ML20062H638
| ML20062H638 | |
| Person / Time | |
|---|---|
| Site: | Allens Creek File:Houston Lighting and Power Company icon.png |
| Issue date: | 07/29/1980 |
| From: | Gunther L, Malec W EBASCO SERVICES, INC. |
| To: | |
| Shared Package | |
| ML19331C559 | List:
|
| References | |
| ISSUANCES-CP, NUDOCS 8008190307 | |
| Download: ML20062H638 (9) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of S
3 S
HOUSTON LIGHTING & POWER COMPANY S
Docket No. 50-466 S
(Allens Creek Nuclear Generating S
Station, Unit 1)
S s
AFFIDAVIT OF DR. GERALD M.
GC p20N j
)
My name is Dr. Gerald M. Gordon.
I am employed by the General Electric Company as Manager, Plant Materials i
Engineering and Technology, Nuclear Power Systems Engineering Department.
I have been so employed for two years.
A l
statement of my experience and qualifications is set out in
{
For the purposes of clarity, the following defini-j i
tions apply to this affidavit:
a.
Austenitic Stainless Steel.
Austenitic Stainless j
Steel (nominal 18 percent chromium and 8 percent nickel compositions being the most popular) are steels that possess an austenitic (face centered cubic atomic) structure at room temperature and are non-magnetic.
Austenitic stainlocs steels are generally either normal carbon (0. 03 % maximum) or low carbon (0.03% maximum).
The icw carbon versions are referred to as L-Grade.
- r O
e 452
i b.
Sensitization.
The intergranular precipitation of chromium carbide and resultant depletion of chremium level in austenitic stainless steels when exposed to temperatures in 1,2/
the approximate range of 800 to 1500*.
This depletion leads to decreased corrosion resistance at the grain boundaries.
c.
Intergranular Stress Corrosion Cracking (IGSCC).
Cracking occurring preferentially at grain boundaries re-sulting from a special combination of stress, material condition and environments.
Sensitized austenitic stainless steel is a material condition where IGSCC has occurred in BWRs.
d.
Type 316 Nuclear Grade Stainless Steel.
A classi-fication of steel alloys that has approximately 16 percent i
i chromium, 10 pcreent nickel, 2 to 3 percent Molybdenum, less than 0.02 percent carbon, and some other minor alloying ele-ments, with the remainder being iron.
Type 316 Nuclear Grade does not sensitize when welded and therefore is not susceptible
?
to IGSCC under BWR conditions.
e.
Plain Carbon Steel.
A classification of non-stainless steel alloy that has approximately.2 percent carbon and
.5 percent manganese.
This class of alloys has not exhibited stress corrosion cracking in contact with BWR coolant.
f.
Heat Affected Zone.
A region of base metal on either side of a weld which is heated above 300*F during.. 453
welding.
In materials subject to intergranular stress corrosion this results in sensitization.
]
Sensitization of normal carbon content (0.05-0.08%) stainless steels occurs in those places where pipe welding has heated a narrow band of the material to an elevated temperature and the material has been allowed to cool slowly without a subsequent heat treatment.
These heat-affected zones are thus " sensitized."
When these sensitized areas were exposed to a particular ccmbination of stress and dissolved oxygen in high temperature waters, these zones have in the past shown some susceptibility to t
stress corrosion cracking at grain boundaries.
Through July 28, 1980, only 209 out of about 34,000 stainless steel i
pipe weld heat-affected zones within the Reactor Coolant j
j Pressure Boundary (RCPB) have experienced IGSCC in all operating BWRs.
Of these, the bulk have been in the recirculation
+
bypass line, the core spray line, control rod drive hydraulic l
return line, and reactor water clean up lines.
Counter measures have been identified and qualified for these lines in ACNGS.
For example, the recirculation bypass line and l
the control rod drive hydraulic return line were eliminated i
l from the ACNGS design and the core spray line and reactor j
water clean up lines were changed from normal carbon stainless steel to plain carbon steel.
Plain carbon steel has not
~3-e 454
exhibited stress corrosion under BWR conditions.
The remainder of the RCPB piping is either plain carben steel or Type 316 I
Nuclear Grade stainless steel.
The specific material changes in stainless steel piping for ACNGS are the result of programs suggested by a special interdisciplinary General Electric Task Force investi-gation conducted in 1975 to determine the cause of cracking in stainless steel piping lines.
Potential improvements were identified and extensively tested.
Only after being 3,4/
proven were they implemented into ACNGS and other plants.
More recent changes made to the ACNGS plant to further avoid IGSCC incidents include the use of feedwater spargers and collet cylinder tube and recirculation pump
+
housing which are made of low carbon stainless steel and
{
Control Rod Drive Housings which are fabricated from Type 316L stainless steel.
i ACNGS is designed to eliminate the occurrence of IGSCC.
The most direct and certain solution to eliminate the potential for IGSCC in BWR piping, as recommended 1 - the 5/
NRC,~
is the use of materials resistant to stress corrosion.
To that end, all of the RCPB will be composed of materials not subject to IGSCC.
The NRC Staff established in Regulatory Guide 1.44 and NUREG-0313-5/
the criteria for testing and 4
fabricating austenitic stainless steels to minimizc the incidence of IGSCC.
These criteria are not applicable to the very low carbon grades of austenitic stainless steels and plain carbon steel because these materials have been shown to resist IGSCC.
This immunity can be produced because the most significant factor affecting the degree of sensitization is the carbon content of the alloy.~6/
Stainless steels with a maximum of.03% carbon are essentially immune to IGSCC in a SWR environment.
At great expense, Applicant has specified that all stainless steel material in the recirculation system be made of the most impervious material available--316 Nuclear Grade stain-less steel.
This material may not have a carbon content exceeding.02 percent which is even lower than the carben level of 316L (.03 % maximum).
Hence, the entire recirculation system can be considered immune to IGSCC.
In conclusion, the materials used for ACNGS piping supplied by General Electric comply fully with 10 CFR 50, Appendix A, Criterion 31, and reduce the potential incidence of intergranular stress corrosion cracking to virtually nil.
The NRC has reviewed the substitution of materials described above and accepts this alternative as a resolution for the generic problem.~5/ r -~~ 45 S
References 1.
G.
E.
Linnert, " Welding Metallurgy," American Welding Society, 1949.
2.
American Society for Metals, Metals Handbook, Volume 1.
" Properties and Selection of Metals," Eighth Edition, 1961.
t 3.
"The Application of Low Carbon Type 316 Stainless Steel for BWR Recirculation Piping Systems," J.
F. Copeland and E.
D.
Sayre.
Paper to be presented at Symposium
" Material-Environment Interactions in Structural and Pressure Containment Service," organized by the Metal Properties Council, Inc., in cooperation with the Materials Division of ASME, to be held during the 1980 ASME Winter Annual Meeting, Chicago, Illinois, November 16-21, 1980.
4.
" Mitigation of Stress Corrosion Cracking in Boiling Water Reactors" by R.
E. Hanneman and R.
L. Cowan II.
Paper presented at the American Power Conference, Chicago, Illinois, April 1980, to be published in proceedings.
5.
" Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping,"
NUREG-0 313, Rev. 1 (October, 1979).
6.
" Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Light Water Reactor Plants,"
!TUREG-0531 (February, 1979).
ATTACHMENT 1 GEPALD M. GORDON I
PRESENT POSITION Manager, Plant Materials Engineering and Technology, Nuclear Power Systems Engineering Department, General Electric Company.
EDUCATION B. S. - Metallurgical Engineering, Wayne State University,195o Ph.D. - Metallurgical Engineering, The Ohio State University,1959 TECHNICAL ASSIGNMENTS l
Prior to joining General Electric, Dr. Gordon was a Senior Metallurgist at
)
Stanford Research Institute, Menlo Park, California, frca 1959-63. He served j
as a Project Leader en a number of government and comercially sponsored programs t
in the areas of nigh temperature oxidation and mechanical performance of refrac-tory metal alloys.
Dr. Gordon joined the General Electric Company Nuclear Energy Division in 1964 x
as a Senior Metallurgist in the Reactor Materials Development Group at Vallecitos.
L He became Manager of the Metallurgy Development Component in 1969. This group had materials research and development responsibility for physical metallurgy, fracture toughness and radiation damage of reactor materials and aqueous corrosion and stress cracking of nuclear reactor pressure boundary and internals materials.
In 1973, Dr. Gordon became Manager of the Zircaloy Performance Group with respon-sibility for development and evaluation of nuclear fuel cladding and channel materials. He also served as Manager, Plant Ccmponent Behavior Analysis and was respcnsible for implemencation of laboratory developments in design of reactor p l a n '.s. He assumed the position as Manager, Plant Materials Engineering in 1976, i
and his current position as Manager, Plant Materials Engineering and Technology
)
in 1978, and is currently responsible for evaluating and specifying BWR plant materials as well as materials surveillance and identification and solution of potential or actual stress corrosion cracking problems.
Dr. Gordon is a Registered Professional Engineer in California and a Fellow of the American Society of Metals. He has authored numerous publications and patents and has been an invited lecturer or Session Chairman at several International Confer-ences on Corrosion & Stress Corrosion Cracking. He is past Chairman of the National Association of Corrosion Engineers Committee T-11A on Corrosion in High Purity Power Plant Water.
'-~
458 f
O U'IITED STATES OF AMERICA NUCLEAR FIGIEATORY COMMISSICN BEF0PI THE ATOMIC SAFETY A'iD LICENSING 30ARD In the Matter of
)
)
HOUSTON LIGHTING & PCWER
)
Docket No. 50-466 COMPA'"i
)
)
(Allens Creek Nuclear
)
Generating Station, Unit
)
No. 1)
)
AFFIDAVIT OF LOUIS A GUNTHER State of New Jersey County of Bergen I, Louis A Gunther, Welding and Materials Engineer, Allens Creek Project for Ebasco Services Incorporated, of lawful age, being first duly sworn, upon my oath certify that I have reviewed and am thoroughly familiar with the statements contained in the attached affidavit addressing intervenor TexPirg's Contention 10 regarding IGSCC and that all statements contained therein are true and correct to the best of my knowledge and belief.
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Subscribed and sworn to before me this
'? N day of
,1980.
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CARCL A. CPITENOK P;0T,GV PtP,UC O'
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U'lITED STATES OF AMERICA NUCLEAR REGULATORY CO3' MISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
HOUSTON LIGHTING & POWER
)
Docket No. 50-466 COMPANY
)
)
(Allens Creek Nuclear
)
Generating Station, Unit
)
No. 1)
)
AFFIDAVIT OF WALTER F MALEC State of New Jersey County of Bergen I, Walter F Malec, Supervising Mechanical Nuclear Engineer, Allens Creek Project, for Ebasco Services Incorporated, of lawful age being first duly sworn, upon my oath certify that I have reviewed and am thoroughly familiar with the statements contained in the attached affidavit addressing intervenor Tex?irg's Contention 10 regarding IGSCC and that all statements contained therein are true and correct to the best of my knowledge and belief.
P l
A_
I Subscribed and sworn to before me this day of
,1980.
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CARCL A. CPITENOK NOTARY P!JAL'C r
,' int jeFecy Mf COMY:S!ICN D?:RE3 CEPr. ;3,1933 460
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of S
S HOUSTON LIGHTING & PONER S
COMPANY S
Docket No. 50-466 S
(Allens Creek Nuclear S
Generaring Station, Unit 5
No. 1)
S AFFIDAVIT ADDRESSING TEXPIRG'S CONTENTION NO. 10 RELATING TO INTERGRANULAR STRESS CORROSION CRACKING My name is Louis A. Gunther.
My business address is Two World Trade Center, New York, N. Y.
I am the Welding and Materials Engineer for the Allens Creek Project employsd by Ebasco Services Incorporated.
The statement of my background _and qualifications is attached as Exhibit I to this testimony.
My name is Walter F. Malec.
My business address is 160 Chubb Avenue, Lyndhurst, N.
J.
I am the Supervising Mechanical Nuclear Engineer for the Allens Creek Project employed by Ebasco Services Incorporated.
The statement of my background and qualifications is attached as Exhibit II to this testimony.
This affidavit responds to the Intervenor's concerns about intergranular stress. corrosion cracking of austenitic stainless steels supplied by Ebasco Services Incorporated.
The phenomenon of IGSCC is described in the affidavit of Dr. ' Gerald M. Gordon of General Electric.
i 461
The piping within the reactor coolant pressure boundary (RCP3) of the standby liquid control system, instrenentation of the nuclear boiler system, and instrumentation of the recirculation system will be fabricated from 304L stainless steels.
This classification of steel alloy has 18-20 percent chromium and 3-12 1/
percent nickel, a maximum of 0.03 percent carbon,-
some other minor alloying elements and the remainder is iron.
The resistance of ice carbon steels, such as 304L, to IGSCC is also described in the affidavit of Dr. Gerald M.
Gordon.
Cespite great confidence in the prophylaxis provided by proper materials selection and processing, ACNGS will also be provided with a positive leak detection system.
This system, which is described in PSAR Section 5.2.7, will detect any uncon-j i
trolled or unanticipated leakage from the RCP3.
Since all IGSCC failures produce easily detectable leakage well before the presence of rapidly propagating cracks, this detection system provides the final conservative assurance that the safety of ACNGS will not be threatened.
6 I
1/
Scme stainless steel A312 piping with a 0.035 percent carbon content, will be used in the ECCS for piping in direct contact with the Suppression Pool.
This is a corrosion prevention measure.
This piping is open-ended and not subject to the same stress levels as in the pressurised piping in which IGSCC has been observed. -
462
5/30 EXHIBIT I Page 1 of 3 FISDE - LOUIS A GU5!HER Senior Engineer - Materials Applications SD0'A?Jf 07. E:3ERIENCE (Since 1968)
Total Experience - >bre than 12 years engineering experience in recal-lurgical and welding engineering in the areas of welding design and
=aterial selection, pressure vessel f abrica:Lon and advanced welding process develop =ent for utili:7, naval nuclear, deep sea sub=ergence and aerospace projects.
?:ofessional Affilia: ions - ?:ofessional Engineer in the Sea:e of New York.
Patents - Method of Welding a Tube to a Tube Sheet, ?aten: No. 3,324,663.
Honors and Awards - Tau 3 eta ?i Noah A Kahn Me=orial Award - ASTM 3
?:ofessional Society Me=berships - A=erican Socie:y for Me:als American Welding Society Welding Research Council Education - 3S Metallurgical Engineering (=sgna cen laude)
?olytechnic Insti:ute of 3:coklyn - 1968 15 Metallurgy - New York University 1970 i
MBA Manage =en: Sys:e=s - New York Universi:7 1975 Specialised Training - Cc= plated the following courses:
(a)
TT-4 ? actical Nuclea ?over ?lan: Technolo gy Course / sponsored by Ebasco-1977.
(b) 3&M 3asic Steas Generating Technology Course /
sponsored by Ebasco-19 76.
(c)
GE-3WR Course / sponsored by Ebasco-1975.
(d)
Titanium and I:s Alloys / sponsored by the A=erican Society for Metals-1963.
463
r Pega 2 of 3 LOUIS 'A GUNTHER REPRESE: CAT!77 E3.iSCO ?ROJECT IZ?ERIENCE (As f anior Engineer)
Nuclear Louisiana ?oue: & Light Co= pan;-
Waterford Unit 3 g
Houston Lighting & Power Co=pany Allens Creek Uni: 1 Fossil i
New York Sts:e Electric & Gas Cc=pany Ho=er City Unt: 3 Pennsylvania Electric Co=pany Iowa ?ublic Service Co=pacy Neal Uni: 4 Public Service Co=pany of Colorado Pawnee Unit i Houston Lighting & Power Co=pany Li=estone Units 1 and 2 i
E3ASCO E:CERIENCZ (Since 1974)
Senior Engineer - (6 years), New York Office Responsible for all =atters concerning New York Office velding f abrication and,=aterials selection during design and construction phases on assigned projects and for providing technical support for project site support engineers. Assigned to special.o. rojec.ts for development of auto =atic f.ixed p.osition pipe-welding p rocedure s.
~~
,i PRIOR E:OEF2NCE (6 Years)
Curtiss Wright Corporation Wood-Ridge, New Jersey Senior Engineer (3 years)
Assigned to the Welding Technology Depart =ent, Nuclear Division.
Re spon sible for develop =en:, i=ple=entation and surveillance o f specialized welding procedures e= ployed in the =anufacture of Naval Nuclear Congonents to NAVSHI?S-250-1500-1 require =ents. These procedures included specialized seal welding, auta=a:ic tube-to-tube shee: welding, and aut:=atic orbi:a1 pipe welding processes. Additional responsibilities included estallurgical studies for develop =ent projects and production support, canpower and schedule esti=ating for new welding projec:2, capi:al equip =en: selection, and vendor auditing.
464
? age 3 of 3 RESDE - LOUIS A GI."EdER PRIOR EX?ERIENCE (5 Years) (Continued)
Curtiss Wright Corporation Wood Ridge, New Jersey Engineer (2 years)
Asaigned to the ?:ccess Metallurgy Depart =ent, Aerospace Division.
Respcasible for develop =en: projects concerned with repal: welding and hea ::ea:=ent o f turbine bladas, plas=a are welding, inertia welding, and produe:Lon welding of E6AC s: eel asse=blies for the G: --na 714
?:o3:1=-
U S Naval Applied Science Laboratory
~
New York, New Yo rk Physical Metallurgist (1 year)
Assigned to the Yi:anie= Develop =en: ?:ogra=, responsible for carrying welding develop =ent studies and welder ::aining prog:a=s on heavy ou:
section :itani== alloys in support of U S Navy deep sub=ergence vehicle p ro gra=s.
Ibasco Services Incorporated Materials Laboratory Technician (Sc:=er E= ploy =ent)
Responsible for specinen preparation, =etallographic work en failure analyses, and bra =ing and =achining opera:Lons perfor=ed during laboratory studies for the power industry.
.oo f
W 465
UALTER F MALEC Supervising Engineer i,c.... l v,\\ I C ES EXHIBIT II 4 Years With E3ASCO SFR EBiSC1 Born Philadelphia, Pennsylvania Education Polytechnic Institute of Technology, degree of Engineer in Nuclear Engineering - 1978 Massachusetts Institute of Technology, is in Nuclear Engineering - 1970 U.S. Coast Guard Academy, 3S - 1963
\\
Member American Nuclear Society Licensed Registered Professional Engineer in the State of New York (No. 56673)
Experience:
f 1980 Ebasco Services Incorporated, Lyndhurst (NJ) Office; Supervising Engineer, Mechanical-Nuclear Engineering i
Depart = cat:
g i
Houston Lighting & Power Co - Allens Creek NCS - Unit No. 1-1200 >M(e) BWR f
Technical and administrative responsibility for rechanical, j
fire protection, plumbing, HVAC, stress analysis, hangers and
)'
supports, and inservice inspection activities.
Includes schedules, budgets, and client relations.
1978-1930 Ebasco Services Incorporated, Lyndhurst (NJ) Office; I
Principal Engineer, Mechanical-Nuclear Engineering Depart = cat Houston Lighting & Power Co - Allens Creek NCS - Unit No. 1-1200 FM(c) EWR, Lead NSSS Engineer Responsible for preparation and maintenance of ECCS and 30?
flow diagrams, piping layouts, system design descriptions, inservice inspection provisions, Nuclear Island building general arrangements, PSAR and FSAR preparation, equipment sizing and specification, NSSS vendor interface for corre-spondence, drawing review, and contract administration.
1976-1978 Ebasco Services Incorporated, New York Cffice; Senior Engineer, Mechanical-Nuclear Engineering Depart tne including:
Houston Lighting & Power Co - Allens Creek NCS - Unit No. 1-1200 >M(e) BWR, Lead NSSS Engineer Louisiana Power & Light Co - Waterford SES Unit No. 3 -
Lead NSSS Engineer (Sa=e responsibilities as listed for 197S-1980 above.)
468
EBASCO SERVICES I4CetF0Alfta 4
1976-1978 Responsible for preparation and =aintenance of ECCS and (Cont'd) 30P flow diagrams, piping layouts, system design descrip-tions, inservice inspection provisions, Nuclear Island building general arrange =ents, PSAR and FSAR preparation, equipment sizing and specification, NSSS vendor interface for correspondence, drawing review, and contract adminis-tration.
1974-1976 United States Coast Guard, Marine Inspection Of fice, New York; Lieutenant - Supervisory 3 oiler Inspector.
Responsibility for supervision, assign =ent and training of Marine Inspectors in largest Marine Inspection Office in country. Inspection of hull and machinery caterial condition of U.S. flag and foreign merchant vessels, and pressure vessels under construction. Application of various laws and regulations of the United States, ASME Code, ANSI, TEMA, NEC and NFPA S tandards.
Review of j
engineering plans and alterations, reports from field and
~
resident inspectors.
1973-1974 United States Coast Guard, USCGC Spencer (WHEC-36),
Lieutenant - Chief Engineer.
Responsibility for operation,
=aintenance and repair of hull and engineering plant of 6200 slip twinscrew steamship.
Direct supervision of 40 officers and men.
Duties included preparation of repair specifications and maintenance of vessel records.
Received Coast Guard Achievement Medal for superior performance of
- duty, i
1970-1973 United States Coast Guard, Marine Inspection Office, New York, Lt and Ltjg - Marine Inspector.
Inspection of hull and machinery of U.S. and foreign flag =erchant vessels.
1968-1969 United States Coast Guard, USCCC Mellon (WHEC-717), Ensign, Assistant Engineer Officer.
467