ML20040H306
| ML20040H306 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/12/1982 |
| From: | Shum D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18023A006 | List: |
| References | |
| NUDOCS 8202180061 | |
| Download: ML20040H306 (5) | |
Text
-
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING.B0ARD In the Matter of TEXAS UTILITIES GENERATING COMPANY, Docket Nos. 50-445 et al.
50-446 (Comanche Peak Steam Electric
)
Station, Units 1 and 2)
)
AFFIDAVIT OF DAVID H. SHUM I, David H. Shum, being duly sworn, do depose and state the following:
Q1. By whom are you employed, and what is the nature of the work you perform?
A1.
I am employed as a Senior Containment Systems Engineer in the Containment Systems Branch of the Office of Nuclear Reactor Regu-lation, U.S. Nuclear Regulatory Comission. A statement of my professional qualifications, including the nature of the work that I perform, is attached to this affidavit.
Q2. What is the nature of the responsibilities you have regarding the Comanche Peak Steam Electric Station ("CPSES")?
A2.
I was responsible for the review of Sections 6.2.1 through 6.2.6 of the CPSES Final Safety Analysis Report ("FSAR"), with regard to the adequacy of the containment systems.
L F202190061 820212 gDRADOCK05000
~_.
- Q3. Would you describe the scope of the subject matter addressed in your affidavit?
A3.
I will address Contention 2, which alleges that:
One or more of the reports used in the construction of computer codes for the CPSES/FSAR have not been suitably verified and formally accepted; thus con-clusions based on these computer codes are invalid.
In particular, I will address whether the facts presented in para-graphs 2 and 3 of the Applicants' " Statement of Material Facts As To Which There Is No Material Dispute Regarding Contention 2" (" Statement of Material Facts"), with regard to NRC Staff acceptance of Report 28, WCAP-8326, and NRC approval in Section 6.2 of the CPSES Safety Evaluation Report ("SER") of the Applicants' analyses using Report 7 are correct; and if the Staff supports the Applicant's position.
Q4. Have you read, and do you agree with paragraph 2 of Applicants' Statement of Material Facts relating to Staff acceptance of Report 28?
A4.
I have read paragraph 2 of Applicants' Statement of Material Facts, and I agree with that paragraph with regard to NRC Staff's acceptance of Report 28.
QS. Have you read, and do you agree with paragraph 3 of Applicants' Statement of Material Facts regarding NRC Staff acceptance of the C
particular sequence of events which is based upon Report 7, WCAP-7909?
AS. I have read, and I disagree with paragraph 3 of Applicants' Statement of Material Facts, with regard to NRC Staff acceptance in the CPSES SER Section 6.2 of the Applicants' analyses using Report 7.
Report 7, WCAP-7909 " MARVEL, A Digital Computer Code for Thermal Transients In a U0 Fuel Rod" (June 1972) was not 2
referenced by. Applicants in Section 6.2 of the CPSES FSAR. The Staff did not base its safety conclusions on the CPSES containment on a review of Report 7.
Q6. Describe the subject matter of WCAP-8326?
A6. This topical report, WCAP-8326, " Containment Pressure Analysis Code (C0CO)", was submitted by Westinghouse Electric Corporation for NRC Staff evaluation and acceptance during July,1974, as part of its Emergency Core Cooling System ("ECCS") evaluation model. The C0C0 computer code predicts the temperature and pressure response of a reacter building to a loss of coolant accident ("LOCA"). The code has the capability of analyzing the effectiveness of the engineered safeguards system for the containment, including internal and external sprays, containment venting, and ventilation fan coolers. The Appli-cants referenced Report 28 in Section 15.6.5.3 of the FSAR for CPSES.
Report 28 was accepted as part of the Staff's review and acceptance of the ECCS evaluation model on May 30, 1975.
. Q7. Was Report 7 referenced by the Applicants in Section 6.2 of the FSAR for CPSES; and did the Staff rely on Report 7 in its conclusion in the CPSES SER regarding the safety of the CPSES containment?
A7. No.
The above statements and opinions are true and correct to the best of my personal knowledge and belief.
David H. Shum Subscribed and sworn to me, a Notary Public on the County of Montgomery, State of Maryland, thisp Aday of February,1982.
on n Mo J$n 490taty Publi4
[~
My Comission expires:
/s / [
l l
l l
l
DAVID H. SHUM PROFESSIONAL QUALIFICATIONS I am a Senior Containment Systems Engineer in the Containment Systems Branch of the Nuclear Regulatory Commission. In this position I am responsible for the technical analysis and evaluation of the public health and safety aspects of containment systems.
.,From September 1980 to June 1981 I was assigned to review the Final Safety A'nalysis Report for Comanche Peak Steam Electric Station, Units 1 and 2.
I participated in the preparation of NUREG-0797. " Safety Evaluation Report Re-lated to the Operation of Comanche Peak Steam Electric Station Units 1 and 2."
Prior to September 1980, I have had about 14 years of experience in the nu-clear engineering field.
I received a Master of Science (M.S.) degree in Mechanical Engineering from' North Carolina State University in 1966 and a Bachelor of Science (B.S.) de-'
gree in Mechanical Engineering from the National Taiwan University in 1963.
I am a registered Professional Engineer in Ohio and Pennsylvania.
G b
j.....
l
.