ML16175A606

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Containment Delamination Update
ML16175A606
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/20/2009
From:
Progress Energy Florida
To:
Office of Nuclear Material Safety and Safeguards
References
Download: ML16175A606 (83)
v • d • e


Text

November 2Qth 2009

  • Introduction
  • Plant Overview
  • CR3 Containment Design Features
  • SGR Opening Sequence & Identification of Delamination
  • Investigative Approach
  • Condition Assessment
  • Root Cause Analysis (RCA)
  • Operational Experience (OE)
  • Design Basis Analysis (OBA)
  • Repair Approach
  • Summary Comments I Questions 2 ~

Progress Energy

  • Babcock and Wilcox Pressurized Water Reactor
  • 2609 MWth
  • 838 MW8
  • Commercial Operations began 1976 3 ~

Progress Energy

2009 Crystal River 3 Outage Overview Building a nuclear future for Florida customers

  • Routine refueling scope
  • Off line maintenance and fuel for 2 years
  • Extensive steam plant work
  • Taking advantage of longer OTSGR duration
  • Steam plant efficiencies
  • Part of total,..; 15°/o Uprate 4 ~

~

~ Progress Energy

  • Containment Opening
  • Lifting and Rigging
  • Cutting and welding 5 ~

~

~ Progress Energy

  • Generator Replacement
  • Moisture Separators
  • MSR Drain Coolers Lube Oil Coolers Feed Water Heaters lso-Phase cooling 6

~ Progress Energy

CRYSTAL RIVER #3 DESIGN FEATURES

~

~ Progress Energy

Liner Concrete Tendons (horizontal)

Barrier # 3 - Containment Liner Barrier # 2 - Reactor Vessel & Coolant Piping Barrier # 1-Cladding Enclosing The Fuel 8 ~

Tendon depiction is for illustrative purposes and is not an exact scale

9 CR3 Containment Dimensions Dimension Value Containment Outside 137 ft 0.75 in Dimension (OD)

Dome Thickness 36in Basemat Thickness 12 ft 6 in Liner Thickness 0.375 in Wall Thickness 42in Buttress Wall Thickness 5 ft 10 in Vertical & Hoop Conduit OD 5.25 in

  1. of Vertical Tendons 144
  1. of Tendon Hoops 94
  1. of Tendons per Hoop 3
  1. of Prestressed Dome 123 Tendons MECHANICAi..

sc.<irCLonc;

  • ~..

l90 lDN REACTOR BUlLDlNG CRANE CONHWL ROD DRJVE MECHAN[SH HANDLING CRANE SUPPCRT RN-Gl9 TRAPELO TYPE TA-f>:l(V)

OETECraR I. A)(- 50 IJAL L IHi!ACKE T KJUNT£ D s*-o* ABOVE IUilf

~.....

SGR OPENING SEQUENCE &

IDENTIFICATION OF DELAMINATION 10~

Progress Energy

B 11 ~

SGR Opening Dimensions

@ Liner 23' 6" x 24' 9"

@ Concrete Opening 25' O" x 27" O"

~

~ Progress Energy

12~

~

~ Progress Energy

14~

~

~ Progress Energy

Note - Tendon depiction is for illustrative purposes and is not an exact scale 15

INVESTIGATION APPROACH a

16~

~

~ Progress Energy

Root Cause Analysis Performance Improvement International (Pl/)

Condition Assessment Construction Technology Laboratories {CTL)

DrChon Chiu Design Basis Analysis MPR Associates, Inc Repair Alternatives Analysis Structural Preservation Systems (SPS)

Implement Repairs Contractor - TBD 17 Analysis Cross Check Progress Energy

Condition Assessment & Laboratory Testing

  • NDT - Construction Technology Laboratories (CTL)
  • Labs - MacTec, Soil& Materials Engineers (S&ME)
  • Other Field Data - Sensing Systems, Inc; Core Visual Inspection Services (Core VIS), Nuclear Inspection & Consulting, Inc; Precision Surveillance; Gulf West Surveying Inc; AREVA
  • Root Cause Analysis
  • Lead - Performance Improvement International (Pl/)
  • Owner's Support - Worley Parsons, Bechtel 18~

~

~ Progress Energy

Design Basis Analysis

  • Owner's Support - Worley Parsons
  • Repair Analysis
  • Lead - Structural Preservation Systems (SPS)
  • Owner's Support - Wiss, Janney, Elstner, Inc (WJE)
  • Industry Support
  • Exelon, SCANA, and Southern Company 19~

~

~ Progress Energy

I Technical Analysis Root Cause Design Basis Analysis Analysis Condition Repair Analysis Assessment 20 Containment Project Manager I

I I

Interfaces Project Controls NEl/ INPO Contract Administration NRC Scheduling

- Public I Media -

Financial SMC/ Board Oversight &

Independent Review PNSC NSRC Nuclear Oversight CEO

& Board Nuclear Safety Oversight Committee Containment Sub-Committee

Nuclear Safety Oversight Committee (NSOC)

Containment Sub-Committee Membership Member Title Bob Bazemore (PGN)

VP-Audit (Chairman)

Joe Donahue (PGN)

Chris Burton (PGN)

Greg Selby Dr. Shawn Hughes Dr. Paul Zia Hub Miller Darrell Eisenhut 21~

VP-Nuclear Oversight VP-Harris Technical Director - EPRI VP - Shaw Stone and Webster Civil Engineering Professor, NCSU 33 years industry oversight experience 41 years industry operation and oversight experience

~

~ Progress Energy

CONDITION ASSESSMENT 22~

Progress Energy

  • Determine Extent of Condition
  • Characterize the extent of delamination at the SGR opening
  • Determine condition of other portions of structure
  • Non Destructive Testing (NOT) of Containment Wall Surfaces
  • Use of Impulse Response (IR) Method
  • Comprehensive on external exposed surfaces
  • Accessible areas in adjacent buildings 23~

Progress Energy

  • Concrete Cores
  • Used to confirm IR results (over 80 cores)
  • Visual examination of core bore holes with boroscope to identify if delamination present
  • Containment Dome Inspections
  • NOT IR scans in segment above the SGR opening
  • Concrete cores with boroscope examination of bore holes
  • Physical survey with established benchmarks 24~

Progress Energy

  • IR Equipment
t..\\1'.l:>l)\\.'>6 UW,,.Q b.,;,'">'e

(_"I.~\\

  • Primary test method used in this evaluation 25~
  • IR Performed in the Field Progress Energy
  • Ground Penetrating Radar (GPR) Equipment
  • Locates internal features (rebar, tendon conduits, etc.)

26~

  • GPR Performed in the Field Progress Energy

Examination - Inward View 27~

Core #63, 4" Dia x 20 " Long Core end at fac~

  • of wall Core end Into wall Examination - Side View Core 51, Gap 1 Depth 5-1/4" Gap 1 Width Less than 1 /8" Progress Energy
  • IE Equipment
  • Ability to determine depth of delamination
  • IE Performed in the Field

~

~ Progress Energy

Buttress#

(typical)

Source Drawing:

101-112SHOOO 29~

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'MiERE ROOFING DET AD..S SPEClflC COMPOSITION FC ROOF, PROVIDE MANUFACl CONFlGURA TtOH.

Buttress #2 Buttress #3 Buttress #4 Buttress #5 IR scans completed per PT-407T:

Blue = no delamination Actual IR scan output data:

Blue = no delamination Yellow= transition Red = delaminated Drawing scale is not exact 30

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EL 164" 10' EL 150" 14' 6'

Pour16

- - - - - - - - - - - EL 240' Pour15

-- - - - - -- - - - EL 230' Pour 14

-- - - - - - - - - - EL 220' Pour 13

- - - - - - - - - - - EL 210' Pour12

-- - - - - -- - - - EL 200' Pour11

-- - - - - -- - - - EL 190' Pour10

- - - -- - - - - - - EL 180' Pour9

-- - - - - -- - - - EL 170' Pours

- -- -- - -- - - - EL 160' Pour?

- - - - - - - - - -- EL 150' Pour6

- - - - - - - - - -- EL 140' Pours

- -- -- - -- - - - EL 130' Pour4

- - - - - - - - - - - EL 120' Pour3

-- - - - - -- - - - EL 11 O' Pour2

- - - - - - - - - - - EL 100' Pour1 L.....:.....1-~~~~~~~~~~~--1.....;.......11--~~~~~~~~~~---.1..._._.._~~~~~~~~~~~_._~ -----------EL 90'

~

~

~

10' x 60' 13' x 42' Conclusion - IR scans with confirmation core bores identified delamination only

~ Progress Energy in the Buttress 3-4 span above the Equipment Hatch, as shown in red above

Buttress #5 IR scans completed per PT 407T:

Blue = no delaminatio r Actual IR scan output data:

Blue = no delaminatio Yellow= transition Red = delaminated Drawing scale is not exact n

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31 Conclusion - No delamination identified in these Buttress spans B

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AA AC AD Intermediate Bldg Roof EL 149' O" EL 122' Buttress #2

- - - - - - - - - - - EL 250' Pour16

- - - - - - - - - - - EL 240' Pour15

- - - - - - - - - - - EL 230' Pour14

- - - - - - - - - - - EL 220' Pour 13

- - - - - - - - - - - EL 21 O' Pour12

- - - - - - - - - - - EL 200' Pour11

- - - - - - - - - - - EL 190' Pour10

- - - - - - - - - - - EL 180' Pour9

- - - - - - - - - - - EL 170' Pours

- - - - - - - - - - - EL 160' Pour?

- - - - - - - - - - - EL 150' Pour6

- - - - - - - - - - - EL 140' Pours

- - - - - - - - - - - EL 130' Pour4

- - - - - - - - - - - EL 120' Pour3

- - - - - - - - - - - EL 110' Pour2

- - - - - - - - - - - EL 100' Pour1

- - - - - - - - - - - EL 90'

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~ Progress Energy

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INTERMEDIATE

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Conclusion - Delamination is confined between Buttresses 3-4 span I

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CORE BORE WITH DEl.AMINNTON CORE BORE NOT OE1.JrMINATEO 0

TO BE CORE BORED 0 CORE BORE DRLLED SCALE TO PRINT

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  • 54 65 INTERMEDIATE BLDG. ROOF EL. 149'-0" Conclusion - Core bore hole(s) boroscopic exams on these Buttress spans confirm the IR results, that no delamination has occurred c

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POOR EL113' NOi/EMBER H, 2008 1715 CORE BORE wm4 CIEl.NaWTON CORE BORE NOT 0£l..AWrilATED 0 TO BE CORE 90A£O 0 CORE BORE ORUEO SCAlE TOPRINT

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~BORE Willi DELAM NATION COAE BOA£ NOT DELWJNATED 0 TO COR BOA 0 CORI! BORE UEO Conclusion - Delamination has only been observed in core bore hole(s) boroscopic exams in the buttress 3-4 span, as accurately predicted by IR 34~

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POUR16 POUR15 POUR14

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Horizontal Tendons Buttress 2 - 4 Additional tendons to be detensioned prior to closing SGR opening (pre-outage plan)

Tendons Removed Additional tendons to be detensioned prior to closing SGR opening (pre-outage plan)

Source Drawing:

0425-006 SH001

- SH 000 35~

EL 248'- 9 3/ 4" EL 245'- 7 1/ 2" EL 242'- 5 1/ 4" EL 239'- 3" EL 236'-0 3/ 4" EL 232'- 10 1/ 2" EL 229'- 8 1/ 4" EL 226'-6" EL 223'- 3 3/ 4" EL 220'- I 1/2" EL 216'- 11 1/ 4" EL 213'- 9" EL 210'-6 3/4" EL 207'-4 1/ 2" EL 204'-2 1/ 4" EL 201 '-0" EL 197'-9 3/ 4" EL 194'- 7 1/ 2" EL 191'-5 1/ 4" EL 188'-2 3/ 4" EL 184'- 11 3/4" i EL 181'-8 J/ 4" J EL 178'-5 3/ 4" I EL 175'-2 3/4" i EL 171 '- 11 3/4"

~ EL 168'-8 3/ 4" EL 165'- 5 3/ 4" EL 162'-2 3/ 4" EL 158'- 11 3/ 4" EL 155'-8 3/ 4" EL 152'-5 3/ 4" EL 149'- 2 3/ 4" EL 145'- 11 3/ 4" EL 142'- 8 3/ 4" EL 139'-5 3/ 4" EL 136'- 2 3/ 4" EL 132'- 11 3/4" EL 129'- 8 3/4" EL 126' - 5 3/ 4" EL 123'- 2 3/ 4" EL 119'- 11 3/ 4" EL 116'-8 3/ 4" EL 113'- 5 3/4" EL 110'-2 3/ 4" EL 106'-11 3/ 4" EL 103'-8 3/ 4" EL 98'-

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BUTTRESS NO 2 BUTTRESS NO 3

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Horizontal Tendons Buttress 3 - 5 Additional tendons to be detensioned prior to closing SGR opening (pre-outage plan)

Tendons Removed Additional tendons to be detensioned prior to closing SGR opening (pre-outage plan)

Source Drawing:

0425-007 SH001

- SH 000 36~

~BUTTRESS NO 3 EL 247'-9"~~~~~~~~~~~~~~~::--:::::::-=::--=:--::::::--::=-:=-:::--:::::::-=::--=:--=:::--::~~==-~~~~~~N~0~4::--:::::::-=:--=:--::::::--::=-:=----------,-,--2~4~0~*~~~~~~~

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-,- --------.,.:;;;>=--m-- ""-m-- -=-i-=-

EL 131'-103/4" I-

"-...._ -=====:..-~t- _<;[_'!:_37-"f-.::.'.

I EL 128'-73/4"

_L

"'~b 6_"'""' -

-i

~:~:~:;;:_

=~- ~;~=->- _ _,:<:: =t=====1~~~F ~i~

-+--

/ -~

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~:11=~--~~~~-=-=-==-=-~~}~-=---=-~f- ~YEt~~~ ~~=

EL 102'- 73/4"

____________ '.'.'.:::"'~~ ".'.'.:."'

-t- ~PPJ~I~~-

=*+/--~

EL 96'- 1 3/4"

.,._,..,z,t. -~

~,.._,...,._,,,

-i -

I 120*

RBTN-53H28 RBTN-53H22

37~

Additional tendons to _be detensioned prior to closing SGR opening (pre-outage plan)

38

_...__ SPLIT SHIMS (IWL)

_...__ STRESSING WASHER CHECK VALVE END CAP ---====----~

0-RING BEARING PLATE(IWL)

FACE OF CONC (IWL TENDON WIRES (IWL)

TRUMPET 0

p 0

0 0

OoooO'loo oOf\\o' '

a 'Yo a fl;' o,

o ~ 'o o o oo o oo 0

o 0 0 ~

Q 0

po D o

0 o o /\\ o o 'o o ' o D'lo a

, //o 0 {7 o o 6 O /\\ o 0

0 0 I o D 0 o J/o 0 [7 0 Q o

o o,o o'oo SECTION TRANSITION CONE Source Drawing:

425-020-SH-001-SHOOO

~

~ Progress Energy

Tendon Pattern at time of cutting SGR Opening Energized Tendon I Buttress # 3 I SGR Opening Removed Tendon

....... :r....m=1========

Equipment Hatch area Buttress I j ! f (typical)~

~

39~1~

  • (tefJdo_ns..corJfifJ.ue_beJoW I ~ !!1!!11111lli Buttress # 4 I I

B...1110' e 150' I 1 I ! !

I Cl 1MV I t

40 Tendon Pattern at time of cutting SGR Opening Energized Tendon Buttress (typical)

Buttress# 3 SGR Opening Buttress# 4 EL 22J1 a. 21a 200' EL1 180' EL 170' R-- ~~E;;,~;i=li~!~~:;;;;;lj;;;;1~1E~l:~~-Eb..1£..

EL180' Equipment Hatch area tendons continue below I r !!

I I I !

I I t I

I I I I I I I i I I ! I

Wall Section at SGR Opening (elevation view}

Source Drawing:

425-033 SHOOO 41~

11 2114CL

.fEL. I l0'-0

I II

-~-

L. ~~==

3-==

0 -

---~~

~

1 1

a I I o:J -1)1,.::1 {.~'

<(

_(a) 12" Q I I

) (4 3/e; LINER Fl

--- FI ELD CUT EX 15T. REIN TO SUIT A1 PENE1R. SL

=ff.

I II 1

Ii

  • 1a)I'.. ri-3@ 1-4 (LENG\\\\.\\S

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Energy

Bottom of Ring Girder II lCATION Wall section at higher elevations showing additional stirrup reinforcement (elevation view)

Source Drawing:

425-033 SHOOO 42~

I I

'"""Ti 0 1

1.

I

~

I 11--t~ q' I 18x24-0 t

  1. ax 24 '- 0 11 ~ ~

~

CY\\

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1ress Energy

~

\\\\

l l A 5 2 3 Q \\~. -

ff:

I II 4x21-G -

~

I

\\I 1 1

~x23-0 --

Wall Section at SGR Opening

{Plan View) 43~

Source Drawing:

425-033 SHOOO 21 04~lA53l

_ ( 4 PER \\C.ND<J~ 4 Sf>\\RA.\\.-)

Buttress match-line BUTTRESS#1 BUTIRESS#4 PERSONNEL ACCESS

ROOT CAUSE ANALYSIS Progress Energy

80

~

70 -

60 50 -

40 -

30 -

20 -

10 - -

0 -

46

~

~

I

  • External Events 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

~

~ Progress Energy

0 Impulse Response (IR) Scans 0 Boroscopic Inspections

° Core bore holes 0 Inside the delaminated gap 0 Visual inspections 0 Delamination cracks at SGR Opening 0 Larger fragments from concrete removal process *

° Containment external surface

~

Progress Energy

~-

.~~'

,,- --, \\ /--

(- - "

/ ', _) \\,'* /;' <,/ (\\_ __/*'

I' - _/:

'> __,/ 1

'- /'

\\-.._

r-,

(

I

\\., __

I

\\, -*

0 Nearby energized tendons lift-off (vertical and horizontal)

° Containment dimension measurements 0 Strain gauge measurements 0 Linear variable displacement transducer (L VDT) gap monitoring 0 Building natural frequency

~

Pro(J'&SS Energy

~

,'" -,\\

'\\

~

/

_./

-- )

'~ - /I

/

J

'\\,

/'

/

I'

_/

~ -*

° Core bores laboratory analysis 0 Petrographic Examination

\\

/

i

\\

0 Modulus of Elasticity and Poisson's Ratio 0 Density, Absorption, and Voids

° Compressive Strength, Splitting Tensile Strength, and Direct Tensile Strength 0 Accelerated Creep test 0 Accelerated Alkali Silica Reaction (ASR) test

° Chemistry and contamination test 0 Scanning Electron Microscope (SEM) examination of micro-cracking 49~

~

Progress Energy

OPERATIONAL EXPERIENCE {OE) 50~

~

Progress Energy

I j

,r --,

'~- /J

\\, __,

--._ /)

._/

---.I I

r

(, '

~

'\\

'---I

'e-./ ',__/'

'*../

'-_. J

\\

Steam Generator Replacement (SGR) OE Type of Information Collected from the Industry 0 Architect Engineer and Constructor 0 Type of Containment and design pressure o # of Buttresses

° Concrete design strength requirement 0 Dimensions 0 Internal containment diameter and wall height

° Containment cylinder wall and dome thickness 0 Tendons details (#vertical, # horizontal, # dome, strand diameter) 0 Liner thickness

~

Progress Energy

I

--....,,1

,--°"

"' - '. /

I

/

~"'- /I

"\\

'!/

,~

- \\,', r--,--, c I

~

I I

1

\\_ - ' \\

',, '\\ '

j

' ',,/

' '/

\\ _

_,t

'--I

,,,/

/

~*

-.,~

Steam Generator Replacement (SGR) OE Type of Information Collected from the Industry (cont) 0 Reinforcement details 0 Whether concrete opening was made 0 Was hydro-excavation used 0 And if so, equipment operating parameters 0 Detensioning details 0 # by cutting o # by relaxation 0 #of tendons removed/detensioned beyond the SGR opening

~

Progress Energy

- - c'.,;*,0_-,,*w~*~1~y::_*p;'~

7

~:oris 0 1976 dome delamination investigation and repair (as Gilbert I Commonwealth) 0 Structural Preservation Systems (SPS) 0 Largest Concrete Repair Contractor in the US, 2nd largest Concrete Contractor (of any type) in the US 0 Defects, Damage, and Deterioration 0 Performs > 4,000 repair projects per year 0 3,.000 employees in 27 offices Nationwide, and London, Dubai &

Singapore 0 Wiss, Janney, Elstner, Inc (WJE) 0 Structural engineering and materials science firm specializing in failure investigations and problem solving 0 Specialist in structural condition assessments and design of repairs and retro-fits for reinforced and post tension concrete structures

° Conducted original CR3 Structural Integrity Test (SIT) 0 450 employees in 20 offices nationwide

~

Progress Energy

  • Compression - tension 00 interaction failure occurred 3<D0° N
  • Contributing Effects 1

/

Radial tension due to pre-

/

0 0

/

/

0 stressing

/

0 "'

Thermal effects I

\\

I 0

0

\\

  1. (Q

~1 0

\\

  • Tendon alignment I

\\

I

,.-INlilt-.LLY

\\

DISCOVERED Stress concentrations I

.bo.RE~

0 I

s 0 I

~I Shrinkage 5/1...'N CUT ~RE~

~'2.

\\

SEE SECTION OE.T e:..IL fl.:.'

  • Combined with biaxial

\\

E.DGE OF I

\\

DEL.bo.MIN A.llON

()

0 I

  1. 5 compressive stresses and

\\

I

\\

0 I

lower than normal(2) direct 0

/

/

0 0

/

/

tensile strength of concrete

.. ~---

54~

(1lCause information taken from 1976 Final Report prepared by Gilbert I Commonwealth (2lLower than normal (or typical), but above design requirements 16 0°

~

~ Progress Energy

'Z.70

  • Tendons detensioned (18)
  • Delaminated surface was removed
  • Lower level cracks grouted with epoxy
  • New reinforcement placed
  • New cap poured and cured
  • Tendons partially re-tensioned (18) 55~

N CJ 0

" '\\

0

'\\ \\

\\

0

\\

\\

\\

o I

E.DGE OF.

I DELA.MINA.llON

()

I 0

160°

/

I I

/

/

/

1

J Progress Energy

DESIGN BASIS ANAL VSIS 1

J\\N 56~

~

~ Progress Energy

  • Reinforced Post-Tensioned Concrete Structure
  • Live and Dead Loads
  • Wind (110mph @ 30' increasing to 179 mph@ 166'10")
  • Tornado Wind (300 mph)
  • Tornado pressure (external pressure of 3 psig)
  • Seismic (QBE - 0.05 and SSE - 0.10)
  • Temperature Loads
  • Accident Pressure (55 psig)

Progress Energy

  • 180 degree Symmetric model
  • Symmetry plane @ 150 degrees midway Between Buttress 3 & 4 I 1 & 6
  • Y2 Opening, Y2 Damage & Y2 Hatch Modeled Explicitly
  • Concrete Model
  • Brick elements for all components
  • Dome and Base modeled independently
  • Simplified ring beam and buttress geometry
  • Constraint equations used to join dome and ring girder for meshing efficiency
  • Constraint equation used to model sloped surfaces of the hatch 58~

Progress Energy

  • Liner Model
  • Shell mesh with variable thickness
  • Shared nodes with containment inner surface
  • Tendon Modeling
  • Hoop tendons modeled explicitly for release and re-tensioning
  • Vertical Tendons modeled explicitly for release and re-tensioning
  • Dome tendons modeled independently with forces ported to global model 59~

Progress Energy

'" **** t *

,........ ~

Ol 'T' 1.

00 1

(

U,,.0*

60

-- ----*--* ~E ~ ~

=----+-;

1.. ~\\\\-r

\\

  • A4* 1i.'

/

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~-=:-=- * <.~

\\:!..

J

    • H*~*

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~,........ -.. -*+

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. ~..

/

/..

./

~

~ Progress Energy

~ * *'.

":. *"" '*:-~

7 '

~*

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61

~

.. ~ * --*

~....

  • l. 11'\\1

~..

~.M *..........

... ~....... l~--.-- "-

  • ~..n....-...:.r-r

""°'"'I I/I~

n-.e*7"... 11.1 *

~-

  • n.U

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(I.aw

,.,.... 'U"CI',...

~.. *-

1..&.....r.

., ~, *

~= w......

-:r,,_*

  • .&ii* --,,,_

1t... _.t ~~~.W:t...,_,,,, __ ~,4... * (~

~

,........... ~

.. ~'

    • ""'"*-............. _,_.. __ **'>--.. c..-t -- ~
  • .,r,....... -... -.

....._.7*.r. '!io.--

... c...-

.. ~1.TI" o.-*

~.:>~ ~

.,.......,.._.....,,. "bo,.,...,,,..,,.w:

.t--.

JM.......... -

.... ~~, r-...

x...- -._ ~

  • , a... -......,,._,.,...._.....

,. ~

Progress Energy

ELEMENTS

~

Gravity Loading 62 ~~

NOV 6 2009 17 : 48 : 48

~

~ Progress Energy

63~

CO>IST. :rT. -SEE NOTE. NO. ~ DWG. SC-4Zl-30\\

(T 'l'P. 'I> EACH c.ot..i.'OT. J"T.)

'-~*-a-R. TO._

E.ACT 81..DG.

\\ \\

\\/

~\\

~4 ~ G.* TO°' RL.t.CTOR &LOG.---

ELEMENTS TRANS Tt01'1 RAD n..CIJR li:L.k:V. 95'- o*

--~;{:ff~th' *

~ VERT. TENDONS 66'- 8 J/8' R TC q_ REACTOR BDLG.

F DON ACCESS (;ALLERY

'WALL & DOME 64~

65~

~

~ Progress Energy

66~

~

~ Progress Energy

ELEMENTS MAT NUM

~

CR3 FEA Model 67 ~~

NOV 10 2009 07:44:56

~

~ Progress Energy

The tendons are preloaded to a prescribed load magnitude.

The application of the tendon loads is achieved in the analysis using initial strain input An empirical formula has been developed to account for the loss of load as the distance from the anchor point increases:

p-p e-(ma+ks) 0

  • Where:
  • P 0

= preload magnitude

  • m

= friction coefficient

  • a

= inflection angle (0.16)

  • k

= wobble coefficient (0.0003)

  • s

= distance from anchor point

  • Tendon preloads used in analysis:

Po-dome

= 1635 Kips (1,215,000 lb. 40 years)

Po-horizontal

= 1635 Kips (1,252,000 lb. 40 years)

Po-vertical

= 1635 Kips (1,149,000 lb. 40 years)

Progress Energy

69~

~

~ Progress Energy

70~

~

~ Progress Energy

71~

ELEMENTS MAT NUM

~

~ Progress Energy

72

1 J\\N ELEMENT SOLUTION NOV 8 2009 STEP=l 15:29 : 39 SUB =l TIME=l SMISl (NOAVG)

TOP OMX =1. 169 SMN =598638 SMX =.120E+07 598638 998834

. 113E+07 932135

.1 07E+07

.120E+07 73

~

~ Progress Energy

  • Existing Design Cases
  • Planned Analysis Steps for Comparison
  • Gravity (.95 G)
  • Internal Dead Load (200 psf)
  • Tendons (1635 kips I tendon)
  • Include losses
  • Internal Pressure (55.0 psi)
  • Wind Pressure (0.568 psi)
  • Seismic
  • Accident Thermal
  • Dead Load + Tendons
  • Remove Hoop +Vertical Tendons in SGR Opening
  • Remove SGR Opening
  • Delamination(1)
  • Remove Additional Hoop &

Vertical Tendons Replace the SGR Plug(2)

Repair(2)

Re-tension Tendons

  • SAVE Path Dependent Model for Starting point to Run 5 Controlling Design cases 74~

(1) Analysis will consider timing of delamination and specific concrete properties

~

(2l Sequence of replacing SGR concrete plug and repair may be adjusted

~ Progress Energy

  • Restart the Re-tensioned Model and solve the following Controlling Load Steps
  • 1.5 Internal Pressure+ Accident Thermal
  • 1.25 Wind + 1.25 Pressure + Accident Thermal
  • 1.25 Earthquake + 1.25 Pressure + Accident Thermal
  • 2.0 Wind + Pressure + Accident Thermal
  • Run Comparison to original building elastic design results 75~

Progress Energy

Preliminary Comparison of FEA Results to Extent of Condition Measurements NOE Measurements (figure not to scale)

Calculated Gap Status behind Delamination Calculated Displacements SGR OPENING 76~

c:::J Jll!!arContact D

Sliding Sticking

-. 797454

-. 708848

-.620242

-.531636

-.44303

-.354424 D

-.2650 10 D

-.177212 D

-. 000606

[t Pro9r8ss tnergy

REPAIR APPROACH 77 ~

~

~ Progress Energy

  • Incorporates and is compatible with Root Cause Analysis findings
  • Restores applicable design basis margins
  • Incorporates Extended Life
  • Long Term Surveillance and/or Maintenance Requirements
  • Constructability 78~

Progress Energy

  • Use-as-ls - Rejected
  • Anchorage Only - Rejected
  • Cementitious Grout - Rejected
  • Epoxy Resin - Rejected
  • Delamination Removal and Replacement - Selected Progress Energy

80 Simplified Overview of Engineering & Repair Work Flow Tentative - Subject to RCA and DBA Results EC Mod Phase 1 Install crack arrest strategy Failure Modes Analysis Update MPR Tendon Calculations I

SGREC Mod (Rev)

MPR3D Finite Element -

Analysis EC Mod Phase 2 De-tension I additional *-*

tendons I Preparations for Final Repair ****llM,.

Implement Final Repair Failure Modes Analysis Update Final Root Cause Analysis Post-Repair Testing

~

~ Progress Energy

  • Approach - ILRT and System Pressure Test
  • Concrete exterior will be visually examined prior to pressurization and following de-pressurization
  • Evaluating other additional instrumentation based on the final repair that is implemented, and as driven by:
  • Root cause analysis NDE will be required for restored liner plate 81 ~

[/ Progress Energy

  • Prompt Notification of Regulator & Industry
  • Engagement of Critical Industry Organizations
  • NEI Nuclear Energy Institute (NEI)
  • Including Nuclear Safety Information Advisory Council (NSIAC)
  • Institute for Nuclear Power Operations (INPO)
  • Electric Power Research Institute (EPRI)
  • Continued Transparency with Regulator
  • Special Inspection Team (SIT)
  • Region and NRR/RES technical discussions
  • Periodic Updates with U.S. Licensees Progress Energy

Questions 83~

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