ML20141F504
| ML20141F504 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 03/14/1986 |
| From: | Winslow T GENERAL ELECTRIC CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 26673, NUDOCS 8604230050 | |
| Download: ML20141F504 (23) | |
Text
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GENERAL h ELECTRIC NUCLEAR FUEL MANUFACTURING DEPARTMENT GENER AL ELECTRIC COMPANY - P. O. 80X 780 - WILMINGTON NOMTH C AROL4NA 28402 RETURN 10. 394-SS March 14, 1986 PK Dr. J. Nelson Grece, Regional Administrator U.
S. Nuclear Regulatory Commission, RII 101 Marietta Street, NW - Suite 2900 e5 Atlanta, Georgia 30323
Dear Dr. Grace:
References:
(1) NRC License SNM-1097, Docket 70-1113 (2) Letter, TP Winslow to WT Crow, 3/14/86
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Subject:
WAREHOUSE LEASE TERMINATION
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on April 30, 1986, General Electric Company Nuclear Fuel &
Components Manufacturing will terminate its lease on a warehouse facility in Greenville, South Carolina.
Attached are the radiological report and other pertinent information required pursuant to NRC License SNM-1097.
If you have any questions regarding this matter, please contact me at (919) 343-5461.
Very.truly yours, GENERAL ELECTRIC COMPANY
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T. PreGton Winslow, M inager Licensing & Nuclear Materials Management M/C J88 TPW:bsd
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NUCLEAR FUEL MANUFACTURING DEPARTh*ENT GENER AL ELECTRIC COMPANY - P. O. BOX 780 - WILMINGTON, NORTH CAROLINA 28402 March 14, 1986 Director A.
p Office of Nuclear Material Safety & Safeguards U. S. Nuclear Regulatory Commission D
Washington, D. C.
20555 RECENED j
Attention:
Mr. W. T. Crow, Acting Chief h
MAR 2 S '030 #
Uranium Fuel Licensing Branch
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Gentlemen:
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Reference:
NRC License SNM-1097, Docket 70-1113 L/
Subject:
WAREHOUSE LEASE TERMINATION On April 30, 1986, General Electric Company Nuclear Fuel &
Components Manufacturing will terminate its lease on a warehouse facility in Greenville, South Carolina.
Operations at that facility are covered by Condition 9, Part I, Chapter 1, Paragraphs 1.8.4.2 and 1.8.4.3 of the subject license.
Pursuant to license requirements, NF&CM hereby submits the required radiological report and other pertinent information, as follows:
General Project Description Radiological Assessment Survey Instructions to Monitoring Personnel Survey Results Figures NRC License Excerpt As demonstrated by this submittal, GE has satisfied all applicable requirements for unconditional release of the warehouse to the landlord.
GE hereby requests NRC concurrence by the lease termination date, 4/30/86.
General Electric personnel would be pleased to discuss this matter further with you and your staff if deemed necessary.
Very truly yours, 4
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Preston Winslow, Manager "2
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i G EN E R A L (l) E LE CTR IC Director - ONMSS March 14, 1986 - Page 1 ATTACHMENT 1 GENERAL PROJECT DESCRIPTION Effective April 30, 1986, General Electric Company Nuclear Fuel &
Components Manufacturing, Wilmington, North Carolina will terminate the lease on its Greenville, S. C. warehouse.
This facility was used for storage of packaged uranium as authorized by NRC License SNM-1097, Condition 9, Part I, Paragraphs 1.8.4.2 and 1.8.4.3.
Radioactive material was stored in the varehouse either in Fissile Class I packages or in the metal inner containers of the RA-series shipping package.
(The warehouse was also used to store non-radioactive GE reactor components including stainless steel equipment and parts, aluminum structural materials, zirconium tube shells and tubes, and other similar materials.)
The Greenville warehouse was constructed in September 1973 for lease to GE; GE has been the sole occupant.
Nuclear material storage activities in the warehouse ceased in February 1986, and final radiological and sampling assessments were performed on February 27, 28, and March 1, 1986.
During the lease period, the Greenville warehouse has been audited on a quarterly basis by the NF&CM radiation safety and radiation protection functions.
Periodic surveys inside the warehouse have not indicated radioactive contamination due to storage activities.
Additionally, there have been no known breaches of container integrity which would create the potential for the release of j
nuclear materials.
A brief description of the warehouse is summarized below.
(See, Figures 1 and 2 for further details.)
Designation:
Storage Warehouse "E"
Owner / Lessor:
Eastern Distribution, Inc., same location Location:
Perimeter Road, near Donaldson Center (at edge of an industrial park formerly an Air Force airport),
Greenville, SC 29606.
(Warehouse "E"
is essentially adjacent to other l
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ERALk> ELECTRIC Director - oNMSS March 14, 1986 - Page 2 public warehouses of the owner / lessor.)
Size:
20,000 square feet, heated, sprinklered space.
Lease does not include grounds within fenced area.
Type:
Prefabricated steel, insulated; concrete floor.
Built:
September 1973 Occupied:
September 1973 through February 1986 solely by GE.
Lease Type:
All space in building, with landlord operated forklift handling services for unloading trucks, storing material, and loading trucks.
Lease Termination:
April 30, 1986 Abandonment of the Greenville warehouse will be accomplished pursuant to NRC License SNM-1097, Condition 9, Part I, Chapter 1, Annex A,
" Guidelines for Decontaminaton of Facilities & Equipment Prior to Release for Unrestricted Use...", and Part I, Chapter 7,
" Decommissioning Plan".
Since the limited activities in the Greenville warehouse involved only storage of materials which were well contained and because there has been no evidence of a breach in containment during these operations, radioactive contamination was not expected.
The results of the survey, internal and external to the warehouse, confirm the absence of any radioactive contamination associated with the licensed activities conducted there by NP&CM.
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RAL$ ELECTRIC Director - ONMSs March 14, 1986 - Page 1 ATTACHMENT 2 RADIOLOGICAL ASSESSMENT SURVEY A detailed radiation survey of the facility and soil sampling were performed on February 27, 28 and March 1, 1986, by certified radiation protection personnel, to confirm the absence of residual radioactivity.
Applicable sections of NUREG/CR-2082, " Monitoring for Compliance with Decommissioning Termination Survey Criteria",
were used in establishing the survey plan.
The floor inside the leased warehouse was divided by rectangular grid sections, as shown in Figure 1.
The blocks formed in this manner were.approximately 10' to a side, resulting in 200 predetermined survey points.
In addition to these systematic, pre-established survey points, direct and indirect radiation measurements were obtained from forty-four randomly selected locations.
These locations were selected at the time of the survey based on professional judgment, in areas wh'ere contamination would be anticipated if there were any present.
The radiological conditions characterized included alpha contamination levels by direct reading, beta-gamma dose rates at one centimeter above the surface, removable alpha and beta contamination levels, and external gamma radiation levels at one meter above the floor.
The condition of each gridded area was established using the first three methods and external gamma levels were measured as indicated on the warehouse floor plan survey sketch (Attachment 5, Figure 1).
Direct surface contamination levels were measured by making sequential measurements with portable survey meters.
Alpha contamination levels were measured using an alpha scintillation probe (Eberline model AC-3) which has a counting area of 59 cm 2 2
and a lower limit of detection of approximately 200 dpm/100cm,
Surface beta-gamma dose rates were established using a thin window
" pancake" GM probe (Eberline model HP260).
This instrument has a 2
mica window thickness of less than 2.0 mg/cm, a counting area of 15 cm2 and a lower limit of detection of approximately 0.05 mR per hour.
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GENER AL 4l) ELECTRIC Director - ONMSS March 14, 1986 - Page 2 Indirect monitoring included smearing or wiping of the surface with soft absorbent material, such as a filter paper, which would partially pick up any loose radioactive contamination, if present.
The smear samples were initially checked in the field and subsequently taken to a remote radiation detector for counting and final assessment of contamination.
External radiation levels were measured using a 1" x 1" NaI scintillator capable of measuring low levels of gamma radiation (Eberline Micro R Meter PRM-7).
Gamma radiation levels were measured at one meter above the center of each indicated survey block.
Typical inside background radiation levels were between 12 and 15 pR per hour, as determined in two other general use warehouses within the complex but not associated with the NF&CM leased facility.
All survey results ware well within the limits specified for the decontamination and sJrVey of surface 3 or premises and equipment prior to abandonment or release for unrestricted use as specified in NRC License SNM-1097, Condition 9, Part I, Chapter 1, Annex A.
(See Attachments 4 and 6.)
The absence of outdoor radioactive contamination attributable to fuel storage was confirmed by selected soil sample analysis.
Twenty-two locations were sampled on March 1, 1986, chosen where contamination, if present, would be anticipated.
(See Attachment 5, Figure 2.)
Uranium levels (ppm) in each sample were checked by chemical uranium analysis and then converted to a pCi per gram of soil basis.
Sample results all indicated expected background levels ranging from 0.5 to 2.0 pCi per gram of soil.
(See, Page 8.)
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s Director - ONMSS March 14, 1986 ATTACHMENT 3 INSTRUCTIONS TO MONITORING PERSONNEL (1)
Check current instrument calibration date.
(2)
Perform operability checks using appropriate check sources per internal procedure NSI 0-4.0,
" Nuclear Safety Engineering Radiation Protection Instrumentation."
(3)
Indicatemeasuredbackgroundlevelsforeachinstrumenggtobe used.
(4)
Take the following measurements at the center of each grid survey block:
Use Units 2
Direct a (contact)
AC-3 probe dpm/100cm Direct 8-y (1 cm)
HP-260 probe mR/ hour Smear (100 cm )
Absorbent paper dpm/100cm 2 2
(5)
Choose additional " random" monitoring locations such as adjacent walkways, floor cracks, floor drains, building roof vents or ventilators, etc., where contamination, if present, would have the potential to exist.
Measure as in Item 4 above.-
(6)
Take the following measurements as indicated on the warehouse floor plan survey sketch.
Use Units External Gamma (1 meter)
Micro R Meter pR/ hour (7)
Record all results in appropriate units.
Also record name of surveyor, date of survey, and instrument type, model, serial number and calibration date.
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GENER AL llk ELECTRIC Director - ONMSS March 14, 1986 Page 1 ATTACHMENT 4 SURVEY EASTERN DISTRIBUTION WAREHOUSE E GREENVILLE, S. C.
RADIOLOGICAL SURVEY - 2/27-28/86 - RESULTS PAGES 1-7 SOIL SAMPLING
- 3/1/86
- RESULTS PAGE 8 Performed by:
.sG Lewis, Radiation Protection Supervisor SD Smith, Radiation Protection Technician TYPE OF MEASUREMENT DIRECT ALPHA DIRECT BETA SMEAR GAMMA INSTRUMENT Eberline Eberline Eberline
~Eberline MODEL #
PRM-6/AC-3 E520/HP260 MS-3/RD-14 PRM-7 SERIAL 585 1019 751/296 576 DATE 1/21/86 12/11/85 2/24/86 12/10/85 CALIBRATED MEASURED 60 cpm
.05 mR/hr 2.4 cpm 12-15 BACKGROUND LR/hr*
-12% eff 4w COMMENTS 45% eff 2w 45% off 2x (U 235 2.5 (Pu 239)
(Sr 90) w/o)
-N/D = non-detectable
-6 cpm (1 min count)
- Background was established using the Eberline PRM-7 inside two other warehouses within the Eastern Distribution complex and at an outdoor location 5 miles south of Warehouse E.
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R AL dl> ELECTRIC Director - ONMSS March 14, 1986 - Page 2 SURVEY READING BY GRID NUMBER (Reference Attachment 5, Pigure 1)
GRID DIRECT a, dpm DIRECT S,mR/hr, SMEAR, dpm GAMMA, tR/hr 1
BKG BKG N/D 10 2
BKG BKG N/D 3
BKG BKG N/D 4
BKG BKG N/D 5
BKG BKG N/D 11 6-BKG BKG N/D 7
BKG BKG N/D 8
BKG BKG N/D 9
BKG BKG N/D 10 BKG BKG N/D 11 11 BKG BKG N/D 11 12 BKG BKG N/D 13 BKG BKG N/D 14 BKG BKG N/D 15 BKG BKG N/D 10 16 BKG BKG N/D 17 BKG BKG N/D 18 BKG BKG N/D 19 BKG BKG N/D 20 BKG BKG N/D 10 21 BKG BKG N/D 22 BKG BKG N/D 23 BKG BKG N/D 24 BKG BKG N/D 25 BKG BKG N/D 26 BKG BKG N/D 27 BKG BKG N/D 28 BKG BKG N/D 29 BKG BKG N/D 30 BKG BKG N/D 31 BKG BKG N/D 32 BKG BKG N/D 33 BKG BKG N/D 34 BKG BKG N/D 35 BKG BKG N/D 36 BKG BKG N/D 37 BKG BKG N/D 38 BKG BKG N/D 39 BKG BKG N/D
s Director - ONMSS March 14, 1986 - Page 3 SURVEY READING BY GRID NUMBER (Reference Attachment 5, Figure 1),
GRID DIRECT a, dpm DIRECT S,mR/hr SMEAR, dpm GAMMA, tR/hr 40 BKG BKG N/D 41 BKG BKG N/D 42 BKG BKG N/D 43 BKG BKG N/D 44 BKG BKG N/D 45 BKG BKG N/D 46 BKG BKG N/D 47 BKG BKG N/D 48 BKG BKG N/D 49 BKG
.BKG N/D 50 BKG BKG N/D 51 BKG BKG N/D 52 BKG BKG N/D 53 BKG BKG N/D 54 BKG BKG N/D 55 BKG BKG N/D 56 BKG BKG N/D 57 BKG BKG N/D 58 BKG BKG N/D 59 BKG BKG N/D 60 BKG BKG N/D 61 BKG BKG N/D 62 BKG BKG N/D 63 BKG BKG N/D 64 BKG BKG N/D 65 BKG BKG N/D 66 BKG BKG N/D 67 BKG BKG N/D 68 BKG BKG N/D 69 BKG BKG N/D 70 BKG BKG N/D 71 BKG BKG N/D 72 BKG BKG N/D 73 BKG BKG N/D r
74 BKG BKG N/D 75 BKG BKG N/D 76 BKG BKG N/D 77 BKG BKG N/D 78 BKG BKG N/D 79 BKG BKG N/D
4 Director - ONMSS March 14, 1986 - Page 4 SURVEY READING BY GRID NUMBER (Reference Attachment 5, Figure 1)
GRID DIRECT a, dpm DIRECT 8,mR/hr SMEAR, dpm GAMMA, tR/hr 80 BKG BKG N/D 81 BKG BKG N/D 11 82 BKG BKG N/D 83 BKG BKG N/D 84 BKG BKG N/D 85 BKG BKG N/D 11 86 BKG BKG N/D 87 BKG BKG N/D 88 BKG BKG N/D 89 BKG BKG N/D 90 BKG BKG N/D 15
-91 BKG BKG N/D 10 92 BKG BKG N/D 93 BKG BKG N/D 94 BKG BKG N/D 95 BKG BKG N/D 12 96 BKG BKG N/D 97 BKG BKG N/D 98 BKG BKG N/D 99 BKG BKG N/D 100 BKG BKG N/D 12 101 BKG BKG N/D 102 BKG BKG N/D 103 BKG BKG N/D 104 BKG BKG N, D 105 BKG BKG N/D 106 BKG BKG N/D 107 BKG BKG N/D 108 BKG BKG N/D 109 BKG BMG N/D 110 BKG BKG N/D 111 BKG BKG N/D 112 BKG BKG N/D 113 BKG BKG N/D 114 BKG BKG N/D 115 BKG BKG N/D 116 BKG BKG N/D 117 BKG BKG N/D 118 BKG BKG N/D 119 BKG BKG N/D I
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t ERALk> ELECTRIC Director - ONMsg March 14, 1986 - Page 5 SURVEY READING BY GRID NUMBER (Reference Attachment 5, Figure 1)
GRID DIRECT a,
dpm DIRECT S,mR/hr SMEAR, dpm GAMMA, tR/hr 120 BKG BKG N/D 121 BKG BKG N/D 122 BKG BKG N/D 123 BKG BKG N/D 124 BKG BKG N/D 125 BKG BKG N/D 126 BKG BKG N/D 127 BKG BKG N/D 128 BKG BKG N/D 129 BKG BKG N/D 130 BKG BKG N/D 131 BKG BKG N/D 132 BKG BKG N/D 133 BKG BKG N/D 134 BKG BKG N/D 135 BKG BKG N/D 136 BKG BKG N/D 137 BKG BKG N/D 138 BKG BKG N/D 139 BKG BKG N/D 140 BKG BKG N/D 141 BKG BKG N/D 142 BKG BKG N/D 143 BKG BKG N/D 144 BKG BKG N/D 145 BKG BKG N/D 146 BKG BKG N/D 147 BKG BKG N/D 148 BKG BKG N/D 149 BKG BKG N/D 150 BKG BKG N/D 151 BKG BKG N/D 152 BKG BKG N/D 153 BKG BKG N/D 154 BKG BKG N/D 155 BKG BFG N/D 156 BKG BKG N/D 157 BKG BKG N/D 158 BKG BKG N/D 159 BKG BKG N/D
5 Director - ONMSS March 14, 1986 - Page 6 SURVEY READING BY GRID NUMBER (Reference Attachment 5, Figure 1)
GRID DIRECT a, dpm DIRECT S,mR/hr SMEAR, dpm GAMMA, tR/hr 160 BKG BKG N/D 161 BKG BKG N/D 162 BKG BKG N/D 163 BKG BKG N/D 164 BKG BKG N/D 165 BKG BKG N/D 166 BKG BKG N/D 167 BKG BKG N/D 168 BKG BKG N/D 169 BKG BKG N/D 170 BKG BKG N/D
'l 171 BKG BKG N/D 172 BKG BKG N/D 173 BKG BKG N/D 174 BKG BKG N/D l
175 BKG BKG N/D i
176 BKG BKG N/D 177 BKG BKG N/D 178 BKG BKG N/D 179 BKG BKG N/D 180 BKG BKG N/D i
181 BKG BKG N/D 11 182 BKG BKG N/D 183 BKG BKG N/D 1
184 BKG BKG N/D 185 BKG BKG N/D 10 186 BKG BKG N/D 187 BKG BKG N/D 188 BKG BKG N/D 189 BKG BKG N/D 190 BKG BKG N/D 15 191 BKG BKG N/D 15 192 BKG BKG N/D 193 BKG BKG N/D 194 BKG BKG N/D 195 BKG BKG N/D 10 l
196 BKG BKG N/D 197 BKG BKG N/D 198 BKG BKG N/D 199 BKG BKG N/D l
200 BKG BKG N/D 11
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Director - ONMSS March 14, 1986 - Page 7 i
SURVEY READING BY GRID NUMBER (Reference Attachment 5, Figure 1) i FIRST HORIZONTAL GIRDER FLOOR EDGES AT WALL
( ~ 4 feet above floor)
GRID DIRECT a,
DIRECT 8, SMEAR, DIRECT a,
DIRECT 6,
- SMEAR, 4
dpm mR/hr dpm dpm mR/hr dpm 1
BKG BKG N/D BKG BKG N/D 5
BKG BKG N/D BKG BKG N/D 10 BKG BKG N/D BKG BKG N/D 11 BKG BKG N/D BKG BKG N/D 16 BKG BKG N/D BKG BKG N/D 17 BKG BKG N/D BKG BKG N/D 20 BKG BKG N/D BKG BKG N/D l
60 BKG BKG N/D BKG BKG N/D 61 BKG BKG N/D BKG BKG N/D 81 BKG BKG N/D BKG BKG N/D 100 BKG BKG N/D BKG BKG N/D 121 BKG BKG N/D BKG BKG N/D 140 BKG BKG N/D BKG BKG N/D 181 BKG BKG N/D BKG BKG N/D 185 BKG BKG N/D BKG BKG N/D i
187 BKG BKG N/D BKG BKG N/D 190 BKG BKG N/D BKG BKG N/D 191 BKG BKG N/D BKG BKG N/D 193 BKG BKG N/D BKG BKG N/D 195 BKG BKG N/D BKG BKG N/D 197 BKG BKG N/D BKG BKG N/D 200 BKG BKG N/D BKG BKG N/D DIRECT a,
MISCELLANEOUS SURVEYS dpm Sprinkler System Piping BKG Floor Area Sprinkler System Piping BKG Brooms BKG Trash Cans BKG Desk and Chairs BKG Water Fountain BKG Small Cabinet BKG j
AL4 ELECTRlC Director - ONMSS March 14, 1986 - Page 8 SOIL SAMPLE ANALYSES I
Reference Chemical U Numberl Description of Location ppm pCi/g 2 1
5 miles north of Warehouse E 0.44 0.7 2
Ditch, NW of warehouse by RR tracks 1.12 1.7 3
NW fence line 1.23 1.9 4
NE fence line 0.52 0.8 5
Ditch, SW warehouse 0.87 1.4 6
Ditch, NW 0.85 1.3 7
Ditch NE 0.82 1.3 8
Roll-up exit door, W end of warehouse 0.91 1.4 9
SW ditch by RR tracks 0.67 1.0 10 Personnel exit door, W end of warehouse 1.03 1.6 11 NE RR tracks 0.70 1.1 12 Ditch, E 0.55 0.8 13 Personnel exit door, E end 0.64 1.0 14 SE RR tracks 0.52 0.8 15 Roll-up exit door, SW warehouse 0.64 1.0 16 Roll-up exit door, SE warehouse 0.76 1.2 17 SW 1.12 1.7 18 SE 1.27 2.0 19 Between Warehouse E and maintenance building 0.78 1.2 20 SE of maintenance building 0.79 1.2 21 Culvert, maintenance building, oil discharge 0.55 0.9 22 4 miles south of Warehouse E 0.34 0.5 ISee Attachment 5, Figure 2 2 Calculated from ppm U using specific activity for nominal plant enrichment of 2.2 W/O U 235 as follows:
ppm (pg U/g soil) x S.A.
(1.55 pCi/ts) = pCi/g soil If specific activity for natural uranium were used, the results would be lower by a factor of 2.
GENERAL $ ELECTRIC Director - ONMSS March 14, 1986 ATTACHMENT 5 FIGURES FIGURE 1
- FLOOR PLAN <- SURVEY GRIDS WAREHOUSE E EASTERN DISTRIBUTION GREENVILLE, S. C.
FIGURE 2
- SOIL SAMPLE LOCATIONS SITE PLAN WAREHOUSE E EASTERN DISTRIBUTION GREENVILLE, S. C.
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FIGURE 1 WAREHOUSE E - EASTERN DISTRIBUTION i
GREENVILLE, S.
C.
N GRID MAP I
SECTION A SECTION B 100ft 100 ft 18 182 183 184 185 186 187 188 189 9
192 193 194 9
196 197 198 199 0
161 162 163 164 165 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 141 142 143 144 145 146 147 148 149 150 151 152 153 154 155 156 157 158 159 160 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 137 138 139
'14 0 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 e
8 82 83 84 8
86 87 86 89 9
92 93 94 95 96 97 98 99 00 100 f t 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 1
2 3
4 5
6 7
8 9
1 12 13 14 16 17 13 19 20 24' Door 24' Door b es
FIGURE 2 WAREHOUSE E - EASTERN DISTRIBUTION GREENVILLE, S.
C.
@ 5 miles N.
SOIL SAMPLE LOCATIONS
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h WARE,IlOUSE E p
0 8-FT 11 AWG PENCE EASTERN DISTRIBUTION MAINTENANCE BUILDING RAILROAD RAILROAD RIGIIT OF WAY
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RIGilT OF WAY C ULVE R T gg SAMPLE LOCATION
> SURFACE WATER FLOW DIRECTION g 4 MatgS S
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.1 GENERAL $ ELECTRIC Director - ONMSS March 14, 1986 ATTACHMENT 6 NRC LICENSE SNM-1097, DOCKET 70-1113, CONDITION 9 PART I, CHAPTER 1, ANNEX A
" Guidelines for Decontamination of Pacilities & Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, source, or Special Nuclear Material" TPW:bsd
DEC 3 01922 ANf4EX A GUIDELINES FOR DECO.'iTAMIt!ATION OF FACILITIES AND EQUIPMEliT PRIORTORklEASEFORUNRESTRICTEDUSE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE,
._t OR SPECIAL NUCLEAR MATERIAL
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l U. S. Nuclear Regulatory Co.T. mission t
Division af Fuel Cycle and Material Safety t'ashington, D.C.
20555 July 1982
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LICENSE SNM-1097 DATE' 10/10/85 PAGE DOCKET 70-1113 RevIs tot!
I 12 I-1.18 l
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The instructions in this guide, in ccnjunction.with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior
.to abandonment or release for unrestricted use.
The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radio-activity for which the radiological considerations pertinent to their use may be differ,ent. The release of such facilities or items from regulatory cctntrol is considered on a case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
g *. i 2.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contam-ination at these l'ocations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are
(,.
likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
4.
Upon request, the Conaission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified.
This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status.
Such requests must:
a.
Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree cf residual surface contamination.
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b.
Provide a detailed health and safety analysis which reflects 7
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that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
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LICENSE SNM-1097 DATEi
_10/10/85 PAag l
DOCKET 70-1113 RCVISION I
12 I-1.19 l
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5.
Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of 3
the survey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC,14ashington, D.C.
20555, and also the Administrator of the NRC Regional Office having jurisdiction.
The report should be filed at least 30 days prior to the planned date l
of abando'nment. The sorvey report shall:
s a.
Identify the premises.
b.
Show that reason'able effort has been made to eliminate
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residual contamination, c.
Describe the scope of the survey and general procedures followed.
i d.
State the. findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
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j LICC!iSE Stim-10 97 DATE' 10/10/85 PAGE DOCKET 70-1113 REVISIO;I I
12 I-1.20
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ACCIFTA8(t 5t;ItFACI CC4fAMlMAf!C4 LEV [L1 hi,CtlCI58 AVERAGthcf mangw d f REPOVA0ttb ' f il nat. U 235. U-230. and allociated decay productl 5.C00 dpe e/1CO ca!
1$.000 d.ve e/100 ca!
1.000 das e/ loo c.2 Traaluraetcl. Ra.226. 34 228 Th.2 30, lh.223 p3 231,
\\C0 dpm/1CQ Ce2 300 dahtCO cm2 Ac.227. !.125.1 121 20 dae/ICO cal th. eat. Th 232. Sr 93 2a.223. sa.221. U-232.1 128 1000 40s/1C3 cm2 3000 eM/100 cm2 200 des /lC0 c,2 3.I31. l.133 leta.(a"B"4 ewitterl (avCildet with Cecay redel OLPer LPam 4ICha e9ttliam or Spcataceowl 5000 dpq 3g/100 ceI 15.000 dpe pe/100 ce!
gogo dp. p,fjeg g,2 filline) escept Sr.90 and StPern nateJ aborg.
t 8
nuCltdel SPGuld apply Independently,khere $4rface conta91Pation by both alpha. and beta gava.emittleg nuClldet etiltl the llelts eliablllhe SAS usei se thin table, dre (dillnte7 Patient per minute) regel towntl per minWte oblerved by an appropriate detector 8 the rate of e1$l1004 by radleaClive Faterf el al cetermfred by C0rrectlng the b4(kgr0und, ef flcleftcy, and ge9 metr 1C fattern allectated wit % tie instru.entation.
67 I'ealdrementt Of evereje centaminant theuld eet be averajed Over more th44 I 19uare Deter.
I thowid be Cerived for each twch object.
For Objects of lell Surface area, the avera7e d The easte e contaalnation level appliel to as area of not more them 100 cm2, v
'the amow t of removable radfoacttre materf al per 100 (=I of Surface area thould t>e determined by utstag tha* area with dry filter or lef t n
ehtorbeat taper. applync3 coderate prellere, aad al'ellist the 4.evnt of radioattive matertal on the wipe isitb as appropriate in$trueent of Sna a ef f ectency. 6.nem re'ovable contanteation on objectl of tell Surf ace area il geterutned, the pertteent levell thould be reduced pr6portionally aed tPe entire turf ace thould be wsped, f ve average and esatews radiat10m levell allectated with lerface contamination relultteg free beta game eeltterl thould not esteed i
0.2 s. ras /ar a t I ce and 1.0 arad/ar at I (n. relpectively, mealure1 through not more tnam 2 ellligraal per Square centimeter of t tat ableri.er.
-7' L I C E'IS P.
Stim - 10 97 DATE 10/10/85 PAGE DOCKET 70-1113 RCV IS IO!!
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