ML20129C136
| ML20129C136 | |
| Person / Time | |
|---|---|
| Site: | 07000398 |
| Issue date: | 10/18/1996 |
| From: | Pevey L NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL |
| To: | Soong S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9610230228 | |
| Download: ML20129C136 (9) | |
Text
/
g UNITED STATES DEPARTMENT OF COMMERCE m
v V'
g%,,
/y NationalInstitute of Standards and Technology Gaithersburg, Maryland 208990001 October 18,1996 Dr. Sean Soong License No. SNM-362 Licensing Branch Expiration Date: 07/31/%
U. S. Nuclear Regulatory Commission Docket: 70-398 Mail Stop T 8-D-14 Washington, D.C. 20555-0001 Gentlemen:
Six copies of the summary of information are enclosed to satisfy the environmental report requested in the letter of August 20,1996 from Robert C. Pierson, Chief of the Licensing Branch.
If you need additional information, please contact Mr. T. G. Hobbs at the National Institute of Standards and Technology, Room C125, Building 245, Gaithersburg, MARYLAND. 20899. His telephone number is 301-975-5800; his FAX is 301-975-4893, and his e-mail address k thomas.hobbs@nist. gov.
Sincerely, Ly an E. Pevey, Chief Occupational Health and Safety Division (Materials License Manager)
/J FO ^/ ' /
enclosures 1
9610230228 961018~
PDR ADOCK 07000398 C
PDR NLST 230063
l I
ENVIRONMFNTAL INFORMATION FOR NIST SNM-362 uCENSE RENEWAL APPLICATION I
i Dere is one stack, at Building 235, the Reactor Building, with a possibility of releasing radioactive i
effluents. It is approximately 30.3 m above grade, and is attached to the reactor's Confinement Building, which is, itself, approximately 17.6 m above grade. The stack is approximately 400 m from the site boundary and approximately 450 m from the nearest resident, to the southwest direction. The stack has two plenums, one from the reactor-licensed area and the other from the warm laboratories, licensed under SNM-362. The exhaust rate is approximately 14 kl/s from each plenum.
1 A free-standing stack is at the rear of Building 245; it is not normally used for release of raJioactive materials. General purpose laboratory buildings are approximately 19.7 m high, including the attic and a penthouse at one end of the roof area. Laboratories are in the three working floors, with exhausts about 0.6 m above the roofline; some few labs exhaust about 0.6 m above the top of the penthouse. Radioactivity hoods are maintained with a nominal face velocity of 0.5 m/s. The laboratory buildings locations range from Building 222, approximately 420 m from the nearest boundary and 500 m from the nearest resident, to Building 226, approximately 325 m from the nearest boundary and 720 m from the nearest resident.
No emergency plan is required for NIST Materials License operations. An accident evaluation presented to USNRC and accepted by them on December 6,1994, resulting in an amendmer, to License Number SNM-362. Meteorological data for the NIST site remains unchanged from that published in NUREG-1007 and NBSR-9.
Table 1-1 shows environmen.al monitoring characteristics. Should any sample show 10% ALI, or should TLD results for a quarter show greater than i2 standard deviations from the average value observed for the past five years, a professional Heal:h Physicist is to review the data and recommend further action. A map showir,g environmental sampling locations is attached to this document. A copy of the WSSC permit for liquid discharges is attached to this document; no permit for gaseous discharges is necessary.
Table 1-1. Environmental Sample Parameters media collection frequency analysis frequency analysis method minimum detectable activity (MDA) grass monthly (seasonal) quarterly gamma see Table 1-2 spectroscopy soil monthly (seasonal) quarterly gamma see Table 1-2 spectroscopy water monthly monthly gamma see Table 1-2 spectroscopy water monthly monthly liquid see Table 1-3 scintillation TLD quarterly quarterly TLD System see Table 1-4 10/96.....page 1
1
' No sample of soil, grass, nor water taken from 1991 to the present has demonstrated measurable levels of radioactivity attributable to NIST operations as determined by gamma spectroscopy.
Table 1-2. Typical Minimum Detectable Activities by Gamma Spectroscopy for radionuclides typically relevant to NIST operations i
nuclide soil grass water pCi/g pCi/g pCi/ml i
Na-24 short short 4x10*
Cr-51 8x 10-'
2x104 2x104 Co-58 1x104 2x104 2x10*
Fe-59 3x10-8 6x104 3x10*
j Co-60 9x104 2x104 2x104 Cu-64 short short 8x104 Zn-65 3x104 5x104 6x10*
Br-82 short short 3x10*
Zr-95 2x104 4x104 3x10*
Nb-95 2x104 3x104 2x104 Mo-99 2x104 3x10-5 2x10*
Tc-99m*
2x104 3x105 2x10*
Ru-103 9x10*
2x104 2x10*
Rh-106*
9x104 9x104 2x104 Ag-110m 2x104 2x104 2x10*
Sb-125 3x10-8 4x104 5x104 l
I-131 1x104 2x104 2x10*
Cs-134 2x104 2x104 2x104 Cs-137 1 x 10-'
1x104 2x10*
La-140*
1x104 5x10*
2x104 Ba-140 4x104 3x104 6x104 Ce-144 6x10' 7x104 2x104 Eu-152 3x104 3x10-8 4x10*
NOTES:
The entries of "short" indicate that the half life of these nuclides are too short to pr.mit detection in the samples' measurements.
The entries marked "*" indicate that the nuclide activity, and hence the MDA, are determined by the decay of the radioactive parents.
10/96.....page 2
' Water sam'les are collected and analyzed monthly by liquid scintillation. Table 1-3 shows the results in pCi/ml for p
those months of 1991 through the present that had any sampling location or locations demonstrating greater than MDA. For those. positive data, the values are not statistically different from MDA.
Table 1-3. Tritium Analyses for Environmental Water January,1991 to present time (S) = surface water sample; (G) = ground water sample units are pCi/ml sample Clopper Main Izaak Brick Rt #28 Kentlands NIST NIST date Road (S)
Gate (S)
Walton (S)
House (G)
(S)
(G)
- 6 (S)
- 7 (S)
Jan 1991
< mda
< mda
< mda 1.2x10-8
< mda
< mda
< mda
< mda Feb 1991
< mda
< mda
< mda
< mda
< mda
< mda
< mda 1.6x104 Mar 1991
< mda
< mda
< mda
< mda
< mda
< mda
< mda 2.0x104 Jun 1991
< mda
< mda
< mda
< mda
< mda
< mda
< mda 1.0x104 Jul 1991
< mda
< mda
< mda 2.3x 10-8
< mda
< mda
< mda
< mda Aug 1991
< mda
< mda
< mda 2.8x10 8
< mda
< mda
< mda 7.2x10-8 Feb 1993
< mda
< mda
< mda
< mda
< mda
< mda
< mda 4.9x104 May 1993
< mda
< mda 9.0x104 2.3x104 6.8x104
< mda 3.5x104 1.9x104 Jun 1993 6.8x104 5.9x104 2.9x104 4.0x104 8.1x104
< mda 4.9x104 1.4x104 Jul 1993 7.7x104 4.1x104 2.7x104 5.9x104 9.9x104
< mda 5.4x104 2.2x104 Aug 1993
< mda
< mda
< mda
< mda
< mda
< mda
< mda 1.3x104 Sep 1993
< mda 2.3x104 2.3x104 3.6x104
< mda
< mda 8.1x104 2.5x104 Oct 1993 6.0x104
< mda 9.2x104 3.4x104 7.4x104
< mda 4.7x104 3.1x104 Nov 1993
< mda
< mda 5.7x104 5.1x104
< mda
< mda 5.6x104 2.0x104 Dec 1993
< mda
< mda 2.1x104 6.3x104 4.9x104 3.2x104 5.1x104 1.4x104 Jan 1994
< mda
< mda 2.6x104 4.0x104
< mda
< mda 1.3x104 1.8x104 Feb 1994
< mda
< mda 1.8x104 3.0x104
< mda
< mda 3.6x104 1.8x104 Mar 1994 6.5x104
< mda 3.4x104 5.6x104 1.1x104 1.2x104 6.6x104 6.6x104 Apr 1994
< mda
< mda 1.5x104 3.4x104 1.4x104
< mda 3.6x104 1.8x104 May 1994 7.9x104
< mda 2.3x104 3.7x104 2.3x104 2.9x10-'
3.4x104 1.9x104 Jun 1994 9.5x104 2.7x104 3.1x104 3.6x104 6.8x104
< mda 4.2x104 2.4x104 Jul 1994
< mda
< mda 1.8x104 3.2x104 1.4x104
< mda 2.4x104 2.8x104 Aug 1994
< mda
< mda 2.3x104 9.0x10*
< mda
< mda 1.9x104 1.3x104
)
Jan 1995
< mda
< mda 1.4x104
< mda
< mda
< mda 6.3x104
< mda j
Mar 1995
< mda
< mda
< mda
< mda
< mda
< mda 4.5x104 2.3x104 Apr 1995
< mda
< mda
< mda
< mda
< mda
< mda 9.0x104
< mda Oct 1995
< mda
< mda
< mda 1.2x104
< mda
< mda
< mda
< mda Dec 1995 2.3x104 4.5x10*
< mda 9.1x104 4.5x104 4.1x104 2.9x104 1.5x104 Jan 1996
< mda
< mda 1.8x104 8.5x104
< mda
< mda 2.2x104 1.4x104 Feb 1996
< mda
< mda 8.1x 10 '
5.6x104 5.0x104
< mda 2.5x104 1.2x104 Apr 1996
< mda
< mda
< mda
< mda
< mda
< mda
< mda 5.0x104 Jun 1996
< mda
< mda
< mda 1.1x104
< mda
< mda 2.5x104
< mda Jul 1996
< mda
< mda
< mda 1.7x104
< mda
< mda
< mda
< mda Aug 1996
< mda
< mda
< mda 1.4x104
< mda
< mda 7.1x104
< mda NOTE:
MDA at 95% confidence level for 10 mi samples counted by liquid scintillation, for 100 minutes each: 4.0x104 pCi/ml (Beckman LS3801, used prior to May,1993) 2.0x104 pCi/ml (Packard 2500TR, used after May,1993) 10/96.....page 3
' TLDs are positioned on the fence about the NIST site so that each quadrant has four stations, using the stack at Bldg. 235 as a center point. Background information is provided by five offsite locations that encircle the site, at distances ranging from 3.3 km to 6.5 km from that center point. It is estimated that an MDA of I mrem (1 mR) can be assigned to the monitoring program for a dosimeter. None of the net results is statistically different from MDA.
Table 1-4. NIST Perimeter TLD Monitor Results, 1991 - 1996 2
Ouarter Eint Second Ibird Fourth Y. fat 1991 gross mR 21.3 22.8 33.2 21.9 net mR 0.9 1.8
-0.6 1.2 1992 gross mR 20.0 19.8 21.5 22.6 net mR
-0.2
-0.8 0.2
-0.8 1993 gross mR 19.3 20.6 22.4 21.7 net mR
-0.4
-0.6 0.2
-1. 4 1994 gross mR 18.4 21.2 26.8 24.0 net mR
-0.6
-1.1 0.2
-0.4 1995 gross mR 22.9 22.4 26.8 25.0 net mR 0.1 0.2 1.2 0.6 1996 gross mR 22.1 22.5 NA NA net mR 0.5 0.0 NA NA Note: " net mR" values are the differences between " gross mR", measured at the NIST perimeter, j
and the offsite monitor results. "NA" are data unavailable at the time of preparation of this
)
table.
10/96.....page 4
d 4
t j
Radioactive liquid and gaseous effluents released from NIST operations are shown in Table 1-Sa, j
and the EPA COMPLY code calculations for environmental dose impact, i.e., dose equivalent in each l
year to a member of the public, are shown in Table 1-5b.
Table 1-Sa. Isotopic Breakdown of Effluents Gaseous Liquid ygg d' Ar (Ci)
'H (Ci)
'M (Ci)
B-v (Ci) 1991 971 251 0.7
< 0.01 1992 665 351 1.5
< 0.01 1993 879 425 1.6
< 0.01 1994 469 637 2.7
< 0.01 1995 267 209 1.3
< 0.01 NOTE:
Very low activities of S'Cl and "Br have also been detected in the gas release streams.
Using the EPA's COMPLY code, the maximum annual dose equivalent to the whole body, which is i
the critical organ for '8A and 'H, the nuclides of concern in the effluent stream, is shown in Table 1-5b.
Table 1-Sh. Environmental Dose from Effluents by COMPLY Ygg dose eauivalent (mrem) 1991 0.68 1992 0.49 1993-0.65 1994 0.39 1995 0.21 i
l 10/96.....page 5
A
'In addition to the gases and liquids released, solid radioactive wastes were generated and delivered to agents for disposal at appropriate repositories. Proposals with radioactivity implications are reviewed prior to start-up by Health Physics. Should any proposal include processes that might generate mixed waste, modifications are incorporated, if possible, to preclude such waste generation.
Unavoidable mixed wastes that are generated, e.g., liquid scintillation discards or activated lead from accelerator operations, are transferred to licensed disposal contractors or are stored pending approved action.
Table 1-6. Volume and Activity of Solid Radioactive Wastes ysat volume (m')
activity (Ci) 1991 38 0.1 1992 90 141.0 1993 7
0.3 1994 231 79.5 1995 39 1.2 Population estimates for the environment at various distances about the NIST site were prepared by the Maryland-National Capital Park and Planning Commission, Research and Information Systems Division (source: W. Robinson). The estimates are presented in Table 1-7 for information from the 1990 census and from a 1995 review and update of that information. It is understood that population estimates from MNCPPC's Planning Area census tracts were visually incorporated in whole or in part to arrive at these estimates. Since the 10 mile radius involves some areas outside Montgomery
{
County, those estimates are based on Montgomery County populations adjacent to the non-County areas.
Table 1-7. Population Estimates for NIST Environs radius 1990 census 1995 undate i mile 27 100 28 400 3 miles 113 300 126 800 5 miles 180 100 205 800 10 miles 449 900 489 000 10/96.....page 6
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A BOUNDARY TLD STATION LOCATIONS A
OFFSITE TLD STATION LOCATIONS THE NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY ENVIRONMENTAL MONITORING LOCATIONS 1696
COMMISSIONERS Robert M. Potter, Chauman WASHINGTON SUBURBAN
"*""Teh:-
Waymond D. Bray SANITARY COMMISSION
"!: tact GENERAL MANAGER 14501 Sweitzer Lane
- Laurel, Maryland 20707 5902 (301)206-8000
- 1(800)3284439 + 1TYC91)206-8345 Cortez A. White DISCHARGE AUTHORIZATION PERMIT Industry Name:
National Institutes of Standards and Technoloav Correspondence Address:
Buildinc 301, Room 124 00 Muddy Branch Road Gaithersburc, MD 20899 Site Address:
Same as Above Permit No.:
05813 In accordance with the provisions of the Washington Suburban Sanitary Commission's (WSSC's) Plumbing and Gasfitting Regulations, Chapter 9,
" Industrial and Special Waste Regulations" and applicable provisions of Federal and State law, the above named industry, hereinafter referred to as " Industrial User", is hereby granted permission to discharge industrial wastewater into WSSC's sewer system (s).
This wastewater will be treated at the District of Columbia's Blue Plains Wastewater Treatment Plant.
In the event that this Discharge Authorization Permit expires, is revoked, or otherwise made invalid, all industrial discharges into the sewer system shall immediately cease.
This Discharge Authorization Permit is granted to the Industrial User, at the specified site address, by the Washington Suburban Sanitary Commission, for the time period set forth as follows:
Effective date:
04/14/95 Expiration date:
04/14/98 q
l
>d Issued by:
A J& n Mathers,'Section Head I
e Enforcement Section Date of Issue 4 "'/4
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