 0.05 5200 24.0 6 27.4 108 2004 232011/4/29 600 0.05 5200 24.0 6 27.4 108 2004 232011/4/29 8:00 0.05 5200 23.9 6 27.5 108 2004 23

2011/4/29 10:00 0.05 5200 23.9 6 27.4 108 2004 232011/4/29 1200 0.05 5200 23.9 6 27.4 108 2006 232011/4/29 14.00 0.05 5200 23.9 6 27.4 108 2005 232011/4/29 16:00 0.05 5200 23.9 6 27.4 108 2005 232011/4/29 1800 0.05 5200 23.9 6 27.4 108 2004 232011/4/29 20:00 0.05 5200 23.9 5 27.4 108 2006 232011/4/2922,00 0.05 5200 23.9 5 27.4 101 2006 23

2011/4/30 H00 0.05 5200 23.9 5 27.4 107 2004 232011/4/30 20 0.05 5200 23.9 5 27.4 107 2004 232011/4/304200 0.05 5200 23.9 5 27.4 107 2004 23

2011/4/30 6:00 0.05, 5200 23.8 5 27.5 107 2004 232011/4/308:00 -

2011/4/30 10:002011/4/30 12:002011/4/3014:002011/4/3016:002011/4/30 18:002011/4/30 20:002011/4/30 22:00

2011/5/1 0:001

2F-2- • (TAF)iJ'G(*i*=A +4200[mm]

0 ro (Ma [ ;I timjc] D/WEt NSAI/ S/CEt• S/C7X[ MICRfl~r,'j [MPa [mm]

(gage)] U O ,*14 I2 [kPa(gage)] [0C] [kPa(abs)] [mm] [0C]

2011/4/280:00 0.04 6050 24.8 4.6 28.6 104 1200 242011/4/28 2:00 0,03 6050 24.8 4.9 28.5 104 1200 242011/4/28 4:00 0.03 6050 24.8 5.1 28.5 104 1200 242011/4/28 6:00 0.03 6050 24.9 5.0 28.4 104 1200 242011/4/28 8:00 0.03 6050 24.9 5.0 28.4 104 1200 24

2011/4/28 10:00 0.03 60501 24.9 5.0 28.5 104 1200 242011/4/28 12:00 0.04 6050 24.9 5.0 28.5 104 1200 242011/4/28 14:00 0.03 6050 24.9 5.0 28.4 104 1200 242011/4/28 16:00 0.03 6050 24.9 4.9 28.4 104 1200 242011/4/28 18:00 0.03 6050 24.9 4.7 28.4 104 1200 242011/4/28 20:0 0,03 6050 24.9 4.2 28.5 104 1200 242011/4/28 22:0 0.03 6050 24.9 4,1 28.4 104 1200 242011/4/29•0:00 0.03 6050 24.9 3.9 28.4 104 1200 242011/4/29 2:00 0,03 6050 24.9 3.9 28.4 104 1200 242011/4/29 4:00 0.03 6050 249 3.7 28.5 104 1200 242011/4/29 6:00 0,03 6050 24.9 3.5 28.4 104 1200 242011/4/29 8.00 0.03 6050 24.8 3.5 28.4 104 1200 24

2011/4/29 10:00 0.03 6050 24.8 3.4 28.4 104 1200 242011/4/29 12%:0 0.03 6050 24.8 3.4 28.5 104 1200 242011/4/29 14%0 0.03 6050 24.8 3.4 28.4 104 1200 242011/4/29 16:00 0.03 6050 24,8 3.4 28.4 104 1200 242011/4/29 18:00 0.03 6050 24.8 3.2 28.4 104 1200 242011/4/29 20:00 0.03 6050 24.8 3.0 28.3 104 1200 242011/4/29 22200 0.03 6050 24.8 2.9. 28.3 104 1200 24

2011/4/30 H000 0.03 6050 24.1 2.8 28.4 104 1200 242011/4/30 2:00 0.04 6050 24.1 2.8 28.3 104 1200 242011/4/30 4:00 0.03 6050 24.8 2.1 28.3 104 1200 24

2011/4/30 6:00 0.03 6050 24.7 2,7 28.4 104 1200 242011/4/30 8:00 6050 24.8 2_2.10 20

2011/4/30 1: 0.03O _ 050 2.. 2 4 _4 022011/4/30 12:002011/4/30 14:002011/4/30 18:002011/4/30 18.02011/4/30 20:00]2011/4/30 22:00i

2011/5/1 0:001

2F-3- 'IAI(TAF)SO) §= P -1+4200[mmlFE k• oft 0*-Eoc] o/wEt O/W"I'S S/CEt :S/C7X,% S/C :E

0• FoalJ EMPa [mm]___ __77(gage)] 0 #*K 'i; [kPa(gage)] [°C] [kPa(abs)] [mm] [0C]

2011/4/28 0.00 0.00 3576 32.9 11 33.0 110 2100 262011/4/28 2.0 0.00 3575 32.8 11 33.0 110 2100 262011/4/284.00 0.00 3570 32.7 11 33.0 110 2100 262011/4/286:00 0.00 3570 32X9 11 33.0 110 2100 262011/4/28 8O0 0.00 3568 32.9 11 32.9 110 2100 26

2011/4/28 1000 0.00 3565 32.8 11 33,1 110 2100 262011/4/28 12:00 0.00 3561 32.7 11 32.9 110 2100 262011/4/281400 0.00 3558 32.8 11 33.0 110 2100 262011/4/2816:00 0.00 3555 32.5 11 33.0 110 2100 262011/4/2818900 0.00 3555 32.5 11 33.1 110 2100 262011/4/28 20:00 0.00 3549 32.4 10 32.9 110 2100 262011/4/28 22:0 0.00 3549 32.3 10 32.8 110 2100 262011/4/29 0:0 0.00 3545 32.4 10 32.8 110 2100 262011/4/29 200 0.00 3545 32.4 10 32.8 110 2100 262011/4/294•00 0.00 3542 32.3 10 32.8 110 2100 262011A/296:00 0.00 3538 32.3 10 32.8 110 2100 262011/4/29 H0 0.00 3535 32.3 10 32.8 110 2100 26

2011/4/29 10: 0.00 D 3532 32.3 10 32.8 110 2100 262011/4/29 12:00 0.00 3532 32.2 10 32.8 110 2100 262011/4/29 14:00 0,00 3524 32.2 10 32.8 110 2100 262011/4/291N00 0,00 3521 32.2 10 32.9 110 2100 262011/4/2918:00 0,00 3520 32.1 9 32.8 110 2100 262011/4/29 20:00 0.00 3511 32.1 9 32.1 110 2100 262011/4/29 22:0 0.00 3506 32.1 9 32.6 110 2100 26

2011/4/30 0UO 0.00 3506 32.5 9 32.6 110 2100 262011/4/30 210 0.00 3502 33.1 9 32.7 110 2100 262011/4/30 4:00 0.00 3500 33.4 9 32.7 110 2100 26

2011/4/306:00 0.00 3497 33.5 9 32.8 110 2100 262011/4/30 8:00

2011/4/30 10.00_2011/4/30 12:0012011/4/30 14:002011/4/3016:002011/4/30 18022011/4/30 20:002011/4/30 22:00

2011/5/10:001 1 L

2F-4,0 ______TAF)S0 %*+ 4200[mm]FEE [mm ft [°C] D/WE] DANU SicED S/OC*q S/ChitMaa [mm] 7*/JbIA4ki" [kPa(gage)] [rC] [kPa(abs)] [mm] [0c]

___________( age)] 7•7" _______ _____1____

2011/4/28 0:00 0.10 4589 29.4 B 32.3 108 2050 302011/4/28 2:00 0.07 4589 29.3 7 32.5 106 2050 302011/4/28 4:00 0.07 4589 29.1 7 32.1 too 2050 302011/4/28 8:00 0.07 4589 29.0 7 31.7 106 2050 302011/4/28 8:00 0.07 4589 28.9 7 32.0 106 2050 30

2011/4/28 1000 0.07 4589 28,7 7 31.6 106 2050 302011/4/28 12:00 0.07 4589 28.6 7 32.4 106 2050 302011/4/28 1400 0.07 4589 28.5 7 31.9 106 2050 292011/4/28 16:00 0.07 4589 28.3 6 32.1 106 2050 292011/4/28 18:00 0.07 4589 28.2 6 32.1 106 2050 292011/4/28 20:00 0.07 4589 28,1 6 31.4 106 2000 292011/4/28 22:00 0.07 4589 28.0 6 31.2 106 2050 29

2011/4/29 0:00 0.07 4589 27.9 5 31.3 106 2050 292011/4/29 2:00 0,07 4589 27.9 5 31.6 106 2050 292011/4/29 4:00 0.07 4589 27.8 5 31.7 106 2050 292011/4/29 6:00 0.07 4589 27.7 5 31.6 106 2050 292011/4/29 8:00 0.07 4589 27.7 5 31.7 106 2050 28

2011/4/29 10:00 - 0.07 4589 27.6 5 31.6 106 2050 282011/4/29 12:00 0.07 4589 27.5 5 31.8 106 2050 282011/4/29 14:00 0.07 4589 27.4 5 31.7 106 2050 282011/4/29 16:00 0.07 4589 27.4 5 31.6 106 2050 282011/4/29 18:00 0.07 4589 27.3 4 31.4 106 2050 282011/4/29 20:.00 0.07 4589 27.2 4 31.5 106 2050 282011/4/29 22:00 0.07 4589 27.2 4 31.5 106 2050 282011/4/30 0.00 0,07 4589 272 4 31.7 106 2050 282011/4/30 200 0.07 4589 27.1 4 31.5 106 2050 282011/4/30 400 0.07 4589 27.1 4 31.4 105 2050 28

2011/4/30 6:00 0.07 4589 27.0 4 31.6 106 2050 282011/4/30 H.00

2011/4/3010.9002011/4/3012:002011/4/3014:002011/4/30 16:0012011/4/3018:002011/4/30 20:002011/4/3022:00

2011/5/1 0:.00

Fukushima Daiichi Daily Update

April 28, Thu. 17:00

1. Major evolutionsUnit 1 trial flooding operation is continuing. RPV injection flow was increased from 6m3/h to 10m3/h yesterday10:00AM. RPV water level increased by 10cm but stabilized after 10 hours. The reason of level stabilization is notidentified. RPV pressure and D/W pressure decreased gradually. Various temperature parameters decreased.Estimation of D/W water level is not available. Injection flow rate was maintained at 10m3/h and will be returnedto 6m3/h when D/W pressure drops below 0.11 MPa abs to avoid negative pressure. There is no change observed inthe water level in Unit 1 trench or turbine building.

Tepco corrected yeasterday's communication concerning possible leakage from Unit 4 SFP. Recent data didn'tshow any indication of leakage.

Tepco press released their plan of radioactive water treatment. The treatment system is composed of Cs Absorber,Decontamination System, Desalination System and reservoirs, as outlined in the "Roadmap for Restoration". Someprincipal parameters are;

Treatment Capacity: 1,200m3/dayD/F: IOE+4-IOE+6 on Cs (from IOE+5-IOE+6 Bq/cm3 to 1OE+I-1OE+2 Bq/cm3)Reservoir Capacity: 31,400 m3 will be installed before early June. Addition is considered, including

HLW reservoir)87,500 m3 currently plus 210-500 m3/day of injected waterAccumulated water:

2.Unit statusUnit 1:RPV injection flow was increased from 6m3/h to 10m3/h. Reactor pressure and D/W pressure decreased gradually.FW nozzle temperature and RPV bottom temperature decreased.

4/28 5:00 4/27 5:00 4/25 23:00Reactor Pressure (MPa g) 0.415/1.168* 0.450/1.205* 0.450/1.173*FW Nozzle Temperature (0 C) 107.3* 132.0" 133.3*

RPV Bottom Temperature (°C)Injection flow rate (m3/h)DfW pressure (MPa abs)

No SFP spray scheduled today.

*under examination98.510.00.125

110.55.90.155

111.36.10.150

Unit 2:FW Nozzle Temperature continues to decrease;

4/28 5:00Reactor Pressure (MPa g) -0.016*/-0.020*FW Nozzle Temperature (C) 119.912 11I tt T. . t- i- -- 4

4/27 5:00-0.01 8*/-0.023*120.4

6.90.08057.0

4/25 23:00-0.020*/-0.025*121.9indication incorrect7.00.08071.0

Injection flow rate (m3/h)D/W pressure (MPa abs)SFP temperature (C)

7.00.07550.0

SFP water supply is scheduled today 10:00-11:30, 60 t.

1

Unit 3:No big changes within a limited band;

4/28 5:00Reactor Pressure (MPa g) -0.055*/-0.089*FW Nozzle Temperature (°C) 86.0*

*under examination

RPV Bottom Temperature (C) 109.6Injection flow rate (m3/h) 6.8D/W pressure (MPa abs) 0.1017

4/27 5:00-0.053*/-0.089*72.0*

110.76.90.1031

4/25 23:00-0.055*/-0.091 *

84.9*

109.86.80.1041

SFP water supply is not scheduled today.

Unit 4:SFP water spray was conducted on 4/27 12:18-15:15, 85 t. No schedule for today.

Common pool:32C (4/27 6:50)

3. T/B and Trench drainageUnit I T/B and Trench level unchanged. Unit 2 trench level decreased. Unit 3 Trench level and Unit 4 T/B levelare increasing;

T/B (above floor level) Trench (below grating) as of 4/28 7:00Unit 1 3.15 m (no change since 4/27 7:00) 1.53 m (no change since 4/27 7:00)Unit 2 1.20 m (no change since 4/27 7:00) 0.90 m (-1cm since 4/27 7:00)*

Unit 3 1.10 m (no change since 4/27 7:00)Unit 4 1.20 m (+5cm since 4/27 7:00)

4. Site Environmental DataSite environmental dose is gradually decreasing;

4/28 9:00

*water transfer continued.0.95 m (+ 2cm since 4/27 7:00)

Main Gate (tSv/h):West Gate (gSv/h):Adm. Bldg. (gSv/h):

48.021.8430

4/27 9:0051.022.7440

4/26 9:QO52.023.3450

2

[Environmental Data]a. Radiation Level during on Apr. 27-Apr. 28

Time and Date Dose rate I Location

(,u Sv/h)

16:00 2011/04/27 22.7 Monitoring Car in West gate of Fukushima Daiichi NPS

00:00 2011/04/287 22.4 Monitoring Car in West gate of Fukushima Daiichi NPS

08:00 2011/04/28 21.9 Monitoring Car in West gate of Fukushima Dajichi NPS

Monitoring post data ti Sv/h)

MP-1 M-2 MP-3 MP-4 MP-5 MP-6 MP-7 MP-8

16:00 201104/27 7 29 23 21 32 58 155 149

00:00 201104/28 7 29 23 21 31 58 154 148

08:00 2011 04/28 7 28 22 20 30 56 150 144

b. Iodine and Cesium are detected by the isotopic analysis;0 Site Dust Sampling Data, 4/26, at west gate

4/26

11:25-11:45

(0) ()limitation

Measured Ratio of breathingair for

(Bq/cm3) ()/• radiation

worker

Volatile

1-131 5.0E-05 0.05 1E-03

Cs-134 1.2E-05 0.01 2E-03

Cs-137 1.4E-05 0.00 3E-03

Particulate

1-131 4.OE-05 0.04 1E-03

Cs-134 9.7E-06 0.00 2E-03

Cs-I37 1.0E-05 0.00 3E-03

3

* Dust Sampling Data, 4/25 beyond 20 km from stationTime and Date 1-131 Cs-137 Location

(Bq/m3) (Bq/m3)

10:01-10:21 4/25 ND ND (Pointl) 60 km northwest of station

12:36-12:56 4/25 ND ND (Point2-1) 40 km northwest of station

11:32-11:52 4/25 ND ND (Point2-6) 45 km south of station

* Pond Water and Soil Sampling Data, 4/25 beyond 20 km from station

Place Distance from Sample Nuclide Radioactivethe plant level(Bq/k

4/25litate I 40km northwest Pond 1-131 43.0

Point2-1 waterCs-137 32.1

Soil 1-131 4,390.Cs-137 10,800

Kawamata 45km northwest Soil 1-131 1,780IPoint2-2 Cs-137 3,720

Tamura 40km west. Soil 1-131 333Point2-3 Cs-137 484

Minamisoma 25km north Soil 1-131 698Point2-4 Cs-137 1,0601

Ono 40km southwest Soil 1-131 189Point2-5 Cs-137 744

Iwaki 45km south Soil 1-131 2,080Point2-6 Cs-137 1,010

Kawamata 35km northwest Soil 1-131 8,690Point2-7 Cs-137 22,400

Date 50kmn northwest Soil 1-131 1,870Point2-8 Cs-137 1,850

Nihonmatsu 45km west- Soil 1-131 3,010northwest Cs-137 12,400Point2-9

4

1-131 (Bq/kg)

100,000

10,000 "A'

-V -4-* litate-,-Kawamata

1,000 .. -- *--Tamura

--*4-Minanlisoma

--*-Ono

100 --- Iwaki

* Kawamata

-Date

10 - Nihonmatsu

4/4 4/5 4/6 4/7 4/8 4/9 4110 4/11 4/12 4113 4/14 4/1•5 4/16 4117 4/18 4/19 4/20 4/21 4/22 4/23 4/24 4/25

CS-137 (Bq/kg)

100,000

--4--litate10,000-- - T-Kawamata

--*--Tamura--,4--Minamisoma

100-*-Ono

..-- Iwaki

100 -*--KawamataDate

10 Nihonmatsu

10

4/4 4/5 4/6 4/7 4/8 4/9 4/10 4/11 4/12 4/13 4/14 4/15 4/16 4/17 4/18 4/19 4/20 4/21 4/22 4/23 4/24 4/25

5

* Measured from potable water samples at several prefectures.4/26

Tochigi I- 131 (Bq/kg) ND

(Utsunomiya) Cs-i 37(Bq/kg) ND

Ibaraki I- 131 (Bq/kg) 0.45

(Hitachinaka) Cs-137(Bq/kg) ND

Tokyo 1-13 1(Bq/kg) ND

(Shinjuku) Cs- 137(Bq/kg) ND

0 Nuclide analysis result for sea water samples at 330 m south from the discharge point of units 1-4

4/26 14:10

(DSample Ratio ®National SafetyNuclide concentration guideline limitation

(Bq/cm3) (Bq/cm3)

1-131 2.7E-02 0.68 4.OE-02

Cs-134 1.3E-01 2.2 6.OE-02

Cs-137 1.3E-01 1.4 9.OE-02

Nuclide analysis result for sea water samples at 30 m north from the discharge point of units 5&6

4/26 14:30

(DSample (Rt National SafetyNuclide concentration guideline limitation

(Bq/cm3) (Bq/cm3)

1-131 8.6E-02 2.2 4.OE-02

Cs-134 2.IE-01 3.5 6.OE-02

Cs-137 2.3E-01 2.6 9.OE-02

6

Nuclide analysis result for sea water samples at unit 2 screen

4/26

@Sample R o National Safety

Nuclide concentration R/ti guideline(Bq/cm3)limitationqc (Bq/cm3)

Inside 1-131 l.3E+02 3,300 4.OE-02the silt Cs- 134 2.4E+01 400 6.OE-02fence Cs-137 2.5E+01 280 9.OE-02

Outside 1-131 7.7E+01 1,900 4.OE-02the silt Cs-134 1.7E+01 280 6.OE-02fence

Cs-137 1.7E+01 190 9.OE-02

Nuclide analysis result for sea water samples at 15 km offshore points (4/26)

4/26

ai National@Sample Safety guideline

Nuclide concentration R/© limitation

(Bq/cm3) limio(Bq/cm3)

15 km off the 1-131 ... 777 -7 4.OE-02coast of Cs-134 ,, 6.OE-02

Fukushima-Daiichi site Cs-137 9.OE-02

15 km off the 1-131 2.8E-02 0.70 4.OE-02coast of Cs-134 8A4E-02 1.4 6.OE-02Fukushima -Daini site Cs137 8.8E-02 0.98 9.0E-02

15 km off the 1-131 ND - 4.0E-02

coast of Cs- 134 2.8E-02 0.47 6.OE-02Iwasawa Cs-137 2.7E-02 0.30 9.OE-02

7

* Measurement result for sub drain on 1s' floor of turbine building(Bq/cm3) (4/25) (No new dataavailable)

Unit Unit 1 Unit2 Unit3 Unit4 Unit5 Unit6 Unit 1

Sub drain Sub drain Sub drain Sub drain Sub drain Sub drain Deep well

1-131 1.3E+02 6.1E+02 2.OE+O1 9.3E-02 1.3E-01 3.8E-01 ND

Cs-134 5.5E+O1 3.3E+OI 3.9E+00 1.2E-01 2.5E-01 3.3E-01 ND

Cs,137 6.4E+O1 3.7E+01 4.2E+00 1.3E-01 3.1E-01 3.9E-01 ]ND

-8

Pbotpaoam eters of Fukushbia-DaiHNPS*I ;Gauge out of order* 2;Notm onnkred# 3; U nder exam hatbn

28 A pyrt 0600

U n inueoelr I 1 2 1 3 1 4 II1I77] i &

Water h ictbn to RPV

Con tituous fresh w ate rhjtctbn byu shg feed w ate rsystem lb.Fbw iane: lOkm 2/Hr 067L/rn h)Mta sured by" ieporm hsorun entatbit88 AprUot0500)

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F b rae;7.0m/H r 0I7Um i)I easurdbýto pomrary hsurumeeoatbnN8 Apri at 05 00)

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Wittick, Brian

From:Sent:To:


FYI,Al

Hochevar, Albert R. (INPO) [[email protected]]Thursday, April 28, 2011 1:57 AMHuffert, Anthony; Wittick, Brian; Moore, Carl; Chuck Casto; Norwood, Donald; Gepford,Heather; Mitman, Jeffrey; Salay, Michael; Hay, Michael; Meighan, Sean; Garchow, Steve;Reynolds, Steven; CAPT Dirk L Foster; Reid TanakaFW: Press release on Unit injectionUnit 1 injection.doc

Al HoclievarInstitu of Nuclear Power OperationsCell (b)(6) I

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale or forcommercial use. Reproduction of this report without the prior written consent of INPO is expressly prohibited.Unauthorized reproduction is a violation of applicable law. The persons and organizations that are furnishedcopies of this report should not deliver or transfer this report to any third party, or make this report or itscontents public, without the prior agreement of INPO. All other rights reserved.

.011SCLAINTR:rhis"e4ai~idao, oni its attbchrnenis rmiyconlain~,pr IN!'Ct olWANQ InIo-L!n irni tiY xivilenelý. rndev;iThf orwpot-iateJ t- bA to.

N O 0 VVANO. Ihi.; ý-j*;ril iss 1renCi:1 S ¾>Iý1 t'i 0"t- ;hi1i6'- ;; " 4%,i f¾-r i;1Itnd4t J1 WJ ;"t P1, !Ie liýt06?k ofi' any~~~f~r,

i~iI-ýrj ?:, ;11t rpJlar; T: 11. IC~ ~ ieIt s"' 4 C(jrifd t'. S (it thit;ý mai hzI( t rv n h' ý IN~t PC a no 1,;c

~rnrh~bi~ca if ycu arr, rct tnir! lnt~ncea r~cipcwr ot ;.his e-irli: t(e;; Iy O(lv0e. ser'cI;1 cit-.I by ýelurnlerv-i .-nsi; n~ .p ernizni-if iiy VU. nurgina? andi Iny.(i. ;t OruVin!CUI Of TLiV *f.Mali~ andiay.~Cf1

la tr I Y~nk

TEPCO monitoring No.1. reactor

Tokyo Electric Power Company is monitoring one of the reactors at the FukushimaDaiichi nuclear plant to determine whether more water could be pumped inside to coolthe fuel rods.

Tokyo Electric plans to submerge the fuel rods at 2 reactors in water by July this year.

On Wednesday morning, the utility increased the amount of water injected into the No.1reactor from 6 tons per hour to 10 tons per hour on an experimental basis.

As a resudt, the temperature at the top of the reactor was 107.3 degrees Celsius Thursdaymorning, down 24.7 degrees from before the water increase. The temperature at thebottom of the reactor had dropped 12 degrees to 98.5 degrees Celsius.

Pressure inside the reactor containment vessel was also down.

Tokyo Electric says it's not yet knuown how deep the water inside the reactor container is,but that no leakage outside the reactor building has been confirmed.

The utility had initially planned to increase the amount of water injected to 14 tons perhour on Wednesday, but it says it will continue to monitor temperatures and pressurethrough. Thursday evening.

Thursday. April 28, 2011. 12:48 +0900 (JST)

Meighan, Sean

From:Sent:To:


Hochevar, Albert R. (INPO) [[email protected]]Thursday, April 28, 2011 12:47 AMHuffert, Anthony; Wittick, Brian; Moore, Carl; Chuck Casto; Norwood, Donald; Gepford,Heather; Mitman, Jeffrey; Salay, Michael; Hay, Michael; Meighan, Sean; Garchow, Steve;Reynolds, Steven; Bradley Gawbow; CAPT Dirk L Foster; Reid TanakaFW: April 28 Updates20110428 0500 Unit I Drywell Pressure[1 ].pdf; 20110428 0700 Water Levels[1 ].pdf;20110428 Rev.14 Evaluated Water Level in U1 PCV[1].pdf; 20110428 0600 PlantParameters[1].pdf

(b)(4) I

(b)(4)

have relieved him by tomorrow.ThAks,Al

J Also, please add me to your distribution list and remove Lee Gard as I will

Al HochevarInstitute of Nuclear Power OperationsCell (b)(6) I

Restricted Distribution: Copyright© 2011 by the Institute of Nuclear Power Operations. Not for sale or forcommercial use. Reproduction of this report without the prior written consent of INPO is expressly prohibited.Unauthorized reproduction is a violation of applicable law. The persons and organizations that are fumishedcopies of this report should not deliver or transfer this report to any third party, or make this report or itscontents public, without the prior agreement of INPO. All other rights reserved.

From: Ryan, Robert D (WANO)Sent: Wednesday, April 27, 2011 10:55 PMTo: INPO EmergencyResponseCtr (INPO); INPOERCTech; INPOERCAnalysisCc Gard, Lee A (INPO); Maddox, James E. (INPO); Garchow, David F.(INPO); Gambone, Robert L (INPO)Subject: April 28 Updates

Latest information on N2 purge, drywell level, building water levels and temperature / pressure graphs

(b)(4)

Bob

.DISCLAIMER:This e-mail and any of its attachments may contain proprietary INPO or WANO information that is privileged, confidential, or protected by copyright belonging toINPO or WANO. This e-mail is intended solely for the use of the individual or entity for which it is intended. If you are not the intended recipient of this e-mail, anydissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mail is contrary to the rights of INPO or WANO and isprohibited. If you are not the intended recipient of this e-mail, please notify the sender immediately by return e-mail and permanently delete the original and anycopy or printout of this e-mail and any attachments.Thank you.

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Wittick, Brian

From:Sent:To:


Hochevar, Albert R. (INPO) [[email protected]]Thursday, April 28, 2011 12:47 AMHuffert, Anthony; Wittick, Brian; Moore, Carl; Chuck Casto; Norwood, Donald; Gepford,Heather; Mitman, Jeffrey; Salay, Michael; Hay, Michael; Meighan, Sean; Garchow, Steve;Reynolds, Steven; Bradley Gawbow; CAPT DirkL Foster; Reid TanakaFW: April 28 Updates20110428 0500 Unit 1 Drywell Pressure[Il.pdf; 20110428 0700 Water Levels[1].pdf;20110428 Rev.14 Evaluated Water Level in UI PCV[1].pdf; 20110428 0600 PlantParameters[I1.pdf

At

Al HlochevarInstitute of Nuclear Power OperationsCell (b)(6) I


From: Ryan, Robert D (WANO)Sent: Wednesday, April 27, 2011 10:55 PMTo: INPO EmergencyResponseCtr (INPO); INPOERCTech; INPOERCAnalysisCc: Gard, Lee A (INPO); Maddox, James E. (INPO); Garchow, David F.(INPO); Gambone, Robert L (INPO)Subject: April 28 Updates

Latest information on N2 purge, drywell level, building water levels and temperature / pressure graphs

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From:Sent:To:


For review

RST01 HocSaturday, April 02, 2011 3:46 PM

(b)(6)

f

FW: Q385 Rev. 6Q385 Final Rev 6.pdf

From: GE Hitachi Nudear Response Team (GE Power & Water) [mailto:[email protected]]Sent: Saturday, April 02, 2011 3:32 PMTo: RST01 HocCc: [email protected]: Q385 Rev. 6

Rev 6 from GEH

t

From: GE Hitachi Nuclear Response Team (GE Power & Water)Sent: Saturday, April 02, 2011 2:06 PMTo: ý[email protected]'Cc: '[email protected]'Subject: RE: Q385 Rev. 5 1245

Rev 5 from GEH

From: GE Hitachi Nuclear Response Team (GE Power & Water)Sent: Saturday, April 02, 2011 7:50 AMTo: '[email protected]'Cc: '[email protected]'Subject: Q385 Rev. 4 0400

GEH has reviewed the Supplemental Paper on Containment Venting dated 02 April 2011 (Q385 Rev. 4 0400 file)transmitted by the RST on 02 April 2011 at 5:22 AM EDT.

(b)(4)

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II From:

Sent:To:Subject:Attachments:

Hoc, PMT12Wednesday, March 16, 2011 1:55 PMPMTERDS HocFW: Press.Release PDF 16 March 2010 02Press Release PDF 16 March 2010 02.pdf

From: PMT02 HocSent: Wednesday, March 16, 2011 1:10 PMTo: Hoc, PMT12Subject: FW: Press Release PDF 16 March 2010 02

From: PMT02 HocSent: Wednesday, March 16, 2011 1:08 PMTo: Burnell, Scott; Coggins, Angela; (b)(6) ; Jones, Cynthia; Brenner, EliotCc: [email protected]; [email protected]; ;OO Hoc; LIA1 HocSubject: Press Release PDF 16 March 2010 02

Attached as requested by the NRC Chairman is the PDF version of the NRC Protective Measures Team (PMT) doseestimates that support the NRC and State Department press release to expand the evacuation zone to 50 miles

I (b)(5)

It is ourunderstanding that NRC's Office of Public Affairs will attach this PDF containing dose projections to their next pressrelease.

Protective Measures TeamNRC Operations Center301-816-5100

i'

(S&/Jg 2--1

From: HoOtMPwVro A•bert R. (INPO)To: Mitmlan. Jeffrey;h Cato; Rcman. Scottil 'lrk Mitchell, lah; Preson. Hironon: Pla

Richard Reynolds, Stey;n: Temos. Robert.Subject-. FW: Curie Content of Fuel Cores and Spent Fuel Pools

Date: Saturday, April 30, 2011 10:46:22 PM

Attachments: T8 Samole.PDFFukushima - ActViity Release from U1. U2 & U3 reactor copes.ntcfSFP U2 samofinr data 041611.ioWATER TREATMENT.docx

All,Here is some information I received from the Shaw group. I have permission from Bob

Holland to release this to you.Al

Al HochevarInstitute of Nuclear Power OperationsCell J (b)(6) I

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations.Not for sale or for commercial use. Reproduction of this report without the prior writtenconsent of INPO is expressly prohibited. Unauthorized reproduction is a violation ofapplicable law. The persons and organizations that are furnished copies of this report shouldnot deliver or transfer this report to any third party, or make this report or its contentspublic, without the prior agreement of INPO. All other rights reserved.

From: Holland, Robert (Stoughton) [mailto:[email protected]]Sent: Saturday, April 30, 2011 8:17 AMTo: Hochevar, Albert R. (INPO)Cc: Gard, Lee A (INPO); Fadel, Daniel PSubject: FW: Curie Content of Fuel Cores and Spent Fuel Pools

Al,This is info we asked Shaw Radiological folks to provide. Please use as you see fit. I just forwardedTom Stevens' table on SFP data to her for additional info. She had asked for some additional info at

bottom...

V/r BobRobert HollandProject ManagerNuclear ServicesShaw Power Group100 Technology Center DriveStoughton. MA 02072-4705617.589.1256 direct

(b)(6) /cell

61.589.2969 faxrober.ho1!3ndc$shawqro.corn

ShawTM a world of Solutionsn•

wwwoshawgra-com

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From: Ho-hevar. Albert R. (INPO)To: Reynolds, StevenCc: C ; Freeman, Scott Miller, Mar Mitchell, Matthew: P-terson Hirono: Plasse. Richard: Iro

R Mitman. JeffrevSubject: [WARNING: MESSAGE ENCRYPTED]OFF SHORE CONTAMINATION RESULTSDate: Saturday, April 30, 2011 11:25:34 PM

Attachments: OFF SHORE CONTAMINATION Press Releasp.rlocxNUCLIDE SUMMARY.adf

Steve,Off shore contamination results. Not sure if you have this or not. If I am sending you

information that is not useful, please let me know.Al

Al HochevarInstitute of Nuclear Power OperationsCell[ (b)(6) ]

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale orfor commercial use. Reproduction of this report without the prior written consent of INPO is expresslyprohibited. Unauthorized reproduction is a violation of applicable law. The persons and organizationsthat are furnished copies of this report should not deliver or transfer this report to any third party, ormake this report or its contents public, without the prior agreement of INPO. All other rights reserved.

.J, ."

Results of Nuclide Analysis of Seawater <Offshore of Ibaraki Prefecture> Reference

(Data summarized on April 30)

Place of Sampling 3km offshore of 3km offshore of 3km offshore of Oarai 3 km offshore of Hirai 3 km offshore of Hasaki @ Density limit bylTakadokobama shore Kujihama shore shore shore shore the announcement of

Time and Date of At 9:00am At 7:59am At 10:46am At 8:20am At 9:38am Reactor Regulation(Bqlcin3)Sample Collection April 29, 2011 April 29, 2011 April 29, 2011 April 29, 2011 April 29, 2011 (the density imilt in

the water outside ofDetected Nuclides @Densityof Scaling TDensityof Scaling 0Densityof Scaling (Densityof Scaling (Densityof Scaling surrounding monitoredetceNulides Sample Factor Sample Factor Sample Factor Sample Factor Sample Factor areas in the section(Half-life) (Bqc 3) ( ) (Bq/cM 3) ( ) (Bq/ci 3) (@I/) (Bqlcm3) (0@/) (Bq/cm3) (9/0) 6 of the appendix 2)

1-13 1ND ND - ND ND - ND - 4E-02(about 8 days)

Cs-134 F0Ns ) ND ND - ND ND ND 6E-02(about 2 years)

Cs-137 E0Cs17ND ND - ND ND ND 91E-02(about 30 years)

'X O.OE-O means O.Ox 10-'X Data of other nuclides are under evaluation.

Press Release (Apr 30,2011)The results of nuclide analyses of radioactive materials in seawater collected at the offshore area of Ibaraki Prefecture

On April 29, 2011, we started sampling survey of the sea water at 5 pointsin the 3km offshore area of Ibaraki Prefecture.

Today we have conducted nuclide analysis of radioactive materials in thewater sampled on April 29. We have reported the result of the analysis toNISA and the government of Ibaraki Prefecture as per attached.

From:To:Subject:Date:Attachments:

Hayden. ElizabethBrenner. EliotFW: d4awingsMonday, March 28, 2011 4:50:00 PMDocument.pdf

PDF of Bechtel equipment drawings.

----- Original Message -----From: Hayden, ElizabethSent: Friday, March 25, 2011 10:06 AMTo: '[email protected]'Subject: FW: d4awings

Michelle,

Here are the 3 drawings on the equipment that evolved.

Beth HaydenSenior AdvisorOffice of Public AffairsU.S. Nuclear Regulatory Commission

--- Protecting People and the [email protected]

----- Original Message -----From: [email protected] [mailto: ELIZABETH. hayden(nrc.gov]Sent: Friday, March 25, 2011 8:51 AMTo: Hayden, ElizabethSubject: d4awings

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-50 meters

-30 meters

Spray pump500 gpm ,

-10 meters

Booster pump

Ocean

Submerged pump w/ strainer

"-, Educator to add boron

- -500 meters units 1 & 4

.. -700 meters units 2 & 3

*Notes:Also need diesel trucksRobots to enter high radiation areas rot Y, 2

15.24 (SOFT)0 OR40 WASH FIT FlHOSE LENGTHS WITH

7. ON SHMT SLONIRE TWOSL ASCCSSORIES fGE~IITOAILC POWER tull ["I0 PW020A, THREE 10K045FUEL (0115 bnECONNEIED AND W00HSTATION P110204.

00~2 VT3WO ELIEVAISO (00045 FLIEL TIlNS FOR EACH PUD230PLWd EWM. 51610 2 10 BESEALED TO (TOO $1511a"0 em0u SNIALL TAKl

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EXAMPLE SHOWN IS ONE1 TRA•N

600. METERS 150 mm HOSE FOR UNIT 1

800 METERS 150 mm HOSE FOR UNIT 2

NEED: 800 VEIERS 150 mm HOSE FOR UNIT 3

600 METERS 150 mm HOSE FOR UNIT 4

75 METERS 150 mm HOSE FOR EACH CRANIBOOM OR CONCRETE PUMPING RIGARRANGEMENT

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From: Hoc, PMT12Sent: Friday, April 29, 2011 11:26 AMTo: OST01 HOCSubject: FW: DRAFT Document - Recommendation on Update to Travel Advisory - Official Use

OnlyAttachments: OUO DRAFT Rec for Travel Advisory Update 29Aprilll.docx

From: Hoc, PMT12Sent: Friday, April 29, 2011 11:21 AMTo: Hoc, PMT12; Bentz, Julie A.; [email protected]; [email protected];[email protected]; Keith, Sam (ATSDR/DTEM/ATB); [email protected];[email protected]: McDermott, Brian; Evans, Michele; Skeen, David; Milligan, Patricia; Brock, KathrynSubject: DRAFT Document - Recommendation on Update to Travel Advisory - Official Use Only

Sorry...here is the attachment.

From: Hoc, PMT12Sent: Friday, April 29, 2011 11:09 AMTo: 'Bentz, Julie A.'; '[email protected]'; '[email protected]'; '[email protected]';'Keith, Sam (ATSDR/DTEM/ATB)'; [email protected]'; '[email protected]'Cc: McDermott, Brian; Evans, Michele; Skeen, David; Milligan, PatriciaSubject: DRAFT Document - Recommendation on Update to Travel Advisory - Official Use Only

Hello Interagency Partners,

The attached document provides draft language to assist with communications (b)(5)

(b)(5)

NRC wants to collect any critical comments (show-stoppers) from the Interagency (one set of comments per agency) byno later than COB on Monday 2MAY11 ET, so that NRC may integrate/resolve any issues raised and finalize thedocument. Once the document is finalized, the NRC team in Japan will provide the document to the Ambassador andprovide the team's current assessment of the decision considerations.

NRC would be happy to discuss your comments either individually or in a conference call, perhaps on Monday if there isinterest. Please direct all replies/comments to PMT12, Kathryn Brock, and Brian McDermott ([email protected],[email protected], [email protected]). Or, we may be reached by telephone through the OperationsCenter at 301-816-5100.

Sincerely,

Kathryn BrockUS Nuclear Regulatory CommissionProtective Measures Team (PMT)

OFFICIAL USE ONLY

(b)(5)

DRAFT as of 09:15 hrs 29 April 11

(b)(5)

DRAFT as of 09:15 hrs 29 April 11

a

(b)(5)

DRAFT as of09:15 hrs29 Apri 11

From: OST01 HOCSent Friday, April 29, 2011 4:25 AMTo: RST01 Hoc; Hoc, PMT12Subject: FW: OUO FW: April 28 briefing notes, excel spreadsheet and radiation survey map OUO

Attachments: April 28 Ryan 6 pm briefing notes.doc; TEPCO Sumarry Rev.102 final April 28(1).xls;20110427 0850 Facility Area Survey Data[1].pdf

From: ET02 HocSent: Friday, April 29, 2011 4:02 AMTo: OST01 HOCSubject: FW: OUO FW: April 28 briefing notes, excel spreadsheet and radiation survey map OUO

From: ET01 HocSent: Friday, April 29, 2011 4:01:35 AMTo: ET02 HocSubject: FW: OUO FW: April 28 briefing notes, excel spreadsheet and radiation survey map OUOAuto forwarded by a Rule

From: LIA08 HocSent: Friday, April 29, 2011 4:01:30 AMTo: ET01 HocSubject: OUO FW: April 28 briefing notes, excel spreadsheet and radiation survey map OUOAuto forwarded by a Rule

Liaison Team CoordinatorUS Nuclear Regulatory Commissionemail: [email protected] Ph: 301-816-5185

From: Wittick, BrianSent: Friday, April 29, 2011 2:22 AMTo: Emche, Danielle; LIA08 HocSubject: FW: April 28 briefing notes, excel spreadsheet and radiation survey map

FYI

From: Hochevar, Albert R. (IN PO) [mailto:[email protected])Sent: Thursday, April 28, 2011 5:44 AMTo: Huffert, Anthony; Wittick, Brian; Moore, Carl; Chuck Casto; Norwood, Donald; Gepford, Heather; Mitman, Jeffrey;Salay, Michael; Hay, Michael; Meighan, Sean; Garchow, Steve; Reynolds, Steven; CAPT Dirk L Foster; Reid TanakaSubject: April 28 briefing notes, excel spreadsheet and radiation survey map

FYI,

, A]

Al HochevarInstitute of Nuclear Power OperationsCellI (b)(6) I (,P

Restricted Distribution: Copyright © 2011 by the Institute of Nuclear Power Operations. Not for sale or forcommercial use. Reproduction of this report without the prior written consent of INPO is expresslyprohibited. Unauthorized reproduction is a violation of applicable law. The persons and organizations thatare furnished copies of this report should not deliver or transfer this report to any third party, or make thisreport or its contents public, without the prior agreement of INPO. All other rights reserved

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cODy or prinout of .his e-mail anti any anacniments.Th•ia you.

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Wittick, Brian

From:Sent:To:


FYI,Al

Hochevar, Albert R. (INPO) [[email protected]]Thursday, April 28, 2011 5:44 AMHuffert, Anthony; Wittick, Brian; Moore, Carl; Chuck Casto; Norwood, Donald; Gepford,Heather; Mitman, Jeffrey; Salay, Michael; Hay, Michael; Meighan, Sean; Garchow, Steve;Reynolds, Steven; CAPT Dirk L Foster; Reid TanakaApril 28 briefing notes, excel spreadsheet and radiation survey mapApril 28 Ryan 6 pm briefing notes.doc; TEPCO Sumarry Rev.102 final April 28(1).xls;20110427 0850 Facility Area Survey Data[1].pdf

Al HochevarInstitute of Nuclear Power OperationsCell F ()6


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" N2 purging of the Unit 1 Drywell continues. TEPCO increased injectionflow to the primary containment vessel to 10 m3/hr at approximately10:00 am Wednesday morning. Reactor vessel temperature, drywelltemperature and pressure were observed to decrease after the start ofthe injection increase. The rate of change of these parameters slowedthis morning. TEPCO intends to stop the increased injection ratebefore drywell pressure reaches atmospheric.

* The robot is scheduled to enter the Unit 1 reactor building today tocheck for possible leakage following the increase in vessel injectionrate.

" Transfer of highly radioactive water from Unit 2 to the CentralizedRadioactive Waste Treatment Facility continues at a rate of 250tons/day. Level in the Radioactive Waste Facility has risen 1055 mmsince the start of transfer.

* Unit 2 trench level has decreased only slightly since Monday and isnow 900 mm from the top of the trench. Unit 3 trench level hasincreased an additional 20 mm and is now 950 mm from the top.

" Unit 4 turbine building water level increased 50 mm and is at 3050 mm(1.2 m above floor level). Unit 3 turbine building water level remainedsteady at 3000 mm.

" Eighty five tons of water was added to the Unit 4 Spent Fuel Pool(SFP) yesterday. No addition to the Unit 4 SFP is scheduled for today.Sixty tons of water is scheduled to be added to Unit 2 SFP today.

* After reexamining the recent differences between observed water levelincrease and calculated water level increase following water additionsto the Unit 4 SFP, TEPCO now believes the Unit 4 SFP pool may notbe leaking. The condition of the Unit 4 SFP will continue to beevaluated closely by TEPCO.

" A water sample for radionuclide analysis is scheduled to be taken fromthe Unit 4 SFP today.

I

TEPCO released their plan for radioactive water treatment today.Ultimately it will have a capacity of 1,200 m3/day. A reservoir capacityof 31, 400 m3 will be installed by early June. Additional capacity will beadded later. Currently there is an accumulation of 87,500 m3 ofradioactive waste water at the station. Injection into the reactorpressure vessels is adding to this total daily.

Unit Status

* In Unit 1, non-borated fresh water injection into the main feedwater linewas increased in steps up to 10 m3/hr yesterday on a temporary basis.Future injection flow will be determined following analysis of dataobtained during the injection flow increase. Comments on parameters:

- Reactor pressure decreased to .415 MPa abs (60 psig).

- Feedwater nozzle temperature is considered to be suspect butdid show a decrease of approximately 25 C (77F).

- Reactor vessel lower decreased approximately 12 C to 98.5 C(209 F)

- Drywell and Torus pressure decreased to .125 MPa abs (18 psia).


" In Unit 2, injection of non-borated fresh water using the low pressurecoolant injection continues at approximately 7 m3/hr. Comments onparameters:


- Feedwater nozzle temperature was steady at 120 C(248 F)




* In Unit 3, of non-borated fresh water using the low pressure coolantinjection continues at approximately 6.8 m3/hr. Comments onparameters:



- Reactor vessel lower temperature was steady at 110 C (230 F)



2

Dose and Dose Rates

" As reported yesterday, a female employee received a cumulativeradiation dose of approximately 18 mSv during the first quarter of 2011.This exceeds the maximum allowable dose for a female of 5 mSv/3months. Upon examination it was determined that the woman received13.6 mSv internal exposure. The woman was working in a building thatwas contaminated by the hydrogen explosion on March 12 and wasnot wearing a protective mask. Two other females working in the samebuilding may have also exceeded their exposure limits.

* Overall site dose rates are stabilizing or decreasing slightly. Forexample:

The last reading reported at the main gate was 48 pSv /hr (4.8mrem/hour) and 22 pSv /hr (2.2 mremlhour) at the west gate.

The side of the administration building facing the unitsdecreased slightly to 430 pSv/hr or 43 mrem/hr.

3

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ML13140A210.pdf - Nuclear Regulatory Commission

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Transcript of ML13140A210.pdf - Nuclear Regulatory Commission