ML20154P000
| ML20154P000 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 02/14/1986 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML20154N981 | List: |
| References | |
| XN-2, NUDOCS 8603200098 | |
| Download: ML20154P000 (33) | |
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PAGE 1
OF 2
(O 00CUMENT REVISION INSTRUCTION SN54T DOCUMENT NUMSER:
XN-2 DOCUMENT TITLE:
APPLICATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227 (NRC DOCKET NO. 70-1257)
DOCUMENT REVISION:
12 IDENTIFICATION RENOVE INSERT (i.E., SPEC FICATION, DRAWING, PROCEDU RE, ETC.)
PAGE(5)
REVISION PAGE(S)
REVISION Distribution Table of Contents i
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12 Section 1 1.1 0
1.1 12 1.2 0
1.2 12 1.5 0
1.5 12 1.9 1
1.9 12 Section 3 3.4 0
3.4 12 3.8 0
3.8 12 3.10 1
3.10 12 3.11 5
3.11 12 3.12 0
3.12 12 3.13 1
3.13 12 3.14 1
3.14 12 3.15 1
3.15 12 3.16 0
3.16 12 3.19 2
3.19 12 3.20 9
3.20 12 3.21 9
3.21 12 3.43 5
3.43 12 3.44 6
3.44 12 3.50 6
3.50 12 3.51 0
3.51 12 3.71 4
3.71 12 3.72 1
3.73 1
3.73 12 3.74 1
3.74 12 3.75 1
3.75 12 8603200090 G60212 3.76 1
3.76 12 PDR ADOCK 07001257 C
PDR O
e IF THE SPEOFICATIONS OR PAGES ARE ONLY REMOVED AND NOT REPLACED, PLACE DASHES IN THE INSERT COLUMNS.
e IF THE SPECIFICATIONS OR PAGES ARE ONLY ADDITIONS (NO REPLACEMENTS),
PLACE DASHES IN THE REMOVE COLUMNS.
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2 PAGE 2
OF DOCUMENT REVISION INSTRUCTION SHEET (Con't)
DOCUMENT NUMBER:
XN-2 12 DOCUMENT REVISION:
IDENTIFICATION REMOVE INSERT (l.E., SPECIFICATION, DRAWING, PROCEDURE, ETC.)
PAGE(S)
REVISION PAGE(5)
REVISION Appendix I I-0 0
I-0 12 I-2.1 1
I-3.1 0
I-2.1/2.2 12 J
l O
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XN-2, Rev. 12 Issue Date: 2/14/86 Table.of Contents l
l Section Section Title Page 1.
AUTHORIZATIONS.......................................
1.1 1.1 Activities...........................................
1.1 1.2 Possession Limits....................................
1.2 1.2.1 Uranium-235 (20,000 Kilograms).......................
1.2 12 l
1.2.2 Plutonium (<500 grams)...............................
1.2 1.3 Location of Use......................................
1.2 1.4 Restrictions and Exclusions..........................
1.3 1.4.1 Source and By-Product Materials......................
1.3 1.4.2 Special Nuclear Material Safeguards..................
1.3 j
1.4.2.1 Physical Security....................................
1.3 Accountability.......................................
1.4 1.4.2.2 1.4.3 Special Processing of Uranium Enriched From 5 to 19.99 wt% U-235......................................
1.5 l
1.4.4 Plutonium Storage....................................
1.5 12 1.5 Respiratory Protection Equipment Usage...............
1.5 1.6 Criticality Accident Alarm System Exemption..........
1.6 2.
CAPABILITIES COP 9tITMENT..............................
2.1 l
2.1 Compliance Policy....................................
2.1 2.1.1 Responsibility and Implementation....................
2.1 I
2.2 Safety Council.......................................
2.2 2.2.1 ALARA Committee......................................
C.3 4
2.3 Organizational Safety Responsibilities and Authorities 2.5 2.3.1 President and Chief Executive Officer................
2.6 2.3.2 Vice President, Engineering and Production...........
2.6 2.3.3 Manager, Operations-Richland.........................
2.6 2.3.4 Manager, Plant Operations............................
2.7 2.3.5 Manager, Process and Equipment Engineering...........
2.8 i O
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XN-2 Rev. 12 Issue Date: 2/14/86 a
APPLICATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO. SPM-1227 (NRC DOCKET NO. 70-1257) i i
DISTRIBUTION 1-7 WT Crow 8
BL Brock 9
Richland Public Library 10 PE Fuller 11 LA Bisping 12 LD Gerrald
]
13 JE Pieper 14 i
15 16
{
17 18 RG Frain 19 HL Caudill 20 MG Hill 21 22 JW Key 23 BE Berst J
24 25 J Ryden 4
26 27 MK Valentine 28 JL Glesener 29 RH Purcell 30 31 TC Probasco 32 TC Probasco 33 34 TC Probasco 35 36 37 GV Mulligan 38 WS Nechodom l
39 NS Wing 40 LA Bisping 41 CJ Francis j
42 l
43 CJ Voln.er 44 i
45 Library 46 CW Malody j
47 i
48 RY Hansum 49 RW McCullugh i
Document Control (10)
E@ NUCLEAR COMPANY,Inc.
xN-2 O)
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET N0. 70-1257 tV Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
APPLICATION FOR RENEWAL 0F SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227 Pursuant to the Atomic Energy Act of 1954 and Title 10, Code of Federal Regulations, Chapter 1, Part 70, "Special Nuclear Material," application is hereby made by Exxon Nuclear Company, Inc., for renewal of Special Nuclear Material License No. SNM-1227 to receive, possess, use and transfer special nuclear material.
The license is requested to be renewed for a period of five (5) years.
/
CONDITIONS OF LICENSE O)
I, 1.
AUTHORIZATIONS v
1.1 Activities The operations conducted under this license are related to the development and fabrication of nuclear fuels for nuclear reactors.
For uranium, this includes receipt, possession, storage, transfer and all operational steps from UF -UO2 conversion to packaging finished fuel 6
elements, associated scrap recycling and reprocessing, and waste treatment and disposal. Also included is hydraulic flow testing with finished U02 fuel elements.
For plutonium contaminated waste, this includes possession, storage, repackag-12 ing and shipment.
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I'l Amendment Application Date:
January 1986 Page No.:
ED(ON NUCLEAR COMPANY,Inc.
XN-2
)
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
6-eCM Ns Rm 1.2 Possession Limits 1.2.1 Uranium-235 (20,000 Kilograms) 112 a) 25 grams of any enrichment or form for analytical purposes.
b) 200 kilograms contained in uranium compounds enriched to a maximum of 19.99 wt% in the U-235 isotope (see Section 1.4.3 for restrictions).
c) The balance shall be contained in uranium compounds enriched to a maximum of 5 wt% in the U-235 isotope.
1.2.2 Plutonium (<500 grams) l12 a) One milligram and not more than 1.5 millicuries as contained in sealed sources and standards.
b) Less than 500 grams as Pu02 or Pu0 -UO2 as stored waste (see Appendix I 12 2
for restrictions).
l 1.3 Location of Use The location of use of the special nuclear material covered by this license shall be Exxon Nuclear's Richland, Washington fuel f abrication plant (address: 2101 Horn Rapids Road, Richland, WA 99352). Uranium is used in the Uranium 0xide Fuel Fabrication (UO ), Mixed 0xide & Speciality Fuels (MO&SF),
2 Engineering Laboratory (ELO), Engineering Test (ET), and Waste Uranium Recovery (WUR) facilities whereas plutonium shall be stored only in the MO&SF building. Also, sealed containers of uranium compounds, as well as packaged l
UO2 fuel
\\v 1.2 Amendment Application Date:
January 1986 Page No.,
E@ NUCLEAR COMPANY,Inc.
xN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
1.4.4 Plutonium Storage 2 and Pu0 -UO ) as waste shall be stored in the MO&SF 12 Plutonium (as Pu0 2
2 Building in accordance with the special conditions described in Section 2 of Appendix I.
1.5 Respiratory Protection Equipment Usage Pursuant to 10 CFR 20.103(c), Exxon Nuclear may employ the use of respiratory protective equipment to limit the inhalation of radioactive material by personnel, and may make allowances for such use in estimating exposures of individuals to such materials.
f Such equipment may be used 1) as a precautionary measure; 2) during mainte-nance work on contaminated equipment; 3) when abnormal operating conditions exist; or 4) during accidents.
The use and maintenance of such equipment shall be in accordance with Regulatory Guide 8.15, " Acceptable Programs for Respiratory Protection."
1.6 Criticality Accident Alarm System Exemptig Pursuant to 10 CFR 70.24(d), Exxon Nuclear has previously requested O
Amendment Application Date:
January 1986 Page No.:
EDRON NUCLEAR COMPANY,Inc.
xN-2 Ov/
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257 s
Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
TABLE 1.3-1 Specific Locations of Authorized Activities Location SNM Authorized Activity MO & SF Bldg.
Pu & Pu0 -UO2 Storage and repackaging.
2 12 contaminated waste UO2 (up to 19.99 Storage, blending, pressing, wt% U-235) sintering, fuel rod loading and downloading, fuel rod welding, fuel rod autoclaving, fuel element assembly; process tests; associated quality control activities.
UO2 Bldg.
Uranium Compounds All operational steps of fuel (including (up to 5 wt%
manufacturing from UF -UO2 conver-G h)
Powder Storage)
U-235) sion to packaging finished fuel L/
elements, scrap recycling and reprocessing; process tests; asso-ciated quality control activities.
UO2 (5 to 19.99 All operational steps of fuel wt% U-235) manufacturing involving U0 ;
2 associated quality control activi-ties; no operations involving. gas or liquid forms.
ELO Bldg.
Uranium Compound All operational steps of fuel (up to 19.99 wt%
manufacturing involving uranium U-235) compounds; process tests; no opera-tions involving UF6 gas; no opera-tions involving liquid forms of uranium of enrichments above 5 wt%
ET Bldg.
UOg(upto5 Hydraulic flow tests involving wt U-235) single fuel elements.
L.)
19 Amendment Application Date:
January 1985 Page No.:
I i
E(ON NUCL. EAR COMPANY,Inc.
XN-2 SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
12 b)
Drinking, Eating and Smoking Only foot-operated or side-operated water fountains are permitted in Contamination Control Areas. Normal water fountains are allowed in all other areas.
Eating is permitted in General Areas only.
Smoking is not permitted in Contamination Control Areas.
c)
Protective Clothing C\\
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Protective clothing is required for entry into Contamination Control Areas. The type (s) of clothing required is dependent upon the levels and types of contamination present or expected work assignments.
Visitors are instructed in the proper use of protective clothing.
d)
Respiratory Protection Appropriate respiratory protective equipment is required for entry into areas where airborne radioactive materials exist in excess of the concentrations stated in 10 CFR 20, Appendix B, Table I, Column 1. Such equipment is not used in lieu of proper ventilation or contamination control (see Section 1.5).
.)
3.4 Amendment Application Date:
January 1986 Page No.:
l
E@ NUCLEAR COMPANY,inC.
XN-2
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(v)
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
e)
Exposure awareness, planning and scheduling.
3.1.3.2 Radiation Surveys A detailed survey of radiation levels (S-y and 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 12 access.
Radiation surveys are performed on all incoming and outgoing shipments of radioactive materials.
t,-
3.1.3.3 Personnel Dosimetry All persons entering the exclusion area of the plant are required to wear S-y sensitive dosimeters at all times while they are in the exclusion area.
The B-y dosimeters are supplemented, as appropriate, by other types of dosimeters (i.e., finger rings, direct-reading dosimeters, and neutron dosimeters), and by radiation measurements made with radiation survey instruments in cases where the standard dosimeters either are lost, destroyed, cannot provide the desired information, or are not practical.
Personnel dosimeters shall be capable of measuring the following radiation exposure ranges:
i l
S-y dosimeters:
10 mrem - 1000 rem i
Neutron dosimeters:
100 mrem - 1000 rem l
w/
Amendment Application Date:
January 1986 Page No.:
3.8
ED(ON NUCLEAR COMPANY,Inc.
xN-2 m
(Q
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SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
intake of such materials by personnel as low as is reasonably achievable. As appropriate, and to a reasonable extent, operations involving readily dispersible forms of radioactive material are accomplished within enclosures (i.e., process equipment, glove boxes, glove-port hoods, laboratory type hoods, etc.) which are exhausted to facility exhaust air systems.
12 3.1.4.2 Ventilation Ventilation systems are designed and maintained to limit the spread of airborne contamination by maintaining air pressure gradients and airflows from areas of low potential airborne contamination to areas of higher potential contamination. These systems are balanced so that air pressure differentials between General and Contamination Control Areas are maintained
)
at a minimum of 0.05 inches of water.
Air locks are provided between areas where necessary to insure maintenance of proper air pressure differentials.
Periodic smoke tests are conducted to visually demonstrate that the airflows are in fact from areas of low contamination potential to areas of higher contamination potential.
Installed differential air pressure measuring instruments are read routinely and the readings recorded at least monthly.
[LI Amendment Application Date:
January 1986 Page No.:
3.10 i
l
Ep NUCLEAR COMPANY,InC.
XN-2 A)
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID:
The ventiliation rate in Contamination Control Areas is maintained at a minimum of seven air changes per hour for uranium operations.
The average minimum air velocity through openings in uranium handling hoods and equipment containing readily dispersible forms of uranium is maintained at 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 II, Column 1.
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 one stage of fire-retardant HEPA filters 12
)
which is assured to have installed efficiencies of at least 99.95% for 0.8 micron particles.
Recirculation air in the fuel fabrication buildings 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.
Recirculation air system HEPA filter installations are equipped with continu-ous pressure differential measuring / indicating systems, which are read and the readings recorded at least monthly.
O l
>V Amendment Application Date:
January 1986 Page No.:
3.11
E@ NUCLEAR COMPANY,InC.
XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET N0. 70-1257 v
Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
3.1.4.3 Contamination Surveys Surveys for radioactive contamination shall be performed, and corrective 12 action taken, in accordance with the following schedule.
A)
Facility Surveys A detailed survey of contamination levels is performed for each specific operation involving radioactive material when the operation is initi-ated, and frequently thereafter for a period of time, dependent on demonstrated operational controls as reflected in survey results.
Operations involved in the production of fuel are repetitive in nature, equipment and systems employed in development activities are normally p) similar to those used in the production facilities, and the containment t%_
and confinement principals are employed consistently throughout Exxon Nuclear's facilities, thus making it possible to effectively establish routine and repetitive contamination surveys. The frequency of routine surveys is determined by a combination of professional judgment and experience, and are periodically reviewed by the Health Physics Component.
In general, reduced frequencies are permittcd when the stability of an operation, as demonstrated by the consistency of survey results and the relationship between observed values and operational controls, is established.
However, the following minimum frequency schedule is applied to the facility contamination survey program:
Contamination Control Areas:
Weekly Radioactive Materials Areas:
Monthly Intermediate Areas:
Daily v'
Amendment Application Date:
January 1986 Page No.:
3.12 4
Ep NUCLEAR COMPANY,Inc.
XN-2
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SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257
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Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
General Areas:
Weekly Lunch Rooms Within the Exclusion Area: Daily Operational controls are considered adequate for uranium operations when the following conditions. prevail:
1)
No visible (smearable) contamination on exposed or non-hooded surfaces in the process areas (not applicable to nonroutine tasks being conducted under special controls).
2)
No smearable contamination on exposed or nonhooded surfaces in the process areas in excess of 10,000 dpm (alpha) per 100 cm2 (not applica-ble to nonroutine tasks being conducted under special controls).
/
3)
No smearable contamination on Intermediate Area floors in excess of 500 dpm (alpha) per 100 cm2, 4)
No smearable contamination in General Areas in excess of 200 dpm (alpha) per 100 cm2 and no fixed contamination greater than 2000 dpm (alpha) per 100 cm2, Uranium contamination in excess of the levels specified in 1, 2, 3 and 4 above are cleaned up when detected.
12 (nV) i 1
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l Amendment Application Date:
January 1986 Page No.:
3.13 l
Ep NUCLEAR COMPANY,Inc.
XN-2 O
e i
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257 V
Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
B.
Release of Persornel, Materials, Equipment, Facilities and Shipments Contamination surveys are performed on all personnel leaving Contamina-tion Control Areas, on all materials, equipment and 12 O
Amendment Application Date:
January 1986 Page No.:
3.14
E@ NUCLEAR COMPANY,Inc.
xn-2 m
(v)
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
facilities to be released from radiation protection requirements, and on all incoming and outgoing shipments of radioactive materials.
1)
Personnel Personnel contamination surveys are conducted according to the following schedule:
a)
All persons leaving Contamination Control Areas are required to survey themselves for contamination with survey instruments located at respec-tive step-off areas af ter removing protective clothing and prior to leaving the step-off area to enter General Areas.
A) b)
Personnel working in glove boxes (through glove ports fitted with gloves), or through glove ports in hoods, are required to survey their hands, forearms and the front of their clothing for contamination with survey instruments located at the work stations prior to leaving their 12 respective work stations.
c)
Personnel are not released to eat or leave the respective facility if their personal clothing is contaminated in excess of the following limits, except with the approval of the Radiological Safety Supervisor and the respective facility manager:
Smearable:
2001 dpm (alpha) per 100 cm2 Fixed Uranium:
2000 dpm (alpha) per 100 cm2 l12 d)
For routine release, personnel skin surface contamination shall not exceed background.
1 200 dpm (alpha) per 100 cm2 represents the practical lower detection O
level for most direct-reading contamination survey instruments.
gC Amendment Application Date:
January 1986 Page No.:
l l
Ep NUCLEAR COMPANY,InC.
XN-2 A
(v)
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
2)
Materials, Equipment, Facilities and Shipments Contamination surveys are performed by Health Physics Technicians on all materials and equipment removed from Contamination Control Areas, on areas and f acilities to be released from radiation protection require-ments, and on all incoming and outgoing shipments of radioactive materials.
These surveys and releases are performed in accordance with the conditions specified in Annex C (attached to the License by the NRC).
Materials and equipment exhibiting contamination levels in excess of those specified in Table I of Annex C may be released from Contamination Control p)
Areas for use under radiation protection requirements specified by the g
Radiological Safety Supervisor (or his delegated alternate.
The specific radiation protection requirements shall be properly documented.
3.1. 4. 4 Room Air Monitoring
.~
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 radioactive materials.
12 The air monitoring systems are multifacet and flexible combinations of equipment and instruments; the major components and use of these systems are described in the following sections.
v 3.16 Amendment Application Cate:
January 1986 Page No.:
l
EDRON NUCLEAR COMPANY,Inc.
XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET N0. 70-1257 1
Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
The following aspects of the bioassay program apply:
a)
An in-vivo examination is performed on all new employees who have previously handled special nuclear material prior to allowing them to work in Contamination Control Areas.
b)
A urine specimen from each employee scheduled for routine work in Contamination Control Areas is obtained and analyzed for uranium prior to allowing them to work in these areas.
c)
Employees working in uranium Contamination Control Areas submit monthly urine specimens for routine uranium analysis, d)
Employees routinely working in Contamination Control Areas shall receive 112 in-vivo examinations at least annually.
e)
If the most recent quarterly average of the airborne uranium concentra-l12 tion for any work area exceeds 25% of the respective OAC, 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.
Unusual occurrences with documented evaluation will not be included in calculating the quarterly average. 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.
Amendment Application Date:
January 1986 Page No.:
3.19
E@ NUCLEAR COMPANY,Inc.
xN-2 (O
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
f)
The following action guides and actions shall apply:
l12 1)
For transportable uranium compounds, an individual whose urine specimen exhibits a concentration in excess of 25 micrograms uranium / liter is required to submit another urine specimen on his first work day follow-ing the Company's receipt of the result, and at least weekly thereafter until a concentration of less than 25 micrograms uranium / liter is reached.
2)
For nontransportable uranium should the future dose comitment to an 12 individual's lung (based on in-vivo examinations) exceed 7.5 rem for the following 12 months, that individual will receive in-vivo examinations at least bi-monthly as long as he continues to work in Contamination (g)
Control Areas, and until that time when the future dose commitment to the lung for a subsequent 12-month period is less than 5 rem.
Any time that a dose evaluation is necessary, an investigation as to the possible source and cause shall be jointly conducted by the Radiological Safety Supervisor and the Health Physics Component of Corporate Licens-
- ing, g)
Individuals shall be restricted from work in Contamination Control Areas 112 according to the following:
n v
Amendment Application Date:
January 1986 Page No.:
E@ NUCLEAR COMPANY,inC.
XN-2 (m'v)
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID_:
Application - License Conditions Rev.
1)
For transportable uranium compounds, any individual whose urine specimen exhibits a concentration in excess of 100 micrograms uranium / liter; such individuals shall not be allowed to work in Contamination Control Areas until subsequent urine specimens exhibit a concentration of less than 25 micrograms uranium / liter.
2) for nontransportable uranium, any individual whose future dose comit-12 ment to the individual's lung (based on in-vivo examinations) exceeds 12 rem for a subsequent 12-month period; such individuals shall not be allowed to work in Contamination Control Areas until that time when his future dose comitment to the lung for a subsequent 12-month period is less than 7.5 rem.
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3.1.5 Radiation Safety Instruments and Equipment Sufficient radiation safety instruments, equipment and supplies are main-tained readily available at the plant and, as appropriate, strategically located.
The general capabilities of radiation safety instruments used to make radiation protection measurements are described in Table 3.1-1.
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 instruments:
a)
All radiation detection instruments are inspected, repaired when necessary, and calibrated at least semi-annually.
O V
3*21 Amendment Application Date:
January 1986 Page No.:
E(ON NUCLEAR COMPANY,InC.
XN-2 (mv)
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
3.3.3 Filter and Exhaust Air Monitoring All HEPA filter installations are equipped with continuous pressure differen-tial measuring / indicating devices, which are read and the readings recorded at least monthly.
HEPA filters are normally replaced before respective op readings reach four inches of water gage, and the op across final HEPA filters is not allowed to exceed four inches of water gage.
In-line exhaust air samplers, which operate continuously and whose samples are analyzed at least weekly, are located af ter each stage of HEPA filtra-tion.
The above described system will provide early warning of leakage of radio-l12 (G) active material through or around HEPA filters, or of blockage or rupture of HEPA filters.
Continuous isokinetic sampling is provided on all exhaust air stacks servic-ing areas in which uncontained radioactive materials are used, processed, or otherwise handled.
These samples are analyzed for respective radioactive material content on a weekly basis. Samples of gaseous effluents potentially containing uranium are analyzed for gross alpha activity in the range of 4.1 to 4.8 MeV.
(m Amendment Application Date:
January 1986 Page No.:
1 1
Ep NUCLEAR COMPANY,InC.
XN-2 SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257 v
Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
12 Additionally, fluoride monitoring is conducted on exhaust air stacks servic-ing UF -UO2 conversion equipment and facilities, and oxides-of-nitrogen 6
monitoring is conducted on exhaust air stacks servicing uranium scrap liquid recovery operations involving the use of nitric acid. Fluoride sampling is continuous with samples being analyzed at least weekly. Semi-annually, the particulate-to-gaseous fluoride ratio is determined in order to estimate the total fluoride released. Oxides-of-nitrogen sampling and sample analysis is conducted at least monthly during periods that respective operations are operated.
3.4 Liquid Effluent Controls Exxon Nuclear shall maintain and use all liquid effluent treatment systems
(
installed to maintain releases of radioactive material in liquid effluents to unrestricted areas as far below the limits specified in 10 CFR 20.106 as is reasonably achievable, and in accordance with 10 CFR 20.303. Procedures have been established which are adequate to assure that the effluent treatment systems function properly and that immediate steps are taken to rectify any observed deficiencies as soon as practicable. The liquid waste management plan outlined in this section (3.4, Liquid Effluent Controls) has been approved by the Washington State Department of Ecology and has issued Waste Discharge permit 3919 to regulate liquid effluents.
tv 3.44 Amendment Application Date:
January 1986 Page No.:
E$N NUCLEAR COMPANY,Inc.
xN-2
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET N0. 70-1257 V
Section/ Appendix / Attachment ID:
Application - License Ccnditions Rev.
a)
Vegetation samples are collected from the 450 feet and the 2000 feet Northeast sampling stations, and at the station 3/4 mile to the east monthly during the normal growing season. Quarterly vegetation samples are collected from the rest of the stations.
Vegetation samples from the 450 and 2000 feet Northeast stations are analyzed for uranium and fluoride; all other vegetation samples are analyzed for fluoride only, b)
Air samples are analyzed for fluoride. The sampling mechanism consists of a strip of filter paper treated with NaCO3 housed in a protected housing which allows ambient air circulation.
Samplers are set out at each sampling station and allowed to remain approximately 30 days; this procedure is repeated every month, m
)
c)
Soil samples are collected at each staton at least quarterly.
Only those collected from the 450 feet and 2000 feet Northeast stations are routinely analyzed; the rest are stored for historical purposes.
3.6 Solid Radioactive Waste Disposal Solids contaminated with radioactive materials are stored an-site awaiting treatment and/or shipment.
12 Uranium-contaminated solid wastes, which contain amounts of uranium larger than desirable to discard, are held for uranium recovery.
Solid wastes held for reprocessing are adequately sealed and appropriately labeled.
O)
(v Amendment Application Date:
January 1986 Page No.:
3.50
Ep NUCLEAR COMPANY,InC.
XN-2 n
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID:
Rm Radioactive solid wastes are disposed of by a private waste disposal contractor who is licensed and equipped to manage such wastes.
3.7 Storage of Special Nuclear Material 12 Except as specified in Sections 3.7. 2.1, 3.7.2.2 and 3.7.2.3, all Special Nuclear Material is stored within the process buildings or other buildings constructed and maintained to the following minimum specifications:
a)
Situated within the fences exclusion area.
b)
Ccnform to nuclear criticality safety controls specified in Section 3.2.
t c)
Covered by the plant criticality accident alarm system.
d)
Designed and constructed to withstand an average wind loading of 20 2
lb/ft,
e)
All packages (including solid waste and contaminated equipment) packaged and stored such as to prevent spread of contamination.
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Amendment Application Date:
January 1986 Page No.:
3.51
Ep NUCLEAR COMPANY,Inc.
XN-2 (m)
SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257 N_/
Section/ Appendix / Attachment ID:
Application - License Conditions Rev.
Table 3.3-1 Minimum Stages of HEPA Filters in Exhaust Air Systems No. of Definition of Material, Area and/or Facility Stages Uranium Contamination control areas, process equipment and enclosures where unencapsulated uranium compounds are handled................................................
1 Rooms and faciliites where closed fuel rods (both end-caps welded in-place) are processed or stored, or where closed containers which have been surveyed and released by Radiological Safety personnel of uranium compounds are stored.............................................
O 12 Recirculation Uranium
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In addition to the HEPA filtration provided in the normally operating recirculation air systems...........
1
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- N Amendment Application Date:
January 1986 Page No.:
i E@ NUCLEAR COMPANY,Inc.
XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID:
Rev.
" CONTENTS DELETED" 12 O
Amendment Application Date:
Page No.:
3.72
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If sustained immediately if this concentration 5$
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Ep NUCLEAR COMPANY,Inc.
xN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Appendix I - Special Conditions Rev.
APPENDIX I SPECIAL CONDITIONS CONTENTS n
Section No.
Section Title 1.
URANIUM ENRICHED FROM 5 WT% TO 19.99 WT% U-235 2.
PLUT0NIUM STORAGE 112 Amendment Application Date:
January 1986 Page No.:
~
Ep NUCLEAR COMPANY,InC.
XN-2 r(v)
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET N0. 70-1257 Section/ Appendix / Attachment ID:
Appendix I - Special Conditions Rev.
2.
PLUT0NIUM STORAGE Exxon Nuclear is presently in possession of plutonium, as Pu02 and Pu0 -
2 U0. This material is in the form of contaminated solid waste stored in 2
drums.
These containers shall be stored in the MO&SF building storage vault in accordance with the following controls:
1)
These stored containers shall be sealed with gaskets.
2)
The MO&SF building storage vault shall continue to be exhausted by the building HVAC system.
Two stages of HEPA filtration are provided O) prior to exiting the exhaust stack.
12 (v
3)
The air exiting the MO&SF building storage vault shall be continuously monitored and sampled, and the samples analyzed weekly for radioactive material content.
Assurance of containment shall be verified at least once every six months by visual inspection and smear survey of the stored waste drums.
The inspection and surveys will be documented. All indica-tions of drum leakage will be investigated and appropriate action taken.
4)
In order to provide continued containment, Exxon Nuclear may find it necessary to repackage the containers.
These activities shall be performed using a special RWP.
A 1-2.1 Amendment Application Date:
January 1986 Page No.:
l t
~
Ep NUCLEAR COMPANY,Inc.
XN-2 SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227, NRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID:
A endix I - Special Conditions Rev.
5)
All alpha discovered by smear surveys or air sampling shall be considered as plutonium alpha unless proven otherwise.
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1-2.2 Amendment Application Date:
January 1986 Page No.:
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