ML20205J765
| ML20205J765 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/24/1986 |
| From: | Bockhold G, Quasny H BECHTEL GROUP, INC., GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20205J720 | List: |
| References | |
| OL, NUDOCS 8602260403 | |
| Download: ML20205J765 (13) | |
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US C February 24, 1986
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'86 FEB 25 P2:32
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UNITED STATES OF AMERICA [C
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NUCLEAR REGULATORY COMMISSION
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1 BEFORE THE ATOMIC SAFETY AND LICENSING BOARD i
l In the Matter of
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GEORGIA POWER COMPANY, et al.
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Docket Nos. 50-424 (OL)
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50-425-(OL) j-(Vogtle Electric Generating Plant, )
l Units 1 and 2)
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i APPLICANTS' TESTIMONY OF GEORGE BOCKHOLD, JR.,
AND HAROLD J. QUASNY ON CONTENTION 10.1 (DOSE-RATE EFFECTS)
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My name is George Bockhold,_Jr.
I am employed by Georgia 1
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Power Company as General Manager, Vogtle Nuclear Operations.
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My business address is Georgia Power Company, P. O. Box 1600, Waynesboro, Georgia 30830.
A summary of my professional quali-s fications and experience is attached hereto as Exhibit A, which i
j I incorporate herein by reference.
My name is Harold J. Quaany.
I am_ employed by Bechtel Power Corporation in the position of Equipment Qualification i
Supervisor.
My business address is Bechtel Power Corporation, 4
12440 East Imperial Highway, Norwalk, California 90650.
A sum-mary of my professional qualifications and experience is h
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attached hereto as Exhibit B, which I incorporate herein by reference.
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Please state the purpose of your testimony.
A1.
The purpose of this testimony is to' describe the VEGP Maintenance and Surveillance Program as it portains to Conten-tion 10.1.
This testimony relates to the last two issues that f.
the Atomic Safety and Licensing Board designated for hearing in its January 23, 1986 Memorandum and Order (Ruling on Motion for Summary Disposition of Contention 10.1 re Dose Rate Effects).
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Q2.
Please describe the VEGP maintenance and surveillance
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j program.
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j A2.
Prior to fuel loading at Unit 1, Applicants will in-plement a Maintenance and Surveillance Program following the j.
guidance of Regulatory Guide 1.33, Revision.2.
Applicants' commitment to Regulatory Guide 1.33 is set forth in Section i
1.9.33 of the FSAR.
Applicants' Maintenance and Surveillance i
Program is described in Section 4.2 of " Environmental Qualifi-t l
j cation of Safety-Related Equipment Located in a Harsh Environ-1 i
ment" (September 1985), and in FSAR response to NRC Staff ques-1
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tion Q271.1 (Sept. 6,-1983).
J Planned. Maintenance and Surveillance is a program 4
t that schedules equipment maintenance, calibration, and i
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I surveillance activities.
Its purpose is to maintain equipment in a condition safe for operation, minimize unplanned outages due'to breakdown, and provide a mechanism by which greater than anticipated degradation of safety-related equipment can be de-tected and remedied.
The program is being developed using per-sonnel experienced in the area of maintenance and surveillance of electrical, mechanical, and instrumentation and controls equipment.
Under the program, a planned maintenance and surveil-lance checklist is prepared for each piece of safety-related equipment and identifies the maintenance and surveillance tasks to be performed.
If the task requires removing components for internal inspection, an equipment-specific procedure is refer-1 enced describing how the removal and inspection is to be per-formed.
If the task only requires visual inspection of the outer areas of the equipment, it is described on the checklist.
The content of the program is derived from the following sources:
Manufacturer / Vendor recommendations Lubrication requirements Calibration requirements Field verification of equipment descriptions Industry experience Qualification testino results a
With respect to contention.10.1, the qualification testing results have special significance.
All vendors sup -
plying safety-related equipment,to Plant Vogtle are required to j
identify critical, age-sensitive, environmentally-degradable organic components and to specify replacement intervals based on test or analysis.
Bechtel, the VEGP Architect-Engineer l
(AE), reviews and verifies each vendor's test and analysis re-sults.
The information is then used in preparing Environmental I
Qualification Data Packages (EQDPs) which include maintenance i
j and surveillance requirements specified by vendors in their test reports.
These EQDPs are transmitted to Applicants' Environ-mental Qualification Task Force (EQTF), which reviews the ven-dor's information and the AE's evaluation for completeness and f
validity.
If satisfactory, the EQTF approves each EQDP and transmits a copy to the VEGP Equipment Qualification (EQ)
I group.
The EQ group identifies all equipment tag numbers in-4 l
cluded in the EQDP and transmits this information along with the maintenance and surveillance requirements from the EQDP to the Planned Maintenance (PM) group.
The PM group then prepares replacement schedules, planned maintenance and surveillance checklists, and procedures (if necessary).
In addition to that required by the planned mainte-nance and surveillance checklists, surveillance and operability 4
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O testing are performed by the VEGP Inservice Testing Program and i
i the Technical Specification Surveillance Program.
The f Inservice Testing is cL-' ducted in_accordance with ASME Section XI.
All safety-related pumps with a Class lE power source and safety-related active valves required by ASME Section XI are tested on a regular basis.
The pump testing in-cludes determination of flow curves, vibration, bearing temper-atures, and differential pressure.
The valve testing includes determination of leak rates for isolation valves, stroke times, fail safe verification, and position indication verification.
The Technical Specification Surveillance Program covers all equipment required by the VEGP Technical Specifications.
The VEGP Technical Specifications specify requirements for test frequency, acceptability of testing, and measured parameters.
When required, corrective maintenance will be per-formed to assure that equipment will operate satisfactorily.
Such corrective maintenance will become part of an equipment iI history file.
Proper documentation of corrective maintenance actions will highlight recurring situations in similar equip-ment and will provide data to identify component past-performance trends.
Furthermore, equipment or component failures detected in other nuclear power-plants will be avail-able to VEGP through Industry Event Reports, NRC IE Bulletins, Information Notices, Letters, and Directives, and
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Manufacturers' Information Notices.
VEGP will review these re-ports to determine their applicability and will modify its maintenance and surveillance program accordingly.
Q3.
Please describe the surveillance act.ivities that will be performed on safety-related cables.
A3.
The maintenance and surveillance program for safety-related motors includes a provision for the megger of insulation in accordance with the manufacturers' recommenda-tions, typically every 72 months.
This testing is planned to be performed for the motors from the associated motor control center or switchgear.
Thus the cables and electrical-penetra-tion assemblies will be meggered with the motor windings.
This surveillance is capable of detecting insulation degradation, and the location of degradation can be traced to determine which component is at fault.
In addition, a program will be implemented to period-ically inspect selected cables inside the containment.
The ca-bles will be selected by type and material to envelope VEGP instrument and control cables.
The location or locations of the inspected cables will be selected in areas where higher temperature and radiation fields are anticipated.
The inspec-tion will be a visual check of the cables to identify signs of 1
degradation, i.e.,
cracking, flaking, discoloration or -
O powdering of the exterior of the cable.
The first (baseline) inspection will be conducted prior to commercial operation, and visual inspection will be periodically repeated every five years.
This interval is adequate; since all VEGP safety re-lated cables have undergone an IEEE-323-1974 qualification pro-gram, which included pre-aging, and all have a qualified life of 40 years, rapid degradation of cables should not occur.
Q4.
With respect to Contention 10.1, what is the signifi-cance of the VEGP maintenance and surveillance program?
A4.
Critical, age-sensitive, environmental-degradable components in safety-related equipment located in a harsh envi-ronment are environmentally qualified for their service life by_
test or analysis, and this qualification does not depend on maintenance or surveillance.
Maintenance and-surveillance does, however, provide a mechanism by wh'ich greater than antic-ipated degradation of such components can be detected and remedied.
Hence, the maintenance and surveillance' program pro-
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vides additional assurance that safety-related equipment will perform its intended function if needed.
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EXHIBIT A o
I Resume j
MAME:
George Bockhold, Jr.
TITLE:
Nuclear Plant Manager DEGREE:
BS, Power Plant Engineering DATE OF BIRTH:
8/31/44 i
DATE EMPLOYED:
April 1983 WORK EXPERIENCE: Various Nuclear Assignments NUCLEAR (GPC) Position:
Plant Manager Dates:
April, 1983 - Present Location:
Plant Vogtle Plant Status:
Construction Job
Description:
Manager of the startup and operation of two 1160 Mwe West-inghouse nuclear units. Responsi-
.bilities include staffing an or-ganization of over 600 technical and support personnel, directing the initial plant test program and safely and efficiently managing the operation and maintenance of these units. These responsibil-ities include utility assets of 6.6 billion dollars.
Position: Manager Nuclear Training Dates:
1981-1983 Location: Atlanta Job
Description:
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Managed the initial startup and operation of two Georgia Power Training Centers. Directed the growth of nuclear training to put in service 20 million dollars of training equip-ment including a staff change from 7 to 70 employees. Training responsibilities included licensed 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 the most professional operations
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and maintenance personnel for their nuclear plants.
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NUCLEAR (OTHER)
Position:
Vice President, General Physics Corp.
Dates:
1976 - 1981 Location: Chattanooga, TN Job
Description:
Mr. Bockhold was the Vice President of the Chattanooga Division responsi-ble for managing and coordinating the company's efforts in the areas of simulator training, simulator pro-curement, operator performance re-search, computer products, and on-site support of utilities startup, maintenance, and operation of power plants. Both the nuclear and fossil Chattanooga groups report to Mr.
Bockhold. He supervised the Chattanoo-ga Division's growth from 6 to 100 employees. The Chattanooga Division was involved with capital projects worth more than 60 million dollars.
.He also was the project manager of the following company projects:
Limerick Simulator Managed the procurement of a multimillion dollar training center which' included a BWR simulator for Philadelphia Electric's Limerick Station. Responsibilities included specifi-cation preparation and negotiation with the simulator vendor to obtain fidelity of simulation, flexibility in the computer system, and a training simulator which exceeded NRC require-ments and provides 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 exper-tise associated with selection testing, human factors engineering, and mathematical relia-
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bility modeling. This project included both j
I nuclear and fossil simulators.
Mr. Bockhold was previously Director of Oper-ations Services and Manager, Training Center Services. He managed activities associated with on-site support of power plant startup, operations, and maintenance. He directed Gen-eral Physics' use of Browns Ferry and Sequoyah Power Plant Simulators at the TVA Power Pro-duction Training Center.
Responsibilities in-cluded the supervision of the. simulator training
staff and NRC licensing and requalification programs. He was the supervisor of experienced instructors. Directed the preparation of and developed BWR and PWR sinmlator courses and course materials.
During this period, he per-formed detailed investigation of Browns Ferry and Sequoyah Plant design, construction, and operation to develop control room procedural materials.
Position:
Various Location:
Con Edison New York-Indian Point Station, NY Dates:
1971-1976 Job
Description:
Experience related to Indian Point Nuclear Units and their Central Control Room Simulator.
BREAKDOWN OF VARIOUS POSITIONS WITH CON EDIS0N Position:
Nuclear Training Director Dates:
1975-1976 Job
Description:
Responsible for all Indian Point training.
Responsibilities range from general employee training to licensed operator training and job performance evaluation. Sup'ervisor of licensed instructors and director of the Nuclear Simulator.
Simulator responsibilities included direction of maintenance personnel to maintain and up-grade system hardware and software, and super-vision of simulator training, NRC licensing and certification programs.
Further responsibil-ities included the review and pretesting of Unit No. 3's startup procedures.
1973 - 1975 Nuclear Simulator Director Manager of the Simulator project; responsible for the coordination of activities between the contractor, the NRC, and Con Edison's depart-ments.
Interface included programs to pro-duce fidelity of simulation, and NRC demon-stration and certification.
Preparation for responsibilities required both formal and in-formal training associated with computer technology. Director of training for licensed operators and operator ct.ididates utilizing the simulator facility; responsibilities included supervision of instructors, programmers, and maintenance personnel.
Instructed and directed Unit No. 3's startup crew simulator training to achieve operator licensing on both Units No. 2
& 3.
1971 - 1974 Production Engineer Various maintenance and operations responsibili-ties for Indian Point Units.
Specifically, special responsibilities included:
1 (1) Licensed shift engineer responsibilities during Unit No. 2 startup to above 20%
power including unit testing.
(2) Supervision of mechanics and operators during the refueling of Unit No. 2.
(3) Maintenance supervision in High Radiation i
areas during steam generator tube plugging of Unit No. 1.
Position: Connissioned Navel Officer Dates:
1970-1C71 Location: Various with United States Navy.
Job
Description:
U. S. Naval Nuclear Power School, Bainbridge, 1
Maryland. Division Director of Chemistry, i
Materials, and Radiological Fundamentals.
Instructor of undergraduate college level courses in Nuclear Engineering Systems.
Responsibilities included supervision of in-structors and preparation of course material.
Dates:
1968-1970 i
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 6 to 15 technicians on operation and maintenance of various equipment, equipment varied from air conditioning systems to reactor protection circuitry.
Further responsibilities included implementation of a computer orientated preventive maintenance systen for shipboard equipment. Watchstanding duties included Officer-of-the-Deck (000) and Engineering Officer-of-the-Watch (E00W). The E00W is the senior watch officer who is responsible for the safe operation of the nuclear power plant, including reactor safety, electrical power generation, and propulsion.
The 000 reports directly to the Comanding 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 E00W at Nav~al Reactor's land based nuclear power plant in Windsor, Connecticut.
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EXHIBIT B HAROLD J. QUASNY Education:
BS, Electrical Engineering, Chicago Technical College Business Management Certificate, University of California, Berkeley Summary:
39 Years:
Electrical engineering supervision in power plants and industrial and government facilities Experience:
Mr. Quasny is presently the Supervisor of the Equipment Environmental Qualification Group providing technical support for all of the domestic and overseas nuclear power plants.
Prior to this, he was a coordinator for the Chief Electrical Engineer for three nuclear and two fossil power plants and modifications to two existing power plants.
Responsibilities included the technical and administrative coordination of the project and review of the discipline operations.
Mr. Quasny was the Assistant Project Engineer and Electrical Engineering Supervisor on the 80-MW Hawaiian Wind Fara Project.
Prior to this, he was on the electrical technical staff as senior technical representative of the Chief Electrical Engineer for various power plant projects.
His responsibilities included solution of key technical areas on projects requiring multi-project overviews, including four nuclear and one fossil fuel projects.
Previously, Mr. Quasny was an Administrative Assistant to the Chief Electrical Engineer 1
responsible for personnel and salary administration and also manager of the reliability engineering group.
He had the project engineering responsibilities for the conceptual studies, master planning, final engineering design, and client assistance during the construction of a gas turbine assembly and test facilities of over 260,000 square feet.
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Engineering Group Supervisor, Mr. Quasny was responsible for the engineering and design of more than 10 types of facilities, including the i
Mead Converter Station to convert high voltage AC i
to 750-v de for power transmission.
He has been responsible for the engineering design of high reliability power systems for airports and prepared a handbook on the engineering design of airport high reliability power systems.
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HAROLD J. QUASNY (continued) j i
Prior to joining Bechtel, Mr. Quasny was associated with Aerojet-General, where he was Project Engineer on a high thrust nuclear rocket test facilities complex and high powered radar l
facilities, including a diesel power plant in the Pacific and various facilities at Vandenberg Air Force Base.
In addition Mr. Quasny was a Lead Engineer responsible for various industrial and government projects, including additions and modification at the Idaho Falls Complex.
Mr. Quasny was an Electrical Engineer for C. F.
Braun active in the design of the multi-million dollar flying "A"
refinery complex.
At Harza Engineering, Mr. Quasny was an Assistant Project Engineer on an underground hydroelectric power plant for El Salvador.
He also had engineering design responsibilities on hydroelectric power plants, transmission systems, and substations.
Professional Affiliations:
1 Member, Institute of Electrical and Electronics Engineers Member, Electrical Maintenance Engineers Association Member, Society of Military Engineers Member, Institute for the Advancement of Engineering 4
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