ML19259C864
| ML19259C864 | |
| Person / Time | |
|---|---|
| Site: | 07001379 |
| Issue date: | 07/17/1979 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19259C861 | List: |
| References | |
| NUDOCS 7908160026 | |
| Download: ML19259C864 (4) | |
Text
.
PAPL* ELL DECONTAMINATION PLAN A.
Instrumentation and Monitoring Accessories (1)
Eberline LCS-1, Electronics (2)
Eberline, RM-3A, Radiation Monitor (3)
Eberline FC-2, Gas Proportional Detector
(?)
Ebe-line CS-10, Th-230 source, SN 866 nominal activity 3.75 x
-3 10 juCi (3) Air Sampling heads (6) Whatran //1, Smear Paper (7) 1:~i- 0, Air Sample Paper (S) 90% Argon, 10 Methane Counting Gas 3.
Instrument Preparation (1) Radiation Mcnitor (RM-3A)
(a) Turn on instrument and allow to ware up prior ta use.
(b)
Check fer coerability by placing probe over Th-230 source until a stable count rate is obtained.
Record count rate.
Operability will be checked prior ta use each morning and/or af ternoon, and at the end of a survey day (c)
Determine counting efficiency ?sily.
Cbserved count rate frc: E.1.5 (c/21
. g;
,g
,,, (s (5curce strength (,cci)) (2.22 x 10' d/ / pCi)
(2) Stear and air sample counter (LCS-1 and FC-2)
(a)
Turn on gas to FC-2 and allcw to purge fcr three rinutes.
(b) Turn en LCS-1 and allcw te war: up.
(c)
Deter:ine the 21pha operating plateau according tc manuf atturer's specification.
(d)
Check for operability by placing the Th-230 source under the purged charber.
A series of 100 second counts will be made until ti.e counts =rc teproducible to I 2 Ns.
hecord t!.e stable count rate.
Operability will be chec'..ed prior to use each day.
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. ~. -3 rc a
7 9 0816 0 c32f:,
(e) Determine an alpha background daily for five minutes by counting (an) empty purged cha ber(s).
Record background.
(f) Determine counting efficiency daily.
Obse rved count rate fro: B.2.d (c/ )
, f, (,. )
d/ / pC1) x 100 c.
=
(Source strength ( pCi)) h2.22 x 10 6
C.
Survey Procedures (1) Ncnrenovable (by dry scear) contamination (a) Surveys for nonremovable contamination will be_ =ade with the RM-3A prebe in direct contact with tne surface to be measured.
(b)
The probe will retain over the surface to be ceasured until a stable count rate is achieved.
(c) Metheds for averaging survey results and applicable levels of activity will be in accordance with " Guidelines For Decontamination of Facilities and Equipment Prior to Release For Unrestricted Use or Termination of Licenses For Byproduct, Source or Special Nuclear Material" (Appendix A, Table 1) (copy attached).
(d)
Initial and final survey results will be recorded.
(2) Removable Conta ination (a) Smears will be collected using dry What=an #1 filter paper in accordance with Appeadix A, Table 1.
(b)
S= ears will be counted in the LCS-1/7C-2 syste: for a 100 second cc 2nt and backgr.und subtrac__d.
(c)
Initial and final erear survef results will be recorded in d/2/100 ca".
(d) A caekgrcund count (see Sectice 3.2.e) will be taken after ever; tenth smear ccunt to checs for detec:cr centleination-(3) Air sampling (a) Air sa ples.'ll be collected in the 12:ediate area being decen:aninated cn Hi-70 paper daily at a ficw rate of 2 x 10' =1/ min.
(b) Air sa ples will be ccunted on the LCS-1/FC-2 for 3,100 seccad counts, backgrct ' subtracted and averaged.
(c) All air sample results will be recorded in juC1/ 1.
(d) The decentamination operation will be te rinated if airborne Al concentrations aro grea:er than 3 x 10
,cC1/11 (Pu-238 insoluble 10 CFR 10, Appendix B, Iable 1, Column 1) until corrective action can be taken.
c - vs n,o U U L'<*J y3'
D.
Protective Clothing (1) Protective clothing (pants, shirt and shoes) will be worn during the decontamination operatien, surveyed prior to leaving the facility and disposed of as radioactive waste if found to be contaminated.
(2)
Protective clothing will be removed prior to leaving the facility and left at the entrance to the facility.
(3) Personnel surveys will be made when leaving the facility.
E.
Decontamination Procedures (1) Re:cvable surface contamination (a)
Detergent water at.- paper towels will be used to wash contaminated areas, minimizing the use of liquids.
(b) The areas will be dry and a survey performed (see Section C.2).
(c) Repeat E.1.a and E.1.5 as necessary.
(d) Waste (wet towels and smears) will be retained.
(2)
Surface contamination not able to be removed by Section E.1 methods.
(a) Paint thinner / recover will be applied to local contaminated areas and allowed to remain in place as paint softens.
(b) Affected paint will be recovci wi h a putty knife.
Pa:nt will be recoved frc the putty.:.fe.
(c)
The area will be dry and a survey performad (see Section C.1).
(d)
Repeat E. 2.a and E. 2.b as necessary or until no caint remains.
(e) Waste (:mLnt residue) will be retained.
(3)
Surface centa:Inatica net able to be recovec by Sect ;n E.2 methods.
(a)
Concrete etch will be applied to local ;ntacinated areas and alicwed to retain in place for a predetermined time (manufacturer's specificatien), minimizing the use of liquids.
(b)
The etch and cen ete residue will be reccve using a wet i
towel.
(c) The area will be dry and a survey perforced (see s ection C.1).
(d) Repeat E.3.a through E.3.c until no reduction in activity is noted.
(e) Waste (paper towels and contrete residue) will be retained.
U d: o o m e g
s MJ C '
(4)
Surface centamination not able to be rencved by Section E.3 methods (Mechanical removal - chipping).
(a) Accurately determine the contaminated area.
(b)
Construct a tecporary shield to prevent scattering of chips and concrete residue.
(c)
Dampen the area to be chipped.
(d)
Chip area.
(e)
Recove debris using a wet paper towel.
(f) The area shall be dry and a survey perforced (see Section C.1).
(g)
Repeat E.4.c through E.4.f until activity is in accordance with Appendix A, Table 1.
F.
Ite=s Above Grade (1)
Items above grade (electrical panels, electrical outlet boxes, shelves, etc.) will be decontaminaed using Section E.1 and/or E.2 =ethods or disposed of as radioactive waste.
Care will be taken in the disposal of these ite=s to prevent the spread of contaminatien.
These itens will be cleaned / disposed of before the floor is decontaminated.
C.
Waste Retention and Disposal (1) Liquid waste will be solidified.
(2) Waste will be collected and stored in metal druts, with lids and lid clamps.
(3)
Radioac:ivity in waste will be quantified and ei:her transferred to a li:ensed burial site, depending en the rarerial, er buried in accordance with 10 CFR 20.3 4 Ne raterial will be bur.eu.n accordance w.,_..n
.3ns c.: R a v,. ;t 4 un t.,.,
- s. c~. -. :.s21I 4.s 4
2,
notified in writing of the type and quantity.
(4) Wacte will not be dispesed of until af:2r a final acceptance survey is performed by NRC:IE:RIII and results are in a:?.ordance with Appendix A, Table 1.
H.
Sanpling (1) A sample of the liquid and semi-salid caterial in the septic tank will be collected and split with NRC:IE:R!ll for analysis.
A representative of NRC:IE:RIII will be present when this sa:ple is collected.
-on n r-ss.
(2)
The Parkwell portion of this sample will be counted for gross alpha activity.
(3)
If the results are greater than 35 d/=/gra: (dry) either an alpha isotopic analysts will be perfort 2d or the waste will be considered to be plutoniur ar.d disposed of accordingly.
rs
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Apper. dix A 1
t' GUIDELINES FOR DECONTAMINATICN OF FACILITIES AND EQUIPMENT FRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECI AL NUCLEAR HATERI AL U.S. Nuclear Regulatory Conr.ission Division of Fuel Cycle and Katerial Safety Washington, D. C. 20555 9
The instructions in this guide in conjunction with Table I sp accomplishing the deconta.ination and survey of surf aces or premises and i
The limits equip ent prior to abandonment or release for unrestricted use.
i radioactivity for which the radiological considerations pertinent to their The release of such faciliti s or ite's from regula-use may be different.
tory control will be considered on a case-by-case basis.
Tne licensee shall rake a reasonable effort to eliminate residual 1.
contamination.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering ratrial unless contamination leve 2.
A reasonable effort must in Tables I prior to applying the covering.
be made to minimize the contamination prior to use of any covering.
The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by raking reasurerents at all traps, and 3.
other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the in-Surfaces of premises, terior of the pipes, drain lines, or ductwork.
equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to take the surf ace inacces-sible for purposes of measurement shall be pretumed to be contaminated in ex:ers of the limits.
Upon request, the Coa-ission may authorize a lice 35ee to relinquish possession or control of premises, equipment, or s rap having surf aces 4.
This contaminated with raterials in excess of the limits specified.
ray include, but would not be limited to, special circums continuin; work with radioactive caterials, or conversion of facilities Such requests must.
to a long-term storage or standby status.
Provide detailed, spe:ific infor atico describing the premises, equiprent or scrap, radioactive contaminants, and the nature, a.
extent, and degree of residual surfa:e contamination.
Provide a detailed health and safety analysis which reflects that the resi:ual amcunts of raterials on surf ace areas, together witn b.
other considerations such as prospective use of the pre-ises, equipcent or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
~
Prior to release of premises for unrestricted use, the licensee shall rake a comprehensive radiation survey wti:n establishes that conta -
5.
A copy of the ination is witnin the limits specified in Table 1.
survey. report shall be filed with the Chief, Materials Branch, Divisien j
('
e m,,, T m, ? $ f'l Appendix A p
p)'
Page 2 o E !.
tJ Q,a bbbb
' '2 of Fuel Cycle and Material Safety. USNRC, Washingten. D.C. 20555, and als:
the Director of the Pegional Office of the Office of Inspection and Enforce.
rent, USNR, having jurisdiction.
The report should be filed at least 30 days prior to the planned date of abandor. ment.
The survey report sha*1:
-a.
Identify the premises.
b.
Show that reasonable effort has been made to eliminate residual contamination.
c.
Describe the secpe of the survey and general procedures followed.
d.
State the findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the facili-ties to confirm the survey.
Tm -
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