ML20236K981
| ML20236K981 | |
| Person / Time | |
|---|---|
| Site: | 07003051 |
| Issue date: | 07/28/1987 |
| From: | Mccreery P TRANSNUCLEAR, INC. |
| To: | Horn M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 28442, A-290, A-315, NUDOCS 8708100080 | |
| Download: ML20236K981 (21) | |
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l Ms. Merri L. Horn
'%.s US Nuclear Regulatory Commission M
i Uranium Fuel Section i
Fuel Cycle Safety Branch Washingt.on, DC 20555 Subj ect :
Tranonuclear. Inc., License Application Dockec No. 70-3051
Dear Ms. Horn:
The enclosed information is in response to the list of questions sent to Transnucl.;pr with your letter of June 22, 1987.
If any,of tlAJe responses are insuffi-d cient in content or depth, please do not hesitate to request whatever is lacking.
Thank you very much for the copy of ORO-651, Rev 5.
It will be most useful as we develop our UF6 storage program and procedures.
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3 Sinc-rely, i
't Paul N. McCreery Manager, Aiken Operations
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July 28, 1987 1
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ADDITIONAL INFORMATION RE TRANSNUCLEAR, INC.
LICENSE APPLICATION, DOCKET NO. 70-3051 Question 1.
Provide the minimum qualifications required for the Radiation Protcetion Officer, Manager of the Aiken q
l Facility, Chief Engineer, and the General Manager or the
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l resumes for the people currently in these positions.
Also
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provide an organization chart.
Response
Attached to this package of additional information j
is an organization chart (Attachment I), and resumes j
(Attechment II) for the following personnel:
I 1.
Kathryr. Lester - Radiation Protection Officer 2.
Paul M Creery
- Manager, Aiken Operations j
3.
Don Nolan
- Chief Engineer 4.
John Mangusi
- General Manager Question 2.
Describe the training program for employees.
Response
Radiation Safety training is described in detail in the Radiation Safety Training Manuel, e copy of which was given to Ms. Merri Horn Juring her visit to the Aiken site on June 2, 1987.
Reproductions of the supplementary materials and typical employee examinations are included.
As a prerequisite I
to entering a radiation area at the Aiken site all employees, and visitors who require more than occasional access to a radiation area, are required to complete this training program and to requalify annually.
Training continues with each job in the form of a Work Instruction (WI) tha.t is unique to the Job to be performed.
This is intended to accomplish the goal of ALARA and to keep waste and Job performance time to a minimum.
Question 3.
Describe your radiation protection program, including your ALARA policy, and contamination monitoring program.
Response
Transnuclear's radiation protection program is documented in the "Aiken Facility Radiation Safety Manual".
This manual documents existing practices and will be expanded to include procedures for working with UF before a license to 6
store UF becomes effective.
The manuel requires that e Work 6
Instruction and a Rediation Work Permit (RWP) must be issued to i
l direct all work performed in a Radiation Control Area (RCA).
I
The RWP informs the worker of the radiation levels in the RCA, the contamination levels, air concentrations and the anti-contamination clothing requirements.
Both the WI and the RWP must be reviewed and approved by the Manager, Aiken Operations and the Radiation Protection Engineer (RPE>.
Each worker must acknowledge by signeture that he or she has reed and understands the WI and RWP before he or she enters the RCA.
An RCA is established prior to the start of work.
It consists of a roped-off area which incorporates a step-off pad and waste receptacles et the exit point.
It is posted "C3ution:
Radiation Control Area" or Radioactive Contamination Area" as appropriate.
The floor of the eree is covered with plastic sheeting.
After the work in the RCA is completed, a comprehensive survey is performed.
The RCA is removed only after the fevel of removable contamination is less than 1000 dpm/100 cm beta-gamma and 100 dpm\\100 cm alpha, and the fixed contamination is less than 0.5 mR/hr contact (above background).
All employees who work in an RCA must first complete the Radiation Safety Training course and pass a written examination.
Training certification remains valid for one year.
All employees entering an RCA are issued a self-reading dosimeter (SRD) and a TLD badge.
A cumulative exposure log is kept for each individual's SRD readings until the quarterly TLD report is received.
Transnuclear's quarterly administrative exposure limits are as follows:
Rems / Calender Quarter Whole body: heed and trunk; active blood forming organs; lens of eyes: or gonads 1.0 Hands and forearms; feet and enkles 12.0 Skin and whole body 5.0 Total annual exposure limit for whole body is 3.75 R.
TLDs are located in offices and work areas ad 3acent to the radioactive materials storage area and elong the outside perimeter fence.
These TLDs are evaluated quarterly and have consistently recorded levels well below the 10CFR20.105 permissible levels for unrestricted areas.
Gross-wipe surveys are conducted weekly in the radiation area and the ad acent office space.
If any activity greater than 3
twice background is noted a smear survey is performed.
A comprehensive survey is done monthly in the radiation area.
An air semple is collected and analyzed daily.
Hi-volume grab samples are taken before removing the lid on any radioactive packege end randomly while work is in progress in the RCA.
No entry is allowed when air concentrations are greater than 25'4 MPC.
l Containers with dose rates greater than 20 mR/hr are stored within an internel fenced area which is padlocked when not occupied by personnel.
All other items not qu.slifying as " free
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release" are stored in the RCA.
4 The procedures used by Transnuclear are intendel to keep all employees' exposure es low as reasonably achievable.
l Question 4.
Describe the safety review committee, including i
purpose, membership, responsibilities, reporting authority, and frequency of meetings for activities covered by this license application.
Response
The Safety Review Committee consists of Dr. Alan Henson (President, Transnuclear, Inc.) Chairmen, Kathryn Lester, Radiation protection Engineer, and Paul McCreery, Manager, Aiken Operations.
The committee meets in Aiken at least once each year.
The agende for the meeting is drawn up by the RSO and reviewed by the President prior to the meeting date.
Meeting dates are announced in advance so that any employee may submit items to be considered by the committee.
Individual employees with responsibilities peculiar to the radiation safety topics on the meeting agenda also attend the meetings.
The requirement for t>is committee is given in Radiation Safety Procedure (RSP) -001.
The purpose of the committee is to review situations which may not have been specifically covered in an existing procedure, to i
determine the need for a new procedures and to discuse methods f
for reducing radiation exposures, weste volume, etc.
For this i
license application specifically, items will be discussed concerning the hazards of handling UF and the procedures necessary to assure safe storage and krensfer of the cylinders.
Question 5.
Confirm that records shall be maintained in accordance with 10CFR20.401.
Also provide the retention period for training and celebration records.
Response
The Aiken facility operates under en agreement state license, South Corolina No. 377.
The facility has been audited and has been found to be in complience with all of the requirements of the facility license, including 10CFR20.401.
The minimum retention period for training records and calibration records is 10 years past the date that the facility is released from all obligations by a licensing agency (South Carolina Department of Health end Environmental Control or the United States Nuclear Regulatory Commission).
Question 6.
Identify the types (not_ manufacturer names) of instrumentation used for measuring radioactivity, including their purpose, range calibration method and frequency, and testing that will be used for activities covered by this license application.
Response
Information regarding instrumentation in use at the Aiken site is presented in Attachment 3.
It should be noted that prior to the first use each day of a portable instrument, the response of that instrument is checked for consistency of its reading against a selected source.
The battery condition is checked and, where applicable, the HV reading is checked.
If any condition is noted that cannot be readily and accurately corrected (e.g.,
changing batteries) by the Radiation Safety Engineer, the instrument is declared to be out of calibration regardless of the calibration due date.
Question 7.
Describe your inspection program for receipt, transfer, and long-term storage.
Include how cylinder valves are protected if protectors are not used.
Confirm that a valve repair kit, as described in ORO-651, Rev. 5, will be available on the premises or at a minimum, the wooden pegs contained in the kit.
Response
Upon receipt, the UF cylinders will be surveyed in accordance with Transnuclear Rkdiation Safety procedure (RSP) -003, Section 4, except that the 35 ci limit will not apply to materials not covered by SC license No. 377.
If all radiation measurements are acceptable, and before unloading, each cylinder will be visually inspected in accordance with Figure 1 of ORO-651, Rev.5, " Examples of Acceptable and Unacceptable Damage to UF Cylinders" and a "UF Cylinder Inspection Data Sheet" (ibid., Figure 2) will bb completed for each cylinder, in its as-received condition.
A second
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inspection data sheet will be completed for each cylinder shipped.
Cylinder valves will be protected by storing the cylinders with the valve ends facing one another and with each pair of cylinders in near contact.
If the total inventory is odd in I
number, one grouping of three cylinders, end to end, will provide mutual valve protection.
All other cylinders will be stored in pairs, resting on timbers of 4" x 4" (nominal)
I
minimum size with heavy chocking pieces nailed in place to prevent rolling.
Only wooden pegs will be available to insert into a cavity left by a broken valve, rather than having an entire valve repair kit.
Since the cylinders will contain only
" heels" they will be at a slight negative pressure unless a valve is broken.
Once internal pressure has stabilized at ambient, there will be no driving force to cause material to escape, so simple plugging should be adequate.
Question _8.
Describe the location of the site, including the address.
The mailing address of the Aiken facility is:
Transnuclear, Inc.
Rt. 2, Box 777 Aiken, SC 29801 The shipping address is:
Transnuclear, Inc.
US Highway 78, 1.5 miles east of SC Rt. 302 Aiken, SC A map is enclosed (Attachment IV) which identifies the location with respect to surrounding landmarks.
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Attachment I Organization Chart
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Attachment II Resume's I
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RESUME' NAME:
Kathryn S.
Lester EDUCATION:
BS Health Physics, University of Nevada, Las Vegas, 1981 - 1985 l
EXPERIENCE
SUMMARY
Transnuclear, Inc. - Radiation Safety Engineer, 1987 to present Functions as the Radiation Safety Officer for Transnuclear's Aiken (SC) Facility.
Responsible for all aspects of the radiation protection program including training, regulatory compliance, instrumentation, records maintenance (both personnel and operational history) and for liaison with licensing authorities.
Also functions as the Aiken Facility QA Engina9r for instrument calibration work and on en as-needeo basis as a i
Cask Maintenance Field Engineer.
Chem-Nuclear Systems, Inc. - Senior Radiological Control Technician / RAM Broker, 1986 - 1987 As Senior RedCon Tech, was responsible for implementing the radiation and safety program, directing daily project activities to minimize radiation exposure, conducting radiological and safety surveys, radiological training programs, and maintaining pro]ect records pertaining to radiation and safety.
As NRC/ DOT Broker, acted as the l
company's legal representative for verifying that hazardous material shipments were in compliance with all federal and state laws, rules and regulations, and burial criteria.
Superviseu projects for the proper handling, packaging, l
shipping, and ultimate disposal of various radioactive materials.
This included supervising work activities, scheduling and personnel utilization, and providing l
technical guidance.
l DOE, Les Vegas, Nevada, Co-op Health physicist, 1985 - 1986 As a college student, participated in a co-op program with l
the US government.
Involved in projects with the nations weapons testing program at the Nevada Test Site.
Researched noble gas leakage occurring during tests and reported on the extremity TLD program implemented at the Nevada Test Site.
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RESUME' NAME:
Paul N.
McCreery EDUCATION:
1.
BS Physics, Louisiana State University, 1946 - 1948 2.
Master of Business Administration Program, Miami of Ohio, 1966 - 1969 EXPERIENCE
SUMMARY
Transnuclear, Inc. - Manager, Aiken Operations, 1983 to present.
Responsible for operations, testing, maintenance and spare parts programs for the Transnuclear cask fleet.
Conducts site surveys in preparation for cask handling operations at' reactors.
Also conducts personnel training programs and j
cask ha'.dling operations.
Project Manager for DOE-sponsored development programs which produced new conceptual designs for spent fuel casks and transport systems, and an on-site, dry, spent fuel consolidation system.
Responsible for adaptation of computer software
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(R: Base, System V) to control inventory, decertification schedules and other administrative applications.
Primarily responsible for obtaining a radioactive materials license for Transnuclear's Aiken facility (SCDHEC No. 377) for storage, handling testing and decontamination of cask ancillary equipment.
Allied-General Nuclear Services - Project Manager, 1978 - 1983.
Prepared detailed evaluations of all spent fuel casks (transport and storage) for use at Barnwell Nuclear Fuel Plant (BNFP).
Developed and implemented improved equipment and techniques for use of each cask, which vendors retained for use at other sites.
Managed several major projects for 4
DOE, including development of spent fuel cask fleet servicing facility designs and preparation of spent fuel cask interfacing requirements for all US commercial reactors.
Managed the design, fabrication, testing and operation of specialized remote handling equipment for use at BNFP.
Published over 15 me]or documents pertaining to his activities.
NL Industries, 1952 - 1978.
Barnwell Operations, Barnwell, SC, 1973 - 1978 As Manager, Cask Transportation Services was responsible for the cask fleet (NLI 1/2's, NLI 10/24's, MTR and ACEL) to serve exclusively the Barnwell reprocessing plant.
During this time the casks were used, under his direction, to transport spent fuel and non-fuel-bearing components throughout the US and from Canada into the US.
l Resume' for Paul N. McCreery Page 2 1
Fabrication Center, Wilmington, DE, 1972 - 1973 As Manager of Administration, supervised Quality Assurance, Accounting, Procurement and Data Processing.
He worked closely with fabrication operations (spent fuel casks for GE, Navy, GA, FFTF transfer cask, etc.).
After later being transferred to Barnwell Operations, he was on two occasions temporarily reassigned to this facility to troubleshoot operational problems.
Fuel Fabrication Plant, Albany, NY, 1970 - 1972 As Technical Services Menager hed direct responsibility for two QA organization (fuel, non-fuel), nuclecr material accountability and data processing.
Feed Materials Production Center, Fernald Ohio, 1952 - 1970 At this facility held positions in the nuclear materials accountability department from Technologist to Department Head.
Also served as Department Head for Quality Assurance.
Both departmental positions involved extensive work with procedure preparation, oversight and audits.
Industrial and Professional Organizations Member at Large, ANSI N-14 Transportation Committee Member, ANS Past Sr. Member, ASQC Founding Member, INMM
RESUME' NAME:
Donald J.
Nolan EDUCATION:
1.
BS in Marine Engineering, New York State Maritime College, 1956 2.
MS in Mechanical Engineering, University of Wisconsin, 1963 EXPERIENCE
SUMMARY
Transnuclear, Inc. - Chief Engineer, 1987 to present
- Meneger, Mechanical Design and Structural Analysis, 1982 - 1987; Project Engineer, 1977 - 1982.
Responsible for all design and analyses of systems and equipment, including casks, fuel baskets, lifting hardware, transport trailers and rail cars, licensing analyses and SAR material.
Also responsible for materials selection, analysis methods and procedures, design criteria j
development, procurement specification preparation, j
fabrication follow-up testing procedures and programs, and l
operational procedure development.
Performed concept l
evaluation and valve / impact studies in such areas as dry storage vault and ductile cast iron transport cask designs.
His duties also include responsibility for the l
Transnuclear QA program.
l Burns and Roe, Inc. - Supervisor, Building Design, 1975 - 1977.
Responsible for the coordination and oversight of designers and engineers of various disciplines in the performance of building designs for nuclear plants.
Was responsible for the design of the reactor containment and service buildings l
for the Clinch River Breeder Reactor.
Position required detailed familiarity with regulatory requirements, codes, i
standards, analysis methods and procedures.
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F.
Braun Co. - Senior Vessel Engineer, 1974 - 1975.
Responsible for preparation of specifications, design, fabrication and testing of ASME Code Vessels for Chemical I
and petrochemical industries.
Performed fabrication follow-up and audits of fabricators.
Gulf United Nuclear Corp. - Section Manager, 1973 - 1974; Project Engineer, 1963 - 1973.
As Section Manager, responsible for the design and development of liquid metal systems and components.
i Performed design and analysis of heat exchangers and l
evaluated performance of prototypes during tests.
As j
Project Engineer, was responsible for mechanical design and I
I
R Resume' of Donald J. Nolan Page 2 stress analysis of pressure vessels, piping systems, internal reactor components, and support structures for nuclear plants.
Allis-Chalmers Manufacturing Co. - Design Engineer, 1956 - 1962.
Responsible for design, stress analysis and testing for l
pressure vessels, support structures, and internal reactor components for both BWR and pWR designs.
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s RESUME' NAME:
John Mangusi EDUCATION:
1.
BS Civil Engineering, pennsylvania State University, 1962 2.
MS Nuclear Engineering, Pennsylvania State University, 1971 3.
Thirty-two Semester Hours Completed (MBA Program), Pace University, 1977 4.
Interstate Commerce Law and practice Course, College of Advanced Traffic, 1978 EXPERIENCE
SUMMARY
Transnuclear, Inc. - General Manager, Operations, 1971 to present.
Mr. Mangusi is responsible for directing the activities of Transnuclear's transportation group in bid preparation and pricing, transportation mode selection and coordination, packaging evaluation and selection, route evaluation and selection, and satisfaction of regulatory and safeguard requirements.
Transportation data base maintenance, close liaison with other international transport companies, carriers and transport officials (federal, state and local),and import / export licensing area also responsibilities of his group.
The groups has successfully managed thousands of transports.
He is also directly involved in management reviews of design, manufacturing, quality assurance and licensing of spent fuel casks.
Mr. Mangusi is responsible for preparing and administering Transnuclear's NRC approved security and contingency plans and administering Transnuclear's personnel security clearance program.
In preparation of the plans it is necessary to coordinate with airport security police, local police, state police and the FBI as well as federal, state and local regulatory authorities.
Nuclear Power Plant Operation and Staff Engineering Management, US Navy, 1963 - 1969.
He was a commissioned officer in the US Navy, a graduate of the US Navy Nuclear Power Program, and a qualified nuclear reactor operator and Engineering Officer of the Watch on the DIG prototype reactor at West Milton, NY and aboard the nuclear cruiser USS Long Beach CG(N)9.
He also served es Material Officer on the staff of an amphibious squadron commander responsible for engineering department material readiness and for logistic support of nine squadron ships.
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Attachment III Radiation Instrumentation Summary 1
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Instrumentation at the Aiken Facility 1
Automatic Recycling Scaler with alpha scintillation probe:
Purpose:
Counting smear tabs for alpha contamination.
Range:
0 - 99,999 counts.
Calibration:
Daily - source and background check.
-Yearly - by manufacturer.
1 Automatic Recycling Scaler with GM probe:
Purpose:
Counting smear tabs for beta-gamma contamination.
Range:
0 - 99,999 counts Calibration:
Daily - source and background check.
Monthly - new operating voltage and correction factor selected from GM plateau.
Yearly - by manufacturer.
2 Ion Chambers:
Purpose:
Dose Rates Range:
0 - 5,000 mR/hr Calibration:
Yearly - by manufacturer.
1 AC-DC Radiation Monitor with lead shielded GM pancake probe:
Purpose:
Frisking personnel at control point.
Range:
0 - 50,000 counts per minute Calibration:
Yearly - by manufacturer.
1 AC-DC Radiation Monitor with side wall GM probe:
Purpose:
Area monitor for radiation levels near storage aret Range:
0 - 800 mR/hr.
Calibration:
Yearly - by manufacturer 2
Portable Survey Meters with pancake GM probes.:
Purpose:
Frisking equipment and tools in the radiation area.
Range:
0 - 60,000 counts per minute Calibration:
Yearly - by manufacturer 1
Hi-Volume Air Sampler:
Purpose:
Grab air samples Range:
0 - 70 cubic feet per minute Calibration:
Yearly - by Transnuclear's Radiation Protection Engineer with manufacturer's calibration kit.
1 Low-Volume Air Sampler:
Purpose:
Daily air samples.
Range:
0 - 8 cubic feet per minute Calibration:
Yearly - by manufacturer l
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