ML102710333
| 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:
Sent:
To:
Subject:
Attachments:
Categories:
Lake, Louis Thursday, November 12, 2009 7:27 AM Khanna, Meena; Boyce, Tom (NRR); Sykes, Marvin; Franke, Mark; Farzam, Farhad; Thomas, George; Jessup, William; Kuntz, Robert; Tsao, John; Reyes, Rogerio; Lake, Louis; Carrion, Robert; Masters, Anthony; nausdj@ornl.gov; Orf, Tracy; Paige, Jason; Saba, Farideh FW: CR-3 Reactor Building Design Model CR3_ModelOverviewNRC.ppt 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, Sammy; Zimmerman, Tony; McCabe, Brian; Miller, Garry; Powell, Sid; Herrin, Dennis W.
Subject:
CR-3 Reactor Building Design Model Paul; Radford, 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 In this 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 Crystal River 3 Containment FEA Model Progress Report
- Analysis Model Status
- Required capabilities defined for model
- Analysis approach defined
- Load cases identified
- Geometry model complete
- Initial model checks completed
- Analyses underway CR3 FEA Model
- Snrrmebo plahe 0 150 aegr0es midway Betwesen tBhns 3 t 4/ 1 & 6 Opernin. r', Dsramae & tr Hatch Modeled ExiiiiAly
- eas eferhmet ol allrbrrnol Ninoe and Ease m"Aw independolerlntly
- Srntrrelbd bourn h awl. buialess gesometry
- Constraint erfrualioni used ta licn dome and nng girder fm nrnntsnr nfficiency r
amuau esluaetin used to Mooa] 5100054 surfaceStit CAtse htch~
- Lnnnrl srl
- Shelf tresh veh vaurelta th~ickness
- Stared srioest w545 coairmofra Unnitt surlace
- ~
d rnnuedinle f tgmu ld"Man nneadnln nexplinll for 51045 Aan re-rnnseolrun
- verianln TooendaS nlunled enjatlcoy tar "Ieneane and m-eansioring Dom trandemues trdortere wnleres uith frce ponied4 tn %itl nmodel CR3 FEA Model
" Gravity Analysis solved for Model check
- Symmetry boundary ant full base fixity D-splacement Plots Stress Plots
" Tendon Loads solved for Model check
- Symmetry Doundaty and lull base fixity (will add scil springs)
-- Displacement Plots
- Stress Plots
- Tendon Force Plots Preliminary Data
-- Removed Hole
- Removed Tendons Tu
,4 9 Concrete Geometry Based on Gilbert Associates drawings - 1970 Tendon Geometry Based on Prescon drawings - 1971 St5
~.X~...A n.
-. 51.0'~. 5
55 \\~ ~
C, r~'~ "~
t~
- 1*1 t~""
/
o'.,-it.r-1
3/17/201.0 P
Ring Beam Simp ified Axisymmeiric FrA Mesh L ;;.,
- Core Building Geometry - FEA Mesh Hood Tendo* Locations Defined Core Building Geometry -Buttresses Liner D
Dome Tendon Loss assumptions:
- Flicrioncoofficien t fDc=0 t6
.. Wo.. eValue; :
t3 p
bo 5, 00003 EndorFco:
165k5inps(1t2
-5l -tOyears) 2
3/17/2010 Tendon Loading
- The tendons are preloaded to a piroscrioed load maqntituoe.
- The applicatron at the tendon toads is acnleved in the analysis using Mnillet Str~Ial inptt
- An empirical formula haseen OCeOnOv DO to Xacc;or or t
0 lOS 0t load
,IS Oe distance from the anchor "IIrI MIredAWS:
Where:
P = P,
- a
= irf'tian antle
- k I worale coefricnmn I
-* rirta ru fnr arrCtr pore Tendon rbeO*ds used in analyorse It*,35K*(1t,2149r0O 40ayear) 9, --
1635 t
KW O(1,190M lbOtt40 years)
Dome Tendon Analysis
- Geometry profite mrtCheS ail tendwos !hat inrtersect the ' model
- 3 layers of tendons defined: 1t0. 200 arrd 300 sefres
" FEA Model & Boundary Conditions All f'tOdS ined in all dwrectron.
Onrtial strair' deftned to represent Tendon LoaJing and Loss Forces to be pored to glosal mooel
- Dorne Force Vectors AN Dome Force Vectors AN
" Dome FEA AN 3
3/17/201-0 P
PEA Model - Vertical and Hoop Tendons 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 Existing Design Cases for Comparison
-. Gravity (.95 G)
Internal Dead Load (,00 pat)
. Tendons ( 1635 kips I tenool)
- trthe r*-r, tnternali Pressure (55.0 Ps)
Wind Pressure (0,56 psi)
Seismic
, Accident Thermal
- Planned Analysis Steps Dead Load + Tendons
- Remove Hoop + Vetical Tendons in SGR Opening
- Remove SGR Opening
- Detamination Remove Additional Hoop &
Vertical Tendons
- Replace tIe SGR Plug tGrout
/ Epooy Repair Rotension Tendons
.,SAVE Path Dependent Model tot Slarting point to Run 5 Controlling Design cases Design Basis Controlling Load Steps
" Restart the Re-tensioned Model and solve tne following Controlling Load Steps
.5 Internal Pressune ý Accident Thermal
.25 Wind + 1.25 Pressure + Acciident Thermal 1.25 EantlrqnaKe - 1.25 Pressure, Accident Thermal
- 2,0 Wind + Pressure - Accident Thermal
- SSE Eertnruake + Pressure + Accident Thermal
" Restart with Accident Thermal with plastic material properties for liner such that load capability limited to 36 ksi stress.
" Run Comnparison to onginal building elastic design results to show repair has restored building to orginal condition Is 5