ML20236W940
| ML20236W940 | |
| Person / Time | |
|---|---|
| Site: | 07000754 |
| Issue date: | 07/09/1998 |
| From: | Murray B GENERAL ELECTRIC CO. |
| To: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9808060321 | |
| Download: ML20236W940 (41) | |
Text
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GE Nuclear Energy twwan uga, VJhuCIL'5 Nyh n Cen!M Udb wwtu: %d bana CA 9 565 July 9,1998 Michael F. Weber, Chief Licensing Branch Division of Fuel Cycle Safety and Safeguards Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Reference:
License SNM-960, Docket 70-754
Dear Mr. Weber:
Enclosed are revised pages to the SNM-960 Materials License. The revised license pages includes changes to the Vallecitos Nuclear Center mailing address and telephone number, personnel and r6 sum 6 changes, conversion of regulation references from the superseded version of 10CFR20 to the revised replation, and other descriptive changes. Included in the other changes are the criticality detection system replacement, revision of the RML hot cell water supply system, and addition ofleased facilities at the VNC site. The leased facilities were previously used by GE personnel for conducting classified work for the United States government. The contract for this work was terminated by GE. It was acquired by a private company, who will continue the classified work and lease the facilities located at the Vallecitos Nuclear Center.
A listing and brief description of the changes to the SNM-960 Materials License follows:
1.
Page 1: The mailing address and telephone area code have been changed.
2.
Page 4, S-7, l.e.: Correct the reference to a "suberitical area" definition from Section 3.14 to Section 3.17.
3.
Cover page to Appendix A: Change mailing address of the Vallecitos Nuclear Center.
4.
Page A-5-4, Appendix A, Section 5.9.2: Correct references to 10CFR70.24.
5.
Page A-5-4, Appendix A, Section 5.9.3: Delete the section (alarm point exemption).
6.
Page A-8-1, Appendix A, Section 8.1.1.4: Correct typographical error.
7.
Page A-8-2, Appendix A, Section 8.3.3: Correct the reference from Section 8.11 to f
Section 8.10.
. l, 3 Ik 9808060321 9807d9 r
l PDR ADOCK 07000754 C
l Michael F. Weber (USNRC) July 9,1998 8.
Page A-8-3, Appendix A, Section 8.4: Restate the detection capabilities for laboratory analysis.
9.
Page A-8-4, Appendix A, Section 8.9: Change the format of Table 11 to Table 2.
10.
Page A-10-1, Appendix A, Section 10.1.1: Revise Stack Action Levels of Table 10.1, and add descriptive text.
I 1.
Cover page to Appendix B: Change mailing address of the Vallecitos Nuclear Center.
12.
Page 1-1, Appendix B, Section 1.1: Correct the reference to 10CFR70.22 to 10CFR70.25.
13.
Page 1-2, Appendix B, Section 1.2: Revise text of the site description.
14.
Page 1-3, Appendix B, Section 1.3: Revise the reference to Section 70.4(j) of 10CFR70 to j
Section 70.4.
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15.
Page 1-5, Appendix B, Section 1.5.4: Add the description ofleased facilities in Building 105.
16.
Page 1-8, Appendix B, Figure 1.2: Revise Site Plan to reflect removed buildings.
17.
Page 2-1, Appendix B, Section 2.0: Add text to describe GENE management oversight of VNC activities.
I 8.
Page 2-14, Appendix B, Figure 2.14: Revise VNC Administrative Organization Chart I
(delete ANA).
19.
Pages 2-1 A & 2-2A, Appendix B, Addendum A to Section 2.0, A.1: Revise title in G. L Stimmell's r6 sum 6.
20.
Page 2-5A, Appendix B, Addendum A to Section 2.0 A.4: Add II. A. Stuart's r6 sum 6.
21.
Page 3-3, Appendix B, Section 3.4: Add track etch dosimeters to the dosimeter description.
I 22.
Pages 3-5 & 3-6, Appendix B, Section 3.8.1: Revise the description of the criticality alarm system (new gamma detection system).
23.
Pages 4-1 & 4-2, Appendix B, Section 4.2: Revise reference to superseded 10CFR20 to the revised 10CFR20.
24.
Page 4-5, Appendix B, Section 4.4: Add alternative neutron detector calibration method.
25.
Page 4-6, Appendix B, Section 4.5: Revise reference to superseded 10CFR20 to the revised 10CFR20.
26.
Page 4-8, Appendix B, Section 4.9.1: Generalize the identity of the emergency hospital to which injuied persons may be taken. The destination decision is made by the emergency transport agency, unless there is radioactive contamination involved. Valley Care Medical Center in Pleasanton, California, has committed to receive contaminated patients.
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Michael F. Weber (USNRC) July 9,1998 27.
Page 6-1, Appendix B, Section 6.2.1: Revise the Building 102 air supply description.
4 1
28.
Page 6-8, Appendix B, Figure 6.1: Correct typographical error.
j 29.
Page 6-9, Appendix B, Figure 6.2: Revise plan of Building 102 Main Floor - Radioactive Material Areas (Remove Cell 6).
30.
Page 7-3, Appendix B, Section 7.3.2: Revise description of the RML hot cells water l
l supply system.
31.
Page 7-5, Appendix B, Section 7.3.7: Delete cell 6.
32.
Page 7-6, Appendix B, Section 7.3.10; Revise the description of the RML criticality alarm sensors.
33.
Nge 10-3, Appendix B, Section 10.3.3: Revise reference to superseded 10CFR20 to the revised 10CFR20.
34.
Page 10-4, Appendix B, Section 10.3.4: Revise the description of the Building 103 criticality alarm system (removed).
35.
Pages 10-8 & 10-9, Appendix B, Figures 10.1 and 10.2: Delete criticality detectors from Building 103 floor plans.
36.
Page 12-1, Appendix B, Sections 12.1 and 12.3: Add a description ofleased facilities in Building 105.
37.
Page 13-4, Appendix B, Section 13.1.5: Revise reference to superseded 10CFR20 to the revised 10CFR20.
38.
Page 13-4, Appendix B, Section 13.1.6: Correct the reference to a "subcritical area" l
definition from Section 3.16 to Section 3.17.
Any questions concerning this application should be directed to B. M. Murray on (925) 862-4455. Thank you.
Very truly yours, mW w
B, M. Murray l
Senior Licensing Engine r Enclosures I
_._____________________)
O GENuclearEnergy l
Vallecitos & Morris Operations LICENSE CONDITIONS 1
FOR THE i
VALLECITOS NUCLEAR CENTER l
APPENDIX A LICENSE SNM-960 DOCKET 70-754 General Electric Company, Vallecitos Nuclear Center 6705 Vallecitos Road, Sunol, California 94586 L-
5.9 CRITICALITY MONITORING 5.9.1 No transfers of fissile materials between criticality limit areas shall 1 - permitted in criticality areas required to have a monitor alarm system unless the system is operable.
Transfers may resume following repair and verification of the monitoring system's operability.
5.9.2 Exemption from the monitor alarm requirement of Section 70.24(a) of 10CFR70 is l granted for the Remote Handling Operation (RHO) pool and hot cells. At the high-level solid waste storage facility and the storage pit in the RHO pool area, for the purpose of conipli.mee with 70.24(a)(1) of 10CFR70, the source of a possible accidental condition of l criticality may be considered as the accessible surface of the eanh or concrete shielding.
5.9.3 Exemption from the requirements of Section 70.24 of 10CFR70 is granted for each area in which there is not more than one shipment of packages containing special nuclear materials licensed pursuant to 10 CFR Part 71 for transport outside the confines of the Vallecitos Nuclear Center (packages in any shipment which depend on special arrangement for nuclear safety shall be retained in that same arrangement during such storage); oc one safe batch of finished reactor fuel rods of assemblies, providing no i
activities could cause rearrangement of fuel-bearing portions into more reactive
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configurations; or which meets the requirements of a subcritical area as defined in Section 3.15 of this Appendix.
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i License No. SNAf-960 Docket No.70-754 Sect. No.
50 Page A-5-4 AppendixA Date 7/9/98 Amends Sect.(s) 592.59.3
1 8.0 RADIATION CONTROL CONDITIONS -
l TECHNICAL AND OPERATING REQUIREMENTS i
8.1 AIR CONTAMINATION CONTROL 8.1.1 The following design criteria for ventilation systems shall be used to provide air contamination control.
8.1.1.1 Airflow shall be from areas oflesser contamination to areas of higher contamination.
Potential accident conditions shall be considered.
8.1.1.2 Duct flow velocities and design shall be such to minimize possible accumulation of contamination.
8.1.1.3 Air shall be sampled continuously in normally occupied areas in which dispersible SNM is handled. Samples are analyzed for gross alpha and gross beta-gamma.
I 8.1.1.4 Potential airbome radioactivity-producing operations shall utilize close-capture ventilation devices, e.g., hoods and high-velocity local exhaust when compatible with l
8.1.1.5 All ventilation exhaust systems for facilities that routinely handle dispersible SNM in quantities in excess of the limits specified in Appendix C of 10CFR20 shall be sampled continuously as proof of filter performance. All HEPA filters for such facilities will be fire resistant.
8.1.1.6 At least one filter in each such stream (8.1.5) shall be equipped with a device for measuring differential pressure that shall be read monthly. Filters shall be changed when readings deviate from specification values (.8 to 4.0 inches WG) or following I'
evidence of damage.
License No. SNM-960 Docket No.70-754 Sect. No.
- 8. 0 Page A-8-1 AppenditA Date 7/9/98 Amends Sect.(s) 81.1.4
8.1.2 Smearable contamination in excess of 10,000 dpm/100 cm alpha in normal working 2
areas shall be cleaned up expeditiously.
8.2 INSTRUMENT CAPABILITY Dose rate range capabilities of portable instrumentation shall include the following:
1 to 50,000 mR/h (10-5,000 pR/hr for enviromnental monitoring) gamma beta
- 4 to 200,000 mrad /h 1 to 5,000 mrem /h neutrons 8.3 CONTAMINATION DETECTION 8.3.1 Contamination detection capabilities of portable instrumentation shall be:
alpha 200 to 300,000 disintegrations per minute beta-gamma twice background to 400,000 disintegrations per minute on a Geiger-Mueller counter 8.3.2 Contamination detection capabilities of portable instrumentation when used in the smear j
survey technique shall be 200 disintegrations per minute for alpha and 500 disintegrations per minute beta-gamma.
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8.3.3 Detection equipment shall be maintained on site to meet the requirements of Section 8.10 l
of this Appendix for contamination-free items.
8.3.4 For unconditional release surveys (Section 8.10), laboratory-type counting equipment may be used to meet the release limits of Table 8.2.
License No. SNM-960 Docket No.70-754 Sect. No.
- 8. 0 Page A-8-2 l
l AppendixA Date 7/9/98 Amends Sect.(s) 833 j
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8.4 SAMPLE DETECTION Sample detection capabilities for laboratory analysis of effiuents shall be no greater than the concentrations specified in 10CFR20, Appendix B, Table 2. The detection limits of the VNC Analytical Counting Lab are listed in Section 3.9 of Appendix B.
8.5 EXPOSURE DETECTION Personnel dosimeters shall be capable of detecting gamma, beta, and x-ray radiation. Additional neutron detection capability shall be available as appropriate. Primary dosimeters (film badges, TLD dosimeters) are worn in a manner as to record the maximum whole body exposure.
8.6 INSTRUMENT CALIBRATION Portable monitoring instruments shall be calibrated upon initial acquisition, after major maintenance, and at least annually.
Fixed gamma area monitors used as detection or warning devices (i.e., not for personnel monitoring) shall be source checked at least annually.
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8.7 INSTRUMENT CIIECK SOURCES Field check sources shall be available for use in functional response checks of portable radiation-measuring instrumentation.
8.8 LIQUID WASTE DISPOSAL l
Potentially contaminated liquid wastes shall be collected, solidified, and disposed of as solid waste.
i License No. SNM-960 Docket No.70-754 Sect. No.
80 Page A-8-3 AppendixA Date 7/9/98 Amends Sect.(s)
- 8. 4
8.9 AIRBORNE EFFLUENT CONTROL Potentially contaminated airborne effluents shall be released through HEPA filter systems which shall be at least 99.95% efficient for 0.3-micrometer particles. Such effluents shall be limited at i
the point of release to the atmosphere so that the annual average concentration at the site
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boundary does not exceed the concentrations specified in 10CFR20, Appendix B, Table 2, j
Column 1. The limits at the points of release shall be based on a x/Q calculation, reconcentration i
factors, and the effects of other site stacks. If the environmental sampling program indicates a
{
reconcentration of these materials, the release levels shall be lowered such that the reconcentration trend is reversed.
j These represent maximum release limits. Actual normal releases shall be controlled to meet
]
ALARA objectives (see Section 10.0).
8.10 CONTAMINATION-FREE ARTICLES Articles which have been handled, used or stored in areas with a potential for contamination with radioactive materials may be disposed of or transferred to persons not licensed to possess radioactive materials when all of the following conditions are satisfied:
8.10.1 Either all surfaces are accessible for survey or it is reasonable to assume from the design and usage that no radioactive materials could have contaminated inaccessible surfaces without having contaminated the accessible surfaces as well.
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8.10.2 Articles are considered contamination free which meet the requirements of Table 8.2.
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License No. SNM-960 Docket No.70-754 Sect. No.
80 Page A-8-4 l
ApperidixA Date 7/9/98 Amends Sect.(s)
R9 1
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10.0 EFFLUENT AND ENVIRONMENTAL SAMPLING 10.1 EFFLUENT SAMPLING Gaseous and liquid effluents are sampled for compliance with 10CFR20 at the site boundary.
Action levels have been assigned to various parameters. When an action level is reached, the cause must be investigated. (Note: Corrective action may or may not be required.)
10.1.1 Gaseous Effluent Sampline (Continuous)
Table 10.1. Stack Action Levels Concentration Parameter (pCi/cm')
3 Gross Alpha 3.0 x 10 "
l Gross Beta-Gamma 3.0 x 10 "
I-131 6.0 x 104 Noble Gases 1.4 x 10
3 1
The values in Table 10.1 are based on the Building 102 stack and a nominal flow rate. Not all I
I stacks are sampled for all parameters. Action level concentrr,tions will vary with the stack flow rate.
10.1.2 Liauid Effluent Sampline Each site retention basin is sampled and the sample counted prior to release to the environment.
l Table 10.2. Lianid Effluent Action Levels L
Action Level Parameter
( Ci/cm')
Gross Alpha 3.0 x 10~'
Gross Beta-Gamma 5.0 x 10-8 License No. SNM-960 Docket No. 70-7S4 Sect. No.
10.0 Page A-10-1 AppendixA Date 7/9/98 Amends Sect.(s) 101.1 & Table 10.1
O GENuclearEnergy Vallecitos & Morris Operations DEMONSTRATION FOR SPECIAL NUCLEAR MATERIAL LICENSE RENEWAL FOR TIIE VALLECITOS NUCLEAR CENTER APPENDIX B LICENSE SNM-960 DOCKET 70-754 MARCH 27,1989 (REVISED DECEMBER 1,1992)
(REVISED DECEMBER 3,1993)
I General Electric Company, Vallecitos Nuclear Center 6705 Vallecitos Road, Sunol, California 94586 j
1.0 GENERAL INFORMATION 1.1 CORPORATE AND FINANCIAL This application is filed by General Electric Company, a New York corporation with a principal place of business at One River Road, Schenectady, New York. A list of the names of the directors and officers appears in General Electric's latest Annual Report, a copy of which is forwarded to the Commission each year for inclusion in Docket 70-754. All correspondence may be addressed to 3135 Easton Turnpike, Fairfield, Connecticut 06431.
General Electric is not controlled by any alien, foreign corporation, er foreign government; it is controllec' by its Board of Directors and the Officers elected by the Board.
General Electric is a publicly held corporation whose stock is traded on the principal security exchanges. The applicant has no knowledge or any information indicating any appreciable ownership of General Electric stock by an alien, foreign corporation, or foreign government. No person owns of record or is known by General Electric to own beneficially one percent or more of the outstanding shares ofits capital stock.
Financial information required by 10CFR70.25 appears in the aforementioned Annual Report.
1.2 LOCATION AND GENERAL DESCRIPTION OF VALLECITOS NUCLEAR CENTER The General Electric Vallecitos Nuclear Center (VNC) is operated in conjunction with the operation of a 100-kW nuclear research reactor, for the development and examination of reactor fuels, and to provide nuclear products and services. It is located near the center of the Pleasanton quadrangle of Alameda County, California. The laboratory is east of San Francisco Bay, approximately 35 air miles east-southeast of San Francisco and 20 air miles north of San Jose.
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The site is indicated on the Bay Area map, Figure 1.1. The nearest sizeable towns are Pleasanton License Ao. SNAf-960 Docket No.70-754 Sect. No.
- 1. 0 Page 1-1 l
Date 7/9/98 Amends Sect.(s) 1.1 l
L__________________________---------______________-----__
with a 1990 population of approximately 51,000 located 4.1 air miles to the north-northwest, and l
Livermore with a population of approximately 57,000 located 6.2 air miles to the northeast. A United States Veterans Administration Hospital with a population of approximately 500 is located about four miles to the east.
The site is on the north side of Vallecitos Road (State Route 84), which is a two-lane paved highway. The ' Union Pacific railroad lies about two miles west of the site. The laboratory site consists of approximately 1,600 acres, about one-third of which is relatively flat. Approximately 1,400 acres of the site are leased for raising feed crops and cattle grazing.
There is light industrial activity within a 10-mile radius of the plant. The light industry is located l
at Pleasanton, Fremont and Livermore, but these towns are not industrial centers. The city of San Jose to the south, 20 miles distant, and Oakland and San Francisco, 30 and 35 miles, respectively, to the northwest are the major industrial centers in the vicinity. In the southeast quadrant, there are no industries and very sparse population for 20 miles and beyond.
The property on which the laboratory buildings are located is drained by ditches leading to Vallecitos Creek. This creek discharges to Arroyo de la Laguna near the north end of Sunol Valley, two to three miles southwest of the property.
Water is supplied from the Hetch-Hetchy aqueduct by means of a 14-inch line capable of supplying over 3,000,000 gallons per day. A 500,000-gallon storage tank is provided on the laboratory site. One hundred thousand gallons are reserved for fire protection.
Electrical power is supplied by Pacific Gas & Electric to the main laboratory substation from whence it is distributed to each building on the site.
A sewage treatment system is provided in the southwest corner of the site. Effluent from this system is disposed to site land.
i License No. SNM-960 Docket No.70-754 Sect. No.
- 1. 0 Page 1-2 Date 7/9/98 Amends Sect.(s)
- 1. 2
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l 1.3 GENERAL PLANS A% bsEs OF SPECIAL NUCLEAR MATERIALS I
This application requests authorization under Title 10, Code of Federal Reg a.tions, Part 70, to receive and possess the special nuclear material designated in Section 1.4 herein; to receive and possess the special nuclear material and associated byproduct material produced by the irradiation thereof; and to use said special nuclear materials in research and development activities as defined in Section 70.4, in chemical and physical analysis, and examination and l
investigation of nuclear fuels, associated materials and devices at the Vallecitos Nuclear Center.
1.4 SPECIAL NUCLEAR MATERIAL POSSE.SSION LIMITS 1.4.1 Vallecitos Nuclear Center The special nuclear materials used in connection with activities authorized by License SNM-960 at the Vallecitos Nuclear Center will not at any time exceed those limits listed in Section 2.1 of Appendix A to License SNM-960.
1.4.2 Form and Enrichment Specifications l
The majority of the Vallecitos Nuclear Center activities are conducted in facilities and under l
procedural controls which accommodate any chemical or physical form and any U-235 isotopic content. If specific limitations are placed on these parameters in connection with an individual activity in order to assure the radiation or nuclear safety of that work, the limit is described in the appropriate section of this application entitled," General Plans and Uses of Materials".
l License No. SNM-960 Docket No.70-754 Sect. No.
- 1. 0 Page 1-3 Date 7/9/98 Amends Sect.(s)
- 1. 3 O
a
1 l
1.5.4 Buildine 105 Just north of Building 102 is Bu!! ding 105. The principal facilities located in this building are an experimental reactor (the Nuclear Test Reactor) and laboratories leased to another company. ' The laboratories in Building 105 use only minute quantities of special nuclear materials, which are l
possessed and controlled by GE.
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1.5.5 Eneineerine Shon
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l Building 106 contains various maintenance shops (e.g., machine, carpentry, electric, and instrument calibration facilities).
1.5.6 Solid Radioactive Waste Storaec Facility Solid radioactive wastes generated at the various laboratory and facility locations are stored in j
the waste storage facility located approximately midway between the deactivated Vallecitos l
Boiling Water Reactor (VBWR) and General Electric Test Reactor (GETR) areas. This storage
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area includes shielded horizon'al tubes for storing 5-inch and 7-1/2-inch-diameter waste liners.
1.5.7 Waste Evanorator Plant The Waste Evaporator Plant is located adjacent to the deactivated VBWR site. This plant is used to concentrate and solidify liquid radioactive wastes generated at the Vallecitos Nuclear Center or other licensed facilities prior to transfer to authorized waste disposal firms or waste burial sites. Such wastes may contain minute quantities of special nuclear material.
l 1.5.8 Reactors and Auxiliary Facilities The ESADA-Vallecitos Experimental Superheat Reactor (EVESR), th:: VBWR, and the GETR are deactivated.
License No. SNM-960 Docket No.70-754 Sect. No.
- 1. 0 Page 1-5 l
1 Date 7/9/98 Amends Sect.(s) 1.5.4 1
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2.0 ORGANIZATION AND ADMINISTRATION i
I All Vallecitos Nuclear Center (VNC) activities involving SNM and radioactive materials are l
l conducted under the management of General Electric Nuclear Energy (GE-NE).
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Several components of GE NE perform activities at VNC. However, the Manager, Vallecitos
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and Morris Operations (V&MO), who is responsible for regulatory compliance at VNC, reports i
to the President, GE Nuclear Energy.
2.1 ORGANIZATION
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An organization chart for VNC is included at the end of this section as Figure 2.1.
An organization chart for the Nuclear Safety function is included as Figure 2.2.
2.2 DELEGATION OF RESPONSIBILITY l
The management of the components at VNC has established a policy of protection of employees, the public, and the environs from potential industrial, radiation, and nuclear hazards that could occur through activities conducted in each component's facilities.
He has delegated the responsibility for implementing this basic policy through line managers to the manager and supervisor of each activity in which radioactive materials are handled, used or stored.
Additionally, V&MO has experienced and' competent staff personnel to provide expert advice and guidance to all components in matters of radiation and criticality safety. The Manager,
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V&MO, has been delegated responsibility to act as the chief compliance safety officer for all VNC operations. Industrial safety is provided for VNC by the Industrial Safety & Hygiene function located in San Jose.
With respect to the radiation and criticality safety programs, the basic line and staff relationships are illustrated in Figures 2.3 and 2.4, respectively.
LicenseNo. SNM-960 Docket No.70-754 Sect. No.
2.0 Page 2-1 Date 7/9/98 Amends Sect.(s)
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ADDENDUM A TO SECTION 2.0 R8 SUM S OF KEY MANAGERIAL AND SAFETY PERSONNEL A.1 G. L. Stimmell: Manager, Vallecitos & Morris Operations; B.S., Mechanical Engineering, l
California State University, Fresno; M.B.A., University of Santa Clara.
1 Mr. Stimmelljoined the General Electric Company, Vallecitos Nuclear Center (VNC) in 1964 on the Vallecitos Training Program. He had assignments in Nuclear Safety, Test Engineering, the Radioactive Materials Laboratory, and Design Engineering. In 1971, he became a Project 1
Engineer responsible for irradiation programs conducted in the GE Test Reactor (GETR). In 1974, he became Manager, Design and Test Engineering, where he managed a multidisciplined I
engineering unit responsible for the design and analysis of experiments for irradiation in the GETR, and design of equipment for several VNC facilities, including the GETR and RML.
During this period, the engineering unit also conducted analyses in support oflicense renewal for the GETR and the Nuclear Test Reactor (NTR).
From 1984 to 1986, Mr. Stimmell became a Senior Program Manager, Neutron Sources. In this position he was responsible for establishing the Californium-252 neutron source production facilities and the development of neutron source markets.
From 1986 to 1988, Mr. Stimmell was the Manager of Project Engineering for the Nuclear Waste Repository Project where he was responsible for the development and design of waste packages and repository equipment for a high-level waste repository in salt.
From 1988 to 1992, he became Manager of Systems Engineering for the Advanced Liquid Metal L
Reactor project. In this capacity he was responsible for the coordination and specPication of overall plant design requirements and the integration of the systems level plant design. He was also responsible for the refueling system concept development, plant operations and maintenance assessments and staffmg estimates, and fuel cycle facility concept development. He was also responsible for coordination and support ofinternational ccJlaboration by arranging economics and safety technical exchanges with the European Fast Reactor Associates.
License No. SNM-960 Docket No.70-754 Sect. No. 2.0. Addendum A Page 2-1A l
l Date 7/9/98 Amends Sect.(s) 2.0.A.]
_ _ ~
In 1992, Mr. Stimmell retumed to VNC as the Manager ofIrradiation Processing (now V&MO).
l He is responsible for the operation of the radioisotope production and post-irradiation examination facilities, the operation of the Nuclear Test Reactor and its support functions, and three shut down reactors maintained under possess-only licenses. Mr. Stimmell has been designated by the General Managers of the General Electric divisions represented at VNC as the manager responsible for the nuclear safety, industrial safety, and environmental compliance for the entire site.
Mr. Stimmell is also a Licensed Professional (Mechanical) Engineer in the State of California.
i V
License No. SNM-960 Docket No.70-754 Sect. No. 2.0. Addendum A Page 2-2A Date 7/9/98 Amends Sect.(s)
- 2. 0. A. ]
-_.________________u
A.4
_H. A. Stuart: Specialist, Radiological Engineering.
Mr. Stuart joined the U.S. Navy in 1983 and was trained as a nuclear reactor operator and nuclear plant electronics technician. Following his training, he was assigned as a reactor operator on the l
U.S.S. Enterprise. His duties included operating a nuclear reactor, supervising a shut down I
l nuclear power plant, and coordinating training and supervising maintenance for a reactor controls division.
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j In 1992, Mr. Stuart joined the General Electric Company, Vallecitos Nuclear Center (VNC) and certified as a Radiation Monitoring Technician. In this capacity, he evaluated radiological conditions, specified appropriate radiological safety measures, and ensured that radiation workers followed safe work practices.
In 1997, Mr. Stuart was assigned to his current position of Specialist, Radiological Engineering.
His responsibilities include the auditing and regulatory oversight of the Nuclear Test Reactor and the non-operating reactors at VNC, oversight of the bioassay program and health physics instrumentation, maintenance of'.he site Special Nuclear Material inventory, and review of safety standards, procedures, and proposed site activities.
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l License No. SNM-960 Docket No.70-754 Sect No. 2.0. Addendum A Page 2-SA i
Date 7/9/98 Amends Sect.(s)
- 2. 0. A. 4
3.4 FILM BADGES AND POCKET DOSIMETERS Film badges or TLD's are worn where there is potential for radiation exposure. Albedo and/or track etch neutron dosimeters are used where appropriate. Pocket ionization chamber dosimeters may be used. If pocket dosimeter results indicate an off-scale or unexpectedly high reading, the badge is processed; and if these results are confirmed, the circumstances are investigated and the individual is removed from radiation work if appropriate. TLD extremity dosimeters are worn when radiation exposure to the hands is expected to exceed total body exposure to a significant degree. Film, TLD, and track etch dosimeters are serviced by a commercial vendor.
l 3.5 RADIOACTIVE WASTE FACILITIES The wastes containing the most significant quantities of special nuclear material are items such as irradiated fuel specimens which have been examined and analyzed at the Building 102 hot cell complex. Some of the wastes are delivered to a licensed waste contractor while others are stored at the Hillside Storage Facility (HSF) complex. Other radioactive wastes ordinarily contain only gram or milligram quantities of special nuclear materials. Facilities used for waste storage and i
handling at the site are specified in the sections which follow.
3.5.1 Dry Wastes l
Dry contaminated wastes are placed in sealable drums, tubes, boxes, or casks available at each l
laboratory or facility where such wastes may be generated. Each laboratory or facility maintains l
a designated area for temporary waste storage. Dry wastes are transferred to Building 102 for final inspection and any necessary repackaging. Waste packages then are transferred to the site radioactive material storage facility, HSF.
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License No. SNM-960 Docket No.70-754 Sect. No.
- 3. 0 Page 3-3 l
Date 7/9/98 Amends Sect.(s)
- 3. 4
I 3.6 EMERGENCY EQUIPMENT
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A vehicle is available to Radiation Safety and can be equipped quickly with a supply of
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protective clothing, first aid equipment, respiratory protection equipment, and portable 1
instrumentation and sampling equipment for use during emergencies. Emergency equipment also is stored in selected areas on site.
3.7 INDUSTRIAL SAFETY EQUIPMENT In conjunction with the radiation safety program at VNC, industrial health and safety of VNC personnel also are emphasized. Some of the protection facilities and equipment which are available include portable extinguishers, sprinkler systems, and a wide range of typical industrial safety equipment.
3.8 CRITICALITY ALARM SYSTEMS In any Vallecitos Nuclear Center area in which special nuclear materia! containine more than 500 grams of U-235 is used or stored and does not otherwise qualify as a "suberitical area" as defined in Section 3.16 of Appendix A, a monitoring system, including gamma-or neutron-sensing devices which will energize an audible alarm in the event of criticality, is installed and i
maintained. The systern in use on site is described in the following paragraphs.
3.8.1 Gamma Detection System I
l This monitoring system consists of three commercially designed and manufactured gamma l
detectors which monitor each designated area. Two of the three detectors which are subjected to a dose rate in excess of preset alarm points will cause an alarm condition. Failure of any l
detection circuit component which would prevent criticality detection activates a warning light on the unit. Failure of any signal-producing component is detected during the monthly test.
The system is capable of energizing the alarm when the radiation level at a distance of 2 meters from the special nuclear material is equivalent to 20 rads of combined neutron and gamma radiation within one minute.
License No. SNM-960 Docket No.70-754 Sect. No.
- 3. 0 Page 3-5 Date 7/9/98 Amends Sect.(s) 3.8.1
_1
Sensing devices are positioned within 120 feet, air equivalent, of every required location where special nuclear material is handled, used or stored. The system is tested by exposing the detectors to appropriate sources and sounding the alarm monthly. The alarm system is designed so that the alarm continues to sound until reset. The alarm is clearly audible in all locations where radiation exposure may result from an accidental criticality incident. If a facility does not have emergency backup power, all movements of SNM are suspended during a power failure.
3.8.2 Excepted Areas l
Criticality sensors are not provided below the surface of the water in the RML storage pool or I
within the RML cells, nor in the horizontal tube solid waste facility. Shielding surrounding the special nuclear material is as follows:
RML Storage Pool 16 feet of water e
e RML Hot Cells 1.5 to 3.0 feet of high-density concrete Horizontal Waste Storage 5.5 feet of compacted earth i
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l License No. SNM-960 Docket No.70-754 Sect. No.
30 Page 3-6 Date 7/9/98 Amends Sect.(s) 3.8.1 J
l 4.0 RADIATION PROTECTION PROCEDURES A system of Vallecitos Safety Standards establishes the site radiation and criticality protection and regulatory compliance programs. The manager of the Nuclear Safety component issues the standards with review and comment of the managers of the major organizational components l
located on the site.
Currently, there are about 40 standards dealing with radiation protection matters. The principal features of these are summarized below.
4.1 PERSONNEL WORK RULES Requirements are established to prevent or minimize the hazards of radioactivity and radioactive materials. Eating, storing or preparing food, smoking, or storing tobacco are not normally permitted in areas where there is a potential for contamination with radioactive materials. Food containers may not be used for storing or handling radioactive materials.
General Electric furnishes protective clothing for service in areas where contamination is likely to contact personal clothing. Protective clothing standards are set by the site Radiation Safety function to assure effective quality, positive identification, and to avoid use for other than its intended purpose. The amount and type of clothing for any specific activity are assessed on the basis of pgtial for personnel contamination.
4.2 LIMITS OF RADIATION IN CONTROLLED WORK AREAS All Vallecitos locations where there is a potential for radiation exposure are classified (radiation area, high radiation area, etc.) in accordance with the definitions of 10CFR20, Sections 20.1003, 20.1502,20.1601, and 20.1602. General Electric's philosophy of protection is to keep radiation exposure at the lowest reasonably achievable level in all cases.
I License No. SNM-960 Docket No.70-754 Sect. No.
- 4. 0 Page 4-1 Date 7/9/98 Amends Sect.(s)
- 4. 2 l
With respect to operations which could produce airborne radioactive contamination, managers of facilities are responsible for providing ventilation equipment to meet the concentration limits of 10CFR20.1502 without the necessity, or credit, for personal respiratory devices during routine operations. In certain nonroutine situations where adequate ventilation equipment could not ensure control of airborne material, respiratory protection of demonstrated integrity is utilized.
In such cases, respiratory protection equipment will be used in accordance with NUREO 0041,
" Manual of Respiratory Protection Against Airborne Radioactive Materials".
The respiratory equipment currently in use at VNC is approved by the National Institute of Occupational Safety & Health (NIOSH) and, as such, achieves compliance with 10CFR20.
U.S. Divers Company's Survivair self-contained breathing apparatus (SCBA) or other NIOSH-approved SCBA having a backpack air supply, hose, harness, pressure-demand regulator, and a facepiece may be worn in emergency situations.
VNC has adopted only equipment that is approved by NIOSH.
No individual will be permitted to work more than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per week under conditions requiring n: asks. No individual will be permitted to work in a mask until he has received a medical clearance for respirator use and has been thoroughly instructed in methods of proper use, fitting, and field testing of respirators.
4.3 PERSONNEL MONITORING Instructions for the use of film and TLD badges, finger TLD dosimeters, and pocket dosimeters include the proper part of the body on which the device is to be worn and procedures to prevent spurious readings. In addition, personnel are instructed to use monitoring instruments upon leaving a radioactive materials area.
Hand-and-shoe counters are also provided at some locations.
l License No. SNM-960 Docket No.70-754 Sect. No.
- 4. 0 Page 4-2 Date 7/9/98 Amends Sect.(s)
- 4. 2
Neutron instrument calibrations are performed by measuring a response to a pulse c.
generator and to an Am-Be neutron source. Altematively, 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 source in the same geometry as the filter paper used for collecting particulate. Stack gas monitor systems are checked routinely by placing a reference ganuna 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. Iodine 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.
However, in view of the degree of control inherent in the security of the site and the required prerequisite training program for employees, there is an exemption from the provisions of 10CFR20.1601 for high radiation area alarms which General Electric deems should be continued.
l 1
An exemption from the alarm provisions of 20.1602(a) is requested for any area or location j
which is:
License No. SNM-960 Docket No.70-754,_.
Sect. No.
- 4. 0 Page 4-5 Date 7/9/98 Amends Sect.(s) 4.4 j
ll.
a.
(1)
Used for the temporary placement of strong, weatherproof containers such as shipping casks not exceeding the limits of 49CFR173.441, i.e., 200 mR/h at any l
point of readily accessible surface; or (2)
An established area in,which there may be radioactive materials in containers, the readily accessible surfaces of which do not exceed dose rates of 1,000 mR/h at any time and which do' not exceed 100 mR/h at the barrier for any continuous period greater than 30 days, such as radioactive waste pickup areas from which wastes are collected on a weekly or monthly basis; and is b.
Located within the 94-acre inner fenced exclusion area of the site; and is Bounded by a distinctively colored rope or chain providing a barrier at dose rate values not c.
greater than 100 mR/h and posted as a High Radiation Area in accordance with 10CFR20.1902(b).
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 function. The procedures define low, high, and intermediate levels of solid waste on the basis 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 of liquid 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. SNM-960 Docket No.70-754 Sect. No.
- 4. 0 Page 4-6 Date 7/9/98 Amends Sect.(s)
- 4. S 1
1
l 4.9.1 Nuclear Emergencies The accidental criticality alarm is a distinct sound which is activated automatically when criticality detection instrumentation in that local area reaches a preset limit. Personnel in the affected area immediately evacuate.
At the same time, the origin of the signal is designated at the main security building. The site-wide public address system is used to instruct all personnel at the site concerning further action.
Upon the sounding of any alarm, an assessment is made of the indicated or reported situation, and whatever action is deemed necessary to minimize personnel injury and property damage is taken. A radio communication system and a dedicated telephone network can be used for conference contact with VNC site managers representing most fields of technical competence at the site, with the person reporting the emergency, and with the security building.
If the nature and severity of the emergency requires evacuation, either complete or partial, instructions are broadcast.
Personnel who have been trained in the use of survey instruments and protective apparel are available. Guidelines to assist management in formulating dose limits for emergency exposures for the protection of human life, recovery of victims, and protection of health and property are available. A system which has undergone a criticality accident will be left undisturbed until competent review has produced a plan to cope with the situation. Calibrated instruments are available at strategic locations.
Injured persons, if any, may be taken to a local area hospital. Approximate travel time to most hospitals is 15 minutes. Arrangements have been made with a hospital in Pleasanton, Califomia, to receive and care for injured persons who are contaminated. Assistance will be provided by Nuclear Safety personnel as necessary. In the event of spurious alarms, the all-clear will be announced on the public address system. Periodic drills are conducted to assure adequate personnel response to emergency situations.
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License No. SNM-960 Docket No.70-754 Sect. No.
- 4. 0 Page 4-8 Date 7/9/98 Amends Sect.(s) 49.1
6.0 LABORATORY BUILDING E2 6.1 LOCATION AND GENERAL DESCRIPTION Building 102 is a single-story with basement, concrete and steel structure located as shown in Figure 6.1. The predominant feature of the building is the multikilocurie facility known as the Radioactive Materials Laboratory (RML). General support laboratories for these facilities also are located in the building. The current layout of the building is shown in Figure 6.2. The laboratory areas of the main floor are separated from general office areas by a fire wall. Inherent in the building design are general service facilities such as the main ventilation system, decontamination rooms, and other areas which are described later in this section.
6.2 VENTILATION SYSTEM 6.2.1 Air Supply Inlet air to Laboratory Building 102 is provided by multiple air conditioning units fumishing l
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modulated, filtered and tempered outside air to the operation and office areas. The capacity of the inlet air system is a nominal 65,000 cubic feet per minute, adjusted as necessary to maintain a balance with the exhaust system.
6.2.2 Direction of Flow Airflows in the laboratory are from areas oflow radioactivity toward and through areas of higher radioactivity. The arrows in Figure 6.2 indicate general direction of flow. The system of directional airflow minimizes the possibility of accidental contamination of nonradioactive areas.
Airflows are all single pass and continuous except a portion of the RML operating gallery air which is recirculated through absolute filters.
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i License No. SNM-960 Docket No.70-754 Sect. No.
- 6. 0 Page 6-1 Date 7/9/98 Amends Sect.(s)
- 6. 2.1 1
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Figure 6.2. Building 102 Main Floor - Radioactive Materials Areas l
l License No. SNM-960 Docket No.70-754 Sect. No. Fleure 6.2 Page 6-9 Date 7/9/98 Amends Sect.(s) Figure 6.2
I Each high-level cell has an operating area approximately 17 feet long by 6.5 feet wide and is 14 feet high inside. There are four operating stations in each cell. Three of the stations are located along the side wall of the cell and the fourth at the end wall.
There is a total of 16 operating stations available. Typically, the elements of each cell operating station are a pair of through-wall master-slave manipulators, a viewing window, and the "in-cell" l
work or experiment apparatus required for carrying out one or more functional tests or l
operations. Six to seven feet of width are available at each station internally and externally. This permits adequate space for one or two operators and the miscellaneous control and operating equipment which is required on the cold side.
Water is piped to the hot cells by an independent supply system. A 23-gallon pressurized storage l
tank located on the top of the mezzanine is filled by a "back flow prevented" water line directly connected to the tank. Tids tank is connected through a manual valved line which, in turn, 1
i supplies the pressurized water at a maximum of 60 psi to a process water header with branches to I
each hot cell. Refill of the supply tank is accomplished by manual actuation of a spring-loaded push button which opens a normally closed solenoid valve. This independent system provides positive assurance against feedback of cell water to the potable water system as well as preventing large quantities of water (more than 42 gallons) to enter the cells in the event of piping failure.
l 7.3.3 Cell Door Interlock System The high-level cells are equippped with inner and outer steel shielding doors which form a radiation lock. The eell doors are operated and controlled hydraulically by a panel at the cell operating face. The operating controls are interlocked such that the outer door normally cannot 1
i be opened when the inner door is open. A key-locked override switch is provided for unusual J
circumstances such as cell decontamination activities.
l I
License No. SNM-960 Docket No.70-754 Sect. No.
- 7. 0 Page 7-3 Date 7/9/98 Amends Sect.(s) 7.3 2
7.3.6 In-Floor Dry Storace Pit Located immediately adjacent to the RML storage pool, a dry storage pit is available for temporary storage ofirradiated fuel assemblies, rods or other rod-shaped materials. This storage device consists of 19 recessed pipes fabricated of 6-inch Schedule 40 steel pipe 46.5 inches long attached to two horizontal circular steel plates 91.25 inches in diameter and 6 inches thick. The device rests on a ledge cast in the concrete floor so that the top surface is flush with the floor with the tubes extending downward below the floor surface. The pipes are arranged to provide a minimum center-to-center spacing of 18 inches. Twelve-inch-thick stepped plugs provide shielding of sources up to 500 R/h at 1 MeV to dose rates of 2.5 mR/h.
Fuel materials are placed in sealed tubes called waste liners prior to insertion into the storage pipes. Movement of the material is accomplished by means of shielded transfer casks which have top and bottom entry ports. Handling tools which are attached remotely to the waste liner can permit insertion and withdrawal of stored objects without encountering direct radiation from the top of the open cask. Each tube has two 1-inch-diameter holes located 3 inches above the bottom and one 1/4-inch hole in the bottom plate to prevent accumulation of water.
7.3.7 Other Cells Cells 9,10 and 11 (see Figure 6.2) are used in support of research and development activities authorized under California License 0017-60.
7.3.8 Radiochemistry Laboraton' The radiochemistry laboratory, used principally for the analysis of samples of irradiated fuel materials from the RML, is located immediately adjacent to the RML area. Hoods or glove boxes are connected to the previously described 102 ventilation system and are designed to provide a minimum face velocity of 125 linear feet per minute.
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License No. SNM-960 Docket No. 70-7A Sect. No.
- 7. 0 Page 7-S Date 7/9/98 Amends Sect.(s)
- 7. 3. 7
73.9 Servicine Areas and Eauipment The Radioactive Materials Laboratory section of Building 102 rJso contains several shielded cells used in non-SNM work, a waste analyzing area, an equipment decontamination room, a machine shop, equipment storage areas, and a manipulator repair room.
A hot shop facility now occupies the former Plutonium Analytical Laboratory (PAL) next to the radiochemistry laboratory. The PAL was surveyed completely (except for the area behind a metal security wall) and decontaminated following the discontinuance of plutonium operations.
The area now is used for the repair of contaminated equipment. Only traces of SNM are present in the contamination.
73.10 Criticality Alarm Sensors The Radioactive Materials Laboratory is monitored for criticality accidents by three detectors located in the storage pool area (Figure 6.2).
7.4 RML CRITICALITY CONTROL SYSTEM Special nuclear materials used in connection with RML operations are principally in the form of oxides in irradiated fuel elements and experimental capsules. The spectrum of material and activity types may be quite broad. This required flexibility has been taken into account in the establishment of criticality controls and is reflected in considerably larger safety margins than -
might be appropriate to more routine or repetitive situations. For example, each CLA in each fuel examination cell is limited to 45 percent of a critical number of units (fuel rods, assemblies, etc.), and each fuel examination cell is limited further so that criticality is not possible if all of the fissile material in the cell comes together simultaneously under conditions of optimum water moderation and full water reflection; but normal activities preclude moderation to any degree and I
License No. SNM-960 DocketNo.70-754 Sect. No.
- 7. 0 Page 7-6
\\
Date 7/9/98 Amends Sect.(s) 7.3.10 E__.___._____
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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 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 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 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.
I I
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 directly to the site radioactive material storage facility or may be placed in a waste storage building approximately 11 feet by 12 feet constructed i
t on a concrete pad adjacent to Building 103 (Figure 10.1). This building is of corrugated steel l
and aluminum construction. The waste storage building is conspicuously posted in accordance with 10CFR20.1902. Waste packages stored in this area are removed periodically to the site l
waste storage facility for delivery to a licensed waste disposal contractor.
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License No. SNM-960 Docket No.70-754 Sect. No.
10.0 Page 10-3 Date 7/9/98 Amends Sect.(s) 10.3 3
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Liquid contaminated wastes originating in Building 103 are routed from laboratory sinks and gravity drains through regulated pipes to waste setention tanks.
Two tanks, each of approximately 5,000-gallon capacity, are provided. The tanks are equipped for representative l
sampling and for draining to drums or tank trucks. All tank wastes are sent to the site waste evaporator for concentration and solidification.
4 10.3.4 Criticality Alarm l
Building 103 currently is not monitored for a criticality accident. The quantity of SNM pennitted in Building 103 is below the "subcritical area" limit of Section 3.17 of Appendix A.
10.3.5 Fire Protection Building 103 is provided with an automatic sprinkler system. Fire extinguishers also are located strategically throughout the laboratory areas. Accidental fires in the hood enclosures are oflow potential. Three types of fuel are available for such accidents: general paper and plastic combustibles, flammable solvents, and pyrophoric materials. VNC fire prevention procedures i
mmimize the fire potential; however, extinguishing equipment and materials are provided at strategic locations in the building. Additionally, smothering agents such as Metl-1-X, asbestos cloth, etc., are available in each enclosure where sufficient fire probability exists. Special precautions are taken when quantities of special nuclear materials are handled in hoods or glove boxes to minimize fire hazards in these enclosures. For example, metal containers will be used for pyrophoric materials.
i License No. SNM-960 Docket No.70-754 Sect. No.
10.0 Page 10-4 Date 7/9/98 Amends Sect.(s) 10.3.4 l
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12.0 BUILDING 105 12.1 LOCATION AND GENERAL DESCRIPTION
' Building 105 is located immediately north of Building 102 in the 100 Area (Figure 6.1). The building houses the Nuclear Test Reactor (NTR) and facilities leased to an external company l
(Figure 12.1).
i 12.2 NTR FACILITIES The Nuclear Test Reactor (NTR) is licensed pursuant to 10CFR50 (License R-33). SNM licensed pursuant to License SNM-960 is taken to the NTR North Room or the NTR South Cell (Figure 12.1) primarily for pulposes of neutrographic examination. Such material is in the form of scaled units, and only one safe batch (<45% of the minimum critical accumulation) is l
permitted in the North Room or South Cell at any one time. The materials are handled pursuant to the safety provisions and requirements of License R-33.
l 12.3 OTHER LABORATORY AREAS (LEASED FACILITIES) l Other laboratory P.ieas in Building 105 use SNM only as sealed sources, standards, foils, or as electronic components ender general license and only in gram or microcurie quantities. The l
radioactive materials are controlled and inventoried by the Nuclear Safety function.
l LicenseNo. SNM-960 Docket No.70-754 Sect. No.
12 0 Page 12-1 Date 7/9/98 Amends Sect.(s) 12 1 & 12.3 E__________-_______________________________
The main exhaust then is directed through a HEPA filter system (99.95% efficient for 0.3-m l
particulate). Filters appropriate for high relative humidity service are used.
The filtered air then is discharged to the atmosphere through a continuously sampled stack at a point approximately 7 feet above the roof of the building. Approximately 18 air changes per hour maintain proper contamination control. Air discharged from the stack at the rate of 3,000 q
cfm is driven by an electrically powered blower mounted at the base of the stack.
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13.1.5 Monitorine Procedures i
Monitoring and/or step-off procedures are observed at points where each potentially contaminated regulated area exits into the clean or non-regulated areas. In addition, survey instruments are provided at convenient locations for fimal surveying. The doors to the process equipment area are alarmed or padlocked in accordance with 10CFR20.1601(a).
l 13.1.6 Criticality Control The facility meets the requirements of a suberiticality area as defined in Section 3.17 of l
Appendix A to License SNM-960.
13.2 SOLID WASTE IIANDLING A single organization has been designated by VNC management as responsible to assure that all solid wastes leaving the site meet the appropriate regulatory requirements. For the purposes of this application, it will be referred to as the Waste Handling Function (WHF).
l License No..}NM-960 Docket No.70-754 Sect. No.
13.0 Page 1.1-4 Date 7/9/98 Amends Sect.(s) 13.1.5 & 13 1.6
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