ML20127E872
| ML20127E872 | |
| Person / Time | |
|---|---|
| Site: | 05000172 |
| Issue date: | 02/02/1971 |
| From: | Dewar M LOCKHEED AIRCRAFT CORP. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20127E447 | List:
|
| References | |
| FOIA-84-737 NUDOCS 8505200238 | |
| Download: ML20127E872 (6) | |
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2 February 1971 1.
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4 c.a United States Atomic Energy Coasnission _
Division of Reactor Licensing
. Washington, D. C. 20545
Subject:
Radiation Effects Reactor, Docket 50-172 Gentlemen k ckheed-Georgia Company is in the process of preparing plans for de-coannissioning the Radiation Effects Reactor, and has encountered certain -
unique problems because of the uniqueness of the facility. One problem is the fact that a considerable amount of relatively low level activation has occurred in various items of equipment and structures. We have been unable to determine where a situation such as this is addressed in the Code of Federal Regulations, and hence we would like an opinion from the Comission on the proposed criteria listed in the following paragraphs.
Guidelines fg Decontamination g Pa'c111 ties gd,, Eouitment fyj,or, jig, EpJ,3gs, f,gt, Unrestricted y,g,g, or, Temination g Licenses for_ Byeroduct_.
Source. g Special Nuclear Material. which was published by the Division of Materials Licensing on April 22, 1970, appears to be a reasonable standard for release of non-activated components from the reactor facility.
Furthemore, we understand that Guidelines has already been used as a de-contamination standard in several reactor decomissioning programs including Hallam and Piqua. Mckheed requests the Division of Reactor ,
Licensing to confim to Mckheed that the above Guidelines -- two copies of which are attached -- is acceptable as a decontamination standard during decomissioning of the R1!lR.
With regard to activated equipment and structures, Lockheed proposes to release from control all items which meet the smearable contamination standard in the above Guidelines and which have residual radiation levels j of less than 0.2 mrad /hr at 1 cm when measured in accordance with the j
above Guidelines. Lockheed would like confimation of Comission's acceptance of these criteria for release of activated structures and equipcent.
I e50520023e e41025 Ek hMA 737 PDR g' 531
_2 If the-Conunission does not concur with one or both of the above suggested approvals by Lockheed, we wish to be so advised, and would appreciate
- guidance as to a solution which would be acceptable to the Consnission.
Very truly yours, ,
IAC10'FRn-GEORGIA CO!&ANY N -
N SM $
M. A. Dewar, Scientist Dept. 72-14, Zone 401 MADadh 6
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? The. instructions ~in this guide in conjunction with Tablea. I and II J.
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specify the radioactivity and radiation exposure rate limits which should be used in accomplishing the decontamination and survey of
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'sufaces of premises and equipment prior to abandonment or release ' .
for' unrestricted use. The limits in Tables I and II do not apply .
to premises, equipment, or scrap containing induced radioactivity
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, for which the radiological considerations pertinent to their use may be difresent. The release of such facilities or items from
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regulatory control will be considered on a case-by-case basis. -
- 1. The licensee shall make a reasonable effort to eliminate '
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residual contamination. - .
- 2. Radioactivity on equipment or surfaces shall not be covered '
by paint, plating, or other covering material unless con-
,.j. .. ... tamination levels, as determined by a survey and documented, f,!,1.. .
'." are below the limits specified in Tables I or II prior to -
/. applying the covering. A reasonable effort must be made to -
- minimize the contamination prior to use of any covering. -
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..* 3. .The radioactivity on the interior surfaces of pipes, drain .
. , lines, or ductwork shall be determined by making measurements '
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at all traps, and other appropriate access points, provided , ,
'; ~g that contamination at these onlocations is likely of thetopipes, be repre-J ; sentative of contaminatten the interior drain
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lines, oriductvork. Surf. aces of premises, equip =ent, or scrap *
,, . '.l1 :. which are likely to be contaminated but are of.such size, . -
.j" . _- . h'constiuction, or location as to make the surface inaccessible *
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' for purposes of measurement shall be presumed to be contaminated A. in excess of the limits.
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- 4. Upon request, the Co= mission may authorize a licensee to relinquish
't , possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits-
- , l .- .specified.- This may include, but would not be limited to,- special * ,
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'circuir. stances such as razing of buildings; transfer of pre =ises '~
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- to another organization continuing work with radioactive materials, i or conversion of facilities to a long!. term storage or standby j,:jl-
- status. Such requests must
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'I , ", n. Provide detailed, specific information describing the premises,
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. equipment or cerap, radioactive contahinants, and the nature, extent, and degree of residual surface contamination.
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- b. Provide a detailed health and safety anelysis which reflects
.' that the residual a:tounts of materials on surface areas,
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t of the pre =ises, equiptent or scrap, are unlikely to result 1.. - .
in an unreasoncble risk to the health and safety of the public.
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'I 5 Prior to release of premises for unrestricted use, the licensee shall ,
i make a comprehensive radiation survey which establiches that contam- -
ination is within the limits specified in Tables I or II. A copy of
.[! , the survey report shall be filed with the Director, Division of .
Materials Licensing, USAEC, Washin6 ton, D. C. 20$5, and also the - -
Director of the Regional Division of Compliance Office having i jurisdiction. The report should be filed at least 30 days prior to 8
the planned date of abandonment. The survey report shall: .
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- a. Identify the premises. .
I b. Show that reasonable effort has been made to eliminate residual *
~i~ . contamination. .
? c. Describe the scope of the curvey and ge.teral procedures followed. , ,
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State the find 1nc,s of the survey in units specified in the ';-/
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, instruction. '
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Following review of the report,'the AEC will consider visiting the facilities to confim the survey. _
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TAB 1.E H_
" ME I RDOVABL3(3) ~ g, TOTAL (3) REMOVABLE {3) g4) TOTAL (3)
ISOTOPE (2) .
2 2 Average (6)
U-nat U-235, U-238, 10,000 dpa e/100 cm 1,000 dpa a/100 cm 2 1,000 dyin o/1,00 5,000 dpa n/100 ca i4 Th-nat. Th-232, an'd ,
f'u t Maxir.um
'l,. Essociated decay products '
- 25,000 dpm n/100 cm 2- ,,
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j 2 2 gy,,,g,(6) 1,000 drm a/100.cm 100 dpa a/100 cm 2 100 dpm al.
[ .' 500 dpm a/100 ca
, .'Other isotopes caissionwhich or by decay by alpha Maximum 2
spontaneous fission ,
2,500 dpm o/100 cm
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0.4 mrad /hr at 1 cm .)~
I 1,000 dpmfFy/100 cm Average-
.' ' [ ,'. . Beta-gamma emitters (iso-0.2 mead /hr at 1 ca(5) 1,000 dpa h /10
- topes with decay modes
- Maximum ' -
other .than alpha amission , . .
1.0 r. rad /hr at 1 cm(5)
.or spontaneous fission) t' rither Table I or Table II may be used. For example, if all beta-gamma readings were less than 0.4 mrad /hr at I
's. (1) Table I could be used; but-if the maximum reading were 0,8 mrad /hr, material could be released under Table II p l
'. I~ viding the average was less than 0.2 mrad /hr.
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' (2)
Where surface contamination by both alpha and beta-gamma emitting isotopes exists, the limits established for i
',,i and beta-ganma emitting isotopes shall apply independently.
- - As used in this table, dpa (disintegrations per minute) means the rate of emission by radioactive
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, ,f .' *(3)determined by correcting the counts per minute observed by an appropriate detector and count rate me j ..
ground, efficiency, and geometric factors associated with the instrumentation. .
.g of surface area shc11 be deternined by wiping that area, (4) The amount of removabic radioactive material per 100 cm
,' '}~ with dry filter or soft absorbent paper and with the application of moderate pressure, In determiningand' assessing removabic the cc radioactive material on the wipe with an appropriate instrument of known efficiency. d the entil.
I' tamination on objects of lesser surface area, the pertinent . levels shall be reduced proportionally, an ~
surface shall be wiped.
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Heasu' red through not more than 7 milligrams per square centimeter of total absorber.
For objects of lesser l
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of total contaminisnt shall not be averaged over more than 10 square meters.
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REFERmED TO OATE RECElvED sv og3Caar TION. (uws: Se unclausfed)
Ltr advising of proposed plaa for Schl 24-3 gfg e,, g g,3 d'ecomissioning of the RER......
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