ML20196F828
| ML20196F828 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| 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 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 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 CASS.WPD l
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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 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 austeniti stainless steel (CASS) components to thermal embrittlement in J
g 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 the industry approach, representa 'ves from Electric Power Research Institute presented details regarding how the evaluation of CAhS components was performed.
I 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
David L. Solorio, Project Manager License Renewal and Standardization Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. List of Attendees
- 2. Meeting Slides cc w/ encis: See next page DISTRIBUTION:
See ne4 page DOCUMENT NAME: G,:\\RLSB\\SOLORIO\\ December 3rd 1998 BGE & NRC meeting summary on CASS.WPD
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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 Mr. Richard I. McLean 1
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 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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NRC & BGE MEETING ON DELTA FERRITE CRITERIA ATTENDANCE LIST DECEMBER 3.1998
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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.
NRC/NRR/EMCB 8.
JOE MUSCARA NRC/RES/EMMEB l
9.
CAYETANO SANTOS NRC/RES/EMMEB 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 30.
SAM LEE NRC/NRR/PDLR 31.
EDMUND SULLIVAN NRC/NRR/EMCB 32.
ROBERT WEISMAN NRC/OGC 33.
CHRIS GRIMES NRC/NRR/PDLR
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FLOW CHART FOR EVALUATING POTENTIALLY SIGNIFICANT THERMAL AGING EMBRITTLEMENT EFFECTS FOR CLASS 1 CAST AUSTENITIC STAINLESS STEEL COMPONENTS Does the CASS mponent Require Agin j
Aging Management No geview7 l
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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.
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Crack Extension, Aa(mm) 1%ure3.
Predicted lowet" bound J-R curves at RT and 290*Cfor static-cast SSs withferrite contents >15,10-15, or <1096 s
g Crack Extension Aa(In.)
Crack Extension Aa(in.)
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g 10-15% Ferrite g
g Room Temp.
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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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EPRI TR-106092 P
Final Report September 1997 Electric Power R: search Institute 1'
i Evaluation of Thermal Aging Embrittlement for Cast Austenitic 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 =24%
E 5, 2000--
1 c
x v
18,000 h at 400*C c
7 Unaged
--10000 C c
J = 544 aa)0.34
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y
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-- 5000 E
o
- ** n o
e b
K Saturation a = 2n '6a)0.29 --
0 1g:
- : ll :
ll l l l: : : ' : : :
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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
- 2000.".
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7
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Saturation 5
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E o
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a 01-l l l ll l l l: : l l: : : ll : :
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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 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
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c Unaged Saturation c
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m u
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Crack Extension, Aa (mm)
)
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n
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5
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, 2000 -.
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)
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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).
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i i
0 0
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Comparison of Crack Growth Resistance (J-R) Curvesfor Type 316 SA W and Statically-Cast CF-8M Material at 555*F.
l I
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0 l
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Comparison of Crack Growth Resistance (J.R) CurvesJor lype 316 SAW and Centrifugally-Cast CF-8M Material at 555'F.
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