ML20210E869

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Requests Release of Centrifuge Test Facility (CTF) Bldg from Restrictions of License SNM-1227 as Bldg Will Not Be Included in Application for License Renewal.Ctf Release Survey Provided.Related Info Encl.Fee Paid
ML20210E869
Person / Time
Site: Framatome ANP Richland
Issue date: 07/18/1986
From: Pieper J
SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To: Crow W
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
27251, NUDOCS 8609250109
Download: ML20210E869 (22)
v • d • e


Text

M*ssNa o

ERON NUCLEAR COMPANY INC.

2101 HORN RARDS ROAD. Po Box 130. H!CHLAND.WA 99352 Es t

15091375 8100 TELEX: 15 2978 July 18, !986 0

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Dock:TED g

USNRC cr3 m-Mr. W. T. Crow, Acting Chief t

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Uranium Fuel Licensing Branch

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Division of Fuel Cycle and Material Safety, NMSS g U.S. Nuclear Regulatory Commission Docxtr ctcax g/

c3 Washington, D. C.

20555 N

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License No. SN, -

Q Docket No. 70-1257

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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, o final resurvey of the facility (attached) 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 as it will not be included in the forthcoming application for license renewal.

CTF Release Survey introduction / Conclusion Between 1976 and 1979, the Centrifuge. Test Facility (CTF) was operated to mechanically test centrifuge enrichrnent equipment with UF6 gas. In order to perform the test several containers of compressed natural UF6 gas were introduced into the f acility.

In addition, a few small cylinders of enriched UF6 gas were utilized to calibrate a inass spectrophotometer. There were no known leaks of the UF6 gas into the building.

Some UF6 gas sampling occurred in the single, open-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 valves. 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 attached for your

, _ review.

8609250109 860718 4p!! cad ',',jkj)," * ".....

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ADOCK 0700 7

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DOCKET NO. -,ldWNl CONTROL No. 0 7X/

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DATE OF 000.

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DATE RCVD.

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FCAF LPOR I& E REF.

SAFEGUARDS __._ _

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$ INIHAL b

O Mr. W.LT. Crow

' July 18, 1986 Page.2

The activity
. detected by oil surveys is significantly below the Annex C release level for uranium. The contaminated pieces of equipment found, on exhoust-t, filter housing, on exhaust duct, and' fan items 2, 3 and 4 of survey number 12 have been removed from the facility _ond 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, t

J. E. Pieper Corporate Licensing JEP:jrs Attachment As Stated I

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l

1 Survey Instruments 1.

Portable alpha meter (PAM) - Ludlum Model 12 using an air proportional probe with counting area of 60 cm2 and an ef ficiency of 13% 4 pi for uranium.

2.

Ludlum Scaler (alpha scintillation) - Ludlum Model 1000 with alpha scintilla-tion probe Model 43-1, counting area of 75 cm2 and on efficiency of 22% 4 pi for. uranium.

3.

GM Survey Meter (ECM) - Eberline Model E-140 with HP-260 pancake probe.

Counting area of 15.5 cm2 and efficiency of 30% 2 pi for Tc-99.

4.

Ludlum-Scaler (beta / 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 cfficiency f actor X (c/m - background in c/m) 1.67 X 7.46 X (c/m - background in c/m) 1.PAM

=

1.33 X 3.33 X (c/m - background in c/m)

2. Scaler

=

Smear Survey for Alpha Alpha in d/m

= efficiency X (counts per minute - background in c/m)

Scaler

= 3.33 X (counts per minute - background in c/m)

Direct Survey Beta Gamma I mrad /hr

= 3600 c/m for HP-260 or HP-210T hand probes 0.2 mrad /hr

= 720 c/m

. Total c/m

= 3.33 efficiency factor (2 pi) X (observed c/m - background in c/m)

--e e:

tr.-.-.

s..

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Attachment i Survey Number 011

'5-20, 5-21.1986-

' Survey Number 012 -'6-13-1986 Floor,' Drawings 451004-80-4-310 451004-80-4-311 451004-80-4-312 451004-80-4-315 Survey Instrument Dato t

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E:RON NUCLEAR a^o'^7'oa PaotacT*oa a*comes COMP ANY, INC.

RADIATION SURVEY REPORT

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LOCATION T ' ME.

DATE SURVEY LOG NO.

CTF inside 0700 TO 1;nn 5-20,5-21-86 011

'"' Survey of CTF building for unconditional release. Survey was made of all rooms or areas within the building. Survey was made of floor drains, sink drains, sumns. pyhaust ducts and sunn1v air duc+c _

I 8 TEM OR LOCATION METE R DE FL.

SOURCE DETA GAW A MEUTRON WW MAM' N O.

DIST*

ME ASUR E ME N T WO WC SIZE mresseA r.

mR/h r.

mrcm/h r. umory k/m orbirj 1.

Found no detectable con-aminat inn ah,vp rei naen 1-mits insida nf buildinn 200

  • 41.6 i

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Ma v i no,- cnntaminatinn fnnna m e in f innr armin w

i 4

4

  • indicates a less than value SURVEv seusTRuutNTts USED - 1.D. NUMSER (PIN OR SERLAU RESPt RATORY PROTECPOh RE QutREO

<l-

,,17520.31 c.r.

sNooey SvPPuEo A'a O area T ~o~'

L.A8 COUNTERM. 33 orNER I7550.31 Ecu 17520. 68 1

I PE RSONNEL DOSE RATES

[

PH ASE O F WOR K N O.

WHOLE SODY PEN.

WHOLE SODY SK.N E XT RE ME TIES mesm/nr.

=remine.

m,cm m e.

l 5

" ""'" Survev of all rooms or areas. involved smears of entire floor surface that was accessible and direct survev with both aloha and beta-gama survev instromonts.

Dirpet curvove envared at loact 2n? nf finnr enrfaco fnr aroae whora raainac+4uo materials we're not normally handled or stored. Areas where radioactive materials were known to have been handled or stored were surveyed for direct contamination on all accessi6le surfaces of floors. Walls, dust 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 detailed results.

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f All survey results for contamination are for areas of 100 cm#

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l M AX. UNCORRECTED ME ASUREMENT MAX. CORRECTED OOSE R ATE TURE gg x -N,...

Survey # 011 5-21-86 Fixed Smearable Fixed Radiation Contamination 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*

1 00*

200*

9. Room 111: floor, walls and air ducts 0.2*

100*

200*

10. Room 103: grating, walls and air ducts 0.2*

100*

200*

11. Room 104: floor, walls and steps 0.2*

103*

200*

12. Room 112: floor 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*

1 00*

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*

2 00*

  • indicates a less than value

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a^o' AT'ON PROTECTION RECORDS ERON NUCLEAR COMPANY, INC.

RADIATION SURVEY REPORT

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LOCATION T8ME DATE SU R V E Y LOG N O.

CTF outside nnnn TO linn 6-13-86 012 l

Survey of CTF building for unconditional release. Survey was made of exhaust duct, exhaust filter system and exhaust fan system. Survey was also made of steel suconrts and oratino removed from level 7 in buildinc ITEM OR LOC.. TION ME TE R DE F L.

SOURCE BETA GAMMA NEUTRON DIRECT SMEARS DIST*

N O.

MEASUREMENT WO WC S62E mrede/hr.

m R/hr.

mecm/hr. n/m or d/ rec /m or d/m 1.

exhaust duct (inside aiid outs ide) 0.2*

200*

40*

2.

exhaust filter housing (inside) -

4000 400 3.

exhaust duct leading to exhau st fan 800 200 4.

fan housing and fan 0.2*

300 200

5. steel supports and grat-ng 0.2*

200*

200*

6. fan housing and fan after cleaning 0.2*

200*

40*

7.

exhaust filter housing after c leanin ;

0.2*

250 40*

8. exhaust duct leading to fan.after cl eaning 0.2*

200*

40*

  • indicates a less thai; value l

suavEv i=sTRu=E Ttsa usEo - i.D. NUM8ER WIN OR SERLAU RESPIRATORY PMCTECTION RelOuaMEC PAM C.P.

e 0 5ur"* o

^'a O a tea @ ~o~e Ecu 17520. 66 t.AB COUNTER 1/530.3erwER 7550.31 PE RSONNEL DOSE RATES

' OF wCRK N O.

WHOLE BODY PEN.

WHOLE SODY SKIN E XTRE ME TIES

/w,.

mrem /n,.

m ~.

Exhaust duct has been in use and had been previously decontaminated. Exhau-C MuENTS st filter housino and exhaust fan have not been in use in recent years, items were dernntaminated tn inwest nractical lovpl. Fnnnd all items tn hp at 1pvols helnw rp-lease limits for uranium.

ACTION TAKEN

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Max. UNCOR REcTED ME AsuREMENT MA A. CORR ECTE o oOSE R ATE S

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