ML20214W704
| ML20214W704 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 05/26/1987 |
| From: | Olsen A BABCOCK & WILCOX CO. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 28235, NUDOCS 8706160140 | |
| Download: ML20214W704 (39) | |
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Babcock & Wilcox
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yn P. O. Box 11165 Lynchburg, Virginia 24506-1165 (804) 522-6000 May 26, 1987 Fuel Cycle and Safety Branch RECE P'E T' ATTN: Mr. Leland C. Rouse, Chief Division of Fuel Cycle, Medical, Academic and Coninercial Use Safety
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NMSS U. S. Nuclear Regulatory Commission Washington, DC 20555
,.y 7}y <ii License: SNM-778, Docket 70-824
Subject:
Renewal Application, Revision No. 5 Gentlemen:
This is in response to comments by the NRC Staff on the proposed re-organization of the NNFD Research Laboratory. Attached is an instruction sheet for entering the attached replacement pages in the application manual. Changes are denoted by a vertical line in the right margin oppo-site each line where a change appears.
One change has been proposed by the Laboratory and is not in response to a Staff comment.
This change appears on Page 1-2, Section 1.4.7.
The Laboratory is requesting the addition of 1 gram of U-233 to the list of materials authorized under the license.
This material is used in the preparation of a tracer material that is needed to perform burnup analy-sis on irradiated fuel.
The addition of this material in the amount requested will not raise the possession limit above one effective kilo-gram.
These changes have been discussed with Dr. Soong of your office and it is my understanding that these responses address the final questions on the renewal application.
If, however, additional information is needed ease call me.
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INSTRUCTION SHEET LICENSE. RENEWAL. APPLICATION'
. DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 5
' AMENDMENT.0
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Docket Number 70-824 Period of Time - It is requested that this license be renewed 'for a period of 10 years.
1.4 POSSESSION LIMITS Material Physical Form Enrichment Amount
- 1. Uranium enriched Encapsulated or
> 20 %
3.5 Kg con-in U-235 irradiated tained U-235
- 2. Uranium enriched Unencapsulated
> 20 %
0.53 Kg con-in U-235 and unirradiated tained U-235
- 3. Uranium enriched Encapsulated or 5 % to <20%
1.2 Kg con-in U-235 irradiated tained U-235
- 4. Uranium enriched Unencapsulated 5 % to <20%
0.5 Kg con-in U-235 and unirradiated tained U-235
- 5. Uranium enriched Encapsulated or
.711 % to <5%
55 Kg con-in U-235 irradiated tained U-235 O
- e. uranium enriched Unencapsulated
.711 % to <5%
11 Kg con-in U-235 and unirradiated tained U-235
- 7. U-233 Any 1 Gram
- 8. Plutonium Unencapsulated 0.05 Kg and unirradiated
- 9. Source Material Any 6000 Kg
- 10. Fission Products Irradiated Fuel Quantity
& Transuranium contained in Elements 4 irradiated fuel as-semblies.
- 11. Fission Products Irradiated fuel 5,000,000 C1.
& Transuranium Elements License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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- 12. Any byproduct
. Irradiated 50,000 Ci.
material structural materials &
components
- 13. Byproduct Any 3000 Curies material with each, total at. nos. 3 not to exceed thru 83 1,000,000 Curies
- 14. Transuranium Any 20 mil 11 Curies elements each, total not to exceed 100 mil 11 Curies
- 15. Cf-252 Sealed Sources 4 milligrams
- 16. Am-241 Sealed Sources 30 Ci
- 17. H-3 Sealed Sources 100 Ci
- 18. H-3 0xide 3 Ci
- 19. H-3 Ni plated Sc 3 Ci tritide foil gV 1.5 LOCATION OF POSSESSION AND USE 1.5.1 Licensed material shall be possessed and used at the NNFD Research Laboratory (site).
1.5.2 Byproduct material in the form of sealed sources with activities of up to 500 mil 11 Curies may be possessed and used in locations other than the site for performing instrument calibration, elec-tronic noise analysis, shielding studies, or similar operations.
1.5.3 A restricted zone shall be established on the area north of the Chessie System main line right-of-way with a fence line based on radiation levels not exceeding an exposure dose rate of 500 milli-rems / year.
1.6 DEFINITIONS 1.6.1 Site means NNFD Research Laboratory.
License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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(3 v-2.0 GENERAL ORGANIZATIONAL AND ADMINISTRATIVE REQUIREMENTS 2.1 POLICY It shall be the policy of the site to maintain radiation exposures to employees and the general public as low as is reasonably achievable.
The facility procedures to ensure the safe handling of licensed material are the Area Operating Procedures.
2.2 ORGANIZATION RESPONSIBILITIES AND AUTHORITIES 2.2.1 Vice President, NNFD is ultimately responsible for ensuring that all operations at the site are conducted safely and in full com-pliance with NRC requirements.
2.2.2 Manager, EC&RR - The Manager, EC&RR is responsible for all safety of all operations at the site.
2.2.3 Facility Supervisor - The Facility Supervisor is responsible to the Manager, EC&RR for the safe conduct of all operations at the site and for ensuring that all applicable operations are conducted in compliance with the license and applicable regulations. To fulfill (q
these responsibilities the Facility Super-visor shall have the j
authority to stop any operation that he feels is unsafe or in violation of license. The Facility Supervisor shall review all new Area Operating Procedures and RWP's, and changes there to, for license and regulatory compliance and for facility safety; and he shall have approval authority for them. He shall submit items for review to the SRC. He shall have approval authority for Area Super-visors.
2.2.4 Area Supervisors - Area Supervisors are recommended by their division management and their appointment shall be jointly approved by the Supervisor, Health and Safety, and the Facility Supervisor.
They shall functionally report to the Facility Supervisor. They shall be responsible for the safety and compliance of all operations in their assigned areas. They shall be responsible for the maintaining the exposures of personnel assigned to their area below 300 millirem / week; 1250 millirems / quarter. They shall have approval authority for Radiation Work Permits that apply to their assigned areas.
They shall keep the Facility Supervisor advised of all plans for projects and work to be carried out in their areas.
License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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2.2.5 Manager, Safety and Licensing - The Manager, Safety and Licensing directs technical ar.d administrative activities and establishes policies related to facility decommissioning, accountability and safeguards of special nuclear material, radiation protection, nuclear criticality safety, industrial hygiene, industrial safety, and licensing.
He coordinates resources to perform operations in compliance with Federal and State regulations.
2.2.6 Supervisor, Health and Safety - The Supervisor, Health and Safety is responsible for providing adequate facilities, procedures, and properly trained personnel to implement the Health Physics and Industrial Safety Programs. He is responsible for health physics and industrial safety activities. The Supervisor, Health and Safety reports to the Manager, Safety and Licensing. The Super-visor, Health and Safety has the authority to stop any operation that he believes is contrary to accepted safety practices or license requirements. He shall review all new Area Operating Procedures, Radiation Work Permits and changes thereto, for the radiation safety aspects of the procedurc, RWP, or change, and he shall have approval authority for them. He shall conduct training programs for new employees and Authorized Users of Radioactive Ma terial. He shall be responsible for the shipment of licensed ma terial. The Supervisor, Health and Safety shall be a member of the Safety Review Committee but shall not be a member of the Safety
,m Audit Subcommittee. He shall have approval authority for Area
()
Supervisors.
2.2.7 Senior Health Physics Engineer - The Senior Health Physics Engineer shall administer activities of the Health Physics Staff. He shall report to the Supervisor, Health and Safety.
2.2.8 Industrial Safety Officer - The Industrial Safety Officer shall administer the industrial safety program. He shall report to the Supervisor, Health and Safety.
2.2.9 Nuclear Criticality Safety Officer - The Nuclear Criticality Safety Officer shall be responsible for ensuring that no operation at the site results in the inadvertent assembly of a critical mass. He shall review all new Area Operating Procedures and changes thereto, for nuclear criticality safety and shall have approval authority for them. He shall conduct training programs in criticality safety and perform criticality safety calculations. He shall report to the Manager, Safety and Licensing.
License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
O Revision No.
5 Page 2-2 Babcock & Wilcox a McDermott company
n 2.2.10 License Administrator - The License Administrator shall be V
responsible for administering the license. He is the primary liaison with -the NRC and other federal, state, and local agencies in matters that pertain to nuclear activities. He shall be the l
coordinator of the SRC and the Safety Audit Subcommittee and shall represent management on both. He shall maintain the permanent records of the SRC and shall be responsible for assuring that appropriate action is taken to correct SAS audit findings that are approved by the Manager, EC&RR. He shall report to the Manager, Safety and Licensing.
2.2.11 Accountability Specialist - The Accountability Specialist shall be responsible for the maintenance and retention of SNM accountability records. The Accountability Specialist shall report to the Manager, Safety and Licensing.
2.3 SAFETY REVIEW COMMITTEE 2.3.1 Function 2.3.1.1 The SRC shall review and approve all new Area Operating Pro-cedures, and shall concur with all changes made to them in the time interval since their last regular meeting.
2.3.1.2 The SRC shall review and approve new projects and major changes to f~d~
existing projects that utilize licensed materials.
2.3.1.3 The SRC shall review the annual report prepared by the Supervisor, Health and Safety. The report of the SCR's review shall be sent to the Manager, EC&RR, with a copy to the Vice President, NNFD.
2.3.1.4 'The SRC shall provide general consulting services in the field of radiation protection and the safe handling of licensed material.
2.3.1.5 The SRC shall review all SAS audit findings, all overexposures and unusual occurrences which must be reported to the NRC. These reviews shall be conducted during the next regularly scheduled meeting following the event and the results of the review shall be documented in the minutes.
2.3.1.6 The SRC Coordinator shall be responsible for resolving comments l
and recommendations made by the SRC.
2.3.2 Frequency of Meetings License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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n-2.3.2.1 The'SRC shall meet at least four times annually for the purposes V
of conducting its business as specified in Section 2.3.1.
2.3.3 Safety Audit Subcommittee 2.3.3.1 The SAS shall perform audits for. the Safety Review Committee.
2.3.3.2 The SAS shall audit facilities, procedures, records, and opera-tions for compliance with written requirements and the exercise of acceptable safety practices.
2.3.3.3 The SAS shall perform at least three audits annually, distributed over a 12-month period. Audits shall be made in accordance with written guidance to assure all aspect of 2.3.3.2 are audited.
2.3.3.4 SAS membership shall be appointed by the Manager, EC&RR.
2.3.4 Reporting 2.3.4.1 The SRC shall report to the Manager, EC&RR.
2.3.4.2 The SAS shall report to the Chairman, SRC.
2.3.5 Recordkeeping 2.3.5.1 Minutes of the SRC proceedings shall be prepared by the Chairman, (n)
SRC.
2.3.5.2 SRC Minutes shall be forwarded to the Manager, EC&RR, with a copy to the Vice President, NNFD, by the Chairman, SRC.
2.3.5.3 The permanent records of the SRC shall be kept by the SRC Coordinator.
2.3.S.4 SAS audit reports shall be prepared by the Chairman, SAS.
2.3.5.5 SAS audit reports shall be forwarded to the Chairman, SRC by the Chairman, SAS.
2.3.5.6 SAS audit reports shall be forwarded to the Manager, EC&RR with a copy to the Vice President, NNFD by the Chairman, SRC with comments, as he deems appropriate.
License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
O Revision No.
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V 2.4 APPROVAL AUTHORITY FOR PERSONNEL SELECTION 2.4.1 The Manager, EC&RR shall approve the personnel selected for' safety-related positions specified in Section 2.2 of this Part and shall appoint the members of the Safety Review Committee in writing. The NNFD shall appoint the Manager, EC&RR.
2.5 PERSONNEL EDUCATION AND EXPERIENCE REQUIREMENTS 2.5.1 Vice President, NNFD - The Vice President, NNFD shall be appointed in accordance with Company policy.
2.5.2 Manager, EC&RR - The Manager, EC&RR shall, as a minimum have a Bachelor's degree or equivalent and three years experience in the nuclear field.
He shall have demonstrated sufficient judgement and experience to manage the functions under his direction.
2.5.3 Facility Supervisor - The Facility Supervisor shall have a BS degree in science or engineering and three years experience in the use and handling of licensed material, or an AS degree in science or nuclear technology with five years experience in the use and handling of licensed material.
2.5.4 Area Supervisors - Area Supervisors shall have at least a high school education and two years of experience in the handling and O
use of licensed material. They shall have demonstrated sufficient knowledge and experience in the equipment and techniques employed in projects performed in their assigned areas to ensure that all operations are conducted safely and in full compliance with appli-cable license conditions and area operating procedures.
2.5.5 Manager, Safety and Licensing - The Manager, Safety and Licensing shall have a BS degree in a technical field and five years experience in the nuclear field.
2.5.6 Supervisor, Health and Safety - The Supervisor, Health and Safety shall have a BS degree in a technical field and professional experience in assignments involving radiation protection at the supervisory level. He must have four years experience and demonstrate proficiency in the application of radiation safety principles and be knowledgeable in fields related to radiation protection.
2.5.7 Senior Health Physics Engineer - The Senior Health Physics Engineer shall have a BS degree which shall include at least 20 quarter License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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(~'j hours health physics related course work, and two years of radi-ation control related experience or an MS degree and one year of radiation protection experience.
2.5.7 Industrial Safety Officer - The Industrial Safety Officer shall have at least one year's experience in radiation and industrial safe ty.
He shall be familiar with the codes and requirements of the Occupational Health and Safety Act of 1970 and the National Fire Protection Association.
2.5.8 Nuclear Criticality Safety Officer - The Nuclear Criticality Safety Officer shall have a BS degree in science or engineering. He must have either two years experience with nuclear criticality safety calculations similar to those associated with site activities or he must have one year's experience with nuclear criticality safety calculations similar to those associated with site activities if he has at least an additional two years' experience in nuclear reactor physics calculations.
2.5.9 Accountability Specialist - The Accountability Specialist shall have at least a high school education and three years' experience in the use of licensed material. He must demonstrate to Company management his knowledge of the principles necessary for the accountability and safeguarding of special nuclear materials.
2.5.10 License Administrator - The License Administrator shall have a BS fs!,)
degree in science or engineering and three years experience in s
nuclear technology or an AS degree in science or nuclear technology with five years experience in nuclear technology.
2.5.11 Safety Review Committee - The SRC membership, as a body, shall have expertise in chemistry, nuclear physics, health physics, and the safe handling of radioactive material. The SRC membership shall have a general understanding of nuclear criticality safety as it pertains to site operation.
2.6 TRAINING 2.6.1 Program 1 - This course is presented to site workers and non-site workers who will be granted access to the restricted area but who will not be granted unescorted access to the controlled areas. The course provides an introduction to radiation and radioactivity (understandable to a non-technical person) and a thorough coverage of safety rules and procedures, including the site emergency pro-cedures. The Supervisor, Health and Safety may modify the course License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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(l content for those individuals knowledgeable in the basics of radi-ation and radioactivity. However, safety rules, procedures, and emergency procedures that apply at the site shall be covered..
2.6.2 Program 2 - This course is presented to site workers and non-site workers who will be granted unescorted access to the restricted area and controlled areas but who will not be permitted to work with radioactive materials without supervision. The Supervisor, Health and Safety may modify the course content for those indi-viduals knowledgeable in the basics of radiation and radioactivity.
However, safety rules, procedures, and emergency procedures that apply at the site shall be covered. The effectiveness of the training shall be determined by a written examination.
2.6.3 Program 3 - This course shall be presented to site workers and non-site workers who will be granted unescorted access to the restricted area and controlled areas and will be permitted to work with radio-active materials and supervise such work. This course shall meet the requirements for designating a worker as an Authorized User.
The Supervisor, Health and Safety may modify the course content for those individuals knowledgeable in the basics of radiation and radioactivity. However, safety rules, procedures and emergency procedures that apply at the site shall be covered. The effective-ness of the training shall be determioned by a written examination.
p 2.6.4 Retraining - Persons who are designated as Authorized Users shall d
be retrained annually. Satisfactory completion of the retraining shall be determined by passing a written examination.
2.6.5 Respiratory Protection Training - Training in respiratory pro-tection techniques and equipment shall be required of all workers before the use of such equipment will be permitted.
Satisfactory completion of this training shall be determined by passing a written examination.
2.6.6 Respiratory Protection Retraining - Retraining in respiratory pro-tection shall be performed at two year intervals.
Satisfactory completion of this retraining shall be determined by passing a written examination.
2.6.7 The training specified in Section 2.6 shall be administered by the Supervisor, Health and Safety, or his designated and qualified al terna te.
2.6.8 Nuclear Criticality Safety Training - Nuclear Criticality Safety training provided as a part of the programs specified in Sections License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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2.6.2, 2.6.3 and 2.6.4, shall be performed by the Nuclear Criti-U cality Safety Officer or his designated alternate. The designated alternate must meet the same minimum qualifications as those speci-fled for the Nuclear Criticality Safety Officer (2.5.8).
2.7 OPERATING PROCEDURES 2.7.1 Area Operating Procedures 2.7.1.1 All operations with licensed material shall be conducted in accordance with Area Operating Procedures or Radiation Work Permits (see 3.1.1).
2.7.1.2 Area Operating Procedures (A0P) - Area Operating Procedures shall be established for all routine operations in which SNM, source and byproduct materials are stored or handled. A0P's shall include those nuclear criticality and radiation safety controls and limits that apply to the operation.
Each A0P shall be approved by the Nuclear Criticality Safety Officer or his designated alternate, the Supervisor, Health and Safety or his designated alternate, the Facility Supervisor or his designated alternate, and the Safety Review Committee.
2.7.1.3 A0P's may be revised with the approval of the Nuclear Criticality Safety Officer or his designated alternate, the Supervisor, Health n()
and Safety or his designated alternate, and the Facility Supervisor or his designated alternate. The revised procedure may be used with these approvals until the next scheduled regular meeting of the Safety Review Committee when the revision must be approved by the SRC.
2.7.1.4 A0P's shall be available in each operations area where they apply and shall be followed by site personnel.
2.7.1.5 Distribution of new and revised procedures shall be made in accordance with a document control system which assures that the procedure manuals contain only the most current revision of the procedures.
2.7.1.6 A0P manuals shall be reviewed annually by the Facility Supervisor to assure that the manuals contain the most current revision of the procedures.
2.7.2 Technical Procedures License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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2.7.2.1 Technical procedures shall be established, reviewed, approved, and V
followed for Health and Safety or Nuclear Criticality Safety. They shall be reviewed and approved by the Senior Health Physics Engineer
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or the Nuclear Criticality Safety Officer, respectively, or their designated alternate. The designated alternate for a Senior Health Physics Engineer must meet the minimum qualifications specified in Sections 2.5.6.
The designated alternate for the Nuclear Criti-cality Safety Officer must meet the same minimum qualifications specified in Section 2.5.8.
Approval signatures shall appear on the procedure.
2.8 INTERNAL AUDITS AND INSPECTIONS 2.8.1 Nuclear Criticality Safety 2.8.1.1 The Nuclear Criticality Safety Officer or his designated alternate shall conduct internal audits for the purpose of evaluating the nuclear criticality safety aspects of operations. This audit shall be conducted in accordance with written audit guidance.
This audit shall be conducted once each calendar quarter. A report of his findings shall be made to the Manager, EC&RR within two weeks of completing the audit. The audit reports shall be forwarded to the Facility Supervisor and the License Administrator.
The License Administrator shall be responsible for assuring that the appropriate corrective actions are taken to address the audit findings.
g 2.8.1.2 The Facility Supervisor shall perform an inspection weekly for compliance with the nuclear criticality safety aspects of the operations. Findings resulting from these inspections shall be reported to the Nuclear Criticality Safety Officer.
2.8.2 H,ealth Physics 2.8.2.1 The Supervisor, Health and Safety or his designated alternate shall conduct internal audits for the purpose of evaluating the health physics aspects of operations. This audit shall be conducted in accordance with written audit guidance. This audit shall be conducted once each month. A report of his findings shall be made to the Manager, EC&RR within two weeks of completing the audit. The audit reports shall be forwarded to the Manager, EC&RR and the License Administrator. The License Administrator shall be responsible for assuring the appropriate corrective actions are taken to address the audit findings.
License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
0 Revision No.
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2.8.3 General Safety and Compliance 2.8.3.1 The SAS performs audits of general safety and compliance...These audits shall be conducted three times annually. The audits shall be distributed over a 12-month period. The SAS shall include an audit of the Health and Safety Group at least once annually. This annual audit shall be performed by a qualified individual who is independent of the Health and Safety Group. Other areas shall be audited for compliance with written requirements and the exercise of acceptable safety practices. Audits shall be made in accordance with written guidance to assure all aspects of Section 2.3.3.2 are audited. The Chairman, SAS shall file a report of the audit findings with the Chairman, SRC, with a copy to the License Admin-istrator and the Facility Supervisor and members of the SRC. The Chairman, SRC shall forward the report to the Manager, EC&RR with comments, as he deems appropriate. The License Administrator shall be responsible for assuring that the appropriate corrective actions are taken to address the audit findings.
2.9 INVESTIGATIONS AND REPORTING 0F 0FF-NORMAL OCCURRENCES 2.9.1 License Administrator The License Administrator shall investigate and report, when n
required, the following types of off-normal occurrences:
V 2.9.1.1 Excessive levels of radiation from or contamination on packages upon receipt.
2.9.1.2 Thef ts, attempted thef ts, or losses of licensed material, other than normal operating losses.
2.9.1.3 Incidents as specified in 10 CFR 20.403 2.9.1.4 Overexposure of individuals and excessive levels and concentra-tions of radioactivity.
2.9.1.5 Failures to comply and defects pursuant to 10 CFR 21.
2.9.1.6 Changes to security, safeguards, or emergency plans made without prior NRC approval, when prior approval is required.
2.9.1.7 Failures to comply with license requirements.
2.9.1.8 Unapproved storage or use of licensed material.
License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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'O 2.9.2 Supervisor, Health and Safety V
The Supervisor, Health and Safety shall perform investigations and issue reports of the following:
2.9.2.1 Higher than expected personnel exposures.
2.9.2.2 Higher than expected concentration of airborne activity in the facili ty.
2.9.2.3 Unauthorized entry into a High Radiation or Airborne Radioactive Material area.
2.9.2.4 Failure of equipment or instrumentation to meet Health and Safety requirements.
2.9.3 Facility Supervisor The Facility Supervisor shall perform investigations of the following:
2.9.3.1 Any violation of nuclear criticality safety criteria.
2.9.3.2 Any violation of Area Operating Procedures or RWP's, i
2.10 RECORDS The following positions or organizations shall be responsible for maintaining the indicated records, for the period specified.
Records may be kept in original form, microfilm or in computer storage. The symbol (*) indicates that the record will be retained until the NRC authorizes its disposition.
2.10.1 Health and Safety Group Health and Safety Supervisor aucits 2 years Shipping and receiving RM forms 5 years Waste disposal records
(*)
Personnel dosimetry records
(*)
Results of Bioassays and Whole Body Counting
(*)
Releases to the environment
(*)
Radiation survey data 2 years Contamination survey data 2 years Radiation Work Permits (completed) 5 years Radiation detection instrument calibration 2 years License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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-(~T Leak tests of sealed sources 2 years x_/
Personnel training
(*)
Personnel retraining
(*)-
Airborne radioactivity sampling data
(*)
NRC-4 forms
(*)
NRC-5 forms
(*)
2.10.2 Nuclear Criticality Safety Officer Nuclear criticality safety 6 months after evaluations and calculations termination of the approved process.
Nuclear Criticality Safety Officer 2 years Audit Reports.
2.10.3 License Administrator Safety Review Committee Minutes
(*)
Safety Audit Subcommittee Audit Reports 2 years Investigation reports of off-normal occurrences 2 years 2.10.4 Emergency Records
.O Records perteiains to emerseacy respease end neeperedness sheii de retained in accordance with Radiological Contingency Plan, Section 8.0.
License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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FIGURE 2-1 SITE ORGANIZATION NNFD RESEARCH LABORATORY ORACANIZTION NAVAL NUCLEAR FUEL DIVISION VICE PRESIDENT EMPLOYEE, COMMUNITY, &
REGULATORY RELATIONS MANAGER FACILITY SAFETY SUPERVISOR REVIEW COMMITTEE SAFETY & LICENSING MANAGER Am,/
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I NUCLEAR LICENSE -
HEALTH & SAFETY CRITICALITY ACCOUNTABILITY ADMINISTRATOR SAFETY SPECIALIST SUPERVISOR OFFICER SENIOR INDUSTRIAL HEALTH PHYSICS SAFETY ENGINEER OFFICER HEALTH PHYSICS GROUP 1
1 AREA AREA SUPERVISOR SUPERVISOR I
License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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hV 3.2.4.9.1 Site Workers (Restricted Area) shall be issued a film badge, a thermoluminescent dosimeter (TLD), and either a self-reading dosimeter (SRD) or an indirect-reading dosimeter (IRD).
3.2.4.9.2 Site Workers (Controlled Areas) shall be issued a film badge, a TLD, and either a SRD or an IRD.
3.2.4.9.3 Visitors shall be issued a TLD.
3.2.4.9.4 Non-Site Workers (Restricted Area) shall be issued a film badge, a TLD, and either a SRD or an IRD.
3.2.4.9.5 Non-Site Workers (Controlled Areas) shall be issued a film badge, a TLD, and either a SRD or an IRD.
3.2.4.9.6 Film badges and TLD's that are issued pursuant to 10 CFR 20,202 shall be processed and evaluated monthly.
3.2.4.9.7 Whole body dose equivalents to workers shall be limited to 300 mrem / week and 1.25 Rem / quarter by the appropriate Area Supervisor.
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License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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n 7.0 DECOMMISSIONING PLAN U
The site'is committed to decommissioning the facilities which have been used for the use and storage of licensed material at the end of their useful life. At the time of this application for renewal of License No. SNM-778, two programs are underway to decommission Buildings A and C.
It is presently estimated that these two facili-ties will be decontaminated and ready for release for unrestricted use by March, 1987.
7.1 PLANNING CONSIDERATIONS 7.1.1 The history of the facility shall be determined to facilitate the identification of services, equipment, and areas that should be included in the survey plan.
7.1.2 The decontamination of facilities and equipment must meet the levels of contamination specified in Table 1. Guidelines for Decon-l tamination of Facilities and Equipment Prior to Release for Unre-stricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material, dated May,1987, as amended.
In ad-l dition, a reasonable effort will be made to further reduce contami-nation levels to those which are as low as reasonably achievable.
7.1.3 No covering will be applied to remaining surfaces until it has been O
determined that contamination levels are below those of Table 1 l
Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for By-product, Source, or Special Nuclear Material, dated May,1987, as amended, and until it has been determined that a reasonable effort has been made to further reduce contamination below those specified above.
7.1.4 The radioactive contamination of interior surfaces of pipes, ductwork, and other conduits will be determined by taking measurements at all traps and other appropriate access points, provided contamination at these locations is likely to be representative of interior conditions.
If such access locations are not likely to be representative, or if interior surfaces are inaccessible, the interior surfaces will be assumed to be contaminated in excess of levels specified in Table 1, Guidelines l
for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material, dated May,1987, as amended.
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7.1.5 A radiological survey plan shall be designed and implemented to V
assess the extent of decontamination necessary. The survey plan will include the taking of smear samples of roofs, ceilings, walls, floors, and equipment.
It shall also include the taking of core samples of concrete floors, walls, ceilings and pools. Core samples shall also be taken of soil beneath floors and pools and in the vicinity of under ground drainlines. Records of the survey and sample results shall be prepared and maintained.
7.1.6 Equipment will be disposed of by burial or sale. The decontami-nation of equipment scheduled for burial will be sufficient to meet the requirements of transportation and those of the receiving facili ty. The decontamination of equipment scheduled for sale to a licensed facility will be sufficient to meet the requirements of transportation and those of the receiving facility. Equipment scheduled for receipt by a non-licensee shall be decontaminated to levels specified in Table 1, Guidelines for Decontamination of l
Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material, dated May,1987, as amended.
7.1.7 At the completion of decommissioning activities, a report of the final survey shall be prepared and submitted to the NRC with a request that a confirmatory inspection be made and that the facility be released for unrestricted use.
O 7.2 COST AND FINANCIAL ARRANGEMENTS 7.2.1 Financial Arrangements - Financial arrangements to cover the cost of decommissioning are set forth in the letter dated September 16, 1985, from L. V. Jordan, Assistant Controller.
7.2.2 Cost Estimate Guidelines - The following are the general guidelines upon which the estimates are based.
7.2.2.1 No facility will be razed.
7.2.2.2 No "mothballing" of any facility or perpetual surveillance is contemplated. All facilities will be released for unrestricted use upon approval by NRC.
7.2.2.3
" Reasonable" efforts to decontaminate below levels specified in Table 1, Regulatory Guide 1.86, dated June 1974, shall be required only to the extent that the benefits derived clearly justify the additional cost expenditures.
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0 7.2.2.4 There wiii be no requirement to prenere or furnish prior to.
s concurrent with, or subsequent to decommissioning, any environ-mental data or impact reports.
7.2.2.5 Phys /d$1 security pursuant to 10.CFR 73 will not be required at the J f,-
-J time' thef ecommissioning Plan 4I implemented.
D 7.2.2.6 All eit$ dates are given in 1985 dollars. No factor for escalation has been included.
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7.2.3 Technical Guidelines - The following are the technical guidell'nes t ; j' '
upon which the estimated costs'are based.
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7.2.3.1 Surface removal will be required for decontamination of the interior surface of' hot cells, transfer canal and storage pool,:.
a-liquid waste retention basins SK-1, SK-2,10K-1,10K-2 and the r
Building A basin, primary equipment cell pump pit, ard the
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Building B Containment Pool.
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burial facilities in Richland, Washington.
i 7.2.3.3 No decontamination of cold area's will be required.
7.2.3.4 Removal of ventilation ducting beyor.d the first stage cf HEPA Cv')
filtration will not be requirec'.
7.2.3.5 Removal of piping in the ifquid waste system will be required.
7.2.3.6 Disassembly and off site burial of liquid waste tanks 2K-1.# 2K-2, 2K-3,13K, 4K-1, 4K-2, 300-1 ard 300-2.will be required.
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7.2.3.7 Disassembly and off site burial of the waste storagp tubes will be required.
7.2.3.8 Health and Safety labor will be approximately 20 percent of the total labor cost.
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'7.2/J.9 Rental of special shippi'ig. containers will be required.
ty 7.2.4 Cost Estimate I
License No SNM-778 Docket No.70-824 Date May, 1987:
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c 7.2.4.1 Building A
$500,000 Lb Building B
$8,500,000 Building C
$4,500,000 Building J
$500,000 Liquid Waste Disposal Facility
$1,000,000 TOTAL 515,000,000 License No SNM-778 Docket No. 70 824 Date May, 1987 Amendment No.
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8.0 RADIOLOGICAL CONTINGENCY PLAN v
The site shall maintain and execute the response measures of the Radiological Contingency Plan submitted to the NRC on November 15, 1983, in accordance with provisions of the February 11,1981 order.
The site shall maintain implementing procedures for the Radiological Contingency Plan as necessary to implement the Plan. The site shall make no change in the Radiological Contingency Plan that would decrease the response effectiveness of the Plan without NRC approval.
The site may make changes to the Radiological Contingency Plan without prior NRC approval if the changes do not decrease the response effec-tiveness of the Plan. The site shall maintain records of changes that were made to the Plan without prior approval for a pericd of two years from the date of change and shall furnish the Chief, Fuel Cycle and Safety Branch, Division of Fuel Cycle, Medical, Academic and Commercial Use Safety, NMSS, USNRC, Washington, DC 20555 and Region II, a report containing a description of each change within six months after the change is made.
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O 11.0 ORGANIZATION AND PERSONNEL 11.1 SITE ORGANIZATION 11.1.1 Vice President, NNFD - The Vice President, NNFD is responsible for ensuring that all operations on site are conducted safety and in full compliance with NRC requirements.
11.1.2 The Manager, Employee, Community, and Regulatory Relations (Manager, EC&RR) - The Manager, EC&RR is responsible for the safety of site operations. The Manager, Safety and Licensing, Manager, Facilities, and the Facility Supervisor report to him.
11.1.3 Facility Supervisor - Research and development work at the site will be performed by personnel who do not report to the Manager, EC&RR. Therefore, the positions of Facility Supervisor and Area Supervisor have been established to control the workers and their activities.
The Facility Supervisor shall report to the Manager, EC&RR. He shall be responsible for the safety of all oprations performed pursuant to License SNM-778. He shall utilize the expertise of the Supervisor, Health and Safety, the Accountability Specialist, Nuclear Criticality Safety Officer, and the Industrial Safety bm Officer to ensure the safety of operations.
11.1.4 Vea Supervisors - Area Supervisors are selected by their Division Management and shall be jointly approved by the Facility Supervisor and the Supervisor, Health and Safety. Area Supervisors function-ally report to the Facility Supervisor and are responsible for the safe performance of all activities in their assigned area and that all activities within their assigned areas are performed in full compliance with the license.
11.1.5 Manager, Safety and Licensing - The Manager of Safety and Licensing is appointed by and reports to the Manager, EC&RR.
He is respon-sible for the proper management of the materials accounting function, licensing function, nuclear criticality safety function, and the Health and Safety Group. He manages the allotment of funds and other resources and assures the proper assignment of personnel priorities. The Supervisor, Health and Safety, Accountability Specialist, Nuclear Criticality Safety Officer, and License Admin-istrator, report to him.
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11.1.6 Supervisor, Health and Safety - The Supervisor of Health and Safety is appointed by the Manager, EC&RR and reports to the Manager, v
Safety and Licensing. The Supervisor directs the overall operation i-of the Health and Safety Group and the Industrial Safety Officer.
He also serves on the Safety Review Comittee. He has the authority to stop any operation that he believes is contrary to accepted safety practices, or license requirements. The Supervisor has over-all responsibility for the shipment and receipt of licensed material and exercises signature authority on all Area Operating Procedures.
He performs audits of the site for compliance with Health and Safety rules. The Senior Health Physics Engineer and Industrial Safety Officer report to him.
11.1.7 Senior Health Physics Engineer - A Senior Health Physics Engineer reports to the Supervisor, Health and Safety. He administers the activities of the Health Physics staff, which include:
1.
Performing area surveys 2.
Administering the air sampling program 3.
Administering the respiratory protection program 4.
Administering the bioassay program 5.
Leak testing radioactive sources q
V 6.
Supervising shipping and receiving of licensed material 7.
Supervising and coordinating the waste disposal program 8.
Assisting in personnel, equipment, and facility decontamination 9.
Conducting radiation safety training
- 10. Providing expertise in all aspects of radiation protection
- 11. Generating, maintaining and distributing records and reports that are required by NRC regulations or Health Physics procedures
- 12. Providing expertise in health physics to the Facility Supervisor.
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3 11.1.8 Industrial Safety Officer - The Industrial Safety Officer reports (J
K to the Supervisor, Health and Safety. His responsibilities include the following:
1.
Administering the industrial safety program 2.
Reviewing proposed facility changes to ensure fire safety 3.
Providing expertise in fire prevention to the Facility Supervisor and the Safety Review Committee 4.
Performing tests, maintenance, and inspection of fire protection, control, and extinguishing equipment 5.
Providing training for the site Fire and Rescue Team and off site support agencies 6.
Inspecting all areas of the site periodically to ensure:
a.
Proper storage and use of flammable solvents b.
Proper placement of fire extinguishing equipment c.
Elimination of fire hazards d.
Reduction, to the extent practicable, of the accumulation O
of fiammebie materiais e.
Proper use and maintenance of electrical equipment.
7.
Working with Area Supervisors to formulate safety rules and elimination of hazards 8.
Investigation of all personnel injuries 9.
Keeping management informed concerning industrial safety activities
- 10. Conducting industrial safety training.
11.1.9 Accountability Specialist - The Accountability Specialist reports to the Manager, Safety and Licensing.
He is responsible for the maintenance and retention of SNM accountability records. He prepares and transmits the reports required by regulation to inform regulatory agencies of SNM transactions.
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/"3 11.1.10 License Administrator - The License Administrator reports to the V
Manager, Safety and Licensing. The License Administrator is responsible for administering the license. He is the primary liaison between the site and the NRC and other federal, state, and local agencies regarding nuclear matters. He is the coordinator of the Safety Review Committee and Chairman of the Safety Audit Sub-committee and represents site management on both. The License Administrator is responsible for ensuring that corrective action is taken in response to audit findings as they pertain to licensed activi ties.
'11.1.11 Nuclear Criticality Safety Officer - The Nuclear Criticality Safety Officer is appointed by and reports to the Manager, Safety and Licensing. The Nuclear Criticality Safety Officer is responsible for ensuring that no operation at the site can lead to the inad-vertent assembly of a critical mass. To help assure this, he has signature authority for all new Area Operating Procedures and changes to these procedures, he observes operations, institutes educational programs if and when he deems them necessary, and carries out confirming nuclear criticality safety calculations.
The Nuclear Criticality Safety Officer will inspect all site oper-ations where special nuclear material is being processed, quarterly.
Other areas may be inspected less frequently, but all licensed fa-cilities will be inspected at least twice a year. He will consider p
area operations when scheduling these inspections and will, if d
necessary, schedule his inspection at more frequent intervals. His consideration should include inspection of new operations, an audit of nuclear safety records, a check for area posting, a review of current practices and a review of corrective actions recommended during previous audits and the status of the recommended actions.
He shall submit a report of his finding to the Manager, EC&RR, with a copy to the License Administrator. Prior to the submission of the report, he will discuss its contents with the Facility Supervisor.
The following information is to be included:
1.
Areas visited 2.
Operations observed 3.
Unsafe practices and situations noted 4.
Nuclear safety activity of the quarter 5.
Recommendations.
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. reports to the Manager, EC&RR.
He shall be responsible to the Manager, EC&RR for the safe conduct of all operations at the site and for ensuring that these operations are conducted'in accordance with all license conditions. The Facility Supervisor shall review and have approval authority for Area Operating Procedures. He shall have authority to terminate any operation that he deems contrary to license conditions, Area Operating Procedures, or general safety conditions. The Facility Supervisor shall become familiar with all license conditions and procedures concerned with radiation safety, nuclear safety, industrial safety, and nuclear materials safeguards.
He may consult with the following personnel to ensure compliance with all safety regulations and principles:
Supervisor, Health and Safety Nuclear Safety Officer Industrial Safety Officer Accountability Specialist 11.1.13 Safety Review Committee - The Safety Review Committee (SRC) shall be comprised of at least five technically trained and experienced members appointed by the Manager, EC&RR. One member shall be se-lected by the Manager, EC&RR to be the SRC Chairman. The Chairman Cm shall preside at the meetings and keep the minutes. The Manager, EC&RR shall appoint an Alternate Chairman who shall act for the Chairman during absences.
One member shall be appointed by the Manager, EC&RR to be the SRC Coordinator. The Coordinator shall represent site management on the SRC, set the meeting agenda, and maintains the permanent files of the Committee.
The SRC membership shall have expertise in chemistry, nuclear physics, health physics, and the safe handling of radioactive ma terial. The SRC membership shall have a general understanding of nuclear criticality safety as it pertains to site operations.
Consultants with special expertise are available to the Committee when needed.
The SRC shall meet at least four times a year. A quorum shall consist of a simple majority of the membership including the Chairman. The SRC shall review and approve all Area Operating Procedures.
It shall review and approve new projects that utilize licensed material that are significantly different from previously reviewed and approved projects. The SRC shall review the annual License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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(a report issued by the Supervisor, Health and Safety which summarizes V
site workers' exposures, environmental releases, and a summary of the ALARA program accomplishments. The SRC Chairman shall forward the Committee minutes to the Manager, EC&RR, with copies to the Vice President, NNFD and the SRC Coordinator.
The Manager, EC&RR shall appoint the members of the Safety Audit Sub-committee (SAS). The SAS shall be comprised of at least two individuals, one of whom shall be designated as Chairman and he shall report to the Chairman, SRC. The SAS shall audit site oper-ations at least three times annually, with successive audits separated by at least two months. Additional audits may be performed at any time. The SAS Chairman shall develop the audit report and submit it to the SRC Chairman. The SRC Chairman shall submit the audit report to the Manager, EC&RR with appropriate comments, with a copy to the License Administrator.
11.2 EDUCATION AND EXPERIENCE OF KEY PERSONNEL 11.2.1 Safety and Licensing Manager - Richard L. Bennett Education:
B.Ch.E. - Chemical Engineering, University of Delaware, 1958 O
ExPerieace:
(1985-Present)
Babcock & Wilcox, Manager, Safety and Licensing, Lynchburg Research Center, Lynchburg, Virginia.
See Section 11.2.1 (1982-1985)
Babcock & Wilcox, Manager, Building C Decommissioning, Lynchburg Research Center, Lynchburg, Virginia He was responsible for decontaminating facilities that were used for preparation of experimental quantities of nuclear fuels containing plutonium.
(1973-1982)
Babcock & Wilcox, Supervisor, Process Technology Group, Lynchburg Research Center, Lynchburg, Virginia License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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This group was responsible for long-range studies, design assistance, start-up assistance, and preparation of environmental reports and safety analyses related to nuclear fuel conversion.
Some of the specific projects performed by the group were prepa-ration of the designs for a low-enriched nuclear fuel conversion plant, preparation of a conceptual design for a spiked nuclear fuel fabrication plant, process engineering assistance to nuclear fuel conversion plants, development of a halide volatility scrap recovery process, development of alternative effluent treatment systems for various nuclear fuel conversion processes, and evaluation of fabrication nethods for advanced fuels.
(1971-1973)
Babcock & Wilcox, Senior Research Engineer, Lynchburg Research Center, Lynchburg, Virginia He was responsible for the conceptual design of a facility to treat the effluent from a nuclear fuel plant and developing and evaluating processes for recovering byproducts from B&W wastes.
(1959-1971)
American Cyanamid Company, Process Engineer, Piney River, Virginia He has had broad experience in chemical engineering. This includes research and development, designing equipment and processes, testing and operating new equipment, pilot plant operation, process engineering, and economic evaluation. He has specific knowledge in p) pigment manufacture, effluent treatment, and byproduct recovery.
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Professional Affiliations:
American Institute of Chemical Engineers (Member)
American Nuclear Society (Member) 11.2.2 Supervisor, Health and Safety - Gary S. Hoovler Education:
B.S. - Nuclear Engineering, University of Virginia M.S. - Nuclear Engineering, University of Virginia
- 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> toward Master of Engineering Administration, George Washington University
- Respiratory Protection for Nuclear Industry Experience:
(1986-Present)
Babcock & Wilcox, Supervisor, Health and Safety, License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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Mr. Hoovler is responsible for the Health Physics and Industrial Safety functions at the Lynchburg Research Center; reporting to the Manager, Safety and Licensing.
Mr. Hoovler is responsible for assuring that all radioactive ma-terials at the LRC are properly handled, labeled, and stored. He is responsible for the proper packaging and shipping of radioactive materials, and for radioactive waste disposal.
He is responsible for the proper use, storage and disposal of other hazardous materi-l als at the LRC.
Mr. Hoovler is responsible for establishing, maintaining and admin-istering training programs in health physics and industrial safety for employees. He is responsible for reviewing all Area Operating Procedures, Radiation Work Permits, and all Technical Procedures that apply to the Health Physics and Industrial Safety operations.
He is a member of the Safety Review Committee.
1984-1986)
Babcock & Wilcox, Project Manager, Decommissioning, Lynchburg Research Center, Lynchburg, Virginia Mr. Hoovier was the Project Manager for the Decommissioning Program reporting the the Director, LRC.
O He developed methods ead directed ect4vities for decoatemiaetioa and survey of Building A and the Critical Experiment Facility, which together compromise an area of 14,000 square feet. He was also responsible for the development of methods and directing the activities for the decontamination and survey of the 20,000 square foot Plutonium Development Laboratory. The objective of both pro-I jects was for their release for unrestricted use and designation as non-use areas for NRC-licensed materials.
(1981-1983)
Babcock & Wilcox, Supervisor, Radiation Experiments l
Group, Lynchburg Research Center, Lynchburg, I
Virginia Mr. Hoovler was Supervisor of the Radiation Experiments Group in the Nuclear Physics Section. He helped to develop the soil assay method used in the plutonium decontamination project, worked on the EPRI Radiation Control Program, and performed experimental work developing radiation gauges for several company applications.
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h (1976-1981)
Babcock & Wilcox, Research Experiments Group, V
Lynchburg Research Canter, Lynchburg, Virginia y
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Mr. Hoovler worked in the Reactor Experiments Group of the Nuclear Physics Section.
He joined B&W in 1976 as a research engineer.
In 1978, af ter receiving his Senior Reactor Operator's License, he was appointed as the CX-10 Operations Supervisor and promoted to Senior Research Engineer in 1980.
He worked on the Department of Energy's Spent Fuel Storage critical experiment program and served on ANS Working Group 15.1.
He worked on the neutron spectrum unfolding code SAND II. addy current analysis, and on experiments to demonstrate the use of beryllium-gold as a passive technique for measuring fission product distribution in spent fuel.
11.2.3 Senior Health Physics Engineer - Steven W. Schilthelm Education:
B.S. - Nuclear Engineering, University of Wisconsin, Madison, 1983 M.S. - Health Physics, University of Wisconsin, Madison,1985
- Domestic & International Shipping of Radioactive Material.
Experience:
O (1985-Present)
Babcock & Wilcox, Senior Health Physicist, Lynchburg Research Center, Lynchburg, Virginia Mr. Schilthelm is responsible for administering the Health Physics Program at the Lynchburg Research Center. His duties include external and internal exposure control, shipping and receiving of radioactive material, maintaining the respiratory protection pro-gram, preparation and presentation of radiological safety training courses, maintaining the support for licensed activities.
Mr. Schilthelm is the Emergency Radiological Safety Officer and is the designated alternate for the position of Supervisor, He'alth and Sa fety.
(1984-1985) Research Specialist, Synchrotron Radiation Center, University of Wisconsin, Madison, Wisconsin Mr. Schilthelm was responsible for Radiation Surveys and subsequent shielding calculations and design at the 800 Mev electron acceler-License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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ator/ storage ring. He co-authored a shielding upgrade proposal that was presented to the National Science Foundation, and he pro-vided the experimental basis for the proposal. Mr. Schilthelm presented a paper at the 1985 Health Physics Society meeting, en-titled " Radiation Survey Measurements at the Aladdin Synchrotron Light Source."
Professional Affiliation:
American Nuclear Society (Member)
Health Physics Society (Member) 11.2.4 Industrial Safety Officer - Reginald R. Spradlin Education: - Graduate, Appomattox County High School
- Certified Instructor Trainer, Basic Cardiac Life Support, American Heart Association
- Certified Instructor, First Aid & Advanced First Aid, American Red Cross
- Training in the following areas:
Industrial Safety Fire Fighting Rescue Extrication Fire Protection Fire Extinguishing Equipment and Materials f-(,3/
Arson Investigation.
Experience:
(1972-Present) Babcock & Wilcox, Industrial Safety Officer, Lynchburg Research Center, Lynchburg, Virginia Mr. Spradlin is the LRC's Industrial Safety Officer. As such he is responsible for compliance with the regulations of the Occupational Health and Safety Administration. He advises the LRC on the standards and requirements of the National Fire Protection Associ-ation and performs reviews of equipment and systems for compliance with NFPA standards. He performs inspections of facilities and equipment for fire protection purposes. He reviews facility changes and modifications to ensure fire safety. Mr. Spradlin performs tests, maintenance, and inspection of fire protection, control and extinguishing equipment. He is responsible for investi-gating all accidents, and keeping his management informed of safety activities. He performs fire and rescue training for the members of the LRC's Fire and Rescue Team, and serves as the Captain of the License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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team. He is a certified Shock -Trauma Technician, an Emergency V
Medical Technician, and certified instructor in CPR and Standard and Advanced First Aid.
(1971-1972) Babcock & Wilcox, Accountability Technician, Lynchburg Research Center, Lynchburg, Virginia Mr. Spradlin served as the Accountability Technician.
In this capacity he was responsible for the recordkeeping system for SNM accountability in the Plutonium Development Laboratory. He recorded all transfers of SNM, performed inventories, and updated the unit log records.
(1969-1971) Babcock & Wilcox, Health Physics Technician, Lynchburg Research Center, Lynchburg, Virginia Mr. Spradlin was a health physics technician in the Plutonium Development Laboratory.
He was responsible for performing contamination surveys of the facility, assisting in the monitoring of bagging operations, and supervising decontamination.
He implemented the surveillance program for airborne radioactive material.
He performed maintenance, testing, and calibration of alpha particle survey instrumentation and counting equipment. He implemented the respiratory protection program in that laboratory.
' "'~ ** * ' "" ' *' "'*"* '""**"'"' '**""*"'
CJ' Lynchburg Research Center, Lynchburg, Virginia As a plant engineering technician, Mr. Spradlin performed installation, modification, and repair of facilities, equipment, and experimental apparatus at the LRC. He performed these duties on electrical, mechanical and plumbing systems.
(1952-1967) Mead Corporation, Maintenance Superintendent, Mead Paper Company, Lynchburg, Virginia Mr. Spradlin served in several capacities during this period, including: finishing operation, paper machine operation, M111 wright, Maintenance Foreman, Maintenance Superintendent, Safety Inspector and Accident Investigator.
Professional Affiliations:
Concord Rescue Squad - Founding President American Heart Association - Cardiac Care Committee License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
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11.2.5 Accountability Specialist - Kenneth D. Long
-v Education:
Graduate - White Sulphur Springs High School 1958 Certificate - Bookkeeping, Central Virginia Community College,1983 Experience:
(1974-Present)
Babcock & Wilcox, Accountability Specialist Lynchburg Research Center, Lynchburg, Virginia Mr. Long, as tne Accountability Specialist, is responsible to the Manager of Safety and Licensing for the accurate accounting of all Special Nuclear, Source, and Byproduct material at the LRC. He is responsible for recording all transfers of SNM that are made within the LRC and for preparing the reports and records of off site transfers. He prepares all NRC/ DOE 741 Transaction Forms.
He is responsible for the timely completion of inventories of licensed material.
He initiates the paper work required for all shipments of licensed material.
In addition to his normal duties he is a Document Custodian.
In this capacity, he is responsible for the safe storage of all classified DOE and D00 documents at the LRC. He is also an authorized classifier and an authorized courier of classified O
metertei-(1970-1974) Babcock & Wilcox, Shipping & Receiving Clerk Lynchburg Research Center, Lynchburg, Virginia Mr. Long was responsible for the shipment and receipt of all materials at the LRC. This assignment included the processing of all the necessary forms and documents used for shipping and receiving licensed materials as well as the many items that are required for operation of a research and development laboratory.
(1967-1970) Babcock & Wilcox, Technician Lynchburg Research Center, Lynchburg, Virginia Mr. Long was a technician in the Plutonium Development Laboratory during this period. He performed chemical operations utilizing uranium and plutonium materials and was responsible for the accountability of SNM materials into and out of his area.
Professional Affiliations:
License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
O Revision No.
5 Page 11-12 Babcock &Wilcox a McDermott company
rn Institute of. Nuclear Materials Management (Senior Member)
V Nuclear Materials Control Committee, B&W (Secretary)
American Nuclear Society, Virginia Chapter (Member) 11.2.6 License Administrator - Arne F. Olsen Facility Supervisor
- Arne F. Olsen Education:
AAS - Nuclear Technology, Central Virginia Community College,1978 Experience:
(1972-Present) Babcock & Wilcox, Senior License Administrator and Facility Supervisor, Lynchburg Research Center, Lynchburg, Virginia Mr. Olsen is responsible for preparing, amending, and administering the licenses that the LRC possesses with the NRC and the Common-wealth of Virginia. He acts as the primary liaison between the LRC and the NRC and other federal, state, and local agencies regarding nuclear matters. He coordinates the visits made by the NRC's Office of Inspection and Enforcement, and coordinates the LRC's compliance with NRC and state regulations and the licenses. He is the coordinator of the Safety Review Connittee and is Chairman of the Safety Audit Subcommittee, and represents LRC management on O
both. Mr. Olsen is the Facility Supervisor and as such is responsible to the Manager, Lynchburg Technical Operations for the safety of all operations at the LRC.
Mr. Olsen is the Alternate LRC Security Officer, Alternate Emergency Officer and an internal auditor.
(1968-1972) Babcock & Wilcox, Health Physics Technologist, Lynchburg Research Center, Lynchburg, Virginia In this capacity, Mr. Olsen was responsible to the site Health Physicist (Supervisor, Health and Safety) for the implementation of the Health Physics Program in the Plutonium Development Laboratory.
This responsibility included the implementation of the smearing, survey, air sampling, environmental sampling, and waste disposal i
programs.
(1964-1968)
Babcock & Wilcox, Technician and Shift Leader, Babcock & Wilcox Test Reactor, Lynchburg Research Center, Lynchburg, Virginia License No SNM-778 Docket No.70-824 Date May, 1987 Amendment No.
0 Revision No.
5 Page 11-13 Babcock &Wilcox a McDermott company
k]/
Mr. Olsen possessed a Senior Reactor Operator's License for the
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BAWTR. He was in charge on one of four shifts of reactor operators charged with the proper operation and maintenance of the BAWTR. He supervised the loading and unloading of fuel and experiments in the reactor and kept all required records of operations and maintenance performed on his shift.
(1960-1964)
U. S. Navy, Reactor Plant Electrical Supervisor, USS Enterprise CVA(N)-65 Mr. Olsen was an Electrician, First Class and was responsible for the proper operation and maintenance of all electrical equipment serving one of the reactor plants aboard the Enterprise.
Professional Affiliation:
Health Physics. Society (Member)
Site Environmental Committee, B&W (Member) 11.2.7 Nuclear Criticality Safety Officer - Francis M. Alcorn Education:
B.S.
- Nuclear Engineering, North Carolina State College,1957 M.B.A - Business Administration, Lynchburg College,1974
- Graduate study in Nuclear Engineering, University of q'u Virginia Experience:
(1971-Present)
Babcock & Wilcox, Supervisor, Nuclear Criticality Safety Group, Lynchburg Research Center, Lynchburg, Virginia This group is the Company's central organization which provides guidance, develops and validates the analytical methods needed for criticality evaluations, does criticality calculations, performs nuclear safety audits, and gives assistance to the I
various divisions of the Company and the Company's customers in l
matters related to nuclear criticality safety.
In addition to his responsibility as supervisor of this group, he is the Nuclear
[
Safety Officer for the Lynchburg Research Center.
(1969-1971)
Babcock & Wilcox, Criticality Specialist, Nuclear Safety Engineer, Lynchburg Research Center, Lynchburg, Virginia License No SNM-778 Docket No.70-824 Date May, 1987 llO I Amendment No.
O Revision No.
5 Page 11-14 l
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11.3.2 Technical Procedures -_ Technical procedures provide detailed techni-C cal standards and instructions for performing specific tasks.
Pur-suant to this license application, they are not intended for use by operations personnel and are not distributed in the same manner as A0P's. Neither are they necessarily approved by the Safety Review Commi ttee.
Technical procedures for the Health and Safety Group and the Nuclear Criticality Safety Group are reviewed and approved by the Senior Health Physics Engineer and the Nuclear Criticality Safety Officer, respectively, or by their designated alternates. The distribution list for each procedure is specified in the procedure.
11.4 TRAINING 11.4.1 General Radiation Protection Training The site provides three training programs covering the nature, use l
and control of radiation, and radioactivity. These courses are presented to ensure that all site personnel receive training appropriate to their activities and to fulfill obligations under the NRC license to provide such training.
The courses consist of a series of lectures intended to present the o
proper background and technical base to allow workers to understand V
the principles of radiation safety. The Supervisor, Health and Safety administers the course and, in general, teaches each course.
Where practical, basic general procedures and federal regulations are included and discussed. Training aids, such as motion pictures and self-study materials, are used as appropriate.
Program 1 is intended for site workers and non-site workers who will be authorized access to the restricted area. Program 2 is intended for site and non-site workers who may enter the restricted and controlled areas but who will not be permitted to work with licensed material without supervision. Program 3 is intended for authorized users (those who will be authorized to work with licensed material and to supervise such work).
Training in area operating procedures and special area procedures is the responsibility of the Area Supervisor. This training should ne accompanied with appropriate formal and on-the-job training as the job requirements dictate.
License No SNM 778 Docket No.70-824 Date May, 1987 Amendment No.
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(-.)
FIGURE 11-1
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NNFD RESEARCH LABORATORY ORGANIZATION NAVAL NUCLEAR FUEL DIVISION R. E. TETRAULT VICE PRESIDENT I
EMPLOYEE COMMUNITY REGULATORY RELATIONS J. A. EANES MANAGER FACILITY SAFETY REVIEW SUPERVISOR A. F. OLSEN COMMITTEE SAFETY & LICENSING R. L. BENNETT MANAGER
,r' L)
NUCLEAR LICENSE HEALTH & SAFETY CRITICALITY ACCOUNTABILIT ADMINISTRATOR SAFET'l SPECIALIST G. S. HOOVLER OFFICER A. F. OLSEN SUPERVISOR F. M. ALCORN K. D. LONG SENIOR INDUSTRIAL HEALTH PHYSICS SAFETY ENGINEER OFFICER S. W. SCHILTHELM R. R. SPRADLIN HEALTH PHYSICS GROUP i
I AREA AREA SUPERVISOR SUPERVISOR May, 1987 License No SNM.778 Docket No.70-824 Date O
5 11-21 i
i Amendment No.
Revision No.
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