ML20052B190
| ML20052B190 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/26/1982 |
| From: | Malur S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), NUS CORP. |
| To: | |
| Shared Package | |
| ML20052B185 | List: |
| References | |
| ISSUANCES-OLA, NUDOCS 8204300136 | |
| Download: ML20052B190 (7) | |
Text
g UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE TIIE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
) Docket No. 50-155-OLA CONSUMERS POWER COMPANY
) (Spent Fuel Pool
)
Modification)
(Big Rock Point Nuclear Power Plant)
)
't AFFIDAVIT OF SAMPATil MALUR DISTRICT OF COLUMBIA: SS:
I, Sampath Malur, of lawful age and being first duly sworn, hereby depose and say:
1.
I reside at 20416 Ryecroft Court, Gaithersburg, Maryland 20879.
I have been employed by NUS Corporation, an
~
engineering services firm in Gaithersburg, Maryland, since May 1973.
I am currently a Project Manager in the Engineering Division.
I was one of the NUS Project Managers during the initial phases of Consumers Power Company's Big Rock Point Plant Spent Fuel Rack project.
My duties included approval of the fabrication drawings aad specification.
My resume is attached to this statement.
2.
Based on my educational background and work experience, I believe I am qualified to answer the Atomic Safety and Licensing Board's question s_tated on pages 38 and 8204 30 o f J
. 39 of the Memorandum and Order (Concerning Motions for Summary Disposition) dated February 19, 1982.
The Board specifically asked if " techniques will be employed in the manufacture" of the Big Rock Point spent fuel racks to minimize sensitization to corrosion due to cold work and welding.
This question deals with Christa-Maria Contention 3.
3.
The specifications and drawings which were used by Consumers Power Company to procure the spent fuel racks for the proposed expansion of the Big Rock Point spent fuel pool were developed by the NUS engineering staff and were approved by me.
Speedway Machine and Tool Co.,
located in Indianapo-lis, Indiana, was selected by Consumers Power Company to fab--
ricate the racks in accordance with those specifications and drawings, and that fabrication is in progress.
The material specified for use in the fabrication of the racks was ASTM type 304 stainless steel.
Consideration was given to tech-niques fy,at would be used during fabrication either to avoid or to minimize sensitization of the stainless steel material due to cold work and welding during the fabrication process.
j 4.
COLD WORK.
The materials specification for the racks requires that prior to fabrication, the ASTM type 304 stainless steel be given annealing heat treatment.
Specifi-cally, the materials specification stated:
. Material condition to be hot rolled, annealed, pickled, and unsensitized.
Moreover, the design of the racks is such that there is no bending of the material because all of the individual parts of the rack are assembled by welding.
Thus, the materials specification provided the protection suggested by Mr. Birkle in his September 28, 1981, affidavit.
5.
WELDING.
As Mr. Birkle stated in his affida-vit, sensitization of ASTM type 304 stainless steel can be controlled during the welding process by minimizing the time the weld heat-affected zone spends in the 850*P to 1450*F temperature range.
Normal welding techniques are designed to l,
achieve this objective.
However, when it is necessary to insure that the welding process be precise in controlling temperature in the heat-affected zone, welding procedures and welder qualification requirements uniquely tailored.to this objective are prepared and verified by rigorous quality assurance.
These controlled welding procedures are generally used in the fabrication of systems that experience harsh environments during operation, e.g.,
reactor piping for l
primary systems.
6.
These stringent welding procedures were not needed for the fabrication of the Big Rock Point racks, and
l hence, they were not employed.
Ucids for the spent fuel racks are small, fillet welds, 1/2 inch or less, and one butt weld.
For these welds, the time spent by a welder in the heat-affected zone is inherently very short because of the small size of the weld pass.
This short duration, coupled with controlled heat input and rapid cooling in air, necessarily means that the length of time the weld zone is at the 850*F to 1450*F temperature is short.
The fabricator's welding proce-dures containing these welding parameters and welder quali-fications were carefully reviewed and then approved by NUS and Consumers Power Company.
7.
Finally, the racks will be placed in a spent fuel pool environment that is essentially benign from the point of view of stress corrosion cracking.
This judgment was made after reviewing the plant water chemistry specifications for the spent fuel pool at Big Rock Point.
As recognized by Mr. Birkle at page 4 of his affidavit, the spent fuel pool o
environment was the most important reason for not requiring i
additional special or uniquely controlled welding procedures to minimize material sensitization from welding.
8.
CONCLUSION.
Techniques are being employed in
(
the fabrication of the spent fuel racks to avoid sensitization 1
due to cold work.
The welding procedures used are adequate t
-S for the intended application, namely, the fabrication of the racks.
The special welding procedures described above to minimize sensitization were unnecessary because of the size and type of welds and the benign nature of the Big Rock Point spent fuel pool environment.
s 1
1 wij)) f f )(c th
JW Subscribed and sworn to before me this c::94I,. L day of g7/2A,'/, 1982.
/~
Notary tiblic My Commision Expires January 1,1987 l
l l
l l
I I
i l
w
S. K. M ALUR EDUCATION Institute of Science, Bangalore, India, M.S., Power Engineering (Mechanical),1959 University of Mysore, B.S., Mechanical Engineering,1957 Calder Operations School, England, Reactor Operations Course,1962 REGISTRATION Professional Engineer, State of Maryland,1976 Professional Engineer, State of Washington,1977 EXPERIENCE NUS CORPORATION,1973-Present Department of Atomic Energy, India, 1959-1973 NUS - Currently providing engineering supervision as Project Manager for projects involving installation of post-accident sampling systems, radwaste system modifications, and high density fuel racks. Supervised activities such as design, bid specifications and bid evaluations, vendor followup, field engineering, and cost control.
As Project Engineer, reviewed NSSS and BOP system designs for the 600-MWe Krsko plant in Yugoslavia: provided consulting assistance in all design-related taatters and assisted the client at
' the SAR review meetings with the International Atomic Energy Agency.
Served as Manager, Nuclear Engineering Department, responsible for the design of fluid systems, mechanical co nponents and structures associated with nuclear power plants such as spent fuel and new fuel racks, liquid and gaseous radwaste systems, component cooling systems, and sampling systems. Prepared and reviewed portions of safety analysis reports for BWRs and PWRs, conceptual designs for ECCS modifications for operating plants, and conceptual designs for auxiliary systems for nuclear power plants. Has also supervised review of system descriptions, flow diagrams, specifications, and evaluation of bids for the NSSS & BOP systems.
Department of Atomic Energy, India - As special assistant, assisted the director for power projects of the Indian AEC for a period of 18 months on all matters related to site selection, plant layout, safety, PERT & CPM, cost estimates, bid selection, and design and construction progress monitoring for three CANDU type nuclear power projects, each consisting of two 200-MWe units.
As design coordinstor, supervised the work of architect-engineers on the design of balance of plant items (secondary, process, service, liquid and solid radweste systems, etc.) and coordinated interface areas between nuclear designers and the A-E. Reviewed system designs with safety and regulating authorities, supervised scheduling and critical path networks, and coordinated quality assurance groups, for a CANDU-type nuclear power plant consisting of two 200-MWe units in Madras, India.
As erection superintendent, supervised the installation of nuclear equipment, piping, ventilation systems, bid evaluation, and contract management for installat.on of subsystems for a nuclear power plant consisting of two 200-MWe units in Rajasthan, India.
oo h
Operated a 40-MWt research reactor as a shift erigineer and designed in-core and out-of-core test facilities. During the construction and commissioning phases of this reactor, was assigned to assist the engneers (Shawinigan Engineering Company of Canada)in testing and commissioning of primary and process systems.
NLIS CC APC AATION
~
l n
s.
~
x
S. K. M ALUR
. age Two Assigned to the Central Electricity Generating Board, London, UK,8or a period of 6 months to work on bid evaluation for gas-cooled reactors.
Assigned to Atomic Energy of Canada, Ltd., Toronto, for a period of 8 months to work on fuel engineering, physics and fuel vibration in flow channels for CANDU. type reactors. During this period reviawed fuel fabrication specifications and visited fuel fabrication plant for discussions with fabricatcr. Concur.ed tests to determine vibration characteristics of fuel assemblies in test loops.
MEMBERSHIPS American Nuclear Society American Society of Mechanical Engineers I
i t
l l
l
~
NUS CCAPCRATION