ML102710333

E-Mail from Lake to Khanna, CR-3 Reactor Building Design Model

ML102710333
Person / Time
Site:	Crystal River
Issue date:	11/12/2009
From:	Lake L NRC/RGN-II
To:	Boyce T, Meena Khanna, Marvin Sykes Office of Nuclear Reactor Regulation, NRC/RGN-II
References
FOIA/PA-2010-0116
Download: ML102710333 (30)

Text

Masters, Anthony From: Lake, Louis Sent: Thursday, November 12, 2009 7:27 AM To: Khanna, Meena; Boyce, Tom (NRR); Sykes, Marvin; Franke, Mark; Farzam, Farhad; Thomas, George; Jessup, William; Kuntz, Robert; Tsao, John; Reyes, Rogerio; Lake, Louis; Carrion,

Subject:

Robert; Masters, Anthony; nausdj@ornl.gov; Orf, Tracy; Paige, Jason; Saba, Farideh FW: CR-3 Reactor Building Design Model Attachments: CR3_ModelOverviewNRC.ppt Categories: Perform Review See attached presentation for today's conference call scheduled for 10:00am.

Lou Lake From: Herrin, Dennis W. [1]

Sent: Wednesday, November 11, 2009 8:23 PM To: Paige, Jason; Lake, Louis Cc: Saba, Farideh; Reyes, Roger; Williams, Charles R.; Dyksterhouse, Don; Fagan, Paul; Radford, Sammy; Zimmerman, 5 Tony; McCabe, Brian; Miller, Garry; Powell, Sid; Knott, Ronald

Subject:

RE: CR-3 Reactor Building Design Model Mr. Paige, As promised, please find attached the information developed by MPR Associates, Inc., to support the conference call on the CR-3 Reactor Building design model.

Lead Engineer - Licensing & Regulatory, Programs Progress Energy Florida, Inc.

Crystal River Unit 3 352-563-4633 Voicenet 240-3299 p bennis.Herrin@p*nmail~com From: Herrin, Dennis W.

Sent: Wednesday, November 11, 2009 3:08 PM To: Jason Paige (Jason.Paige@nrc.gov); Louis Lake (Louis.Lake@nrc.gov)

Cc: Farideh Saba (farideh.saba@nrc.gov); Reyes, Roger; Williams, Charles R.; Dyksterhouse, Don; Fagan, Paul; Radford, Sammy; Zimmerman, Tony; McCabe, Brian; Miller, Garry; Powell, Sid; Herrin, Dennis W.

Subject:

CR-3 Reactor Building Design Model Mr. Paige, Mr. Louis Lake (NRC Special Inspection Team Lead) has requested that a conference call be scheduled for 10:00, on November 12, 2009, between the NRC (Special Inspection Team and NRR), the CR-3 Reactor Building Concrete Delamination Root Cause Team and MPR Associates, Inc. The purpose of this conference call isto discuss the CR-3 Reactor Building design model. The following conference call information will be used:

AT&T Toll-Free number: (877) 848-7030 Acce %bn Inthis rcord was do 'A I

SJ Information being developed by MPR Associates, Inc., to support the conference call will be provided as soon as-it is available.

DemzWiW. 9(m&i Lead Engineer - Licensing & Regulatory Programs Progress Energy Florida, Inc.

Crystal River Unit 3 352-563-4633 Voicenet 240-3299 Dennis.Herrin@pqnmail.com 2

3/17/2010

• Analysis Model Status

- Required capabilities defined for model

- Analysis approach defined

- Load cases identified

- Geometry model complete

- Initial model checks completed Crystal River 3 - Analyses underway Containment FEA Model Progress Report CR3 FEA Model CR3 FEA Model

" Gravity Analysis solved for Model check

- Symmetry boundary ant full base fixity

• Snrrmebo plahe0 150aegr0es midwayBetwesen tBhns 3 t 4/ 1& 6 Opernin.r',Dsramae&tr HatchModeled ExiiiiAly D-splacement Plots Stress Plots

• easeferhmet ol allrbrrnol NinoeandEasem"Aw independolerlntly " Tendon Loads solved for Model check

• Srntrrelbd bourn h awl. buialess gesometry

- Symmetry Doundaty and lull base fixity(willadd scil springs)

• Constraint erfrualioniused ta licndomeandnnggirderfm nrnntsnrnfficiency

-- Displacement Plots r esluaetin amuau usedto Mooa]5100054 surfaceStit CAtsehtch~

• Lnnnrlsrl - Stress Plots .. .

• Shelf tresh vehvaureltath~ickness - Tendon Force Plots

• Staredsrioest w545coairmofra Unnittsurlace

• ~rnnuedinle d Preliminary Data ftgmu ld"Mannneadnln nexplinllfor51045 Aanre-rnnseolrun

-- Removed Hole

• verianlnTooendaS nlunled enjatlcoy tar"Ieneaneandm-eansioring trdortere Dom trandemues wnleres uith frce ponied4 tn%itl nmodel - Removed Tendons Tu

,4

. Tendon Geometry Based on Prescon drawings - 1971 9 Concrete Geometry Based on Gilbert Associates drawings - 1970 St5

~ .X~...A n.

• -. 51.0'~.5 55 \~ ~ ..........................

o'.,-it.r-C, r~'~ "~ t~

• 1*1 t~""

/

1

3/17/201.0 P

Ring Beam Simp ified Axisymmeiric FrA Mesh L ;;.,

• Core Building Geometry - FEA Mesh . Core Building Geometry -Buttresses Hood Tendo* Locations Defined

. Liner Dome Tendon Loss assumptions:

D

- Flicrioncoofficien t fDc=0t6

.. Wo.. eValue;: pt3 bo5, 00003 EndorFco: 165k5inps(1t2 -5l -tOyears) 2

3/17/2010 Tendon Loading Dome Tendon Analysis

• The tendons are preloaded to a piroscrioed load maqntituoe.

• The applicatron atthe tendon toadsis acnlevedin the analysis using

• Geometry profite mrtCheS ail tendwos !hat inrtersect the ' model MnilletStr~Ial inptt - 3 layers oftendonsdefined: 1t0. 200 arrd300 sefres

• An empirical formula haseen OCeOnOv DOto Xacc;oror 0 0t load t lOS " FEA Model & Boundary Conditions

,IS Oedistance fromthe anchor "IIrIMIredAWS:

All f'tOdS ined in all dwrectron.

Onrtialstrair' deftnedto represent Tendon LoaJing and Loss Where: P=P ,

Forces to be pored to glosal mooel

• a =irf'tian antle

• k I worale coefricnmn I -* rirta ru fnr arrCtr pore Tendon rbeO*dsused in analyorse

-

• It*,35K*(1t,2149r0O40ayear) 9, -- t 1635 years)

KWO(1,190M lbOtt40

. Dome Force Vectors

• Dorne Force Vectors AN AN

" Dome FEA AN 3

3/17/201-0 PEA Model - Vertical and Hoop Tendons P o FEA Model - Verrca and Hoop Tendons Supports v FEA Model Materials Define Tendon Groups 22 Hoop Tendon Forces AN e Equipment Hatch Model 2~

4

3/17/2010 SGR Opening Model

• SGR Opening and Tendons removed Planned Analysis Design Basis Controlling Load Steps Existing Design Cases for

• Planned Analysis Steps

" Restart the Re-tensioned Model and solve tne following Comparison - Dead Load + Tendons Controlling Load Steps

-. Gravity (.95G) - Remove Hoop + Vetical - .5 Internal Pressune ý Accident Thermal

- Internal Dead Load (,00 pat) Tendons in SGR Opening

.25 Wind + 1.25 Pressure + Acciident Thermal

. Tendons ( 1635 kips I tenool) - Remove SGR Opening - 1.25 EantlrqnaKe - 1.25 Pressure , Accident Thermal

- trthe r*-r, - Detamination

- 2,0 Wind + Pressure - Accident Thermal tnternaliPressure (55.0 Ps) Remove Additional Hoop&

Vertical Tendons - SSE Eertnruake + Pressure + Accident Thermal

- Wind Pressure (0,56 psi)

Seismic - Replace tIe SGR Plug tGrout/ Epooy Repair " Restart with Accident Thermal with plastic material properties for

, Accident Thermal liner such that load capability limited to 36 ksi stress.

Rotension Tendons

. ,SAVEPath Dependent Model tot Slarting point to Run 5 Controlling " Run Comnparison to onginal building elastic design results to show Design cases repair has restored building to orginal condition Is 5