ML20040F998
| ML20040F998 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/08/1982 |
| From: | Hodges M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040F986 | List: |
| References | |
| NUDOCS 8202110057 | |
| Download: ML20040F998 (7) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE AT0tHC SAFETY AND LICENSING BOARD In the Matter of ARIZONA PUBLIC SERVICE
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Docket Nos. STN 50-528 COMPANY, et al.
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STN 50-529
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STN 50-530 (Palo Verde Nuclear Generating
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Station, Units 1, 2 and 3)
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AFFIDAVIT OF M. W. H0DGES ON CONTENTION NO.6B I, M. W. Hodges, being duly sworn, upon my oath state as follows:
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- 1. I am employed by the Nuclear Regulatory Commission as a Sectidn Leader in the Reactor Systems Branch, Office of the Nuclear Reactor Regulation. A copy of my statement of professional qualifications is attached.
- 2. One of my responsibilities is the evaluation of the implementation of ATWS requirements for all light water commercial power reactors.
- 3. ATWS is an acronym for " anticipated transients without scram".
- 4. Anticipated transients are deviations from normal operating conditions which are expected to occur one or more times during the operation of a nuclear power plant.
- 5. Scram.is the termination of the nuclear reaction by rapid insertion of control rods.
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01202110057 820209 PDR ADOCK 05000528 O
' 6. An ATWS is the failure to rapidly terminate the nuclear reaction when such rapid termination is required, as a result of an anticipated transient, to prevent violation of transient design limits.
7.
The Intervenor has alleged, in contention 6B, that the Joint Applicants have not incorporated measures designed mitigate a postulated ATWS event. Contrary to that assertion, tu Staff has developed interim requirements for operating and trainiti procedures to
' accomplish precisely that purpose pending final resolution t." the ATWS issue by the Commission. These interim requirements are discussed in Section 15.3.9 of NUREG-0857 " Safety Evaluation Report related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2 and 3."
(SER).
8.
Section 15.3.9 of the SER, as well as the affidavit of F.
W. Hartley attached to the " Joint Applicant's Motion for Summary Disposition of Intervenor's Contention 6B," (Motion) reflects a committment by the Applicant to develop and submit the procedures mandated by the Staff requirements at least 60 days prior to fuel load.
9.
The discussion of ATWS in the SER was prepared by the Reactor Systems Branch.
I have reviewed that discussion and can affirm that (1) the requirement of procedures and training as discussed in Section 15.3.9 is consistent with the interim requirements used for other pressurized water reactors and (2) while the Commission has published in the Federal Register a proposed rule to require design and operational improvements in nuclear power reactors to reduce the Tiklihood of occurrence and consequences of ATWS events, these interim requirements provide adequate ATWS mitigation until a formal rule is issued and implemented.
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- 10. I have carefully reviewed the Joint Applicant's Motion.
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conclude that its technical content, as reflected in the affidavit of F. W. Hartley, is correct, and that the comittments of the Joint Applicants as described above satisfy the Staff's requirements for interim protection against ATWS events.
4 Marvin W. Hodges Subscribed and sworn to before me this 8th day of February,1982.
(bmle_ ~i9 J EGrn d
Notary Public My Commission expires: t1(i /, / 9 sg;t v
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Marvin W. (Wayne) Hodges Professional Qualifications Reactor Systems Brancn Division of Systems Integration U. S. Nuclear Regulatory Commission I am employed as a Section Leader in Section B of the Reactor Systems Branch, Division of Systems Integration.
I graduated from Auburn University with a BS degree in Mechanical Engineering in 1965.
I received a Master of Science degree in Mechanical Engineering from Auburn University in 1967.
In my present work assignment at the NRC, I supervise a team of engineers involved in the review of boiling water reactors. Prior to July 26, 1981, I served as principal reviewer in the area of boiling water reactor systems.
I also participateri in the review of analytical models used in the licensing evaluations of boiling water reactors and I had the technical review responsibility for many of the modifications and analyses being implemented on boiling water reactors after the Three tille Island, Unit-2 accident.
In addition, I participated in the review of the core protection calculator for ANO-2 and subsequent Combistion Engineering plants and consequently I am familiar with systems behavior for CE plants.
- As a member of the Bulletin and Orders Task force which was formed after the Ti1I-2 accident, I was responsible for the review of the capability of BWR systems to cope with loss of feedwater transients and small break loss-of-coolant accidents.
I have also served at the NRC as a reviewer in the Andlysis Branch of the NRC in the area of thermal'-hydraulic performance of the reactor core.
I
' served as a consultant to the RES representative to the program management group for the BWR Blowdown / Emergency Core Cooling Program.
Prior to joining the NRC staff in March,1974, I was einployed by E. I. DuPont at the Savannah River Laboratory as a research engineer., At SRL, I conducted hydraulic and heat transfer testing to support operation of the reactors at the Savannah River Plant.
I also performed safety limit calculations and participated in the development of analytical models for use in transient analyses at Savannah River. My tenure at SRL was from June 1967 to March 1974.
From September 1965 to June 1967, while in graduate school, I taught courses in thermodynamics, statics, mechanical engineering measurements, computer programming and assisted in a course in the history of engineering. Durina the summer of 1966, I worked at the Savannah River Laboratory performing hydraulic testing.
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9 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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ARIZONA PUBLIC SERVICE
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Docket Nos. STN 50-528 COMPANY, ET AL.
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STN 50-529
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STN 50-530 (Palo Verde Nuclear Generatirg
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Station, Units 1, 2 and 3)
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CERTIFICATE OF SERVICE I hereby certify that copies of NRC STAFF"S RESPONSE IN SUPPORT OF APPLICANT'S MOTION FOR
SUMMARY
DISPOSITION OF CONTENTION 5 and NRC STAFF'S RESPONSE IN SUPPORT OF JOINT APPLICANT'S MOTION FOR
SUMMARY
DISPOSITION OF CONTENTION 6B in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Commission's internal mail system, this 9th day of February,1982.
Robert M. Lazo, Esq., Chairman
- Administrative Judge Ms. Lee Hourihan Atomic Safety and Licensing Board 6413 S. 26th Street U.S. Nuclear Regulatory Comission Phoenix, AZ 85040 Washington, DC 20555 Atomic Safety and Licensing Dr. Richard F. Cole
- Board Panel
- Administrative Judge U.S. Nuclear Regulatory Comission Atomic Safety and Licensing Board Washington, DC 20555 U.S. Nuclear Regulatcry Comission Washington, DC 20555 Atomic Safety and Licensing Dr. Dixon Callahan Appeal Board
- Administrative Judge U.S. Nuclear Regulatory Comission Union Carbide Corporation Washington, DC 20555 P.O. Box Y Oak Ridge, TN 37830 Docketing and Service Section*
Arthur C. Gehr, Esq.
Office of the Secretary Charles Bischoff, Esq.
U.S. Nuclear Regulatory Comission Snell & Wilmer Washington, DC 20555 3100 Valley Center Phoenix, AZ 85073
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i Rand L.-Greenfield l
Assistant Attorney General P.O. Drawer 1508 Santa Fe, New Mexico 87504-1508 i
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5tepherf f1. Schinki.
Counsel for NRC Staff i
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