ML20205M921
| ML20205M921 | |
| Person / Time | |
|---|---|
| Site: | 07001489 |
| Issue date: | 09/01/1984 |
| From: | Bassett A GOODYEAR ATOMIC CORP. |
| To: | |
| Shared Package | |
| ML20205M785 | List: |
| References | |
| 81768, MSE-HP-238, NUDOCS 8811030360 | |
| Download: ML20205M921 (8) | |
Text
-..
b" MEDICAL, S AFETY, AND ENVIRONMENT pag.gr.238 cooovt At 4Tomc CORPORAT1oN
():;g; 09-01-84 HEALTH PHYSICS PROCEDURE Page 1
4 g
REPORTING CONTAMINATION LEVELS
SUBJECT:
1.
PURPOSE To instruct Industrial Hygiene and Health Physics personnel and Environmental, Safety and Health Surveyors in the proper methods for reporting contamination survey results.
II.
SCOPE Due to the diversity of con tamina tion survey in s t rum en ts in use on plantaite, the reporting of searvey results in "counts per minute" is no longer an acceptable practice.
Because instrument efficiencies and geometries vary from one contamination survey instrument to the next, contaminat'.on leveis reported in count rate values are meaningless to anjoue unfamiliar with the particular instrument used in the survey.
For this
- reason, all survey results will be r e por te d in activity units (dpm, microcuries, dps, etc...)
for direct comparison with Plant Allowable Limits.
Conversion factors for converting count rates to trua 4 pi d i s in teg ra tion r a t i. s are provided for all common use CAT contamination s ur 'ey instruments in the attachments to this procedure.
111.
KEFERENCES None IV.
DEFINITIONS None V.
REQUIREMENTS Adequate procedures for all aspects of the Goodyear A tomic Corporation's Industrial Hygiene and Health Physics P r o tec tion Program are required by the Department of Energy as part of the overall Industrial Hygiene and Health Physics Quality Assurance Program.
0311030360 860931 PDR ADOCK 07001489 C
PDv FREPARED BY:
APPROVED BY:
REVIEWED BY-SupeMor.
Adminutrator, lnd Hysiene A Medral A.C. Bassett Hestth thpks Safety, & Env.
}'d' 9O CONTRot ho, g ] 7 g g HP 5-01 0P12
N"" #
MEDICAL. SAFETY, AND ENVIRONMENT X3E-HP-238 cooorus amic comum o,,,.
09-01-8h HEALTH PHYSICS PROCEDURE 8'
2 of 4
SUBJECT:
REPORTING CONTAMINATION LEVELS VI.
RESPONSIBILITIES A.
The IHHP Department will determine 4
pi de te c to r efficiencies, detector-source geometries and applicable self-absorption factors in order to derive conversion f a c tors necessary to convert instrument count rates obtained from surface and removable (wipe) contamination surveys to activity units.
A t ta chmen t s will be added to this procedure to incorporate conversion factors for all new con tamina tion survey instruments procured in the future.
These attachments will be reviewed and updated t
as needed.
B.
All IHHP and ES&H Surveyors IHHP and ES&H Surveyors will multiply instrument count rates by the appropria te conversion f ac tors provided in the addenda of this procedure to quantify the actual activity present on contaminated surfaces and the removable a c tivity present on wipe samples.
These activity levels will be reported on con tamina tion surveys.
VII.
PROCEDURE None HP 5-01 OP12
l Numba:
-HP-236 MEDICAL, SAFETY, AND ENVIRONMENT COODYEAR ATOMK CORMEAN Da te 09-01-84 i
HEALTH PHYSICS PROCEDURE I'8' 3
of 4
SUBJECT:
REPORTING CONTAMINATION LEVELS ATTACHMENT I Co_nversion Factors for_the Ludium Model 12 w/Model 43-5 Alpha Scin tilla tion Detector Multiply surface reagings by 4 to get the surface alpha activity in units of dpm/100cm Multiply wipe readjngs by 2 to get the r e m o v a ts l e alpha ac tivi ty in units of dpm/100cm HP 5-01 OP12
i Num W MEDICAL, SAFETY, AND ENVIRONMENT PSE-HP-236 cooovtAR ATONK COUCLADON gggg; 09-01-84 HEALTH PHYSICS PROCEDURE Page 4
of 4
SUBJECT:
REPORTING CONTAMINATION LEVELS ATTACHMENT 11 Conversion Factors for the Ludlum Model 12 w/Model 44-9 Pancake G-M Probe.
Multiply surface reagings by 60 to get the surface beta activity in units of dpm/100cm wipe read by 8 to get the removable be ta activity in d pm /100 c m) n g s Multiply units of
- For beta contamination monitoring, the probe face should be covered with a
thin-mil plastic bag.
Subtract the gamma background contribution befose applying conversion factors per Health Physics Procedure "Use of The Ludium Model 12 Count Rate Meter with the Mojel 44-9 Pancake G-M Probe."
CONTROL NO. 81768 i
HP 5-01 f
OP12
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t ATTACHMENT (3)
J e T. FFt ". CIE - Tea-trial Mystientat. Sr.
Assistant Radiation Protection Officer Goodyear Aerospace Corporation Training:
"Occupational and Environmental Radiation Protection" Harvard School of Public Health Boston, Massachusetts 1
August 20 - 24, 1984 1
i DANIEL E. GIREIDEN. CSP - Manager. Industrial Hvalene & safety Radiation Protection Officer Goodyear Aerospace Corporation l
Training:
"Principles and Practices of Radiation Protection Radioactivity Measurements and Monitoring, Mathematics and Calculation, Biological Effects of Radiation and Common U.S. NRC Regulations" Ohmart Cincinnati, Onio March 1981 1
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OMfl JUL 0 7 i,56 Goodyear Aerospace Cor poration
't.icense No. SNM-1461 ATTN:
J. V. P f l a urr, C Iri Industrial Hygienist Senior Corporate :r.dustrial Pygiene and Safety
~
Departn er.t 131 G I 1210 Pessillon Foad Akron, Clic 4431!-0D0; Cear V.r. Pf'. am:
This is in r J o encS to a follca-up, confirratory surs ey of your Wingfoot L ake Advanced %..elogy Center perforced by Oak Ridge fssociated Universities (0RAU) cr.U e 19, 19Fi.
As discut;e: mith you daring the survey and sut sequent telephone consersati;r3., the C#U sursey identified areas with residual radioacth ity above NRC s o iteria for release for unrestricted use.
This criteria was gisen tc. ycc in our letters doted 5' arch 27, 1986 and June 11, 1986.
Since this wes the s?cond tire we base requested ORAU to perfort a survey and each tire the results indicated areas with residual radioactivity exceedir{ %C's criteria, we will not request ORAU to perfort furtter sur.tyi until you subrit esicence that the ectigities ir the areas identif tec it this let ter are belcw NRC's criteria.
Tris evidence should be in the forr of e report ar c ccr.tain the follcwing inf erration:
Tr.e scope of the decontasinattor,ar.d sur'ey.
This should in:lufe e description ard/0.- cicgra of all art., decerterinated anc su N.
ec, ttt c ec c r.t ami r.e t i er pro:ecures usec Ge survey gric size or !10:.5 used, the type surse,. perfomed (direct reading alpha end teta-gro, trear testing, soil tv;les), and the locations of sarples taber..
C.
ine r.are and cualificetions o' the individuals perforring the ce:.c.r.t an'i na t t or a nd s u rs e,, s.
3.
The instruments anc rethods used to analyze the results.
4 The results of the sursey ke,ved to the locations specified in Ite-1 a t.o v e.
I
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Goodyear Aerospace Corporation 2
UUL 0 7 "
The following is a litt of the areas that nust be decontaminated, a final survey perforred, and evidence submitted as requested above. is a diagram which will be utilized to describe these areas.
1.
The areas travcrsed by the drain line frort the sink and shower stalls thrcugh the septic system.
This encorpasses areas where tre drain was found to contain residual radioectivity abcve hRC's criteria. All soil samples taken by OPAU denn to the "T" for the,
.,,4 drain line indicated acceptable levels for release as of""
June 20, 1986.
Scoc,er, any further decontamination and/or removal of contaminated drain line r.ay Fase led to contamination of soil in those areas.
2.
Two areas identified as C-42 and F-48 grid blocks by ORAU sursey.
The C-42 grid block is Northeast of the test pit area in Enclosure 1 and Southeast of the decontamination area.
The F-48 grid block is an area to the west of an area (E-46 grid block) where one-half inch of concrete was rmoved for a 30 by 50 centiceter square.
The E-45 grid block is located in the decertv ir.ation area in Enclosure 1.
3.
The concrete pad cuiside the facility tra r as the casing area where contaminated floors, etc. were ceposited e f ter retrosal from the Wingfoot site, 4
Ary equipcent utilized to perform the decor.tv.ination (e.g., sacuum c1(aners, saws, chisels,etc.).
Upon receipt or d esaluation of your report, we will schedule OFAU to perform a final survey of the site.
Tte survey will include the areas identified in this letter and areas where there is a potential for contarrination as a result of your de;crianination efforts.
If OPAU's survey indicates no further arcas with residual radioactivity, we will continue with our licensinq action to release the Wingfoot site for unrestricted use.
Prior to our receipt of your report and ORAU's final survey, it is our understanding that you will contirme to renosate the sites for office use.
Lc.ever, you will take steps neces.ory to insure that the rcr.cyatirn will not cause spr(ad of contarinatior in any area identified it. this letter and the soil areas where drain lirts were removed can be eartled by ORAU.
In addition, we understand that steps will be taker, to ensure against spread of centaminatiur in material stored in the outside castr; area until the material is packagec 6rc transferred to an authorized recipient.
s
,A t;
v Goodyear Aerospace Corporation 2
jut. 0 7 1986 If you have any questions concerning the above, please contact Bruce Mallett or Bob Burgin of ry staf f at (312) 790-5625.
Sincerely, 1N ils WIlliamL.
xe son, Chief "'*
~._*
huclear Materials Safety and Safegaards Branch Encleture: As stated cc w/ enclosure A, B c.c r rie r,
Of.AU DCS/RSB (RIDS)
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O cncesc WH _11 198G Goodyear Aerospace Corporation License No. SNM-1461 ATIN:
J. V. Pflaum, CIH Industrial Hygienist Senior Corporate Industrial Hygiene and Safety Department 131 G 1 1210 Massillon Road Akron, Ohio 44315-0001
Dear Mr. Pflaum:
This refers to the confirmatory survey of your Wingfoot Lake Advanced Technology Center by Oak Ridge Associated Universities (0RAU) during the week of May 12-16, 1986.
As was discussed with you during the survey and in subsequent telephone conversations with this office, several areas were identified that exceeded maximum release levels of 15,000 dpm per 100 cm3 (specifically,the decontamination areas and grid block C-42). While the ORAU survey report has not yet been finalized, it is our understanding that the referenced areas will either be further decontaminated or physically removed to meet the NRC facility release criteria established in Policy and Guidance Directive FC 83-23. "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material" (copy enclosed).
Subsequent to these activities, we request that you provide us with a final close-out survey of the facility includina:
a.
A diagram of your facility with survey results keyed to specific locations.
b.
The name of the person performing the survey.
c.
The date the survey was perfomed.
d.
The instrument (s) used.
e.
Background readings.
f.
The date that the survey instrument was last calibrated.
Following our review of your final survey, we will (1) arrange for ORAU representatives to confim that r.11 previously excessive areas teet NRC release fc01
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Goodyear Aerospace Corporation 2
JUN 11 1988 criteria, and (2) continue with our licensing action to release the Wingfoot Lake Advanced Technology Center for unrestricted use.
Should you have questions concerning the above, please contact this office.
Your cooperation with us is appreciated.
Sincerely,
( Al'Y*
WilliamL.AIeso.n, Chief Nuclear Materials Safety and Safeguards Branch
Enclosure:
As stated cc w/ enclosure:
J. D. Berger, OPAU DCS/RSB (R105) bcc w/ enclosure:
J. A. Hind, RIII k
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GUIDELINES FOR DECONTANINATION OF FACILITIES AND EQUIPMENT PRIORTORELEASEFORU$RESTRICTEDUSE OR TERMD:ATION.,0F LICENSES FOR BYPRODUCT, IOURCE, OR SPECIAL NUCLEAR PATERIAL e
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O U. 5. Nuclear Regulatory Comission Division of Fuel Cycle and raterial Safety
as hington, D.C.
20555
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The instructions in this guide, in cor..'onction 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 abandenment or release for unrestricted use. The limits in Table 1 do not a'pply to premises, equipment, or scrap containing induced radio-activity for which the radiological considerations pertinent to their use may be different.
The release of such facilities or items from
, regulatory contro') is considered on a case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or su faces shall not be covered by paint, plating, or other i.cvering material unless contamination levels, as determined by a survey *and docu ented, are below the limits specified in Table 1 prior to the application of the cevering.
A reasonable ef fort must be made to minimize the centamination prior to use of any cevering.
3.
The radicactivity on the interior surfaces of pipes, drain lines, or duct-ork shall be detemined by making measurements at all traps, and other appropriate access points, pr:vided that conta.>
ination at these heations is likely to be representative of centamination on the interior of the pipes, drain lines, or ductwork.
Surfaces of premises, equipment, or scrap which are likely to be contaT.inated 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 re;uest, the Co cission may authori:e a licensee to relinquish possession or control of premises, equip ent, or scrap having surfaces contaminated with materials in excess of the limits specified.
This may include, but would not be licited to, special circumstances such as ra:ing of buildings, transfer of premises to another organi:ation continuing work with radioactive materials, or conversion of facilities to a long-tem storage or standby status.
Such requests raust:
Frovide detailed, specific information describing the premises, i
a.
equipment or screp, radicactive contaminants, and the nature, extent, and degree of residual surface contamination.
b.
Provide a detailed health and safety analysis which reflects that the residual arounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment cr scrap, are unlikely to result in an unreascnable risk to the health and safety of the public.
l 4
m 2
s 5.
Prior to release of premises for unrestricted use, the licensee shall make a ccmprehensive radiation survey which establishes that sontamination is within the limits specified in Table 1.
A copy of the survey report shall be filed with the Division of Fuel Cycle and ?.aterial Safety, USNRC, Washington, D.C.
20555, and also the Administrator of the NRC Regior.a1 Of fice having jurisdiction. The r(port should be filed at least.30 days prior to the planned date of abandonment, The survey report shall:
a.
Identify tf e premises.
b.
Show that reasen'able effort h'as teen made to elicinate residual contamination.
c.
Describe the scope of the sur!ey and general procedures followed.
d.
State the findings of the survey in units specified in the instruction.
Fo11cning review of the report, the NRC will consider visiting the f acilities to confirm the survey.
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