ML20154M160
| ML20154M160 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 02/25/1986 |
| From: | Olsen A BABCOCK & WILCOX CO. |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 26516, NUDOCS 8603130342 | |
| Download: ML20154M160 (118) | |
Text
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'?d-JW RET. URN IO.' 39A-55 PE g,, e g Research & Development Division Babcock & Wilcox Lynchbur9 Research Center P. O. Box 11165 Lynchburg, Virginia 24506 1165 (804) 522-6000
_.EQruary 25, 1986 Uranium Process Licensing Section E
uranium Fuel Licensing Branch aarg e
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g US Nuclear Regulatory Commission pEB
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27' N 6 m~l 3 Washington, DC 20555 g
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Subject:
License Amendment g
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Reference:
License SNM-778, Docket 70-824 o
b Gentlemen:
The Lynchburg Research Center requests that the reference license be amended to reflect a change in its organization. These changes are shown on the attached replacement pages for the license application and the renewal application.
This reorganization affects the line organization in the following manner. The position of Director, Lynchburg Research Center shall be replaced with the position of Manager, Lynchburg Technical Operations.
This new position, as did its predecessor, will report to the Vice President, Research and Developc.ent Division. This change is being made to have the position titles at LRC agree with the similar position at our sister research center in Alliance, Ohio.
One new position, Manager, Special Projects / Decommissioning, reports to the Vice President. The Manager, Decommissioning will continue to functionally report to the Manager, Lynchburg Technical Operations, but will report administratively to this new position.
2 The Department Managers -- i.e., Purchasing, Accounting bnd AdrEEnistb-tive Services, Facilities, and Quality Assurance -- willgfAport" 3
functionallytotheManager,LynchburgTechnicalOperationsandMdminy, istratively to their respective Division managers.
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No change is being made in the safety organization except the tige change from Director to Manager, Lynchburg Technical Operations."
One additional change is in the experience requirement for the Super-visor, Health and Safety. Presently it is required that a candidate for this position have five years experience.
I would like this changed to four years to conforn with the recommendations for the Radiation Safety Officer found in the proposed Regulatory Guide dated April 1982, Division 8. Task OP-722-4, entitled Qualifications for the Radiation Safety Officer in a Large-Scale Non-Fuel-Cycle Radionuclide Program.
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License Amendment - License SNM-778, Docket 70-824 s
February 25, 1986 Page 2 The management at the Lynchburg Research Center and the Vice President, Research and Development Division are eager to implement these changes and your early attention to this matter will be greatly appreciated.
A check for $150.00 is attached to cover the application fee for.this
. amendment.
i Very truly yours, l
...BABC0CK'A WILC0X
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- Arne F. Olsen
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U DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 20 AMENDMENT 10 DESCRIPTION OF CHANGES Page Section Change 2-1 2.1 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations" in two pl aces.
2-2 2.2.2 The title of " Director" has bcan replaced with
" Manager, Lynchburg Technical Operations" in two places.
2-3 2.2.4 In line 3, the term "four" replaces the "five."
The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations" in one place.
/T 2-4 No change.
V 2-5 No change.
2-6 2.2.7 The title of " Director" has beui replaced with
" Manager, Lynchburg Technical Operations" in one place.
2-7 No change.
2-8 New Figure 2-1.
2-9 New Figure 2-2 4-5 4.4 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations" in one place.
4-6 4.4 Same as above, in one place.
4-21 4.5 Same as above, in one place.
4-32 4.5.3.1.3 Same as above, in one place.
4-41 4.5.12 Sane as above, in one place.
A-6 A.5.1 Same as above, in one place.
()
A-10 A.6.1.1 Sane as above, in one place.
la Saneasabove',inonehiaEe.
A-11 A.6.3 Same as above in one e.
A.6.4.1 I
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BAW-381 DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 20 AMEN 0 MENT 10 DESCRIPTION OF CHANGES Page Section Change A-12 A.7.1 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations" in two places.
A-13 A.7.2 Sane as above, in on? place.
A.7.4 Same as above, in two places.
A-13a A.7.5 Sane as above, in one place.
A-18 A.9.2 Same as above, in one place.
A-19 A.9.2.2 Same as above, in one place.
A-32 A.9.5.1 Sane as above, in two places.
O-C 4-1 4.1 Same as above, in two places.
4.2 Same as above, in one place.
4.2.1.1 Sane as above, in three places.
C 4-2 4.2.1.2 Same as above, in one place.
4.2.2.1 Sane as above, in one place.
4.2.2.2 Same as above, in one place.
~C 4-3 4.2.2.3 Same as above, in one place.
4.2.2.4 Same as above, in one place.
4.2.2.6 Same as above, in one place.
C 4-3a No change.
C 4-8 New Figure 4-1.
C 4-9 New Figure 4-2.
C 5-10 5.3.1.3 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations" in one place.
C 5-11 5.3.1.3 Same as above, in one place.
5.3.1.4 Same as above, in one place.
C 5-14 5.3.2.1 Sane as above, in one place.
C 5-15 5.3.9. 2 Sane as above, in one place.
BAW-381
()
DEMONSTRATION AND CONDITICNS FOR LICENSE SNM-778 REVISION 20 AMENDMENT 10 DESCRIPTION OF CHANGES Page Section Change C 5-17 5.3.2.2 The title of " Director" i.as been replaced with
" Manager, Lynchburg Technical Operations" in two places.
C 5-18 5.3.3 Same as above, in one place.
C 6-1 6.1 Same as above, in one place.
6.2.1 Same as above, in two places.
C 6-2 6.2.1 The title of "71 rector" has been replaced with
" Manager, Lynchburg Technical Operations" in one place.
C 7-1 7.2 Same as above, in three places.
C 7-2 7.2 Sane as above, in one place.
(
D-1 0.1 Same as above, in one place.
D.2 Same as above, in one place.
D-3 0.3 Same as above, in one place.
D.4 Sane as above, in two places.
E-1 E.1 Same as above, in one place.
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INSTRUCTION SHEET s.
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BAW-381 DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 20 AMENDMENT 10 Take Out Pages Replace With Pages Page Rev Date Page Rev Date 2-1 19 8/85 2-1 20 2/86 2-2 19 8/85 2-2 20 2/86 2-3 19 8/85 2-3 20 2/86 2-4 19 8/85 2-4 20 2/86 2-5 19 8/85 2-5 20 2/86 2-6 19 8/85 2-6 20 2/86 2-7 19 8/85 2-7 20 2/86 2-8 19 8/85 2-8 20 2/86 2-9 19 8/85 2-9 20 2/86 4-5 2
10/79 4-5 20 2/86 4-6 3
11/79 4-6 20 2/86 4-21 14 7/81 4-21 20 2/86 4-22 14 7/81 4-22 20 7/81 4-31 1
9/79 4-31 1
9/79 4-32 14 7/81 4-32 20 2/86 4-41 14 7/81 4-41 20 2/86 4-42 14 7/81 4-42 14 7/81 A-5 16 6/83 A-5 16 6/83 A-6 19 8/85 A-6 20 2/86 A-9 19 8/85 A-9 19 8/85 A-10 3
11/79 A-10 20 2/86 A-11 3
11/79 A-11 20 2/86 A-12 2
10/79 A-12 20 2/86 A-13 2
10/79 A-13 20 2/86 A-13a 3
11/79 A-13a 20 2/86 A-17 2
10/79 A-17 2
10/79 A-18 3
11/79 A-18 20 2/86
9 6
INSTRUCTION SHEET
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BAW-381 DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 20 AMEN 0 MENT 10 Take Out Pages Replace With Pages Page Rev Date Page Rev Date A-19 3
11/79 A-19 20 2/86 A-20 2
10/79 A-20 2
10/79 A-31 3
11/79 A-31 3
11/79 A-32 2
10/79 A-32 20 2/86 C 4-1 17 10/83 C 4-1 20 2/86 C 4-2 17 10/83 C 4-2 20 2/86 C 4-3 17 10/83 C 4-3 20 2/86 C 4-4 17 10/83 C 4-3a 20 2/86
(~'S C 4-4 17 10/83 V
C 4-7 17 10/83 C 4-7 17 10/83 C 4-8 17 10/83 C 4-8 20 2/86 C 4-9 17 10/83' C 4-9 20 2/86 C 4-10 17 10/83 C 4-10 17 10/83 C 5-9 17 10/83 C 5-9 17 10/83 C 5-10 17 10/83 C 5-10 20 2/86 C 5-11 17 10/83 C 5-11 20 2/86 C 5-12 17 10/83 C 5-12 17 10/83 C 5-13 17 10/83 C 5-13 17 10/83 C 5-14 17 10/83 C 5-14 20 2/86 C 5-15 17 10/83 C 5-15 20 2/86 C 5-16 17 10/83 C 5-16 17 10/83 C 5-17 17 10/83 C 5-17 20 2/86 C 5-18 17 10/83 C 5-18 20 2/86 C 6-1 17 10/83 C 6-1 20 2/86 C 6-2 17 10/83 C 6-2 20 2/86 C 7-1 17 10/83 C 7-1 20 2/86 x
C 7-2 17 10/83 C 7-2 20 2/86
l INSTRUCTION SHEET BAW-381 4
DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 20 AMENDMENT 10 4
i Take Out Pages Replace With Pages Page Rev Date Page Rev Date D-1 1
9/79 D-1 20 2/86
}
D-2 1
9/79 D-2 1
9/79 D-3 1
9/79 D-3 20 2/86 i
E-1 12/78 E-1 20 2/86 E-2 12/78 E-2 12/78 O
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O 2.
ORGANIZATION AND SUPPORT SERVICES 2.1 ORGANIZATION The Manager, Lynchburg Technical Operations shall be responsible for all operations and personnel at the Lynchburg Research Center that involves the use and control of NRC licensed material.
The Laboratory Managers shall report to the Manager, Lynchburg Technical Operations and shall be responsible for operations that fall within the areas of expertise encompassed by the sections under their control.
Research and development performed at the Lynchburg Research Center may result in projects being performed by sections of different laboratories in the same building. The position of Facility Supervisor has been estab-lished to ensure the uniformity of safety within each facility.
He shall advise the Laboratory and Section Managers in the safety aspects and the-d control of licensed material, and coordinate the safety program within each facility. The Facility Supervisor utilizes the expertise of the Supervisor, Health and Safety, the Accountability Specialist, Nuclear Safety Officer,
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and the Industrial Safety Officer to ensure the safety of operations per-formed at the Lynchburg Research Center.
i 2.2 POSITION RE0VIREMENTS The minimum requirements for key positions in the organization are as follows.
2.2.1 Laboratory Manager They shall be appointed in accordance with Company policy.
License No SNM 778 Docket No.70-824 Date February 1986 OQ Amendment No. 10 Revision No.
20 Page 2-1 Babcock & Wilcox a McDermott company
O 2.2.2 Facility Supervisor The Facility Supervisor must demonstrate to Company management, pro-ficiency in the application of good principles of radiation protection, industrial safety, and nuclear criticality safety as related to the activities at the Lynchburg Research Center.
He shell have a minimum of three years of related experience and either hold a degree in his related work or have five years of experience in the use of handling of licensed material.
The Facility Supervisor shall be appointed by the Manager Lynchburg l
Technical Operations.
Me shall be responsible to the Manager, Lynchburg l
Technical Operations for the safe conduct of all operations at the Lynchburg l
Research Center and for ensuring that these operatioris are conducted in compliance with all license conditions.
O The Facility Supervisor shall become familiar with all license con-ditions 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 In addition to the general responsibilities stated above, the Facility Supervisor shall be responsible for:
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No.
20 Page 2 -2 Babcock & Wilcox a McDermott company
k (3
(J 1.
Reviewing and approving all Area Operating Procedures.
2.
Terminating any operation he deems contrary to license conditions, area operating procedures, or general safety conditions.
3.
Designating an alternate to assume his responsibilities in the event of his absence.
2.2.3
. Manager, Safety and Licensing The Manager, Safety and Licensing shall have a BS degree in a technical field and four years experience in the nuclear field.
The Super-visor, Health and Safety, License Administrator, and the Accountability Specialist report to him.
2.2.4 Supervisor, Health and Safety n
v The Supervisor, Health and Safety shall have a BS degree in a technical field and professional experience in supervising a radiation protection program. He shall have at least four years experience and I
demonstrate proficiency in the application of radiation safety principles and be knowledgeable in fields related to radiation protection.
The Supervisor, Health and Safety reports to the Manager, Safety and Licensing.
He has direct access to the Manager, Lynchburg Technical Operations in matters concerning Health and Safety. The Health Physics Group and the Industrial Safety Officer report to the Supervisor, Health and Safety.
License No SNM-778 Docket No.70-824 Date February 1986 O
Amendment No. 10 Revision No.
20 Page 2-3 G
Babcosit &Wilcox a McDermott company
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O 2.2.5 Health Physics Engineer The Health Physics Engineer shall have a 'BS degree, with course work in health physics.
He shall report to the Supervisor, Health and Safety and is responsible for the activities of the health physics staff at the LRC, which include:
1.
Performing area surveys 2.
Administering the air survey program 3.
Administering the respiratory protection program 4
Administering the bioassay program 5.
Leak testing radioactive sources 6.
Supervising shipping and receiving of radioactive 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 required by regulations or procedures within the Health Physics Group.
- 12. Distributing and processing personnel monitoring equipment, notifying supervisors of exposures that exceed permissible limits, and recommending appropriate restrictions.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page 2-4 Babcock & Wilcox a McDermott company
1 4
A 2.2.6 Industrial Safety Officer The Industrial Safety Officer shall have at least one year's experi-ence in radiation and industrial safety.
He shall be familiar with the codes and requirements of the Occupational Safety and Health Act of 1970 and the National Fire Protecticn Association. The Industrial Safety Officer reports to the Supervisor, Health and Safety.
The responsibilities of this position are:
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 pro-tection, control, and extinguishing equipment 5.
Providing training for the LRC fire and rescue team and O
all site support agencies 6.
Inspecting all areas of the LRC 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 minimum practicable levels, of flammable materials e.
Proper use and maintenance of electrical equipment 7.
Working with supervisors to formulate safety rules and eliminate hazards 8.
Investigating all accidents 9.
Keeping management informed concerning safety activities License No SNM 773 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page 2-5 Babcock &Wilcox a McDermott company a
O
- 10. Arranging for safety films, lectures, and other training in industrial safety, as required 2.2.7 Nuclear Safety Officer The Nuclear Safety Officer must be technically trained and have a BS degree in science or engineering with experience as a responsible reactor engineer or nuclear physicist.
He must have been engaged for one year in an activity that would develop an understanding of the nuclear criticality problems as they relate to the LRC.
It shall be this Officer's responsibility to ensure that no operation at the LRC can lead to the inadvertent assembly of a critical mass.
To help assure this, he will review all new Area Operating Procedures as well as changes to these procedures, observe operations, institute educa-tional programs if and when he cleems them necessary, and carry out confirm-ing nuclear criticality safety calculations.
The Nuclear Safety Officea does not in any way relieve the Facility Supervisor of his responsibility f or ensuring safe operations at the LRC, nor will it eliminate the necessity for the reviews by the Safety Review Committee.
Once a month, the Nuclear Safety Officer will inspect all LRC opera-tions where special nuclear material is beine processed.
Other areas shall be inspected less frequently; however, all jreas shall be inspected at least twice a year.
He shall consider area olierations when scheduling these in-spections and shall, if necessary, schedule his inspection at more frequent intervals.
His consideration should include inspection of rew operations, an audit of nuclear safety rer.ords, a check for area posting and a review of current practices.
A written report is to be filed with the Manager, Lynchburg Technical Operations quarte'ly with a copy to the License Administrator.
I License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page 2-6 Babcock & Wilcox a McDermott company
4
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Prior to submission of the report, he shall discuss its contents with the Facility Supervisor. The report shall be brief, concerning itself with inspections made during the quarter, and with the nuclear safety activity of the quarter.
The following information is to be included:
1.
Areas visited 2.
Operations observed 3.
Unsafe practices or situations noted 4
Nuclear safety activity of the quarter 5.
Recommendations 2.2.8 Accountability Specialist The Accountability Specialist shall have at least a high school education or equivalent and at least one year's experience in the nuclear fuel business. He is responsible for the maintenance and retention of SNM accountabilty records, preparing and transmitting required reports generated from these records.
The Accountability Specialist reports to the Manager, Safety and Licensing.
2.2.9 License Administrator The License Administrator shall have a BS degree in science or engine: ring and three year's experience in nuclear technology or an AS degree in science or nuclear technology with five year's experience in nuclear technology.
He is responsible for administering the license. He is the primary liaison with the U.S. Nuclear Regulatory Commission and other federal, state, and local agencies regarding nuclear matters.
He is the coordinator of the Safety Review Committee and the Safety Audit Subcommittee and represents LRC management on both.
The License Administrator reports to the Manager, Safety and Licensing.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page 2-7 Babcock &WHcox a McDermott company
FIGURE 2-1.
LRC LINE ORGANIZATION RESEARCH AND DEVELOPMENT DIVISION VICS PRESIDENT LYNCH 8URG RESEARCH CENTER SPECI AL PROJECTS /
LYNCH 8URG TECHNICAL OPER ATIONS DECOMMISSIONING MANAGER MANAGER DECOMMIS;; TONING
~~~~~~~~~
PURCHASING PURCHASING j
R&DD LRC MANAGER MANAGER SAFETY AND ACCOUNTING LICENSING CONTROLLER AND R&DD ADMINISTRATIVE MANAGER SERVICES LRC MANAGER SYSTEMS FACILITIES DEVELONWENT AND FACILITIES LABORATORY OUALITY ASSURANCE LRC MANAGER R&DD MANAGER MANAGER l
QUALITY OUALITY MATERIALS ASSURANCE ASSURANCE ENGINEERING R&DD LRC LABORATORY MANAGER ADMINISTRATOR MANAGER SCIENTIST
---INDICATES FUNCTIONAL REPORTING License No SNM 778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No. 20 Pege 2-8 Babcock & Wilcox a McDermOtt company
l t
FIGURE 2-2.
LRC SAFETY ORGANIZATION LYNCHOURG RESEARCH CENTER LYNCHOURG TECHNICAL OPERATIONS MANAGER SAFETY REVIEW COMMITTEE I
I l
PACILITY SUPERVISOR SAFETY AalO UCENSING l
NUCLEAR SAFETY l
OFFICER MA88AGER I
O i
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1 LICENSING HEALTH ANO SAFETY ACCOUNTAtluTY ADMINISTRATOR SUPERVISOR SPECIALIST HE ALTH PHYSSCS IMOUSTRfAL STAPP SAPETV
---INOICATES FUNCTIONAL MEPORTING License No SNM 778 Docket No. 70 824 Date Feb'uary 1986 Amendment No.
10 Revision No.
20 Page 2-9 Babcock &Wilcox a McDermott company
4.3 SAFETY REVIEW COMMITTEE The responsibilities and functions of the Safety Review Committee are given in Appendix D of this document.
4.4 (A.9.5) NUCLEAR-SAFETY The ultimate responsibility for nuclear safety rests with the Manager, Lynchburg Technical Operations. However, first-line responsibility I
is with the facility supervisor supported by the nuclear safety officer.
It is the facility supervisor's responsibility to see that personnel follow all nuclear safety procedures and to question any doubtful procedure.
The nuclear safety officer is generally responsible for establishing nuclear safety limits and nuclear safety considerations in operating proce-dure, processes, and the like.
His duties are shown more specifically in the following statement.
The position of nuclear safety officer has been established at the Lynchburg Research Center. It will be this officer's responsibility to ensure, as far as possible, that no operations in the Lynchburg Research Center can lead to the inadvertent assembly of a critical mass.
To this end he will review all ns.w procedures which involve the handling of special nuclear materials as well as changes in old procedures, observe operations, inaugurate educational programs if and when he deems them necessary, and carry out confirming criticality calculations.
This appointment does not in any way relieve the facility supervisor of his responsibilities for ensuring safety operations in his areas, nor will it eliminate the necessity for the reviews by the Safety Review Committee required by this license.
Once a month the nuclear safety officer or qualified person designated by him will inspect all LRC operations where special nuclear materials are being processed.
Other areas shall be inspected less fre-quently; however, all areas shall be inspected at least twice a year.
He License No SNM 778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No. 20 Page 4-5 Babcock &Wilcox a McDermott company
shall consider area operations when scheduling these inspections and shall, if necessary, schedule his inspection at more frequent intervals. His con-sideration should include inspection of new facilities, inspection of hazardous non-routine operations, an audit of nuclear safety records, a check for area posting and a review of current practices.
A written report is to be filed with the Maqager, Lynchburg Technical Operations quarterly with a copy to the LRC license administrator.
prior to submission of the resport, he shall discuss any findings with the facility supervisor.
The report shall be brief, concerning itself with inspections made during the quarter and with the nuclear safety activity of the quarter.
The following information is included:
o Areas visited o
Operations observed o
Unsafe practices or situations noted o
Nuclear safety activity of the quarter (brief summary) o Recomendations o
Resolution of previous recommendations 4.4.2(A.9.5.5) Nuclear Isolation Special nuclear material at the LRC is isolated from all other special nuclear material for nuclear criticality safety purposes if any of the three conditions (or equivalent) listed in A.9.5.5 are met.
These three isolation criteria are accepted industrial practice for maintaining nuclear criticality safety.
It is recognized that 12 inches of high density concrete may not be adequate as isolation between two large parallel slabs of SNM; this does not describe any SNM configuration at the LRC and will not be permitted without additional evaluation and NRC approval.
4.4.3(A.9.5.6) Building A Note:
The critical experiment facility is nuclearly isolated from the units specified in this license.
A minimum of 5 feet of high density concrete and/or water separates them from these units.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Hevision No.
20 Page 4-6 Babcock & Wilcox a McDermott company
i OQ 4.5 RADIATION-SAFETY The responsibility for overall safety at the LRC is vested in the facility supervisor.
The Supervisor of Health and Safety is available to the facility supervisor for expertise in the field of radiation safety. The Supervisor of Health and Safety reports tc the Manager, Safety & Licensing, with direct access to the Manager, Lynchburg Technical Operations when l
necessary. The Health and Safety group is comprised of the health physics and industrial safety staff.
4.5.1 Responsibilities The health physics staff is presently constituted as follows:
o A certified health physicist o
A health physics engineer o
Three health physics technicians The health physics staff is responsible for:
1.
General surveiliance of all radiation activities.
2.
Distributing and processing personnel monitoring equip-O" ment, maintaining individual exposure records, notifying supervisors of exposures greater than the permissible levels, and recommending appropriate restrictions.
3.
Leak testing radioactive sources.
4 Supervising shipping and receiving of radioactive material.
5.
Supervising and coordinating the waste disposal program.
6.
Assisting in personnel, equipment and facility decontamination.
7.
Radiation safety training.
8 Providing expertise in all aspects of radiation protection.
9.
Generating or acquiring, maintaining and appropriately distri-buting all records and reports required by regulations or pro-cedures that pertain to the staff's scope of interest.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No.
20 Page 4-21 Babcock &Wilcox a McDermott company
10.
Implementing the LRC's respiratory protection program.
4.5.2 General Surveillance General surveillance includes smear surveying, air sampling, water sampling, environmental sampling, effluent air monitoring, effluent liquid monitoring, and direct radiation surveys.
4.5.2.1 Smear Surveying - Smear surveying is performed in all areas which, in the judgment of the health physicist, have a potential for surface contamination.
The frequency of smear sampling will vary depending on the potential for contamination, the previous experience with the area, and the need for keeping the area free of contamination.
Schedules and areas listed in this section for discussion are subject to change, f
4.5.2.1.1 Smear samples are taken with small absorbent, filter papers. The smear pr.rer is moved across an area 2
of approximately 100 cm using about 5 pound pressure.
The smear may be counted with a portable gas flow proportional counter which is capable of detecting alpha or beta activity. Appropriate factors are applied to obtain results in disintegrations / minute.
Large area smears are taken of the reactor areas and main hallway in Building A, the hot cell operations areas, the change room and main hallways in Building B, and the laboratory areas of Building C.
Records of smear results and actions taken in response to these results are retained by the health physics group.
I 4.5.2.2 Air Sampling and Monitoring
- 4. 5.2. 2.1 Air Monitoring Program - Air monitoring can be separated I
into two types: fixed continuously indicating and portable continuously indicating. The type or types to be used are at the discretion of health physics personnel.
1.
Fixed Continuously Indicating This type of air monitor, with a preset alarm level, is normally placed in each radioactive material handling area where, in the opinion of the health physicist, there is a potential for airborno activity.
4-22 License No.
SNM-778, Docket No.70-824 Date July, 1981 Page Amendment No.
Revision No. 14 Elmhenelt n Wilenn
TLD attached to the ID badge does not have to be worn in close proximity with the film badge, however, it must be carried on the person of the worker.
Personnel will wear film badge or TLD badge when they visit or work at another installation (including the CNFP and the NNFD) for periods under 30 days, where they could be exposed to radiation.
If visiting or working exceeds 30 days or extends over the first of the month, personnel must contact health physics for additional instruction concerning the changing of the film badge or TLD badge.
4.5.3.1.3 Types of Monitors - Film badges monitor external exposure to gamma, beta and in some cases neutron radiations. These badges are pro-cessed (read, recorded, and reported) by a commercial concern every month.
Beta and gamma range is from 15 to 500,000 millirems.
TLD's measure gamma exposure; the range is from 10 millirads to 10,000 Rads. They will be read at yearly intervals or less.
Indirect-reading dosimeters measure external exposure to gamma radiation (range is 0 to 200 millirads) and are read and recorded daily.
If a TLD is used in place of dosimeters, it will be read on a frequency
,r y determined by the health physicist.
Persons handling radioactive sources shall wear finger rings also, when deemed advisable by health physics; these rings monitor gamma and beta exposure to the hands (range is from 50 millirads to greater than 10,000 Rads).
Direct-reading packet dosimeters will be worn also, when deemed advisable by health *Sysics. These dosimeters measure accumulated expo-sure when personnel are working in variable radiation fields. They mea-sure external exposure to gamma radiation from 0 to 200 millirada, or from 0 to 500 millirads.
All new employees and all new persons monitored as employees must be initially admitted using Form LRC-129 and must receive proper indoctrination.
- Ihe determination and estimation of 100 millirems exposure will be made He will take into a,ccount the job assignment,
__by the health physicist.
past exposure records, etc., in his decision.
4-31 License No.
SNM-778 Docket No.70-824 Date September 1979 page
\\mendment No.
Revision No.
1 Babcock s.Wilcox
The limits of exposure (see 10 CFR, Part 20) are as follows:
1.
Whole body, 1.25 Rem / calendar quarter.
2.
Skin, 7.5 Rem / calendar quarter.
3.
Hands, forearms, feet and ankles,18-3/4 Rem / calendar quarter.
4.
Whole body, 300 mrem / week; the long-term exposure is con-trolled by the supervisor.
During extreme emergencies, section and laboratory managers are
~
authorized to e*,posure their personnel to 3.0 Rem / calendar quarter of whole body radiation.
At other times, the Manager, Lynchburg Technical Operations l
may authorize whole body exposure of 3.0 Rem / calendar quarter.
4.5.3.2 Personnel Dosimetry for Non-LRC Personnel - No visitor may receive a radiation exposure exceeding 10 millirems in one week unless he is working under a radiation work permit * (Fig. 4-6).
Certain non-LRC employees may be monitored and badged as employees; currently these include selected personnel assigned to the Facilities Department.
If there is a question, health physics will decide whether a person will be monitored as a visitor or as an LRC employee. Non-LRC employees will be badged and monitored to comply with the following sections.
4.5.3.2.1 Category-A Visitors - A person visiting the LRC for one day or less and not covered by any of the following categories will sign in and sign out with the receptionist upon each visit.
The receptionist will issue one film badge and one pocket dosimeter or two TLD's to each Category-A visitor.
The visitor will leave the monitoring equipment with the receptionist upon Signing out.
- This statement means that visitors have access to nonradiation areas at the site under the suparvision of the LRC person they are visiting.
If their visit takes them into a radiation area, the LRC person being visited must make a stay-time calculation of the dose.
The dose estimate must be less than 25 mrem / week, or the visitor must visit under a radiation work permit.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No. 20 Page 4-32 Babcock & Wilcox a McDermott company
OV 4.5.11 Respiratory Protection Program The health physics group is responsible for the implementation of the respiratory protection program.
The primary objective of a respiratory protection program is to limit the inhalation of airborne radioactive or other hazardous materials.
This objective is normally accomplished by the application of engineering controls, including the use of process, containment, and ventilation equip-ment. When such controls are not feasible or cannot be applied, respiratory protective devices must be used.
The program will include the following:
1.
Procedures governing the selection, fitting, and use of respirators.
2.
Procedure for training of users of respiratory protection.
3.
Procedure for respiratory decontamination, maintenance, and storage.
4 Medical surveillance for users of respiratory protection.
U 5.
Regular inspection and evaluation of the program to deter-mine its continued ef fectiveness.
4.5.12 Audit The health and safety supervisor or his designee per orms audits monthly. A written report is to be filed with the Manager, Lynchburg Technical Operat'ons quarterly with a copy to the license administrator.
The audits are co1di cted in accordance with a written plan.
An example of the contents of an audit plan is:
1.
Each month the following items are audited:
a.
Records of shipments and receipts of radioactive material are reviewed with completeness.
b.
LRC-229 " Facilities Work Order Forms" are reviewed to en-sure that appropriate signatures have bacn entered.
c.
Selected work areas are inspected to ensure proper posting, labeling and storage of radioactive material, and safety practices and procedures are being followed.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page 4-41 Babcock &Wilcox
}
a McDermott company I
2.
During the year the following ie ms are covered:
a.
An evaluation of the respiratory protection program.
b.
An evaluation of employee whole body exposure.
c.
An evaluation of environmental releases, d.
An evaluation of bioassay results.
e.
An evalustion of airborne radioactivity.
f.
An evaluation of environmental monitoring, g.
An audit of health physics records.
4.5.13 ALARA The management at the Lynchburg Research Center is committed to the philosophy of maintaining radiation exposure to levels that are as low as reasonably achievable. This commitment is made known to all employees within the first month after they report to work. Employees who's work assignment involve exposure to licensed material are provided with the initial training and annual retraining that reinforces this commitment and provides the employee with the fundamental knowledge necessary to assist in implementing the ALARA principle.
The implementation of the radiation protection program is the responsibility of the health and safety supervisor. The qualifications of this position are presented in Section 2.
These qualificattons ensure that the individual holding the position is eminently capable of dealing l
with potential problems encountered at the LRC. The supervisor has the authority to suspen.1 operations until correctiva action is taken if he observes practices which could result in a definite hazard.
The health and safety supervisor is responsible for reviewing personnel exposures to assure that ALARA principles are being applied.
Table 4-8 is a summary of whole body radiation exposure for the calendar year 1977 and 1978.
It can be seen by this data that there is an increase in exposure dose in 1978 as compared with 1977. This is an example of a trend in exposures that resulted from an increase in the icvel of work in licensed activities rather than a reduction in the application of License No.
SNM-778 Docket No.70-824 Date July. 1981 Page 4-42 Amendment No.
Revision No.
14 O
Babcock & Wilcox
O
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IMAGE EVALUATION O
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Material Physical Form Enrichment Amount 12.
Any byproduct Irradiated 50,000 Ci material structural material &
components 13.
Byproduct Any 3000 C1 each; total material with not to exceed atomic nos.
1,000,000 Ci 3 thru 83 14.
Trans-uranium Any 20 millircuries each elements 15.
Cf252 Sealed 4 milligrams sources Am +1 Sealed 30 Ci 2
16.
sources 17.
H3 Sealed 100 Ci sources
,O 18.
H3 Oxide 3 Ci o
19.
H3 Ni plated Sc 3 Ci Tritide foil License No.
SNM-778 Docket N o.70-824 Date 3"na-IW Amendment N o.
5 Revision N o.
16 Page A-5 Babcock & Wilcox
A.4 RESTRICTIONS A.4.1 Unirradiated Plutonium Research and development activities utilizing unirradiated plu-tonium shall be limited to the following operations:
1.
Research and development of analytical chemistry techniques and procedures.
2.
Preparation of irradiation and test samples.
3.
Scrap recovery.
4 Research and development of sintering process techniques.
5.
Fuel characterization.
6.
Performance of studies of the conversion of plutonium nitrate of plutonium oxide.
A.4.2 Pyrophoric SNM Research and development or processing of special nuclear material in pyrophoric form is limited to quantities not exceeding 200 grams of U-235, U-233, or plutonium.
Pyrophoric SNM is finely divided U-233, U-235, or Pu metal powders no greater than 0.044 m in diameter.
A.4.3 Plutonium-238 Research and development or processing of plutonium containing greater than 127, Pu-238 shall be performed in the hot cells.
A.4.4 Uranium Hexafluoride The LRC is restricted from processing or conducting research and development utilizing uranium hexafluoride.
A.5 ORGANIZATION AND POSITION REQUIREMENTS A.5.1 Organization The Manager, Lynchburg Technical Operations has ultimate responsi-l bility for the safety of operations and the control of activities at LRC.
He directs License No SNM-778 Docket No.
70 824 Date February 198f4 Amendment No.
10 Revision No.
20 Page A-6 Babcock & Wilcox a Mc Dermott company
i A.S.2.10 Industrial Safety Of ficer - The Industrial Safety Of ficer shall have at least one year's experience in radiation and industrial safety.
He shall be familiar with the codes and requirements of the Occupational l
Health and Safety Act of 1970 and the National Fire Protection Association.
1 l
l j
A.6 ADMINISTRATIVE CONTROL Procedures control and provide the necessary direction to coordinate and ensure the safe operation of activities at the LRC.
In addition to formal procedures, numerous routine activities are conducted in accordance with established practices developed through years of operational experience.
l l
Many of these have never been produced in written form since the basis for ensuring safe operation rests with the experienced scientist, engineer, and j
technician. Work involving the use of licensed material that is not covered l
by an approved written procedure shall be performed pursuant to a Radiation Work Permit (RWP).
RVP's shall be reviewed and updated quarterly.
l-i i
1 I
l License No SNM 778 Docket No.70-824 Date Augunt, 1985 1
Amendment No.
9 Revision No.
19 Page A-9 l
i Babcock &Wilcox a McDermott company L
The LRC procedures are defined as follows:
A.6.1 Demonstration and Conditions for License SNM-778 This document presents the procedures necessary to show compliance with the license conditions.
1.
Additions or changes to the procedures in the demonstration sections of
" Demonstration and Conditions for License SNM-778" are submitted to the LRC license administrator, who, with the concurrence of the Manager, Lynchburg Technical Operations, laboratory managers and facility super-visor, may implement these changes or additions.
Prior to implementa-tion, all changes or additions are referred to the Safety Review Committee.
A.6.2 Area Operating Procedures Area operating procedures are facility procedures for the safe handling of licensed material.
1.
Additions or changes to area operating procedures are submitted to the representative facility supervisor.
The facility super-visor forwards the submittal to the supervisor, health and safety, and nuclear safety officer for review and approval.
The health physicist and nuclear safety officer shall be independent of the operations under review.
Subsequent to these approvals he shall review and approve the addition or change.
The f acility supervisor shall consider the recommendations of the industrial safety of ficer.
2.
All area operating procedures and revisions therato shall be aporrved by the Safety Review Comnittee except:
a.
Revisions correcting spelling or typographical errors, b.
Revisions in the procedure form or format.
c.
Procedures and revisions that govern the use of equipment that does not have an effect on the use or handling of licensed material.
3.
Area operating procedures shall be followed and shall be avail-able in each operations area.
Licensa No SNM.778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No.
20 Page A-10 Babcock & Wilcox a WDermott wmpany
A)
(V 4
Area operating procedure manuals shall be issued to specified individuals.
New and revised procedures are distributed in accordance with a document control system which assures that the manuals contain only the most currently approved procedures.
The facility supervisor shall review the procedures for his facility annually to ensure that procedures are up to date and applicable.
5.
General health physics and nuclear criticality safety procedures shall be established, maintained and followed for all operations involving the processing, handling and storage of licensed material.
A.6.3 License SNM-778 Requests for changes to License SNM-778 are made to the license administrator, who, with the concurrence of the Manager, Lynchburg Technical Operations, the laboratory managers, and the facility supervisor, will forward the request to the U.S. Nuclear Regulatory Commission. Requests for license amendments will also be referred to the Safety Review Committee.
A.6.4 Safety Audits A.6.4.1 Nuclear criticality safety and radiation safety audits shall be per-formed monthly by the nuclear safety officer and the supervisor, health and safety respectively, or similarly qualified persons designated by them.
The audits shall be cor. ducted in accordance with a written plan and documented.
A written report of the audits shall be filed quarterly with the Manager, Lynchburg Technical Operations and with a copy to the license administrator including the areas inspected, findings, and status of action taken to correct previous findings.
A.6.4.2 The nuclear safety officer and the supervisor, health and safety shall have the authority to suspend operations until action is taken t - correct observed practices which could result in a definite hazard.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page A-11 Babcock & Wilcox a Mc Dermott comp.my
A.6.5 Radiation Work Permit Radiation Work Permits (RWP) shall be prepared for operations or maintenance work not covered by an area operating procedure and which in-volves entry into a system containing SNM or where a potential for release of contamination exists such that the airborne radioactivity concentration to which employees are exposed from the proposed operation or work is likely to exceed the concentration in Appendix B, Table 1, of 10 CFR 20 or the potential external radiation exposure to which employees are exposed from the proposed operation or work is likely to exceed 100 mR in one work week.
The RWPs shall specify the necessary radiation safety controls including but not limited to respiratory protection, special air sampling, and special local ventilation.
All RWPs shall be signed by representatives of the appropriate line supervision and the responsible representative of health physics prior to the start of operations except that during off-shift hours approval of the Supervisor, Health and Safety or his designee may be obtained via telephone.
A.7 SAFETY REVIEW COMMITTEE A.7.1 Membership The Safety Review Comittee (SRC) shall be comprised of at least five technical members having expertise in chemistry, radiological safety, industrial safety, and nuclear engineering.
The members shall be appointed by the Manager, Lynchburg Technical Operations who shall also appoint the
}
chairman, alternate chairman, and the members who serve on the Audit Subcommittee.
The Manager, Lynchburg Technical Operations shall appoint a
}
management representative to be a committee member who shall serve as the committee coordinator.
License No SNM 778 Dock et No.
70 824 Data february 1986 Amendment No. 10 Revision No.
20 Page A-12 Babcock & Wilcox a W Detmott (ompany
l j
I A.7.2 Function i
l The SRC reports to the Manager, Lynchburg Technical Operations.
It I
l reviews and approves new projects and major changes to existing projects
]
l that utilize licensed materials.
It reviews and approves all area operating l
procedures pursuant to Section A.6.2.2.
The Safety Audit Subcommittee (SAS) shall perform audits of LRC operations to assure compliance with safety requirements.
It is the responsibility of the license administrator to act on the recommenoations of the SAS and confirm the actiores taken.
A.7.3 Frequency of Meetings The SRC shall meet at least four times annually.
The SAS shall conduct audits of the LRC at least three times annually.
A.7.4 Documentation Minutes of the SRC actions shall be submitted to the Manager, Lynchburg Technical Operations and the permanent records of the SRC shall be kept by the committee coordinator.
A report of the SAS's audits showing the items audited, findings and disposition of action taken on previous findings i
shall be sent to the SRC chairman who shall forward the report to the Manager, Lynchburg Technical Operations with comments as appropriate.
l A.7.5 Annual Report An annual report by the supervisor, health and safety shall be made to and reviewed by the SRC reviewing employee exposures and effluent release data to determine:
1.
If there are any upward trends developing in personnel exposures for identifiable categories of workers or types of operations or ef fluent releases.
2.
If exposures and releases might be lowered in accordance with the concept of as low as reasonable achievable.
3.
If equipment for effluent and exposure control is being properly used, maintained, and inspected.
License No SNM 778 Docket No. 70 824 Date February 1986 Amendment No. 10 Revision No. 20 Page A-13 Babcock & Wilcox a McDermott company
The report shall include a review of audit and inspections performed by supervisor, health and safety during the previous 12 months and review data from the following areas:
1.
Employee exposure 2.
Bioassay results 3.
In-plant airborne radioactivity 4
Environmental monitoring The SRC recommendations on the annual report shall be made to the Manager,
(
Lynchburg Technical Operations subsequent to completing its review of the report.
O License No SNM 778 Docket No.
70 824 Date february 1986 h
Amendment No.
10 Revision No.
20 Papi A-13a Babcock & Wilcox
.* Mr Dermt;tt c omp.wiy
t 4.
Pumping or pouring through a service line.
5.
Pouring into a container inside the pass-in box.
V 6.
Removing the glove-box face inside a " tent".
7.
Sending in from the pass-through tunnel between glove boxes.
Current methods for removing materials from the glove boxes include *.he following:
t i
l 1.
Bagging procedures.
l 1
2.
Pumping or pouring through service line.
3.
Transferring to a clean container inside the pass-in box.
j 4.
Removing the glove box face inside a " tent".
i 5.
Sending out into the pass-through tunnel between glove boxes.
{
The following types of cont.tiners will be used for transferring l
plutonium between glove boxes: Tygon tubing, metal tubing, metal liner, plastic bottles, metal cans, plastic bags, and others approved in accordance with the preceding paragraph.
I l
Plutonium-bearing waste material shall be stored in plastic bags in a DOT container approved for off-site shipment of radioactive material.
Plutonium not in solution or in glove boxes shall be stored in prescribed !
l storage areas in double-bagged plastic or metal containers.
Solutions shall be i
stored in the vault in vented plastic bottles. Small quantities of plutonium-
[
t bearing solutions shall be stored in unvented plastic bottles according to special procedures approved by the SRC.
4 A.8.2.5 Open-Port Clove Boxes and Fume Hoods Used for plutonium i
l or Transuranium Elements - The open-port glove box and fume hood operations j
]!
are limited as follows:
(
1.
Plutonium powders are limited to less than 50 micrograms of l
p I
2.
Plutonium metal and solutions are limited to 200 milligrams of l
(
3.
The maximum permia=1ble contamination level for the interior l
of open-port giuse boxes in 10,000 dpm/100 cm'.
j 1
)
?
I l
License No.
8106-778 Docket No.70-824 Date October 1979 Page A-17
)
ndment No.
Revision No.
2 i
1 i
I 7
i Babcock & Wilcox l
Detailed operating procedures for these boxes and hoods will be developed by operations personnel and approved by the SRC.
All boxes shall have an air velocity of at least 100 ifm through the open face.
A.9 SAFETY A.9.1 Emergency Plan Appendix C is the emergency plan for the LRC.
A.9.2 Radiation Safety the facility supervisor will approve written area operating pro-cedures encompassing radiation safety developed by the line organization.
A health physicist, appointed by the Manager, Lynchburg Technical Operations shall assist the facility supervisor in this responsibility.
A.9.2.1 Training - The radiation safety program is administered by the supervisor of health and safety.
The contents of the courses are described in Section 4.5.8.
Program I shall be presented to each new employee within 30 days of reporting to work.
personnel shall not be per-mitted to work with licensed material unsupervised until they are authorized and trained in radiation and nuclear criticality safety.
Programs !! and
!!! are presented to employees who are selected by their section manager to be designated as an authorized user of radioactive material (i.e., employees who may handle licensed material unsupervised, health physics technicians and emergency team monitors) on an as-needed basis.
Retraining of authorized users of radioactive material is performed annually.
Attendance and the identity of the instructor shall be documented.
The effectiveness of the training program shall be evaluated on the basis of a written examination and documented.
A.9.2.2 Personnel Protection - Personnel monitors (film badges, dosimeters, or other suitable devices) are provided to nurasure the radiation exposure of visitors and employees.
Personnel dosimeters issued pursuant to 10 CFR 20.202 shall be read on a monthly basis.
The use of respiratory pro-tective equipment shall be in accordance with 10 CFR 20.103.
t.icenso No SNM 778 Docket No.
70 874 Date february 19Bf Amendment No.
la Flevision No.
20 Page A-18 Babcock & Wilcox e Mc Dermott tamp.my
i l
The employee's line supervisor shall be responsible for keeping exposures below 300 millirems per week and 1250 millirems per quarter.
The supervisor of health and safety may approve weekly exposures above 300 millirems, but the quarterly limit of 1250 millirems shall not be exceeded without the approtal of the Manager, Lynchburg Technical Operations.
If an employee has received the quarterly limit and the Manager, Lynchburg Technical Operations has not authorized exceeding the limit, the employee's l
work shall be restricted to prevent further exposure for the remainder of l
the quarter.
A.9.2.3 Bio-Assay Program l
A.9.2.3.1 Uranium Bio-Assay program - Health physics shall administer the bio-assay program for uranium.
The sampling frequency shall l
comply with Tables 2 and 3 of Regulatory Guide 8.11. " Application of Bio-l l
assay for Uranium," dated June, 1974 The program shall follow Regulatory l
O
[
Guide 8.11 except as follows-1.
When an employee is not at the LRC during a period when the bioassay counting service is on site, a special counting (make-up) shall not be performed for routine exposure control monitoring.
t 2.
Bloassay samples (urinanalyses and in-vivo lung counting) shall be analyzed for plutonium and uranium if tho sample involves an I
employee working in an area where both plutonium and uranium may
[
t be present in air.
However, the health and safety supervisor may decide to analyze for Pu only if pu and U are mixed and it can be shown that analyzing for Pu would be more sensitive.
l l
I LleoneeNo SNM 778 Docket No. 70 824 Date February 1980 l
Amendment No.
10 Movision No.
20 Pese A-19 l
Babcock & Wilcox m on,m>n w w,
A.9.2.3.3 Plutonium Bio-Assay Program - llealth Physics shall administer the bio-assay program for plutonium.
All personnel who routinely work in plu-tonium handling areas shall be subject to the plutonium bio-assay program. The minimum frequency for urine sampling shall be six months. The action levels and actions to be taken are presented in Table A-1.
The minimum frequency for invivo counting (lungs) shall be annual.
The action icvels and actions to be taken are presented in Table A-1.
More frequent analyses may be performed if other data (air samples. floor and clothing contamination) indicates that workers are being exposed. The Supervisor, Health and Satety shall determine
~
this increase in frequency.
A.9.2.4 Air Sampling - Air samples shall be taken in all areas of the 1.RC in which operations are conducted that might cause personnel to be exposed to airborne radioactive materials.
Any of these areas in which the concentration of airborne radioactive material exceeds 25% of the applicable MPC shall be continuously monitored for as long as the process that causes the airborne activity is in progress.
Permanently mounted air sampling equipment nortnally used to determine con-centrations in a worker's breathing zone shall be evaluated for representa-tiveness at least once every 12 months and whenever any licensed process or equipment changes are made.
In addition, the location of air samplers shall be checked out at the beginning of operations in an area that has been shut down for more than 6 months to verify the representativeness of the air sampling.
License No.
SNM-778_
Docket No.
70-824_
Date october _1919 Page A-20 Amendment Hu.
Revision No.
2 Babcock & Wilcox
l i
1.
The health physics protection and monitoring requirements i
during removal and while glove boxes and equipment are in standby condition.
l O 2.
Cleaning procedures.
l 3.
Package preparation procedures.
i 4.
Means and methods to prevent the leakage of contamination j
during package preparation and during storage.
5.
Procedures for removal of off-gas lines and packaging of i
these and other contaminated equipment.
l l
l I
l A.9.4.4 Decommissionina - At the end of plant life the LRC shall decontaminate the facility and site in accordance with Appendix F. LRC
(
f Decommissioning Plan.
A.9.4.5 Water Level Control - A float-type alarm switch is provided j
in the storage pool adjacent to the hot cell.
If the water level exceeds either the high (3 inches below the overflow) or low limit (29 inches be-low the overflow), an alarm is actuated in the Building B health physics area. A switch shuts off the pool recirculator pump in the event of loss of pool water.
i A.9.4.6 Audit of Shippina Procedures - The health physica group is responsible for auditing all shipping records (monthly) to ensure that pro-i l
cedures are adequate and that the LRC follows these procedures in preparing l
l shipments of radioactive materials. The SAS audits the health physics group i
r
[
periodically.
t I
(
A.9.4.7 Health Physics Procedures - written and approved health 1
physics shall be established, maintained and followed to include as a minimum f
r procedures fort l
t
- 1. Alarm source check and calibrations
- 2. The conduct of surveys, l
- 3. Sample counting l
- 4. Counting system calibration.
t t
License No.
8386-77 8 Docket No.70-824 Date November 1979 Page A +11 I
ment No.
Revision No.
3 f
(
Babcock & Wilcox l
A.9.5 Nuclear Safety A.9.5.1 Administrative Requirenents - The facility supervisor is responsible for the overall administration of the nuclear safety progran for his areas. The facility supervisor advises the nuclear safety of ficer of his nuclear safety requirenents.
All postings, training prograns, and other written instructions containing nuclear safety rules shall be approved by the facility supervisor.
The facility supervisor naintains a record of the number of units authorized and present in his material balance area.
The nuclear safety officer or person designated by hin provides nuclear safety evaluatons (including calculational support) as requested or as he deens necessary; these calculations are used to support the license conditions.
Nuclear safety evaluations and calculations are riviewed by a s
qualified individual as defined in A.S.2.4; results of the review are documented and natntained with the nuclear safety evaluations for the same period of time that the evaluations are maintained. He will naintain records of these calculations for at least six nonths after termination of the approved process.
The nuclear safety officer perforns nonthly inspections in areas where SN'i are being processed. Other areas are inspected less f requently; however, all areas are inspected at least twice a year.
This irspection includes an audit of nuclear safety records, a check for area posting, and a review of current practices.
A written quarterly inspection report, noting any items of nan.conformance, is given to the Managor.
Lynchburg Technical Operations.
Tho facility supervisor advises the fianager, Lynchburg Technical Operations of corrective action.
A.9.5.2 Training. All authorized users shall be trained in nuclear safety by the nuclear safety officer or by a qualified person designated by hin. All authorized users shall be retrained annually by the nuclear safety of ficer or by a qualified person designated by hin.
The instructor shall bo identified and attendance shall bo documented for each training sossion.
Ucente No SNM 778 Docket No.
70 824 Date f ebruary 19B' h
Amendment No.
10 Heviilon No.
20 Page A-12 Babcock & Wilcox w o,, m m.,,,,,
m i
l t'
4.0 Organization for-Control of Radiological Contingencies 4.1 Normal Plant Organization Figure 4-1 "LRC Line Organization" is an illustration of the normal plant organization.
The Manager, Lynchburg Technical Operations is responsible for all LRC l
Operations.
Two laboratory manage s report to him - Materials Engineering Laboratory Manager and Systems Development Laboratory Manager.
Each laboratory is divided into two or more sections, each headed by a section manager who directs the work of various group supervisors.
The Manager, Safety and Licensing reports to the Manager, Lynchburg Technical Operations.
Four department nanagers, Purchasing, Accounting and Administrative Services, Facilities, and Quality Assurance report furctionally to the Manager, Lynchburg Technical Operations.
Theta department heads report administratively to their Otvision Managers.
During abnor.nal or accident conditions the L9C receptionist notif tes the primary members of the Emergency Control Organization.
The Emergency Of ficer is authorized to classify and declare an emergency.
4.2 Onsite Radiological Contingency Response Organization o
(V)
Figure 4-2 " Emergency Control Organization" is an illustration of the onsite radiological contingency response organization.
Each person assigned to the emergency control organization is appointed, based on the appropriateness of his experience and training to the duties of his assigned position. Appointments are recomended by the energency officer and approved by the Manager, Lynchburg Technical Operations in l
writing.
4.2.1 Ofrection and Coordination 4.2.1.1 Manager Lynchburg Technical Oparations - The Manager, Lynchburg Technical Operations appoints key members of the emergency control organization and reviews and approves plans and procedures for its function.
The Manager, Lynchburg Technical Operations may assume control of the energency control organmization by inforntng the emergency officer of his desire to do so.
The Manager, Lynchburg Technical Operations will authortie the release of information to the senior 84W, Lynchburg public relations official for eventual release to the news media.
The senior BAW, Lynchburg public relations official will coordinate such releases with government authorities.
Licenso No SNM 778 Docket No.
70 (124 Date february 1986 (m)
Amendment No. 10 Hevhion No.
20 Paue C 4-l V
Babcock & Wilcox
., e, n m,.,,,,
4.2.1.2 Emergency Officer - An emergency officer and two alternates shall be appointed by the Manager. Lynchburg Technical Operations in l
writing.
In the event of an emergency, the emergency of ficer shall classify the emergency, evaluate the situation, initiate and assume control of all recovery operations, and ensure that all necessary of f-site notifications are made.
The emergency officer shall be responsible for assuring that reviews of the Emergency Plan and Emergency procedures are per-formed and changes to the Plan and Procedures are made when required.
The emergency of ficer is responsible for assuring that drills and exercises are conducted in accordance with Section 7.0 of this Plan.
4.2.2 Plant Staff Radiological Contingency Assignments During working hours the below listed staff functions are available for response.
During nonworking hours this same staff is available for recall in accordance with procedure.
4.2.2.1 Evacuation Officer - An evacuation officer and two alternates snall be appointed by the Manager, Lynchburg Technical Operations in writing.
The evacuation officer shall be responsible for personnel accountability during emergencies.
He shall report any unaccounted for persons to the emergency officer and assist the emergency officer by providing traffic control and by maintaining order.
He shall be assisted in these efforts by the evacuation of ficer alternates and the emergency rr: order from the af fected facility.
LRC employees have been ins'ructed that they are responsible for their visitors in the event of an emergency.
In the event of an evacuation the emergency recorder from the af fected faci 11ty wt11 work with the LRC receptiontst to ensure that visitors are accounted for.
4.2.2.2 Fire and Rescue Officer - A fire and rescue officer and two alter-nates shall be appointed by the Manager, Lynchburg Technical l
Operations in wr1 ting.
ine fire and rescue officer is responsible for the direction of fire fighting, rescue and first aid operations.
He shall report the Status cf the fire fighting, rescue, and first aid operations as approJrtate to the emergency officer.
He shall provide the direction for the fire and rescue team during the emergency and during recovery operations.
Liceme No SNM 718 Docket No.
70 fl24 Data february 19)l6 Amendment No.
10 Hevision No.
20 Page C 4-2 Babcock & Wilcox a hk Ornw tt t omp.sny
(
4.2.2.3 Radiological Ssfety Officer - A radiological safety officer and two alternates shall be appointed by the Manager. Lynchburg Technical Operations in writing. The radiological safety officer is responsible for evaluations of suspected radiological hazards as they affect emergency recovery operations.
He directs monitoring teams in acquiring accident evaluation data and their support of other recovery operations.
He shall be assisted in these efforts by the radiological safety officer alternates and the LRC health and safety group.
4.2.2.4 Nuclear Criticality Safety Of ficer - A nuclear criticality safety officer and one alternate snall be appointed by the Manager, Lynchburg Technical Operations in writing.
The nuclear criticality safety of ficer is responsible for the evaluation of conditions affecting the prevention of termination of nuclear criticality accidents.
He maintains cognizance of fissile material use and storage conditions.
When fissile materials are involved, he recommends recovery actions that preclude accidental criticality.
He may be assisted in these efforts by the LRC nuclear criticality safety group.
The nuclear criticality safety of ficer reports to the radiological safety of ficer.
4.2.2.5 Emergency Recorder - The emergency recorders, appointed by the emergency officer in writing are responsible for the generation o)
(V and maintenance of records of events and conditions associated with the emergency activities.
These records include, but are not limited to, personnel accountability, radiation exposure, and Incident Ouestionnaires.
The emergency recorders report to the emergency officer.
4.2.2.6 Facility Supervisor - The facility supervisor is appointed by the Manager, Lynchburg Technical Operations.
He shall supply l
information to the emergency officer regarding operations in the area that were transpiring prior to the onset of the emergency.
He shall assist the emergency officer in determining the causes of the emergency.
4.3 Offsite Assistance to LRC 4.3.1 NNFD Emergency Sup) ort - In the event of an emergency after normal worning nours the GTE Security Shif t Supervisor will be t.otified of the emergency via the emergency telephone system.
The NNFD Security Shift Supervisor will take action as outlined in the LRC Emorgency Procedures.
The emergency control organization of NNFD has agreed to provide the following support.
Licente No SNM 778 Docket No. 70 824 Date February 1986 (m)
Amendment No.
10 Hevision No.
20 Page C 4-3 v
Babcock & Wilcox A % Dehnott (Ornpany
O o Ambulance service o First aid and decontamination as'>
- v ce o Monitoring and health physics ass' tance o Fire brigade assistance o Security assistance o Communication with off-site emergency organizations.
4.3.2 CNFP Emergency Support - In the event of an emergency, the emergency control organization of CNFP has agreed to provide the following support.
o First aid and decontamination assistance o Monitoring and health physics assistarce o Environmental sample collection assistance O
License No SNM 778 Docket No.
70 824 Date February 1986 Amendment No.
10 Hevision No.
20 Page C 4-3a Babcock & Wilcox
,e Mr Dermott t orfip,wty
l l
4.3.3 Lynchburg General Marshall lodge Hospital - Lynchburg General Marshall Codgi Hospital will accept all accident victims, but will rely on the l
LRC emergency control organization to provide radiological safety t
control when necessary.
(Ref. Figure 4.3)
Procedures have been l
developed to outline Lynchburg General Marshall lodge Hospital's i
actions regarding LRC patients referred as a result of an accident resulting in radiation exposure or contamination.
(
4.3.4 Concord Rescue Squad - The Concord Rescue Squad has agreed to provide first aid assistance in the event of an emergency at the LRC.
(Ref.
Figure 4.4) l l
4.3.5 Sheriff's Department and State Police - the Campbell County Sheriff's l
Department, tustburg, Va. and the Virginia State Police Appomattox, Va. will provide traffic control in the event of an emergency at the l
i LRC.
4.3.6 Concord Volunteer Fire Department - The Concord Volunteer Fire l
Department will respond to emergency calls for assistance from the LRC emergency control organization.
(Ref. Figure 4.5) Depending on the severity of the emergency condition, the Concord Volunteer Fire I
Department may request assistance from the Lynchburg Fire Department.
l i
4.3.7 Lynchburg Fire Department - The Lynchburg Fire Department will respond to emergency calls for assistance from the Concord Fire Department in the event of an emergency at the LRC.
4.4 Coordination with Participating Government Agencies l
4.4.1 Campbell County, Virginia l
i 4.4.1.1 Autho*ity_
[
l 1.
County of Campbell, Emergency Operations Plan, Basic Plan, dated j
Aurjust 1979, approved by the Board of Supervisors, December 17, 1979.
l 2.
Commonwealth of Virginia Emergency Services and Olsaster Law of 1973, as amended.
[
4.4.1.2 Responsibilities.
County agencies and departments will plan and prepare for response to radiological emergencies in accordance with the Campbell County Radiological Response plan.
Lleense No SNM 778 Docket No. 70 824 Date October,1983 II C 4-4 Amendment No.
2 Moviolon No.
Pg l
d Babcock &Wilcox A W Detmott t OrnpAny f
l 4.4.1.2.9 State Department of Highways and Transportation (Richmond, VA) i 1.
Barricade State-maintained roads in those areas affected by the l
radiological emergency.
4.4.1.2.10 Campbell County (Rustburg. VA) 1.
Coordinate radiological response actions with the City of i
l Lynchburg and other adjacent political subdivisions.
i l
t 2.
Provide radiological monitoring and other support to other l
local governments.
l 4.4.1.2.11 Rescue Services (Concord and Rustburg, VA) 1.
Provide personnel to staff at least two monitoring teams from each squad.
l 2.
Conduct monitoring as requested by the County Coordinator of 1
l Emergency Services.
i l
4.4.2 Virginia State Office of Emergency Services - The Virginia State Of fice of Emergency Services, Richmond, Va., will be contacted in the event of a major emergency condition involving actual or potential off-site release of radioactive materials. The State Emergency Operating Center l
will be activated and the provisions set forth in the Commonwealth of Virginia Radiological Emergency Response Plan shall be inacted.
i 4.4.3 Department of Energy - The Department of Energy has available a radfological assistance team. Depending on the severity of the emergency condition, this team, which is on call from Oak Ridge, Tennessee, will be requested to provide assistance.
License No SNM 778 Docket No. 70 824 Date October,1983 II C 4-7 Amendment No.
2 Mov6elon No.
Pege l
l Babcock & Wilcom e hok 099MDIt tD!DpAt1f I
- - -. ~
FIGURE 4-1.
LRC L!flE ORGANIZATION RE$tARCH AND OtVELOPMENT OtvillON VICE PREllutNT LYNCH 8URG RESEARCH CENf t R SPt CI AL PROJECil/
LYNCHSUPO f tCHNICAL OP.tR ATIONS DICOMMist ONsNQ MANAGIR MANAQtR DE COMM118tONsNQ
~ ~ ~ ~ ~ ~ ~ * * ~
PURCHASING PURCHAllNG R400 LRC
==.
MANAGER MANAotg SAFEfV AND AccouNilNo LICE Ntimo CONTROLLER ANO R&OO AegimitTR AflV E MANAGgg SE RVICE S
=
LRC MANAQtR STIII"8 P ACILif f t8 CIVitorutNT AND P ACILIfit t LAnoRATORY OU ALifV LRC ASSURANCE
="-
MANAotR R400 MANAGER MANAGtR OUAlefV 00Allf V MAgge,Atg AltVRANCE ASIVRANCI E NGINE B RING R&DO L80 LANORATORY MANActR ADMINit f R A TOR
,,g,c,,
SCitNfilf
= = =4NDICAf fl PUNCflONAL plPOR flNG License No SNM 778 Docket No.
70 824 Data february 19M Amendment No.
10 FleVision NO.
20 Page C48 Babcock & Wilcox A Me ()ctmott e ornp.wiy
O I
\\
C' FIGURE 4-2.
EMERGENCY CONTROL ORGANIZATION L
SEBScamCT offICte negosmos messance seette tvassaoume teenessag esenerises teeteleete efforte I
I I
I WStGenCT STactAfl05 FIBA AND RA8totDGtCAL facttttf BSCOGASS OFftCBS R89Cpt OfftCSS
$ArtTY OrflCES SUPT 491908 Fire Flahttee nedleleelset lefety Desh itseet Feroommet Centres neeeee op sesettettog feems semesh Castelestes foresenet.itit, Ft..
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,c
=
m.et e e,its.eistF s.e.tf i
inns swme I
{
I License No SNM 778 Docket No. 70 824 Date February 1986 Amendment No.
10 RevWon No.
20 Page C 4e9 l
Babcock &Wilcox A MDermott COmpAnf
Figure 4-3 M Lynchburg General-Marshall Lodge Hospitals T5e can;s naad tsara, vepu 2co. (eou 5:smo n.rymorus E Htmpn, Esa2 Ave Vrm5%=shw July 11, 1980 Hr. JcFa W. Cure, !!!
Supervisor, Hesith 6 S fety Lynchburg Researth Center and Research Develeprent Division Babcock 6 kilcox P. O. Box 1260 Lynchburg, Virginia 24505
Dear John:
In response to pur letter of July 9,' 1930, please be advised that it is the intent of this institutien to continue to handle ceployees frus your cc: pany in the event of a nuclear accident in accordance with the precedures which have been outlined by you and which are in our files.
If you need further specific infor.ation relative to this natter, please do not hesitate to call rm.
Sincere 1
- ours, pay n I
'1 Executive Vicc Frtsiitnt RDtiphs cct L. H. H ward, M.D.
License No SNM.778 Docket No.70-824 Date Oc tober', 1983 C 4-10 Amendment No.
2 Hevision No.
Page Babcock & Wilcox A Mc Dermott comp.w,y
~
5.2.2 Alert 5.2.2.1 High Radiation The assessment of this situation will be made by the Radiological Safety Officer (RS0), based on information provided by surveys performed by the radiation monitors and information supplied by the facility supervisor. The RSO will decide on correction action.
5.2.2.2 Fire of Explosion (Major)
The ECO will assess this situation based on information supplied by the facility supervisor from observations of those on the scene ar1 the RSO from it. formation supplied by radiation monitors based on surveys and instrument readings (air monitors and stack sampling moni tors).
5.2.3 Site Area Emergency 5.2.3.1 Criticality Assessment and corrective action will be made by the RSO based en infomation provided by radiation monitors from surveys and instrument readings (air monitors and stack sampling monitors), and advice of the Nuclear Safety Officer.
5.3 Corrective Actions The events below are assumed to have proceeded beyond the state where control can no longer be maintained by normal procedures and the Emergency officer has declared an emergency.
It must also be recognized that in emergency situations actions taken by individuals or teams are largely dictated by the specific situation and on the scene decisions based on training.
5.3.1 Unusual Events 5.3.1.1 Fire or Explosion (Minor)
The fire and rescue team will terminate the event using standard fire fighting methods depending on the origin. The receptionist will stand by to notify the CNFP, NNFD or Concord Volunteer Fire Depart-ment if back-up support is needed.
License No SNM 778 Docket No. 7G824 Date Oc tober,1983
~
Amendment No.
2 Rev6olon No.
Page Babcock & Wilcox a McDermott company
5.3.1.2 Bomb Threat Upon instruction by the Emergency Officer, the receptionist will evacuate the buildings. A roll will be taken to identify missing persons.
The bomb search teams will search their facilities for unusual devices or objects.
If no suspicious objccts are found, the Manager, Lynchburg Technical Operations and Fire and Rescue Officer will determine if and when to authorize re-entry into the buildings.
If a suspicious object or device is found, arson investigation officers at one of the following locations will be notified:
U.S. Treasury Department, ATF State Arson investigators Roanoke, Richmond, Marion, Culpepper, Norfolk All personnel will remain clear of the affected area.
The Emergency Officer will notify Region II, NRC.
Emergency status will remain in effect until the device is found to be or made safe by the arson investigators.
The Emergency Of ficer will update CNFp and NNFD of the emergency status.
5.3.1.3 Civil Disturbance o
The person discovering that the LRC may be threatened by a civil disturbance shall contact the receptionist using the emergency telephone number (5000) and provide the following information:
- 1. Location of the disturbance
- 2. Nature of the disturbance
- 3. Severity of the disturbance o
Receptionist shall contact the Emergency Officer and primary members of the EC0 using the pocket paging system and advising them of the situation.
o ECO and Manager, Lynchburg Technical Operations sha'.1 meet to l
decide on the action to be taken. Civil dt<*arbances which threaten the LRC will also be threatening to the NNFD.
Because of the nature of the operation at NNFD and tne large size of the security force, NNFD will take the lead in handling e.ivil disturbances threatening the BAW facilities.
o The Emergency Officer will contact the NNFO Security Depart-ment to assure they are appraised of the situation and is taking action.
License No SNM 778 Docket No.70-824 Date february 1980 Amendment No.
10 Revision No.
20 Page C 5-10 g
Babcock & Wilco::
A M(Dermott (ompany
o When the threat has subsided the Emergency Officer will con-suit with the Manager, Lynchburg Technical Operations on l
further actions.
5.3.1.4 Earthquake, Hurricane or Flood Earthquakes are not forecasted.
o Evacuate all buildings by sounding the evacuation alarms.
o Take a roll to identify missing persons, o
Fire and Rescue Teams to standby to fight fires if they occur and attempt to locate missing persons.
o Emergency Of ficer, meet with primary members of ECO to deter-mine further action.
Hurricanes are forecasted.
o Emergency Of ficer meet with primary merr.bers of the ECO to determine actions to be taken.
Time permitting the following steps may be taken:
- 1. Move radioactive material to secure storage.
- 2. Shut down CX-10.
- 3. Release all nonessential personnel.
- 4. Notify NNFD and CNFP.
Flooding is forecasted and cannot be reasonably expected to i
directly affect the LRC.
Exit routes 72 and 460 may become impassible, o
Manager, Lynchburg Technical Operations will release employees l
prior to road flooding.
l o
Emergency Officer will ensure all operations within the LRC i
are safely secured and buildings are secure.
5.3.1.5 Release of Toxic Gas o
Individual discovering release, notify receptionist, using j
emergency telephone number (5000).
Provide the following Information:
- 1. Location of release.
- 2. Personnel injuries.
- 3. Identification of gas.
o Activate the buildina evacuation alarm.
License No SNM.778 Docket No. 70 824 Date february 1986 i
Amendment No.
10 Revision No.
20 Page. C 5-11 i
Babcock &Wilcox a McDermott company
I
)
f o
Receptionist notify EC0 using the pocket paging system and give details.
o Receptionist assemble Fire and Rescue Team using building paging system and direct them to assemble in an area specified by Emergency Officer.
o Emergency Officer advise receptionist of area for Fire Rescue Team to assemble.
o Emergency Officer direct Fire and Rescue Officer and RSO to assembly area.
o Evacuation Officer to identify any missing persons.
o Emergency Officer advise NNFO and CNFP of situation and request assistance if needed.
o Radiological Safety Officer shall take action to terminate on on-site toxic gas release.
o Emergency Officer authorize re-entry, Emergency Officer close out with verbal summary to NNFD and CNFP.
o 5.3.1.6 Nearby Industrial or Forest Fire o
The person discovering the fire, contact receptionist using emergency telephone number (5000) and provide the following i nfonnation:
1.
Location of the fire.
2.
Nature of the fire.
3.
Severity of the fire.
Receptionist contact primary members of the ECO using the pocket O
paging system and advise them of the situation, Receptionist standby to notify the Fire and Rescue Team and if o
directed by Emergency Officer, notify NNFD, CNFP or the Concord Fire Department or any combination thereof.
o Primary ECO meet to evaluate the hazard to LRC.
o If fire is at CNFP or NNF0, assemble the Fire and Rescue Team to provide assistance if requested.
License No SNM 778 Docket No.70-824 Date October,1983 Amendment No.
2 Flavision No.
Page Babcock & Wilcox a W Dermott company m
o If the fire threatens the LRC, Emergency Officer to assemble the O
V Fire and Rescue Team and have Fire and Rescue Officer begin fire fighting operations. Emergency Officer to notify CNFP, NNFO and Concord Fire Department and request assistance.
5.3.1.7 Radioactive Spill o
Person discovering the spill, contact Health and Safety group.
o Health Physics to make initial assessment. If corrective action cannot be affected using standard operating procedures - contact receptionist using emergency telephone number (5000).
o Receptionist to notify primary members of the ECO using the pocket paging system and advise them of the situation.
o RSO evaluate the situation and direct corrective a'ctions.
o RSO to keep ECO appraised of situation progress.
o Receptionist to alert employees to remain clear of the affected area, using the building paging system.
o RSO to notify Emergency Officer when situation is under control.
3 o
Emergency Officer close out with verbal and written report to the
/
Director.
5.3.2 Alert 5.3.2.1 High Radiation Nomally, high radiation at the LRC will be picked up by the fixed radiation monitors located throughout buildings at the site. The building evacuation alarm will activate automatically if two of these i
monitors detect high radiation.
o The person discovering the high radiation shall take the necessary action to activate the building evacuation alarm.
o Once the building is evacuated the person discovering the high radiation condition shall report to the Emergency Of ficer and, if possible, provide the following information:
Liceme No SNM 778 Docket No.70-824 Date October,1983 Aniendesnt No.
2 Revision No.
Page Babcock & Wilcox a McDermott company
- 1. Location of the high radiation.
- 2. Severity of the emergency condition.
- 3. Cause of the high radiation condition.
- 4. Operations in progress in the area of the high radiation condition just prior to the onset of the emergency condition.
o Receptionist contact the Manager, Lynchburg Technical Opera-tions and the following Emergency Control Organization per-sonnel via the pocket paging system, radio, or telephone.
- 1. Emergency Of ficer
- 2. Fire and Rescue Officer
- 3. Radiological Safety Officer
- 4. Evacuation Officer
- 5. Nuclear Criticality Safety Officer
- 6. Fire and Rescue Team Chief
- 7. Fire and Rescue Team Assistant Chief o
If Building D is not evacuated, receptionist standby to request NNFD and CNFP Health Physics assistance. Page the Fire and Rescue Team and direct them to report to the Building D evacuation assembly area.
o If Building n is evacuated, Fire and Rescue Officer requests for assistance from NNFD and CNFP will be made by the Fire and Rescue Officer via portable radio, o
E. O. ensure that evacuated personnel have assembled in an area where the radition level is acceptable.
o E. O. determine if any personnel from the affected building (s) are missing.
If personnel are missing, direct the Fire and Rescue Officer to set up search teams and begin search and rescue operations for missing personnel.
Ensure that Health Physics technicians accompany each search team with suitable radiation monitoring equipment.
If no personnel are missing, direct the Radiological Safety Officer to set up Health Physics monitoring teams and survey the affected building (s) to determine the extent of the high radiation, o
Based on input from the Health Physics monitoring teams, RSO determine the cause of the high radiation and advise the License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page C 5-14 Babcock & Wilcox a McDermott company
Emergency Officer of the proper actions to be taken to resolve the emergency condition.
o E. O. utilize Health Physics monitoring team personnel and Fire and Rescue Team members to take the actions necessary to resolve the emergency condition.
5.3.2.2 Fire or Explosion (major) o The person discovering the fire / explosion shall activate the building evacuation alarm, o
Once the building is evacuated, the person discovering the fire / explosion shall report to the Emergency Officer and, if possible, provide the following information.
- 1. Location of the fire / explosion
- 2. Personnel injuries, if any
- 3. Severity of the fire / explosion
- 4. Nature of the fire
- 5. Potential for radioactive materials involvement
- 6. Potential for radioactive materials release o
Receptionist contact the Manager, Lynchburg Technical O
Operations and the following Emergency Control Organization b
personnel via the pocket paging system, radio or telephone.
- 1. Emergency Officer
- 2. Fire and Rescue Officer
- 3. Radiological Safety Officer
- 4. Evacuation Officer
- 5. Nuclear Criticality Officer
- 6. Fire and Rescue Team Chief
- 7. Fire and Rescue Team Assistant Chief o
If Building D is not evacuated, receptionist standby to request NNFD, CNFP, Concord Fire Department or Concord Rescue Squad assistance.
Page the Fire and Rescue Team and direct them to report to the Building D evacuation assembly area.
License No SNM-778 Docket No.70-824 Date February 1986 m,
Amendment No.
10 Revision No.
20 Page C 5-15 Babcock &Wilcox a McDermott company
o If Building D is evacuated, requests for assistance for both on-site and off-site emergency support groups shall be made by the Fire and Rescue Officer via portable radio.
o Based on the location and severity of the fire / explosion, RSO direct Health Physics technicians to survey the affected area to detennine if there has been a radioactive materials release.
NO RADI0 ACTIVE MATERIALS RELEASE o
Fire and Rescue Team report to the Building D evacuation assembly area and begin to assemble equipment from unevacuated buildings for possible injured personnel recovery operations, Upon completion of the personnel roll call and under the super-o vision of the Fire and Rescue Officer and the Radiological Safety Officer, Fire and Rescue Team re-enter the affected building and attempt to locate and rescue any missing personnel. One Health Physics technician with suitable radiation monitoring equipment shall accompany the re-entry team.
o If there are no missing personnel and the fire in the affected building is out of control, the Fire and Rescue Team will attempt to contain the fire so that adjacent buildings will not be affected.
Upon the arrival of the Concord Fire Department, LRC Fire and o
Rescue Team personnel will assist fire department personnel as requi red, If directed by the Emergency Of ficer, the Evacuation Officer send o
home non-essential LRC employees.
Essential personnel, as determined the Emergency Of ficer, the Fire and Rescue Officer and the Radiological Safety Officer will remain on site and render assistance as necessary.
RADI0 ACTIVE MATERIALS RELEASE RSO attempt to determine the type and magnitude of the o
radioactive material release. Determine if it is possible for a Fire and Rescue re-entry team to enter the affected area and attempt to locate and rescue any missing personnel. One Health Physics technician with suitable radiation monitoring equipment shall accompany the re-entry team.
License No SNM-778 Docket No.70-824 Date October,1983
~
2 Revision No.
Page Amendment No.
Babcock & Wilcox a McDermott company
o RSO utilizing LRC, NNFD and CNFP Health Physics personnel, set up survey teams to conduct a radiological survey of the B&W Mt. Athos site.
If it is determined that there has been an off-site radioactive materials release imediately inform the Emergency Of ficer.
o E0 with the assistance of the Radiological Safety Officer determine if the radioactive materials release exceeds the limits of Appendix 3 of the Commonwealth of Virginia Radio-logical Emergency Response Plan.
- o If the radioactive materials release is reportable, complete Tab A " Report of Radiological Emergency." The LRC Reception-ist has a supply of " Report of Radiological Emergency" forms, o
If recommended by the Manager, Lynchburg Technical Operations l
and approved by the RSO, Evacuation Officer send home non-essential LRC employees.
o E0 notify the Campbell County Sheriff's Department that an emergency condition exists and that local residents may have to be evacuated.
E0 notify the NRC, Region II,' Atlanta, that a radiological o
O emergency condition exists.
V o
E0 notify the Department of Energy, Oak Ridge, TN that a ra-diological emergency condition exists and request assistance through the activation of NRC Radiological Assistance Plan.
o At the conclusion of the emergency situation, E0 initiate recovery actions, review the actions of the Emergency Control Organization and the NNFD Emergency Team and make a report to the Manager, Lynchburg Technical Operations.
Implement l
corrective action as necessary.
NO RADI0 ACTIVE MATERIALS RELEASE o
Assist the Fire Department personnel as directed by the Fire and Rescue Officer.
5.3.3 Site Area Emergency An uncontrolled criticality at the LRC will be detected by the fixed criticality monitors located in buildings throughout the site. The building evacuation alarm will activate automatically if two of these monitors detect high radiation.
License No SNM-778 Docket No.70-824 Date February 1986
(
Amendment No.
10 Revision No.
20 page C 5-17 Babcock & Wilcox a McDermott company
o Once the building is evacuated, any person with knowledge of the circumstances of the criticality shall report to the Emergency Officer and provide the following information:
- 1. Location of the criticality
- 2. Severity of the emergency condition
- 3. Cause of the criticality
- 4. Personnel activity in the area of the criticality o
Receptionist contact the Manager, Lynchburg Technical Operations and the following Emergency Control Organization personnel via the pocket paging system, radio or telephone.
- 1. Emergency officer
- 2. Fire and Rescue Officer
- 3. Radiological Safety Of ficer
- 4. Evacuation Officer
- 5. Nuclear Criticality Safety Of ficer
- 6. Fire and Rescue Team Chief
- 7. Fire and Rescue Team Assistant Chief o
RSO determin.e that the radiation level in the personnel assembly area is within acceptable limits.
If the radiation level is too high, advise the Emergency Officer that the assembly area must be relocated.
o Evacuation Officer take charge of non-essential personnel and if directed by the Emergency Officer, relocate them to the training drea, NNFD for debriefing, completing of question-naires and Health Physics monitoring.
o EC0 meet to discuss circumstancer of the criticality incident.
Items of concern include the following:
- 1. Location of the criticality incident.
- 2. Severity of the criticality incident.
License No SNM-778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page C 5-18 Babcock & Wilcox a McDermott company
pd 6.0 Equipment and Facilities 6.1 Control Point No formal emergency control center is provided for at the LRC.
The primary control point is in the assembly area in the parking lot in front of Building D.
If the need arises for an off-site control point, the training area at NNFD would be used.
For situations re-quiring prolonged control, the reception area and the office of the Manager, Lynchburg Technical Operations may be used.
I 6.2 Communications Comunication Systems The LRC utilizes telephones (normal and emergency extensions),
radios and pocket paging equipment for internal communication.
Communication between the LRC and the CNFP is maintained utilizing telephones and portable radios.
Portable radios are used and stored throughout the buildings at the LRC. Off-site communication is maintained utilizing telephones.
The security force, NNFD maintains radio communication with the Campbell County Sheriff's Department and the Virginia State Police Department.
During emergency situations communication between various elements of the Emergency Control Organization is accomplished through the use of a megaphone and portable hand held radios. Communication between the Emergency
~
Contral Organization and the remainder of the LRC personnel is accomplished through the use of a megaphone.
6.2.1 Emergency Telephone System - An emergency telephone system in opera-tion at the LRC is part of the emergency communications system. An energency telephone number, extension 5000, is used in emergency situations when an LRC employee determines a need to contact the Emergency Control Organization during normal work hours and the NNFD Security Shif t Supervisor during after hours.
This emergency telephone number is a dedicated number on the normal telephone system. The emergency telephone number rings in a secretarial loction in Building A, the receptionist's desk in Building D-2, and Gate #1 NNFD Security. During normal work hours the receptionist.
Building D-2, will respond to the emergency number in accordance with detaileo instructions.
During non-work hours the NNFD Security Shift Supervisor will respond to the emergency number in accordance with written procedures outlined in the LRC Emergency Procedures Manaual.
In addition, a dedicated emergency telephone system is in operation between the LRC and NRC Headquarters, Washington, DC.
The l
LRC Manager, Lynchburg Technical Operations shall authorize use of l
the dedicated emergency telephone system.
The locations of the dedicated emergency telephone system are the office of the Manaqer.
I License No SNM 778 Docket No.70-824 Date February 1986 l
Amendment No. 10 Revision No. 20 Page C 6-1 Babcock & Wilcox a McDermott company
I Lynchburg Technical Operations, Bay #2 control room, receptionist, Building D-2, health physics control Building B, and Gate #3 NNFD Securi ty.
6.2.2 Paging System - The normal paging system enables the receptionist, Building D-2 to make announcements as required in Buildings A, B, and C.
This system is a backup system for the evacuation alarm system.
In the event that the evacuation alarm system fails, emergency announcements can be made utilizing the normal paging system.
In addition to the normal paging system a pocket paging system is in use as part of the LRC's emergency communications system. The principle members of the Emergency Control Organization can be notified of an emergency situation via a group call on the pocket paging system.
6.2.3 Evacuation Alarm System - The evacuation alarm systen can be operated automatically or manually. Criticality monitors located throughout the LRC site will automatically activate tne evacuation alarm when high radiation is detected.
Toggle switches to operate the evacuation alarm manually are also located throughout the LRC site.
LRC employees are instructed to use the manual switches when the emergency situation dictates rapid evacuation of the affected building.
6.3 Facilities for Assessment Teams Monitoring systems including wind speed and direction, outside air temperature (8 ft and 130 ft elevation), criticality, stack sampling, waste tank levels, alarm or print out in the Building B health physics area. Operating procedures manuals that may be needed are located thro 0ghout the LRC buildings.
Drawings of the buildings and engineering drawings are located in the two emergency lockers.
6.4 On-site Medical Facilities Emergency first aid equipment on-site consists of the following:
1.
Stretchers (D-ring, spineboards, chair litter)
~
2.
Bandages 3.
Splints (hard and inflatable) 4 Slings 5.
Oxygen resusitator 6.
Disinfectants 7.
Eye washes 8.
Showers 9.
Soap i
License No SN M-778
- Docket No.70-824 Date February 1986 Amendrnent No.,
10 Revision No.
20 Page C 6-2 Babcock & Wilcox a McDermott company
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s 7.0 Maintenance of Radiological Contingency Preparedness Capability 7.1 Written Procedures - The Emergency Officer is the planning coordinator.
He is responsible for the adequate distribution of the contingency plans and for approving changes, j
l 7.2 Training - Training in emergency response begins with the indoctrination of each new employee in his assigned responsibility in time of emer-gency. The E0 or his designated alternate conducts this new employee indoctrination. Specialized training programs have been established to assure competent support in first aid, fire fighting and radiological monitoring. Members of the EC0 will be retrained i
annually. The E0 is responsible for the training and retraining of the ECO. He is assisted by the radiological safety officer for the training of health physics technicians and by the fire and rescue team chief for the training of the fire and rescue team. The E0 will ensure that all training sessions, drills and exercises are properly documented. The E0 will assess the adequacy of the ECO training program and recommend changes as required in his report to the Manger, 4
Lynchburg Technical Operations following planned or actual evacuations.
The Manager, Lynchburg Technica'l Operations is ultimately responsible I
for the opeation of the Center in routine and emergency conditions.
However, in an emergency condition, the E0 is in direct control of the
(""s ECO. The E0 is also responsible for ensuring that the Manager,
(,)
Lynchburg Technical Operations is cognizant of changes to the LRC Emergency Plan and Emergency Procedures. Major changes to the Emergency Plan and/or Emergency Procedures are reviewed by the Mananer, Lynchburg Technical Opeations so that he has first-hand information concerning the emergency program for the Center.
Emergency control organization personnel are involved in major changes to the emergency program for the Center.
Each evacuation drill con-ducted at the Center is in effect a retraining of EC0 personnel.
In addition, major changes to the Emergency Plan /or Emergency Procedures are reviewed with primary EC0 personnel so that position responsi-i bilities are adequately defined.
The emergency control organization for the LRC does not have a formally defined radiological monitoring team.
A radiological safety officer is identified and health physics technicians are available for radiologi-cal monitoring assistance.
Health physics technicians by the nature of their normal day-to-day responsibilities are qualified to perform radiological monitoring operations during emergency conditions. The radiological safety officer conducts periodic retraining of the health License No SNM 778 Docket No.70-824 Date February 1986 Amendment No.
10 Revision No.
20 Page C 7-1 Babcock & Wilcox a McDermott company
physics technicians as changes in equipment, techniques and facilities occur.
The fire and rescue team portion of the emergency control organization undergoes quarterly training which includes hands-on and/or classroom training.
The hands-on training includes actual fire fighting uti-lizing such equipment as fog systems, dif ferent types of fire extin-guishers and fire hoses. Classroom training is utilized to update fire and rescue training. At least half of the members of the fire and rescue team are trained in first aid. Ccurses such as the American Red Cross Standard First Aid and Personal Safety and The American Heart Association Basic Cardiac Life Suppor' are used to train team members in first aid support.
Retraining of on-site medical support personnel will be conducted each three yaars in accordance with the retraining requirements of the American Red Cross Standard First Aid and Personal Safety Course.
When an emergency condition exists at the LRC, the EC0 relies on tssistance from the emergency organizations at the NNFD and CNFP.
In addition to these on-site emergency organization servicer, the LRC can utilize the Concord Fire Department, the Campbell County Sherif f's Department, and the Virginia State Police.
The local fire departments and law enforcement personnel visit the LRC periodically to become familiar with facility and egoipment changes.
The frequency of visits by local emergency assistance personnel is dependent upon the need for i
a review of the LRC facility.
The emergency officer will, in conjunc-tion with the fire and rescue officer and the fire and rescue team chief, determine the need for retraining of local emergency assistance personnel. A tour of the facility for local emergency assistance personnel will be conducted annually.
The annual drill shall include as a minimum a test of the communica-tions links and notification procedures for early warning of the public between the LRC and state and local emergency units.
The ECO, as directed by the E0, will critique each drill.
A report summarizing each preplanned drill will be submitted to the Manager, Lynchburg Technical Operations.
The E0 is responsible for preparing this report.
All training sessions, drills, and exercises will be documented.
The docu-mentation shall include evaluations and follow-up corrective actions.
Medical support for the LRC, in the event of an emergency condition, is provided by the health and safety department of the NNFD, the Concord Rescue Squad and the Lynchburg General Marshall Lodge Hospital.
If the fire and rescue officer determines that there is a need for specialized training, such training will be conducted.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No. 20 Page C 7-2 Babcock & Wilcox a McDermon company
D.1 OBJECTIVE The Safety Review Comittee (SRC) is instituted to advise the Manager, Lynchburg Technical Operations cf the Lynchburg Research Center l
(LRC) on the safety aspects of the LRC's reactor and critical experiment operations and on the handling of licensed material.
D.2 ORGANIZATION The SRC is composed of at least five senior technical members. No more than 75% of the senior technical members shall be from the LRC.
In addition to the technical members, one member will be a management repre-sentative who will act as the Comittee coordinator. Members of the Com-mittee are appointed by the Manager, Lynchburg Technical Operations, who l
will also designate one of the members to act as chairman and one member to act as the alternate chairman. The combined experience of the members includes reactor operations, reactor engineering health physics, radio-logical safety, the handling of licensed material, and chemistry. Com-mittee membership may fluctuate according to needs due to the experimental nature of the work performed at the LRC.
Specialized consultants are also available to the Comittee.
D.3 FUNCTION The Comittee shall review all major changes or additions to the facility operating procedures and processes before they are implemented.
The facility supervisor shall determine whether the changes require Comittee approval before implementation.
The following are examples of changes or additions which are considered major:
1.
Any change requiring a license amendment.
2.
Any new process which involves the use of licensed material.
3.
Any change of the technical specifications.
4 Any change to a reactor involving an unreviewed safety safety question as defined in 10 CFR 50.59(c).
License No SNM 778 Docket No. 70 824 Date February 1986 Amendment No.
10 Revision No.
20 pese D-1 Babcock &Wilcox a McDermott company
The fccility cup:rvisor is n:t limited to th:23 clina; ha may requira that cny cr cil pr:cxdurca er pr:ctsaca b2 rcvi wad cnd cpprov:d by the Committee before implementation.
The Cormittee also.has the following functions:
lh 1.
Review general procedures for handling and using licensed material.
2.
Review procedures for the acquisition and disposal of licensed material.
3.
Review procedures for maintaining an accurate inventory of licensed material.
4.
Review procedures for the control of radiation and the protection of personnel from radiation exposure.
5.
Review procedures and proposed projects for fire safety and fire prevention considerations.
6.
Review any changes in the foregoing procedures that require a significant deviation from established pro-cedures before the changes are instituted.
7.
Review abnormal occurrences as defined in appropriate reactor licenses.
8.
Review proposed experiments and tests at the reactor and critical experiment facilities which are significantly different from those previously performed at.the facilities.
9.
Provide the LRC with general consulting services in the field of radiation protection and radioactive materials handling.
Committee approval of new processes and practices prior to the writing of procedures will be occasionally necessary due to the experimental nature of the work performed at the LRC.
In these instances, the Committee will review, with those responsible for the safe operation of the process or practice, the potential hazards and philosophy of operation. The approval by the Committee shall constitute approval to perform the work without written procedures.
D.3.1 Meetings The Committee shall meet at least four times annually for the purpose of conduction business as outlined in D.3 - Function. A quorum, consisting of a majority of the members including the Committee chairman l
l License No.
SNM-778 Docket No.70-824 Date _ September, 1979 Page D-2 Amendment No.
Revision No.
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Babcock & Wilcox
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or the alternate chairman, must be present, Comittee approvals are determined by a majority vote of the members l
present.
Failure to obtain unanimity on a vote shall be so nott:d in the minutes and the dissenting voters shall be afforded the opportunity to express their minority opinion in the minutes.
Comittee minutes shall be kept by the chairman and forwarded to the Manager, Lynchburg Technical Operations with copies sent to all Committee l
members, laboratory managers, facility supervisor, facilities manager, section managers, and reactor operations supervisors. The Committee coordinator shall keep the permanent files of the Committee.
l D.4 SAFETY AUDIT-SUBCOMMITTEE The Manager, Lynchburg Technical Operations shall designate two or l
I more members of the SRC to serve on a subcommittee to audit LRC operations.
He shall designate one member of the subcommittee to act as the subcomittee chairman.
The Safety Audit Subcomittee (SAS) will conduct audits of each licensed facility at least three times annually.
As a guide, the SAS uses the following records: operating procedures, maintenance records, health physics records, nuclear safety records, safeguards records, and reactor and critical experiment records.
The SAS l
chairman will file with the SRC chairman a written report of the subcomittee's findings and recomendations. The SRC chairman will forward this report to the Manager, Lynchburg Technical Operations with l
comments as appropriate.
It shall be the responsibility of the license administrator to act on the recomendations of the SAS.
The license administrator shall also confirm the action take1 License No SNM 778 Docket No.
70 824 Date February 1986 Amendment No.
10 Revision No.
20 Page D-3 Babcock & Wilcox a McDermott company
(3 E.1 RESPONSIBILITIES The supervisor of health and safety reports to the manager of Safety and Licensing with direct access to the Manager, Lynchburg Technical Operations when appropriate (see Fig. E-1).
E.1.1. Health Physics Health physics is responsible for the general surveillance of all radiation activities, distributing and processing personnel monitoring equipment, maintaining individual exposure records, notifying supervisors of exposures greater than the permissible levels, and recommending appro-priate restrictions. Other responsibilities are as follows:
1.
Leak testing of all sealed radioactive sources.
2.
Supervising the shipping and receiving of radioactive materials.
3.
Supervising and coordinating the waste disposal program.
4 Assisting in personnel and equipment d-ontamination.
5.
Orienting and training LRC personnel in radiological l
safety.
6.
Furnishing consulting services on radiation protection.
7.
Generating or acquiring, maintaining, and appropriately distributing all records and reports required by applicable regulations or procedures.
E.1.2 Employees Management at the LRC is committed to the philosophy of maintaining occupational radiation exposure "as low as reasonable achievable." The employee must do all that he can to assist in this poloicy. He should also be aware that this policy is required by the NRC, and the LRC can be I
cited under their license if it is not followed. Therefore, each employee is responsible for complying with each of the following health physics rules.
License No SNM 778 Docket No.70-824 Date February 1986 Amendment No. 10 Revision No. 20 Page E-1 I
Babcock &Wilcox a McDermott company
1.
Following all approved health physics procedures.
2.
Seeing that any visitor is his custody observes all approved health physics procedures.
3.
Reporting any radiation hazard or potential hazard to his supervisor or to a health physics representative.
4.
Minimizing radiation exposure to himself and others to the extent possible.
5.
Wearing the prescribed monitoring equipment.
6.
Surveying hands and shoes for radioactivity af ter working in a contamination area or with materials that present a significant contamination potential (other areas of the body, work areas, clothing, etc., may require surveying) and removing loose contamination to prescribed tolerance levels to comply with approved decontamination procedures (see Section E.7).
7.
Wearing appropriate protective clothing whenever con-tamination of clothing is possible, and not wearing such clothing outside prescribed areas.
8.
Using recommended safety equipment; using proper techniques and procedures.
9.
Observing regulations governing eating and smoking in contaminated areas.
10.
Promptly reporting injuries and ingestion or inhalation accidents to health physics.
11.
Cooperating in all attempts to evaluate exposures, particularly by returning requested urine specimens promptly.
12.
Roping off hazardous areas, controlling potential hazards, and reporting contamination to his supervisor.
13.
Cleaning up contamination for which he is responsible and reporting contamination to his supervisor.
14.
Properly storing and labeling radioactive materials for which he is responsible.
E-2 License No.
SNM-778 Docket No.70-824 Date December 1978 Page Amendment No.
Revision No.
Rahcock m. Wilcox
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l RENEWAL APPLICATION O
DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 1 AMEN 0 MENT 0 l
Description of Changes Page Section Change l
l 1-4 1.6.7 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations," in one place.
2-1 2.2.1 Same as above, in one place.
2.2.2 Sane as above, in one place.
2.2.4 Sane as above, in one place.
(
2-2 2.2.6 Sane as above, in one place.
2.2.9 Sane as above, in one place.
l 2.2.10 Same as above, in one place.
2-3 2.3.3.4 Sane as above, in one place.
I I
2.3.4.1 Sane as above, in one place.
l 2-4 2.3.5.2 Sane as abote, in one place.
l 2.3.5.6 Same as above, in one place.
2.5.1 Same as above, in one place.
l 2.5.2 Sane as above, in one place.
2-5 2.5.6 Same as above, in one place, j
2-6 No change.
l 2-7 2.8.1.1 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations," in one place.
l l
2.8.2.1 Sane as above, in two places.
1 2-8 2.8.3.1 Sane as above, in one place.
j l
3-1 3.1.1.3 Same as above in one place, l
l l
Renewal Application O
Denonstration and Conditions for License SNM-778 Revision 1 Amendment 0 Description of Changes Page 2 Page Section Change 4-1 4.1.6 Sane as above, in one place.
11-1 11.1 Sane as above, in two places.
11.2.1 Sane as above, in one place.
11.2.2 Sane as above, in one place.
11-2 No change.
I 11-3 No change.
4 11-4 11.2.7 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations," in one place.
11.2.8 Sane as above, in one place.
11-5 11.2.9 Sane as above, in three places.
11-6 11.2.9 Sane as above, in three places.
11-7 No change.
11-8 No change.
11-9 No change.
11-10 No change.
l 11-11 No change.
l 11-12 No change.
i l
11-13 No change.
l l
11-14 No change.
11-15 No change.
11-16 No change.
11-17 No change.
11-18 No change.
Renewal Application
(~.
Denonstration and Conditions for License SNM-778 i
Revision 1 Amendment 0 Description of Changes Page 3 Page Section Change 11-19 No change.
11-20 No changa.
11-21 No, change.
New Figure 11-1.
11-22 11-23 New Figure 11-2.
12-3 The title of " Director" has been replaced with
" Manager, Lynchburg Technical Operations," in one place.
12-19 12.8.2 Sane as above, in two places.
12-37 12.11.1.2 Same as above, in one place.
14-1 14.1 Sane as above, in two places.
O
Renewal Application
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Demonstration and Conditions for License SNM-778 V
Revision 1 Amendment 0 Page 4 Instruction Sheet Renewal Application Denonstration and Conditions for License SNM-778 Revision 1 Amendment 0 Take Out Pages Put In Pages Page Rev Date Page Rev Date 1-4 0
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testing of nodels, devices, equipment, naterials and processes.
The administration of licensed naterial, internally or externally, to human beings is not included in this definition.
1.6.6 Safety Audit Subconmittee (SAS) means the subcommittee established under the SRC to perform audit functions, 1.6.7 Manager, Lynchburg Technical Operations neans the Manager of Technical Operations for the Lynchburg Research Center.
1.6.8 Qualified Person means a person who is assigned by his supervisor to work in an area where licensed material is handled and who is familiar with the hazards in the area. A qualified person nay also be referred to as a Category A Person, i
1.6.9 Authorized User means a person who may work with licensed naterial unsupervised and may supervise others, not so designated, in the handling of licensed material.
1.6.10 Calibration means a conparison of a neasurement standard of known accuracy with another standard or instrument to detect, correlate or adjust any variation in the accuracy of the iten being con-pared. Calibration also includes standardization.
1.6.11 Standardization neans, the act of using standards which are x
traceable to the NBS, a nationally accepted measurement system, or natural phenonena to set up an instrument. Standardization must be performed before and after use.
1.6.12 Unit means (1) a separate laboratory, room, or work area; (2) a transfer cart where SNM is separated from adjacent units by at least 8-inches edge-to-edge and 24-inches center-to-center. More than one unit may be on a cart provided the preceding edge-to-edge and center-to-center values are naintained, and (3) a processing bench, glove box, furnace, fume hood, or other similar process equipment or container separated from adjacent units by at least 8-inches edge-to-edge and 24-inches center-to-center.
1.7 AUTHORIZED ACTIVITIES 1.7.1 Licensed na'.erial shall be used in the performance of Research and Develo pment.
1.7.2 The LRC may deliver licensed material to a carrier for transport in accordance with the regulations in 10 CFR 71 and 49 CFR.
License No SNM 778 Docket No.70-824 Date February,1980 O
I I~4 Amendment No.
Revision No.
Page Babcock &Wilcox a McDermott company
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2.0 GENERAL ORGANIZATIONAL AND ADMINISTRATIVE RE0lllREMENTS 2.1 POLICY It shall be the policy of the LRC 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 Manager, Lynchburg Technical Operations - The Manager, Lynchburg Technical Operations is ultimately responsible for all safety at I
the LRC.
2.2.2 Laboratory Managers - The Laboratory Managers are responsible for the safety of personnel in their laboratories. The Laboratory Managers report to the Manager, Lynchburg Technical Operations.
l 2.2.3 Section Managers - Section Managers are responsible for the safe p
performance of projects under their purview. To this end, they are responsible for ensuring that personnel in their sections x
follow all applicable Area Operating Procedures. The Section Managers report to the Laboratory Managers.
2.2.4 Facility Supervisor - The Facility Supervisor is responsible to the Manager, Lynchburg Technical Operations for the safe conduct of all l
operations at the LRC and for ensuring that all applicable oper-ations are conducted in compliance with the license and applicable regulations. To fulfill these responsibilities the Facility Super-visor shall have the authority to stop any operation that he feels is unsafe or in violation of license. The Facility Supervisor has approval authority for all Area Operating Procedures and Radiation Work Permits. He shall submit itens for review to the SRC.
2.2.5 Manager, Safety and Licensing - The Manager, Safety and Licensing l
reports to the Manager, Lynchburg Technical Operations. The Supervisor, Health and Safety, the Accountability Specialist, and the License Administrator report to this nanager.
License No SNM 778 Dock t No. 70 824 Date February,1986 I
O 2-2 a>i.
l Babcock &Wilcox a McDermott company
V 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 Plan l
and industrial safety progran. He is responsible for health physics and industrial safety activities. The Supervisor, Health and Safety reports to the Manager, Safety and Licensing, and has direct access to the Manager, Lynchburg Technical Operations in l
l matters pertaining to Health and Safety. The Supervisor, Health and Safety has approval authority for all Area Operating Procedures and Radiation Work Pernits.
le shall conduct training programs for new employees and Authorized Users of Radioactive Material. He shall be responsible for the shipment of licensed material. He shall be a nenber of the SRC.
2.2.7 Health Physics Engineer - A Health Physics Engineer shall admints-l ter 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 Safety Officer - The Nuclear Safety Of ficer shall be responsible for ensuring that no operation at the LRC results in g
the inadvertent assembly of a critical nass. He shall have D) r approval authority for all Area Operating Procedures. He shall conduct training programs in criticality safety and perforn criticality safety calculations. He shall report to the Manager, Lynchburg Technical Operations.
2.2.10 License Adninistrator - The License Administrator shall be l
responsible for administering the license. He is the prinary liaison with the NFC and other federal, state, and local agencies in natters that pertain to nuclear activities. He shall be the coordinator of the SRC and the Safety Audit Subcomittee and shall represent nanagement 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, Lynchburg Technical Operations. He shall l
report to the Manager, Safety and Licensing.
2.2.11 Accountability Specialist - The Accountability Specialist shall be responsible for the maintenance and rett' tion of SNti accountability records. The Accountability Specialist all report to the Manager, Safety and Licensing.
License No SNM 778 Docket No.70-824 Date February,1986 I
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Revision No.
Page Amendment No.
Babcock &Wilcox a McDermott company
rx
'\\b 2.3 SAFETY REVIEW COMt11TTEE 2.3.1 Function 2.3.1.1 The SRC shall review and approve all Area Operating Procedures.
2.3.1.2 The SRC shall review and ap,1 rove new projects and najor changes to existing projects that utilize licensed materials.
2.3.1.3 The SRC shall review the annual report prepared by the Supervisor, Health and Safety.
2.3.1.4 The SRC shall provide the LRC with general consulting servi.es in the field of radiation protection and the safe handling of licensed material.
2.3.1.5 The SRC may approve an operation utilizing licensed material without written procedures, after reviewing the proposed operation.
2.3.2 Frequency of Meetings 2.3.2.1 The SRC shall meet at least four times annually for the purposes of conducting its business as specified in Section 2.3.1.
2.3.3 Safety Audit Subconnittee 2.3.3.1 The SAS shall perform audits of the LRC for the Safety Review Connittee.
2.3.3.2 The SAS shall audit facilities, procedures, records, and operations at the LRC for compliance with written requirenents and the exercise of acceptable safety practices.
2.3.3.3 The SAS shall perform at least three audits annually. At least one calendar month shall separate succeeding audits.
2.3.3.4 SAS nenbership shall be appointed by the Manager, Lynchburg i
Technical Operations.
2.3.4 Reporting 2.3.4.1 The SRC shall report to the Manager, Lynchburg Technical Operations.
2.3.4.2 The SAS shall report to the Chairman, SRC.
License No SNM 778 Docket No. 70 824 Date February,1986 b
O I
2-3 d
Amendment No.
Revision No.
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ph 2.3.5 Recordkeeping 2.3.5.1 Minutes of the SRC proceedings shall be prepared by the Chaiman, SRC.
2.3.5.2 SRC Minutes shall be forwarded to the Manager, Lynchburg Technical Operations by the Chairman, SRC.
2.3.5.3 The pemanent records of the SRC shall be kept by the SRC Coordinator.
2.3.5.4 SAS audit reports shall be prepared by the Chaiman, SAS.
2.3.5.5 SAS audit reports shall be forwarded to the Chaiman, SRC by the Chaiman, SAS.
2.3.5.6 SAS audit reports shall be forwarded to the Manager, Lynchburg Technical Operations by the Chaiman, SRC with coments, as he deems appropriate.
2.4 APPROVAL AUTHORITY FOR PERSONNEL SELECTION 2.4.1 The Manager, Lynchburg Technical Operations shall approve the pb personnel selected for safety-related positions specified in Section 2.2 of this Part. The Manager, Lynchburg Technical Operations is appointed by the R & D Division Vice President.
2.5 PERSONNEL EDUCATION AND EXPERIENCE REQUIREMENTS 2.5.1 Manager, Lynchburg Technical Operations - The Manager, Lynchburg l
Technical Operations shall be appointed in accordance with l
Company policy.
2.5.2 Laboratory Managers - The Laboratory Managers are appointed by the Manager, Lynchburg Technical Operations in accordance with Company l
policy.
2.5.3 Section Managers - The Section Managers shall have a BS degree and three years post graduate work or tquivalent experience in the pertinent technical field.
2.5.4 Facility Supervisor - The Facility Supervisor shall have a degree License No SNM 778 Docket No. 70 824 Date February,1986 O
I 2~4 Amendment No.
Revision No.
Pg Babcock &Wilcox a McDermott company
l l
k in his related work and three years experience, or five years experience in the use and handling of licensed material. He must demonstrate to nanagement proficiency in the application of good principles of radiation prot?ction, industrial safety, and nuclear safety as related to the activities at thr. LRC.
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 nust have four years experience and l
demonstrate proficiency in the application of radiation safety principles and be knowledgeable in fields related to radiation protection.
2.5.7 Health Physics Engineer - A Health Physics Engineer shall have a BS degree which shall include at least 20 quarter hours health physics related course work or the equivalent in work experience.
2.5.8 Industrial Safety Officer - The Industrial Safety Officer shall have at least one year's experience in radiation and industrial O
safety. He shall be familiar with the codes and requirenents of b
the Occupational Health and Safety Act of 1970 and the National Fire Protection Association.
2.5.9 Nuclear Safety Officer - The Nuclear 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 LRC activities or he must have one year's experience with nuclear criticality safety calculations sinilar to l
those associated with LRC activities if he has at least an additional two years' experience in nuclear reactor physics calculations.
2.5.10 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.
t.icones No SNM 778 Docket No.70-824 Date February,1986 i
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l 2.6 TRAINING 2.6.1 Program I - Each new employee shall receive training within thirty days of reporting to work. This training, denoted as Program I, l
provides an introduction to radioactivity and a thorough coverage of safety rules and procedures including emergency procedures.
2.6.2 Program II - New laboratory employees who will be working with licensed material shall be required to complete Program 11 training. Completion of this program requires passing a written examination. Parts of Program 11 may be waived by the Supervisor, Health and Safety for technical and scientific personnel already knowledgeable and experienced in working in radiation areas and with licensed material. However, such personnel nust pass the written examination required for Program II. Persons who complete this course may be designated as an Authorized User.
2.6.3 Retraining - Persons who are designated as Authorized Users shall be retrained annually. Satisfactory completion of the retraining shall be determined by passing a written examination.
' 2.6.4 Respiratory Protection Training - Training in respiratory protection techniques and equipment shall be required of all-employees before the use of such equipment will be permitted, f
Satisfactory completion of this training shall be determined by passing a written examination.
2.7 OPERATING PROCEDURES 2.7.1 Area Operating Procedures ( A0P) - Area Operating Procedures are facility procedures for the safe handling of licensed material.
A0P's contain the provisions to assure the safety of the operation with regard to Health Physics and Nuclear Criticality safety. Each A0P shall be approved by the Nuclear Safety Officer or his desig-nated alternate, the Supervisor, Health and Safety or his desig-nated alternate, the Facility Supervisor or his designated alternate, and the Safety Review Committee.
2.7.2 A0P's may be revised with the approval of the Nuclear Safety Officer or his designated alternate, the Supervisor, Pealth 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.
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2.7.3 A0P's shall be available in each operations area where they apply and shall be followed by operations personnel.
2.7.4 Distribution of new and revised procedures shall be nade in accordance with a document control systen which assures that the procedure nanuals contain only the nost current revision of the procedures.
2.7.5 A0P nanuals shall be reviewed annually by the Facility Supervisor to assure that the nanuals contain the most current revision of the procedures.
2.8 INTERNAL AUDITS AND INSPECTIONS 2.8.1 Nuclear Criticality Safety 2.8.1.1 The Nuclear Safety Officer or his designated alternate shall conduct internal audits of the LRC 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, Lynchburg l
Technical Operations within two weeks of completing the audit.
O The audit reports shall be forwarded to the Facility Supervisor d
and the License Administrator. The License Administrator shall be responsible for assuring that the appropria'te corrective actions are taken to address the audit findings'.
2.8.2 Health Physics 2.8.2.1 The Supervisor, Health and Safety ur his designatM al ternate shall conduct internal audits of the LRC 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 nade to the Manager, Lynchburg Technical Operations within two weeks of completing the audit. The audit reports shall be forwarded to the Manager, Lynchburg Technical Operations and the License Administrator. The License Adminis-trator shall be responsible for assuring the appropriate corrective actions are taken to address the audit findings.
2.8.3 General Safety and Compliance License No SNM 778 Docket No. 70 824 Date February,1986 I
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2.8.3.1 The SAS performs audits of general safety and compliance at the LRC. These audits shall be conducted three times annually with at least one calendar nonth separating succeeding audits.
The SAS shall include an audit of the Health and Safety Group at least once annually. Other areas of LRC operations shall be audited for compliance with written requirements and the exercise of accepta-ble safety practices. The Chairman, SAS shall file a report of the audit findings with the Chairman, SRC and with a copy to the License Administrator and the Facility Supervisor. The Chairman, SRC shall forward the report to the Manager, Lynchburg Technical 1
Operations with comments, as he deens 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 OF 0FF-NORMAL OCCURRENCES 2.9.1 License Administrator The Licer.2e Administrator shall investigate and report, when required, the following types of off-normal occurrences:
2.9.1.1 Excessive levels of radiation fron or contamination on packages upon receipt.
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v 2.9.1.2 Thefts, attempted thefts, 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 energency 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 February,1986
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3.0 RADIATION PROTECTION 3.1 SPECIAL ADMINISTRATIVE RE0UIREMENTS 3.1.1 Radiation Work Permits (RWP) 3.1.1.1 RWP's shall be issued whenever the activity is not covered by an Area Operating Procedure and personnel are likely to be exposed to levels of radiation or concentrations of radioactive naterial in excess of those specified in 10 CFR 20.
3.1.1.2 RWP's shall be approved by the Work Area Supervisor, Employee's Supervisor, Health Physics Supervisor, and the Facility Supervisor.
3.1.1.3 The RWP form shall specify levels of personnel exposure above which a documented ALARA evaluation shall be required. RWP's that re-quire a documented ALARA evaluation must, in addition to 3.1.1.2, be approved by the Manager, Lynchburg Techriical Operations.
l 3.1.1.4 RWP's shall be approved at a neeting of all the signators of the form.
3.1.1.5 The RWP forn shall provide space for entering the estimated exposures to the whole body, extremities, and for the job. These h'
are used to identify the areas of exposure concern and do not v
constitute an exposure goal or linit.
3.1.1.6 The RWP form shall provide space for the workers' supervisor to sign or initial, attesting that the workers have been instructed in the requirements of the RWP.
3.1.2 ALARA Policy The nanagement of the LRC is comitted to a policy of maintaining exposures as low as is reasonably achievable.
3.1.2.1 Employees shall be introduced to this policy during their initial training and shall be reinforced during the annual retraining of Authorized Users.
3.1.2.2 The ALARA policy shall be applied to Area Operating Procedures and RWP's during the approval process.
License No SNM 778 Docket No.70-824 '
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4.0 NUCLEAR CRITICALITY SAFETY l
4.1 SPECIAL ADMINISTRATIVE REOUIREMENTS i
4.1.1 Double Contingency Policy - The Double Contingency Policy as de-fined in the American National Standard ANSI / ANS-8.1-1983 shall be followed in establishing the basis for nuclear criticality safety of all operations.
i 4.1.2 Structural Integrity - Where structural integrity is necessary to provide assurance for nuclear criticality safety, the design and construction of those structures will be evaluated with due regard to load capacity and foreseeable abnormal loads, accidents, and deterioration.
4.1.3 Nuclear Criticality Safety Evaluation - All modifications or additions or both to any operation, system or equipment nust be approved by the Facility Supervisor.
It is the responsibility of the Facility Supervisor, in consultation with the Nuclear Safety Officer, to determine whether or not a nuclear criticality safety evaluation is required for the proposed nodification or addition.
i The Nuclear Safety Officer or a person designated by him shall provide any required evaluations, including calculational support.
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Nuclear safety evaluations shall be reviewed by a second indi-vidual, either the Nuclear Safety Officer or by a person with the n,
same mininum qualifications required for the Nuclear Safety Of ficer.
4.1.4 Posting - Each unit shall be posted with the limits cf SNH permitted in the unit.
4.1.5 Labeling - Each container containing greater than 0.5 grams of SNM shall be labeled to show the amount of element, the percent enrichment, when applicable, and the amount of fissile isotope.
This condition does not apply to irradiated SNM.
4.1.6 Compliance - Compliance with the nuclear criticality safety requirements shall be in accordance with written area operating procedures, reviewed and approved by the Facility Supervisor, the Supervisor, Health and Safety, the Nuclear Safety Officer, and the SRC.
In addition, the Nuclear Safety Officer will perforn a quarterly audit of compliance with nuclear criticality safety requirements and document same in writing to the Manager, Lynchburg l
Technical Operations.
License No SNM 778 Docket No.70-824 Date Februa ry,1986 CT 0
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11.0 ORGANIZATION AND PERSONNEL 11.1 LRC LINE ORGANIZATION The Manager, Lynchburg Technical Operations is responsible for all l
LRC operations. Two Laboratory Managers report to hin.
The Laboratory Managers are responsible for operations that fall within the areas of expertise encompassed by the sections under their control. Section Managers report to the Laboratory Managers and are responsible for the safe perfomance of projects under their purview.
Research and development perfomed at the Lynchburg Research Center may result in projects being perfomed by sections of different laboratories in the same building. For this reason, the Manager, l
Lynchburg Technical Operations has established the position of I
Facility Supervisor. He advises the Laboratory and Section fianagers in the safety aspects and the control of licensed material and coordinates the safety program within their areas. The Facility Supervisor utilizes the expertise of the Supervisor, Health and Safety, the Nuclear Safety Officer, the Accountability Specialist, and the Industrial Safety Officer to ensure the safety of operations perfomed at the LRC.
3 Figure 11-1 shows th'e LRC Line Organization and Figure 11-2 shows (V
the safety organization.
11.2 LRC SAFETY ORGANIZATION 11.2.1 Manager, Safety and Licensing - The Manager of Safety and Licensing is appointed by and reports to the fianager Lynchburg Technical l
Operations. He is responsible for the proper management of the naterials accounting function, licensing function, and the Health and Safety Group. He manages the allotment of funds and other resourses and assures the proper assignment of personnel priorities. The Supervisor, Health and Safety, Accountability Specialist and License Administrator, report to hin.
11.2.2 Supervisor, Health and Safety - The Supervisor of Health and Safety is appointed by the Manager, Lynchburg Technical Operations and I
reports to the Manager, Safety and Licensing, but nay have direct access to the Manager, Lynchburg Technical Operations in natters l
concerning Health and Safety.
The Supervisor directs the overall License No SNM 778 Docket No.70-824 Date February,1986 A
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O Cf3 operation of the Health and Safety Group and the Industrial Safety Officer. He also serves on the Safety Review Comnittee. He has the authority to stop any operation that he believes is contrary to accepted safety practices, or license requirements. The Supervisor has overall responsibility for the shipment and receipt of licensed material and exercises signature authority on all Area Operating Procedures. He performs audits of the LRC for compliance with Health and Safety rules. The Health Physics Engineer and Industrial Safety Officer report to him.
11.2.3 Health Physics Engineer - A 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.
Adninistering the respiratory protection progran 4
Administering the bioassay program 5.
Leak testing radioactive sources 6.
Supervising shipping and receiving of licensed material 7.
Supervising and coordinating the waste disposal program d.
Assisting in personnel, equipment, and facility decontanination 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.
11.2.4 Industrial Safety Officer - The Industrial Safety Officer reports to the Supervisor, Health and Safety. His responsibilities include the following:
License No SNM 778 Docket No.70-824 Date February,1986 O
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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.
Perfoming tests, maintenance, and inspection of fire protection, control, and extinguishing equipment 5.
Providing training for the LRC Fire and Rescue Team and off site support agencies 6.
Inspecting all areas of the LRC periodically to ensure:
a.
Proper storage and use of flamable solvents b.
Proper platenent of fire extinguishing equipment c.
Elimination of fire hazards d.
Reduction, to the extent practicable, of the accunulation of flamable materials O
e.
Proper use and maintenance of electrical equipment.
V 7.
Working with supervisors to fomulate safety rules and elini-nation of hazards 8.
Investigation of all personnel injuries 9.
Keeping nanagement informed concerning industrial safety activities
- 10.
Conducting industrial safety training.
11.2.5 Accountability Specialist - The Accountability Spe:ialist reports to the Manager, Safety and Licensing. He is responsible for the maintenance and retention of SftM accountability records. He prepares and transmits the reports required by regulation to infom regulatory agencies of Silti transactions.
l 11.2.6 License Adninistrator - The License Administrator reports to the l
Manager, Safety and Licensing. The License Adninistrator is i
responsible for administering the license. He is the primary l
Liceme No SNM 778 Docket No.70-824 DateFebrua ry,1986 Amendment No.
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liaison between the LRC and the NRC and other federal, state, and local agencies regarding nuclear matters. He is the coordinator of the Safety Review Comittee and Chairman of the Safety Audit Sub-comittee and represents LRC 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 activities.
11.2.7 Nuclear Safety Officer - The Nuclear Safety Officer is appointed by and reports to the Manager, Lynchburg Technical Operaticns. The l
Nuclear Safety Officer is responsible for ensuring that no operation at the LRC can lead to the inadvertent 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 deens them necessary, and carries out confirming nuclear criticality safety calculations.
The Nuclear Safety Officer will inspect all LRC operations where special nuclear material is being processed, quarterly. Other areas nay be inspected less frequently but all licensed facilities will be inspected at least twice a ys He will consider area operations when scheduling these inspi. tons and will, if neces-sary, schedule his inspection at more frequent intervals. His consideration should include inspection of new operations, an audit
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of nuclear safety records, a check for area posting and a review of current practices. He shall subnit a report of his finding to the Manager, Lynchburg Technical Operations, 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.
Recomendations.
11.2.8 Facility Supervisor - The Facility Superviser is appointed by and reports to the Manager, Lynchburg Technical Operations. He shall be responsible to the Manager, Lynchburg Technical Operations for l
License No SNM 778 Docket No.70-824 Date February,1986 Amendment No.
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C the safe conduct of all operations at the LRC and for ensuring l
l that these operations are conducted in accordance with all license conditions. The Facility Supervisor shall review and have approval l
authority for Area Operating Procedures. He shall have authority l
to teminate any operation that he deems contrary to license con-ditions, Area Operating Procedures, or general safety conditions.
l The Facility Supervisor shall become familiar with all license conditions and procedures concerned with radiation safety, nuclear j
safety, industrial safety, and nuclear materials safeguards. He nay consult with the following personnel to ensure compliance with all safety regulations and principles:
l Supervisor, Health and Safety 1
Nuclear Safety Officer l
Industrial Safety Officer Accountability Specialist 11.2.9 Safety Review Comittee - The Safety Review Comittee (SRC) shall be comprised of at least five technically trained and experienced nenbers appointed by the Manager, Lynchburg Technical Operations.
One nenber shall be selected by the Manager, Lynchburg Technical h
Operations to be the SRC Chaiman.
The Chaiman shall preside at j
V the neetings and keep thc! ninutes.
The Manager Lynchburg Techni-cal Operations shall appoint an Alternate Chaiman who shall act j
for the Chairman during absences. One nenber shall be appointed by t
l the fianager, Lynchburg Technical Operations to be the SRC l
Coordinator. The Coordinator shall represent LRC nanagement on the SRC, set the meeting agenda, and naintains the pemanent files of the Committee.
The SRC membership 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 LRC operations.
Consultants with special expertise are available to the Comittee l
when needed.
The SRC shall neet at least four times a year. A quorum shall l
consist of a simple majority of the nenbership including the Chaiman. The SRC shall review and approve all Area Operating i
l Procedures.
It shall review and approve new projects that utilize License No SNM 778 Docket No.70-824 Date Februa ry,1986 11-5 Amendment No.
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licensed material that are significantly different from previously
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reviewed and approved projects. The SRC shall review the annual report issued by the Supervisor, Health and Safety which sunmarizes LRC personnel exposures, environmental releases, and a sunmary of the ALARA progran accomplishments. The SRC Chairman shall forward the Committee minutes to the Manager, Lynchburg Technical Oper-ations, with a copy to the SRC Coordinator.
The Manager, Lynchburg Technical Operations 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 Chaiman and he shall report to the Chaiman, SRC.
The SAS shall audit operations at the LRC at leist three times annually, with successive audits separated by at least two nonths.
Additional audits may be perfomed at any time. The SAS Chaiman shall develop the audit report and submit it to the SRC Chalman.
The SRC Chaiman shall submit the audit report to the Manager, Lynchburg Technical Operations with appropriate coments, with a copy to the License Administrator.
11.3 EDUCATION AND EXPERIENCE OF KEY PERSONNEL 11.3.1 Safety and Licensing Manager - Richard L. Bennett GV Education:
B.Ch.E. - Chemical Engineering, University of Delaware, 1958 Experience:
(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 Decomissioning, Lynchburg Research Center, Lynchburg, Virginia He was responsible for decontaninating facilities that were used for preparation of experimental quantities of nuclear fuels containing plutonium.
License No SNM 778 Docket No.70-824 DeteFebruary, 1986 Amendment No.
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(1973-1982)
Babcock & Wilcox, Supervisor, Process Technology Group, t,ynchourg Research Center, Lynchburg, v
Virginia 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 methods 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 BAW wastes.
(1959-1971)
Merican Cyanamid Company, Process Engineer, Piney River, Virginia He has had broad experience in chemical engineering. This includes research and developnent, designing equipment and processes, testing and operating new equipment, pilot plant operation, process engineering, and economic evaluation. He has specific knowledge in pigment nanuf acture, effluent treatment, and byproduct recovery.
Professional Affiliations:
American Institute of Chemical Engineers (Menber)
American Nuclear Society (Member) 11.3.2 Health and Safety Supervisor - John W. Cure, III Education:
B. S. - Electrical Engineering, Virginia tillitary Institute,1952 M. S. - Physics, Vanderbilt University,1956
- AEC-Sponsored Radiological Physics Fellowship, 1952-54 License No SNM 778 Docket No.70-824 Date Februa ry,1986 Amendment No.
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(in conjunction with Vanderbilt University and Oak Ridge d
National Laboratory) l l
- Nuclear Safety Training Course, Oak Ridge,1957
- Certified Health Physicist, Anerican Board of Health l
Physics, 1961 l
- In-Place filter Testing, Harvard,1976 Experience:
(1956-Present)
Babcock & Wilcox, Supervisor, Health and Safety, Lynchburg Research Center, Lynchburg, Virginia Mr. Cure established the Health Physics Progran at BAW's Critical Experiment Laboratory, which is now Building A, at the Lynchburg Research Center. This program was expanded as the nuclear activities at the Center grew.
In 1972 this progran provided health physics coverage for four critical experiment reactors, a one-megawatt pool-type research reactor, a six-megawatt test reactor, hot cells, a radiochemistry laboratory, and uranium, thorium, and plutonium fuel laboratories. The Health and Safety Group, in addition to providing operational surveillance, is responsible for the solid waste disposal program, shipping and receipt of radioactive materials, liquid waste disposal progran, and environnental surveillance. This group is responsible for e
administering the bioassay progran, implementing the respiratory
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protection program and maintairng the personnel exposure records system. At the present time tb Health and Safety Group consists of three health physics engineers, three technicians, and the survey monitors associated with two decommissioning projects.
Mr. Cure also provides calculation.i support for the Health and Safety Group.
Mr. Cure is also responsible for Industrial Safety which includes compliance with the regulations of the Occupational Health and Safety Administration, administering the fire prevention and fire protection programs, and enforcing the safety standards of the Company's insurance underwriters.
Mr. Cure serves on the LRC's Safety Review Comittee and the Safety Comittee at the Alliance Research Center. He has served on the Radiation Safety Committee at the Virginia Polytechnic Institute and State University.
In 1973, he was a'nember of the Oak Ridge National Laboratories Applied Health Physics Mvisory Comittee. He has taught fornal courses in health physics and License No SNM 778 Docket No.70-824 Date Februa ry,1986 Amendment No.
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radiation safety in BAW educational prograns such as that D
provided for the N.S. Savannah deck officers (first and second l
crews), CAMEN research reactor operators, and operator training for Arkansas Power and Light Company, Sacranento Municipal Utility District, Florida Power Company, Metropolitan Edison Power Company and Toledo Edison Power Company.
(1954-1956)
U. S. Air Force, Kirtland Air Force Base, 1
New Mexico Mr. Cure was a nuclear research officer. He participated as a l
health physicist during operation " Tea Pot."
(1953-1954)
Junior Health Physicist, Oak Ridge National l
Laboratory, Junior Health Physicist, Oak Ridge, Tennessee Mr. Cure was employed as a junior health physicist at the Oak Ridge National Laboratory and received experience in the design and testing of new instruments and also in field work.
l Professional Affiliations:
American Nuclear Society (Menber)
Health Physics Society (Member)
(q!
Subcomittee on Internal Dosinetry Working Comittee - 1972-75 Virginia Health Physics Society - President, 1975-76, 1981-82
- Councilman, 1976-77 American Industrial Hygiene Association Virginia Manufacturers Association, Water and Air Control Com.
I Virginia Safety Association - Board of Directors 11.3.3 Health Physics Engineer - W. Scott Pennington Education:
B.S. - Biology with an option in Health Physics, Virginia Polytechnic Institute and State University,1978 Experience:
(1979-Present)
Babcock & Wilcox, Senior Health Physicist, Lynchburg Research Center, Lynchburg, Virginia Mr. Pennington administers the LRC's health physics progran. The License No SNM 778 Docket No.70-824 Date Februa ry,1986 O
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program includes the rmasurement and control of the external
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U exposure, internal exposure, environnental sanpling, the respiratory protection program, the solid waste disposal program, the liquid waste disposal program, and providing radiation and centamination surveillance for the Center's decomissioning p roj ects. He provides expertise in radiation safety to project engineers. He implements the bioassay (in vivo and in vitro) program. He has approval authority for radiation work permits, facility work orders, and area operating procedures, in the absence of the Supervisor, Health and Safety.
(1978-1979)
Southwest Research Institute Environmental Science Technician, Environmental Science Department, Houston, Texas Mr. Pennington was involved in a study for the* Bureau of 1.and Managerent of off-shore oil platforms in the Gulf of Mexico, and studies for the Houston Lighting and Power Company on thermal pollution and comercial fish survivability.
Professional Affiliation:
Health Physics Society (Member)
Virginia Health Physics Society (Member)
American Nuclear Society (Member) 11.3.4 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 4 Advanced First Aid, American Red Cross
- Training in the following areas:
Industrial Safety Fire Fighting Rescue Extrication Fire Protection Fire Extinguishing Equipment and Materials Arson Investigation.
Experience:
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t (1972-Present)
Babcock & Wilcox, Industrial Safety Officer, i
V Lynchburg Research Center, Lynchburg, Virginia l
Hr. Spradlin is the LRC's Industrial Safety Officer. As such he is I
responsible for compliance with the regulations of the Occupational i
Health and Safety Adninistration. He advises the LRC on the standards and requirements of the National Fire Protection Assoc 1-ation and perfoms reviews of equipment and systens for compliance l
with NF/A standards. He perfoms inspections of facilities and l
equipment for fire protection purposes. He reviews facility l
changes and modifications to ensure fire safety. Mr. Spradlin l
perfoms tests, maintenance, and inspection of fire protection, control and extinguishing equipment. He is responsible for investi-gating all accidents, and keeping his management inforned of safety activities. He perfoms fire and rescue training for the menbers t
l of the LRC's Fire and Rescue Team, and serves as the Captain of the team. He is a certified Shock Trauma Technician, an Energency Medical Technician, and certified instructor in CPR and Standard i
and Advanced First Aid.
l l
(1971-1972)
Babcock & Wilcox, Accountability Technician, l
Lynchburg Research Center, Lynchburg, Virginia Mr. Spradlin served as the Accountability Technician, in this capacity he was responsible for the recordkeeping systen for SNM O
accountability in the Plutonium Development Laboratory. He l
recorded all transfers of SNM, perfomed inventories, and updated the unit log records.
(1969-1971)
Babcock A Wilcox, Health Physics Technician, Lynchburg Research Center, Lynchburg, Virginia Mr. Spradlin was a health physics technician in the Plutonf un.
Development Laboratory. He was responsible for perfoming contamination surveys of the facility, assisting in the nonitoring of bagging operations, and supervising decontamination. He implemented the surveillanace progran for airborne radioactive naterial. He perfomed maintenance, testing, and calibration of alpha particle survey instrumentation and counting equipment.
He implemented the respiratory protection progran in that laboratory.
(1967-1969)
Babcock & Wilcox, Plant Engineering Technician, Lynchburg Research Center, Lynchburg, Virginia License No SNM.778 Docket No. 70 824 Date Februa ry,1986 11-11 Amendment No.
O Revision No.
I Page Babcock &Wilcox a McDermott company
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As a plant engineering technician, fir. Spradlin performed installation, modification, and repair of facilities, equipment, and experirrental apparatus at the LRC. He performed these duties on electrical, nechanical 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 nachine operation, Millwright, Maintenance Forenan, Maintenance Superintendent, Safety Inspector and Accident Investigator.
Professional A'filiations:
Concord Rescue Squad - Founding President American Heart Association - Cardiac Care Comittee 11.3.5 Accountability Specialist - Kenneth 0. Long Education:
Graduate - White Sulphur Springs High School,1958 Certificate - Bookkeeping, Central Virginia Comunity College,1981 i
Experience:
(1974-Present)
Babcock A Wilcox, Accountability Specialist Lynchburg Research Certer, Lynchburg, Virginia Mr. Long, as the Accountability Specialist, is responsible to the
!!anager of Safety and Licensing for the accurate accounting of all Special fluclear, Source, and Byproduct material at the LRC.
He is responsible for recording all transfers of Stift that are made within the LRC and for preparing the reports and records of of f site transfers. He prepares all flRC/00E 741 Transaction forms. He is responsible for the timely completion of inventories of licensed naterial.
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 00E and 000 documents at the LRC. He is also an authorized classifier and an authorized courier of classified naterial.
License No SNM 778 Docket No.
70 824 Date February,198f I
11-12 O
Revision No.
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La Babcock & Wilcox A Mc Dettnott t emp,iny
O' (1970-1974)
Babcock & Wilcox, Shipping & Receiving Clerk Lynchburg Research Center, Lynchburg, Virginia Mr. Long was responsible for the shipment and recejpt of all naterials 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 itens that are l
l required for operation of a research and development laboratory, j
l (1967-1970)
Babcock A Wilcox, Technician f
Lynchburg Research Center, Lynchburg, Virginia 1
l Mr. Long was a technician in the Plutonium Developnent Laboratory during this period. He performed chemical operations utilizing l
l uranium and plutonium materials and was responsible for the l
accountability of SNM materials into and out of his area.
Professional Affiliations:
Institute of Nuclear Materials Management (Senior Member)
Nuclear Materials Control Comittee, BAW ( Secretary)
American Nuclear Society, Virginia Chapter (Henber) l l
11.3.6 License Administrator - Arne F. Olsen L
Facility Supervisor
- Arne F. Olsen l
t i
l Education:
AAS - Nuclear Technology, Central Virginia Comunity College,1978 Experience:
[
(1972-Present)
Babcock A Wilcox, Senior License Mninistrator and i
Facility Supervisor, Lynchburg Research Center, Lynchburg, Virginia l
l Mr. Olsen is responsible for preparing, amending, and administering the licenses that the LRC possesses with the NRC and the Comon-l wealth of Virginia. He acts as the primary liaison between the LRC l
andtheNRCandotherfederal, state,andlocalagenciesregarding l
nuclear matters. He coordinates the visits nade by the NRC s Of fice of Inspection and Enforcement, and conrdinates the LRC's compliance with NRC and state regulations and the licenses. He is the coordinator of the Safety Review Comittee and is Chairman of L
License No SNM 778 Docket No.70-824 Date February,19M, II"I3 Amendment No.
O Moviolon No.
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l Babcock &Wilcox i
a MDermott tempany l
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n i
I the Safety Audit Subcomittee, and represents LRC nanagement on both. Mr. Olsen is the Facility Supervisor and as such is s
responsible to the hnager, Lynchburg Technical Operations for the l
safety of all operations at the LRC.
Mr. Olsen is the Alternate LRC Security Officer, Alternate Energency Of ficer and an internal auditor.
(1968-1972)
Babcock A 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 inplementation of the Health Physics Progran in the Plutonium Development Laboratory.
This responsibility included the inplementation of the snearing, survey, air sampling, environmental sanpling, and waste disposal programs.
(1964-1968)
Babcock & Wilcox, Technician and Shif t Leader, Babcock A Wilcox Test Reactor, Lynchburg Research Center, Lynchburg, Virginia Mr. Olsen possessed a Senior Reactor Operator's License for the RAWTR. He was in charge on one of four shifts of reactor operators 70 charged with the proper operation and naintenance of the BAWTR. He
(
)
supervised the loading and unloading of fuel and experiments in the reactor and kept all required records of operations and naintenance perforned 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 naintenance of all electrical equipnent serving one of the reactor plants aboard the Enterprise.
Professional Affiliation:
Health Physics Society (Member)
Site Environnental Comittee, RAW (Henber) 11.3.7 Nuclear Safety Of ficer - Francis M. Alcorn Education:
License No SNM 778 Docket No. 70 824 Date February,1986
(
Amendment No.
Hevhlon No.
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Pap L,'
Babcock & Wilcox
.e M( Dermott comp.,rty
I B.S.
- Nuclear Engineering, North Carolina State College,1957 D
M.B.A - Busir,ess Administration, Lynchburg College,1974
- Graduate study in Nuclear Engineering, University of l
Virginia l
Experience:
(1971-Present)
Babcock 4 Wilcox, Supervisor, Nuclear Criticality l
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 l'
for criticality evaluations, does criticality calculations, l
performs nuclear safety audits, and gives assistance to the various divisions df the Company and the Company's customers in 1
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, i
l (1969-1971)
Babcock & Wilcox, Criticality Specialist, Nuclear l
Safety Engineer, Lynchburg Research Center, Lynchburg, Virginia Transferred to the LRC as Nuclear Criticality Safety Specialist I
for Babcock & Wilcox's Naval Nuclear Fuel Plant, C w ercial Nuclear Fuel Plant, and the LRC. He was appointed lluclear Safety Officer for the LRC.
(1964-1969)
Babcock & Wilcox, Power Generation Division,'
Lynchburg, Virginia Mr. Alcorn was a physicist in the PWR Development Section and was t
responsible for deternining the most economical nethod for i
utilizing plutonium as a recycle fuel in BAW's pressurized water l
reactor concepts.
In addition, he was Nuclear Criticality Safety l
Advisor to the Company's Naval Nuclear Fuel Division.
(1961-1964)
Babcock & Wilcox, Nuclear Power Generation Division I
Lynchburg, Virginia 1
He has been concerned with core neutron physics analysis and i
l design of the Consolidated Edison Reactor, the Liquid Metal Fuel Reactor, the Babcock & Wilcox Test Reactor, the Advanced Test 1
i License No SNM 778 Docket No.70-824 Date February,1986 i
I 11-15 O
Revision No.
Page Amendment No.
l l
Babcock & Wilcox a WDermott company
O Reactor, the Heavy Water-Organic Cooled Reactor Concept, and v
Babcock & Wilcox Pressurized Water Reactor Concepts. He developed methods for and performed calculations for criticality, fuel depletion, nuclear safety coefficients, power profiles, nuclear fuel costs and critical experiment analysis. He has also worked in the areas of kinetic safety analysis.
(1957-1960)
Babcock & Wilcox, Atomic Energy Division Lynchburg, Virginia He functioned as a nuclear engineer doing both core neutron physics and shielding calculations.
(1960-1961)
General Nuclear Engineering Cnrporation, Staff Physicist Mr. Alcorn engaged in core neutron physics design and analysis of the Boiling Nuclear Superheat Reactor. He also wrote physics articles for Power Reactor Technology which were published by GNEC for the AEC.
Professional Affiliations:
Sigma Pi Sigma (Member)
Tau Beta Pi (Member)
O American Nuclear Society - Past Chairman of ANS Nuclear Criticality Safety Division
- Member Standards Subcomittee ANS-8.
11.4 OPERATING PROCEDURES 11.4.1 Area Operating Procedures ( A0P) - Area Operating Procedures are prepared ay any technically competent person.
The proposed pro-cedure is delivered to the Facility Supervisor who ensures that the procedure is in the proper format. The Facility Supervisor routes tne procedure to the Nuclear Safety Officer who reviews it to assure that any nuclear criticality safety issues are properly addressed.
If the Nuclear Safety Officer (NS0) has additions or corrections, he notes them on the procedure and forwards it to the Supervisor, Health and Safety ( S.H&S).
If the NSO approves it, he signs the procedure in the space provided and forwards it to the S.H&S. The S.H&S reviews it for proper radiological and industrial safety content.
If he has additions or corrections, he notes then License No SNM 778 Docket No. 70 824 Date February,1986 Amendment No.
O Revision No, I
Page 11-16 Babcock &Wilcox a McDermott company
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on the procedure and forwards it to the Facility Supervisor.
If the S.H&S approves the procedure, he signs the procedure in the space provided and forwards it to the Facility Supervisor. The Facility Supervisor reviews it for general safety and determines its inpact on other work and facilities. The Facility Superviser is responsible for resolving all additions or changes reconmended by the previous reviewers. When the procedure is approved by the three reviewers, the Facility Supervisor forwards it to the Safety Review Connittee.
The Safety Review Committee (SRC) may approve the procedure as written, approve the procedure conditionally with specific changes to be made prior to issuance or the SRC can dis-approve it. The SRC coordinator signs for the SRC when approval is voted. The procedure may be inplemented subsequent to SRC
, approval.
Revisions to A0P's will follow this same approval route, except that the revised procedure may be implemented af ter receiving the approval signatures of the NSO, S.HAS and the Facility Supervisor.
The revised procedure will be placed on the agenda for the next regularly scheduled meeting of the SRC.
A0P's are entered in 3-ring binder manuals.
11.4.2 Availability Manuals are issued to individual workers and placed in areas where the procedures apply.
11.5 TRAIN!NC 11.5.1 General Radiation Protection Training The LRC provides two training prograns covering the nature, use and control of radiation, and radioactivity. These courses are pre-sented to ensure that all LRC personnel receive training appropri-ate 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 proper background and technical base to 1110w workers to understand the principles of radiation safety.
The Health and Safety Group administers the cuurse and, in general, teaches each course. Where practical, basic general procedures and federal regulations are included and discussed.
Training aide, such as motion pictures and self-study materials, are used as appropriate.
License No SNM 778 Docket No.70-824 Date February,198f
/9 Amendment No.
O Revision No.
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Babcock & Wilcox a McDermott comp.iny
l Program I is intended for new enployees who will be scheduled for such training within 30 days of reporting to work at the LRC.
Progran II is intended for personnel working with radioactive materials. Personnel selected by their section nanager to be an Authorized User (Section 1.6) of radioactive materials (i.e.,
enployees who may handle licensed material unsupervised, health physics technicians, etc.) will be scheduled for these courses.
Personnel will not be permitted to work unsupervised with licensed l
naterial until they are trained in radiation protection and criticality safety and designated an Authorized User. Retraining
~l of Authorized Users of radioactive naterials is perforned annually.
Workers who are exposed to ionizing radiation are classified as radiation workers and will receive training connensurate with their exposure as required by Title 10, Code of Federal Regulations, Part 19 (10 CFR 19). This training will include Progran 11 as l
necessa ry.
Training in area operating procedures and special area procedures is the responsibility of the line supervisor. This training should be accompanied with appropriate fornal and on-the-job training as I
the job requirements dictate.
11.5.2 Program I This course is available to new office employees and is presented l
to employees within 30 days of reporting to work at the LRC.
It provides an introduction to radiation and radioactivity (under-l standable to the enployee with no technical education or experi.
ence) and a thorough coverage of safety rules and procedures, i
including the site energency procedures. Subjects include types of radiation, radiation effects on humans, permissible levels, basic health physics rules, a history of radiation protection, and personal hygiene.
l 11.5.3 Progran 11 New laboratory employees who work with radioactive materials are l
required to complete this course and pass a written test. Subjects include the following:
1.
Radioactivity a.
Types of radiation License No SNM 778 Docket No.70-824 Date February,1986 O
I II~IN Amendment No.
Revision No.
Pm Babcock & Wilcox a McDermott company
b.
Radioactive decay c.
Radiation dose and dose rates d.
Exposure control methods - time, distance, shielding e.
External and internal exposure hazards f.
Respiratory protection 9
The importance of maintaining exposures as low as is reasonably achievable (ALARA) h.
Risks from radiation exposure including exposure of females and the embryo / fetus 1.
Radiation exposure compared to other hazards in the work place.
2.
Health Physics Instruments a.
Personnel monitoring devices b.
Cutie pie and Geiger-ftueller counter c.
Alpha survey meter d.
Air monitors e.
Criticality alarm system f.
Emergency equipment g.
Instructions in field use of instruments.
3.
Regulations and Procedures a.
Code of Federal Regulations (including 10 CFR 19) b.
License requirements c.
Shipment of radioactive materials d.
Waste disposal License No SNM 778 Docket No.70-824 Date February,1986 O
I II~I9 Amendment No.
Revision No.
Pe Babcock & Wilcox A McDermott comp.wiy
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i e.
Internal procedures.
l Parts of Progran 11 nay be waived as appropriate for technical and scientific personnel already knowledgeable and experienced in l
working in radiation areas and with licensed naterial. However, i
such personnel must pass the written examination required for Program !!.
11.5.4 Respiratory Protection Training i
Training in respiratory protection techniques will be required of all employees before the use of such equipment will be allowed.
This training will be carried out by a qualified individual, as defined in NUREG-0041 (Section 12.1), who will document that such training as been completed. Those persons who direct the work of employees using respiratory protection will be included in the training courses. Periodic retraining will be scheduled, at the discretion of the qualified individual, to ensure that a high degree of employee proficiency in the use of respiratory protective devices is maintained.
Training in respiratory protection shall include the following l
subjects:
a.
Discussion of the airborne contaminants present in the work
\\
environnent including their physical properties, physiological actions, toxicity, means of detection, and maximun permissible concentrations (MPC's).
b.
Discussion of the importance of selecting the proper respirator based on the hazard and the dangers of using respirators for a purpose other than that intended.
l c.
Discussion of the construction, operating principles, and limitations of the available respirators.
l d.
Olscussion of the use of engineering controls as a substitute for respiratory protection and the need to make every reason-l able effort to reduce or eliminate the need for respiratory l
protection.
e.
Instruction in methods to be used to determine that the l
respirator is in proper working order.
l l
I License No SNM 778 Docket No.70-824 Date February,1986 Amendment No.
O Revision No.
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A RDermott comp.my
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Instruction in fitting the respirator properly, field testing for proper fit, and factors that may influence a proper fit.
1- -
g.
Instructions in the proper use and maintenance of the respirator.
h.
Discussion of the uses of various cartridges and canisters available for air-purifying respirators.
1.
Review of radiation and contanination hazards, including a review of other protective equipment that may be used with respirators.
j.
Instruction in energency actions to be taken in the event of respirator nalfunction, k.
Classroom instruction to recognize and cope with energency situations while working with a respirator.
1.
Any additional training as needed for special use, n.
The wearer nust pass a written examination on the material presented on respiratory protection.
)
11.6 FACILITY CHANGE Changes and nodifications to buildings, exhaust ventilation systens, gas supply systems, energency electrical systems, etc. are requested on Forn LRC-229 " Facilities Work Order Forn" (Figure 9 4). All work orders are forwarded to the nalntenance supervisor.
The Plant Engineering Supervisor determines if the request involves a facility change.
If a facility change is involved, the work order is forwarded to the Facility Supervisor.
It is the Facility Super.
visor's responsibility to determine that all safety and licensing considerations have been addressed and if the request must be approved by the Safety Review Connittee.
Space is provided on the form for the approval signatures of the Supervisor, Health and Safety, the Industrial Safety Of ficer, and the Facility Supervisor.
Completed forms are kept on file by the maintenance supervisor and are audited once a month by the Health Physics Group.
License No SNM.778 Docket No.
70 824 Date February,10%
O I
p,9,11 21 (O
Amendment No.
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Babcock & Wilcox m omion u>,
'l FIGURE 11-1 LRC LINE ORGANIZATION RESEARCH AND DEVELOPMtNT DIVillON VICE PREllDENT LYNCH 8URO RtttARCH CLNTER SPECI AL PROJECTS /
LYNCH 8URO TECHNICAL OPE R ATIONS DECOMMISSIONING MANAGER MANAhtR Of COMMISSIONING
~ ~ ~ ~ ~ ~ ~ ~
PURCHA31NG PURCHASING MANAGER R&DO LRC MANAGER MANAGER SAFETY ANO ACCOUNilNo UCENSING CONTROLLER AND R&DO ADMIN STRATIVE MANAQtR SERVICt3
=
/
LRC m,/
MANAGER SYSitMS PACILiff tS Otyt LOPME N T AND FACILititt LAnoRAfoRy OUALITY LRC ASSURANCE
=
R&DD MANAOIR MANA0tR MANAGER l
OU A LITY OUALifY MAf t RI ALS ASSURANCg ASSUR ANC E g qq:qq g giqq R&DD LRC LAs0RAf0Rf MANAcfR ADMINIS TR A f 0R g,ggng, SCit N filf
= = ~lNDICAf t$ FUNCTIONAL REPORflNO LICente No SNM 778 Docket No.
70 824 Date February,1986 O
I II"22
("}
Amendment No.
devision No.
Pap s
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Babcock & Wilcox A % DMmott (ompany
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FIGURE 11-2 LMC SAFETY OMGANIZATION e,
LYteCMeURG RESEARCH CENTER LY9fCMSURO TECMeetCAL OPERATIOest heAssA40R SAFETY REVIEW Condael7788 4
1 1
PACILITY SUPtRVis04 SAPtTV ANO LICS8864004 l
8eUCL8 AR SA7 ETV l
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knANAceR I
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I L8CGfeel#4 NGALTH A8ec SAFETV ACCOUNTASILifV A0essestSTRATOR SUPT RVit0A 9PtCIAll8T Nt ALTH PHY$lCS INDU$fRfAL STAfP 4ArgTV
= = = lfectCAf R$ PUNCfl0esAL RtronflNo License No SNM 778 Docket No. 70824 Date Februa ry,1986 i
Amendment No.
O Movklon No.
I 11-23 Pm t
Babcock & Wilcox 4 McDermott company w
I i
and the words CAUTION - AIRBORNE RADIOACTIVITY AREA. Entry is limited to those qualified persons classified as radiation workers, s
l working under an approved radiation work pemit. No entry is pemitted until an appropriate area survey has been nade and a l
member of the Health and Safety Group is present. Protective clothing, protective equipment, and personnel nonitoring devices to be worn in the area will be specified by the Health and Safety Group and nust be worn. When exiting these areas, each person must l
remove the protective clothing and monitor hinself in accordance l
with established procedures.
12.3 EXTERNAL RADIATION - PERSONNEL MONITORING i
12.3.1 Adninistrative Exposure Control - Linits for external radiation exposure are set forth in 10 CFR 20.102 and these general limits are used at the LRC. The applicable exposure limits to be used for l
operations at the LRC are:
l 1.
Whole bndy - 300 mRen/ week (with long-tern exposure controlled I
within the 1.25 Ren/ quarter linit by the worker's imediate supervisor) 2.
Skin of the whole body - 1.5 Ren/ week 3.
Hands and foreams, feet and ankles - 3.0 Rem / week.
The Manager, Lynchburg Technical Operations, has the authority to l
approve whole body expnsures up to, but not exceeding, 3.0 Rem / calendar quarter.
In energencies, the Energency Of ficer is authorized to allow personnel exposures to the whole body of up to 3.0 Ren/ calendar quarter. Higher exposures may be authorized by the Energency Officer in a:cordance with the Radiological Contingency Plan.
12.3.2 Personnel Monitoring for LRC Enployees - All LRC enployees will be monitored for radiation exposure while on site.
This nonttoring will be accomplished in two ways:
1.
All enployees will be issued a themoluminescent dosimeter (called an Annual TLD).
2.
Employees will be classified as radiation or non-radiation workers.
In addition to the Annual TLD, those employees License No SNM 778 Docket No.70-824 Date February,1986 Amendment No.
O Revision No.
1 Page 12-3 Babcock & Wilcox A MDermott company
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O 12.8.2 External Occupational Exposure - Personnel monitors (film badges, U
dosimeters, or other suitable devices) are provided to measure the l
radiation exposure of visitors and employees. Personnel dosineters issued pursuant to 10 CFR 20.202 shall be read on a nonthly basis.
The enployee's line supervisor is responsible for keeping exposures l
below 300 millirem per week and 1250 millirem per qu:rter. The i
Supervisor, Health and Safety may approve weekly exposures above 300 milliren, but the quarterly limit of 1250 millirem shall not be l
I exceeded without the approval of the Manager, Lynchburg Technical l
Operations.
If an employee nas received the quarterly limit and the Manager, Lynchburg Technical Operations has not authorized exceeding the limit, the employee's work shall be restricted to l
prevent further exposure for the remainder of the quarter.
l l
12.8.3 Airborne Activity 1
l 12.8.3.1 Air Monitoring Program - Air monitoring in operating areas of the LRC is accomplished with continuous monitors in predetermined, fixed locations. A monitor is placed in each radioactive materials handling area in which there is a potential for the l
release of airborne radioactivity. Locations are selected based l
upon the ability of the monitor to provide a reasonable evalu-ation of the airborne activity in a particular area and to provide adequate warnings to those in the area of changing condi-l tions. The determinations are made by the Health and Safety l
Group based upon the operations in the area, the potential for release, the quantity and chemical forn of the material.
l Alarms are set in accordance with a particular operation, the material being handled, and the potential for release. Actual I
alarm points are set as low as possible connensurate with the anbient radiation levels in the area. Personnel are instructed i
l through procedures and training to evacuate, up wind, if an air monitor alarms and to notify the Health and Safety Group.
Reentry is controlled by the Health and Safety Group.
12.8.3.2 Effluent Monitors - Potentially contaninated air fron chemical hoods, hot cells, and glove boxes is discharged ultimately through the 50-meter stack. Generally, exhaust air cnntaining beta-gamma activity is passed through a single-stage HEPA filter which is sufficient to remove airborne particulates. Air fron more hazardous operations, e.g., from glove boxes, is passed through a two-stage HEPA filter.
License No SNM 778 Docket No. 70 824 Date February,1986 O
12-19 Amendment No.
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Babcock & Wilcox a McDermott company l
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In-vivo lung counting was perfomed on 14 employees during 1984
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for Plutonium-239 and Americium-241. No plutoniun was reported.
The presence of Mericiun-241 was indicated for 5 employees with the highest quantity being 0.26 Nanocuries (10.14) for one person.
In-vivo lung counting was perfomed on 20 employees during 1984 for Uranium-235.
In 5 instances, the results were positive with the highest result being 48 micrograns (137) for one person.
12.11 MEASURES TAKEN TO IMPLEMENT ALARA 12.11.1 Management Comitment - LRC management has made a comitnent to maintaining exposures to radiation and radioactive naterial as low as reasonably achievable.
12.11.1.1 The commitment is reinforced in training and retraining sessions presented to Authorized Users and Radiation Workers.
It also appears as a policy statement in several procedures.
12.11.1.2 Exposure histories of employees are reviewed annually in a summary report prepared by the Supervisor, Health and Safety, l
reviewed by the Safety Review Committee and forwarded to the Manager, Lynchburg Technical Operations.
l rh 12.11.1.3 Each RWP requires an estimate of the exposure dose that will be received by workers performing the described task. This estimate is used by the RWP reviewers in evaluating the protection requirements 1,pecified on the form.
12.11.1.4 The RWP fom requires the preparation of an ALARA study for tasks where the estimated exposure approaches LRC self imposed limits.
12.11.2 Training - The following training prograns are presented to LRC employees.
12.11.2.1 General Radiation Protection Training The LRC provides two training prograns covering the nature, use and control of radiation and radioactivity.
These courses are presented to ensure that all LRC personnel receive training appropriate to their activities and to fulfill obligations under i
the NRC license to provide such training.
1 License No SNM 778 Docket No.70-824 Date February,1986 i
12 37 Amendment No.
O Revision No.
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l Babcock &Wilcox l
a McDermott company
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14.0 NUCLEAR CRITICALITY SAFETY 3
O 14.1 ADMINISTRATIVE AND TECHNICAL PROCEDURES The ultimate responsibility for nuclear safety rests with the l
Manager, Lynchburg Technical Operations. However, - fi rst-li ne responsibility is with the Facility Supervisor supported by the Nuclear Safety Officer.
The Nuclear Safety Officer is generally responsible for establishing nuclear safety limits and nuclear safety considerations in operating procedures, processes, and the like. His duties are shown more spe-cifically in the following statement.
The position of, Nuclear Safety Officer has been established at the Lynchburg Research Center.
It will be this officer's responsibility to ensure, as far as possible, that no operations in the Lynchburg Research Center can lead to the inadvertent assenb'y of a critical mass. To this end, he will review all new procedures whicn involve the handling of special nuclear materials as well as changes in old procedures, cbserve operations, inaugurate educational programs if and when he. deems them necessary, and carry out confirning criti-cality calculations.
[]
This appointment does not in any way relieve.the Facility Supervisor
\\J of his responsibilities for ensuring the safety of operations, nor will it eliminate the necessity for the reviews by the Safety Revicw Committee required by the license.
Once a quarter the Nuclear Safety Officer or qualified person designated by him will inspect all LRC operations where special nuclear materials are being processed. Other areas shall he inspected less frequently; however, all areas shall be inspected at least once a year. He shall consider area operations when schedul-ing these inspections and shall, if necessary, schedule his inspection at more frequent intervals. Pis consideration should include inspection of new facilities, inspection of nazardous non-rout 1ne operations, an audit of nuclear safety records, a check for area posting and a review of current practices.
A written report is to be filed with the Manager, Lynchburg Technical Operations quarterly with a copy to the I.PC License Administrator.
Prior to submission of the report, he shall discuss any findings with the Facility Supervisor. The report shall be brief, concerning itself with inspections made during the quarter and with the nuclear safety activity of the quarter.
License No SNM-778 Docket No.70-824 Date February,1986 Amendment No.
O Revision No.
1 Page 14-1 Babcock & Wilcox a McDermott company