ML17193A524
| ML17193A524 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/03/1980 |
| From: | Brooks W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17193A517 | List: |
| References | |
| NUDOCS 8011070225 | |
| Download: ML17193A524 (3) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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Docket Nos. 50-237 COMMONWEALTH EDISON COMPANY
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50-249
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(Spent Fuel Pool Modification)
(Dresden Station, Units 2 and 3)
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AFFIDAVIT OF WALTER L. BROOKS AMENDING SAFETY EVALUATION REPORT I, Walter L. Brooks, do state as follows:
I am employed by the United States Nuclear Regulatory Commission as a Senior Reactor Phys~cist in the Core Performance Branch of the Division of Systems Integration. A statement of my professional qualifications is attached to this affidavit.
I have reviewed the changes contained in Revision 3 to "Licensing Report",
Dresden Nuclear Power Plant, Units 2 and 3, Spent Fuel Rack Modification (QUAD.;. 1-79-234).submitted by; Commonwealth Edison by letter dated October 29, 1980.
My review was limited to those aspects of the
. revision which relate to the nuclear criticality of the racks.
Description of Changes The sole change in Revision 3.i~pacting on criticality was an increase in magnitude of one of the uncertainty factors-included in the reactivity analysis - that due to a possible reduction in center-to-center spacing of the storage location in the racks. This factor had previously been taken as zero but was increased.to allow for tolerance pile-up in Revision 3.
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- Analysis of Changes 1he uncertainty in center-to-center spacing has been determined to be + 0.006 in the multiplication factor. However, the value of the multiplication factor, with all uncertainties added, is still only 0.927 even with the revised uncertainty value. Thus a margin of 0.023 still exists to our acceptance criterion of 0.95 for this value.,
Conclusion Based on my review of "Revision 3 to the criticality analysis of the Dresden fuel racks I conclude that no revision to the Safety Evaluation Report need be made in the area of criticality considerations.
I swear that the foregoing is true and correct to the best of my knowledge and belief.
Sworn to before me this 3rd day of November, 1980 cfJ~{kw.~
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My CoJTDTiission Expires:
July 1, 1982 Walter L. Brooks
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~alter L. Erool:s Present Enploymcnt - I joined the Nuclear Retulatory Cor.:.::*ission (then the Ato~ic ~nergy Cor.iuission) in September of 1974.
I ~m a member of the Core Performance Branch of the Division of Systc~s Safety with the title of ?;uclear Engineer.
In my position, I have prir.ary review responsibility for core physics aspects of lic~nsing submittals and, upon request from the Auxiliary Systems Branch, the criticality as~ect of fuel storage facilitie~.
Education -
B.A. in P~thematics, Lincoln Menorial University, 1943 M.S. in Physics, New York University, 1950 Ph.D. in Physics, New York University, 1953 Previous Eoployment - Gulf-United Nuclear Corporation and its predecessor companies, United Nuclear Corporation, Nuclear Developnent Corporation of America, and 'Nuclear Development Associates.
}ly duties, during my euploy.:..
tf.:nt* from 1953 to 1974, included the follo~ing:
Publications
- Performance and evaluation of critical experiments for n2o moderated latices
- Performance and evaluation of li&ht ~ater moderated lattice critical e~-periments
- Perf orroance and evaluation of fast reactor critical experimelltS
- Development of calculation methods for D20 moderated reactors
- Verification and mof if ication of a nodal calculation technique,for light water reactors*
Numerous reports on the results of critical experiments and methods development.
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