ML20040H243
| ML20040H243 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/12/1982 |
| From: | Elliot B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18023A006 | List: |
| References | |
| NUDOCS 8202170493 | |
| Download: ML20040H243 (5) | |
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UNITEn STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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TEXASUTILITIESGENERATINGCOMPANY.)
Docket Nos. 50-445 g AL.
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50-446 (Comanche Peak Steam Electric Station, Units 1 and 2)
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AFFIDAVIT OF BARRY J. ELLIOT ON CONTENTION 2 1, Barry J. Elliot, being duly sworn, depose and state:
Q1. By whom are you employed and describe the work you perform?
A1.
I am employed by the U.S. Nuclear Regulatory Comission as a Materials Engineer in the Material Engineering Branch, Division of Engineering, Office of Nuclear Reactor Regulation. A copy of my statement of pro-fessional qualifications is attached to this affidavit.
Q2. Would you describe the nature of your responsibilities you have had regardingtheComanchePeakSteamElectricStation(CPSES)?
A2.
I participated in the evaluation of the Applicants' finite element analysis and analytical stress intensity factor solution, to determine if the Applicants' pump flywheels for CPSES conform to General Design Criterion 4.
8202170493 820212 PDR ADOCK 05000445 O
_2-Q3. Would you describe the scooe of the subject matter addressed in your affidavit?
A3.
I have been asked to address Contention 2, which states that:
One or more of the reports used in the construction of computer codes for the CPSES/FSAR have not been suitably verified and fonnally accepted; thus conclusions based on these computer codes are invalid.
In particular, I have been asked to determine if the facts presented in paragraph 3 of the Applicants' " Statement of Material Facts As to Which There is No Genuine Issue Regarding Contention 2" (" Statement of Material Facts"), with regard to the NRC Staff acceptance of the Applicants' analysis of the reactor coolant pump flywheel integrity in LOCA, are correct; and if the NRC Staff supports the Applicants' position.
I have also been asked to detennine if Report 9, WCAP-8163, " Reactor Coolant Pump Integrity in LOCA", dated September 1973, as referenced by the Applicants for verifying reactor pump flywheel integrity in CPSES FSAR Section 5.4.1.1, constructs, provides verification, and requests Staff approval and acceptance of any computer codes.
Q4. Have you read paragraph 3 of the Applicants' Statement of Material Facts, relating to the issues you are addressing, and do you concur with that portion of the Statement?
A4. Yes.
- 05. What is the subject of Report 9, and how did the Staff evaluate the CPSES pump flywheel integrity during LOCA?
3-A5. Report 9 WCAP-8163 was submitted by Westinghouse, and describes the behavior of reactor coolant pumps under the condition of loss of coolantaccident(LOCA). This topical report was referenced by the Applicants in FSAR Section 5.4.1.1 to demonstrate the integrity of the pump flywheels during LOCA, by a discussion of ductile and brittle fracture evaluations.
The brittle fracture evaluation demonstrates the integrity of the pump flywheels during LOCA utilizing an analytical stress intensity factor solution, and a finite element analysis. The NRC Staff has cross-checkedthefiniteelementanalysis1/withtheanalytical stress intensity factor solution employed by Westinghouse,2_/ and a secondanalyticalstressmethodwhichwasperformedbytheStaff3/
The results of these analyses were used by the Staff to detennine the margins for safe operation of the flywheels. Based on those calculated margins the NRC Staff determined that the Applicants' reactor coolant pump flywheels confonn to General Design Criterion'4.
-1/
S.E. Gabrielse, " User's Manual for Westinghouse Research General Purpose Finite Element Programs", Westinghouse Research Report 70-1E7-PDP SC-R1 (April 23, 1970)(Westinghouse Nuclear Energy Systems Proprietary).
-2/
Williams, J.G. and Isherwood, D.P., " Calculation of the Strain Energy Release Rates of Cracked Plates by an Approximate Method",
c General Strain Analysis, v.3, No.1 (1968).
3/
Tada, Hiroshi, The Stress Analyses of Cracks Handbook, Del Research Corp. (August, 1973).
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..Q6.
Does Report 9, as referenced by the Applicants in the CPSES FSAR Section 5.4.1.1, construct, verify, and request NRC Staff evaluation and acceptance for any computer code?
A6. No.
The above statements and opinions are true and correct to the best of my personal knowledge and belief.
d bay Barrf J.~ Elliot Subscribed and sworn to before me, s
this /,2& day of February,1982 y
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e5tATEMENT OF PROFESSIONAL QUALIFICATIONS BARRY J. ELLIOT U.S. NUCLEAR REGULATORY COMMISSION t
MATERIALS ENGINEERING BRANCH, DIVISION OF m
ENGINEERING, NUCLEAR REACTOR REGULATION I am currently employed as a Materials Engineer in the Materials s
Engineering Branch, Division of Engineering, Office of Nuclear Reactor Regulation.
I am responsible for review and evaluation of safety analysis reports which are related to the material engineering aspects of components in nuclear power plant systens, and for providing technical assistan e to Offices of NRR, I&E and RES in related reactor safety matters.
I have been a member of the Materials Engineering Branch since March 31, 1980.
I was a full-time student at Rensselaer Polytechnic Institut'e, where k
in 1968, I received a Bachelors Degree in Ma Engineering.
I attended evening classes at Fairleigh Dickenson University, where in 1971, I received a Masters Degree in Business Administration.
I was employed by Curtiss Wright Corporation from 1968, when I grad-uated from Rensselaer Polytechnic Institute, to 1980, when I was employed by the NRC. From 1968 to 1971 I worked in the Materials Development Laboratory of the Aeronautical Division where I perfortned failure analysis of reciprocating and gas turbine engines, and developed test apparatus to evaluate material reliablity.
From 1971 to 1980 I worked in the Nuclear Division where I was responsible for developing'and implementing non-destructive examination test procedures and fusion weld procedures for i
j inspection and fabrication of Navy Nuclear Pressure Vessels.
I am a member of the American Society of Metals.
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