ML20211N117
| ML20211N117 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 02/20/1987 |
| From: | Bidinger G, Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20211N108 | List: |
| References | |
| NUDOCS 8702270446 | |
| Download: ML20211N117 (2) | |
Text
,
e FEB 2 01987 DOCKET N0:
70-1257 LICENSEE:
Exxon Nuclear Co.
Richland, Washington
SUBJECT:
SAFETY EVALUATION REPORT, ENC LETTER
.TED JULY 18, 1986 RE-DECOMMISSIONING OF CENTRIFUGE TEST.ACILITY (CTF)
Background
On October 27, 1981, ENC requested that License No. SNM-16 S (Docket 70-4) be terminated and that the CTF be identified as a place of dg for S under License No. SNM-1227. On November 27, 1981, Amendment No. I to
-1227 was issued to incorporate the CTF as a place of use and SNM-1679 was terminated.
In the July 1986 letter, ENC presented a decommissioning survey report and requested that the facility be removed from the license as an authorized place of use.
Discussion On August 4, 1986, NRC Region V was requested to conduct a~ confirmatory survey and provide a recommendation for deleting the CTF as an authorized place of use from the license. On February 3,1987, Region V submitted results of a confirmatory survey conducted by Oak Ridge Associated Universities (0RAU).
Results showed that contamination levels were below limits in the license, viz., " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses by Byproduct, Source, or. Special. Nuclear Material" dated November 1976.
Attachments to this Safety Evaluation Report include the ENC survey report, the ORAU confirmatory survey report, and the " Guidelines."
8702270446 870220
{DR ADOCK 07001257 PDR
2 Conclusion / Recommendation Based on results of the surveys, residual contamination is less than limits in-the license. License amendment-to terminate the CTF as an authorized place of use is recommended.
Original Signed By:
George H. Bidinger Uranium Process Licensing Section Uranium Fuel Licensing Branch-Division of Fuel Cycle and original signed By:
Material Safety, NMSS Approved by:
W. T. Crow, Section Leader Attachments:
1.
ENC Survey Report, dtd 07/18/86 2.
ORAU Survey Report dtd 01/27/87 3.
" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material" July 1982*
- Limits in 1982 revision are same as 1976 copy in the license.
.......... J_M_M_ _ _ _ _ _ _ _:FCUF'
- FCUF OFC:FCUP a NAME:GHBidinger:ht :VL karpe
- WTCrod.d {:
.....__._____..._____'hd___________...__p_g________.._____
p 0
- DATE:02/17 /87
- 02//l/87
- 02/9 /87 :
i 0FFICIAL RECORD COPY i
t
76-425 7 2
ERON NUCLEAR COMPANY,INC.
- *" ' ?.0*T.'J'****
gNgogagxiso.aicsuNo.wa ms2 July 18,1986 Os.
l%'T
(
DOCK.*TED g
d.
UsNRC Mr. W. T. Crow, Acting Chief 9j JllL 2 91983 ).b.
y.
.- 3 Uranium Fuel Licensing Branch j
Divigion of Fuel Cycle and Material Safety, NMSS 9 um iimou
'?
U.S. Nuclear Regulatory Commission Docxtr ettax
- /
Washington, D. C.
20555 g
j s
ca a
License No. SNM-izz/
r u
Docket No. 70-1257
Dear Mr. Crow:
Exxon Nuclear tested UF6 centrifuge enrichment equipment in it's Centrifuge Test Facility (CTF) from 1976 to 1979.
During this testing period, a limited amount of both natural and enriched UF6 was brought into the facility. The facility was operated under NRC license and is currently covered by the reference license.
At the end of the testing, the majority of the equipment was removed and the facility decontaminated. During May of this year, a final resurvey of the facility (ottoched) found all locations to be significantly below the release levels for uranium specified in Annex C of our license.
Exxon Nuclear Company, Inc. hereby request a release of the CTF Building from the restrictions of our current NRC license os it will not be included in the forthcoming application for license renewoi.
CTF Release Survey Introduction / Conclusion Between 1976 and 1979, the Centrifuge Test Facility (CTF) was operated to mechanically test centrifuge enrichment equipment with UF6 g as. In order to perform the test several containers of compressed natural UF6 gas were introduced into the facility.
In addition, a few small cylinders of enriched UF6 gas were utilized to calibrate a mass spectrophotometer. There were no known leaks of the UF6 gas into the building.
Some UF6 gas sampling occurred in the single, cpen-faced hood which was used for analytical work. At the termination of the project all of the equipment was removed, including the centrifuges, hood, piping and volves. Surveys of the building at that time (1979-1980) found essentially no contamination following removal of the equipment. New surveys were performed during May of 1986. Both the 79-80 and the 5/86 surveys and drawings of the building are ottoched for your
~
review. )QQ gp rgf au smum onnonconcunan
. Q _-
Mr. W. T. Crow July-18, 1986 Page 2 The activity detected by all surveys is significantly below the Annex C release level for uranium. The contaminated pieces of equipment found, on exhaust filter housing, on exhaust duct, and fan items 2, 3 and 4 of survey number 12 have been removed from the facility and will be disposed of as contaminated waste.
The layout and dimensions of the facility are shown by the attached drawing.
The building was inspected by Mr. Brock and Mr. Skov of Region V during their inspection on May 12-16, 1986.
Sincerely, J. E. Pieper Corporate Licensing JEP:jrs Attachment As Stated b
c Survey Instruments V
/
1.
Portable alpha meter (P AM) - Ludlum Model 12 using on air procortionc!
probe with counting creo of 60 cm2 and on ef ficiency of 13% 4 pi for uranium.
2.
Ludlum Scaler (alpha scintillation) - Ludium Model 1000 with alpha scintillo-tion probe Model 43-1, counting creo of 75 cm2 and on efficiency.of 22% 4 pi for uranium.
3.
CM Survey Meter (ECM) - Eberline Model E-140 with HP-260 pancake probe.
Counting crea of 15.5 cm2 and efficiency of 30% 2 pi for Tc-99.
4.
Ludlum Scaler (beto/ gamma GM) - Ludlum Model 1000 with HP-210T hand probe. Counting area of 15.5 cm2 and efficiency of 30% 2 pi for Tc-99.
Correction Factors for Detectors Used Direct Survey for Alpha Alpha in d/m
= size factor X efficiency factor X (c/m - background in c/m) 1.PAM
= l.67 X 7.46 X (c/m - background in c/m)
- 2. Scaler
= 1.33 X 3.33 X (c/m - background in c/m)
Smear Survey for Alpha Alpha. in d/m
= ef ficiency X (counts per minute - background in c/m)
Scaler
= 3.33 X (counts per minute - background in c/m)
Direct Survey Beta Commo I mrad /hr
= 3600 c/m for HP-260 or HP-210T hand probes 0.2 mrod/hr
= 720 c/m Total c/m
= 3.33 efficiency factor (2 pi) X (observed c/m - background in c/m)
Attachment i Survey Number 011 5-20, 5-21 1986 Survey Number 012 6-13-1986 Floor Drawings 451004-80-4-310 451004-80-4-3!1 451004-80-4-312 451004-80-4-315 Survey Instrument Dato
- cid?'c= *caracriCm cacons E(ON NUCLEAR CC M P ANY, INC.
RADIATION SURVEY REPORT 9 6 3G.
kOcATICN TI Mg DATE svavey LQG NC.
07**
to 5-20,5-21-86 Oli CTF inside
'"' Survey of CTF buildina for uncondi:ional release. Survey was nade of all rooms or areas wi*.hin the buildino. Survey.as mace of floor drains, sink drains,
e..a r e. ovh s ec
- d..e
- e sad ena a t.* 24*,4?a*e W E ? E " O E 8 L-SC6mCE l SE?A 3Awwa NEv?ach "E:"
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- ises**vuta vlsi vst: - t.. NUMSER iPlh 08 $34 LAG af sp mA tc aw Paorac~'0% "4 3Wi"E3 s
C siL*ta
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- s mscN4st ocss ea Es P** Ast 38 wo e z 40.
- CLA80cvet%.
wwCLE 800v $st.N Ez?atWEfits
=m a,.
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Survev of all roor's or areas. involved s eaes of entire floor sur' ace tha*
was accessible and direct survev wi*h both alska and be*a -n r a curvev fre'eo-aa*e n' eor
- emrvove enuoeo,4 nr tome
- W+4 *T~ne co**s-a tee sense whaec endtese**ua materials were not normally handled or stored. Areas where radioactive materials were known to have been handled or stored were surve.ved for direct contaminati_on on all i
accessf 51e surfaces of floors. Walls, dast collecting surfaces, drains, sinks, sumps, and ducts were also surveyed for both smearable and direct contamination. See attach-ed maps and survey data sheets for more detaileo results.
I t
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All survey results for contamiration are for areas of 100 cm'.
- ~
n MsLu rwa
= Am. w=ccaanerso usaawanus%r
=A A. coaascreo ocsa = Ara A N N* * % 888
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Survey # 011 5-21-86 Fixed Smearable Fixed Radiation Contanination Contamination 2
2 Location (in mrad / hour)
(in d/m/100 cm )
(in d/m/100 cm )
- 1. Room 110: floor and walls 0.2*
100*
200*
- 2. Room 109: floor and walls 0.2*
100*
200*
3.. Room 108: floor and walls 0.2*
100*
200*
- 4. Room 105: floor and walls 0.2*
100*
200*
- 5. Room 106: floor, walls and sink 0.2*
100*
200*
- 6. Room 107: floor, walls and sink 0.2*
100*
200*
- 7. Room 101: floor, walls and exh-aust fan 0.2*
100*
200*
- 8. Room 102: floor, walls and floor drains 0.2*
100*
200*
- 9. Room 111: floor, walls and air ducts 0.2*
100*
200*
- 10. Room 103: grating, walls and air da:ts 0.2*
I?:*
200*
- 11. Room 10a: floc, walls and s e::s 0.2*
102*
200*
- 12. Rocr. 112: flocr and walls 0.2*
100*
200*
- 13. Room 113: grating, walls, air ducts and elevator 0.2*
100*
200*
- 14. Room 114: floor, walls and steps 0.2*
100*
200*
- 15. Mezzanine over room 101: metal roof, wood and fibreboard 0.2*
100*
200*
- 16. Room 115: floor, sub floor, walls and air ducts 0.2*
100*
200*
- 17. Room 116: grating, walls and air ducts 0.2*
100*
200*
- 18. Level 3: grating, walls and air ducts 0.2*
100*
200*
- 19. Level 1: floor, walls, sump and air ducts 0.2*
100*
200*
- 20. Walls above level 6, and I-beams which frame inside of building 0.2*
100*
200*
- indicates a less than value e
A
m"
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- l a^o'^"a 'acT*crioa ancoaos E(ON NUCLEAR COMPANY,INC.
RADIATION SURVEY REPORT e f
DATA suavsv wo stoa.
LocArion Tius CTF outside nnnn
_ to 11on 6-13-86 012
~-
g Survey of CTF building for unconditional release. Survey wafmade_ of ll' '
exhaust duct, exhaust filter system and exhaust fan system. Survey was also made of steel succorts and oratino remnved frnm laval ? in hnildinc.
N sturnos osaN susN
- Taw om Locarson usTr a ce *L.
sounca sata GAuuA o,,7, uaAsuntueNr wo we siza mroser.
m ecm/w e.
sim...;,.c,,,,,,,,
, o, 1.
exhaust duct (inside and outs ide) 0.2*
200*
40-2.
exhaust. filter housing (insite) -
4000 400 3.
exhaust duct leading to exhat st fan 800 200 4.
fan housing and fan 0.2*
300 200 0.2*
200*
200*
- 5. steel supports and grat' ng
- 6. fan housing and fan after cleaning 0.2*
200*
'40*
- 7. exhaust filter housing tf ter cleanin ;
0.2*
250 40'
- 8. exhaust duct leading to fan after el Eaning 0.2*
200*
40*
- indica es a less than value l
l' Suavev pusTauest%Tr.s; ustD - t.D. NUMBE.4 SPIN OR SEMuu pagp,mAtomy Pactic-"tok me cui=Eo PAM C.P.
0 $ur'*o ^'a O arua G'~oha p H520.66 t4s couvism i /co0.3 mem 7530 31 PE RSONNE L DOSE MATES PM ASE CF wcMK N O.
wMOLA SCOY PEN.
wMOLE tooY skin E XT Re ut *iES m,uan/hr.
mesm/hr.
w me.
i z
Exhaust duct has been in use and had been Dreviously decontaminated. Exhau-st filter housino and exhaust fan have not been in use in recent years. items were doenntaminated tn Inwett nrac tical loval - Fnund all frame tn ho at favole heinw re-lease limits for uranium.
ACTION TAKEN
(.*
w All survey results for contamination are for areas of 100 cm'.
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