ML20235Z314
| ML20235Z314 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 12/19/1986 |
| From: | Chapman J, Remley M, Tuttle R ROCKWELL INTERNATIONAL CORP. |
| To: | |
| Shared Package | |
| ML20235Z279 | List: |
| References | |
| N704SRR990027, NUDOCS 8710210085 | |
| Download: ML20235Z314 (78) | |
Text
f,. [ lhM w
~
SUPPORTING DOCUM GO NO.
S/A NO.
PAGE 1 OF TOTAL PAGES EV LygHj NUMBEH 95722 39001 82 82 NEcj N704SRR990027
)
PROGR AM TITLE Building _055 Decontamination and Deactivation DOCUMENT TITLE Final Radiation Survey of the NMDF l
i DOCUMENT TYPE KEY NOUNS l
Safety Review Report Decontamination, Decommissioning-ORIGINAL ISSUE DATE R EL. DATE APPROVALS DATE i
}& ~ l 9-Pfo ~Sw
[ )
,7 e
p M-86 PREPARED BY/oATE DEPT MAIL ADDR J. A. Chapman 641 T100 M. E. Remle 4
f(Agf
.)f. Chp n/n/%
'\\
j IRh PROGRAM? YES O NO F
,g YES, ENTER TPA NO j
DISTRIBUTION ABSTRACT Mall NAME
_f Following the removal of equipment and-ADDR previously detectable radioactivity from the
- J. W. Carroll (5)
LB11 Nuclear Materials Development Facility (NMDF)
- J. A. Chapman (2)
T100 during the course of the decontamination offort,
- F. C. Schrag T020 a formal final rad.iological survey was performed.
- M. E. Remley (10)
LA06 The purpose of the final survey is to determine '
- C. 3. Rozas CB01 the level of effectiveness of the decontamination
- R. J. Tuttle (2)
T100 ef fort and to demonstrate that the~bteilding meets
- NM0F File T100 release criteria for unrestricted use.
The results
- R&NS File T100 show that all inspection tests were satisfactorily
- F&IE LB05 passed and that the area is acceptably clean of radioactive materials.
This survey demonstrates that the facility meets the requirements of Annex B to NRC License No. SNM-21,-
" 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)."
l RESERVED FOR PROPRIETARY / LEGAL NOTIOES 87102)0005 % O 2S PDR nDOCK PDR C
0195Y/bes
% COMPL'iTE DOCUMENT NO ASTERISK. TITLE PAGE/
SUMMARY
OF CH ANGE PAGE ONLY FORM 734.C REV.1244 1.
u i
- /. '
i e
..x
?
.]
'No.:=,
N7045RR990027 e
~Page: '2' I
.i i
i CONTENTS.
')
I Page
)
1.
Introduction..................................................... 'II.
Identification of' Facility Premises..........'.................'...
8.
A.
Bui l di ng Cha racte ri sti c s.....................................
8:
1 B.
Radiological Condition......................................
13 U
III.
Decontamination Efforts..........................................
16 IV.
Survey Scope.....................................................
18
)
A.
Data Acquisition.............................................
19 B.
Data Reduction..............................................
21 1
C.
Data Analysis................................................
24
\\
V.
Sampling Inspection...........................:..................
27"
-l A.
Counting Statistics.........................................
27 B.
Sampling Inspection by. Variables............................-
30-
'l VI.
Procedures.......................................................
33 A.
Calibration and Instrument Checks...........................
33' H
B.
Average Contamination Measurements.................'........
34 C.
Maximum Contamination Measurements......................
35-D.
Removable Contamination Measurements........................
35 E.
Miscellaneous Gamma Qualification Incpection................
35 F.
Surveys of Special Structural Features and Components.......
36 VII.
Survey Results.................
37 A.
Statistical Results..........................................
37 B.
Areas of Increased Sampling.................................
52 C.
Results for Special Structural Features and Components......
56 0.
Anomalies...................................................
60 VIII. Conclusions.....................................................
62 IX. References.......................................................
63 Appendices A.
Sampling inspection Data Group by Lot.......................
64 B.
USNRC License SNM-21, Annex 8................
79
- - - - - = - - - - - - - - - - - -
~
=-
~-
,G r
c, 1
.5 No.:-
N7045RR990027L e
Page:
3 L
'i TABLES Page-j]
1.
Summary of Survey Results (Office Area and'0ther Unposted Areas)'..
37 2.
Summa ry of Su rvey Results ( Glovebox Room)........................
.37 3.
Summa ry of Su rvey Res ults ( Posted Areas )'.........................
38
.)
4.
Maximum Surface Activity.(Hot Spots).............................-
39 i
5.
Additional Sampling Locations.....................................
53.
6.
Summary of Various Equipment and. Features Surveyed for Contamination....................................................
57 A.1 Sampling Inspection Results of the Office Area and
]
All Other Unposted Areas.........................................
'65 A.2 Sampling Inspection Results_of the Glovebox Room.................
69 A.3 Sampling Inspection Results of the' Posted Area Except for the Glovebox Room.....................................
74 FIGURES 1.
Rocketdyne Santa Susana Field Laboratory.........................
9 2.
The NMDF Site....................................................
10 1
3.
The NMDF Architectural Plan......................................
11 4.
Facility Layout and Room Descriptions...........................
12 5.
(Pu Release) Locations in Glovebox Room..........................
14 6.
The Gaussian Probability. Density Function........................
28 7.
The Gaussian Cumulative Distribution Function....................
29 8.
Operating Characteri stics Curve..................................
32 9.
Average Alpha Activity (Of fice Area _ - unposted)..................
a0
]
10.
Removable Alpha Activity (Office Area - unposted)................
41 i
11.
Average Beta Activity (Office Area - unposted)...................
42-1 12.
Removable Beta' Activity (Office Area - unposted).................
43 13.
Average Alpha Activity (Glovebox Room - posted)..................
44 14.
Removable Alpha Activity (Glovebox Room - posted)................
45 1
15.
Average Beta Activity (Glovebox Room - posted)...................
.46 1
i 1
4 e
o
.a
.*r 2No.:
' 704SRR9900270 P"
L Page:
-4
- (.-
FIGURES (Cont'd)
.Page 16.
' Removable Beta Activity (Glovebox! Room - posted).................-
47-
'17.
Average Alpha ^ ctivity (Remaining posted area)...................
48
~
18.
Removable Alpha'Activityf(Remaining posted. area).....'..;.........
~49 19.
Average Beta Activity (Remaining posted a rea)............ '........
1501 j
23.
' Removable Beta Activity (Remaining posted area)..................
'Sil 21.
Survey Results of., am 126 (Process Laborator 1100% F l oo r Sampl e............................. y) 54:
i_
22.
- Survey. Results ' of the. Vault 100% Floor Survey............ '.......
'55.
1 i
4 1
.[
1 R
}, [F a
No. !-
N7045RR990027 Page: -5
~
1.
-INTRODUCTION Located in the Simi Hills of Ventura Countyp California,.the Nuclear.
Materials Development Facility (NM0F) was. designed, constructed,. and operated-by Rockwell. International for research, development, and production work'with alpha emitting and/or highly radiotoxic nuclear and radioisotopic' fuels. - The 4
major effort at this f acility 1.nvolved plutonium-bearing' fuels, primarily.
plutonium-239.
The final products;were solid. reactor fuel materials, radio-isotope heat sources, or radiation sources.in'a variety.of form; and composi-1
'l tions.
Various forms of plutonium and depleted uranium!(oxide, carbide,'
metallic) were used as feed materials for all projects.
d 1
All of the operations involving unencapsulated radiotoxic materials i
were performed in gloveboxes which contain6d all aerosols: generated during normal handling processes.
The facility was operated for a total of about.
16 years, and experienced only three contamination incidents.
The first 1
i occurred in 1973, when a plastic bag connected to a glove port.on gloveboxes 17 and 17A ruptured and released measurable plutonium containination onto the
)
eastern side of the glovebox room.
In the second incident,.a vacuum pump. leak-I resulted in the-release of detectable plutonium contaminationLon the glovebox room floor, toward the vault.
Both releases were determined to be localized I
to the insnediate area of the incident although small quantities of'contamina-,
f tion did spread throughout the room, including the. overhead pipes and duct I
work. A spill of contamination also occurred in the process' laboratory, whichl was used as a waste handling and packaging room during operations; consequent-ly, this room was suspect as containing trace quantities of plutonium or-
{
Except for the boiler located in Room 128, the emergency diesel genera-
.l tor located in-Room 132, and associated compressors.and air' conditioning units -
located outside of the building on cement foundations, the building has been I
gutted.
Most of the equipment removed was disposed of as radioactive waste under the burial criteria for transuranic waste.
All detectable radioactive.
material was removed.
Residual contamination in the facility'is.well below applicable limits specified by Annex B to Special Nuclear Materials Licens'e No. SNM-21.
wt----
l
)
4
.No.:
N7045RR990027 l
Page:
6 1
l 1
Surveys were performed during the decontamination work to identify any areas needing further decontamination.
After these surveys showed that the facility was completely clean and that the' decontamination effort was fin-ished, a formal documented survey was performed to' provide a quantitative demonstration of the satisfactory level of residual contamination.
This sur '
vey is an application of a sampling inspection method, inspection..by varia-bles. This application is similar in performance to inspection by attributes-and variables discussed in Reference 2 (Decon-1)'.
In this sampling inspection, a minimum sample of 11% of the surface was performed on the floors, walls, and ceilings to measure the average alpha sur-f ace activity, removable alpha surface activity, average beta surf ace activ-ity, and removable beta surface activity.
Because of the very low residual activity found, the surface dose rate was not measured.
Samples of soil, drain line sludge, paint, and miscellaneous samples were collected and ana-lyzed as necessary; special structural features were surveyed when determined i
I appropriate. The inspection sample was structured on the basis of.a uniform a
3-meter-square grid, with a single 1-meter-square location selected for meas-urement from the nine locations in each grid.
The 1-meter-square location in each grid was selected with the intent of choosing a location where there could be potentially higher residual contamination.
(The use of the 3-meter-square grid assures roughly uniform distribution of sample locations thrc99 -
h out the facility.)
One-meter-square locations were surveyed with alpha and 2
beta sensitive equipment, and 100 cm of the surface in each location'was 2
swiped and tested for removable activity.
If the results of the 1-m survey exceeded 80% of the release criteria, additional sampling in nearby locations was performed and the results incorporated into the analysis.
All areas determined during this survey to be. greater than 80% of the acceptance criteria were decontaminated further.
While the Nuclear Regulatory Commission has adopted surface contamination limits established in Annex B of Rockwell International's license SNM-21, docket 70-25, as suitable for release of equipment and facilities for
(
f No.:
.N7045RR990027 Page: 7 unrestricted use, the goal.is to eliminate residual contamination to.the extent reasonable.
This:has been done and is demonstrated by the results of-i the survey.
l s
The statistical test applied to the survey, inspection by' variables, is-l based on a consumers' risk.of acceptance'at 10% defective, that is', 0.1, and assumes that the data follows a Gaussian probability density function.
In all cases, the measurements show that the test is satisfactorily passed and the building is acceptably clean.
]
l
e,
'i i
~i
'No,b
'N7045RR9S0027 Page:
.8
]
I II.
IDENTIFICATION OF FACILITY' PREMISES A. ~ BUILDING. CHARACTERISTICS-
'The premises to be released'for' uncontrolled use consist of Build-ing T055,.a security post on the north sidelof'the; building,^and equipment yards surrounding the building but within the f acility security. control fence.
It is' located at the! Santa Susana Field. Laboratory in the Simi. Hills of Ventura County, Cal,ifornia, shown in Figure 1.
.The NMDF site is presented in Figure 2.
The NMDF building enclosure is a tilt-up; concrete structure 200-ft long (running north and south), 60 ft wide, and'.16 ft high-The building'is divided into an administration area, change rooms, chemistry and other servics
~
laboratories, a glovebox roc:::, a vault, and facility equipment rooms.
The architectural plan is shown in Figure 3..The entire facility site was'a con-trolled access area; however, the building was divided into posted and un-posted radiologically controlled areas.
Figure 4 identifies each room of the facility and shows the posted and unposted areas.
The building is constructed of noncombustible materials including' window-less, precast, tilt-up concrete slab walls of 6-in.. thickness'and a concrete-slab floor. The roof, consisting of lightweight concrete, tarred felt, and gravel, is supported on steel deck panels and girders.
The portion of the building surrounding the radiologically posted area was totally enclosed by I
painted concrete surf aces, weatherproof ed doors, and suitable partitions.
The floors of the glovebox room and chemistry laboratory had polyvinyl sheet-covering to provide an easily decon.taminable surface.
Prior to the demolition 1
of the building interior, systems in placo' included:
air conditioning, radio--
active exhaust system for posted areas, a separate radioactive exhaust system
'for gloveboxes, unshielded gloveboxes, radioactive liquid waste holdup, electrical power distribution, annunciator and controls, alarms and instru-mentation, fire protection, and plumbing.
Section III of this report
' :7,'s Y
o S
E 3
,) -
_N. 5 3
, IY-i
.P d
fE V yC-
)
1 8
s G
g s
- '[#
=
e J
'2 9
/4M 0
1 g
=
=
9 E*
.ss "
' = =
.\\'
- '.h-ly; l
/
=
^J E
1
.~
f 1 =
"=
f
,J E"
- ,.[?
r T *"
- +a
~
s'
/
Ty, i
l
.l
,.,/w.~fY
~
~
l
., _ ~
Q
,n
}
s a
~ s., l"p.
n c
o o
b%'Y.
t
_r a
s
. g,n,E
~
+
1 Q#
~.,
s~
g H
g
'3
.z ' ~'y-u M
=
Y
=
R
~
~
~
2 *"
y
,^
?E-O
~
~
b
i T
1*0, f
^
=",
id L -
A R
=
O
[
=
O
&%kw' r
[
L B
~
r 0
A 0
L
+ ~ ~ _f/=
EN D U
2 8
Y 9
0 L 1
e g
T E Y
a
[
I A
e a
E s
=
K F a
B I
gp CO A s-R NA
~
S
.~
U
./
k S
g 3
u A
~
/
T
=
N i
A h
S
=
=
A 53 1jl
zgOE* o
'S
~.
2 9.
mo
~
, g l
I i
iI I
I i.
g I
l l
I J
=
~-
u
-9 3
- .8 5
=
6
'E A
1 7
l" o M
8
~" =-
b"
- =.
E ET
^
m VS IA TW C
- i ADP a
~
i 0IU l
l t
s IUD DQL-AIO L
T RLH
~
J.b4."
=.
N
^
0 E
M
"_8 6
'n P
8 O
?
n i
Eh D
L e
3 hr E )F i
w s
5 __
V e 0 0 e
D 5
-.T
- 3 k' E
e DM0_
"*. e, 0 D t
i ke SN G __
0 s
g S
m s gD L(
F' r
AY N_
O_b n[j h D
g 1
t I
T N
IRI D E L L _.
e
"'1-h I
T I
", cl I T
A CU_
MFAB-D
~
R
( l A
5 a
Y 2
R
?s",_'"{N J,
e F
T
,. s N
E r
M u
A P
,._a g
I s
U i
4'f..'b[
E F
~
N Q
E L
A E
C R
e
.- e A
r
.j U
_ D s
y.-
~
. E N
L E -
.d 1
L g.
_ O R
o T
'a L l' N
l j
h ~ngl I
e O
n C
o i
l i
O n
t
=
a
. T
.n m
."l o
E o
e C
t N
n E
i l
F le T
_ Y i
w k
_I J "'.
c R
o U
C R
E
_S yg l
I 1 !
g il
.I I
I i l I L
!ll1!lltIl
c
,No.:
N7045RR990027' l
-lPage:
11-k u
I I
N' I
.I g
.J i
q
_1,
.qi.,,.. - h Ag T,-
~~ j 'e
'l
}! p;I
. i v il 3 ~ tj l
1 :-
1
!! p hl p 12 lhE3 ;e f
J d Ir
=t -
i I
I I
g;l j.f s 2g
!! ps.>--
- II
];
d x s i
,j.
l 1 f,-!, lid il s
t j
p r
!i' i !f l
l li j
y ac==ei;e i*5I d,.! i 1
.r?
L 9
y
~
+:i r; 'L l9;31
% Dliiiii,l -
-]
i 1
ti, i
1 l
i u
7.,93 --- --
3 e
J
,lli i!
.l'!!dlici.
1 1.
il 5-1
- eli i
i
,e ? *!pi'!lI2ij!,i;dl5
!i!!!!!;
i i
-l j
a r-.. '
r 5
5:iiiiii a
= = =.
g
- g,,':'
EUUI! r I
s'ul'i 51 I-j p1'*
! c 'I s
3:s -
D-r" t
g
~
iiiiii
'Ot 3,1,
- i.
, e _-
5 =
-r.
c L',.,, t e 1
, s..,
O j
l
, '9
~
j e
, 5'N
'gG t,
- k.,
- a'3h 1
'1'i,,
w j
j f
E~'[ s 3"-
j W! _ _ u, _ j'" gs u.. _ _'--
- 4,,.,]'n.
j
- /
j l
l
. r.;u,,w __. 2 -.. 1,%-
3 a
...4
'fg:i%Wnw!g$-9j"C.N,"""i(l..
- $TM9's u
.O, bgi :
',_ j "Tfdg:-
)
y
!i
'i '
i Vi C.
.3 i
e:
! liti 8EB@H
' i 9 e, :3 i
too g
C g
+-.
,r
_.k*
_g (i w n
r
,,_,g
,m,i.mIi le I.4
, :1,! l j;,gerri [i.!
e i
4=>
qi 5
-1 I
i
- p..
o y
3 4
Ea ILli 3 l !l gj j.:
gj 1
a e
as I
s 9 '" g
'" s
'" g 5
1 i
i
4 No.:
N704SRR990027 Page:
12 FIGURE 4 - FACILITY LAYOUT AND ROOM DESCRIPTIONS.
Radiolo.gfca,lly,..Unposted Area _s!
- Sample lot #1 N.
Layout Room Description tumber No.
1 101 office
, ntry 2
102 Storage Area 3
103 Office 4
104 Office 6
3 3
2 1
5 105 Office.
__4 4
>,s 6
13,,
,,,,,, ' p V
6 106 Office yy Q
8 7
7 107-Conference Room 12-10 8
108 Office 9
9 109 Janitorial Service Storage 16 17 isy w
10 110 Restroom
.6 1h 22 21',
'.;' '4'.?'16 -li 12 112 Office
(,,,4~ %.hpg Q;^4f<,^
. ( >19 q.' 23 13 113 Corridor M
14 114 Office
'sw
'P;"
$^?+1 15 115
'Corrider 4"L I6,5,;'usd, 23; I4Q' 17 117 Restroom
~,
,h.pu,l,z+fw> ',"'
'* '.',n,f,p +r',s, e*!i
.> q,"',y,',,'..
' ~ " '
'^
18 118 Loeker Room 28 128 Air Conditioni.ng &
o 9;;g,,->$gjg,g1J',94.'C/e.
/e Supply Equipment Room
- 'g. ;
,;ff,.,,,,>,,.,s. p l. 2pC::l: l::
32 132 Auxilary Power Supply
~c T,'* ,Y:':M 1: ( '.' ','3 ' ;',,.,
-.,.5 ',<},0,",f",/,s!,C,.'i.,./
Ggneratar
'! 'N ' 3
.x.
33 133 Ilectrical Distribution t,,,
n.>
- ,,,', ?,.! ' :: ',',. ~;' T, ',,,, ' o 5'> ?,e.
Equipeent s~
- e>,,,
$, v,,,'y a ' ' faj /,g l.!* $
W,.,, $,,
b >$%;"$7,,
s'f',,;?~ lE *l,','..k',h 11e< ;J)o~'t::,)3, g;,c,%@,,5.i;'.O; P '-
Radiologically Posted Areasg..p..sy,3
---Sam ' : +rw,v,v
,./.,a,. n r.
~
W,!<'x"'; '^r'3':4'","C.PN':
s
.w.
'> ; j, ad'os ~ :; y',I v.4 ~
- s,,. ~ '^'D'. i '
IW Layout Room Description 1
)
'p
.uzber No. _
J
,,~
,,,,e,, '> < ':,., q.e '.,,/ ~' > /
.~;~-Q:,;,{fl""'y) ;', {T" y., p:
16 116 Chanie noou
";'v7::,"/' 'C ' 5.'~, ;,.:P.','/d 2 ji' N,';f *'/' Y,'>'d ,[j[,f[,,',j,
,.jf,'
19 119 5hower L Cha.n6e Room 9 ".
)
20 120 Airloek to Controlied Area j
e- -'
q,f:, ' ~.P. ;,,'.,,.3 'l " /.;., i, I
21 121 Health & Satety Counting Laboratory x
I,s.{!",'-,. E,. -
22 122 Photographic Dar..k. Room
,S.',
23 123 Instrument Labora.. tory
(.
33
- I
- :,,,f fp3
' 'A,W a.
24 124 Chemistry Laboratory
,29,:'.,
26
.)
N>~,
25 125
.. Corridor 1
26 126 Process Laboratory
- , ~~,
i
' [,4, ~5 :'
)
27 127 Glove Box Laboratory 32 29 129 Radioactive Ixhaust N < ;'
Equipment Room
> < h,x.
x-30 130 Airlock to Controlled Area j
31 131 Radioactive Materials
]
Storage Vault 1
i
\\
l
No.:
N704SRR990027 Page:.13 provides information regarding the decontamination ef fort, equipment removed, radiological problems encountered, and final condition of the building prior:
to the final survey.
1 8.
RADIOLOGICAL CONDITIONS
~!
The.only radioactive materials handled in the facility were plutonium (consisting of mixtures of Pu-238, Pu-239, Pu-240,. Pu-241, Pu-242, Am-241) and '
l enriched and depleted uranium. All of the isotopes decay by alpha' emission.
{
with the exception of Pu-241, which decays by beta emission to Am-241, which I
in turn decays by alpha emission.
In addition, depleted uranium, -primarily i
U-238, decays by alpha emission to thorium-234, which has such a short half j
life compared to U-238 that the daughter product is in equilibrium with the parent.
Thorium-234 decays by beta emission, to Pa-234, which also has a a
short half-life and decays by beta emission to U-234. There is essentially no U-234 present in the depleted uranium.
Therefore, two beta particles are emitted following the emission of the U-238 alpha particle.
Since the beta activity is much easier to measure than is the U-238 alpha activity, it has been chosen, for this survey, as the indicator of depleted uranium contamina-tion.
Annex 8 establishes limits for U-238 and associated decay products based upon alpha activity. Since two beta particles are emitted for each alpha decay of U-238, the acceptance limits based on measurements'of. beta 1
i activity are taken to be twice the limits' based on alpha activity.
1 1
1 i
The f acility was operated in a radiologically controlled manner; only l
three contamination incidents occurred during its operation, two involving the j
release of plutonium into the glovebox room; one involving release of activity l
in the Process Lab.
Figure 5 shows.the location of the releases in tne glove-box room. The first release occurred in June of 1973 when gloveboxes number l
17 and 17A were inadvertent ~,, overpressurized.
Although small amounts of contamination were discovered spread over the entire room, the majority-was confined to the localized area of the release.
Following the incident, the room was cleaned as necessary and returned to service.
The'second release
{
1
_J
h No.:
..N704SRR990027-
'N
- Page:
14-1 dO'9 g
n I
k E
f
>co, mal e L
'8 Bl w
s.
A E L, 2
Es G : h. magi.
M
~
.c a
a m
.x l
ist
- g l
. l g '.
, ev l 3 '
E"6 s
s-
.m m
\\[
E r,a m
u
+
5 73 2
- 3 i s ;' n -'
er er g-gs zg 1
N b
jjd:
j ll
.=
_a
.=
g i
g ie
=
. 7, ;
" M l[~~
ets 1
s j
,,~
j (13 fi w
~
~ 7u u
g a
- 7 g
g q
6 E
8
=
ant
- a E
O N( )
gi voo, av \\
s 3
'11Av^
j
=
2:
j.
'l 8
6 h
j l
3 k
f i
i e
i 31 [. { 1i 1
8 1
=
Ig
- =
14
. J a
i
,3 sg s
i 1
3 ti
',! V
} Ei 3
w e
i T.p:)h.g.-
5 b i
j i
n m
4 3-1}3i i
- E l!
tiId !! I 15 l}h0 M
{l t
!n!gil;llll ION mamh!!
1
! !a,um m!u ilj aa" a
a n
'jj j
-~~~~-- -
as:a 5AAsna a e s=:n :n=*
q
-~~.. -. = =,=
,xi.:
2.a.,=.
=
No.:~
N704SRR990027 c
Page:
15' j
occurred when a seal on a vacuum pump used for the gloveboxes ruptu' red.
This i
release was entirely localized to the immediate area. 'The leaked oil was:
1 removed and the floor cleaned. The building was.then. returned to service -
In j
the Process Laboratory, a bag of waste broke, releasing a small amount of -
unidentified contamination.. Special-care was' taken in these' areas during the j
dismantling, demolition,.and final-survev to ensure.that the area is!truly clean.
No conclusive' evidence suggests.nat the. building ever experienced j
1 other contamination problems.
]
1 m
I 1
1 4
1 t
J j
~'
L 5
g i
No.:
N7045RR990027 Page:
16 I
f III.. DECONTAMINATION EFFORTS i
Decontamination and deactivation of the' Nuclear Materials Development Facility were initiated in November 1982.
The progression.of the decontamina-tion efforts was as follows:
(1) decontamination and'then removal'of-glove-i boxes and connecting tunnels, including glovebox' equipment, (2)~ removal of utilities and low-volume exhaust system, (3)' decontamination of support area, (4) disposal of NaK in glovebox atmosphere purifiers, (5) removal of liquid waste holdup system, and (6) removal of high-volume exhaust' system.
The waste ge*1erated during cleanup operations was packaged concurrent 'with the generat-ing operation and shipped for disposal at the discretion of-Radioactive
{
Materials Disposal Facility.
4 Decontamination of the glovebox surfaces was accomplished utilizing ALARA 4
strippable paint.
This proved to be an effective and efficient method'of sur-i face decontamination.
Glovebox and tunnel section removal was completed in November 1985. Survey of the decontaminated gloveboxes was conducted to assure that they were not TRU waste and were within the criteria of LSA waste, j
i All components of the low-volume exhaust system, consisting of blowers, absolute filter banks, and associated valves and controls, were removed except for the stack which was still linked to the high-volume-exhaust system.
This was completed in February 1985.
The utilities that were removed and disposi-tioned included those used specifically for glovebox operations, i.e., cooling water, argon, helium, dry air, vacuum, and electrical and control wiring, and those utilities which serviced the glovebox room, i.e., compressed air, elec-trical power, lighting, PA system, phones, sprinklers, fire alarm circuits, radiation alarm system, and intrusiort alarms.
Removal of utilities servicing the glovebox room was completed in November 1984.
All equipment and materials in the support area were surveyed and dispo-sitioned according to the level of activity found.
This included furniture, sinks, light fixtures, and other office and laboratory equipment.
Decontami-nation of the suppor' areas was completed in October 1984.
Only material with no detectable radioactivity was disposed of as conventional waste.
?[j;;-.,[ i g-t
(
f'.
i q.
J). 2 e
H g.
.,m<<
Sc 1
. cf
(
y['
No.:Q N70.4SRR990027f [
H d <P
- Page: 3 f;
=r 17
- } lly ' %q;j p
q, g;
y a,s y
. Disposal of 'the NaK in the gloveboxcatmosphere ' purifiers. and NaK(bubblers; j c
S requifedtheinstallation:ofaspecialNaK~ disposal.'fabilitylat.tbe'NMDF,w l
n s.
-1 incorporating l remnants of the'f acility utilities andl. liquid-waste! system. ;The:
- l
.NaKbubblerswerenotonly.aproblembecausefo'fLchemicalhazbrdofNaKsbut-it.-
~..
aw.
x,,
s;1 trace. quantities' of alpha. materials were present which requireisningentjen
]
tainment. The NaK' removal process involved a combination of evaporation of K and Na at ~900*F, steaming, and finally, a water rins@g Followin (p/ieaning,-
ry-
!w 4
the. bubblers were surveyed to verify th.em as: LSA waste and trani; erred toI..,
1
~..
nec
. RMDF f or. packaging an'd. staging for shipment. to[disposa'l' sitebThe. processl f[f i
- .c l
water ~ generated during the. removal of 'NaK f rom;the bubblers' was! neutralized,-
1 L
transferred to-the RMDF, and evaporated; the ' residual Lsolids ~were packaged and staged for shipment'to'a disposal; site.
Removal and neutralization ofi he NaK t
)
l f rom the bubblers was accomplished in June 19'86.
1 The removal of the liquid waste system, required the removal of.all drain j
..t lines between the various sources, for' example, laboratory sinks and shower drains, and removal of.the for. process and EtoEage < tanks' and their associated 5
x g
equipment.
All components were packaged and' disposigned eas' necessary.
Com-e plete removal of the liquid waste hold'up system was secomplished in Mayfl386.
i The components of the'high-volume exhaust system which were removed for dis -
<v posal as LSA waste include the hood in.the glovebox room; all filters, duct-3
.e l
ing, and controls associated with the hM/,s 'and filters; and ducting and c9n r,
v
- e y
l trolsinthegloveboxrocmandvault.fThehigh-volume;exhaustsystemremgval,.
which was the final step of the[ contamination,ef fort, was accomplished.in u
i, August 1986.
- f. U,
'.e y
{
N 2 '
3 i
l d
i The contaminated waste generated on'this program were shown to be within therequirementsoflowspecificactivitycategorywiththeexceptionofNome' I
s a
process equipment from inside the gloveboxes.
This process equipment was handled as TRU waste.
L i
q
,O l
. }. /
p
i
~
e 4
No.:
N704SRR990027 d
u
'Page:
18.
.)
- <I i
IV. sSURVEY SCOPE f'
A sampling inspection plan'using variables,. discussed in the next-sec-q tion, has been used to demonstrate that(the residual cc,ntamination'in the' l
building is'below the following limits:.
Alpha Beta *-
]
Criteria (dom /100 cm)-
1
)
Total, averaged.over 1 m2 100 10,000.
')
y3 Total, maximum over'100 cm2 300:
30,000 1
a Removab'le over 100 cm2 20 2',000 l
)
m e
1 The acceptable beta contamination limits 'were derived ~ f rom alpha.contami-nation, limits presented in ~ Annex -B of USNRC license SNM-21 for ti-nat, U-235, U 238,\\and associated decay products.
The beta values are twice those of the 2
alpha limits reported based on the two beta particles emitted from the decay of Th-234, the first daughter of U-238, and Pa-234.
The alpha limits cor-respond with the license annex limits for transuranic.
For the sake of the NMDF analysis, the building was divided into three 2
sample areas: The office' area and Rooms 128,132,133,' and the air condition-I' 4
ing room (all unposted areas); the glovebox room (posted);.and Rooms 117, 118,
]
119,120,121,122,123,124,126,129, and 130 ~(remaining posted areas).
For each of the three sampling lots, the of fice area (unposted), the jl q1ovebox room (posted), and the remaining posted areas a minimum of an 11%
l j
survey was conducted on the walls, floors, and ceilings.
Figure 4 pictorially shows the sampleelots.
The sampling inspection plan that was used is based 2
upon a uniform 3-m grid superimposed on the inspection area.
A 3-m grid '
has been adopted to be consistent with guidance'provided in NRC and State'of California' documents.
The grid was superimposed on the wall, floor, and ceil-ing of each room.
Each survey area was identifi?d in matrix notation with 4
.i e
.i l
n --
3 3
[*.
s
/'
'?
~'
q'
.v.g No.:
N704SRR990027
~
r 1;,
ir Page:
19
.j codes indicating t le surface (F.= floor, C = ceiling, N, E. S, W = north, east, south,'we'it, respectively) and a two-figure Cartesian coordinate indi-cating the distance. in meters f rom a local benchmark.
The'(1,1) position for H
theJfloh w'aq benchmarked as the northwest corner of the room; an identical grid Was ruf Jected onto the ceiling.
The (1,1) position of the walls was I
bcrichmarked as the top left hand corner of the wall as an observer would view 2
2
)
it from the middle of the room.
From each 3-m grid, a 1-m was surveyed;-
fgbcAt6ami mum 11% survey. Each 1-m area was surveyed for 5 min and a 2
100,cm'faseawassmearedforremovablecontamination.
4 j
q J
r
,/
A.
DATA ACQu'SI' ION i
2 2
Within each 3-m grid, a single 1-m area was surveyed.
Each area was outlined by paint, with its coordinates marked beside the arra.
The loca-2 y
tion 'of the 1-m area was left to the surveyor's judgment.
It was to be the p
area, in Ms judgment, that 'was most likely to have retained the most residual 2
contamination of any s'imilar aree within the 3-m grid.
The surveyor was instructen' to do this conscientiously to assure that any significant residual
}
contamination would be detected before a report of acceptability was made to a regulcory agency.
The use of a predetermined grid with discretion for the exact location provides a. uniform survey biased toward the high end of the distribution. Selectionofthe1-m2 area out of the nine within each grid i
r,quare provides an 11% sampling.
If a particular surface of a room was smaller than 9 m2 (3m x 3m), a minimum of 1 m2 was surveyed for contamina-tion; in cany cases within the office area, where a wall measured typically 2
6 en, the sanpling area wts 17%.
In order to detennine the leve)..of ef festiveness of the decontamination 2
effort, four radiological characteristics were neasured for each m :; average alpha surf ace at.tivity, average beta surface activity, removable alpha surface activity, and rernvable beta surface activity.
An alpha probe and beta probe were each connected to Ludlum 2220-ESG scalers for these sneasurements.
t i
e
).
t t
)
l
'A s
L A
r
.,~
6
'No.:
N7045RR990027 Page: 20-Measurements of the average alpha surface activity were made by use of a large-diameter (9.6-cm) alpha scintillation detector, s<nsitive only to a*lpha
~
particles with energy exceeding aboutLl.5 Mey. This detector was calibrated s
by use of a Pu-239 alpha source.
The energy of the Pu-239 alpha particles (5.1 MeV) is similar to that of the isotoper which are alpha emitters handled at the NMDF; Pu-238, Pu-239, Pu-240, Pu-242, and U-238 (DU).
Measurements of the average beta sur: face activity were made.by use of.a thin-window pancake Geiger-Mueller tube.
While this detector is equally sen-sitive to alpha and beta particles and'slightly sensitive to X-and gamma-rays, it is so predominately used to measure beta-activity that it is generally called a " beta-detector." This' detector was calibrated by use of.a Tc-99 beta source. The energy of the Tc-99 beta particles (maximum 0.3 MeV) is close to-those from the U-238 daughters, Th-234 (maximum 0.2 MeV) and Pa-234 (maximum 0.5 MeV).
The measurements were made over the same area as was used for each measurement of average alpha surf ace activity.
Measurements of removable surface activity (alpha and beta) were made by 2
wiping approximately 100 cm of surf ace area, using a Nucon-type cloth disk (NPO cloth sampling smears 2 in. diameter).
The activity on the disks was measured using a thin-window gas-flow proportional counter, calibrated using larger diameter Pu-239 and Tc-99 sources.
In order to facilitate the survey, the alpha and beta probes were con-nected by a face plate such that the separation distance was no greater than a 2
couple of cm.
Eacti m was surveyed using the assembly for 5 min; this'cor-responds to a transit velocity of approximately 3.3 cm/s.
The ANSI draf t standard N13.12 states that the transit velocity (in cm/s) shallinot exceed one-third the numerical value of the detector window dimension (in cm) in the direction of the scan.
The diameter of the window is 10 cm, and therefore, this transit velocity complies with the standard.
The number of: counts registered by the instrument in a 5-min scan were recorded by location.
If a contaminated spot was detected during the' course of the " average scan" survey, the location was identified; subsequently, a 5-min stationary survey of the l
l a
- j No.:
N704SRR990027 Page: '21 2
location was conducted.
The average surface activity of the m, the maximum 2
surf ace activity of one spot located within the m, and the renovable ~activ-2 2
ity of 100 cm in the m were recorded.
2 In order to report the results in disintegrations / min per 100 cm
]
2 (dpn/100 cm ), conversion factors were. applied as follows.
First, " natural l
background" was determined by measurements made in an area of the building _
which was known to be uncontaminated.
Second, an efficiency factor for the ~
survey instrument was calculated by comparing the number of counts recorded by_
the instrument to'the number of disintegrations yielded by a calibration source. These, determinations were made three times each day;. erst thing in the morning, at noon, and just before quitting time in the evening.
- Third, the correction factor for the area of the window was calculated in order t, 2
present results per 100 cm,
Thus, for the surface contamination measurements of alpha and beta'activ-ity, data included the sample location, the total counts recorded in the 5-min scan, the maximum hot spot, natural background for 5 min, efficiency f actor, and the area factor.
The same data was recorded for the removable contamina-tion measurements except for the area factor, which is not applicable for the gas proportional detector since the sample size and check source size are very nearly equivalent.
B.
DATA REDUCTION The data was entered into VISICM.C, a spreadsheet sof tware program on the '
IBM PC.
Columns were established to calculate the total, maximum, and remova-2 ble contamination per 1-m in dpm/100.cm.
The standard error associated
,with the measurement was also calculated.
4
t n
R g
L3 3
a lNo.:
LN7045RR99'0027.
Page:.22 1
Data input:
P
'1.
Room number 2.
Grid ~ location, example N(1,3) _
3.
Alph'a total activity,s averaged over l' m2 '(counts in: 5' min) 4.
Alpha maximum activity for. hot l spot (counts in 5' min) 5.
Alpha removable activity?(counts in 5' min)L 6..
Beta total; activity, averaged,over 1.'m2'(counts in 5' min) 7.
Beta maximum activity, averaged: over 1 m2 (counts.'in 5' min) 8.
Beta removable activity;(counts-in'5 min)'
9.
Alpha survey. instrument background (5 min),' efficiency l factor (dpm/ cpm), and area factor 10.
Alpha gas-proportional' detector background (5 min) and efficiency factor (dpm/ cpm) 11.
Beta survey instrument background (5 min), efficiency factor (dpm/ cpm), and area: factor
' l 12.
Beta gas-proportional detector background (5 min) and
. l ef ficiency factor (dpm/ cpm).
' l Output:
l 1.
Alpha total activity averaged over 1 m2 with standard Ceviation (dpm/100 cm2) q q
2.
Alpha meximum activity and standard' deviation. (dpm/100 cm2) 3.
Alpha removable activity and standard deviation (dpm/100 cm2)
.j 4.
Beta total activity averaged over 1 m2 with standard deviation (dpm/100 cm2) 5.
Beta maximum activity and standard. deviation (dpm/100 cm2).
6.
Beta removable activity and standard deviation (dpm/100 cm2),
l I
l
s No.:
N704SRR990027 Page:
23 l
The counts observed for the alpha and beta surf ace activity were con-
?
verted to dpm/100 cm~ by:
l i
SA = (C - B) E (100)
(Eq. 1) 5 A
where:
SA = surface activity (this is applied to either the average or maximum activity) 1 C = total count in 5 min l
l 5 = count time, min l
l B = background count in 5 min (generally 0-5 for alpha and-l l
about 440-460 for beta) 1
(
l E - efficiency factor, dpm/ cpm (averages about 4.4 for alpha l
and about 4.3 for beta) j 2
100 = 100 cm standard area A = probe sensitive area (71 cm for Ludlum model 43-1 circular alpha scintillator; 20 c,2 for Ludlum model 44-9 pancake G-M).
i 1
Note that the analysis is done using counts rather than count rates.
The 2
l standard error or deviation of the measurement in dpm/100 cm is given by:
1 1
l I2 32 C
E (100)
(Eq. 2) 5 A
l
...._..._._..__..____m
~
No.:
N704SRR990027-
+
Page:
24 The results of the smears counted by the gas-flow proportional ~ counter for the alpha and beta removable surface activity were converted to i
dpm/100 cm by:
u
\\
SA = (C - B)(E)
(Eq.'3);
5 where the appropriate alpha and beta background and efficiency factos were used.
Backgrounds are typically 0-2-counts for. alpha and 120-150 counts for.
beta in a 5-min time period.
Ef ficiency f actors ~ are about 3.5 for alpha and 3.9 for beta. Theoretical standard deviations were also calculated.
j Sof tware was developed to read the data output f rom the Visicalc file 2
into a graphics utility which plots the activity (dpm/100 cm ).against the.
Gaussian cumulative distribution' function (cdf) on a. probability scale.
For convenience, the distribution function, F(x), is plotted as the abscissa (probability grades), and x, the activity, is plotted as the ordinate (linear grades).
The Gaussian function plotted in the following section takes'on the shape of a straight line due to the orientation of the axes and the nonlinear x-axis.
l C.
DATA ANALYSIS
{
l From the plut of activity vs. cumulative probability, the mean contamina-l tion value of the lot is the value on the ordinate axis where the distribution intersects the 50% cumulative probability.
The figures display the results on l
j an expanded scale so that the variations in the data can be. seen in detail.
The distribution is analyzed in terms of sampling inspection, " inspection by va riables. ". The test is satisfied if the Gaussian. straight line (clearly l
l visible in the figure) passes below the intersection of the upper limit U on the y axis and 93% cumulative probability.
In most cases, however, the upper limit is of f scale on the graphs presented; the area is well below contamina-tion limits.
l 1
l
\\
t l
1 l
,j q
+
.l No.::
N704SRR990027-r Page:
25 The test statistic x + ks is compared to the acceptance limit'U, where:-
i x = average (arithmetic mean' of' measured : values)'
i
's = observed sample standard deviation!
j k = tolerance f actor calculated f rom the number. of samples to-achieve desired sensitivity to the test l
U = acceptance limit.
- The State of California has stated.that the consumer's risk of' acceptance (6) at 10% def ective (LTPD) must be. 0.1.
For these choices of B and LTPD, Kg.= K2 = 1.282.
The number of samples is'n.
Values of kLfor each sample.
size are calculated in accordance with the following equations:
i 2
2+
K - ab K
K 2
(Eq. 4) k=
a = 1 2 (n-1)
D"
~
2_
n:
where k
tolerance factor
=
The normal deviate exceeded with probability of 6, 0.10.
K2
=
(from tables, K = 1.282) 3 The normal deviate exceeded with probability equal to the LTPD,
'i K
=
10% (f rom tables, K = 1.282) n = number of samples The criteria for acceptance are presented as a plan of action.
The plan of action is:
1),
Acceptance:
If the test statistic (x+ks) is less than or equal to the limit (U), accept the region as clean.
(If any single measured value exceeds 80% of the limit, decontaminate that location to as near background as is possible, but do not change the value in the. analysis.)
4
l No,': '
N7045RR990027:
b
.Page: 26
{
2)
Collect additional measurements:' If the test statistic l
(i+ks) is greater than the limit (U), but i itself is less-1 L
than'U, independently resample_and~ combine.all measured i
values-to determine if.x+ks < = U for the combined set; if
,.l so, accept the region as clean.; If not, reject the ragion.
1 3)
Rejectioni If_the. test' statistic -(x+ks) is greater'than.the limit (U) and x > =~U, reject.the region.
q l
In addition'to the formal survey measurements made for computerized data I
reduction,, search and survey techniques were conducted throughout the building.
on special structural features'and components where contamination might have
'~
deposited.
Applicable correction factci's were used to convert the counts
(
2 recorded into meaningful data units (dpm/100 cm ).
If the area being.
l measured.was contaminated to a level which was 80% of the acceptance limit, 1
the result was recorded and the area' decontaminated to ALARA principles.
1 I
No.:
N704SRR990n
2
(
1 Page:
27 j
1 d
V.
SAMPLING INSPECTION A.
COUNTING' STATISTICS j
l The emission.of atomic and nuclear ~ radiation obeys the rules of quantum theory. As a result of this, Lone can only determine the probability that an 4
emission will occur.
If one attempts to measure the number of. particles emit-ted by a radioactive source, that number is not constant in time; it has a -
statistical variation because of the probabilistic nature of the phenomenon under study. The number of particles' emitted. per unit time' is dif f erent for successive units of time.
Therefore, one'can only determine the average ntsm-f ber of particles emitted per unit. time and per unit area.
Because of'tha i
probabilistic nature of particles emitted by radioactive elements,' repeated measurements of the average number of_ emissions per unit time will show a distribution a' approximated by the Gaussian (or normal) probability density function (pdf).
If measurements are made at many similar. locations, these measurements will generally show a'somewhat greater variability, but the i
distribution will remain adequately represented by a Gaussian function.
Thus i
the number of occurrences of particular contamination values, f(x), shows a
~
Gaussian pdf relative to.the contamination value, and the data can be plotted accordingly.
Subsequently, based on the results of.the data analysis, a conclusion can be made regarding the level of residual contamination in the.
I
- building, l
j i
The Gaussian distribution, g(x), is given by:
.]
}
'*'"I, g(x)dx =
exp dx (y 2 )o 2 ;2.
I i
i
4
,y
~
No.:
N7045RR990027'
.Page: ' 28'.
.j
.l where l
I 1
g(x)dx -- probability that the value of x, the measured value, lies.
between x and x & dx
~
m-=
Average or mean 'of the distribution -
2 Variance of the distribution.
a
=
1 A graph of'g(x) vs x gives the following. bell-shaped' curve:
j I
l a{ o.s f
)
- i a
l l
l
)
- I
?
o m~amm+a x a + da a
Figure 6.
The Gaussian Probability Density Function Furthermore, the cumulative distribution function (cdf), G(x), (equal to the I
integral of the pdf, for a continuous random variable) is:
X j
G(X) =
g(x)dx t
P(x <= X)
=
This function is commonly referred to as the error function, (erf). The graph of the Gaussian cdf is:
l l
l
~]
.i
- No.:
N704SRR990027.-
'j
.Page:
-29.'
r
- l ca J
i --- _______ ______
l i:-
1 j as - - - - - - - -,
A t
o xem x
l
~f Figure 7.
The. Gaussian' Cumulative Distribution Function 4
A If x is the. survey measurement '(in the case 'of. radiation' measurements, the number of counts), the standard deviation of the measurement.is the-square root of x.
Background radiatica must also be considered to calculate the net.
number of counts. Thus, the error, or standard deviation associated with-the-measurement, becomes:
1 4
l S=IC
+B (Eq. 5)-
where I
i l
C = The number of counts recorded in time,.T, of the sample
'l B = The number of counts recorded in time, T, of the background radiation
.I environment T = Time of count, assumes the sample count time is equal to the back '
i ground count time.
Finally. corrections must be made for instrumentation parameters including _
l geometry and efficiency.
~ q g,
s No.:
LN704SRR990027 Page:
30
'B.
SAMPLING INSPECTION BY VARIABLES 1
l Acceptance inspection by variable's is' a method 'of judging whether a lot!
l
.of-itens is of acceptable quality by examining:a sample f rom the lot, or popu-lation.
In the case ofsdetermining alpha contaminationLin the;NMDF,.it would j!
be unac':eptably time cnnsuming and'not cost' effective to measure and document'.
)
100% of the building.
However, by applying sampling inspection by v'ariables'
{
methods,, the confidence of the conclusion made about the level of contamina '
tion is not sacrificed due to the decrease. in number of ' sampling ~ locations.
J In acceptance inspection by attributes, the radiation measurementiin aL given area is recorded numerically.'and classified as either being def.ective or nondefective, according-to-egulatory acceptance criteria.
A defect means.an instance of a failure to meet a requirement imposed on a unit with respect to; a single' quality characteristic. Second, a. decision-is made from the number of defective areas in the sample whether the percentage of defective areas in the lot is small enough for the lot to be considered ' acceptable In accept-i ance inspection by variables, the. result is recorded numerically'and is not j
treated simply as a boolean statistic, so fewer areas need to.be inspected for j
a given degree of confidence in judging a lot's acceptability.
l The test statistic, i + ks is' compared to the acceptance limit U, where:
x = average (arithmetic mean of measured values) s = observed sample standard deviation k = tolerance f actor calculated f rom the number of-samples to achieve the desired sensitivity for the test
[
U = acceptance. limit.
l I
4 l
I l
__,__---,,_-u-,-"u--m-\\a~
M
3 No.:
N704S'RR990027 Page:
31 The sample mean, standard deviation, and acceptance limit are easily cal-culable quantities; the value of k, the tolerance factor, bears further dis-cussion.
Of the various criteria for selecting plans for acceptance sampling by variables,' the most appropriate is the method of Lot Tolerance Percent Defective (LTPD), also referred to as the Rejectable Quality Level (RQL).
The LTPD is defined as the poorest quality in an individual lot that should be f
accepted.
Associated with the LTPD is a parameter referred to as consumer's risk (B), the risk of accepting a lot of quality equal to the LTPD. USNRC Regulatory Guide 6.6 states that the value for the consumer's risk should be 0.10.
Conventionally, the value assigned to the LTPD has been 10%. These a priori determinations are consistent with the literature and regulatory posi-tion and are the same values used by the State of California.(2)
- Thus, based on sampling inspection, se are willing to accept the hypothesis that the probability of accepting a lot as not being contaminated which is in fact 10%
defective is 0.10.
The value of k, which is a function of the a priori deter-minations made for B and LTPD is given by Equation 4 in the previous'section.
Figure 8 demonstrates this principle.
The operating characteristics curve of a Gaussian sample distribution shows the principles of consumer's and producer's risk, in addition to LTPD and the acceptable quality level.
The criteria for acceptance of a lot are presented in Section IV.
The coefficients K and K are equal because of the choice for the 2
g values of B and LTPD as 0.10.
Statistics textbooks listed in the reference section (5-7) provide additional explanation of this sampling principle.
The a priori values chosen for the sampling coefficients are consistent with industrial sampling practice :nd regulatory guides.
1 1
i l
I
e i
No. ':
N7045RR990027
(
Page: 32
-l l
. O.h5--, k bPRODUCER,S RISK -
W-i
.U i
z 8
w O.
I W
I O
t W
l i
O i
D 3<
1 GI I
O I
c:
1 ONSUMERh RISK a.
i O.10 - - - + - - - - - - - - -
e i
00 AOL ROL p= LOT FRACTION DEFECTIVE Figure 8.
Operating Characteristics Curve il
,i l
'{l I
.,\\
.l
'l
'n
.Q i
No.:
N704SRR990027' Page:
33'
'i 1
VI.
PROCEDURES!
-l
.The following. procedures were used in performing this survey.:
'( Ref erence supporting document, N7040WP990084,." Final Radiological Survey--Detailed Work' I
Procedure").
A.
CALIBRATION AND INSTRUMENT CHECKS Instrument qualification data sheet's were recorded for cach background.
and source check.
Instruments used'for the final survey'were calibrated and checked a minimum of every morning, noon, and evening for the duration.of the project as follows.
Portable Survey Instruments (Ludium 2220-ESG Scalers):
1 1)
Turn the-instrument 'ON' and allow.to warm up for 5 min..
2)
Check high voltage (700-750 V alpha, 800-950 V-beta).
9 3)
Check threshold (140-190 alpha, 250-350 beta).
4)
Window in/out switch is set to out.
l 5,
check battery (greater than.500).
6)
Set range selector to 1, response to fast, and count time.to
)
5 min.
7)
Take and record a 5-min background count in.an uncontaminated j
area which typifies the area to be surveyed.
l 8)
Take and record a 5-min count of known alpha and beta stand-:
ards; an electroplated Pu-239.and electroplated TcL99 source,
.)
respectively.
The, efficiency factor (dpm/ cpm) is calculated l
as the ratio of 2. times the.2v emission rate of the source.
(dpm) to the net count rate of the instrument.
The radio-s activity of the calibration sources is traceable to NBS.
1
u.
~
_ v.
"n
\\
i
No. :
- N704SRR990027
_Page:
34'
,9)'
, Calculate: the area of the-end' window 'and. record Lvalue..(This is performed only,once' for. each probe type.)..
}
Gas-flow Proo'ortional:
1).
. Equipment is to be -lef t in the 'ON' positionL at all-times.
2)-
- Using uncontaminated' planchets, take four 5-minebackground counts.
3) z Take. and record 5-min counts ? of known alpha. and beta' stand-ards; 2-in.-Pu-239 and Tc-99 sources, respectively.
Calcu--
late efficiency factors'accordingly.
Averace the Daily Results:
Calculate the average background and ef ficiency. factor ^of. each instrument 1for morning'and afternoon.
The morning value should be the average of the 7:00 a.m. and'11:30 a.m. measurements; the.
af ternoon value should be the' average of the-11:30 a.m. and'
- i
'16:00 p.m. measurements.
B.
AVERAGE CONTAMINATION MEASUREMENTS 1)
Identif y 1-m2 area to be measured:
1 m2 per 9 m2 s u rl-I face should be surveyed to be consistent with a' minimum 11%
sampling plan.
~
2)
With portable scalar. instrumentation (L' dlum 2220-ESG) set.
I u
for 5-min count time, usingian alpha probe (Ludlum Model'43-1) on one instrument and a beta probe (Ludium 44-9.)
on another, uniformly scan the area.
(Watch and listen for.
" hot spots" where radioactivity may exceed ^ the average limit.
These are to be resurveyed later.)'
3)
Record the location,' total count,' background. efficiency f actor, area factor., and date/ time.
.h 4)
Enter the data into Visicalc spreadsheet.
]
l
+
.No.5 N7045RR990027 d
'Page: -35 l
C.
MAXIMUM CONTAMINATION MEASUREMENT i
q 1)
Return to any area'. identified.as having a " hot spot."
2)
Repeat the uniform scan of-only th'e _ hot spot area, covering approximately.100 cm2 with the _ probe.
3)
Record the ' location,c total. count, background, ef ficiency
{
f actor,' area factor, date/ time, and maximum contamination if value.
W 4)
Enter the data.into Visicalc spreadsheet.
h 1
D.
REMOVABLE CONTAMINATION MEASUREMENTS a
1)
Using an NPO 2-in.-diam cloth swipe, wipe an."S" pattern,.
'f with legs approximately 6.in. long, soLas to sample' removable-j contamination f rom an area of approximately 100 cm2 within I
the 1-m2 grids identified and sampled with the' survey :
l meters.
l l
2)
Place smear in envelope kit and record the location of the' 1
sample grid on the envelope.
Save until. ready for counting.
)
1 3)
Count radioactivity using gas-flow proportional counter (NMC l
l Model ACS-77) for 5 min.
a 4)
Record the location, total alpha and beta counts, background, and efficiency factors for each.
5)
Enter the data into Visicalc spreadsheet'.
E.
MISCELLANEOUS GAMMA QUALIFICATION INSPECTION l
l l
1)
As necessary, collect various. samples of debris, dirt. and-other material which indicate detectable alpha activity.'
I Because Pu and DU were the-only radioactive materials handled at the f acility, it' ~ s desirable 'to qualify the measurement.
.]
2)
Place the sample in the calibrated high-purity germanium (HPGe) detector and.use the multichannel analyzer to qualify-the radioactive material.
~
I I
________---.___n---
7-----__
j.
]I
'No.:
.N704SRR990027
)
)
s Page:
36
'F.
SURVEYS OF SPECIAL STRUCTURAL FEATURES'AND COMPONENTS
'1 )
Using a 'Ludlum Model 12 count rate meter. in connection' with a
!Ludlum Model.43-5 rectangular alpha scintillation probe, sur-j vey various building features and components which are sus--
pect of containing residual contamination.
j i
2)
Perform an instrument calibration check three times daily -
using the Pu-239 source mentioned above.
3)
Ensure tnat the. transit velocity (in cm/s) does not exceed one-third the numerical value of the detector' window dimen-sion (in cm), in the direction parallel to the motion of the i
probe.
j
-l 4
I q
a j
u
)
i
No.:
N7045RR990027 i
1 Page:
37
)
l VII.
SURVEY RESULTS A.
STATISTICAL RESULTS' i
The survey of the NMDF was conducted using the survey plan previously.
j described.
A summary of the survey results appear below in Tables 1 through 3
]
for each of the inspection lots.
The results used in.the' mathematical statis-tical analysis are shown in' Appendix A.
l l
1 TABLE 1
)
SUMMARY
OF SURVEY RESULTS j
(Office Area and Other Unposted Areas)
Q 2
(dpm/100'cm )
[
Inspection.
1 Number of Average Maximum
-Test Measurement Location Value Value Statistic Limit-l
~
Average alpha 141 2.6 14 8.1 100 Maximum alpha 0
300 Removable alpha 141 0.3 4
2.3
- 20 Average beta 141 54.3 1065 744.2 10000
)
Maximum beta 0
30000-Removable beta 141 5.2 34 19.2 2000 1
l TABLE 2
SUMMARY
OF SURVEY RESULTS (Glovebox Room) 2 (dpm/100 cm )
Inspection l
Humber of Average Maximum Test Measurement Location Value Value Statistic Limit Average alpha 202 7.1 94 23.6 100 Maximum alpha 11 1067 300 Removable alpha 202 0.5
. -11 2.4 20 l
Average beta 202 364.5 1361 1156.8 10000 Maximum beta 0
30000 Remova ae beta 202 5.1 36 20.5 2000 l
No.:
N7045RR990027 Page:
38 TABLE 3
SUMMARY
OF SURVEY RESULTS' (Posted Areas) 2 (dpm/100 cm )
Inspection Number of Average Maximum Test Measurement Location Value Value.
Statistic Limit Average alpha 201 5.7 140 26.7 100-Maximum alpha
-11 10465 300 Removable alpha 201 0.4-15 2.4:
s20 Average beta 201
.183.9 1431 978.6 10000 Maximum beta 9
41664 30000 Removable beta 201 3.4 28
-18.6 2000 Because the number of hot spots discovered were few in number, the aver-age value and inspection' test statistic were not calculated; both values are meaningless. Table 4, however, lists the hot spot-locations and corresponding.
levels of contamination. The hot spots found were smaller in area than the detector end window, thus the reported value is greater by a factor of'1.4 for alpha and 5 for beta such that the measurement result is extrapolated to an 2
area equal to 100 cm,
In all cases where contamination was determined to be 80% of the accept-ance limits, the area was decontaminated to activity levels below the instru-ment detection limit.
From the smears taken during the survey,. no removable.
1 activity was found throughout the building.
i The survey data for each test characteristic are displayed as cumulative distribution functions in Figures 9 through 20.
These figures show each sur -
vey value, arranged in order of magnitude f rom lef t to right, and a straight-line representing the derived Gaussian distribution.
In most cases the acceptance limit is substantially above the top edge of the graph; the graph l
is bounded in the positive y direction by the greatest measurement taken for.
that lot.
The mean of each distribution is that value on the ordinate which.
T(
.y No.:
N7045RR990027:
.Page: :39
-y TABLE 4-MAXIMUM; SURFACE + ACTIVITY
.(Hot Spots)..
2
- (dpm/100 cm )
Location-Alpha Beta Colament 127 E5,14 1239-
-OL Orig.' surveyi' paint sampled 127 E5,13 598 0'
Add'l survey,' paint remo'ved-127.E5,15 1067
_0 Add'1' survey, paint removed.
.t 127 E5,16
- 140 0
. Add'1 survey,l paint' removed'
'127 S1,1 87 0-
. Beam, contamination removed-127 S1,8 102 0
- Beam, contamination removed 1
127-82S10 58.
0
' Beam,-contamination removed 127 B3N6
'79' 0'
' Beam,. contamination.' removed -
127 B3S16
'29 0
Beam,: contamination removed; 127 B4N15 118 0
Beam,-contamination l removed 127 B456.
146
-0 Beam, contamination removed-126 F3,4 10465 1
Cleaned to NDA,' add'l-surveys 130 F7,2-236 2
Cleaned.to' NDA, add '1.'. surveys '-
129 S1,2 0
1230 Cleaned to NDA-VAULT F1,3
'42 0
Cleaned to NDA, add'1 surveys VAULT FS,3 0
41664 Cleaned to NDA, add'1' surveys:
HOLDUP F4,3 92 0_
Surveyed add'1 locations HOLDUP F6,5 191 1826 Surveyed a'dd'1 locations HOLDUP F1,3 23 0
Surveyed, add '1.'. locations -
HOLDUP F4,1 68 1742
. Surveyed-add'1-locations-HOLDUP F4,2 94 1247 Surveyed add'1 locations HOLDUP'F3,3
' 49 -
$33 Surveyed add'1 locations-HOLDUP F3,4-113 882 Surveyed add'l locations.
HOLDUP FS,2 158 1333-Surveyed. add'1 locations-NDA:
No Detectable Activity
?
1
'~
No.:
N704SRR990057 a
Page: 40 s
%e
--e
\\.,.
a=
g ell"F"o g;ys o
C O
Q g %
w t
3
)
- 9.. N.
o a __.
cm i
e-
'7 4
M N
W e
e-*
d
-W 5:C3
\\
C sl:CI i
' )
5:::::
s2 l
an Eas3 llrs*
m cn
=:>
O
-)
l s,*
=ECil:
C
-o e=
I a-w
\\
=:::2 N
i 2!.
- =2 w
9
)
h" I
>=
w CD o
~
g:s ma-4 1
-M
]
gr 3
s 4.'%
o o
$ oc s
b
-- 4
- 3
=*
- ca
- *^
A
- a
.a.
lEC 1
2:
CD I
'C' o
W l
--4 sCl:t 8:LellE:NH CD CD O2:sNI i
1 i
l l
l l
l l
l
'.f' 00
'..i 1
./
X 9
y/,.
9
~
)
. y
~
D w /
E TS p
X
/,/
O P
0 N
9 U
_*/
Y T
A W'
E I
R L
A Ti
/&.
I E
B C
A I
B O
G R
/
(
P Y
/.-
E T
I V
V
/
I I
l
/
T C
A A
L A
U i
/U P
M LA C
E L
x B
.0 A
_7 V
O M
E R
[
x h
1
[
j
[
h Nh 0
{
0 4
hpH/10OCgg
00 1
X
/
9 9
l{
)
D E
y/
TSO o
.f P
NU g-x n/.
0 9
A e.
E R
Y A
T E
I C
F L
I I
F B
O
(
AB Y
O T
R I
V P
I T
A C
E A
V A
i -
/-
I T
T E
A B
e L
f U
E G
M A
U RE C
V
/
0 A
x
//
1
/
/,(*o x
/l
- /
0 0
5 0
6 DpM/1 9CM2 5
9 1
~
1 1
l No.:
N7045RR990027 I
~
Page:
43
)
e
-i j
-l i
x e
a0s
~
~*s.
\\
n
, s.,*,\\
i o*
)
O x
g.
cs3 w
cre W8 i
n.
E--e j
2:'
-M e.
e i
g:g:3 4
O, e
s:ca C>
1 l
u M
i
!w
~
5:8-*
n
~
j N
E=1 o
w w
I o --a m
8 >
E -e D
, H C
3 i-a e
M D
e
=z:
o m
U I <w n'-
l f*.
N d
G.
C53 w
el Ts.s:,
ts e
e o
l b
1 s=
s x
W:n W
~%,
A o
C:A g:: -
E
~2ll:
C53
'C' C
co.
M 8l ll% 8:le ENW G3 C538C )E CN1 H
I
,/
~
0 0
1 X
o 9
9 o
$-/, /
X
)
0 D
,/.
9 E
T S
Y O
T P
I L
M I
/
O B
O A
R B
/
X O
. 08 R
P E
/
. V E
O V
L
- G I
(
T A
YT L
I U
V M
I
. T U
C C
A
. A X
l a
i P
wd L
A E
G A
e R
e, E
V A
X I
o 0
t
/
y 9
DPM/100CN2
r l,
s,
'0 9
1 3
1
/_
x 1
9
'/
9 0
4
=
a <.
.**r
/
D E
0 T
1 9
O
/
S F
P s
T M
_AA L
I OO I
R B
A X
B O
B OR E
VO 1
Y
~
s.-
R L
G
(
I T
I I
V A
L I
T U
C M
A O
A C
H r
P L
s 9
A
.1 E
4 L
B AV
~-
0 y
1 tE
=
R n
f X
d I
M f
~
dM D
9 1
p 0
jpMf1lg'CN2 1_
1 Lei
-_..c, 7_
l
.q Nh: '
N7045RR990027
<<F Page:
46
..i
?
CE3 H
5 B
)
i er.
.l L'
j o
o_
_o
'4
.g cr.:
0; c
m A
t -e Q
=
8 Sai m
a::
M 5
O' l
sc m
ICl-e f
y B
s.e w.
d D
5.
~
w E=""g' S
- ==a
.c :
u.
lC A
llllll3 g
C
'::3 v
>C m-w E
'r"'t w
o N
oO O
y N.
M r
cy d
o
'I
'"C$
4
- E::
'S H
o n
WC211ElLe E N W @ @8CJ E slNB m
M w
I
{!
1
0
/
0 1
. /;
9X i-9
./
~
/,r
,, j
)ae X
t 0
sa 9
e Y
T m
I o
L o
a I
B x
o A
c BO e
v R
o P
c
. 4 i
.E
(
V
~
Tv I
T 1
v A
i L
r c
U
^
M
^
A U
T C
t e
x
. r'8 0
Y 1
a v
~
/
onca 0
o O
d F )
X f
.s I
7 2
0 f
/:
d
.~
n ir
- g, pM/198CM2 9
1, o
9 3
2
~
~
\\
~,
~
~
~
0 0
1 X
o 9
j 9
/
o
./ J X
0 sA 9
)^
Y e
T na I
o L
e I
T B
so B
r s,, P O
o R
n in i
E a
i V
rc I
a T
(
A v
- L 1
_l 1
i v
,M 1
J 1
"C ca r
n i
ie ta tca n
e v
a F
x D
L
~
1 V
FDM N
0 0
,4 4
D P M /.f.0 0 C M 2 1
l
/
00 1
x 9
a 9
o A.:_.
)a tn X
a 0
e 9
rs Y
or T
I oi L
c i
I n
B ia A
n B
r O
a R
c y
P r
a_
E i
w V
I 1
T ca A
W/
L a
U n
M et H
a C
tt X
a 9
av M.
one a
FDL V
FDM N
0 o
]
DPN/1g0CM
0 1
0
'f 9
,o 9
A~**
)n d,
ea X
n 0
o 9
e t
Y s
o T
e
/
I L
a i
r I
1 B
r i
A a
B n
e O
a R
sd P
(
v d
E 1
1 Y
v 1
I 1
T
/
c A
a L
n U
r M
e 8
U C
e Y
ca n
0 e
=
1 v
a
~
~
'e F
L
, ^
D 1
Y F
DM N
o 0
1 2
3 DPMjl08CM2 9
4 0
1 2
00 1
X 9
9
/
)nena n-X 0
o 9
ets Y
o T
r I
o L
n I
in B
i A
a B
nr O
a R
c P
y t
E iv Y
i I
r T
c A
AL a
U re M
s OC e
ts X
av
.l D
o I
s
~
ta
- +
~
F
~
D X
/~
I L
VF DN
(
H 0
7 DPH/199Cg2 2
L
'j c.y y
.g
'No.:n N704SRR9900271 Page:
52 co'rresponds to a'50% cumulati.ve' probability of the'abcissa.
One,-two, and.
three standard deviations above the mean corressionds to 84%,: 97.7%,.and 99.8%
cumulative probability,' respectively.
The'value.of k used in thefinspection' test is' very nearly 1.5' for^ each case; thus, the ik":line'will runtperpendicu-
,lar to the abcissaL corresponding to about a 93.3% cumulative probability.
The:
Gaussian distribution'line'must pass-below the intersection of the "k" line (about 93%) and the horizontal line showing the.' acceptance' limit.at that point.
in order to accept the lot as being-noncontaminated.
For all' survey result:
characteristics,- the test statistic, ~i+ ks, !is well below the acceptance'-
limit, U.
The-results. summarized. in these tables and' graphs confirm that all' areas are acceptable for release for unrestricted.use at.the present time.
Many times, because of the conservative action level we' maintained (80%
of the acceptance level), additional samples were taken. Areas of-increased-sampling are discussed in the following subsection, B.
Additionally various components and special features of the building were qualitatively surveyed to-determine possible contamination problems in areas beyond the 1-m grids' surveyed for statistical analysis.
Concurrent with the final survey, addi-tional decontamination was. performed.
Finally, interesting anomalies were I
identified during the course of the final survey; these occurrences ape described in Subsection E.
1 B.
AREAS OF INCREASED SAMPLING i
y Sampling was increased above 11% in several areas'of the building if-either a square-meter grid was found to be contaminated to values' excaeding-80% of the acceptance limits or if a particular section of the building was known to have experienced a contamination incident. Sampling was increased in two areas of the building which were suspect'of containing residual contamina-tion from contamination incidents: -fourteen additional floor samples were collected near the east wall of the glovebox room where theLglovebox overpres-surization incident took place; five additional floor samples were collected
]
in the vicinity of the location of ~ the vacuum pump,.where a seal leaked oil ~
and released contamination.
The samples collected-above'were r.ot taken as a result of a positive indication of contamination'.
All 19 samples were j
included in the statistical analysis; no detectable activity was found.
)
e
~
N'o. : -
N704SRR990027 Page: 153
'.j i
On the other hand', additional.~ sampling'was performed in six separate.
d clocation due to contamination results exceeding 80% ofJthe acceptance; c riteria '
The additional-action taken upon discbveryLof;the contamination is
. summarized:in Table 5.
j 4-TABLE.5 3
q 1 ADDITIONAL: SAMPLING LOCATIONS-2' 3
-Contamination Level Additionalh 2
Location (dpm/100 cm )
Measurements Results
,c Rm'130.F7,,2 236 alpha max F8,2 F7,1 F6,3-No hottspots-found 0
avg. alpha:= 20-
~
HOLOUP 49 alpha avg.
F4,1 F4,2 F3,3_
Activity f airly. uniform at
~
F6,5 191 alpha max F3,,4 F5,2 about 50 alpha ave. and up
~
to 158 alpha max Rm 12T ES.14 83 alpha avg.
E5,13 ES,15 Contamination determined to 239 alpha max E5,16 ES,9 be localized to the: bottom '
ES,11 E4,11 grid, south ~ of the exi,t door-E4,17 E5,17
.and north of the support 1
E3,15 E4,14 be ar,1.
Area was cleaned.
E3.,13 E2,16 E2,12 E2,13 Rm 126 F3,4 140 alpha avg.
100% survey See Figure 21 for results 10465 alpha max of floor VAULT F1,3 16 alpha avg.
100% survey See Figure 22 for results 42 alpha max
. of flo'or F5,3 41664. beta max Note:
Refer to Appendix B for specific values of contamination.
In all cases, the additional samples collected demonstrate that the con-tamination (most of it below acceptance-criteria) was' fairly localized to the' imediate area.
As mentioned earlier, all areas determined to be contaminated-to a level equal to or exceeding 80% of the acceptance' limit were decontami -
nated to levels below the instrument lower limit of' detection.
The'only grid 1
areas with residual contamination above the acceptance limit were localized' hot spots on the floor of Room 126, on the east wall.of' Room 127, and on the:
floor of the vault.
E L)
Py Me Av Sru
'R s O
Ol b
La 0
Fm b0 r
._bb03
%o
)
2 _
5552b 0f 0
tm_
46530 7,
1e lc_
848 5
u0 _
13
/2 3
h s0 _
- /
2 F
)t e1 _
/ /
a Y
a0/
Rf R/_
m a
00 Oo p
0 g0 5 a T
d _
1k505 At
_ 2b216 Rr
(
Oa Bp A.
n_
Le r
o_
i Se t _
Sw a_
12345 E.
c_
Cn o
Oo L_
Ri Pt
( a 5,
t S
6o F
2n 1
x g
Mi Or Ot Ra m
4, 4, e F
On 1
3 i
F P
S Td Le Uk l
Sr Ea Rm Ys 3,
En 4
Vo F
Ri Ut Sa c
o
.l 1.
N 2d 2,
i Er 4
RG F
U(
G I
F g
1, 3
F
n
,4 No.:
N704SRR99002T
,Page:
55:
.: j l
3
?
t Result-2 F1,1 F1,2 F1,2 -
Location ~
-(dpm/10 0cm ) _
gg 1
42.' alpha
'2
'42" alpha F2,1 3
2250 beta' 4
2025: beta 5
'2250-beta 6
30~ alpha.
F3,1 7
2250 beta h
b 3
9 2025 beta 8
1800 beta'
~
/
10 2025-beta F4,1 j
30 alpha O
?
g F5,1-F6,1.
FIGURE'22.
SURVEY RES$5TS OF THE VAULT 100% FLOOR SURVEY 1
)
-a i
1 No.:
N7045RR990027 l
Page:
56 C.
RESULTS FOR SPECIAL STRUCTURAL FEATURES AND COMPONENTS During the course of the formal finai survey, the surveyors determined special features and components to qualitatively survey with the Ludlum Model 43-5 alpha scintillator in conjunction with the Ludlum Model 12 count rate meter.
G-M probes were not considered appropriate because no beta con-tamination had been detected during the cour:e of the final survey, except for the floor of the vault.
Table 6 summarizes the features surveyed and the results of the survey. NDA is conveniently used to designate areas of No Detectable Activity.
The contamination levd is presented in cpm. The area f actor for a planar surface is about 1.3; however, most of the objects sur-veyed were geometrically disproportionate and only came in contact with about 10% or less of the end window.
The phenomenon creates two problems when try-ing to estimate the amount of activity deposited on the surface in rgy in r e ore t reach he t tr e on t
etry fa or applied as the conversion f actor is grossly approximated based on the surveyor's judgment.
Thus, we use the concept of a qualitative survey; if we l
observe more than 5 or 6 cpm on the instrument, we conclude that contamination exists on the object, but most likely below acceptance limits.
The efficiency' factor of the instrument is about 7 for Pu-239 alpha particles.
All contami-nated objects are cleaned and resurveyed.
All findings are reported before further decontamination was performed.
Of the various components and features surveyed, only three major areas were found as containing observable contamination levels:
the fire extin-guisher mount on the east wall of Room 127, the unpainted tops of the sprink-ler pipes in Room 127, and the beams..in Room 127.
Remaining identifiable contaminated areas were cleaned and resurveyed to ensure a complete decontami-nation of the premises.
t.
.. =
~
o,,
l g
n
' No'.':
N704SRR990027
,.Page:
57
~
4 1
. TABLE-6
.l
SUMMARY
OF.VARIOUS EQUIPMENT AND FEATURES SURVEYED FOR CONTAMINATION j
.(Sheetal of 3)
-j q
Alpha.
H 1
Contamination
- l Level l Location
( c pm).'
]
The of fice area which includes Rooms '101,102,s 103,104,..
j 105,1106,107,.108,109,110,111, ' 112,114,116. f ront l
hall, and security. Surveyed tops'of. doors, door handles',
1 corners of, rooms, parts of the: baseboards / floor,'.and electrical outlets..
NDA' 102 - 2 (ea) 1-in. x 8-in. ' x 24.-in. boards NDA
]
1 104 - ledges of plastic' partitions, telephone service 1
panel, closet, entry and exit passageways NDA i
1 108 - wood cover mounted on west wall NDA-109 - sink, floor-area of sink, cleaning' supply shelves, top and under hot water heater-NDA 111 - sink, shelf, floor drain NDA-112 "I" beam on west wall-NDA 116 - two doors and.100% baseboard survey N DA..
Front Hall - ledges, door f acings, electrical panels NDA 128 - top, bottom sides of miscellaneous equipment, electrical control panels, meters, water pump, valves, holes in walls, cracks in' floor, ducting, tubing, removed section of fiberglass from inside of a/cexhaustductfor;gammaspectroscopy NDA 132 - horizontal surf aces; of' EDG, top'of batteries and.
i pipes, fire extinguisher bracket, junction boxes, door threshold NDA.
133 - holes in wall, conduit seals, top of transformer i
housings, fire alarm boxes, switch boxes, door and threshold, top of buss units NDA-A/C
. spot checked floor; walls; ce'ing; top, bottom, and sides of a/c equipment; a1r intake; door NDA~
a
S
- f
. c i
y
+
ig.
"No.:#'N7045RR990027 L
- Page:
58; TABLE 6'
SUMMARY
OF VARIOUS EQUIPMENT.AND FEATURES SURVEYED:FORJCONTAMINATIONi
.1 (Sheet 2-of 3)'
[ Alpha _
' l Contamination 2 R
Level i
Location.
(cpm))
- j 117 - totel and
- soap dispensers', plumbin'gistools. s'nks,.
j i
trash can, miscellaneous floor and wall locations
.NDA 118 - instrument ' shelves, magnahelic unit, electrical:..
out1'ets, plumbing, entry to shower,.100% -baseboard
-NDA.
l 119 - overhead pipes,'a/c supply duct, metal-plate.on'
'y l
floor,100% baseboard. survey NDA
.j 120 - door and door kickplate, electrical outlet, 100%-
baseboard survey NDA q
121, 122, 123, 124 - 100% baseboard survey, various. floor -
.1 I
and wall locations, electrical control box NDA:
126 - overhead pipes, beams, electrical conduit and j
junction box, a/c inlet,100% baseboard -survey
.NDA 1
BH - electrical panel, fire alarm box, fire extinguisher j
rack,100% baseboard survey NDA' I
MEZRM - pipe, edge of beam, top of a/c. ducting NDA
?
130 - light fixtures, all upper horizontal surfaces, l
beams, pipes, top of doors to high bay, floor cracks, thresholds, door handles,100% baseboard.
NDA-survey
(
I i
129 - facility exhaust stack, louvers to blowers NDA t'i louvers to outside 10-30 l
L threshold, inside pipe to roof, cutouts in north wall, 100% baseboard survey-NDA
^
Vault - east wall south port 40 ledge above door, round port above door, north square port and round ports,.100% baseboard NDA 4
__._.a_-a
.--._L A
1 g
1 No.:
-N7045RR990027:
o Paget 59 3
- TABLE 6 1
SUMMARY
OF VARIOUS EQUIPMENT AND FEATURES SURVEYED FOR CONTAMINATION 1
(Sheet.3:of_3)-
-]
.. Alpha Contamination Level
,j
- Location,
- (cpm);
ExitE - entrance door threshold
-4
. exit door threshold 4
porch 10-12 door jamb
- 6 ExitW - horizontal-surf aces, door window' ledges, handles,-
1
' top of sprinkler, thresholds NDA J
HOLDUP - top of rails, ladder rungs,' bottom of gauge rack, drain sump in pit, wall studs in pit-NDA 127 - beams 2, 3, and 4 (numbered from the north wall)'
20-30 top of fire extinguishers, exit door locks 8
I top of vault door 20 i
i east wall fire extinguisher mounting board 6
L baseboard on east wall at meter 14 60 baseboard on east wall:at meter 15 21 baseboard on west wall, meter 10-16 7'
Concurrent with the final survey, all flooring in the posted area was removed, the fire extinguishers and the mounts located'in the glovebox room were removed, the fire protection sprinkler system in the gloveboxLroom was removed, the beams in the glovebox room were scrubbed, lights. were. removed from Room 130, paint was removed from the east wall of the glovebox room, and 3
the east emergency exit door was scrubbed.
All ventilation components sur-i 1
veyed during the decontaminationLeffort were found to be clean. 'In addition, j
the stack plenum is clean.
A 1
During periods of rain, water samples were collected' f rom around the building and analyzed for Am-241 in a gamma spectrometer.
The soil around the' l
removed drain lines was analyzed'previously and found to be well-below release -
criteria of' 25 pCi/g of Pu.I9) All water samples contain no Am-241.
i r
.i l
d
f No.:
N704SRR990027 Page:- 60
-l 1
1 D.
ANOMALIES j
.4 a
This section briefly describes the natural radiological phenomenon and I
miscellaneous. limitations which have impacted the data reduction.and analysis methods used in the final survey.
l l
'i Because the range of alpha particles is so short, the instrument bac'k-
{
ground for detecting the presence 'of alpha particles is typically very low, on the order of no more than 2 counts per minute.
However, under certain.
]
atmospheric conditions (i.e., when a building is locked tight = for the night),
j radon tends to build up within the building.
During the final survey, an
]
increase in natural alpha background was observed in the ' morning for'a period i
of a couple of hours, until the building could be opened up and allowed to air out.
The activity tended to collect more towards the ceiling of the glovebox room.
Furthermore, the " natural" background. of. alpha radiation will be increased by natural activity, such as Th-232 in shower tile located -in Room 119.
During the survey, we noticed a substantial increase in the. alpha count rate when placed directly over the shower tile.
A tile sample was taken i
and analyzed in a gamma spectrometer.
The results showed conclusively the presence of Ac-228, a daughter of Th-232.
The tile was not removed, and the data was not used in the analysis, i
In the case of the outside intake louvers on.the exhaust stack, an increase in activity was observed.
This phenomenon is to be expected due to the large flow rates of bypass achieved through the damper assembly.
Insofar as the distribution of low-level alpha activity is present on this equipment, we can only conclude that it is due to the natural environmental radioactivity.
A few difficulties in the survey were experienced.
The entrance ways to Rooms 128,132, and 133 are standard 7.5-f t doors, and the man-lift could not be moved into these rooms.
The ceilings in each of these rooms is 16 ft.
The.
top two meters and the ceilings were not surveyed in these rooms.
Because these areas were unposted and since no radioactivity was found, it is. felt that this omission did not significantly affect the results of the analysis.
s
.No.:i N704SRR990027 Page:
61 In regard.to the hot spct problems observed on the east wall'of'the glovebox.
room, paint samples were taken and. analyzed on a gamma spectrometer to. deter-mine the amount.of Ani-241 in the sample.
Several additional surveys.were per '
~
formed lin the ' area to determine the extent of the contamination and whether.
the first or second-coat of. paint _'was contaminated.
Evidently,'the:glovebox room was painted.in ' about~ 1974; after the glovebox overpressurization inci-dent.
The. paint condition at the present:is veryLspotty due to excessive-peeling f rom the concrete sweating phenomenon; in l many ' place's there is no.
paint, one coat, and two coats.
Consequently,:the entire area was' surveyed (approximately 16 m ) and ' detectable activity exceeding 80%. of the acceptance criteria was removed.
.I 1
)
4 l
i l
i
e 1
.No.:
N7045RR990027-Page:
62 VIII.
CONCLUSIONS j
J l
An' appropriate survey.has been conduc'ted;throughout the area-to be released. Although a'few localized hot spots Were detected. the results of.
1 i
this survey show statistically that no residual' contamination remains in'the I
area and demonstrate a negligible risk of there being any. undetected;eontami '
i nation exceeding the acceptance limits.
With the concurrence of the U.'S.
Nuclear Regulatory Commission,- the facility license will be. voluntarily termi--
. i nated and the area will be released for unrestricted use.
.j l
q 1
J l
I l
j q
- i l
i l
____u.
.J
l- [i u.f i q
No.'i N704SRR990027' Page:.;63-REFERENCES'-
i
- 1.. " Guidelines fore Decontamination-of ~ Facilities and: Equipment Prior -to
' Release for: Unrestricted l Use or: Termination of Licenses forf 8yproduct,'
n Source, or Special Nuclear ' Material,"' Annex 8, LUSNRC-License SNM-21,'-
Docket 70-25, issued to Energy: Systems..' Group: of RockwellL International,-
/,
last revision June 5,1984.
.y
- 2.
" State of-CalNornia Guidelines; for-' Decontaminating: Facilitiestand:
?
Equipment Prior. to ' Release ' for ' Unrestricted Use," DECON-1,. : revised
'l March '24,11983.
J 3.
" Draft American ' National. Standard. Control ~ of Radioactive : Surface :
Contamination -on Materials, Equipment, Land FacilitiesL.to be' Released for '
4 Uncontrolled Use," ANSI.N13.12,. August 1978, American Nacional Standards.
. Institute, Inc.
4.
" Building 055 -Decontamination and. Deactivation Plan,"' N704TI990061, J.' W. Carroll, F. C. Schrag,L and ' V. A. Swanson, Rockwell International.
j October 1,1982.
1
- )
5.
" Selected Techniques' of Statistical Analysis,". Statistical Research 1
Group, Columbia University,'McGraw-Hill Book Co., Inc., 1947.
6.
"Some Theory of Sampling," W. E. Deming, Dover Publications ~,: Inc., New l
York, 1950.
)
7.
" Statistics in. Research,"
- 8. Ostle and R. Mensing,. The ' Iowa State ~
University Press, 1979.
J 8.
" Measurement and Detection of Radiation,"- N. Tsoulfanidis.. Hemisphere Publishing Corp., Washington, D.C.. 1983.
9.
" Radiation Survey for Release' for Unrestricted Use -- L-85,"
N001SRR140087. F. E. 8egley, Rockwell International, March 6,1986.
- ]
10.
" Plutonium Concentrations in Soil Around Drain ' Lines ' 'at NMDF,"
N704SRR9900124 R. J. Tuttle, Rockwell International, April.3,1986.
11.
" Final, Radiological Survey Detailed-Work Procedure," N7040WP990084, V. A. Swanson, Rockwell International, September 22, 1982.-
i
'0195Y/bes i
- .-__~_-_-
No.:
N704SRR990027 Page:
64
)
APPENDIX A SAMPLING' INSPECTION DATA GROUPED BY LOT l
J The inspection data was entered into. Visicalc, a spreadsheet program-which runs on the IBM PC.
The output of the Visicalc program'gives the data
-]
.which follows in three-lots:
one for-the lot located in the unposted areas' d
(office area, Rooms 128, 132. 133, Security, and the air condition'ing room)';.-
)
one' for the glovebox room; and one for the remaining posted areas in addition.
to the liquid waste holdup platform located outside the building.
f i
The grid locations are identified ' in matrix. notation by room;-
measurements were made on the floor (F), ceiling (C), north wall (N), east wall (E), south wall (S), and west wall (W).
The beams in the glovebox room (127) were surveyed, identified by (B) (beam number) (south or north) (grid
.i location), for example 81S9.
A few of the room number identifiers bear further explanation:
FH
- front hall (unposted),
4 SEC
- security' building; j
4 A/C
- air conditioning room located above Room 126.
Accessible only from outside; VAULT - storage vault adjacent to the glovebox room; BH
- back hall, connecting Rooms 120, 121, 122,.123, 124, 126, and 127; i
MEZRM - a small room accessible from the mezzanine; j
EXITW - the west emergency exit from the glovebox room; j
EXITE - the east emergency exit from the glovebox room; HOLDUP - The liquid ' waste holdup tanks cement slab located outside of the building.
The output shows the alpha and beta total average contamination per square meter, maximum in one square meter, and removable in one square meter; 1
the standard deviations of the measurement are also calculated.
L
+
/
'4.
+
+
+
f
+
- ~
)
L o
+
24363527660521 265551 90C235943O82328 l
+
M1 - - 2 1 - 1 1
- - - - 1 1
1 1 1 2 1
+
E f
i
+
R g
+
a P
+
++
. +
/
s + 2+
a
+
er+M a
C A0X d T0A e E1 M ts B/
o
.M p + P 232006921 600860579708426653835281 3
'n
+ D -
1 4344422433432433322334333332223254333
+
/ 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+
+
. +
rh +
t o ++
2572352205660781 8979096454465271 5753 T75943677831 1 1 081 220681 79379567626832 d +
O6 65531 6 251 29 - 231 3 581 22322351 - 0323 n +
T
~
_~
1 a +
~
+
a e+
1 21 221 1 1 1 21 21 22221 21 21 1 1 221 1 21 1 222 2 r+
a +
/
e ++
+
c+
if +
1 21 221 1 1 1 21 21 1 1 221 21 21 1 1 f +
M-
' 231 2' 3 221 1 2Ol o+
E
+
R e+
ht ++
f +
o+
/
+2+
+
s t
+H l
uAC s
H0X eR P0A L1 M A/
n M
o+P 32554321 235435342OO4331 c +
/
3433223O33353243 i
+D t
e +
+
p +
sn ++
64452941 4541 846O4OO2661 633441 I
1 O31 '
+
T 43 1
g +
O 1 -
- - 1 n+
T i
+
lp+
m i
DE 32 M 2 3,2 2 5 3 2,1 2,2,1,2,4 2 1,2,1 4 3,4 1,441 2,2 4
,2,2,2 2, S
I 1 1 RA
,32 GN1 51 21 322332222221 21 31 1 231 2222GG21 32 FFCNESWFFCNEWFFCNESWFFFFCCNESSNWFFCN R1 1 1 1 1 1 1 E00000000000000000G00000000000000000000002222223 MB1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 OM OU RN
+
+
~
+
- 9280764661 n
+
M1 - -
1 1 -
- i321 5320O6i45861 5 4 5' O1 1 255 2 2
1 1 1 1 1 -
2 I 1 Q
+
E
- 2 s
+
.R
~
+
- g
+
a p
+
+
4
+
/
+
+
f
+2-o
+H 2
C A0X Le T0A g
E1 M a
P B/
" M
~
- 476028960336836
+P 0921 53931 355970033973281 :
.J
,1
+D - 33432433423324332222431 2343332233322
+
/ 1 1 1 1 1 1 1 1 1 1 111 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1
+
+
^
1 1
1
+
+
L 1
- ~
+
23524290623441 2641 8841 31 3332'0552'6875
+
T93721 059530 30977645231 458585068746856
+
O 241 2562334 38 33349264 - 7 22 435: 221 -
+
T
- - - ~
+
+
221
+
1 1 21 1 1 21 1 1 1 1 1
+
' 1 2221 1 1 1 1 l 1'
+
/
1 '
1 1 1 1 1 1 1 1 1 1
+
+
O' i
+
+
. 331 11 01 1
+
1 1 31 1 131 1 33301 01 01 1 1
+
M-
~ -
11 1 11 1 1 l 1
+
E A
+
R E
L
+
B
+
A
+
T
+
/
++2+
+H AC H0X P0A L1 M A/
M
+P 1 341 2331 423433231 332221
~
=
+
/
433343342421 224 1
+D
+
+
++
+
1 1 51 1 051 31 331
+
T -
1 3
041 1 O0l 001 320O6209O321' 1
+
O T
+
+
g DE M 4 2,1 41 2,3 2,2,3,2 1 I
2,3,3,2,1 1 21 1
, 2, 2,1 3,3,3,2,1, 3,1 1
RA 3
, 3,, 2 3, GN1 22331 3231 1 1 21 322221 22232231 1 1 1 1 t FCNESWFFCNESWFFCNESWFCEWFFCNESWFFCNES 1 1 3 H
R66666677777778888888999901 '
. 222222 1 1 1 11 E0000000000000000000000001 NB1 1 1 1 1 11 1 1 1 11 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 11 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 OM OU RN cl' Lt
+
+
L w
s 1
+
692000B442134508867372209I 0838021 55552
- g
+
N 1
1 - 1 1 1 1 1 1 -
1
' 1 1 1 - 1
- 1 1 1 - 1 1 -
1 1
a
+
E
~ -
f
+
~
p
+
R L
1
+
4
+
o
+
+
/
+2+
3
+
g
+M e
1 a
' C P
A0X T0A E1 H B/
M
~
s
+P 8001 94802681 86421 043054221 5303787631
+D
- 1 222321 22233232222222222244442332244
'+
/ 1 1 1 1 1 1 1 1 11 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+
1 1
1 ~
-_1 1
1 1_1
+
+
J'
+
i
~
+
6377793822' 68391 21 902244201 766730489'- 6
+
T64656831 38233521 63362943503323071 41 0
+
O544371 543 72-30334224901 1798644422873
+
T - - - -
+
. - - - - 1 1 1 1
+
+
1 1 1 1 1 21 1 1 1 11 1 1 21 1 1 1 1 1 1 1 1 1 1 -
n
+
/
1
. - ' i 11 1,1 2 1 1 21.l
+
~
+
+
+
+
+
~
+
010O121 O1 O11 1 1 21 001 1 1 01 Ol 1 13O03O1 1
+
N
,1 1 1 1
+
E-A
+
R E
+
L
+
B
+
A
+
T
+
/
+
+
+2
+M AC H0X P0A N
L1 M A/
+P 33434322233424533:333333355544344.4433 2
+ D -
^
+
/
1 1
+
+
+
+
1
~
+
471 60721 24402524425451 4O217922221 0121
+
T 1
1 1
1
+
T 1
+
O
+
+
~ '
DE 0
2
- 3 2 3,3' I M1 21 2,1, 3,1,21, 9,1, 9,1,9 3,1 4 2,1, 3, 3,1 5,5,4,2,2,2 1
,2,4 2 RA
,41 1 1 GN321 21 1 1 33221 71 7223322251 41 481 44353133 NESWFCNESWFFFCCNNESSWFFFFFFFFNESWWFFN R
R4444666666
~
888888888222222
.E1 1 1 11 1 1 1 1 1 MB1 1 1 1 1 1 11 1 1 222222222333333 OM CCCC 1 1 1 1 1 1 11 RN HHHHHHHHHHHEEEE
- 1 1 1 1 OU FFFFFFFFFFFSSSS I
k
s
+
~
+
+
+
~
a
+
' 22759705661 499521 31 g
a
+
M1 1 ~
1 331.-
1 1 - -
p
+
E-4
+
I
+
R O
+
fo
+
0
+
5 4
+
/
1 I
+ - +
e
+2 ga
+ M P
C 5
A0X 8
T0A 0
E1 M 1
B/
M
+ o 764051 33236341 3451 7
+ D - 3334422222233433334
+
/ 1 1 1 1 1 1 1 1 1 1
+
+
1 1 1 1 1 1 1 1 1
+
+
+
1 336463237202849923
+
T 4 0 7 2 1._ 401 835651 9472 1
+
O442605444421 25 1 - 9
+
T 1
+
++
O21 21 1 O1 O1 O1 1 1 1 1 1 1 1
+
+
/
+
+
+
+
+
O4331 2O1 O1 O1 1 01 1 1 1 0 1
+
M
+
E A
t G
E
+
L
+
B
+
6 A
+
T
+
/
+
+
+2
+M AC 5
H0X 1
P0A L1 M A/
M
+P 4344444234334454545
+D
+
/
+
+
+
+
+
31 468554331 0649021 4
+
T
+
O
+
T
++
f DE M63,41, 3,1,6 2,5,1, 5,1,6 2,3,2,3 2 4 I
RA GN3452S45345444565621
- SWWFFNNEE5SWWFFCCSW f
R2223333333333 E3333333333333 HB1 1 1 1 1 1 1 1 1 1 1 1 1 OM OU CCCCCC
//////
RN AAAAAA
s
+
+
a
+
g a
+
1 0
p
+
0325232245202820289540729002'1 41 595
+
M3 1
1
- - - 21 2-
- - 3
- 1 1 - - -
1 1 S
+
E
+
R fo
+
+
+
1
+
a
+
/
g a
+
+
P
+2 T0A
+MC A0X E1 M B/
M m
+P 6044068682268697062833434292964320 o
+D 23333233254444454434444333222222243 1
o
+'
/1 1 1 1 11 1 1 1 1 11 1 1 1 1 1 1 1 1 1 R
+
+
1 1 1 1 1 1 1 1 1 1 1 1 1 1
+
+
xo B
+
5968541 9304596687093447' 00946748' 9762
+
T3820689 9700781 763656521 51 1 5031 878 e
+
O41 1 1 31 4
- - 0473646631 455434 1 1 233 v
+
T l
- - ~ -
o 1
+
t G
+
+
1 1 1 1 I 1 1 1 1 O1 O1 O1 O1 1 1 1 1 2OO21 21 160GO 1 1 1 h
+
/
e
+
+
+
f
+
o
+
+
21 1 1 O1 1 1 1 O1 O1 O1 O1 1 11 7' 1, 1 OO 0 3 O.O 6 1 2
1 1 1 s
+
M t
+
E
~
A lu
+
R E s
+
L e
+
B R
+
8 1
2 A
+
T n 1
1 1
o
+
/
+2+
+
i tc
+M e
AC p
s H0X 9
7 2
n P0A 3
8 0
I L1 M 2
1 A/
g M
n
+P 4445556645553644444651 4464S34333534 i
+D l
1 p
+
/
m
+
+
a S
+++
1 44443025647O651 456503569441 404274
+
T 1 1 1 22 1 '
1 1 1 B 1
1 -
+
+
O u
+
T
+
DE 347 057937 0495 038 26 1
M 3 5,3,6 9,1
, 5, 7,1
,2 2,3,1
,2,1 5,8 1 I
1 1 11 1 1 1 1 1 1 1 1 3,7 1 RA 1
GN1 24531 35223231 21 233n454Si21 32354S4 NNNNNNNNNEEEEEEEEEEEEEEESSSSSSSSSSW 2
E2222222222222222222222222222222222222222R777 1
MB1 F
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D
OM M
OU N
RN
+
+
+
g 1 : -
~
- 0:01 - '
4 L'
~
~
+
J
+
71 B397 223442556372 1 1 2
e
+
E
- - - - - 1 : 9626241 7O272591 72 1
2 1
- s
+
N 1 1 1
1 1
1 1 - - 1 1 1
1 2
+
R ap
+
s i
+
5
+
+
f
+
/
o
+2+
+;
2
+H e
C g
A0X a
P T0A
~
E1 M B/.N 1
' ~ ~
~
1 1
L
. - '0707
+P 673460723957008038201 3 1' 1 052321 1
+D 333233333333221 44344444443444444343
+
/ 1 1 1 1 1 1 1 1 1 11 1 1 11 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+
+
1 1
+
+
3 1
l872
+
55301 337319253355926960934738952'
+
T05030245247801 023644750731 443074933
+
O6641 626360782230281 0021 0071 21 1 0070820
+
T 1
- - - 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+
+
)
+
1 O1 OO1. O11O1
.111
+
O21 1 1 1 1 1 1 1 l' 21 1
~
1 1 1 1 1 1 1 1
1
+
/
+
+
+
+
1
+
1 0O1 OO1 011O1 O4301 - O1 O 1' 211 1 1 1 1 1 1 1
1 2
+
M
.O1 1 F
E A
'+
R E
+
L
+
B
+
AT
+
+
/
+
+
+2
+M AC H0X P0A L1 M 4/
N
+P 434443334544444554544454444544554543
+D 1
+
/
+
+
+
+
+
22541 201 481 01 041 85955O94551
+
O 835963051.
+
T 1
1
+
T
+
+
047 DE946 51 79 2 3 9 2,5,9,1 6,
I M1
- 046 1 1 1 RA 2 2 3,8,1,2 2 2,2,5,9 2,5,9,1, 5, 7,1 247,1 1 1 1 1
,2021 1 03453557 GN333554541 21 321 34S64457987O81 1 1 1 1 1 1 1 WWWWWWWWWFFFCCCFFFFFFF' FFFFFFFFFFFFF L
R777777777777777777777777777777777777 E222222222222222222222222222222222222 MB1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 OM OU
~
RN E
i!
,i
+
_~
.~
+
- ~ ~
~ -
7
+
2230942479'6461 3 9 4 5 2 3 0 7 9 7'4 3 2 7 9 5 5 4 8 8 5 6
+
M1 1 1 - -
1 -
1 21 -
2
~
1' 1
1
+
E. _ = -
~
+
R
+
+
+
+
+./
s
+ :
+2+.
eg a
+H p
C' -
A0X
.5 T0A
.f E1 M o
D/
- M 5347921'1 1 295084 3
+P 1 31 905631 21 2 0 5 9 0 0'0 0 9 0 3' -
?
1
+D - 44434434444444344443444443344444233324_
eg
+
/ 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 P
+
. 'c 1 1 1'1 1 1 1 1 1 1
a
+
+
+
~
' ~
1 c2
+
8' 7421 1 846933447032369381 8861 508035906
~
+
T5983964409506029757622842301 1 89-60935
+
O01 09937888897077777908099579867
+
T1 1 1
- 1 1 4 -
+
. 1
- 1 ~
1 -
L
+
z
. O01 1O1 1 1 O1 01 O1 O1 1
+
I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+
+
/
+
+
+
~
+
L
+
1 1 1 1 1 01 O1 1 1 11 01 1 1 01 1 1 O02101 1 1O1 O1 01 2
+
M
+
E
..+R A
+
+
E
+
L
+
B A
+
/
T
+
+
a
+2
+H AC H0X P0A L1 M A/
M
+P 4464454666456554656554665655505' 34334
~
+D -
+
/
f
+
+
+
+
55545O43536450965450967696994O' 71'1 O51
+
+
T 1
21 2 1 1 1 1 1 1 1 11 1
1
+
O
+
T
+
+
t
. 038 246 139
. - 237,
7 047
~
D E 9,1 5
1 11 1 1 11 1 1
- - 0
, 2,, 8,1 6,6,6,6,9,1 2, 4 8, t
,5,9,1 1 1 1 I M
,1 9323453433576756090089 5,7' RA86781 091 1 1 1
GN1 1 1 1 221 22122222222222222232332245644 FFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFCCCCC R777777777777777777777777777777777777 E2222222222222222222222222222222222222 MB1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1111 1 1 11 1 1 1 1 1 OM OU RN
~
L
1)]
)1!i!ii)1
- $L Ed2EU8Ey
.I Y
- 2$"
e" s
~
~
~
+
22232222322232322223222222333233333333323
+
1 1 11 1 1 1 1 1 1 1 1 1'l 1 1 1 1 1 1 11111 1 1111 1111 1 11 1 111
+
/
+
+
+
+
+
71 84339O271 5667371 15429265069O1 6497244223
+
M 1
- - 1 1 1 -
1 - 1 1, 1 1 11 1
2 s
+
E e
+
R g
+
a
+
p
+
5
+
+
/
f
+ 2+
o
+
4
+ MC e
A0X g
T0A 0
a E1 M P
D/
M
+ P 57828797 01 0546232367563420' 476352364395554-
+ D 22232333444333333333333333333333322222222
+
/1 1 1 1 1 1 1 1 1 11 1 1 11 1 11 1 11 1 11 1 11 1 1 1 1111 11 1 1 1 1 1
+
+
+
+
38299443595862740459604234141 05200264951' 5
+
T1 1 6 51 92383133041 4 5354702804441 491681 669-
+
O432 242421 2 - -
21 41 1 - 23 1
1 - 21 244 - 3333
+
T-
- - - - ~
++
OOO1 1 1 1 1 1 21 1 121 O1 1 1 11 1 11 1 1 1 1 1 111 1 l' 11 11 1
+
1 1
+
+
/
+
+
+
+
+
1 1 OOO1 01 1 1 1 1 1 001 OO1O00111 O011 1O001 1O11 1 1O
+
M 2
+
E g
+
R A
+
E
+
L
+
B
+
A
+
/
T
+2+
+
+M AC H0X P0A L1 M A/
M
+P 33334453444465443443345334554434333333433
+D-
+
/
+
+
+
+
+
554571 0741 61 1 8401 2221580057725020024111 01
+
T
- - - - - 1
~ - - -
+
O
+
T
+
+
047 257 038 246 39.
237 1
D E 3 9 2 5,9,1 6,8,1 1 1 3,5,9,1 1 2,5,8 1 6 9,1 12,4811 1 1 1 1
11 1 1
115
,,,,,9 I M1 1 RA,,2021 03453557686781 091 1
9323433576756090 1
GN8B1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 221 221 222222222222323 CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC
^
R77777777777777777777777777777777777777777_
E22222222222222222222222222222222222222222 MB1 1 11 1 1 1 1 1 11 1 1 1 11 1 1 1 1 1 1 1 1 1 1 11 1 1 111 1 1 1 1 1 1 11 OM OU RN l
+
+
+
+
i' '
m.
+
54339629739991 2650761 92O6002513301 : -
1
+
M 1 -
1 - 21 2 - 2 1 1 21
- 2
- - 3. 5
+
E
+
R 4, -
+
+
s
+
2
+
g
+
/
ap
+
+
+ 2 5
+ M
~
t C
~
f A0X o
T0A 5
E1 M B/
e M
. ~
g
~67698771 8201 291 901 1 96081 78771 783409
+ P a
P
+ D 2221 1 1 1 21 22443434443343432334334443
+
/ 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+
1 11 1 1 1 1 1 11-
+
+
+
98940' 79551 371 52478978932
+
41 8481 51 741
+
T93425221 84673487307483021 2699641 338
+
O2224455342301 90901 097091 81
+
T - - - - - - ~ - - - - 1 1 1
1 1 1 1 '
1 6654478547648
+
+
~
O l' 001 1 221 131 1 1
+
1 1 1 1OO1 1 O21 O1 O1 1 1 O1 1 1 1
+
1
+
/
+
+
+
+
+
- 01 01 OO1 1 O51 O2O1 1 1 O21 3' 41 1 1 'I l' 2
+
M
- D.0 1 l 1 O:
1
+
E
- - - 1 2
+
R A
+
+
E
+
91 734 763 L
+
1 1 1 B
231 A-
+
/
T
+
+
+2
+M AC 89986 870 H0X 5721 4
_964 P0A 1 1 L1 M 501.
A/
1 M
s
+P 33447546676233343444343341 064532446
+D
+
/
1 1
+
+
+
+
~
+
01 4482728942774961 91 62541 4335441 0600
+
T 21 21 22 1
1
- 1 1 1 1
e
- 1 21 n"02'
+
O
+
T
+
+
047 63881 53571575E
- ~
DE1 1 1
- 0 65 1
3 5' 6' 1 1 1 1 1 1 1 1 1 11 1 1
,1
,1 7754362 I M
,9731 61 1 6
,1 1 1 1 1 1 1 1 1 1 RA089NSNSNSNS 355677901 23467
,, 9,1 GH3221 1 2233441 1 1 1 1 1 1 22222225Q355445343:22 CCCB0DB0BBBFFFFFFFFF_FFFFFEEEEEEEEEEE
~
.F
~
f R7777777777777777777' 77777'777777777777
.i E222222222222222222222222222222222222 MB1 1 1 1 1 1 1 1 OM
- 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 OU
~
RN 1
!r'
!(
+
p
+C +
m 4
+
~
+
1 c -
- =.
f 5~
+
'9 3 0 5'6 5 1 84741 5371 4897'959791 5 3'0 1 28
.f
+
M-21 1 -
1 1
- 1? - - 1 t
o
+
E i
l
+
R
+
~
i:
+'
~
e g
+
a'
+.-
P
- +' /
mo
+I2 i+ x o
+
R
+H C
A0XT x
xo B
T0A'
_E1 M
~
oB/
e v
n M 7
f 7
~
) ' ~
5 1
+ P' 1 962808421 355775356400235751453891 3 3 l
G_
'+D 42931 22224331 2234322344322332322332222
+
/ 1 1 '
1 1 1 1 1 1 e
+
+
'- 1 1 1 1 1 1 1 1 11 1 1 1 1 1 11 111 11 h
+
l 1 11 t
+
~
1 r
+
- 79265' 2' 31 9261 9520351 43401 4985861 836 o
+
T25923946727368741 01 41 2488831 1 451 551 f
+
O7- 01 751 3471 381 1 38323 671 21 531 51 1 822
+
T -
2 s~
t
+
pe
+
- - ~
1 c
+
'l OO1 O01 OO00O1 Ol 1 0O1 1 1
x
+
OO1
- ~
E
+
/
O1 1 1 211 1 1 1 1
+
+
ae
+
r +
A
+
1 OO1 O01 3
+
M OO00O1 O1 1 0O1 1 OO1 I 01 1
d
- - - 2O1 1 O 1 1
+
E t
+
R
_A e
E s
+
2 L
o
+
B P
A
~
+
+
T e
h
+
/
~
t
+
t
+2' f
+ H' o
A C'X H0 s
t P0A L1 M l
u A/
se ' M R
+P 33333333333233333333433343323321 23
+D -
n
+
/
o
+
+
i t
+
c +
. =
1' 2 e
+
4.4 1 1 130O644342I p
+
T 1
04O2OO0146O5521 1
s
+
G
~ -
L n
+
T I
+
g +
n DE 1
i l
M 3 3,3,3,1,25,1 2,2,2,2,3 1 3,1 4441 2,1 2,2,3,2,2 2 2,5 3,5,2 2, I
p m
RA 3
a GN1 31 31 2331 32223321 1 33221 1 31 3321 3355 S
FFCCNESSWFFCNESWFCNESWFCNSFCNESWFCN
~
~
_ - ~
12222 R77777777788888889999990000111 1
1 1 y
E1 1 1 1 1 1 1_1 1 1 1 1 1 1 1 1 1 1 1 1 11 2222222222222222 f
MB1 1 1 1 1 1 1 1 1 1 1 1_1 1 1 1 1 1 1 1 1 1 1 1 11 1 11 d
OM~
~
- 1 11 1 1 1 m
OU
- 1
~
n RN
- ~.
s
~
^
u_
0 7
+ e +.
1
+
11.
s
+
e
+
g 53O4446' 2200998838284' 76955771 52071 a
M ~
.E
' 2 12
- 1 1
.2 1 1 1 1 - -
2-p
+
M
- 1 1
+
E
[/
5
+
R
+
f_,
8 f
~
+
o
+
8
.i 2
+
+
/
+ :
s 3
e
+2+
ga P
+N N
C s
2 hOX N
0 TOA
~
^~*
3 FiM 2
F/
- N 3
+P-8834433?2084333943507829521 975489'49 a
h'D 22222223442222223222234334433222222 1
/ 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 11 1 1 1 r
+
~ ^
~
111 1 1 1 11 1 1 1 t'
+. -
1 n~.,. '
t ;T
+
440025451 551 7850948341 2024361 321$07
+
T881 6061 591 1 06362431 1 - 45506641 0898731
+
O 21 22269831 -
+
244 T 1 1 - 920821 091 f23-
. 1 1 1' 1 1 1
/:
+
L
^^
+'
_7 21 1 1 1 1 4
,, f ;, ++,/
- 1 1 1 1 1 1 1 1 1 1 1 0O11 1 1 1 1i 1 1 1 1 '1 1 1I
+
s 1
+
+
+
3
+
.M
,c 22OO1 -
+
2O1 1 1 1 O 1' O.1 1 w* E; 1 1 1 1
1 1 1 1 l 1
- O1110OO21 s
~1 1
?
+
E
_J
+
R L
+
. e L
+
, e a
3'.
B
+
?v.
,~
4 R
+
T 1
+
/
1
+
wHM2+
e nG P0A AC cH0X 5
? ~
6 4
L1 M
+
0 A/
~
~
1 1
2 322232244433333343233435333335434453
+R
+6
~M^/
- 1 1 ~ '.
~
y ++ ~' +
-c g+
021 21 6071 0 2 O' 1 1
+
T 1
~ 1021 0440001 202631O59O 1
+
O 41 1
1
+
T
+
.S-
- f A.,, +
s~
C CE M 2,1,4 5,i 4 3,3,5,3,3,5,3,2,4 3 5 3,1,5,3,1 4 4,7,2,7,5,9,1:. 7,2,5,9 I
,4
,GN521 1 31 21 451 45232S2324331 344S631 3 4 S 6' CCNESSWFFFCCCNNEESWWWFFFFFFFFCCCCCCN
.s
~
R3333333444444444444446666666666' 666666 E222222222222222222222222222222222222 MD1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 11 1 1 1 1 1 ON OU RN 1
n a.
4 5
m
}.
c l-t
.i
+
+
1 J
+
33629267034061 55921 20594l O69" 71 66643 i
+
M1 1
- - 1 2 1i 1 1
s
+
E -
- - = 1 i
' 2 -
1 L
. f e
+
R g
p
+
+
a
+
1 5
+
8 5
f 1
3
+
/
4
+ - +
o
+2 3
+H C
e A0X 0
4 g
3 6
T0A a
2 6
P E1 M 1
B/
1 4
N
. T 1
+P 3336451 1 021 21 29009230701 90367556544
+D
- 255555533333332332333222344222222443
+
/
1 1
+
+
1 1 1 1 1 1 1 1 11 1 1 1 11 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1
~ - - -. -
1
_1 1
+
J -
+
- =
1 1
~
6022774751 07402' 5532854690965031
+
1 1 47
+
T91 787292471 392530595238309763349220 O36576743323223444422436644633443499
+
+
T -
l
+
2 t
+
+
1 1
+
- 1 1 1 1 1 1 1 1 1 1 1 l 1 1 1 1 21 1 1 1 1 1
O O
+
/
- 1 l 1 1 1 1 1 1 1
+
+
+
+
+
01 1 01 1 1 1 1 101 1 l'
1 1 1 1 1 I 1 11 1 1 O1 1 1 1,1 11 O 3
+
N
+
E A
+
R E
+
L
+
B
+
A
+
8 T
+
/
++2+
+H AC H0X 2
P0A 4
L1 M A/M
+ P 353454444344433233232554334, 33~43345l
+ D-l
+
/
4
+
+
+
. 4 7 2 6' 42522462464%:
+
201 71 6721 1 1 21 75466951
+
T - 1 1
1 1 1
'1
~
+
O
+
T
++
DE 1,5
,5 2
' 2 3' 1
0 1
M 9,2,4 1 3,0 0,2,4 1 3,0 0,2 5,4 3,5,8 1 7,1,2,5,3,2 4,8,1 7,1 3,3 I
1 1
RA GN51 3S81 1 1 35O1
,~
2351 21 3S4551 3S231 2451 S1 1
WFFFFFFCCCCCCNNNEEEEEEEESSSWWWWWWFF
~
E R099999999999999999999999999999999E ;
E322222222222222222222222222222222 TTT MB1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 11 11 1 1 11 OM LLL OU
' UUU RN AAA VVV r
[
+
+
+
5541 E
T
+
5' 62I 222709O2909' 2598'5604941 339
+
1
+
.M 1 1 - - 1
- 1 1 1
.. c 1
2-1 -
1 1 1 -
+
E-
+
+
R
+
+
7
+
4
+
/
s
+ -
1
+2+
ega
+M p
C 1
5 A0X 2
T0A 1
f E1 M 1
o B/
4
. M 1
+P 655550648280421 5991 5380078835560761 e
+D - 33332322221 222231 4443332222222322422222 1
g
+
/ 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 11 1 1 1 1
+
1
- 1 1 11-t 1 1 1 1 1 1 1 1 a
+
+
P
+
1
+
20633791 32761 6871 471 87523676' s
1 1 41 207
+
T1 526248438874846732248983681 5890651 1
O87771
+
+
T 41 '
1 - 21
- 1 722708433544436532231 1
+
2
+
+
1 1 1 1 1 1 1 1 1 11 1 1 1 1 O1 1 21
- - 1 1 1 1 11 1
+
/
22O1:
1 2 O I'
1
+
+
+
+
+
+
1 1 01 1 1 1 1 1 01 01 1 0011 3
+
N-
- - - 31 23O221 1 1 3O1
- 11121 A
+
E
+
R E
+
L 6
B 4
AT
+
7 1
+
/
++2+
+H AC H0X 6
P0A 32 L1 M A/
M
+P 44454435344445354445534435333434444
+D
+
/
+
+
+
+
+
531 633364053391 35317201 454220342211 1
+
T
- 1 1
+
O
+
T
+
i - *
+
1 41 3,7 1,2,2,2 2,1 3,2,2 3, 2 2,21 DE 1
1 -
1
- 2,1 -
1 I M1
, 2, 2,1,2,2 1 1
1
,2
', 3, 6 7,1, 2, 8,1 RA GN1 O321 B3323321 1
331 571 1 571 2431 21 542 1
1 FFFFCCCCNNNEESWFCSFFFFCCCCNNEEEEEES
~
J E
00000000000000000000 R
MB NMM3333333333333333333
.RRR1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 OM ZZZ OUHHHHHHHHHHHHHHHEEE RNBBBBBBBBBBBDDBBMMN
1-
~
2
+
+
7 1
se
+
63661 35581 O 2 4_7 9_269157285l0858174422 g
+
M-p
+
R 1 1 -
1 1 2
- - 1
- - 1 2
- - i 1 L
- 1 ;
1 F
a
+
E
+
5
+
f
+
'~
5
_8 1
o
+
6 5
+
/
1 1
5
?
+. +
7
+2 e
g
+M a
C?
6 2
P A0X 8
7 2
a 4
T0A E1 M 1
11 B/ -
M
. ^
l f -
+P 985699767661 05621 74893351 0978411 539967
+D 334322223343333332555555541 33444454444
+
/ 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 11 11 1 1 1 1 1 1 1 1 1 1 1
+
+
2
(
1 s
+
+
' 424257851 802948
~
~
+
642200545421 91 9223451
+
T90608501 471 251 94908391 60606241 501 41 91 1
+
O5593 - - 1 2430 1 1 34901 98465975841 1 80
+
T
- 1 1 1 1 1
-;: 1 1 1 1
+
+
- ' ~
+
OOOO1
~
~
. 1
+
OO1 O1 O1 1 O1 1 1 1 1 l l 1 1 21 1:
1 3O2O1 1 1
+
/
+
+
+
+
f
+
OO0Ol O O.1 O2O11 O1 1 1 21 1 1
+
N tO2Ol11504O1 11 01 4 3.
+
E
- 1 A
+
R E
+
L
+
B
+
1 6 6
0 A
+
11 1
T
+
/
+
+
+2
+M AC 21 3
8 H0X 99 2
L1 M
,6 P0A 1
A/.N
+P 4454533344434334347' 9844953235463479980 L
+D
- 1
- ~
+
/
1
+
+
+
+
+
581 81 41 35841 51 24233964521
+
T 1
1 354 51 : 02275308 1
1 1 2
+
T 2.
J
+
O
+
+
DE'
~
2, 2' 1 3,2 2,1 3,6 1 2,5,5 5,1 3,5,1 2,5,t 3,5,2,1 2, 3,1 I M241 1 1 1
RA,,.,,
f GN1 31 1 1 3221 31 1 22331 224634i1633B76564433S NWFCNEESWWFCNEESWWFFFNESFFWWFFFFFFFF
.~
R PPPPPPP 000 P
ETTEEEEEEEEWWWWWWWWUUUUUUUEEE333 U
MBLLTTTTTTTTTTTTTTTTDDDDDDDTTT1 DD 1 1 OMUUI I I I II I II I I I I I I I LLLLLLLII I LL OUAAXXXXXXXXXXXXXXXXOOOOOOOXXX HHOO RNVVEEEEEEEEEEEEEEEEHHHHHHHEEE BBHHH
~ -
)
.i GUIDELINES FOR DECONTAMINATION OF. FACILITIES AND EQUIPMENT-PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE,,
')
i i
i U.S. Nuclear Regulatory Commission Division of Industrial and Medical Nuclear Safety
' Washington', DC 20555 q
I August 1987 1
1 g
l f f A 1
_ :__:_Q
The instructions in this guide, in conjunction 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 abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different.
The release of such facilities or items from regulatory control is considered on a case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
4 2.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.
l 3.
The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork.
Surfaces of premises, equipment, or scrap which are likely to be contaminated 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 request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified.
This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests must:
a.
Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.
b.
Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
o l
1 5.
Prior to release of premises for unrestricted use, the licensee shall 4
make a comprehensive radiation survey which establishes that contamination-is within the limits specified in. Table 1.'
A copy of the survey' report.
shall be filed with the Division of Industrial and. Medical Nuclear. Safety.
U. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the' Administrator of the NRC Regional Office having jurisdiction. The report-i should be filed at least 30 days prior to the planned date of abandonment.
4 The-survey report shall:
a.
Identify the premises.
l
)
b.
Show that reasonable effort has been made to eliminate residual contamination.
c.
Describe the scope of the survey and general procedures followed.
9 d.
State the findings of the survey in units specified in the j
instruction.
Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
i
'a i
i j
nn r
md a
ie e
rue 2
2 m
t m v
orc d
f m
m m
cu a
t u e
c c
a er rsd e
e g
rt e
ene c
0 2
0 rs h
ti r xf m
0 a
on t
l eo b
0 2m c'
1 t
ci i ee E
1 L
/
c
/
e ftb tr B
a 0
y b
ye a
a oe A
0 0
s bh e
yid nt V
m 0
1 d
t r
rrl e
O p
1
/
m n
d a
'd pu d m M
d
/
m p
a eh oo li E
m p
d nt e
hrh ut R
0 p
d ii c
t ps on 0
d 0
a mw a
i p he 0
0 h
r f
was sc 0,
0 0
0 p
ed r
l 1
2 2
1 l
t e u
ane se a
et s
eav rr da r
e ea r
i s
ahl t u o
sc s
t tq f
ao e
tit is s
l awn m
d l s h
e er e
aa f.
t en e
h i
o pi ap s
rs git m
i er s
nwr ms l
t o t
i e
am b
at c
pep ga a
mc e
ih r
t a
j wte ag s
ef b
h ti
?.
v o
ynt el i c b o bl 2
s ti r
i 2
m t
cr o
dld mm m
c i
at F
eae o
S c
m oe nin r7 L
0 i
i m iri f
mem n
E 0
2 0
l d o 1
ae r
rt r ga V
f 0
2 m
E 1
m c
/
e rg e
eae nh L
d
/
c y
h t
t mt it a
0 s
t yd e
e e
t N
b 0
0 bn m
ded l e m
O M
m 0
1 a
v ur I
U p
1
/
p s
n e
eis so T
M d
/
m d
t o,
r bti em y
a c~
r A
I m
p s
i N
X 0
p d
0 i
sc u
daa t.
A 0
d 0
x sn q
l oe no I
e i e s
uir on 0
0, M
M 0,
mi oda i
0 0
A 1
T 5
0 0
5 s
ec 1
2 h a th m
sre ag N
1 3
3 1
e i
E O
d ff n
c c
nu of a
af a i o L
C i
B l
e h
0 eof mr A
E c
e t
0 r
r ah T
C u
t,
1 at u tt A
n ad e
ns n
F rn r
n eu od R
g u
o a
cos ce U
n eo m
h ams r
S i
h r t
f ae eu t
t g r
r l
cs E
t k
e e
ue aa L
i.
sc v
r shf f e B
n na o
o t o rm A
e ab m
f u
T e
d ogs
- s. y, P
a mr t
nt E
m o
g o 2 ic hl C
2 2
m
)f a
n mse t e iv C
m m
a e
r csj A
c c
g t r e
f ebd wi 2
uo v
o 0soe t
f 0
2 m
0 a
nt a
0s p
dc 0
m c
0 t
i c a
1 ani ee c
1 c
1 e
me e
e ew t p
/
0
/
b t
b r
rd as b
a 0
0 y
re
~a enne ie E
0 1
s d
ed t
paob cr 1
/
n p
o n
i G
m o
A p
/
m m
a e
n a
l
,td s,
R d
m p
p st aeal sm E
p d
d na d
o i rnu ac V
0 d
a oi l
t r ui o A
0 0
0 h
i r u
esmh s1 0
0 0
p t p o
s t sas 0,
0 0
0 l
ao ht e
aet -
let 5
1 1
5 a
rr sc i
mrne va gp e
l poc e
h y ep tj p
e ca l r t'
t a nb p
ve f
h 9*.
n ao a
it er n/
1 n in n
t al u od e
sa ih l
crbs ia yd mc e
aea t r i
bn dy au v
od ve am s
s e
(b t s e
ioor i
8 6
e u
np n
l d mmi d0 2
2 d no oe md oh a
et a
2 1
i ae id pe cc n
rgrn r1 s
lh nd t n d v a
o n
e dt a
I ct an ai r
ee i ein md nc R,
u t a n
',e g
t l
yee un nrn iy es ar a
bl hh ma au
,1 3
02
( eo0 ml l b ro n
a pW t
,d i
o 629 93 h p9 ap b o ef i
vp xm 8r 2 - 2 2
st s -.
t p a
v m
oa
.d ac 3 p 2a1 r-ro re na t e ad a
m n
m 2
- P -
SU e
rS v o
t e
t e,ya I
- y a
I t so o
cd su f v n
rrc d
Ua R,
t e tb l
in oi o
eny nt r a
c 8,
24 id npa eu hi r
c f pel aae S
,e
,25 32 mooe co t m se oail b
E 5d s22 223 emicd ah td m
pca err D
3 c
1
- - 3 sxe f s nr n
u t
in gh o i
2d ih -
ha1 ayset r
ie ee m
ntf o a/s ai o
us p
mb i unfi rdb mcm) l
- e nT1 TR -
n se d
e x
oeet eaa C
Ut a
,1 aeen d
es rd a
mb r
vr U
a r.,
u07 t3,
gd os ei st ul m
arno a m.l N
.i t c s32 a21 air rl un s u owp a
ao n22 n23 ahh se ee u
ao e
esoo e2t
= eg ep e rg1 tt gsh hr 2o bR R rhh: snrD hLe