ML20040H295
| ML20040H295 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/12/1982 |
| From: | Rajan J N Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18023A006 | List: |
| References | |
| NUDOCS 8202180051 | |
| Download: ML20040H295 (5) | |
Text
.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of TEXAS UTILITIES GENERATING CO, et al.
Docket Nos. 50-445 50-446 (Comanche Peak Steam Electric Station, Units 1 and 2)
)
AFFIDAVIT OF JAI RAJ N. RAJAN I, Jai Raj N. Rajan, being duly sworn, do depose and state the following:
Q.1.
By whom are you employed, and what is the nature of the work you perform?
A.I.
I am a Mechanical Engineer, working in the Mechanical Engineering Branch, Division of Engineering, in the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission. A statement of my professional qualifications, including the nature of the work that I perform, is attached to this affidavit.
Q.2.
What is the nature of the responsibilities you have regarding the Comanche Peak Steam Electric Station ("CPSES")?
A.2.
I am the principal technical reviewer of the sections of the c
CFSES Final Safety Analysis Report ("FSAR") which are applicable to the Mechanical Engineering Branch.
8202180051 020212 PDR ADOCK 05000445 0
PDR Q.3.
Would you describe the scope of the subject matter addressed in your affidavit?
A.3.
I have been asked to address Contention 2, which alleges:
One or more of the reports used in the construction of computer codes for the CPSES/FSAR have not been suitably verified and fomally accepted; thus con-clusions based upon these computer codes are in valid.
In particular, I will address whether the facts presented in paragraph 2 of Applicants' " Statement of Material Facts As To Which There Is No Genuine Issue Regarding Contention 2" (" Statement of Material Facts"), relative to NRC Staff acceptance of Reports 4 and 11, are correct; and if the Staff agrees with the Applicants' position.
Q.3.
Have you read, and do you agree with paragraph 2 of the Applicants' Statement of Material Facts with regard to the subject matter you are addressing?
A.3.
I have read Applicants' Statement of Material Facts, and I agree with Applicants' Statement in paragraph 2 that the Staff has formally accepted Reports 4 and 11.
Q.4.
Describe the subject matter of Reports 4 and 11; state whether or not the report describes, constructs and presents verifica-tion for a computer code; and indicate whether or not the reports were accepted by the NRC Staff, c
A.4.
Report 4, WCAP-7832, " Evaluation of Steam Generator Tube, Tube Sheet, and Divider Plate Under Combined LOCA Plus SSE Conditions" (December 1973), evaluates the structural adequacy of steam generator tubes, tube sheet and divider plates of the Westinghouse Series 51 and Model D steam generators when subjected to simultaneous LOCA and Safe Shutdown during Earthquake ("SSE") loadings. This report was referenced by Applicants in Section 5.4.2 of the FSAR for CPSES. Report 4 does not describe, construct and provide verification for any computer codes.
Report 4 was accepted by the Staff on March 2,1978.
Report 11, WCAP-8252 " Documentation of Selected Westinghouse Structural Analysis Computer Codes, Revision 1" (July 1977), describes.
constructs and presents representative verification for eleven Westinghouse structural analysis computer codes used in the analysis and design of mechanical systems and components. Report 11 includes a code to derive a pressure-time analysis of blowdown, and a code which evaluates structural elements using a dynamic response analysis. This topical report was referenced by the Applicants in Section 3.6N of the CPSES FSAR.
This topical report was evaluated and accepted by the NRC Staff on March 2, 1978.
The above statements and opinions are true and correct to the best of my personal knowledge and belief.
Jai Raj N. Rajan Subscribed and sworn to before me this day of February, 1082.
9 Notary Public My Commission Expires:
3T.. 5. -.
-...-a
- o. ;... -.,
s..,.....,.
, :-.f*
PROFESSIONAL QUALIFICATIONS JAI RAJ N. RAJAN U. S. NUCLEAR REGULATORY COMMISSION MECHANICAbENGINEERINGBRANCH DIVISION OF TECHNICAL REVIEW I am a mechanical engineer responsible for reviewing and evaluating safety analysis reports with regard to mechanical engineering aspects of components,
- the dynamic analyses and testing of safety related systems and components and the criteria for protection against the dynamic effects associated with postulated failures of fluid systems for nuclear facilities. I am the Mechanical Engineering Branch's principal reviewer on the issue of the structural integrity and plugging criteria of degraded steam generator tubes. I am also responsible for the review and ev'aluation of' water hammer problems of a generic nature in the piping systems and' components of nuclear facilities.
(
I received a B.S. degree in 1953 from Lucknow University India majoring in Physics, Mathematics and Chemistry. In 1956 I received a b.S. in Civil Eng"ineering from Roorkee University, India majoring in Structural and Hydraulic Engineering.
In 1962 I received a M.S. degree from Duke University majoring in Applied Mechsnics and Ph.D. degree in 1966 from the same university with majors in Fluid Mechanics. From 1960 to 1962 I was an instructor in structural engineering at Duke University. From 1962 to 1966 I was employed by the U.S. Army Research 0ffice in Durham, N.C. as a 9
research engineer conducting theoretical and experimental research in
_y___.
M*_
________.____j
v
.~,,., ~,.
A:.gi.;.~.3,.'.. ;.
L W - b.,.,.; L *.;
. r cx.
. o;.5 * { '
high pressure pneumatic and hydraulic shock tubes and investigating wave propagation phenomenon in pipes. From 1966 to 1973 I worked as a project mechanical engineer and subsequently as a senior project mechanical
~
engineer at the Naval Research and Development Center at Annapolis, Md.
Major projects involved design analysis, test and evaluations of fluid piping systems and power fluid systems of advanced nuclear submarines.
, Investigations were multidisciplinary in scope utilizing advanced techniques. Mathematical models of power plant machinery and piping systems of nuclear submarines were developed and analyzed to determine system response to flow induced vibrations and hydraulic shock.
Tharmo-dynamic and hydrodynamic analyses of naval boilers and steam plants were conducted. including full scale tests.
In April of 1974 I joined the U. S. Atomic. Energy Commission prior to the formation of the U. S. Nuclear Regulatory Commission and have remained with the Mechanical Engineering Branch of the Division of Technical Review as a mechanical engineer performing the type of work as previously described.
I have taught at the University of Maryland on a part-time basis since s
1967 both at the graduate and undergraduate levels in courses of mechanics I
of materials, fluid mechanics and applied mechanics.
Publications include Journals of AIAA and ASME and I am an associate member of Sigma Xi honor society.
c
~
4
+.e...,,,
')
a
..