ML20196F828

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Summary of 981203 Meeting with Representatives of & Contractors to Util in Rockville,Md Re Bge Performance on Aging Mgt Evaluation Re Susceptibility of Cast Austenitic Stainless Steel Components to Thermal Embrittlement.W/Encl
ML20196F828
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/24/1999
From: Dave Solorio
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9906290316
Download: ML20196F828 (33)


Text

..

3 . ' June 24,1999

ti

) LICENSEE: Baltimore Gas and Electric Company I FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2

SUBJECT:

SUMMARY

OF DECEMBER 3,1998, MEETING WITH BALTIMORE GAS AND ELECTRIC COMPANY (BGE) REGARDING EVALUATION OF CAST AUSTENITIC STAINLESS STEEL COMPONENTS TO SUPPORT LICENSE RENEWAL APPLICATION FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS, .1 AND 2 On December 3,1998, the Nuclear Regulatory Commission (NRC) staff held a public meeting a with representatives of and contractors to BGE at Rockville, Maryland. The purpose of the l meeting was to discuss how BGE performed its aging management evaluation regarding the f susceptibility of cast austenitic stainless steel (CASS) components to thermal embrittlement in '

order to respond to a related staff request for additional information (NRC letter dated ,

September 3,1998, Question 8). Because BGE's aging management approach was based on l the industry approach, representatives from Electric Power Research Institute presented details regarding how the evaluation of CASS components was performed.

' Enclosure 1 to this meeting summary provides a list of the meeting attendees. Enclosure 2 ,

provides a copy of slides that were used by BGE and EPRI to summarize the evaluation of '

CASS components to support BGE's license renewal application WWW David L. Solorio, Project Manager License Renewal and Standardization Branch

' Division of Regulatory improvement Programs l Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318  !

Enclosures:

1. List of Attendees
2. Meeting Slides cc w/ encls: See next page DISTRIBUTION: I
See next page-l DOCUMENT NAME
G:\RLSB\SOLORIO\ December 3rd 1998 BGE & NRC meeting summary on
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LICENSEE: Baltimore Gas and Electric Company l

FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2 SUBJECT; MMARY OF DECEMBER 3,1999, MEETING WITH BALTIMORE GAS AND EL CTRIC COMPANY (BGE) REGARDING EVALUATION OF CAST AU ENITIC STAINLESS STEEL COMPONENTS TO SUPPORT LICENSE REN AL APPLICATION FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT S'.1 AND 2 1

On December 3,1998, t Nuclear Regulatory Commission (NRC) staff held a public meeting q

with representatives of an contractors to BGE at Rockville, Maryland. The purpose of the j meeting was to discuss ho BGE performed its aging management evaluation regarding the susceptibility of cast austenitigstainless steel (CASS) components to thermal embrittlement in l J

order to respond to a related staff request'for additional information (NRC letter dated 1 September 3,1998, Question 8). Because BGE's aging management approach was based on the industry approach, representa 'ves from Electric Power Research Institute presented details  !

regarding how the evaluation of CAhS components was performed. I Enclosure 1 to this meeting summary ovides a list of the meeting attendees. Enclosure 2 provides a copy of slides that were usedhy BGE and EPRI to summarize the evaluation of

)

CASS components to support BGE's licente renewal application l l

David L. Solorio, Project Manager License Renewal and Standardization Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation I

Docket Nos. 50-317 and 50-318 .

Enclosures:

1. List of Attendees
2. Meeting Slides cc w/ encis: See next page l

DISTRIBUTION:

See ne4 page DOCUMENT NAME: G,:\RLSB\SOLORIO\ December 3rd 1998 BGE & NRC meeting summary on

\

CASS.WPD s

OFFICE LA RLSB RLSB:D \

/ \

NAME DLhio CIGrimes \

DATE 6lff/99 (p /2,%9 / /99 OFFICIAL R$ CORD COPY

+ . .1 5

Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant cc: Unit Nos.1 and 2 President . Mr. Joseph H. Walter, Chief Engineer Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 James P. Bennett, Esquire Counsel ,

.Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2102 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire

- Shaw, Pittman, Potts, and Trowbridge - Patricia T. Bimie, Esquire 2300 N Street, NW ' Co-Director .

Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Bruce S. Montgomery, Director- Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatell 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Chattanooga, TN 37411-4017 Resident Inspector U.S. Nuclear Regulatory Commission David Lewis P,0. Box 287 Shaw, Pittman, Potts, and Trowbridge ,

St. Leonard, MD 20685 2300 N Street, NW Washington, DC 20037 1

Mr. Richard I. McLean Nuclear Programs Douglas J. Walters ,

Power Plant Research Program Nuclear Energy Institute  !

. Maryland Dept. of Natural Resources 1776 l Street, N.W.

Tawes State Office Buildinn. B3 Suite 400 Annapolis, MD 21401. Washington, DC 20006-3708 DJW@NEl.ORG l Regional Administrator, Region i U.S. Nuclear Regulatory Commission Barth W. Doroshuk 475 Allendale Road Baltimore Gas and Electric Company King of Prussia, PA 19406 Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Mr. Charles H. Cruse, Vice President . NEF ist Floor Nuclear Energy Division . Lusby, Maryland 20657 Baltimore Gas and Electric Company 1650 Calvert Cliffs Parkway National Whistleblower Center Lusby, MD 20657-47027 3233 P Street, N.W.

Washington, DC 20007

m L

DISTRIBUTION. .

Hard copy l w w:n PUBLIC l

RLSB RF N. Dudley, ACRS,- T2E26 EHylton E-mail: M. Evans R. Zimmerman ' R. Bores I W. Kane S. Stewart i D. Matthews F. Bower l S. Newberry B. Latta i

- C. Grimes C. Carpenter B. Zaleman D. Walters, NEl J. Strosnider l R. Wessman l E. Imbro W. Bateman J. Calvo H. Brammer T. Hiltz G. Holahan T. Collins C. Gratton B. Boger. -

R. Correia R. Latta J. Moore

. J. Rutber0 R. Weisman M. Zobler M. Mayfield S. Bahadur N. Chokshi <

J. Vora

' A Murphy D. Martin W. McDowell S. Droggitis RLSB Staff

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T.Kenyon K.Leigh W.Hehl i~ W. Cook y_'_

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NRC & BGE MEETING ON DELTA FERRITE CRITERIA ATTENDANCE LIST DECEMBER 3.1998 )

NAME ORGANIZATION

1. DAVID SOLORIO NRC/NRR/PDLR
2. BOB NICKELL EPRI
3. JOHN CAREY EPRI
4. JOHN RYCYNA BGE
5. MARVIN BOWMAN BGE
6. JIM BENNETT BGE
7. ALLEN HISER - NRC/NRR/EMCB
8. JOE MUSCARA NRC/RES/EMMEB l
9. CAYETANO SANTOS NRC/RES/EMMEB l
10. OMESH CHOPRA ANL
11. GEOFF HORNSETH NRC/NRR/EMCB
12. ALICE CARSON BECHTEL
13. DON SHAW BGE 14 MATTHEW MITCHELL NRC/NRR/EMCB '

15 MICHAEL MAYFIELD NRC/RES/DET

16. ED HACKETT NRC/RES/DET
17. HAl-BOH WANG NRC/NRR/PDLR 4
16. ALEXANDER DROMERICK NRC/NRR/PD 1-1
19. FRED POLASKI PECO ENERGY
20. TERRY PICKF.NS NORTHERN STATES POWER CO.
21. Bill SHACK ARGONNE NAT LAB
22. BOB HARDIES BGE
23. STEPHANIE COFFIN NRC/NRR/EMCB
24. DOUG WALTERS NEl
25. BARTH DOROSHUK BGE
26. LEE BANIC NRC/NRR/EMCB
23. STEPHANIE COFFIN NRC/NRR/EMCB
24. DOUG WALTERS NEl
25. BARTH DOROSHUK BGE 26, LEE BANIC NRC/NRR/EMCB
27. DONALD CHUNG NUS/LIS
28. DOUG WALTERS NEl
29. BARRY ELLIOT NRC/NRR/EMCB l
30. SAM LEE NRC/NRR/PDLR I
31. EDMUND SULLIVAN NRC/NRR/EMCB
32. ROBERT WEISMAN NRC/OGC I
33. CHRIS GRIMES NRC/NRR/PDLR Enclosure 1

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FLOW CHART FOR EVALUATING POTENTIALLY SIGNIFICANT THERMAL AGING EMBRITTLEMENT EFFECTS FOR CLASS 1 CAST AUSTENITIC STAINLESS STEEL COMPONENTS l Does the CASS

, mponent Require Agin j Aging Management I No geview7 l l

l 4 Yes )

Low-Mo High-Mo u Material Material (e.g., CF-3) (e.g., CF-8M) )

Yes Was Was the Component the Component Cast >< Cast Yes Centrifugally? No Centrifugally?

u Can the No calculated or measured delta ferrite No j Yes content be shown to be less than or equal to 20 %?

v Inspect component location in ,

Do the accordance with plant ISI program Yes detected and and evaluate detected and sized sized flaws satisfy , flaws in accordance with IWB-the flaw acceptance 3640 flaw acceptance criteria for criteda of SAW/SMAW weld defects.

IWB-36407 Repair / replace No y component.

Continue to y operate component within the current licensing basis.

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Estimation of Fracture Toughness of Cast Stainless Steels During Therma:. Aging in LWR Systems

.YChra Argonne National Laboratory Prepared for U.S. Nuclear Regulatory Commission 9

s Crack Extension Aa(in.) Crack Extension Aa(lit) 0.00 0.05 c.1o c.15 cm 0D5 c.10 c.15

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g Crack Extension Aa(In.) Crack Extension Aa(in.)

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800 - .1s% Ferrite -

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Lower-Bound J-R Curve  : Lower-Sound J-R Curve .

l l

n'-* Centrifugally Cast Steels --

Centrifugally Cast Steels .P " "d 800 - -

g 10-15% Ferrite 10-15% Ferrite g g g Room Temp. 2- 290*C J=360%4 -;4000

.T.

5 0002- J .sosgq E41 2- J.3c244"88 -

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Lower-8ound J-R Curve Lower-Bound J4 Curve -

" "ge o'-- Centrifu -

Centrifugally Cast Steels  :

800 - ,,gg p.,, gi, gally Cast Steels g ,

<10% Ferrite -

7 RoomTemp. 2- . 290"C .i4000 i 0 qap J 45844i 000 -- - J"N I c'-*

507, 4 a a *'-*  :-  : d;*$8aa"=

, , 3000 s CF-3 -

,5' 40s

~

--2000 '

\ J.3 4ag om CF-eu

-- 7 J . mag "

CF-eu o

[ 7 1000

~ '

0- '

l l l l l l l l 4L0 0 1 2 3 4 5 0 1 2 3 4 5 Crack Extension, Aa(mm) Crack Extension, Aa (mm)

Figure 4. Predicted louw-bound J-R curves at RT and 290*Cfor centrifugally cast SSs with ferrite uontents >J5.10--15. or <J 096

\

~

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R F S 3, tht i v r 2 o>t s h P O LE F- wc oe f ,

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H T C A e J- mct r ohaRead J- ht t sa c

S - -

7 l

i i EPRI TR-106092 Final Report l P

Electric Power September 1997 R: search Institute 1'

i Evaluation of Thermal Aging l Embrittlement for Cast Austenitic i

i Stainless Steel Components in '

LWR Reactor Coolant Systems Prepared by APPLIED SCIENCE AND TECHNOLOGY, Poway, California FRAMATOME TECHNOLOGIES, INC. Lynchburg, Virginia

.]

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(continued on back cover) l 1

r Crack Extension, Aa (in.)

0.0 0.1 0.2 0.3 3000__l l l l ll l l l ll ! : !l l l l --

Heat 758 CF-8M m

m

-- 15000 N N  :: 290 C ..

f

S c=24%

E 5,

x 2000--

1

- v .--. 18,000 h at 400*C Unaged c 7  :: --10000 C c J = 544 aa)0.34 ..

.9  :: -

c y --

,o E 1000-~; -

E o  :: -- 5000 E

  • ** n -

e

. ..*... o b K Saturation a = 2n '6a)0.29 --

0 1g: : : ll : '

ll l l l: : : '::: 0 0 2 4 6 8 10 Crack Extension, Aa (mm)

Crack Extension, Aa (in.)

0.0 0.1 0.2 0.3 3000 _l l l l ll l l l ll l l l ll l l l --

Heat 758 CF-8M --

--15000 N n  :: Room Temp. ..

d E  :: S =24% unaged --

g 7 J = CB1(aa)0.46 j-w 2000.". A. . 18,000 h at 400*C --

g 7 -- --10000 C c  :: --

7 O Saturation 5 E 1000E- J = 270(Aa)U [. j

- 5000 E E  :: , . *" o O  ::

E a -

01-l l l ll l l l: : l l: : : ll : : 0 0 2 4 6 8 10 Crack Extension, Aa (mm)

Experimental and Estimated J R Curvesfor Unaged and Fully-Aged Statically-Cast Elbow of CF-8M Steel (Figure 16from Reference 11).

s

I g

i l

Crack Extension, Aa (in.) l 0.0 0.1 0.2 0.3 3000 .l  !! l ll l l l ll l l l ll l l l -- *

Heat L CF--8M _ 15000 N

- j

^

u (( 320'C --

d l

~ c:: I

S :9 l

$, e=19%

x 2000-.

v -

A e 7,500 h at 400*C C 7  :: --10000 C c  :: "

.O  :: Unaged Saturation c

5 ,

J = 474(6a)0.33 J = 203(aa)0.28

.j m

E u .1000--- -- 5000 E S  :: -- '

S --

__ So i O -- 1

~:g.

0 O

0 1 l l: : l  : ll : : ll l l j 0 2- 4 6 8 10 l l

Crack Extension, Aa (mm) )

l Crack Extension, Aa (in.) 1 0.0 0.1 0.2 0.3 3000 ,_l l l l ll l l l ll ! l l ll l l l--

Heat L CF-8M

-- -- 15000 N, n  :: Room Temp. --

c 5  :: S c=19% ." . h,

,x2000 -. ,.

7,500 h ai4oo.c --

g 7  :: -- 10000 C )

c  :: Unaged

~~

O -- --

c

  • 3

. ,-: J = 564( )0.44 _ g 8 .-

.;=

E 1000-- saturation m

-- 5000 E

.2'  :: J = 177(Aa)0.38 ,, u O

e .. s o  :: A

'E

~

O g-

(( .

i 0' : : : l: : : l: : : l: : : ll : : 0 0 2 4 6 8 10 Crack Extension, Aa (mm)  !

Experimental and Estimated J-R Curvesfor Unaged and Fully.

Aged Statically-Cast Plate of CF-8M Steel (Figure 17from '

Reference 11).

. l

I e R FS d o

l e

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eXe c

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gaea t

nn R T c ao o e6 i mtp E S A wipm3 a cmd t

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T C A w FScwI l eo l

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i a

F - -

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i  ;

I .

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I i i i 8 400 400

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i

. .. Q., ., ' ' . . . . - . . . ..,......... . . . . . . . . . . . . .

A l 100 g 100

~

5 i

f - -Type 316 SAW j

- - -CASS CF-8M Static-Cast FN>15%

--- 1- - CASS CF-8M Static Cast 10-15% FN l

- -CASS CF BM Static Cast FN<.10%

Y i i '

0  :: -

0

'I  !

i i .

A i  !  !

  • l

( '

5 5 5 5

0 1 2 3 4 C. .;.s Extension (mm)

Comparison of Crack Growth Resistance (J-R) Curvesfor Type 316 SA W and Statically-Cast CF-8M Material at 555*F. ,

l I

k S'

]

500 . . . .

._. ...!. .. L. . _ . i

..+ ....

i i i A

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/

.. . . .L. . . .

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100 .q '

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-y-Type 316 SAW - -

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0 ..

8 . t l "

5 f f i i i

a j i

i 0 1 2 3 4 Crack Extension (mm)

Comparison of Crack Growth Resistance (J.R) CurvesJor lype 316 SAW and Centrifugally-Cast CF-8M Material at 555'F.

I a

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