ML20209H232
| ML20209H232 | |
| Person / Time | |
|---|---|
| Site: | 07000754 |
| Issue date: | 07/14/1999 |
| From: | Murray B GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9907200172 | |
| Download: ML20209H232 (10) | |
Text
,
GE NuclearEnergy avnemanc cmwy VJ ICCM (s'JCINI DmfW I
Flob hhedos Huas SunM CA 94' dig July 14,1999 Director, Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission A'ITN: Document Control Desk Washington, D.C. 20555
)
References:
- 1. License SNM-960, Docket 70-754.
Dear Sir:
l The General Electric Company, Vallecitos Nuclear Center (VNC) requests that the following changes are made to the License Conditions (Appendix A) and Demonstration for Special Nuclear Material License Renewal for the Vallecitos Nuclear Center (Appendix B) to our material license SNM-960 (Ref.1). The requested changes are applicable to the January 21, l
1999, request for renewal (Ref. 2). The page changes are:
I 1.
Revise the description of authorized types of activities in Section 1.0 of Appendix A.
Replace pages A-1-1 and A-1-2 with the enclosed pages A-1-1 and A-1-2 dated 6/7/99.
The purpose of this change is to clarify that operations at VNC involving SNM consist of l
l laboratory-scale testing and that fuel manufacturing as a product, is not an authorized activity.
2.
Remove the reference to the " Region IV Walnut Creek Field Office" in paragraph 2.6 of Appendh B. Replace page 2-4 with the enclosed page 2-4 dated 6/7/99.
3.
Delete all but the first paragraph of Section 4.5 of Appendix B," Posting and Labeling".
This deletes the exemption from the provisions of 10CFR20.1601 for high radiation alarms. Replace pages 4-5 and 4-6 with the enclosed pages 4-5 and 4-6 dated 6/7/99. An exemption from all of the required high radiation area controls for a room or other area l
that is a high radiation area solely because of the presence of radioactive materials prepared for transport and packaged and labeled in accordance with the regulations of the Department of Transportation is provided in 10CFR20.1601(e). This exemption is used periodically at VNC provided that:
a) the packages do not remain in the area longer than 3 days; and b) the dose rate at 1 meter from the external surface of any package does not exceed [
0.01 rem (0.1 mSv) per hour.
l PDR ADOCK 07000754 h f 9907200172 990714 C
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USNRC July 14,1999 4.
Revise the last paragraph of Section 10.3.1 of Appendix B to update the description of waste handling at Building 103. Replace page 10-2 with the enclosed page 10-2 dated
- 6/7/99.
5.
Revise the f'irst paragraph of Section 10.3.3 of Appendix B to update the description of waste handling at Building 103, Replace page 10-3 with the enclosed page 10-3 dated 6/7/99.
6.
Replace Figure 10.1 of Appendix B," Building 103 Floor Plan (Ground Level)". The replacement contains an updated layout of the building crdiaust handling area. Replace page 10-8 with the enclosed page 10-8 dated 6/7/99.
These revisions reflect the current operations and facilities at the VNC.
If you or your stafThave any questions concerning this application, please contact me at (925) 862-4455. Thank you.
Very truly yours, L %_w B. M. Murray Senior Licensing Engineer ec:
W. L. Britz, Fuel Cycle Inspector USNRC, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064
1 W
LICENSE CONDITIONS FOR THE VALLECITOS NUCLEAR CENTER Set forth herein are the technical and administrative requirements proposed for governing the l
receipt, possession and use of the special nuclear material and associated byproduct material (as defined in Section 2.0 of this Appendix), subject to licensing and regulation by the Nuclear Regulatory Commission, in activities other than reactors at General Electric's Vallecitos Nuclear l
Center near Pleasanton, California.
\\
1.0 AUTHORIZED ACTIVITIES The following types of activities are authorized.
1.1 LABORATORY OPERATIONS 1.1.1 Chemical Analysis of the chemical and isotopic composition, concentration and behavior of special nuclear materials by wet chemistry and physical measurement techniques.
1.1.2 Metallureical Physical analyses and testing of physical and metallurgical properties of special nuclear materials.
1.1.3 Physics and Health Physics i
Measurements of radiation and its effects on instruments and on the structure and composition of materials.
License No. SNM-960 Docket No. 70-75 1 Sect. No.
- 1. 0 Page A-1-1 AppendixA Date 6/7/99 Amends Sect.(s) 1.1. 1. 2
1 1.1.4 Hot Laboratories Post-irradiation examination, testing, and analysis of fuel elements and materials in shielded enclosures by remote manipulative techniques; research and development and/or pilot plant activities.
1.1.5 Exoeriment Assembly Assembly, modification, cleaning and repair of unirradiated encapsulated experimental assemblies.
1.1.6 Re' search and Develonment l
Including but not limited to the above.
1.2 GENERAL SERVICES OPERATIONS 1.2.1 Eauinment Maintenance and Encineerine Design, fabrication, and testing of equipment containing special nuclear materials and maintenance of such equipment.
1.2.2 Storage Storage of special nuclear materials other than wastes in shielded containers and or at locations as applicable and in designated general purpose storage areas.
1.2.3 Transnortation and Transfer Inspection of packaging and preparation for shipment and/or transfer of special nuclear materials.
l License No. SNM-960 Docket No.70-754 Sect. No.
- 1. 0 Page A-1-2 AppendixA Date 6/7/99 Amends Sect.(s) 1.1. 5. 1. 2. 1. 3 i
I -
b.
Industrial Safety and Hvciene Function. Develop programs to protect the employees from industrial hazards, including operation of medical and safety education programs (located at San Jose),
c.
IInvironmental Safety Function. Develop programs to protect the employees and the general public from exposure to hazardous materials and assure proper disposal of hazardous wastes (located at VNC and San Jose).
2.6 TECHNICAL PERSONNEL CAPABILITIES The primary responsibility for operational radiation safety for the operations conducted in the various Vallecitos facilities involving special nuclear material rests with the supervisor or manager of each facility. Equally important are the knowledge and experience of personnel in the Nuclear Safety function. Since the issuance of License SNM-960 in 1966, the Commission's Regional office (Region IV and Region V) has inspected VNC to assure that adequate levels of l
technical expertise are maintained in all positions. R6sumds for key personnel are included as Addendum A to this section.
2.7 IMPLEMENTATION OF CRITICALITY CONTROL PROGRAM The program for protection against accidental conditions of criticality is implemented by means of functional responsibility assignments.
Managers whose operations require the use of quantities of special nuclear materials approaching a theoretical minimum critical mass, or greater, are responsible for integrating and measuring the efforts of line and staff participants in this program. The principal participants and their responsibilities are outlined below.
License No. SNM-960 Docket No.70-754 Sect. No.
- 2. 0 Page 2-4 Date 6/7/99 Amends Sect.(s)
- 2. 6
6 o
Neutron instrument calibrations are performed by measuring a response to a pulse c.
generator and to an Am-Be neutron source. Alternatively, calibration using a moderated Cf-252 source will be performed.
d.
Gamma calibrations using Cobalt-60 sources standardized with a meter which, in turn, was calibrated with traceability to the National Bureau of Standards.
All radiation monitoring instruments are calibrated as frequently as deemed necessary to assure reliability during use. Portable radiation monitoring instruments are calibrated on an annual basis, before initial use, and after repair.
Stack particulate monitor systems are calibrated by placing a uniformly distributed radioactive l
source in the same geometry as the filter paper used for collecting particulates. Stack gas monitor systems are checked routinely by placing a reference gamma source on the side of the Kanne chamber and observing whether the response falls within prescribed limits. Calibration with a known radiogas standard has been performed to verify this procedure, lodine monitors also are source checked routinely.
4.5 POSTING AND LABELING Instructions are established implementing the posting and labeling requirements of 10 CFR Part
- 20. Additional precautionary signs may be utilized to meet special requirements and detailed procedures. The area supervisor is responsible for maintaining the proper posting and labeling.
l l
License No. SNM-960 Docket No.70-754 Sect. No.
40 Page 4-S Date 6/7/99 Amends Sect.(s) 45
4.6 WASTE DISPOSAL Detailed procedures for the packaging, storage and removal of contaminated material which no longer is useful are established by operating components and reviewed by the Nuclear Safety J
function. The procedures define low, high, and intermediate levels of solid waste on the Sasis of a contact dose rate at the surface of outer packaging and provide specifications for container packaging to prevent loss of contents, repackaging of damaged units, labeling of contents and similar requirements. Procedures for handling or disposal ofliquid wastes in the various waste treatment facilities described in Section 3 are detailed in similar instructions. Area supervision is responsible for adherence to proper handling procedures, for obtaining approved containers and for arranging for transportation of wastes to the appropriate site storage or treatment facility.
License No. SNA1-960 Docket No.70-754 Sect. No.
40 Page 4-6 Date 6/7/99 Amends Sect.(s)
- 4. 5
.1 j
The chemistry areas on the second floor consist of typical chemical laboratories, a counting room, and an instrument room. Equipment in the chemistry laboratories includes the following:
various types of spectrophotometers, fluorimeters, gas chromatographs and a plasma emission spectrometer; other miscellaneous laboratory equipment; lead caves and glove boxes; vacuum systems, including necessary instrumentation; hoods designed foc handling radioactive materials; counting instrumentation; and mass spectrometers of various types.
A concrete storage vault for special nuclear material is provided on the ground floor. The vault has walls and ceiling of 8-inch minimum thickness, without penetrations, and a single locked door.
Packaged wastes and scrap materials which result from the licensed chemistry, metallurgy, and ceramics activities consist of paper, glassware, plates, rods, wire, samples, and other waste residue materials. These wastes normally will contain small amounts of by-product, source, and special nuclear materials. They are transferred to the site waste handling component (Building 102) for final packaging and disposal.
10.3.2 Ventilation System Inlet air supply for Building 103 is provided by air conditioning units fumishing filtered and tempered outside air to the building. Air passes from the office areas through 2-inch fiberglass roughing filters in the laboratory door grills, thereby minimizing the passage oflint and dust into the laboratories. These filters also minimize backfiow of potentially contaminated material in the unlikely event of complete exhaust system failure.
Laboratory doors are equipped with automatic closers.
Air is withdrawn through the hoods and glove boxes passing first through individual high-efficiency filters at each hood or glove box. Only filters having a minimum efficiency of 99.97%
for 0.3-micron-diameter homogeneous particles of dioctyl sebacate, DOS, are used in the laboratory effluent ventilation system. From the individual filters, the air is conducted through a second filtration in one of two parallel banks of high-efficiency (99.95% for the system) filters.
Thus filtered, it is discharged through a 48-foot-high,5 foot-diameter stack. The high-efficiency filters are fabricated of fiberglass to provide high resistance to fire. Filter frames are metal or chemically impregnated for resistance to fire, and permanent duct work is metal or polyvinyl License No. SNM-960 Docket Nr 70-754 Sect. No.
10 0 Page 10-2 Date 6/7/99 Amends Sect.(s) 10.32
i j
chloride. Each laboratory room used to conduct activities with radioactive materials is equipped with air sampling devices. However, airflow rates are adequate to perform routine operations l
with nuclear materials without the use of personnel respiratory protection. The main exhaust blower operates at approximately 36,000 cubic feet per minute. If complete ventilation failure occurs, an evacuation alarm is sounded automatically.
From 9 to 12 air changes per hour are provided for most laboratory rooms. However, in some rooms the airflow rate may be as high as 15 air changes per hour. Hood exhausts are dampered individually to maintain minimum face velocities on the order of 125 linear feet per minute across the openings. Glove boxes are operated at approximately -0.5 inch of water with respect i
to the room. Appropriate instrumentation indicating airflow and/or differential pressure is available.
The efficiency of the Building 103 ventilation filter system has been demonstrated by years of exhaust stack sampling data.
10.3.3 Radioactive Waste Facilities Dry contaminated waste materials generated in Building 103 are packaged as indicated in Section 3.5.1. Waste containers are transferred to Building 102 for inspection and then to the site radioactive material storage facility. Waste packages in the storage facility are periodically delivered to a licensed waste disposal contractor, l
License No. SNM-960 Docket No.70-751 Sect. No.
10.0 Page 10-3 Date 6/7/99 Amends Sect.(s) 10.3 3
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