ML20031H482

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Testimony of Ma Lugo Re Tx Pirg Addl Contention 6 on Mannings Coefficient & ASLB Question on Svc Level Stress Limits.Margin of Safety Above Design Pressure at 15 Psig Is 35 Psig.Prof Qualifications
ML20031H482
Person / Time
Site: Allens Creek File:Houston Lighting and Power Company icon.png
Issue date: 09/18/1981
From: Lugo M
EBASCO SERVICES, INC., HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20031H319 List:
References
NUDOCS 8110270529
Download: ML20031H482 (6)
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Text

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Soptemb3r 18, 1981 1

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 2

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 3

In the Matter of S

4 S

HOUSTON LIGHTING & POWER C MPANY S

Docket No. 50-466 5

5 (Allens Creek Nuclear Generating S

6 Station, Unit 1)

S 7

DIRECT TESTIMONY OF MIGUEL A. LUGO O

CONCERNING (1) TEXPIRG ADDITIONAL CONTENTION 6 - MANNINGS COEFFICIENT; 9

(2) BOARD QUESTION ON SERVICE LEVEL STRESS LIMITS 10 11 Q.

Would you please state your name and position, and 12 describe your educational and professional qualifications?

A.

My icne is Miguel A. Lugo and I am employed by 13 Ebasco Services Inc.

I am in charge of the design of the 14 ACNGS containment vessel and reactor building foundation mat.

A description of my educational and professional back-ground is described in Attachment MAL-1.

Q.

Mr. Lugo, would you please answer the first question asked by the Board at page 8 of the September 1 19 Order, wherein the Board asked a question about the margin 20 of safety in the containment?

21 A.

We have performed preliminary calculations that 22 indicate the Allens Creek containment can withstand 23 approximately 50 psig internal static pressure before 24 reaching its yield strength.

Therefore, the " margin of 8110270529 010918' PDR ADOCK 05000466 PDR T

~

1 safety" above the design pressure of 15 psig is approxi-2 mately 35 psig.

No calculations have'been done to determine at 3

what pressure containment failure will occur.

In structural 4

design, it is not common practice to design against failure, 5

but rather against specific Code limits.

However, it can be 6

said that containment failure will not occur until the 1

internal static pressure is significantly in excess of 50 psig.

This is based on the fact that the total ultimate strength of materials such as concrete and steel greatly 10 exceeds the yield strength.

Therefore it is concluded that 11 unless the incremental static pressure in the containment 12 exceeds the design pressure by substantially more than the 1~3

" margin of safety" shown above, containment failure would 14 not be a concern.

15 With regard to the leakage question in designing 16 tne containment structure, the details for weld seams, 17 penetrations, etc. are c'evelcped to form a completely 1-sk 18 tight barrier.

The actual leakage of tiie as-built contain-19 ment due to a design basis LGCA will be determined by the 20 pre-operational leakage test committed to in the PSAR and 21 compared for comformance with the maximum allowed leakage rate a.lso committed to in the PSAR.

22 Q.

Have you read the question by the Board at Tr.

23 16289 about Service Level C Limits?

24 1

A.

Yes I have.

2 Q.

Can you answer the Board's question?

A.

Yes I can.

The ASME Boiler and Pressure Vessel 3

(B&PV) Code identifies various stress limits for different 4

loading conditions by categorizing these conditions under 5

specific " Service Levels" (A thru D).

In order to be conser-vative, the lowest stress limits (Service Level A) are used 7

for the basic design accident loading cases, including the 15 8

psig design pressure case.

For more extraordinary loading 9

cases, the higher Service Level C stress limits must be met.

10 These higher limits are generally in the range of yield 11 stress.

l'*

The ACNGS containment design actually is not 13 governed by the 15 psig design pressure, but rather by 14 various pool dynamic loads.

Thus, the design has, in effect, 15 inherent extra strength for purely pressure loadings.

Under 16 Service Level C Limits, this pressure capability is actually -

17 above the 42 psig mentioned in Mr. Fields' testimony.

18

\\

19 20 21 22 23 24

. J

r 1

Attachment MAL-1 MIGUEL A. LUGO EXPERIENCE

SUMMARY

Registered Professional Engineer with-seven years experience in structural analysis and. design of various nuclear utility projects.

Responsible for developraent of design criteria, supervision of design and preparation of specifications for BWR Mark III containment structures (containment vessel, bottom liner, embedded supports, foundation mat, platforms and sump liners.

Responsible for structural analysis for research fusion reactor project, including finite element analysis involving development of and alterations to project-oriented computer programs, as well as use of those general programs commer-cially available.

Responsible for design of PWR steel structures, including design calculations and detailing for various buildings in the plant.

EMPLOYMENT HISTORY:

Ebasco Services Incorporated, New York, N.Y.; 1974-Present EDUCATION:

Nek York University - BECE - 1974 New Jersey Institute of Technology - Courses towards MSCE -

In Progress REGISTRATIONS:

Professional Engineer - New York PROFESSIONAL AFFILIATIONS:

ASCE - Associate Member i

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