ML20214X076
| ML20214X076 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 05/31/1987 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML20214W995 | List: |
| References | |
| NUDOCS 8706160317 | |
| Download: ML20214X076 (28) | |
Text
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ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS
- ggy, 1.4 Possession Limits I
l.4.I Uranium-235 (20.000 Kilograms)
,l.
One hundred grams of any enrichment or form for analytical purposes.
2.
Two hundred l<ilograms contained in uranium compounds enriched to a maximum of 19.99 wt% in the U-235 isotope (see Section 1.6.2 for restrictions).
3.
The balance shall be contained in uranium compounds in any form enriched to a maximum of 5 wt% in the U-235 isotope.
l.4.2 Plutonium (<500 grams) 1.
One milligram and not more than 1.5 millicuries as contained in sealed sources and standards.
2.
Less than 500 grams as PuO2 or PuO -UO2 as stored waste.
2 l.5 Authorized Activities Specific locations of authorized activities involving special nuclear materials are identified in Table I-l.l.
l.6 Exemptions and Special Authorizations 1.6.1 Criticality Accident Alarm System Exemption Pursuant to 10 CFR 70.24(d), Exxon Nuclear has previously requested exemption in part from the requirements of 10 CFR 70.24(o), and has been duly authorized to use the criticality occident alarm system described below in its facilities. In addition, the waste storage lagoons have been exempted from coverage by the criticality accident alarm system.
AMENDMENT APPLICATION D ATE:
PAGE NO.:
May 1987 l-2 XN-NF-F01422 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REv.
The responsibilities of the Criticality Safety Component include the following:
1.
Providing technical bases, criteria, and methods related to nuclear criticality safety.
2.
Preparing the Nuclear Criticality Physics Methodology document and the Criticality Safety Standards.
3.
Providing criticality safety determinations for designs and proce-dures.
4.
Providing professional advice and counsel concerning matters within his cognizance.
5.
Membership in the Emergency Cadre.
6.
Performing compliance inspections.
7.
Approving Criticality Safety Specifications.
All determinations concerning nuclear criticality safety shall be reviewed by a second-party reviewer who shall be knowledgeable in the technical data cnd qualified in the techniques of criticality physics.
Second-party reviews shall be arranged for by the Criticality Safety component and may be either from within the component or by on outside reviewer. All nuclear criticality safety calculations and reviews shall be documented and documents shall be held in permanent Company records. Calculational details, work sheets, etc.,
shall be held for a minimum period of six months following termination of the process or operation reviewed.
2.2 Personnel Education and Experience Requirements Responsibilities and authorities of all line managers shall be provided in writing. Hiring of managers and key professionals in plant operations, health physics and nuclear criticality safety shall be subject to approval by the Vice President, Engineering and Production.
Manager of operations wherein special nuclear material is processed, stored or handled shall have a minimum of two years experience in the nuclear industry and a degree in Science or Engineering. There are certain positions where a technical degree is not normally required in that the technical content is not high.
In those cases, the incumbeat will have adequate job training and technical support will be available.
Specific requirements for those key safety professionals whose major responsibility is in a safety field are listed below.
AMENDMENT APPLICATION DATE:
P AGE NO.:
May 1987 2-1I XNWF F01-822 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS R Ev.
contact with radioactive and fissionable materials. Employee instruction is provided by personnel knowledgeable in the various training topics. All formal training is documented and records are maintained by the Safety and Security Operations.
2.4.1 initial Training Each employee is provided initial instruction adequate to allow him to safely start on-the-job training; they are provided the full instruction within two weeks after starting work. Prior to assignment to independent operation, each employee is required to have been instructed in radiation protection, criticality safety, and emergency requirements and procedures as appropriate to his position.
2.4.2 Followup Training When changes are made in radiation protection, criticality safety controls (procedures, specifications, etc.), or in emergency procedures, each employee offected is promptly informed and propei4 instructed.
Safety topics are routinely discussed in monthly safety meetings.
Additionally, each employee routinely working with special nuclear material receives annual refresher instruction as part of Exxon Nuclear's continuing program in radiation protection and criticality safety awareness. The effec-tiveness of this annual refresher training is determined by giving the employees a written examination and reviewing the correct answers to the questions at the end of the test.
2.4.3 Health Physics Technician Training Health Physics Technicians are given special training related to their radiation protection assignment. Previous training is accepted if considered equivalent to the Exxon Nuclear training program. Despite previous accept-able training, the Health Physics Technicians are required to become profi-cient in Exxon Nuclear radiation protection and criticality safety programs, criteria, specifications, procedures and routines, as demonstrated by success-fully passing an Exxon Nuclear certification examination within six months af ter employment as a Health Physics Technician.
In addition, refresher training is provided to all Health Physics Technicians annually.
2.4.4 Training Evaluations Employee awareness of and conformity to safety requirements and procedures, as well as the effectiveness of safety training programs, shall be evaluated at least monthly by the Radiological and industrial Safety Supervisor for radiation protection and by the Plant Criticality Safety Engineer for AMENDMENT APPLICATION DATE:
P AGE NO.:
May 1987 2-IS XN-NF-FO1-822 (2/87)
ADVANCEDNUCLEARFUELSCORPORATiON XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REV.
criticality safety. These Exxon Nuclear staff members have the authority to require retraining of employees. These evoluotions shall be documented along with actions required by them.
2.5 Operating Procedures, Standards and Guides Exxon Nuclear conducts its business in accordance with a system of Standard Operating Procedures, Company Standards and Policy Guides. Exxon Nuclear is committed to controlling activities involving special nuclear materials in accordance with these approved written procedures, standards and guides.
These documents are prepared, reviewed, revised, approved and implemented in accordance with the Approval and Responsibility Matrix (Figure 1-2.2).
Plant and facility managers are responsible for assuring compliance with all pertinent radiation protection and criticality safety procedures, specifications and practices within their respective facilities.
Violations of radiation protection or criticality precedures or specifications which are of repetitive or serious nature are subject to disciplinary action.
The Radiological and Industrial Safety Supervisor is responsible for assuring that Health Physics Technician activities are conducted in accordance with established and approved procedures, methods and frequencies.
2.6 Internal Audits and inspections Audits and inspections are conducted to determine that plant operations are conducted in compliance with regulatory requirements, license conditions, and written procedures.
These audits and inspections apply to radiation protection, criticality safety, hozordous chemical safety, fire protection, and environmental protection.
2.6.1 Radiation Protection As part of their normal activities, the Radiological and Industrial Safety Supervisor and Health Physics Technicians perform daily inspections as part their procedures for collecting air samples and performing radiation and contamination surveys of all areas of the plant where uncontained radioactive materials are stored, processed, or otherwise handled. Detected infractions of radiation protection procedures, exposure controls and sound radiation protec-tion practices are corrected on the spot as part of a continuing education effort in their field of expertise. Serious infractions and ncncompliance with license conditions are documented and distributed to the respective facility management and to the Manager, Corporate Licensing.
The Health Physics Component of Corporate Licensing makes monthly audits of radiation protection practices and exposure controls.
These audits are made in accordance with a written plan.
Results of these audits are documented, including any recommended corrective actions, and distributed to AMENDMENT APPLICATION DATE:
P AGE NO.:
May 1987 2-16 XN-NF-FO1822 (2/87)
ADWU4CEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LtCENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 1
PART I - LICENSE CONDITIONS REv.
Chapter 3 RADIATION PROTECTION 3.1 Special Administrative Requirements 3.i.I ALARA Policy it is the policy of the Advanced Nuclear Fuels to conduct its business in a mannet such as to assure that its facilities are in compliance with radiation and other nuclear regulations, and that its operations will not be detrimental to the environs. In implementing this policy, Advanced Nuclear Fuels shall assure that radiation exposure to persons (both in-plant and of f-site) is maintained as low as reasonably achievable (ALARA).
In providing this assurance, conditions of applicable NRC and State licenses and other regulatory permits or licenses shall be complied with and regard shall be given to applicable NRC regulatory guides and industry stondards.
Responsibility for esroblishing and assuring adherence to this policy shall rest with the President, Advanced Nuclear Fuels Corporation. This policy shall be implemented through appropriate delegations to Vice Presidents responsible for f acilities processing or otherwise handling radioactive and nuclear materials.
In order to facilitate implementation of this policy, key positions in organizations involved with facilities processing or otherwise handling radio-active or nuclear materials shall be filled by persons knowledgeable of, and experienced in, tha nuclear industry, and the responsibilities under this policy shall be identiiied in writing. Each responsible manager shall be required to know, understand, and carry out the provisions of this policy and the proce-dures for its implementation.
3.1.2 Radiation Work Procedures Radiation Work Procedures (RWP) are r wored by Radiological and Industrial Safety and establish the radiological.uie y requirements of all work (operation and maintenance) involving re b:,
nd/or radioactive materials.
The RWP shall be immediately availca!. ;y (rsonnel working with the material.
Radiation Work Procedures are approvbd in accordance with Figure 1-2.2.
I Radiation Work Procedures cover such items as:
1 1.
The identification number of the procedure; 2.
A descrintion of the nature and extent of the work to be done and the-locntion of the work; AMENOMENT APPLICA TION DATE:
PAGE NO.:
XN4dF-FO1422 (2/87) o l
s
ADEANCEDNUCLEARFUELSC RPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REV.
3.
A description of types and levels of radiation exposures and contamination that may be encountered; 4.
A statement of the exposure rates or instructions for self-monitor-ing for exposure rates; 5.
Personal survey requirements and protective clothing requirements; 6.
Personal dosimetry requirements; 7.
A statement of the respiratory equipment required for entry into an airborne radioactive materials area.
3.2 Technical Requirements 3.2.1 Controlled Areas All radioactive materials at Advanced Nuclear Fuel's nuclear fuel fabrica-tion plant are stored and processed within a controlled access area. Access is controlled by Advanced Nuclear Fuel security personnel at all personnel and vehicle entrances in accordance with a physical security plan.
3.2.1.1 Restricted Areas Radioactive Material, airborne radioactivity, radiation and high radiation areas, as defined by 10 CFR 20, are identified and their boundaries are visibly markec.
Signs are placed denoting these areas so that at least one sign is visible from any approach.
Radiation Work Procedures for the respective areas s' ecify the existing or potential conditions and the protection measures p
required in these areas.
3.2.1.2 Clean, intermediate and Contaminated, Radioactive Materials / Radio-tion Areas Noncontaminated Radioactive Material Areas (clean areas) are separated from the Contaminated Radioactive Material Areas (contaminated areas) by Intermediate areas. Intermediate areas are identified and their boundaries are visibly marked. Special restrictions or procedures required before entry to iniermediate or clean areas from a contaminated area are posted.
3.2.l.3 Change Rooms and Step-Off Areas Change rooms are divided into contaminated, intermediate and clean areas to facilitate controlled entrance to and egress from contaminated areas.
Step-of f pods are provided when exiting contaminated arcos. Separate toilet AMENDMENT APPLICATION DATE:
P AGE NO.:
May 1987 3-2 XN-NF-F01422 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REV.
facilities may be located in both the intermediate and clean areas of change rooms. Use of toilet facilities in the intermediate area without removal of protective clothing is permitted provided a personnel survey is first performed.
Additional step-off areas may be established for maintenance work, temporary situations or conditions, or to accommodate personnel entry and exit not requiring the use of change room facilities.
Personnel survey requirements are adhered to at all step-off areas.
3.2.l.4 Protective Clothing Protective clothing is required for entry into contaminated areas. The type (s) of clothing required is dependent upon the levels and types of contamination present and work assignment and is specified in the applicable radiation work procedure.
Appropriate respiratory protective equipment is required for entry into Airborne Radioactivity Areas. Such equipment is not used in lieu of proper ventilation or contamination control.
3.2.l.5 Personnel Surveys Personnel working in contaminated areas are instructed to change their protective clothing if excessive contamination is detected. Personnel exiting from contaminated areas are required to survey themselves offer removing their protective clothing to assure themselves that they are free of signZicant contamination prior to leaving the step-off areas. Emergency evacuation is the only exception to these survey requirements. Personnel survey instruments are located,at step-off areas and radiation workers are trained in their use.
3.2.2 Ventilation Ventilation systems are designed and maintained to limit the spread of airborne contamination by maintaining air pressure gradients and air flows from areas of low potential airborne contamination to areas of higher poten-tial contamination. These systems are balanced so that air pressure dif feren-tials between general areas (non Radioactive Material Areas) and contaminated areas are maintained at a minimum of 0.05 inches of water.
Airlocks are provided between areas where necessary to' insure mainte-nonce of proper air pressure differentials. Installed dif ferential air pressure measuring instruments are read routinely and the readings recorded at least monthly.
Monthly smoke tests are conducted to visually demonstrate that the air flows are in fact from nrecs of low contamination potential to areas of higher contamination potential.
AMENOMENT APPLICATION DATE:
P AGE NO.:
May 1987 3-3 XNWF FO1422 (2/s7)
ADVANCEDNUCLEARFUESCORPORATION XN-2 i
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS
- ggy, The ventilation rate in contaminated areas is maintained at a minimum of seven air changes per hour.
The air velocity through openings in uranium handling hoods and equipment containing readily dispersible forms of uranium is maintained at a minimum of 125 linear feet per minute. These velocities are verified at least monthly.
Recirculating air systems are designed and maintained to supply air at concentrations not greater than respective values listed in 10 CFR 20, Appendix B, Table !!, Column I.
To insure this, recirculated air is taken only from room areas (not from process enclosures) and before being returned to work areas it is passed through fire-retardant HEPA filters which are assured to have installed efficiencies of at least 99.95% for 0.8 micron particles.
Recirculation air is continuously monitored prior to the final stage of HEPA filtration. An indication of eight MPC-hours will automatically divert the air from the recirculation mode to the respective facility exhaust air system.
Both recirculation air and exhaust air system HEPA filter installations are equipped with continuous pressure dif ferential measuring / indicating systems, which are read and the readings recorded at least monthly.
The differential pressure across final HEPA filters is not allowed to exceed four inches of water gauge.
3.2.3 Work Area Air Sampling The air in all areas where uncontained radioactive materials are handled, processed, or are likely to exist is regularly sampled, and the samples are analyzed for radioactivity.
The air sampling system is a flexible combination of equipment and instruments. Field-run lines (flexible or hard-piped) connect individual air samplers to the overhead vacuum lines such that the samplers may be moved about and located at any desirable point without causing obstructions or creating industrial safety problems. Some samplers are located at points of maximum airborne contamination potential, some are located at points representative of the contamination level of air breathed by personnel at work stations, and some are located so as to provide background data.
AMENDMENT APPLICATION DATE:
PAGE NO.:
May 1987 3-4 XNWF-F01822 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, ilRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS
- ggy, The frequency of air sample changes in contamination control areas is based upon historical experience with each sampling area and varies from weekly to shif t-wise. Selected samples representative of the personnel's work environment are taken once per shift during operation in contamination control areas where uncontained radioactive materials are being stored, processed, or otherwise handled by personnel.
Additional samplers may be added or the frequency of samples modified to assess the effectiveness of radioactive material containment following equipment modification or maintenance, or to assess the air quality of sequential shift operations.
Specialized air sampling or monitoring equipment such as continuous air monitors, portable high volume air samplers, and lapel air samplers are available to supplement the normal air sampling system and for use in studies or work on special problems.
Permanently mounted air sampling equipment used to determine the concentrations at work stations shall be evaluated for representativeness at least every 12 months or following significant process or equipment changes.
The air _ flow rates through air samples, as measured by in-line rotome-ters, are checked at the start and at the end of each respective sampling period. Rotometers shall be calibrated at least yearly.
I Air sample counting instruments are checked for proper operation each workday and background values are determined.
Personnel are not allowed into areas without adequate respiratory protection when the concentration of uranium in air samples exceeds lx10-lu microcuries/ml.
If an air sample from a worker's breathing zone during normal operations indicates the airborne concentration has exceeded the 10 CFR 20 MPC, or the weekly average airborne concentration level to the worker has exceeded 25 percent of 40 MPC hours, an investigation shall be performed to evaluate the cause and prevent the reoccurrence of the high airborne contamination.
3.2.4 Radioactivity Measurements Instruments 3.2.4.1 Radiation Safety Instruments and Equipment The general capabilities of radiation safety instruments used to make radiation protection measurements are described in Table I-3.1.
The Manager, Plant Maintenance, is responsible for the maintenance and calibration of radiation safety instruments and equipment.
The following general requirements apply to all such equipment and instroments:
AMENDMENT APPLICATION DATE:
P AGE NO.:
May 1987 3-5 XN-NF#01422 (2/87)
ADVANCED NUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REV.
1.
All radiation detection instruments are inspected, repaired when necessary, and calibrated per the guidance of Regulatory Guide 8.24 at least semiannually except for dose rate instruments which are calibrated quarterly.
2.
Instruments are calibrated following any maintenance on them before they are put back into routine service.
3.
Each on-line radiation detection instrument is checked for proper operation by Health Physics Technicians daily (Monday through Friday). When daily checks are performed in a manner which qualifies as calibration, separate semi-annual calibrations are not required.
4.
Portable survey instruments are source checked each time they are turned on for use.
5.
AC-operated personnel contamination survey instruments are provided with individual check sources to allow personnel to source check the instruments at random.
6.
Calibration sources are traceable to the National Bureau of Standards.
3.2.4.2 Criticality Accident Alarm System See Chapter I, Section 1.6.l.
3.2.4.3,, Criticality Dosimeters Criticality dosimeters are strategically located throughout the procesd These criticality dosimeters are capable of measuring 0.1 to 10 f acilities.
rem of neutron radiation over a neutron spectrum of thermal to 2.5 MeV. The criticality dosimeters are inspected at least annually to assure their integrity.
3.2.5 Radiation Exposure Advanced Nuclear Fuels shall maintain external radiation exposures as far below the normal limits specified in 10 CFR 20.10l(o) as is reasonably achievable. Radiation exposure records are reviewed by the ALARA Coromittee.
In the event that it is necessary to exceed the exposure limits specified in 10 CFR 20.10l(a), exceptions will be authorized in accordance with 10 CFR 20.10l(b).
Respiratory protective equipment will be used for entry into areas where airborne radioactive materials exist in excess of the concentrations stated in 10 CFR 20. Appendix B, Table 1, Column I.
AMENDMENT APPLICATION DATE:
PAGE NO.:
May 1987 3-6 XN-NFfot422 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS R Ev.
In addition to the controls specified elsewhere, the following methods of external radiation exposure control are employed as applicable and reasonable:
1.
Automation of operations.
2.
Minimization of quantities of radioactive material and/or use of shielding.
3.
Time and distance control.
4.
Special handling tools.
5.
Exposure awareness, planning and scheduling.
3.2.5.1 Radiation Surveys A detailed survey of radiation levels (S-y ar.d neutron, as applicable) is performed for each specific operation and radioactive material storage area as activity in the area is initiated.
Routine radiation surveys are performed at least monthly in all areas where radioactive materials are stored or processed, and where personnel have access.
Radiation surveys are performed on all incoming and outgoing shipments of radioactive materials per 10 CFR 20.
3.2.5.2, Dosimetry Al'l persons entering a radioactive materials area of the plant are required to wear 8-y sensitive dosimeters. The B-y dosimeters are supple-mented, as appropriate, by other types of dosimeters (i.e., finger rings, direct-reading dosimeters, and neutron dosimeters), and by radiation measure-ments made with radiction survey instruments.
Personnel dosimeters shall be capable of measuring the following radio-tion exposure ranges:
beto/ gamma dosimeters:
10 mrem - 1000 rem For personnel routinely working in areas containing radioactive materials, radiation exposure dosimeters (whole-body beta / gamma) are exchanged and analyzed quarterly. Film badge dosimeters, if used, shall be exchanged and l
analyzed monthly.
AMENDMENT APPLICATION DATE:
PAGE NO.:
May 1987 3-7 XNWF FO1422 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS
- ggy, Indication of exposure of uranium fuel fabr,ication workers exceeding the action levels stated below shall be investigated and the report placed in the personnel folder of the individual.
Action / Investigation Levels Rem /Otr.
Whole body, head and trunk, active blood-0.5 forming organs, lens of the eye or gonads Skin of whole body 3.0 Hand, forearms, feet and ankles 7.5 3.2.6 Surface Contamination Radioactive materials are contained and/or confined during processina, transfer and storage to the extent of maintaining intake of such materials by personnel as low as is reasonably achievable.
As appropriate, operations involving readily dispersible forms of radioactive materials are accomplished within enclosures (i.e., process equipment, glove boxes, glove-port hoods, laboratory type hoods, etc.) which are exhcusted to facility exhaust air systems.
3.2.6.1 Facility Surveys The following minimum f requency schedule is applied to the facility contamination survey program:
Contaminated Radioactive Materials Areas:
Weekly Noncontaminated Radioactive Material Areas:
Monthly Intermediate Areas:
Daily Lunch Rooms Adjacent to Radioactive Materials / Radiation Areas:
Daily Action levels for clean up of the various areas are listed below.
1.
Noncontaminated Radioactive Material Areas. These areas are to be kept contamination free.
Any contamination in excess of background is to be cleaned up during the shif t detected.
2.
Intermediate Areas. These areas are to be kept free of significant contamination.
Any contamination less than 500 dpm (alpha) per 100 cm2 is to be cleaned up during the shif t detected. Contamina-tion in excess of 500 dpm (alpha) per 100 cm2 is to be cleaned up immediately. If the contamination level is in excess of 2,000 dpm 2
(alpha) per 100 cm, the area is reclassified as a contamination control area until it is cleaned up.
AMENDMENT APPLICATION DATE:
PAGE NO.:
May 1987 3-R xN-NF#01-822 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REV.
3.
Contaminated Radioactive Material Areas. Visible contamination in these areas and/or smearable contamination in excess of 10,000 dpm (alpha) per 100 cm2 will be cleaned up immediately. These limits are not opplicable to nonroutine tasks being conducted under special controls.
4.
Plutonium Contamination. Plutonium contamination is limited to:
100 dpm/100 cm2 overage fixed 300 dpm/100 cm2 maximum fixed 20 dpm/l00 cm2 removable 3.2.6.2 Release of Personnel, Materials, Equipment, Facilities and Shipments Contamination surveys are performed on all personnel leaving contami-noted creas, on all materials, equipment and facilities to be released from radiation protection requirements, and on all incoming and outgoing shipments of radioactive materials. Release of equipment and packages from the plant site or to clean areas on-site shall be in accordance with NRC Guidelines dated July 1982 (see Appendix A).
~
I.
Personnel.. Personnel contamination surveys are conducted accord-ing to the following schedule:
All persons leaving contaminated areas are required to survey a.
themselves for contamination with survey instruments located at respective step-off areas af ter removing protective clothing and prior to leaving the step-off creo.
b.
Personnel are not released to eat or leave the respective facility, except with the approval of the Radiological and Industrial Safety Supervisor and the respective facility manager, if their personal clothing is contaminated in excess 100 cm2 (alpha) or skin is contaminated in of 1000 dpm(ber excess of 200 epm per 100 cm2 (alpha).
c.
Cloth protective clothing is not reused if the contamination exceeds 1000 dpm/l00 cm2 alpha. Rubber shoe covers shall not be reused if after cleaning contamination exceeds 5000 dpm/l00 cm2 alpha.
By procedure, protective clothing in a contaminated area will be changed if contamination is visi-ble/ exceeds 10,000 dpm/l00 cm4 alpha.
I 200 dpm per 100 cm2 (alpha) represents the practical lower detection level for most direct-reading contamination survey instruments.
AMENDMENT APPLICATION DATE:
PAGE NO.:
May 1987 3-9 XNWF-F01422 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS g gy, 2.
Materials, Equipment, Facilities and Shipments.
Contamination surveys are performed by Health Physics Technicians on all materials and equipment removed from contaminated areas, and on areas or facilities to be released from radiation protection require-ments. Limits for release are:
Smearable:
Less than or equal to 220 d/m/l00 cm2 alpha Fixed:
500 d/m/100 cm2 alpha in special cases, the NRC guidelines contained in Appendix A to this chapter may be utilized.
3.
Shipments of radioactive materials arriving at the facility are surveyed to the requirements of 10 CFR 20.205. All outgoing shipments of radioactive materials are packaged and surveyed in accordance with 10 CFR 71 and 49 CFR 173.443.
3.2.7 Bioassay Program Bioassay measurements shall be conducted so os to assure compliance with 10 CFR 20.103 and the ALARA policy.
The bioassay program will normally be used as a verification of contamination control, but may in occident or abnormal situations be used to estimate the uptake by an individual or estimate the exposure that an individual has or will receive. The normal bioassay program shall consist of a monthly urinalysis and yearly lung count.
The lung counts shall be scheduled among the workers throughout the year (as possible) to provide a continuing status of the plant environment.
Additional diagnostic assays may be performed on workers who have entered on airborne radioactivity crea as indicated by air sampling results.
The pertinent elements of the Advanced Nuclear Fuels bioassay program are outlined below.
1.
Employees routinely working in contaminated area submit monthly urine specimens for routine uranium analysis.
2.
Employees routinely working in contaminated area shall receive in-vivo examinations at least annually.
3.
If'the most recent quarterly average of the airborne uranium concentration for any work area exceeds 25 percent of the respec-tive DAC, the frequency of sampling and the type of bioassay measurements for workers in that work area shall be modified to that given in Table 3 of Regulatory Guide 8.11. " Application of Bioassay for Uranium," June 1974.
AMENOMENT APPLICATION DATE:
P AGE NO.:
May 1987 3-10 XN-NF F01822 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION
- XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REv.
Unusual occurrences with documented evaluation will not be included in calculating the quarterly overage. However, diagnostic evaluations, as defined in Section C.2.b(4) of Regulatory Guide 8.11, shall be performed in accordance with criteria set forth in Figure 2 of the same Guide.
4.
The following action guides and actions shall apply to soluble, biologically transportable uranium compound:
a.
A dose evaluation shall be performed for an individual whose urine specimen exhibits a concentration in excess of 25 micrograms uranium / liter. The employee shall be required to submit another urine specimen immediately and at least weekly thereaf ter until a concentration of less than 25 micrograms uranium / liter is reached. Based upon the results of the evaluation, worker restriction may be considered.
b.
An individual whose urine specimen exhibits a concentration in excess of 100 micrograms uranium / liter; such individuals shall not be allowed to work in contaminated areas until subsequent urine specimens exhibit a concentration of less than 25 micrograms uranium / liter.
5.
The following action guides and action shall apply to insoluble, biologically nontransportable uranium compoundsl.
a.
Should the future 12-month dose commitment (based on in-vivo examination) exceed 5 rem (approximately 125-micrograms,.27 nanocuries U-235) a dose evaluation and investigation shall be performed. The individual will receive in-vivo examination at least bi-monthly as long as he contin-ves to work in a contamination control area and until future dose commitment is less than 3 rern for the subsequent 12 months (75 micrograms,.16 nanocuries U-235).
I The action limit calculation is based on the quantity of an alpha emitter, with a 500 day biological half-life in the pulmonary lung which delivers an annual dose equivalent of 15 rems to the lung tissues according to ICRP recommendations first issued in 1960. Fif teen rems per year is the dose criterion on which the Maximum Permissible Concentrations (MPCs) are based (i.e., for radioactive materials having the long as the critical organ) which are presently in effect in 10 CFR Part 20.
AMENDMENT APPLIC ATION DATE:
PAGE NO.:
May 1987 1-1i XNWF#01422 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REv.
b.
Should the future 12 month dose commitment exceed 8 rems (approximately 200 micrograms,.43 nanocuries U-235) the actions of "a" above shall apply and the workers shall be considered for exclusion from work in a contamination control area.
c.
Should the future 12 month dose commitment exceed 12 rem (approximately 300 micrograms.64 nanocuries (male) 260 micrograms, 56 nanocuries (female) U-235. The actions in "a and b" above will apply and the worker shall not be allowed to work in a contamination control area until the time when his future dose commitment for the subsequent 12 month period to the lung is less than 8 rem.
AMENDMENT APPLICATION DATE:
PAGE NO.:
May 1987 3-12 XNWF#01422 (2/s7)
ADVANCED NUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS l REv.
Table I-3.1 Radiation Safety Instrument Capabilities Radiations Lower Detectior Type of Instrument Detected Rcnge Level Air Sample Analyzers a
0 - 106 I cpm cpm Air Contamination Monitors a
0-5x103 I cpm cpm AC-Operated Survey Meters a
0 - 106 20 cpm cpm Portable Survey Meters a
0-5x105 20 cpm cpm Portable Survey Meters B,y 0-5x104. cpm 20 cpm Portable Low Energy Dose Rate Survey Meters 8,y,x 0 - 300 mR/hr 0.1 mR/hr Portable Dose Rate Meters B,y,x 0-25 R/hr 0.1 mR/hr 0 - 100 R/hr 0.1 mR/hr 0 - 300 R/hr 0.1 m8/hr 0 - 500 R/hr 0.1 mR/hr Portable Dose Rate Meters n
0 - 2 rem /hr 0.1 mrem /hr Direct-Reading Dosimeters y,x 0 - 200 mR y
0 - 10 R y
0 - 600 R x,y,n 0 - 200 mrem AMENOMENT APPLIC ATION O ATE:
P AGE NO.:
May 1987 3-13 XNWF.F01422 (2/87)
EXXON NUCLEAR COMPANY, INC.
XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC D CKET NO. 70-1257 PART I - LICENSE CONDITIONS REV.
APPENDIX A CHAPTER 3 AMENDMENT APPLICATION DATE:
^
Se tember 1986 3-14 XN-NF-F01422 (4/86)
,,-9 s.
.).
(
GUIDELINES FOR DECONTAMINATION 0F FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE
'OR TERMINATION,OF LICENSES FOR BYPRODUCT, SOURCE,-
p ORSPECIALNUCLEARMATERIA0
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U. S. Nuclear Regulatory Comission Division of Fuel Cycle and Material Safety Washington, D.C.
.20555 s.
July 1982 G
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The instructions in this guide, in conjunction.with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior
.to abandonment or release for unrestricted use. The limits in Table i do not a'pply to premises,- eq0ipment, or scrap containing induced radio-activity for which the radiological considerations pertinent to their use may be differ,ent. The release of such facilities or items from regulatory control is considered on a case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or surfaces shall'not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey *and documented, are below the limits specified in Table 1 prior to the application of the covering.
A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain liines, or ductwork shall be determined by making measurements at alTi traps, and other appropriate access points, provided that comtam-ination at these 1ocations is likely to.be representative of contamination on the interior of the pipes, drain lines, or
(
ductwork.
Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in' excess of the limits.
4.
Upon r~equest, the Co=aission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified.
This may include, but would not be limited to, special circurnstances such as razing of buildings, transfer of premises to another organization continuing work with radi.oactive materials, or conversion of facilities to a long-term storage or standby status.
Such requests must:
a.
Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.
4 b.
Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
6
. 1.
-2
([
5.
Prior to~ release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of the survey report shall be filed with the Division of Fuel Cycle and ' Material Safety, USHRC, Washington, D.C.
20555, and also the
_I Administrator of the NRC Regional Office having. jurisdiction.
The report should be fi. led at least.30 days prior to the planned date of abandonment.
The survey report shall:
a.
Identify the premises.
b.
Show that reason'able effort has been made to eliminate f
' ~ '.
~
res.idual contamination.
Describe the scope of the surfey and general procedures c.
followed.
d.
State the. findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting '
the facilities to confirm the survey.
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TABLE'i
- V ACCEpTADLE SURFACE CUtiTAMINATION EEVELS
., ; c-i
=
ilUCLIDE5*
AVERAGEbcf
'~
MAXIMUttbdf REH0VADLEbcf l
U-nat. U-235 U-230, and associated decay prodt. cts 5,000 dpa e/100 cm2 15,000 dpm a/100 cm2 1,000 dpm'o/100 cm2 T nsuranics, Ra-226 Ra-228, Th-230. Th-228, Pa-231, 100 dpm/100 cm2 300 dpm/100 cm,2 20 dpm/100 cm2 Ac-227, 1-125, 1-129 Th-na t, Th-232, Sr-90, Ra-223, Ra-224. U-232, 1-126, 1000.dpe/100 cm2 3000jfpm/100 cm2 200 dpm/100 cm2 1-131. 1-133 Deta-gam a emitters (nuclides with decay modes other than alpha emission or spontaneous 5000 dpa sy/100 cm2 15,000 dpm sy/100 cm2 1000 dpa s'y/100 cm2 fissinn) except $r-90 and others noted above.
anthere surface contamination by both alpha-and beta-gamma-cmitting nucildes exists, the limits established for alpha-and beta-ganna-emitting nuclides should apply independently.
DAs used in this table, dpra (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting' the counts per minute observed by an appropriate detector for background, cfficiency, and geometric factors associated with the instrumentation.
CHeasurements of average contaminant should not be averaged over more than 1 square meter, for objects'of less surface area, the average should be cerived for cach such object.
dIbe maximua contamination level applies to an arca nf not more than 100 cm2 CThe amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that arca with dry filter or sof t absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument.of' L. awn efficiency. When removable contamination on objects of Icss surface arca is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
t f ne average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed i
O.2 arad/hr at,1 cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of l
Latal absorber.
s e
e o
e
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS g gy, unlikely even after failure of any single control. Concentration control may be applied to both overmoderated and undermoderated occumulations of material as described below.
4.2.S.1 Concentration Control - Solutions The c6ncentration of fissile material dispersed or dissolved in another medium may be limited to prevent criticality, provided that:
1.
The permitted concentration of fissile' material in solution shall be equal to or less than fif ty percent of the minimum critical concentration in the vessel.
' ~.
2.
The kef f of the system at the maximum allowable concentration shall be limited by using the guidelines given in Section 4.2.2.
3.
For individual tanks (non-geometrically safe) using concentration control, the mass shall be limited such that keff s limited by the i
guidelines given in Section 4.2.2 for the maximum uranium mass occumulated in the tank under the worst conditions attainable by inadvertent concentration of the fissile material. For large storage systems where concentration of the fissile material is not a credible condition, or where administrative practices are imple-mented to prevent concentration of the fissile material, the above requirement may be disregarded.
4.2.5.2 Concentration Control - Powders and Pellets The concentration of hydrogenous material within the fissile material may be, limited to a small percentage by weight of the fissile material (moderation control) to prevent criticality, provided that:
1.
The permitted concentration of hydrogenous material shall be equal to or less than fif ty percent of the critical concentration for the system in question; 2.
The maximum reactivity of the system full of the material in question, under the worst credible accident conditions, shall be limited by the guidelines given in Section 4.2.2; and 3.
The material shall be contained within a fireproof' barrier or in a l
process crea containing limited sources of hydrogenous material. In the absence of a fireproof barrier, special controls shall be used to prevent fires and to control the use of moderators in fire fightinq in such process creas.
AMENDMENT APPLICATION DATE:
PAGE NO.;
May 1987 4-6 XNWF FOt 422 (2/87)
a ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS R Ev.
4.2.6 Multi-Unit Arrays The spacing between units within on array is limited by mechanical means such that the following requirements are met.
1.
The kef f of the array under the maximum credible accident conditions shcIl be limited by the guidelines given in Section 4.2.2.
2.
For multi-unit arrays where keff is not used as a basis, the number of units in the array shall not exceed 50 percent of the calculated critical number.
The mechanical design of equipment or storage arrays in which deforma-tion or rearrangement could result in the loss of a contingency, shall be reviewed by a person competent in mechanical engineering.
4.2.7 Criticality Safety Parameters 4.2.7.1 Criticality Data Critical parameters used to establish primary criticality safety limits shall be based on one or more of the following (see Section 4.2.8 for sources of data currently acceptable to Exxon Nuclear):
1.
Criticality parameters obtained directly from experimental measurements.
2.
Criticality parameters derived from experimental measurements.
3.,
Calculations using methods validated in accordance with Section 4.3 of ANSI /ANS-8. l-1983.
4.2.7.2 Enrichment Levels Design isotopic compositions shall be established and appropriate criti-colity safety controls implemented to assure conformance with the respective fissile element composition prior to initiating respective activities.
Normally, equipment is designed to assure criticality safety by geometry control.
Where batch control is utilized, enrichment level or other isotopic composition limits are clearly posted at the respective equipment or location.
AMENOMENT APPLICATION.DATE:
P AGE NO.:
May 1987 4-7 XNWF FOt 422 (2/e7)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REv.
4.2.7.3 Moderation Critical parameters derived from nuclear criticality safety analyses shall be based on optimum moderation unless the requirements of Section 4.2.5 are applied.
4.2.7.4 Reflection Critical parameters for units and arrays of units shall be based on full water reflection unless other reflectors in the immediate vicinity could result in higher reactivities.
4.2.7.5 Neutron Interaction Neutron interaction (exchange between individually subcritical units) shall be considered. Consideration of the interaction between units or arrays of special nuclear material may be accomplished through the use of the Solid Angle method.
The Solid Angle method is applied according to the constraints in the
" Nuclear Safety Guide." TID-7016, Rev. 2, except for the use of the nomi-nolly reflected solid angle acceptance criteria. The nominally re'lected solid angle acceptance criteria are used to limit the allowable solid angle for arrangements of individually subcritical units provided that:
1.
Boundary conditions for the spacing between concrete walls and the array are as stated in Table I of Reference (21), except that a minimum separation of six inches shall be required; 2.
Concrete walls are less than or equal to seven inches in thicl< ness; 3.
Separation distances given in Table 1 of Reference (21) are measured from the outermost vessel in the array to the closest wall; 4.
The array shall be limited in both number and size of vessels to arrays that are reasonable extrapolations of the conditions assumed in Reference (21); and 5.
All vessels within the array shall be subcritical when fully reflected by water and shall have a minimum edge-to-edge separation of 12 inches.
AMENDMEf4T APPLICATION DATE:
P AGE NO.:
May 1987 4-8 XN44F F01422 (2/87)
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS
. ngy, l
CHAPTER 6 SPECIAL PROGRAMS 6.1 Proprietary Information With application for license amendment dated June 12,198S for opera-tion of a dry conversion process, Advanced Nuclear Fuels submitted copies of document XN-NF-837, Part 11, " License Amendment Application, Dry Conver-sion Process, Proprietary Supplement," dated June 1985 and requested that it be withheld from public disclosure pursuant to 10 CFR 2.790. An accom-ponying of fidavit dated June 13, 1985 was also submitted.
The U.S. Nuclear Regulatory Commission did determine that the submitted document did contain trade secrets or confidential or proprietary commercial information (letter, R. E. Cunningham to C. W. Malody, dated July 19, 1985). Amendment No.
26, dated November 7,1986 was subsequently issued permitting operation and no additional conditions of license were imposed.
6.2 Occupational Safety Advanced Nuclear Fuels follows the current American Conference of l
Governmental Industrial Hygienists (ACGlH), Washington Industrial Safety and Health Administration (WISHA) and Nuclear Regulatory Commission (NRC) maximum permissible concentrations, threshold value limits, and permissible exposure limits for radioactive and hazardous chemicals in the design and operation of its fuel fabrication facility.
In case of a l<nown release, Plant Operations personnel will contact Safety and Security Operctions personnel to ascertain the concentration levels and the recommended personnel protective equipment required for cleanuo operatio,ns to proceed.
Safety and Security Operations personnel conduct routine or periodic surveys as appropriate to determine the concentrations of routinely utilized radioactive and hazardous chemicals.
6.3 Emergency Utilities 6.3.1 Emergency Electrical Power Supply Turbine generator sets are installed to provide emergency electrical power to operate the Criticality Accident Alarm System, selected exhaust f ans, telephones, radiation detection instrumentation, critical' process equip-ment, and also provide emergency lighting.
These generators are tested at least monthlv for proper startoo and operation. functional tests consisting of tying the generator to a normal emorgency lonel art-performed at least annually.
AMENOMENT APPUC ATION DATE:
P AGE NO.:
May 1987 6-1 XNM501422 (2/87)
w,
ADVANCEDNUCLEARFUELS CORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS REv.
6.3.2 Emergency Backuo Water Supply The water supply to the Advanced Nuclear Fuels manufacturing facilities is furnished by the City of Richland through separate 10-inch and 12-inch mainlines connected into a loop feeding the plant fire loop. The City of Richland estimates the flow at the fire loop to be 1600 gpm at 40 psi through each line, resulting in 3200 gpm at 40 psi from the two lines.
A more conservative estimate of reliable, available flow of 2500 gpm at 40 psi provides ample supply for hose lines and exhaust ventilation filter deluge protection. Normal UO2 Building water needs are about 200 gpm.
The source of water for Richland is the Columbia River.
Primary backup is furnished by a 15 million gallon equalizing reservoir on a bluff south of the City at an elevation of S45 feet. Wells, which were the earlier source of water for the City before the construction of the present water filtration plant on the river, have been kept in condition as a secondary backup source.
6.4 Radioactive Waste Manaaement 6.4.1 Liquid Wastes Radioactive and chemical wastes from the process and laboratories are routed to the Process Chemical Waste Storage Lagoon System.
Based on the chemical and radioactive (uranium) content the lagoon waste may be processed through the Lagoon Uranium Recovery (LUR) Facility and/or the Ammonio Recovery Facility prior to being samoled and released to the sewer system.
6.4.2 Solid Radioactive Waste Ur'anium-contaminated solid waste is segregated into noncombustible and combustible types and is stored either in a warehouse or other designated crea within the controlled access area.
Containers used for this purpose are adequately sealed and appropriately labeled prior to being stored. In the event that such containers of waste are stored outdoors for extended periods of time, their physical integrity shall be visually inspected and the occumulation shall be surveyed for external radioactive material contamination at least quarterly, and records of such insoections and surveys shall be maintained.
Combustible waste may be processed through the Solid Waste Uranium Recovery (SWUR) facility to obtain volume reduction and th'e recovery of uranium.
floncombustible waste is stored until shipment to a permanent waste disposal site. Woste packaged for disposal is not allowed to remain in storage for extended oeriods but is scheduled for disposal on a current basis, dependinq ooon generation rato and cost-elfective shipment si/es.
AMENDMENT APPLICATION DATE:
P AGE NO.:
May 1987 4-2 numon21 won
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS FIEv.
CHAPTER 8 RADIOLOGICAL CONTINGENCY PLAN Advanced Nuclear Fuels developed and published a Radiological Contin-gency Plan as document XN-NF-32A entitled, Exxon Nuclear Company Richland Fuels Fabrication Plant Emergency and Radiological Contingency Plan. The currently approved plan was submitted on August 27, 1985.
l The licensee shall maintain implementing procedures for the plan. In addition, the licensee shall make no change in the plan, without the approval of the Commission, if the change would decrease the effectiveness of the plan. The licensee may make changes to the plan provided the changes do not decrease the ef fectiveness of the plan.
The licensee shall maintain a record of each change for a period of two years.
In addition, the licensee shall provide a description of each change to the Chief, Fuel Cycle Safety Branch within six months af ter each change is made.
AMENDMENT APPLICATION DATE:
PAGE NO.:
May 1987 8-l XNWO1422 -(2/07)
-.. o ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION R E V.
CHAPTER 13 ENVIRONMENTAL-SAFETY - RADIOLOGICAL AND NONRADIOLOGICAL The Advanced Nuclear Fuels environmental surveillance program consists i
of periodic collection and analysis of samples from the plant gaseous and liquid ef fluent streams (including the leak detection system for the liquid chemical waste storage lagoons) and selected elements of the local environs.
Information on environmental monitoring and releases is provided by the supplement to the applicants Environmental Report XN-NF-14.
13.1 External Radiation The background radiation level in this part of Washington State is approxi-mately 60 mrem /yr.
There are no plant radiation sources which increase external exposure at the plant boundary above background.
13.2 Gaseous Effluents Continuous isokinetic sampling is provided for each exhaust stack with the samples collected and measured at least weekly.
The samplers are located downstream of the final HEPA filters. The total uranium discharged out of all stacks has overaged less than 25 microcuries per year during the last five years.
This amount of uranium (less than 16 grams / year) has had essentially no impact on the cumulative of f-site exposure due to uranium f uel cycle operations.
Soil samples of f-site have shown no increasing trend in uranium concentration and have remained well below acceptable levels.
Using a worst case CHl/O value of 0.ll4-4 with ICRP 30 methodology a committed dose equivalent on the order of 21 micro rem may be estimated from gaseous discharges.
13.3 Liquid Effluents All liquid ef fluents are joined together on plant, continuously sampled and pumped into the City of Richland sewer system.
Three types of liquid waste are blended into a single sewer flow, these are the sanitary wastes, the noncontact cooling water, and the liquid chemical waste.
Liquid chemical wastes were first discarded in the last quarter of 1984.
The discharge of nonradioactive chemicals in liquid waste is regulated by Waste Discharge Permit No. 3919 issued by the Washington State Department of Ecology. The discharge of radionuclides is limited by 10 CFR 20.303.
Uranium releases to the sewer have remained below l/10 of the CFR quantity limit and less than 1/100 of the CFR concentration limit.
A review of the chemical discharges shows an increase in suspended solids, NO3 and AMENOMENT APPLIC ATION DATE:
P AGE NO.;
May 1987 13-1 XN-NF FOf 822 (2/87)
O
ADVANCEDNUCLEARFUELSCORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll - SAFETY DEMONSTRATION REV.
fluoride associated with the start of the chemical discard, however all chemical discards have remained within the limits of the State of Washington Waste Discard Permit as issued by the Department of Ecology.
13.4 Croundwater There has been no leakage to the groundwater as evidenced by the groundwater sampling program. There have been two leaks through the first liner in lagoon 2.
Inspection of the lower liner following the second leak confirmed it to be sound which supports the fact that there were no increases in groundwater activity.
13.5 Field Sampling Of f-site sampling for fluoride in the vegetation and the ambient air has shown the concentrations to be well within the State limits of 40 ppm and 0.5 ppb respectively.
Of f-site sampling for uranium in the soil has shown no increasing trend in the concentration during this latest five year license period.
1 AMENDMENT APPLICATION DATE:
PAGE NO.:
XNhF#01422 (2/s7) l
XN-2 ADVANCEDNUCLEARFUELSCORPORATION 70-1257 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO.
PART 11 - SAFETY DEMONSTRATIONS REv.
The key parameters in these calculations are:
1.
Verify that the appropriate resonance self-shielding corrections have been applied to the cross sections used.
'2.
Verify that the nuclides and the atom densities in the mixing table conservatively represent the media in the system.
3.
Verify the occuracy of the geometry model. Ensure that dimen-sions and media are appropriate for the condition being tested.
To help verify the geometry model, computer plots of the KENO geometry model are routinely made.
These plots are used to ensure that the overall model and the units in the model are appropriate.
4.
Verify that the solution is well converged. If significant trends in generation kef f's are present or if the generation keff distribution is abnormal, determine if additional generations or a different star:
type is needed.
5.
Examine the data on flux, fission density, and by-group absorption-leakoye-fission for anomalies. Assure that the most reactive region was adequately sampled and if necessary, replicate the case with all or most first generation neutrons starting in the most reactive region.
14.3.3 SNM Properties I4.3.3.l Homoceneous Systems The most frequently encountered homogeneous fissile materials are:
1.
UO2 powder with various moisture contents.
2.'
U03 8 powder with various moisture contents.
3.
UF6 (solid, liquid, or gas) in shipping cylinders or in piping.
UO F -HF-water solutions resulting from UF6 hydrolysis.
4.
22 5.
Ammonium Diuranate (ADU) as dry powder, aqueous slurry and "postes" with water contents between these extremes.
6.
Uranyl nitrate in aqueous or organic solution.
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AMENOMENf' APPLIC ATION D ATE:
14-5 May 1987 XNAF FOt422 (2/87)
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