ML103330344

E-Mail from Gilanshahi to Gilanshahi, Presentation, Crystal River 3

ML103330344
Person / Time
Site:	Crystal River
Issue date:	09/08/2010
From:	Gilanshahi N N NRC/NRO/DE/SEB2
To:	Gilanshahi N N NRC/NRO/DE/SEB2
References
FOIA/PA-2010-0290
Download: ML103330344 (21)

Text

Gilanshahi, Nikki From: Gilanshahi, Sent: Tuesday, June 08, 2010 3:03 PM To: Gilanshahi, Nikki

Subject:

FW: Presentation Attachments:

Crystal River 3.ppt 1-7-2010pdf:

Jan 6 Tech Consistency (1).pdf From: Gilanshahi, Nikki Sent Mcnd~ v 1;niiarv 11 2010 2:25 PM To. (b)(6) 1

Subject:

FW: Presentation FYI: From: Gilanshahi, Nikki Sent: Monday, January 11, 2010 8:47 AM To: Hawkins, Kimberly; Riddick, Nicole; Chakrabarti, Samir; Chakravorty, Manas; Gilanshahi, Nikki; Jeng, David; Kazi, Abdul; Xu, Jim; Chuang, Tze-Jer; Jain, Bhagwat; Ma, John; Park, Sunwoo; Patel, Pravin; Tegeler, Bret; Thomas, Brian;Thomas, Vaughn; Valentin, Milton

Subject:

Presentation Good morning All;Please find attached copy of Jan6 and Jan 7 Crystal River presentation and Please let me know, If you have any questions in this regard.Thanks, 94onec (301) 415-3801 tnfornia:uQ, i n-In I i"I &.ni acom W VWs fodjomga 1AL441' I#m I ý I ý I IN:' slow Fowft 2=0-O9L%4 I USNRC People and the /.,ironmr, Crystal River Unit # 3 Containment elaminatio\: ';z ,' l ...Nikki Gilanshahi Structural Engineer NRO/DEISEB2 1/7/2010 1 U.S.NRC Peofple ard thr Purpose: To educate the staff and make them aware of the recent discovery, Crystal River 3, Steam Generator Replacement containment delamination.

Outcome: Staff can apply the insights from this operating experience to our new reactor reviews after presentation.

Safety Significance:

Concrete delamination Could compromise the structural integrity of the containment building, which inturn could potentially release radioactivity to the environment.

==

Conclusion:==

Adequate Containment Design review and good quality of Construction inspection are essential to ensure safety of our future Nuclear Power Plants.'I U.S.NRC N Peropk an (hhe b.minnimenI Crystal River 3# Pressurized Water reactor s Location:

Crystal River Florida# Commercial Operations Electricity Generation since 1976 for Florida* Planned Outage* Routine refueling scope Off line maintenance and fuel once every Extended Power Uprate (EPU)- Phase 2 2 years 3

'U.SNRC NaigPro,4fw

~pke awl the birmoln~il The most importantrole of nuclear containments is toprevent radioactive substances from leaking outactingas*

finabararci in nuclearpowerplants 4

• ;; U.SNRC Containment Opening Lifting and Rigging Cutting and welding 5 U.SNRC Niertflis 1Prcapi and thr EndvinnunetI Steam Generator Replacement Opening Sequence & Identification of elamination 6

cU.SNRCI I 'Note. Tendon depicton is for illust*e puoses and is not an exact scale A t f ,~4 ,~I-I 1ý0 VI 7 U.S.NRC Actual Delamination Delamination and Cause of Delamination Common causes of Delamination occurs in reinforced concrete structures subject to reinforcement corrosion, inadequate use of concrete material, and more 8

)U.Sn4P' pea 4~ ,uiwNtRC They were Approximately 74 Possible failure mode which 1/3 20,2009 remaining and ongoing investigation as of Nov, INVESTIGATION APPROACH 9 I*1 I Prli. Proplo awl thCa e Root Cause Analysi's e External Events o Operational Events , Inadequate Containment Cutting , Inadequate Concrete-tendon interactions Shrinkage, Creep and Settlement Chemically or Environmentally induced aging Inadequate use of Concrete Materials Inadequate Concrete Construction Inadequate Concrete Design due, to High Local Stress 70 30 20 I0 o ...__I_.....'W4 Eve I Ur~e Coraeý DF dntor~?z 1Z2 z 7zz Tz I 6 10 2 U.S,NRC Prplce tini and thr Etw irviini,,.

Condition Assessment Activities Completed or Planned Determine Extent of Condition Characterize the extent of delamination at the SGR opening Determine condition of other portions of structure s Non Destructive Testing (NDT) of Containment Wall Surfaces Use of Impulse Response (IR) Method Comprehensive on external exposed surfaces Accessible areas in adjacent buildings* Concrete Cores Used to confirm IR results (over 80 cores)Visual examination of core bore holes with boroscope to identify if delamination present s ASME Section Xl IWL visual inspection (affected areas)0 Containment Dome Inspections NDT IR scans in segment above the SGR opening Concrete cores with boroscope examination of bore holes Physical survey with established benchmarks 11

'I U.S.NRC Condition Assessment IR Equipment Primary test method used in this evaluation o IR Performed in the Field I L "U.SNRC PnnletiiZ Prople and the Non Destructive Testing (NOT Impulse response (M) method The Impulse Response method can be applied to a variety of situations that require rapid, accurate, and cost-effective nondestructive condition assessment.

Which can be used to test relatively rough concrete surfaces;its fast output, Can detect the delamination of concrete & concrete around steel reinforcement, but, it dose not provide the depth of the delamination.

SOUNoD S.AB -Gooo SuPPoRT/ 7 V77 " 0 DELAMINA'TED SLAB.Frequency

ýHz)High Speed Data Acquisitlion

.Impact Geophone, Hammer V Fr eqency Hz)/ _Higl Speed Data Acquisition

." lone Hammer 1.1----41 F 13 SU.SNRC Nea*ii People and ihe EnurminnewI Ground Penetrating Radar (GPR) Equipment Locates internal features (rebar, tendon conduits, etc.)GPR Performed in the Field 1~Y ' 9~ ~14

/U.S.NRC Ground Penetrating Radar Ground Penetrating Radar technology is ground radar that acts as a type of ground sonar and provides critical information regarding anything that could be located below the surace. It is sometimes called ground sonar, Concrete scanning, surface penetrating radar or ground radar'15

, U.S.NRCProltding Prople and the n'virwrmeinl Concrete Cores Used to accomplish the results and confirm IR results( Over8O cores)Visual examination of core bore holes with boroscope To identify if delamination present Examination

-Inward View Examination

-Side View C ore 51, Gap I Depth 5.114" Gap 1 Width Less than 118"-'-I , ýrjý16 N~tectin Prople a~nd the Eniru.rnnment IE Equipment Ability to determine depth of delamination IE Performed in the Field 17

.USNRC PNrt it.r I-nple ard ih/e h!wninnffrf Delamination has only been observed in core bore holes (s) boroscopic exams in the buttress 3-4 span, as accurately predicated by IR Red: Core bore with delamination Green :Core bore not delamina ted White: To be Core bored A B C-11ý I -I -II I T Tu!~ne I I I B~d~,Concluson -Delan'~nao NS onlY b4nePWedsh c~elore bro *s)bomscooc exanis 0 (re Mmls 3.4 Span as uwraelyPrilrd b Buttress #Ityolca!)re 18 U.SNRC Prvoteri. and the.

This Issue is still under Investigation by a team of Industry experts hired by Licensee.Possible--Repai'r:

Delamination Removal and Replacement.

==

Conclusion:==

Adequate Containment Design review for New Reactors and good quality of Construction inspection are essential to ensure safety of our future Nuclear Power Plants.19 U.S.NRC prohi4-din People and the Efivrunmc',t Questions I~20