ML19211A434
| ML19211A434 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/07/1979 |
| From: | Taboada A NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19211A429 | List: |
| References | |
| NUDOCS 7912180186 | |
| Download: ML19211A434 (4) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Docket Nos. 50-295
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50-304 COMMONWEALTH EDISON COMPANY
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(Proposed Amendment to Facilities
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Operating License No. DPR-39 and (Zion Station, Unit 1 and 2)
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DPR-48 to Permit Storage Pool Modification)
AFFIDAVIT OF ALFRED TAB 0ADA I, Alfred Taboada, being duly sworn, do state as follows:
I am employed as a Senior Materials Engineer in the Systems and Components Standard Branch, Office of Standards Development, United States Nuclear Regu-latory Coninission, on assignment to the Engineering Branch, Division of Operating Reactors, Office of Nuclear Reactor Regulation, USNRC. A statement of my professional qualifications is attached to this affidavit.
I have reviewed the Commonwealth Edison Company response, dated November 16, 1979, to the Board's Memorandum and Order of September 14, 1979, and the affidavit of Dr. John Weeks.
I agree with the general conclusions of Dr. Weeks that, while some Intergranular Stress Corrosion Cracking may not be precluded somewhere in the Zion Spent Fuel Pool, it is highly unlikely to occur in a widespread fashion, and, if it does, it should result in small cracks and minor leaks which would not significantly degrade the function or structural integrity of the fuel storage racks, the fuel pool liner or the spent fuel pool piping systems. This opinion is predicated on the assumptions that (1) the Type 304 stainless steel material is not significantly sensitized, in view of the 1599 259 1912180
[g relatively low carbon content and the measurements made by Mr. W. L. Clarke, Jr., (2) water will be circulating and the water chemistry will be maintained at the low chloride and fluoride levels, and, (3) the levels of temperature and stress are, in my opinion, unfavorable for significant stress corrosion cracking to occur.
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Alfrey Taboada Subscribed and sworn to before me this 7th day of December,1979.
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My Concission expires: July 1, 1982 1599 260
PROFESSIONAL QUALIFICATIONS OF ALFRED TAB 0ADA My name is Alfred Taboada.
I am currently employed by the U. S. Nuclear Regulatory Commission as a Senior Materials Engineer on assignment to the Engineering Branch, Division of Operating Reactors, Office of Nuclear Reactor Regulations.
My duties and responsibilities include the review and evaluation of the intergranular stress corrosion cracking problems at Three Mile Island Unit 1 and other PWR's.
I am a member of the Pipe Crack Study Group reviewing the problem in BWR's and was one of the authors of the NUREG reports issued by this group.
I also co-authored the revision to NUREG-0313 which presents guidelines for reducing susceptibility to intergranular stress corrosion cracking.
As a member of the Office of Standards Development, I was responsible for preparing and issuance of Reg. Guide 1.44 " Control of the Use of Sensitized Stainless Steel" which deals with the problem of intergranular stress corrosion cracking.
I have worked as a materials engineer and researcher for approximately 25 years at the USNRC, USAEC and the Oak Ridge National Laboratory.
I received a Bachelor degree in Chemical Engineerir.g from Newark College of Engineering and a Pasters of Metallurgical Engineering from Rensselaer Polytechnic Institute.
I am a member of Subgroup on Peterials of the Nuclear Section III of the ASME Boiler and Pressure Vessel Code and member of the executive committee of the ASTM Committee E-10 on Nuclear Applications.
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of COMMONWEALTH EDIS0N COMPANY
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Docket Nos. 50-295 (Zion Station, Units 1 and 2) 1 50-304 CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF'S RESPONSE TO MEMORANDUM AND ORDER RELATING TO INTERGRANULAR STRESS CORROSION CRACKING IN STAINLESS STEEL TYPE 304 COMPONENTS OF SPENT FUEL STORAGE P00L" in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Commission's internal mail system, this 7th day of December,1979.
Atomic Safety and Licensing Board John F. Wolf, Esq., Chairman Panel 3409 Shepherd Street U.S. Nuclear Regulatory Conmission Chevy Chase, Maryland 20015 Washington, D. C.
20555 Dr. Linda W. Little Atomic Safety and Licensing Appeal 5000 Hermitage Drive Board Panel Raleigh, North Carolina 27612 U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Forrest J. Remick Docketing and Service Section 305 E. Hamilton Avenue U.S. Nuclear Regulatory Commission State College, Pennsylvania 16801 Washington, D. C.
20555
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Philip P. Steptoe, Esq.
Mr. Gregory Minor Isham, Lincoln and Beale MHB' Associates One First National Plaza 1723 Hamilton Avenue, Suite K Chicago, Illinois 60603 San Jose, California 95125 Susan N. Sekuler, Esq.
/g Assistant Attorney General Environmental Control Division 188 West Randolph Street, Suite 2315 Chicago, Illinois 60601 Ric ard J. Goddard sel M MaH Mr. Rick Konter 617 Piper Lane Lake Villa, Illinois 60046
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