ML19318B241
| ML19318B241 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 05/20/1980 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML19318B238 | List: |
| References | |
| 16420, NUDOCS 8006250160 | |
| Download: ML19318B241 (13) | |
Text
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. llk INSTRUCTION SHEET FOR BAW-381 DEMONS ~ RATION AND CONDITIONS FOR LICENSE SNM-778 (Renewal Application)
Amendment 0 Revision 11 May 1980 Remove Old Page Insert New Page Page Rev.
Date Page Rev.
Date 3-17 1
9/79 3-17 1
9/79 3-18 9
4/80 3-18 11 5/80 3-19 9
4/80 3-19 11 5/80 3-20 1
9/79 3-19a,
9 4/80 3-19b 11 5/80 3-20 1
9/79 3-43 11 5/80 3-44 11 5/80 A-27 2
10/79 A-27 2
10/79 A-28 9
4/80 A-28 11 5/80 A-29 1
9/79 A-29 11 5/80 A-30 3
11/79 A-30 3
11/79 t
1 01S 2ShD l(>3)
e 3.5.7 Criticality Accident Alarm System Figure 3-5 shows the location of the system monitors. The system detects gamma radiation and meets the requirements of 10 CFR 70.24(a)(1).
These monitors are connected to a logic circuit that activates the building evacuation alarm when any two monitors trip. The monitors are connected to the building'e emergency power system, ensuring alarm activation in the event of a failure of normal site power. Monitors may be removed, added, and relocated to meet the Center's experiment programs; therefore the above locations should not be considered permanent.
Changes in monitor location and their removal shall comply with 10 CFR 70.24(a)(1) and be approved by the Safety Review Committee.
3.5.8 Facility Change Reference Section 3.3.3.
License No.
SNM-778 Docket No.70-824 Date Sen t ernbe r. 1079 Page 3-17 Amendment No.
Revision No.
i Babcock & Wilcox
o 3.6 Dry Radioactive Waste Storage
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Dry radioactive waste is stored, awaiting shipment for offsite disposal, in Building J (Fig. 3-2), the temporary addition to Building J (Fig. 3-15), the outside storage area (Fig. 3-2) and the high level waste storage tubes. (Fig. 3-16).
Vaste stored in Building J shall be in closed DOT or NRC approved containers suitable for offsite shipment. These containers may be stored out doors for short periods of time incidental to transportation. Waste stored in the Building J addition and the fenced out door storage area shall be in closed DOT or NRC approved metal containers suitable for offsite shipment. Waste stored in the high level waste storage tubes shall be the metal containers used to remove waste from the hot cells.
All containers may be stored without overpacks if such are required for transpor-tation.
Building J provides 1400 square feet of space for storage. Greater than Type A quantities of radioactive material (ref.10 CFR 71.4(q) per container and/or greater than 0.5 grams of fissile material per container shall be stored within Building J.
Pu waste shall be stored indoors or in the high level waste storage tubes. The building is provided with a smoke detector, that alarms in the Building B health physics area and the guard station at the Naval Nucl-ear Fuels Division, an air sampler, a criticality monitor and a personnel survey instrument. Two shielded areas are provided for storage of intermediate and high level waste.
The temporary addition to Building J provides 178 square feet of storage space. It is constructed af solid, unmortated concrete block. The three outside walls shall consist of four courses of block (approx. 4 ft. thick) and three courses (approx. 3 ft. thick) of block abutting Building J.
The 1
addition is provided with exhaust ventilation through ducting which connects Building J with the addition thereby permitting the smoke detector and air sampler in Building J to serve both. The addition is provided with a metal roof which is hinged to Building J, capable of being locked and provided with side panels which permits the roof to fit flush with the top of the blocks. A l
curbing will be placed on the approach side of the addition to prevent a loading vehicle from accidently contacting the exterior block wall. At least two indi-License No.
SNM-778 Docket No.70-824 Date May. 1980 Page 3-18 Amendment No.
Revision No.
11 i
Babcock & Wilcox
viduals will be in involved in trcusf;rring v2sto contcinars into er cut cf tha addition to prevent the container or container handling boom from contacting the exterior block wall. The quantities of material stored within the addition shall conform to those specified for Building J.
Dry waste containing Type A quantities of radioactive material (ref.10 CFR 71.4(q) per container or less and/or less than 0.5 grams of fissile material per container, except Pu, may be stored in the fenced, locked and paved area adjacent to Building J.
Waste containers shall be closed, metal containers suitable for offsite shipment. The radiation level at the boundry of the restricted area (outer fence surrounding the waste stronge area) shall not exceed the limits specified in 10 CFR 20.105(b).
The High Level Waste Storage Tubes are located under, ground adjacent to the south side of the Liquid Waste Disposal Facility.
There are thirty (30) tubes arranged in two rows of fifteen tubes. They are emersed in concrete. Each tube is censtructed of two secticas of iron pipe; the upper section %42-inches long with a 6-inch diameter; the lower section, which is welded to the upper, is % 80-inches long with a 5-inch diameter. Each tube is provided with a concrete filled iron plug. Details are shown in Figure 3-16.
The tubes are locked and under the control of Health and Safety.
3.7 Liould Waste Disposal Facility The liquid Waste Disposal Facility (LWDF) is shown in Figure 3-2.
The LWDF is a below grade tank farm. A schematic diagram of tank arrangements, piping and pumps is presented in Figure 3-14.
Potentially contaminated waste water is piped from material handling areas to specific tanks so that the type of activity in any given tank can be anticipated. Each tank is provided with piping for thorough mixing by air sparge. The drain lines from each tank is located in the bottom of the tank to permit complete emptying. Exceptions to this are the t.wo 4000 gal. vaste tanks which have floating drains.
The rectangular tanks shown in Figure 3-14 are constructed of concrete.
The interiors are treated with a water-proofing material. The tops ate of 3-19 License No.
SNM-778 Docket No.70-824 Date May, 1980 page Amendment No.
Revision No.
11
____i Babcock & Wilcox
concrete and access to the tanks for cleaning, inspecting and sampling is gained through man holes.
The tanks indicated by circles on Figure 3-14 are constructed of steel. The 300 gallon tanks are stainless steel and are not provided with inspection ports.
The 2000 gallon tanks are constructed of carbon steel, treated with an epoxy lining and are equipped with man holes for inspection.
A 10.000 square foot pond is located appro:dmately 150 f eet northeast of Building J.
This pond collects storm drainage from Buildings B & C.
I 3-19a License No.
SNM-778 Docket No.70-824 Date April, 1980 page Amendment No.
Revision No.
9 Babcock & Wilcox r'
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License No.
SNM-778 Docket No.70-324 Date May, 1980 Page 3-19b Amendment No.
Revision No.
11 Babcock & Wilcox
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$E Table 3-1.
Hot Cell Characteristics CL D 9
fA n a Drt 2o 2
O Nu" cell 1 t' ell 2 Cell 3 Cell 4 50 C1 Purpose Ceneral disassembly Metallography Metallurgical testing Radioisotopa handling
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and testing W rt o
Inside dimensions, f t 8 = 16 = 15 4-1/2 = 15-1/2 = 9 4=9=9 6=6=9
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(width lanath height) 3 2
Shielding, curies co-60 3 = 105 6 = 103 6 = 102 10" O
I cm ea Wall material concrete (240 lb/ft ) Lead shot Lead shot Ferrophosphorus lead shot Thickness, in.
42 13 11 14 gm g
Operating stations 3
2 + optical equipment 1
1 area Manipulators 6 Model E 4 Hodel C 2 Model C 2 Model C gm General Hills 300 F 1-ton electric hoist j
3-ton bridge crane m
h Windows 011-filled lead Lead glass (dry con-Lead glass (dry con-Lead glass (dry a
glass 42 in. thick, struction), 21 in. thick, struction), 21 in, thick, construction, 18 in.
130-deg viewing 150-deg viewing angle 150-deg viewing angle thick, :170-deg angle viewing angle E
Containment' Negative pressure Negative pressure Negative,tressure Negative pressure U
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Figure 3-16 High Level Waste Storage Tubes 30 T U B E.S 7"_.
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Hsw License No.
SNM-778 Docket No.70-824 Date vn,r _ 1980 Page 3-43 Amendment No.
Revision No.
11 c
Babcock & Wilcox
BLANK License No.
SNM-778 Docket No.70-824 Date Mav. 1980 Page 3-44 Amendment No.
Revision No. 1 i
i Babcock & Wilcox
8.
The stack samplers shall be operated isokinetically and con-tinuously, except for short periods to permit equipment repair or calibration, to assure a representative sample.
A.9.3.2 Action Levels - Table A-3 presents the action levels for l
airborne releases. Health physics shall respond to each alarm, monitoring the operation producing the release and shall, if necessary, shut down the operation to prevent exceeding the release limit. When an action level speci-ficd in Table A-3 is exceeded for four consecutive time periods, the operation producing the release shall be shutdown until the cause is corrected.
Table A-3. Stack Release Limits and Action Levels Release Product Release Limit Action Level Beta particulate 2 mci /yr.
200pci/ week Alpha particulate 20pci/yr.
Ipci/2 weeks (Long lived)
Kr-85 2500 Ci/yr.
70Ci/ week H-3 130 C1/yr.
3Ci/ week I-131 6 mci /yr. or 200pC1/ week 300pci/ week i
License No.
SNM-778 Docket No.70-824 Date October 1979 Page A-27 Amendment No.
Revision No.
2 l
Babcock & Wilcox
[
A.9.3.3 Liquid Wr.rto 1.
Low-level r2cioactive liquid wastes 'are collected in under-ground te ds.
Wastes are discharged to the liquid waste treatment plant at B&W's Naval Nuclear Fuels Division (NNFD).
Prior to discharging wastes to the NNFD the solution shall be mixed and sampled. The sample shall be representative of the liquid to be discharged. The ratio of the sum of the composite materials shall not exceed 25% of the MFC values of Table I, Col. 2, of 10 CFR 20, Appendix B, for release to the NNFD waste treatment system. The limiting values in water shall be determined in accordance with the note at the end of Appendix B,10 CFR 20.
Process liquid wastes are collected and stored indoors. These liquid wastes are solidified and handled as dry waste prior to shipment for off-site disposal.
2.
Concentrations of the m'ixtures of radioisotopes will be below those defined in Appendix B,10 CFR 20, averaged over one year.
Measurements are taken at or before the point of discharge to the James River.
3.
Storage tanks are inspected visually upon each tank voiding to ensure that there are no unsafe accumulations of special nuclear material.
4.
The fissile content of the waste tanks shall be less than 0.01 gm/ liter. The tanks shall be analyzed (a) quarterly, (b) whenever emptied, (c) whenever an unknown quantity of fissile material has been released to the tanks.
5.
A 10,000 sq. ft. pond collects storm drainage from Buildings B and C.
This pond shall be sampled quarterly for activity.
A.9.3.4 Dry Wastes - Dry waste containing Type B quantities (ref.10 CRF 71.4 (g) or greater of radioactive material per container and/u greater than 0.5 grams of fissile material per container shall be stored indoors in closed containers suitable for off-site shipment. All Pu waste shall be stored indoors or in the high level waste storage tubes.
l All other dry waste containing licensed material may be stored in a l
fenced, locked and paved outside storage area, in closed metal containers suitable for offsite shipment. The storage area is under positive control and surveillance by health physics, and the area will receive at least a l
quarterly visual and radiological inspection.
I
-28 License No.
SNM-778 Docket No.70-824 Date May 1980 Page l
Amendment No.
Revision No.
11 Babcock & Wilcox
A gamma monitor in the waste storage building meets the requirements for a criticality monitor as defined in 10 CFR 70.24.
Each drum with fissile material is gamma scanned on a drum counter to verify the fissile content. The drum monitor has a limit of sensitivity of grams U-235 and 2 grams of Pu.
Each waste container will be labeled so that the contents of each
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drum can be identified and drums will not be opened without specific approval of the LRC health physicist and the facility supervisor.
Material stored in the high level waste storage tubes shall be in closed metal containers and limited to that resulting from hot cell operations.
The Health and Scfaty group shall control access to the tube.e.
Health and Safety shall perform surveys of the tubes each time waste is removed or inserted.
A.9.3.5 Environmental Samoling - The environment surrounding the LRC and the Mount Athos plant site is sampled periodically to determine whether the radiation and radioactive material levels in the area surrounding the site have changed or increased as a result of the operations at this location. The frequency of these surveys will be a function of the work taking place on the site. Environmental samples are collected and analyzed by LRC personnel or qualified commercial concerns. As a minimum, the environmental program will include the following:
1.
One continuous on-site background air sample.
2.
Monthly water sampling of grab samples taken from the James River below the discharge point.
3.
Continuous sampling of rain water.
4.
Annual grab sampling of river silt and plant life.
A.9.4 Special Conditions 1
A.9.4.1 Restricted Area - The restricted area at the LRC is defined as any area within a building or enclosed by chain-link fence or a single-strand fence and properly marked with radiation area signs, i
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License No.
SNM-778 Docket No.70-824 Date May 1980 Page A-29 Aoendment No.
Revision No.
11 I
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Babcock & Wilcox
A. 9. 4. 2 Records Retention - The following records will be maintained for at least two years.
l 1.
Records showing the results of surveys made to evaluate the 1
radiation hazard incident to the production, use, release, disposal, or presence of radioactive materials or other sources of radiation, as required by 10 CFR 20.401 (b).
1 2.
Records used to prepare Form NRC-4 " Occupational External Radiation Exposure History" as required by 10 CFR 20.102.
l 3.
Records showing receipt, transfer, export, and disposal of by-product material.
4.
Records showing the results of leak tests of sealed sources as required by license.
5.
Records showing the receipt, inventory, and tratisfer of speical
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nuclear materials as required by 10 CFR 70.51.
6.
Records showing the receipt, transfer, export, and disposal of source material as required by 10 CFR 40.61 7.
Records of the SRC meetings.
8.
Records of instrument calibration.
9.
, Safety audit records.
10.
Records of training and retraining.
11.
Records shall be maintained to reflect the quantities of material in categories A-E and I-Q specified in section A.3.
When personnel monitoring is required by 10 CFR 20.202, as required by 10 CFR 20.401(a), records showing the radiation exposure of each individual will be retained in accordance with 10 CFR 20.401(c).
i A. 9. 4. 3 Area Decontamination - Areas previously used for handling radioactive material (including contaminated glove boxes and equipment) will be removed from service, held in a standby condition, or decontaminated in accordance with current health physics procedures and special procedures and l
pra.ctices approved by the SRC. These procedures and practices will describe l
the following activities.
t j.
License No.
SNM-778 Docket No.70-824 Date November 1979 Page A-30 Amendment No.
Revision No.
3 j
m _..
Babcock & Wilcox
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