ML20023C074
| ML20023C074 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/05/1983 |
| From: | Diab S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20023C059 | List: |
| References | |
| NUDOCS 8305090618 | |
| Download: ML20023C074 (5) | |
Text
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a UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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TEXAS UTILITIES GENERATING COMPANY,)
50-446 (Comanche Peak Steam Electric
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Station, Units 1 and 2)
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AFFIDAVIT OF SAMMY DIAB I, Sammy Diab, being duly sworn, do depose and state:
Q.1. By whom are you employed, and what is the nature of the work you perform?
A.1. I am employed by the U.S. Nuclear Regulatory Comission, Division of Systems Integration, Reactor Systcms Branch ("RSB"). A copy of my statement of qualifications is attached to this affidavit.
i Q.2. What is the nature of the responsibilities you have regarding the Comanche Peak Steam Electric Station ("CPSES")?
l A.2. I was the reactor Systems Branch lead reviewer for CPSES.
In this capacity, I was responsible for the safety review of the CPSES Final Safety Analysis Report ("FSAR") Sections 5.2.2, 5.4.7, 6.3 and 15, in accordance with the corresponding sections in the Standard Review Plan, NUREG-0800.
r305090618 830505 PDR ADOCK 05000445 O
Q.3. What is the subject matter of your affidavit?
A.3. In reference to the Semiscale feed and bleed experiment (S-SR-2) and the related subsequent RELAP-5 analyses, the Atomic Safety and Licensing Board (ASLB) inquired about the implications for the Comanche Peak Units 1 and 2 feed and bleed operation. Specifically, Dr. McCollom asked whether a feed and bleed analysis has been done for Comanche Peak (See Transcript of April 7,1983, Conference Call, at16).
I will also address Dr. Jordan's question concerning whether "the Comanche Peak high-pressure injection systems will work against the safety valves so that feed and bleed is possible or whether it would require the operation of the PORV?" Tr. 33.
Q.4. Has a feed and bleed analysis been performed for Comanche Peak and if so, what are the results?
A.4. The staff has not performed a plant-specific analysis of feed-and-bleed for Comanche Peak.
In a topical report WCAP-9744, " Loss of Feedwater Induced Loss of Coolant Accident Analysis Report", May 1980, Westinghouse analyzed the feed and bleed operation for a generic four loop plant. The analysis assumptions, namely the power level, RCS volume-to-power ratio, PORVs capacity-to-power ratio, and safety injection shutoff head are representative of the Comanche Peak Plant. That topical report was provided in support of the Westinghouse emergency guidelines. The topical report analyses show that if the PORVs were opened by the operator early in the transient following the total loss of feedwater a sustained feed and bleed decay heat removal may be obtained. The safety injection was assumed to start automatically on low system pressure.
Q.5. Will the high pressure injection system at CPSES discharge against the safety valve opening pressure or will it require the operation of the PORVs?
A.5. Comanche Peak has two centrifugal charging pumps (CCPs), each is sized to deliver 150 gpm (includes the mini flow) against a system pressure of 2500 psia which is the safety valves opening setpoint.
The combined CCPs flow at that pressure may not be adequate to establish and sustain a stable feed and bleed mode of decay heat removal, especially since CCP flow-head characteristics degrade with pump service life. However, at lower pressures the CCPs discharge will increase. Furthermore, Comanche Peak's ECCS is provided with two safety injection pumps, each is sized to deliver 425 gpm against a system pressure of 1200 psia. Since the CCPs and the safety injection pumps will deliver adequate flow only at relatively low system pressures, the PORVs would have to be operated manually in a timely manner to establish and maintain a stable feed and bleed.
l I hereby certify that the statements and opinions given are true and correct to the best of my personal knowledge and belief.
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Diab l
Subscribed and sworn to before me this y & day of May, 1983 WW $-
l Notary Public My comission expires:
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STATEMENT OF PROFESSIONAL QUALIFICATIONS SAMMY S. DIAB I am a Nuclear Engineer in the Reactor Systems Branch of the U.S.
Huclear Regulatory Ccmmission (NRC).
In this position, I'am responsible
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for the technical analysis and evaluation of reactor systems, accidents and transients, and applicatio.ns for nuclear reactor operating licenses.
I have been in my current position since 1980.
From 1978 to 1980, I was a reactor systems reviewer in the Reactor Safety Branch, Division of. Operating Reactcrs of the NRC.
In that position qy responsibilities included:
systems analyses, accident and transient ar.alyses, and reload application reviews.
From 1977 to 1978, I was a Nuclear Engineer in the Engineering In that Methodology Standards Branch, Office of Standards of the NRC.
position I was responsible for updating and revising the standard review I developed Regulatory Guide 1.139, "Residu.al. Heat Removal Guidance",
plan.
and Regulatory Guide 1.141, " Containment Isolation Provisions for Fluid Systems".
From 1973 to 1977, k was a Nuclear Engineer wit.h Bechtel Power I was responsible Corporation, Gaithersburg Power Division, Maryland.
for reactor containment pressure and temperature analyses following a j
spectrum of high energy line breaks, jet impingement calculations, and subccmpartmen't" transient behavior.
I developed and used computer codes.
t I also modified existing computer codes.
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O p From 1971 to 1973, I was a research assistant with the Nuclear Engineering Department of the Pennsylvania State University. In 1974 I was awarded a M.S. degree in Nuclear Engineering from Pennsylvania State University.
From 1967 to 1971, I was a researcher with the Egyptian Atomic Energy Establishment.
In 1967 I received my B.S. degree in Nuclear Engineering from the University of Alexandria, Egypt.
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