ML20214W238
| ML20214W238 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/03/1986 |
| From: | Bockhold G, Cereghino S, Cesarski W BECHTEL GROUP, INC., GEORGIA POWER CO., WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20214W161 | List: |
| References | |
| OL, NUDOCS 8612100137 | |
| Download: ML20214W238 (22) | |
Text
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A UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
l
)
GEORGIA-POWER COMPANY, et al.
)
Docket Nos. 50-424 (OL)
)
50-425 (OL)
(Vogtle Electric Generating Plant, )
Units 1 and 2)
).
AFFIDAVIT OF STEPHEN J. CEREGHINO, WILLIAM V.
CESARSKI, AND GEORGE BOCKHOLD, JR.
Stephen J. Cereghino, William V.
Cesarski, and George l
Bockhold, Jr., being duly sworn according to law, depose and say as follows:
1.
(SJC)
My name is Stephen J. Cereghino.
I am em-l ployed by Bechtel Western Power Corporation in the position of f
Nuclear Engineering Group Supervisor.
My business address is l
Bechtel Western Power Corporation, 12440 East Imperial Highway, Norwalk, California 90650.
A summary of my professional qualifi-cations is attached as Exhibit "A" to this affidavit.
2.
(WVC)
My name is William V. Cesarski.
I am em-ployed by Westinghouse Electric Corporation in the position of Senior Engineer in the Equipment Qualification Department of the Generation Technology Systems Division.
My business address is Westinghouse Electric Corporation, R&D Center - Building 701, h
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[.
c 1310 Beulah Road, Pittsburgh, Pennsylvania 15255.
A summary of my professional qualifications is attached as Exhibit "B" to this affidavit.
3.
(GB) My name is George Bockhold, Jr.
I am employed by Georgia Power Company in the position-of General Manager, Plant Vogtle Nuclear Operations.
My business address is P.O. Box 1600, Waynesboro, Georgia 30830.
A summary of my professional qualifi-cations is attached as Exhibit "C" to this affidavit.
4.
(SJC,WVC,GB)
The purpose of this affidavit is to re-spond to the Affidavit of Howard M. Deutsch, which was submitted to the Atomic Safety and Licensing Board on November 26, 1986.
We will address the statements on pages 2 through 5 of Dr.
Deutsch's affidavit.
As discussed below, the statements do not raise a timely or significant safety issue that might affect the outcome of the proceeding and therefore do not warrant inclusion ih the record.
We have personal knowledge of the matters stated herein and believe them to be true and correct.
5.
(SJC)
On page 2 of his affidavit, Dr. Deutsch refers to a March 1985 list of ASCO valves, a list which was provided to i
,Intervencrs during discovery and which showed six process valves utilizing NP-8321 ASCOs in MSIV areas.
This list contained a ty-pographical error.
Two process valves listed as having NP-8321s, but with the suffix A185E, should have been listed as having.
4 NP-8320s Las is evident from the designation of all other valves with the A185E suffix).
Of the four orocess valves correctly designated on the March 1985 list, two are located in the control building MSIV area and two are located in the auxiliary building MSIV area.
Subsequently, four more process valves with NP-8321 ASCOs in MSIV areas -- two in the auxiliary building MSIV area and two in the control building MSIV area -- were designated as safety-related and upgraded.
Thus, there are currently eight process valves with NP-8321 ASCOs in MSIV areas, four of which are in the control building MSIV area and four of which are in the auxiliary building MSIV area.
The list of ASCO valves attached to and incoroorated into Apolicants' testimony reflects this design change and shows the correct designations.
6.
(WVC)
At paces 2-3 of his affidavit, Dr. Deutsch dis-cusses the thermal lag analyses performed by Acolicants on ASCO solenoid valves in MSIV areas.
Dr. Deutsch's discussion is con-fused.
7.
(WVC)
Dr. Deutsch commences his discussion by cor-rectly observing that the first thermal laa analysis cerformed by Applicants (at the time when Apolicants had only aeneric MSLB mass and energy release data) modeled three phases of heat trans-fer.
In a second thermal lag analysis cerformed after Aeolicants had obtained Vogtle-soecific mass and energy release data, Apoll-cants used a more conservative approach.
Applicants ignored the P.
e 4
first two phases of heat transfer and assumed that the ambient temperature instantaneously rose to saturation temperature and the valve instantaneously dried out (i.e. Aoplicants took no credit for the first two chases of heat transfer).
Dr. Deutsch then incorrectly oresupocoses that by ignoring the initial phases of heat transfer, Applicants have " eliminated all thermal lac."
Even during the third phase, valve temperature continues to lag behind ambient temperatures.
Thermal lag analysis uses the
, ambient conditions (e.g. the temperature of the steam around the valve) to calculate the actual temperature which the valve would reach.
8.
(WVC)
Dr. Deutsch next observes that the effect of Applicants' approach (i.e. of assuming the ambient temperature immediately rises to saturation temperature and the valve instan-taneously dries out) is to " raise the actual final temperature."
Here, he is correct.
The valve temperature calculated by ignoring the initial phases of heat transfer is higher than the temperature calculated by modeling all phases of heat transfer, and the methodology employed in Applicants' second thermal lag analysis is thus more conservative.
9.
(WVC)
Dr. Deutsch then remarks that Applicants "use the calculated internal temperature of the valve to estimate the surface temperature."
This statement is confusing.
Applicants modeled the ASCO valves as a lump mass and computed the average p,
b l
temperature of the mass when exposed to the ambient temperature conditions in question.
Applicants then adjusted the temperature to take account of the fact that the valves would not heat up uniformly, but would have a higher temperature on the outer sur-face of the valve.
Based on the heat flux on the surface of the valve, the valve dimensions, and the thermal conductivity of the valve materials, Applicants determined that there would be a no more than 0.8*F temperature differential across the ASCO solenoid valve.
Applicants therefore conservatively added 1*F to the cal-culated average temperature to compute a higher surface tempera-ture.
10.
(SJC,WVC)
At the bottom of pace 3, Dr. Deutsch alludes to the Isomedix testing of the NP-8321 valve, and he states at the top of page 4 that he would not conclude "with great certain-ty" that the valves were fully qualified to 346*F.
The adequacy of the Isomedix testing of the NP-8321 was fully discussed in Applicants' testimony.
See Baenteli, et al, ff. Tr. 517 at 31-36.
11.
(GB)
On pages 4-5, Dr. Deutsch refers to several I&E notices, which he acknowledges "are not specifically related to
' environmental qualifications.'"
These I&E notices are therefore irrelevant to contention 10.5.
Moreover, as a factual matter, the I&E notices have little significance to the ASCO valves used at VEGP.
Each of these I&E notices is discussed below.
n 12.
-( G)B )
Dr. Deutsch refers to IEE Notice 85-08 (January 1985).
I&E Notice 85-08 reported no ASCO valve failures, but in-stead summarized the NRC Staff's position that 1) ASCO valves with resilient seats and viton elastomers are considered quali-fled only for those applications in which valves are not required to shift position _following exposure to total gamma radiation doses greater than 20 megarads; 2) that the NP-8316 valve with ethylene propylene elastomers is considered qualified to the level reported in Isomedix testing; and 3) other NP series sole-noid valves are considered qualified to the levels reported in ASCO testing.
The NRC Staff's position and I&E Notice 85-08 were addressed in and are consistent with Applicants' testimony.
See Baenteli et al., ff. Tr. 517, at 29, 43.
See also NRC Staff Testimony of Armando Masciantonio on Joint Intervenors' Conten-tion 10.5, ff. Tr. 550, at 12.
13.
(GB)
Dr. Deutsch refers to I&E Notice 85-17 (March 1985), which alerted the industry to the possible sticking of ASCO valves at Grand Gulf Unit 1 (a boiling water reactor).
This incident, however, involved a double valve model (type HTX 8323-20V) not utilized in safety related equipment at Plant Vogtle.
Furthermore there were indications of foreign substances in the valve, which the oil-free instrument air system at VEGP is designed to preclude.
Finally "HTX" series ASCO valves are not qualified.
I&E Notice 85-17 is thus inapplicable to the safety-related ASCO valves used at Plant Vogtle.
l 14.
4GB)
I&E Notice 85-95 is similarly inapplicable to Plant Vcqtle.
I&E Notice 85-95 reported a problem in scram pilot air solenoid valves used in boiling water reactors.
The problem was the result of the particular configuration of the valves in this application in BWRs.
Plant Vogtle does not euploy scram pilot air solenoid valves.
15.
(GB)
Finally, Dr. Deutsch refers to I&E Notice 86-57 (July 11, 1986).
This I&E notice described several experiences at other plants.
First it reported the sticking of an ASCO model NPL-8323-A36E (a double valve) at Brunswick, apparently caused by hydrocarbons in the Brunswick air system and high ambient temper-ature conditions.
VEGP does not use this model valve, its air system is designed to be oil free, and the ambient conditions to which ASCO's at VEGP are exposed are well within recommended lim-its.
16.
(GB)
I&E Notice 86-57 also reported the failure of de coils in several model NP-8323-A36V valves.
Again, VEGP does not use this model valve.
Furthermore, as discussed in Applicants' testimony, safety-related ASCOs at VEGP are configured so that coil failure would not prevent the valve from assumina its safety-related position (i.e. the valves are in their safety-related position when the coils are de-energized).
I a
Q 17.
iGB)
I&E Notice 86-57 also described problems experi-enced at Brunswick with several scram discharge SOVs, which were Model HV-90-405-2As.
When the problematic valves were disassem-bled, it was discovered that excessive amounts of lubricant had been aoplied, which may have caused the problems.
Again, this model valve is not used at VEGP in safety-related anolications.
Furthermore, Vogtle's maintenance procedures conform with the vendors recommendations regarding lubrication.
18.
(GB)
I&E Notice 86-57 reports a malfunction of one ASCO valve model NP-8320A-185E at the Haddam Neck Nuclear Power Plant.
The licensee has not yet been able to determine the cause of malfunction.
Applicants will keep acorised of these develop-ments.
Indeed, under Applicants' Operations Assessment Program, Apolicants review I&E Notices (and other NRC and industry re-ports), assess the significance of reported events, and modify the VEGP Maintenance and Surveillance Program or take such other corrective actions as may be necessary.
19.
(SJC)
On pages 5-6 of his affidavit, Dr. Deutsch takes issue with Applicants' use of the term " safety-related" equipment and suggests that Apolicants have ignored non-safety related equipment that might be classified as "important to safety".
His suqqestion is incorrect.
- 4
-=
20.
-( SJC )
10 C.F.R.
S 50.49(b)(2) requires that "non-safety related electric equipment whose failure under postu-lated environmental conditions ~could prevent satisfactory accom-plishment of safety functions" also be qualified.
To address this provision, Applicants have performed a number of systems analyses which are documented in the FSAR SS 7.7.2, 7.7.2.9, Re-sponse to Question 420.4, and Response to Question 420.6.
In ad-dition, Applicants have performed a hazards analysis of plant systems (safety-related and non-safety related) demonstrating that safety related systems would not be impaired by the dynamic effects of piping failures.
No non-safety related equipment has been found whose failure could prevent satisfactory accomplish-ment of safety functions.
21.
(SJC)
Moreover, Applicants have employed design prac-tices at VEGP to preclude the interaction of non-safety related equipment with safety related equipment, so that the failure of non-safety related equipment would not prevent satisfactory ac-complishment of safety functions.
For example, safety-related systems at VEGP are powered and operated by safety-related equip-ment, and necessary supporting systems such as cooling water and environmental control systems are also safety-related.
- Thus, with respect to ASCO valves, no safety-related equipment is oper-ated or controlled by a non-safety related ASCO valve.
In addi-i tion, safety systems are functionally separated from non-safety i
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o systems. Jn those instances where there might be a connection between a safety and non-safety related system (i.e., where sys-tems share a common duct or process piping), safety related isolation valves or dampers are installed between the sub-systems to interrupt the connection when an engineered safety features actuation signal is received.
These design practices provide reasonable assurance that no non-safety related ASCO valve will defeat the accomplishment of necessary safety functions at VEGP.
22.
(SJC,WVC,GB)
For these reasons, we believe the Dr.
Deutsch's Affidavit raises no new significant issue.
O StepMn Jd. ere~qhi MA William V.
Cesarski Subscribed and sJw rn to before me this h day of December, 1986.
A a m m 6.K,' Q Notar ublic Q
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<YbbrN x,iz George Bockhold, Jr.
Subscribed and sworn to before me this f day of December, 1986.
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Notary Public
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i EXHIBIT "A" l
l STEPHEN J. CEREGHINO EDUCATION:
B.S., United States Naval Academy Naval Nuclear Power School Naval Nuclear Power Training Unit NBA, Business Administration, Whittier College SUNNARY:
7 Years:
Bechtel engineering responsibilities in licensing and systems integration on the Vogtle project.
6 Years: Various training, operacional and maintenance responsi-bilities associated with the naval nuclear propulsion program.
l EXPERIENCE:
Mr. Cereghino is Project Vogtle's Nuclear Group Supervisor..
In this capacity, he provides technical guidance and assistance in the licensing and design of Plant Vogtle. As licensing engineer, he coordinates the inter-discipline activities of project personnel and coordinates with the client, NSSS and NRC personnel to ensure consistent application of licensing commitments. Mr. Cereghino supervises the administration of the NSSS contract, including such activities as: NSSS vendor data review, evaluation of NSSS proposals, and coordination of A/E-NSSS interface activities.
In the systems integration area, Mr. Cereghino is responsible for the analytical evalua-tion of potential plant hazards, such as:
radiation, pressure, temperature, flooding, internal missiles and seismic inter-actions.
Price to jotaing Bechtel, Mr. Cereghino was an officer in the United States Navy. His shipboard engineering assignments were as Reactor Controls Officer and Maic Propulsion Assistaat. He routinely supervised the operation of the reactor plaat during all modes of operation, and directed the chemistry control and radiation protection progra.as for skips company. Mr. Cereghino's last assiansent with the Navy was as a Division Director at the Naval Nuclear Power School; as such, he coordinated the instruction of Reactor Principles to enlisted plant operators.
Before leaving the Navy, Mr. Cereghino successfully qualified to assume the I
responsibilities of Chief Engineer of a naval nuclear pro-pulsion plaat.
PROFESSIONAL AFFILIATIONS:
Professional Registration: Mechanical Engineering, State of Califorata
\\'
EXHIBIT "B"
Summary ofsProfessional Qualifications and Experience William V.
Cesarski I
Senior Engineer Plant Engineering Division l
Westinghouse Electric Corporation My name is William V. Cesarski.
My business address is Westinghouse Electric Corporation, R & D Center-Building 701, 1310 Beulah Road, Pittsburgh, Pennsylvania 15235.
I am 4
employed by Westinghouse Electric Corporation (" Westinghouse")
as a Senior Engineer in the Equipment Technology Department of the Plant Engineering Division.
C I graduated from the United States Military Ac?demy in I
1964 with a Bachelor in' Engineering Science degree.
I was awarded an Atomic Energy Commission Graduate Fellowship while at West Point and used the AEC fellowship to obtain a Master
'~
of Science Degree in Nuclear Engineering from Massachusetts l
Institute of Technology in 1966.
In 1972 I also received a Master of ~ Science Degree in Industrial Management from New York University.
After spending eight years in the U. S. Army,-I joined Westinghouse in 1972 as an engineer in the Plant 4 paratus Division.
While working at WPAD, I obtained experience in nuclear valve and refueling equipment design, testing and procurement for the Naval Nuclear Program.
In 1981 I joined 'the Westinghouse Nuclear Equipment Division and have had lead engineer responsibility for the IEEE qualifi-cation testing of numerous NSSS valve and motor components.
I have conducted numer'ous qualification test programs and authored numerous Westinghouse qualification test reports on components such as valve motor operators, valve limit switches, soleno_id valves, valve position indication devices, pump motors'and pump assemblies.
I am presently a Senior Engineer and act as a lead engineer in the Equipment Qualification
. Technology Department of the Plant Engineering Division responsible,for electro-mechanical equipment qualification.
+
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EXHIBIT "C" s
VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 1 OF 70)
RESUMES OF ONSITE SUPERVISORY PERSONNEL George Bockhold, Jr.,
general manager - nuclear operations Date of Birth:
August 31, 1944 Educational Background U.S. Naval Academy, 1966 B.S.,
power plant engineering Work Experience Nuclear, Georgia Power Company Position:
General manager, nuclear operations Vogtle Electric Generating Plant Dates:
April 1983 to present Location:
Plant Vogtle p
Plant Status:
Construction and startup Job
Description:
Manayur of the startup and operation of two 1160-MWe Westinghouse nuclear units.
Responsibilities include staffing an organization of over 900 technical and support personnel including contractors, directing the initial plant test program, and safely and efficiently managing the operation and maintenance of these units.
These responsibilities include utility assets of 7.2 billion dollars.
Position:
Manager, nuclear training Dates:
1981-1983 Location:
Atlanta Job
Description:
Managed the initial startup and operation of two Georgia Power Company training centers.
Directed the growth of nuclear training to put in service 20 million dollars of training equipment including a staff change from seven to seventy employees.
Training
. responsibilities included simulator, health physics, maintenance, technician, and general employee training.
The training plans were designed to exceed INPO accreditation and NRC requirements and provide Georgia Power Company with the most professional operations and Amend. 16 4/85
s VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 2 OF 70) maintenance personnel for their nuclear plants.
Position:
Vice president, General Physics Corporation Dates:
1976 - 1981 Location:
Chattanooga, Tennessee Job
Description:
Vice President of the Chattanooga division responsible for managing and coordinating company efforts in the areas of simulator training, simulator procurement, operator performance research, computer products, and onsite support of utilities startup, maintenance, and operation of power plants.
Both the nuclear and fossil Chattanooga groups reported to him.
He supervised the Chattanooga division's growth from six to one hundred employees.
The Chattanooga division was involved witlt capital projects worth more than 60 million dollars.
He also was the project manager of the following company projects:
I Limerick Simulator Managed the procurement of a multimillion dollar training center which included a boiling water reactor simulator for Philadelphia Electric's Limerick Station.
Responsibilities included specification preparation and negotiation with the simulator vendor to obtain fidelity of simulation, flexibility in the computer system, and a training simulator which exceeded NRC requirements and provided excellent manipulation training during all modes of plant operation.
_EPRI Simulator Performance Measurement System Directed a research project which utilizes the simulator computer system to collect data and objectively evaluate operator performance.
Directed the efforts of the system project group and several project participants who have expertise associated with selection Amend. 16 4/85
VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 3 OF 70) testing, human factors engineering, and mathematical reliability moc'eling.
This project included both nuclea r and fossil simulators.
As director of operations services and manager, training center services, he managed activities associated with on-site support of power plant startup, operations, and maintenance.
-He directed General Physics' use of Browns Ferry and Sequoyah Power Plant Simulators at the Tennessee Valley Authority Power Production Training Center.
Responsibilities included the supervision of the simulttor training staff and NRC licensing and requalification programs.
He was the supervisor of experienced instructors.
Directed the preparation of and developed BWR and PWR simulator courses and course materials.
During this period, he performed detailed investigation of Browns Ferry and 1
Sequoyah Plant design, construction, and operation to develop control room procedural materials.
Con Edison, New York - Indian Point Station, New. York Position:
Nuclear training director Dates:
1975-1976 Job
Description:
Responsible for all Indian Point training; responsibilities ranged from general employee training to licensed operator training and job performance evaluation.
Supervisor of licensed instructors and director of the nuclear simulator; simulator responsibilities included direction of maintenance personnel to maintain and upgrade system hardware and software, and supervision of simulator training, NRC licensing and certification programs.
Further responsibilities included the review and pretesting of Unit No. 3 startup procedures.
Position:
Nuclear simulator director Dates:
1973-1975 Job
Description:
Manager of the simulator project; responsible for the coordination of Amend. 16 4/85
e I
a I
VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 4 OF 70) activities between the contractor, the NRC, and Con Edison's departments.
j Interface included programs to produce fidelity of simulation and NRC demonstration and certification.
Preparation for responsibilities required both formal and informal I
training associated with computer technology.
Director of training for licensed operators and operator candidates utilizing the simulator facility; responsibilities included supervision of instructors, programmers, and maintenance personnel.
Instructed l
and directed Unit No. 3 startup crew l
simulator training to achieve operator licensing on both Units No. 2 and 3.
Position:
Jroduction engineer Dates:
1971-1974 Job
Description:
Various maintenance and operations responsibilities for Indian Point l
Units.
Specifically, special 1l responsibilities included:
s 1.
Licensed shift engineer responsibilities during Unit No. 2 startup to above 20 percent power including unit testing.
l 2.
Supervision of mechanics and operators during the refueling of Unit No.
2.
3.
Maintenance supervision in high radiation areas during steam generator tube plugging of Unit No.
1.
Or.her Experience and Training Position:
Commissioned Naval Officer Dates:
1970-1971 Location:
Various with United States Navy Job
Description:
U.S. Naval Nuclear Power School, Bainbridge, Maryland.
Division Director of Chemistry, Materials, and Radiological Fundamentals.
Instructor of undergraduate-college level courses in nuclear engineering systems.
Responsibilities included supervision of Amend. 16 4/85
VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 5 OF 70) instructors and preparation of course material.
Dates:
1968-1970 Job
Description:
USS Simon Bolivar (SSBN 641), a Polaris nuclear powered submarine.
Responsibilities included the following division officer billets - ship's damage control assistant, electrical and reactor control officer.
All duties included direction of six to fifteen technicians on operation and maintenance of various equipment, (from air conditioning systems to reactor protection circuitry).
Further responsibilities included implementation of a computer-orientated preventive maintenance system for shipboard equipment.
Watchstanding duties included officer-of-the-deck (OOD) and engineering officer-of-the-watch (EOOW).
The EOOW is the senior watch officer who is responsible for the safe operation of the nuclear pewer plant, including reactor safety, electrical power generation, and propulsion.
The OOD reports directly to the commanding officer for the safe navigation and operation of the ship.
Dates:
1966-1968 Job
Description:
Navy-specialized training including officer nuclear propulsion and submarine schools.
Qualified EOOW at naval reactor's land-based nuclear power plant in Windsor, Connecticut.
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'86 DEC -8 All :03 UNITED STATES OF AMERICA ggg,
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NUCLEAR REGULATORY COMMISSION 00CXEied 4 ? FV'Li BRAND' Before the Atomic Safety and Licensing Board In the Matter of
)
)
GEORGIA POWER COMPANY, --et al.
)
Docket Nos. 50-424
)
50-425 (Vogtle Electric Generating Plant, )
Units 1 and 2)
)
CERTIFICATE OF SERVICE I hereby certify that copies of " Applicants' Response to Af-fidavit of Howard M. Deutsch," dated December 5, 1986, and the accompanying affidavit and exhibits identified therein, were served upon those persons on the attached Service List by deposit in the United States mail, postage prepaid, or where indicated by an asterisk by hand delivery, this 5th day of December, 1986.
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'Brucr W.
Churchill, P.C.
Dated:
December 5, 1986 w
f.
1 6
i 1
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of y
)
GEORGIA POWER COMPANY, et al.
)
Docket No. 50-424
)
50-425 (Vogtle Electric Generating Plant,
)
Units 1 and 2)
)
SERVICE LIST Gary J. Edles, Chairman Bernard M. Bordenick, Esquire Atomic Safety and Licensing Office of General Appeal' Board Counsel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Washington, D.C.
20555 Commission Washington, D.C.
20555 Christine N. Kohl Atomic Safety and Licensing Bradley Jones, Esquire Appeal Board Regional Counsel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Washington, D.C.
20555 Commission 101 Marietta Street, Suite 3100 Howard A. Wilber Atlanta, GA 30303 Atomic Safety and Licensing Appeal Board Danny Feig U.S. Nuclear Regulatory Commission 1130 Alta Avenue Washington, D.C.
20555 Atlanta, GA 30307
- Morton B. Margulies, Chairman Atomic Safety and Licensino Atomic Safety and Licensing Board Panel Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission washington, D.C.
20555 Washington, D.C.
20555
- Gustave A. Linenberger Atomic Safety.and Licensing Atomic Safety and Licensing Acceal Board' Panel Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C.
20555 Washington, D.C.
20555
- Dr. Oscar H. Paris Docketing and Service Section (3)
Atomic Safety and Licensing Office of the Secretary Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C.
20555
- Carbl Stangler 425 Euclid Terrace Atlanta, GA 30307~
- _ -.