ML19347F537

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Testimony of Ma Ross Re Board Question 8,Seismic Category 1 Control Rods.Prof Qualifications Encl.Related Correspondence
ML19347F537
Person / Time
Site: Allens Creek File:Houston Lighting and Power Company icon.png
Issue date: 05/11/1981
From: Ross M
GENERAL ELECTRIC CO.
To:
Shared Package
ML19347F516 List:
References
NUDOCS 8105190564
Download: ML19347F537 (5)
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Text

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5-11-81 g WTED CORRgsPONDENG UNITED STATES OF AMERICA M 1

NUCLEAR REGULATORY COMMISSION [{

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1319813 f^)'s i 2 "Q BEFORE Tile ATOMIC SAFETY AND LICENSING BOAR Ddg~

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3 4 In the Matter of )

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NM IlOUSTON LIG.i1ING & POWER COMPANY) Docket No. 50-4F; 5

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6 (Allens Creek Nuclear Generating)

Station, Unit No. 1) )

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8 TESTIMONY OF MONTY A. ROSS ON BEHALF OF HOUS'2ON LIGliTING & POWER CO. ON BOARD QUESTION 8 9 __

- SEISMIC CATEGORY l CONTipL RODS 10- Q. P. Nase state your name and place of ertployrrant.

11 A. My name is Monty Ross and i e employed as Manager 12 of Data Acquisition and Operator Systems, the General 13 Electric Company. My business addreas is 175 Curtnd 14 Avenue, San Jose, California.

15 Q. Would you describe your professional qualific cions?

16 A. My professional ga.lifications are set forth in Exhibit 17 MAR-1 to this testimony.

18 Q. What is the purpose of your testimony?

19 A. The purpose of my testimon:r is to address Loard Question 20 8 which questions whether the control tods, control rod 21 drives and the hydraulic control units should be designed as 22 Seismic Catagory I in accordance with Regulatory Guide 1.29.

23 Q. What a2.e the requirements of Regulatory Guide 1.29 with 24 regard to the Control Rod Drive (CRD) System?

l 25 A. Regulatory Guide 1.29 requires that reactor vessel l 26 internals and reactivity control systems, e.g. control rods 27 and control rod drives, be designated as Seismic Category 1 28 and be designed to withstand t.he effects of a safe shutdown 610519c @ 4 -

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1 2- earthquake and rer.;in funct.!onal ,

0 Are the cot;crol rods, control rod drives, and the 3

4 hydraulic control units for F.i ens Creek designated as 5 Seismic Category I in accordance with Regulatory Guide 6 1.29 requirements?

7 A. Generally all systems, equipment, components, and g structures designated as Safety Class 1, 2, or 3 are 9 classified as Seismic Category I (see Section 3.2.1 of 10 ACNGS PSAR). This would include the following portions 11 of the Control Rod Drive System.

12 a. L J housing supports 13 b. Control rods 14 c. CRD's 15 d. valves on scram discharge volume insert, and 16 withdraw lines.

17 c. Piping for scram discharge volume, insert and 18 return lines.

19 f. Hydraulic Control Unit i 20 Therefore, all portions of the CRD System necessary to 21 shutdown the reactor are classified as Seismic Category I.

22 Q. What, if any, is the significance of CRD components l 23 being designated as Safety Class 2 in Table 3.9-4 of the i

24 ACNGS PSAR?

l 25 A. Components are classified as Safety Class 1, 2, 3 or 26 as non-safety in accordance with the importance of the 27 function they are to perform. As previosly indicated, 28 generally all Safety Class 1, 2, and 3 (including the

1 1 _3-2 previously listed CRD components) coniponents are classified 8 as Seismic Category 7.

4 Q. What are your conclusions?

5 A. Safety Class components of the CRD syctem, including 6 control rods, control rod drives, and 1.ydraulic control 7 units are classified as Seisri.c Category !.

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5 1 Exhibit MAR-1 2 EDUCATION AND PROFESSIONAL QUALIFICATIONS 3 Monty A. Ross 4 Mr. Ross is a manager in the Nuclear Steam Supply 5 Systems design organization of the General Electric Nuclear 6 Energy Business Group, in San Jose, California. His employ-7 - nt with General Elect-ic began in 1972, as a's Engineer 8 .c the Det'.e, Engineering section, where he worked on the 9 design and analyses of pressure vessel compe ants, nuclear f

10 piping systems, refueliac. end servicing tools.

11 Starting in 1975, Mr. Poss participated in a career 12 developing program of rotating assignments. Major activities 13 while on this program included the experimental testing of 14 primary containment designs in the evaluation of the thermo-15 d'.*namic transients which may (hypothetically) occur within 16 tL primary containment as a result of a LOCA and non-LOCA 17 events.

18 In February 1979, he took the position of Lead System 19 rngineer (LSE) for the Rod Control System. As the LSE, 20 he was responsible for the design definition of the Rod 21 Control System. Major tasks in this position included 22 gaining NRC acceptance of the Control Rod Drive System return 23 line removal and directing the evaluation and design changes 24 resulting from the Browns Ferry 3 partial scram insertion 25 of June 28, 1980. In October 1980, Mr. Ross assumed his 26 present position as a manager in the Nuclear Steam Supply 27 System design organization. The group that he manages is 28 responsible for the design definition of six (6) BUR Standard

1 2- Plant systems including the Rod Control System.

3 Mr. Ross is a 1972 graduate of the University of 4 California at Davis, with a BS Degree in Mechanical Engineering 5 (power generation option) and in Material Science. In 1977, 6 he received an MS Degree in Mechanical Engineering from the 7 University of Santa Clara. Mr. Ross is a registered pro-8 fessional Engineer in the State of California.

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