ML20236R276
| ML20236R276 | |
| Person / Time | |
|---|---|
| Site: | 05000087 |
| Issue date: | 11/03/1987 |
| From: | Sackschewsky R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Michaels T NRC |
| References | |
| NUDOCS 8711230196 | |
| Download: ML20236R276 (17) | |
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W35tingl100Se ** "'"E""'
Electric Corporation sos sniton Bouievard ,
bon linnois 600S9
'312!8724585 i
November 3,1987
[0' 1 Mr. Ted S. Michaels Nuclear Regulatory Commission Maii Stop P234 7920 Norfolk Avenue i Bethesda, Maryland 28014 Mr. Michaeis, Enclosed is the information requested by John Minns concerning-the radiological status of materials and sources maintained at the NTR Facility. The format of the enclosure consists of a statement '
I or question expressing the desired information followed by the information.
After the second radioactive materials shipment, the radiation levels within the Facility will be minimal. As shown in Figure 7 of the Dismantling Plan, the measured levels in the reactor tank are approximately 80 yR/hr.
If you need any additional information, please call.
Sincerely,
- p. ,
{/ w. 3 yP.Sackschewski <
NTR Coordinator RPS/mtk Enclosures cc: Joe Nardi 8711230196 8711 3 PDR ADOCK 05000087 PDR, P g10 ,
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(1) Resumes of staff coordinating the dismantling process: !
I The organization for the dismantling operations is essentially the same {
i as for the operation of the Facility under the NRC license R-119 as ;
described in Section 1.5 of the Dismantling Plan. The three Resumes of !
the coordinating staff's NTR Facility Manager, Training Reactor Coordinator and NTR Lead Engineer are enclosed. Additional personnel may, however, be utilized under the direction of these three j individuals. Also included are the Resumes of three other NTR Senior Reactor Operators who assist us from time to time as needed. Changes i t
within this group are possible with changes in employment status. )
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PERSONAL RESUME l
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l KAREN M. RUETER I Manager of Nuclear Training Reactor i Westinghouse Electric Corporation '
Training & Operational Services Zion, IL 60099 l
EXPERIENCE Westinghouse,1980 - Present Manager, Fundamentals and Technician Training, Westinghouse Nuclear Training ;
Center, Zion, IL. Responsibilities include the initial and requalification of 1 Nuclear Fundamentals, the conduct of programs and operation of the Nuclear i Training Reactor, Health Physics Training, Chemistry Technician Training, and l STA Training. Coordinate the scheduling of training courses for utility 1 personnel and Westinghouse employees. Responsible for personnel requirements, l supervision and administration.
Lead Engineer, Curriculum and Instruction. Responsibilities included coordination research and development of curriculum for nuclear power plant operator training, including writing and validation of curriculum objectives.
Coordination and participation in semi-annual evaluation of all WNTC faculty.
Development and presentation of instructor skills and methods courses.
Principle author and researcher of thernal science textbook " Thermal-Hydraulic Principles and Applications to the PWR". Presentation of classroom instruction on nuclear theory, thermodynamics, health physics, and power plant j systems and presentation of simulator instruction on power plant operations. i Engineer. Responsibilities included instruction of Nuclear Reactor Operator and Shift Technical Advisor trainees in the fundamentals of Nuclear Reactor Theory, including reactor physics, nuclear physics, radiation protection and health physics, thermodynamics, heat transfer, and fluid flow. Conducted classes at utility sites and at Training Center. Responsible for development of Thermal Science textbook. Holds NRC Senior Reactor Operator license for l Nuclear Training Reactor and conducts classes for trainees on the Training Reactor.
Engineer, Westinghouse Nuclear Equipment Division, Pittsburgh, PA.
Responsibilities included contract administration of orders for Steam Generators and Pressurizer placed with the Westinghouse manufacturing plant in Tampa, Florida. Responsibility for the integrated control of work scope and financial, administrative and schedular requirements of orders placed with ,
the Nuclear Equipment Division. Attended Project Management Workshop for Korean Localization Project. Developed new business procedures to delineate i the administrative and commercial interfaces between headquarter divisions and the manuf acturing plants required by the NRC.
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I PERSONAL RESUME KAREN M. RUETER EXPERIENCE Engineer, Westinghouse Nuclear Fuel Division, Pittsburgh, PA. l Responsibilities included the planning and directing of the execution of l onsite post-irradiation fuel examinations. Reviewed and analyzed fuel !
assembly and fuel rod data. Wrote and edited technical reports to outside j agencies. Made several presentations to utility customers. Developed a '
systematic procedure for long range planning of future examinations and helped to develop a database for the retention of significant field performance data.
I St. Mary High School, McKees Rocks, PA, 1972-1974 Teacher of Algebra II, l Trigonometry, Calculus I, and Physics to high school juniors and seniors.
I EDUCATION !
l Nuclear Training at Westinghouse, 1978 - 1983 I Nuclear Reactor Fundamentals (WNTC Phase I) l NTR Senior Reactor Operator Licensing Class I Instructional Skills Workshop PWR Simulator and Systems Training !
WNTR SRO License I l NRC SRO Instructor Certification l
Westinghouse Corporation Courses:
Business Planning Workshop Problem Salving and Decision Making Statistics for Decision Making Nuclear Core Engineering Duquesne University, Pittsburgh, PA, B.S. Degree in Physics, 1968-1973 East Carolina University, Greenville, NC,1972 Central Catholic High School, Allentown, PA, 1964 - 1968.
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PERSONAL' RESUME ROY P. SACKSCHEWSKY Nuclear Operations Training Coordinator Westinghouse Electric Corporation Training & Operational Services Zion, IL 60099 EXPERIENCE Westinghouse, 1980-Present PWR Principles, Systems and Simulator Instructor. Operator and Instructor Westinghouse Nuclear Training Reactor. Nuclear Training Re'ctora Coordinator; Westinghouse Nuclear Training Center, Zion, IL. Prepared and conducted 1 presentations in classrooms, full scale simulated control room and on the .I training reactor. Prepared and administered written, oral and operational )
examinations. Evaluated student performance and aptitude. Tutored and '
counseled students. Performed research and developed training materials.
Organized training reactor programs and staf f. Administered the training' 1 reactor NRC license and operator licenses and assured their compliance with !
applicable regulations. NRC SRO Instructor Certification, Zion Simulator.
NRC SRO License, Westinghouse Nuclear Training Reactor.
Naval Nuclear Power School NTC, Orlando, FL, 1976-1980 - Instructor / Officer. 1 Responsibilities were instruction of technical and theoretical principles l associated with Naval nuclear reactor design and operations. Training, evaluation, and counseling of instructor skills for the staff at nuclear power school. Evaluation and preparation of instructional' materials.
Hayes Center High School, Hayes Center, NB, 1973-1976 - Teacher, Mathematics ,
and Physics. '
Nebraska Center for Children and Youth, Lincoln, NB, 1971-1973 -
Lincoln Lutheran Jr. High, Lincoln, NB, 1970-1973 - Teacher, Mathematics / l Physical Science. j Alabama Lutheran Academy and College, Selma, AL, 1969-1970 - Instructor, I Mathematics / Physical Science.
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EDUCATION l 1
Nuclear Training at Westinghouse, 1980-1983 l' University of Central Florida, 1979-1980 University of Nebraska, Lincoln, NB, MAT Degree in Math - Sec. Education, 1972-1974 Concordia Teachers College, B.S. Degree in Math / Physics Education, 1965-1969 Waco Public High School, 1962-1965 1040a I l
l PERSONAL RESUME JEFFERY P. KIEFFER ;
Nuclear Operations Instructor i Westinghouse Electric Corporation .
Training & Operational Services l Zion, IL 60099
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EXPERIENCE Westinghouse, Aug 1985 - Present Lead Engineer Nuclear Training Reactor, NRC licensed SRO. Responsible for i utilizing technical manuals and interfacing with the Reactor Safeguards I Committee for assurance of compliance of NTR maintenance procedures with NRC regulations and NTR license conditions (FSAR, Technical Specifications, and NTR Operating Manual). Writing, implementing and performing preventative and corrective maintenance procedures on the reactor and associated equipments, i maintenance of the facility and supervision of the operating staff. Teaching students nuclear fundamentals, reactor operation and radiation protection, performing radiation protection procedures and calibration of radiation detection equipment.
Westinghouse, Mar 1980 - Aug 1985 Systems Engineer for SNUPPS simulator. Responsibilities included, writing, implementing and performing preventative and corrective maintenance on ]
simulator panels, computer systems, input /out equipment, and associated ;
peripheral equipment.
U.S. Navy, 1970-1980 Navy Recruiter f rom 1977 to 1980. From 1973 to 1977, systems technician for Sonar and Underwater Fire Control Systems, work center supervisor responsible for review, rewrite, impitmentation and performance of Navy's Preventative l
Maintenance System. '
EDUCATION Joliet Junior College, Joliet, IL 1984 - 1985 Training at Westinghouse,1983 ;
UW Parkside, Kenosha, WI 1980-1982 Parkersburg High School, Parkersburg, WV, 1968-1970 1040a
G PERSONAL RESUME BARRY TUMBLIN Senior Computer Based Training, Engineer Westinghouse Electric Corporation Training & Operational Services Zion, IL EXPERIENCE HIGHLIGHTS 1979 to 1986 Westinghouse Training & Operational Services: Coordinate and develop lesson materials for presentation on a computer.
Instruct operator classes in the classroom, nuclear training reactor, and simulator. Perform equipment and system qualifications to meet NRC requirements at the utility site.
- Wrote script materials for thermal science review on computer and coordinated progranning.
- Assisted in writing thermodynamic text for TOS.
- Coordinated numerous fundamental training programs at WNTC and at utility sites.
- Performed environmental qualification of Zion Unit 1 and 2 to meet NRC requirements.
Mr. Tumblin's experience includes conducting of classroom, Nuclear Training Reactor, and simulator lectures in the following areas:
TOPICS _ HOURS Chemistry 50 Thermodynamics 300 Reactor Theory 300 Radiation Detection and Safety 100 PWR Core Control 300 Instrumentation and Control 60 PWR Systems 150 Simulator PWR Operations & Transients 300 Nuclear Training Reactor 800 RO/SRO Requalification 100 Plant Tours 300 1971 to 1978 U.S. Navy: Qualified as a Nuclear Plant Mechanical Operator ,
and Engineering Laboratory Technician. Selected to Prototype !
staf f af ter graduation. Coordinated laboratory division aboard ship as leading d'ivision petty of ficer.
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RESUME BARRY TUMBLIN ACCOMPLISHMENTS 8.S., Physics, Ohio University, Athens, Ohio Masters of Education, Illinois University, Champaign, Illinois Nuclear Regulatory Commission, SR0 License, Westinghouse Nuclear Training Reactor,1980 Nuc lear Regulatory Commission, SRO Certification,1983 WESTINGHOUSE TRAINING & OPERATIONAL SERVICES CURRICULUM COMPLETED NEP 211 Fundamentals of Nuclear Reactor Theory NEP 213 Radiation Detection, Protection and Safety NEP 219 Large PWR Core Control NEP 221 Thermal-Hydraulic Principles and Applications for the PWR NEP 233 Nuclear Training Reactor Operational Training NEP 241 Applied Electrical Technology for Control Room Operations NEP 245 Applied Instrumentation & Control Technology NEP 271 Post Accident Sampling System Training for Chemistry Technicians NEP 285 Health Physics Technician Training NEP 359 Mitigatirg Core Damage NEP 361 Transient & Accident Analysis NEP 511 Practical Chemistry for Nuclear Plant Operations NEP 513 Material Considerations of PWRs NEP 515 Advanced Thermodynamics NPS 211 Introduction to Nuclear Power Plants NPS 213 Power Plant Electrical Systems NPS 215 Reactor Systems & Components NPS 217 Reactor Support Systems (Part I)
NPS 219 Reactor Support Systems (Part II)
NPS 221 Engineering Safeguards Systems NPS 223 Steam Cycle Systems NPS 225 Steam Cycle Support Systems NPS 227 Control & Protection Instrumentation Systems NPS 229 System Response During Plant Operations NPO 106 Introduction to PWR Plant Operations NPO 311 PWR Operations Familiarization NPO 313 PWR Normal Plant Operations NPO 315 Simulated PWR Plant Transient Response NP0 317 Technical, Therma l & Radiological l Ana lysis NPO 319 Simulated PWR Minor Plant Casualty Training NPO 321 Simulated PWR Major Plant Casualty Training NPO 323 Integrated Plant Operation Review l ISM 463 Classroom Instructor Skills & Methods ISM 464 Simulator Instructor Skills Workshop 1040a
i PERSONAL RESUME i
CHARLES C. FERGUSON Senior Nuclear Operations Instructor -l Westinghouse Electric Corp. l Zion, IL 60099
.j EXPERIENCE i
Byron Station, September 1983 - December 1985 l Two years; startup and power escalation at Byron Station, twin 1140 MWe PWR, as a Shift Supervisor and Engineering Assistant.
Westinghouse, 1974 - Present PWR Systems and Simulator Instructor: Prepare and conduct presentations in classroom and ' simulated control room concerning nuclear plant systems design and operation. Prepare and administer written, oral and operational examinations. Evaluate student performance and aptitude. ' Tutor and counsel Research, develop and edit training students, especially foreign students.
materia ls . Nuclear Training Reactor Instructor: prepare and conduct training on the Nuclear Training Reactor. Entailing demonstration of fundamental concepts learned in the classroom. Training in proper control room conduct, coordination of manipulative tasks, and setting priorities during hands-on operation. SR0 Instructor Certification. . Westinghouse Nuclear Training Reactor Lead Engineer Westinghouse Nuclear Training Center, Zion.
Responsible for the Nuclear Training Reactor availability to conduct ;
operations consisting of surveillance testing, periodic testing, corrective maintenance and hardware updating.
f U.S. Navy, 1966-1974 - Engineering Watch Supervisor ET-1 (SS), nuclear power plant and instrumentation startup service.
EDUCATION Training at Westinghouse, 1976, 1982 Joliet Jr. College, 1981-1982 DeVry Technical School, Chicago, IL, 1961-1962 Arvada High School Arvada, CO, 1958-1961 1040a
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CHARLES C. FERGUSON !
Core Physics Monitor i l
1 Experience and Training Summary 1966 - 1974: U.S. Navy Engineering Watch Supervisor ET-1(SS). l 1974 - 1982: Nuclear power plant and instrumentation start-up service.
Westinghouse Nuclear Training Reactor Lead Engineer.
Responsible for the Nuclear Training Reactor availability to conduct operations consisting of surveillance testing, periodic testing, corrective maintenance and hardware updating.
1982 - Present: PWR Systems and Simulator Instructor !
Prepare and conduct presentations in classroom and simulated <
control room. 1 i
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Nuclear Training Reactor Instructor l Prepare and conduct training on the Nutlear Training Reactor.
l 1984 - 1985: Startup and power escalation at Byron Station, twin ll40MWe PWR as a Shift Supervisor and Engineering Assistant. :
Qualified as a Core Physics Monitor through training at Westinghouse Nuclear Training Center - Zion, IL.
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PERSONAL RESUME FRED E. ELLIS Senior Nuclear Operations Instructor i Westinghouse Electric Corp.
Zion, IL. 60099 I
I EXPERIENCE 1
Westinghouse Electric Corporation, Zion,' Illinois,1968 - Present. SRO- 1 Instructor Certification. Senior Reactor Operator's License (NRC) for Westinghouse Nuclear Training Reactor (current). Previously ' licensed SRO Zion Station'1080 MWe'PWR (NRC).
Currently developing simulator malfunction testing procedures for the New York Power Authority, Indian Point #3 simulator.
Wrote startup test and power ascension test procedures for Shearon Harris Nuclear Power Plant.
Two years; startup and power escalation at Byron Station,1140 MWe PWR, as a Shift Supervisor and Engineering Assistant.
Radiation Safety Coordinator and instructor on Westinghouse Nuclear Training ,
Reactor, conduct training in reactor theory and operations using the Nuclear i Training Reactor. Responsible for radiation safety, security, emergency preparedness, and student training on the reactor.
l Instructed numerous onsite training programs for the Nuclear Engineering Principles group.
Senior Reactor Operator's License (NRC) for Zion Generating Stations Units 1 and 2.
PWR Systems and Simulator instructor. Prepare and conduct presentations in classroom and simulated control room concerning nuclear plant systems design and operation. Prepare and administer written, oral, and operational examinations. Evaluate student performance, aptitude, along with tutoring and counseling of students. Research, develop, and edit training materials.
Startup crew training (onsite) for Turkey Point plant in Florida: had responsibility for all onsite training of 12 engineers and operators.
Results: all candidates passed their NRC license exams.
United States Air Force, 1948 - 1968, Shift Supervisor, USAF and U.S. Corps of Engineers, Nuclear Power Plants.
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' PERSONAL RESUME FRED E. ELLIS EDUCATION j q
Nuclear Training at Westinghouse, 1968 - 1981 l University of Michigan School of Public Health,1979 George Washington University, Washington D.C., 1964 - 1968 -
University of Virginia, Charlottesville, VA, 1965 j Black Hills Teaching College, Spearfish, SD, 1962 )
University of California, Berkley, CA,- 1961 - 1962 '
Air Force Training, 1948 - 1961 Antelope Valley College, Lancaster, CA, 1957 - 1958 East High School, Huntington, WV,' 1945 - 1948 Total of approximately 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> - Science and Math ;
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(2) Give a description of the Radioactive Materials which have been or are being shipped from the NTR Facility including the calibration and check sources.
I The low power history of the NTR and the use of aluminum in most l components have minimized the activity levels of materials within the Facility. Contamination in the Facility and on reactor components has never occurred, as shown in the results of the water, air and Facility l smear surveys in Tables III, IV, V and VI in the dismantling plan submitted on 7/8/87.
l Activated components consist mostly of stainless steel components i utilized within the reactor. The major portion of th activated stainless steel was utilized to support the fuel element followers in l l the five control rods. The fuel follower was attached to the control rod by a 3/8" stainless steel shaft. Maximum radiation level on a single shaft at its hot spot was 16 pR/hr. Stainless steel collar pieces were utilized to support the upper section of the fuel follower to the stainless steel shaft. These collar pieces are the most l
activated pieces of material f rom the reactor. A single collar measured 0.5 R/hr cn contact and 20 pR/hr at one foot. The collar pieces were l all placed in a single bag which measures 3.5 R/hr on contact and 0.3 R/hr at one foot. This material has been packaged for shipment to a RAM burial site in a single 17H container. Other stainless steel components included in the shipment had low activated levels measuring from a fraction of a pR/hr to 3 pR/hr. The total measurable activity of 1 -2 l the stainless steel was calculated at 2.65 x 10 c u ries .
l Included in this shipment are the following 12 check sources:
Source Description Number Activity Each Total Activity Cs-137 6 ~ 8 pCi 48 pCi Th-230 2 0.005 pCi .01 pCi Th-230 2 0.01 pCi .02 pCi Sry-90 1 6.6 x 10' pCi 6.6 x 10~ pCi Co-60 1 .33 pCi 330 uti TOTAL 378.04 pCi 1040a 1
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The graphite reflector material has been disassembled and placed in the steel drum for shipment. The 430 lbs. of graphite was conservatively calculated to contain a total of 25.3 901 of activity.
A second shipment containing other three sources is presently being planned and processed for approval. This shipment will contain sources
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which are Class C or greater and stabilized by use of greater than 4 inches of portland cement. The description of these sources are given below.
Source Description Source Strength Comments Cs-137 66.5 mci Calibration Source in Pig Sr-90 0.430 mci Sealed Source Am-241 2.21 pCi Smoke Detector Source l
The following sources are being maintained by the Facility as instrumentation check and calibration sources. These exempt sources will be transferred with the appropriate survey instruments.
Source Description Source Strength Comments Cs-137 ~ B pCi Check Source Th-230 .02 pCi Check Source
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Pu-239 1.42 x 10 pCi Ca libration/ Counter Cs-137 .0727 pCi Calibration / Counter Pu-239 1.08 x 10' Ci Calibration Kit
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Pu-239 1.?7 x 10 Ci Calibration Kit l Pu-239 1.9 x 10~ Ci Calibration Kit
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l Pu-239 1.0 x 10 Ci Calibration Kit l
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(3) How are inaccessible areas within the Facility to be checked for possible contamination */
l The extremely low probability of any contamination within the f acility is discussed on pages 8 and 9 of the Dismantling Plan. Inaccessible i areas will not exist within the core region since all the material will be disassembled and removed and shipped for disposition. The low neutron flux outside the actual core regions and the use of aluminum makes activation unfeasible. The monthly water and air surveys in the Facility indicate that no detectable activated corrosion products or fission products have existed in the Facility during its operation.
Therefore, no activated crud deposits could exist in any of the piping or duct works. Those areas which are accessible will be surveyed with the use of smears and micro R meters.
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(4) What is the total curie content of the Radioactive Materials shipment't-The first' shipment of stainless' steel, graphite, and 12 check. sources
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contains a total activity of 9.11 x 10 C1. The second shipment of three sources will be 6.69 x 10~ Ci.
After the second shipment containing the three sources, the radiation levels in the Facility will be very low. Measurements as indicated in Figure 7.of the Dismantling Plan show that levels in the core region will be at a mattimum around 80 pR/hr. A third shipment mostly containing these aluminum core components will contain mininal activity.
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l (5) Contamination Limits for Shipment Offsite Contamination of the Facility or its components has not been found due to the nature of our operations. Contamination limits at the Facility are 200 dpm beta-gamma activity and 10 dpm alpha activity for a 100 cm smear area, as per page 22 of the Dismantling Plan.
1 For Radioactive Materials shipments, the containers cannot be greater j than 200 pR/hr on the exterior of the container or greater than 10 l
pR/hr at one meter (49CFR 173.441). Three smears of at least 100 cm each are taken to assess non-fixed contamination levels. The limiti are 22 dpm/cm beta-gamma and 2.2 dpm/cm alpha (49CFR ,
173.443).
All items remaining in the NTR Facility at the time of the final radiation survey will be within the contamination limits specified in Regulatory Guide 1.86 and within 5 pR/hr above background at one meter l from the surface.
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