ML20206F948
| ML20206F948 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 03/19/1986 |
| From: | Malody C SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | Thomas R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20205S034 | List: |
| References | |
| NUDOCS 8606250037 | |
| Download: ML20206F948 (5) | |
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[0D ERON NUCLEAR COMPANY INC.
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gngiogoy,mx no.nicauwo.WAONS2 fAarch 19, 1986 8F EEGim;;,1.';p i
Mr. Robert Thomas Office of Inspection and Enforcement a
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U.S. Nuclear Regulatory Commission, Region V 1450 Maria Lane, Suite 2iG Wninut Creek, CA 94596 License No. SNM-1227 Docket No. 70-1257 Dcar Mr. Thomas:
The purpose of this letter is to transmit additional survey data with I
respect to the release from plutonium status of Room 173 in the Specialty Fuels Facility at Exxon Nuclear's Fuel Fabrication Facility at Richland, Washington.
We were notified by E. Deming of Ook Ridge Associated Universities that one point scraping from the floor of Room 173 did contain a minor amount of plutonium alpha.
She also identified the location in Room 173 from where the sample was obtained.
The location was very near that where other minor amounts of contamination were discovered during their confirmatory survey.
Although the amounts of contamination under discussion are small, she recommended removing the point from that immediate section of floor as a precautionary measure.
She did state that all other survey results were within release limits.
As a result of the above discussions, point has been removed from on area of approximately 2.3 m2 which encompasses the crea of concern. The area was then surveyed for both fixed and removable contamination.
Details of that effort and survey results are attached. The maximum survey results were fixed 69 d/m and removable 13 d/m. These results are gross alpha and not plutonium alpha.
In light of the fact that the gross alpha are within release limits listed in Annex C, there appeared no need to proceed further.
If you have further questions, please call.
Sincerely, 8606250037 860409 PDR ADOCK 07001257 C. W. Malody, Manager C
PDR Corporate Licensing
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ERON NU(_ EAR a^d.non raOTECriON RECOnos COMPANY,INC.
RADIATION SURVEY REPORT DATE SURVEY LOG NQ.
LOCATION TIME 12:00 3-17-86 007 BLOG.
S.F.
Room 173 10:00 TO Survey of area on floor near east double door exit after paint was DESCRIPTION OF JOB removed from an area measuring 47 inches by 76 inches square. Survey was made for both fixed and removeable contamination.
METE R DE F L-SOURCE BETA CAMMA M E UT ROfs DIRECA SM E A f3$
ME ASUREMENT WO WC SIZC mredeA r.
mR/hr.
mecmAr. c/m or[d/rrh/m orp/m)
ITEM OR LOCATION E
69 13
- 1. Maximum contamination f3und 100 cm c
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9 SURVEY INSTRUMENT (S) USED - 1.D. NUMBER (PIN OR SERIAU RES,fpATORY PROTECTION REQUIRED P
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SNOOPY SUPPLIED AIR FILTER NONE y
LAB COUNTER 17 550.330THER EGM PERSONNEL OOSE RATES WHOLE BODY PEN.
WHOLE BODY SKIN EXTREMETIES PH ASE OF WORK N O.
mrtm/hr.
mecm/hr.
mrcm/hr.
See attached sheets for detail of area surveyed and grid survey results.
CouuENTS Areas A,B,and D on map are areas where paint had been removed previously fcr hot spots on floor. I believe areafC}as area survey team removed paint for lab analy-sis. Due to nattern of previous naint removed. I decided to remove all naint within an area whose sides were 1 foot from outer edne of orevious areas where nai1t had ACTION TAKEN been removed. Total area with naint removed 2.3 so. meters.
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MAX. COfif4ECTED DOSE R ATE ftE
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M AX. UNCOHHECTED MEASUREMENT W
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RADIATIONSURVEYREI(T#007 Continued Page 2(
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Area A about 4" by 4" Area 8 about 2" by 5" EeT l
9 Area C about 5" by 5" Area D about 6" by 5" East door is 8'3" wide, line for door goes off top of page i
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RADIATI0ft SURVEY REPORT # 007 Continued Page 3 or 3 3-17-86 All numbers in c/m unless noted elsewhere.
All open numbers are direct' readings, all circled numbers are removeabic readings l
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Background of counter = 2 c/m j
Efficiency of counter = 30.9 % of 4pi 2
Area of detector
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I C/M - Bkgd C/M X 3.2 x 1.3 = D/M per 100cm for direct reading 2
C/M - Bkgd C/M X 3.2
= D/M for smears (smears taken of at least 100 cm area) l 1
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w Prepared by o*$ Ridge Associated CONFIRMATORY SURVEY Universities l
Prepared for OF THE U.S. Nuclear Regulatory commission s SPECIALTY FUELS BUILDING Region V Office Supported by EXXON NUCLEAR COMPANY Safeguards and l'a'n's". "'
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RICHLAND, WASHINGTON Division of Inspection Programs; Office of E. J. DEMING Inspection and
- -Snforcement U
Radiological Site Assessment Program Manpower Education, Research, and Training Division DRAFT REPORT APRll 1986 l
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DRAFT t
CONFIRMATORY SURVEY O
OF THE SPECIALTY FUELS BUILDING I
EXXON NUCLEAR COMPANY i
RICHLAND, WASHINGTON j
Prepared by E. J. DEMING Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities-4 Oak Ridge, Tennessee 37831-0117 l
Proj ect Staff J.D. Berger F.T. Lange R.D. Condra M.J. Laudeman D.A. Gibson G.L. Murphy l,
C.F. Weaver 7
j Prepared for
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Safeguards and Materials Programs Branch i
Division of Inspection Programs Office of Inspection and Enforcement l
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U.S. Nuclear Regulatory Commission-l Region V Office co
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i DRAFT REPORT j
April 1986 i
4 l
This report is based on work performed under Interagency Agreement DOE l
No. 40-816-83 NRC Fin. No. A-9076-3 between the U.S.
Nuclear Regulatory i
Commission and the U.S.
Department of Energy.
Oak Ridge Associated Universities performs complementary work under contract number
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DE-AC05-760R00033 with the U.S. Department of Energy.
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This draf t report has not been given full review and patent clearance, and the dissemination of its information is only for official use.
No release to the O
nustie swa11
- e made witweet the a,Frev 1 ef the Office er information.
j Services, Oak Ridge Associated Universities.
i 4
DRAFT l
TABLE OF CONTENTS O
tan List of Figures 11 List of Tables iii
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i 1
Introduction and Site History Site Description 1
Survey Procedures 2
Results 4
Comparison of Results with Guidelines 5
Summary 6
i References 33 Appendices Appendix A:
Major Sampling and Analytical Equipment O
Appendix B: Measurement and Analytical Procedures Appendix C: Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source or Special Nuclear Material i
i O
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DRAFT 1
tB LIST OF FIGURES 1
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Figure 1:
Plan View of Exxon Nuclear Co., Inc., Richland,
j Washington, Indicating Survey Locations in the Retention Tank Drain 8
i Figure 2:
Plan View of the Specialty Fuels Building 9
Figure 3:
Plan view of Mixed Oxide Room (Room 173) Indicating Grid System Established for Survey Reference and Grid i
Blocks Selected for Survey 10 Figure 4:
Location of Measurements for Total and Removable l
Contaminations on Upper Walls of Room 173 11 Figure 5:
Location of Measurements for Total and Removable Contamination on Ceiling of Room 173 12 Figure 6:
Location of Measurements for Total and Removable l
Contamination on Floor, Walls, and Ceiling of
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Room 155 13 l
Figure 7:
Location of Measurements for Total and Removable Contamination on Floor, Walls, and Ceiling of Room 156 14 l
Figure 8:
Location of Measurements for Total and Removable i
Contamination on Floor, Walls, and Ceiling of Room 158 15 Figure 9:
Location of Measurements for Total and Removable Centanination on Floor, Walls, and Ceiling of i
Room 158A 16
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Figure 10:
Location of Measurements for Total and Removable
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Contamination--liFr Shower of Room 166A.
17 Figure 11:
Locations of Paint and Caulking Material Samples 18 Figure 12:
Locations of Residual Contamination Identified h
by Surface Alpha Scans.
19 i
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DRAFT l
LIST OF TABLES O
I fage Table 1:
Summary of Surf ace Contamination Measurements Room 173 (Floor) 20 l
Table 2:
Summary of Surf ace Contamination Measurements Room 173 (Lower Walls) 21 Table 3:
Summary of Surface Contamination Measurements Room 173 (Upper Walls) 22 l
Table 4:
Summary of Surface Contamination Measurements Room 173 (Ceiling) 23 Table 5:
Summary of Surface Contamination Measurements Room 155 24 i
Table 6:
Summary of Surf ace Contamination Measurements Room 156 25 Table 7:
Summary of Surf ace Contamination Measurements Room 158 (Airlock) 26 l
Table 8:
Summary of Surface Contamination Measurements Room 158A (Airlock) 27 Table 9:
Summary of Surface Contamination Measurements Room 166A (Shower) 28 Table 10:
Summary of Surface Contamination Measurements on Ventilation Systems in Miscellaneous Samples 29 i
Table 11:
Summary of Contamination Measurements in Drain Systems 30 Table 13:
Results of Plutonium Analysis on Smear Samples 31 j
Table 14:
Heasurements of Plutonium in Plant and Caulking Material From Room 173 32 O
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DRAFT CONFIRMATORY SURVEY i
0F THE SPECIALTY FUELS BUILDING EXXON NUCLEAR COMPANY RICHLAND, WASHINGTON
)
INTRODUCTION AND SITE HISTORY l
The Exxon Nuclear Company in Richland, Washington manufactured mixed (uranium and plutonium) oxide reactor fuel elements in room 173 of the Specialty Fuels Building during the early 1970's.
The manuf acturing process was discontinued in 1975 and equipment was placed in storage.
In 1985 the equipment was cleaned of gross contamination and removed for disposal.
Materials trom the equipment decontamination process are contained in S5-gallon drums, currently stored in an area known as the Vault (room 157).
Surfaces in room 173 and adjacent rooms 155, 156, 158, and 158A were cleaned and surveyed by Exxon Nuclear.
The results of the survey are presented in a report to the Nuclear Regulatory Commission's (NRC) Division of Fuel Cycle and l
Material Safety.I Exxon plans to -. continue using these areas for uranium operations but requested release from the plutonium licensing status.
At the request of the NRC Division of Fuel Cycle and Material Safety and j
the Region V Office of Inspection and Enforcement, the Radiological Site Assessment Program of Oak Ridge Associated Universities (ORAU), Oak Ridge, Tennessee, conducted a
confirmatory radiological survey during l
February 6-12, 1986.
This report describes the findings of that survey.
i SITE DESCRIPTION The Exxon Nuclear Company, Inc., plant is located, on Horn Rapids Road approximately 2 km north of Richland, Washington.
The portion of the site, which is of concern, is located on the western edge of the property, within the Specialty Fuels Building (refer to Figure 1).
Fuel element production was performed in room 173 of this building (Figure 2).
Plutonium packages were received and stored in room 157, where they were surveyed before being transferred to room 173 for processing. Therefore, materials were transported through rooms 155, 156, and the airlocks (rooms 158 and 158A).
In addition to 1
DRAFT these areas, a decontamination shower in the health physics room 166A also had a potential for plutonium contamination.
2 Room 173 has a floor area of about 175 m and a ceiling height of about 8 m.
Although process exhaust ductwork has been removed, a small capped duct from the former glovebox area enclosure known as the " greenhouse" extends through the upper wall near the northwest corner.
A section of ductwork, downstream of the previous HEPA filters also remains in the adjacent room (174).
Four return air floor vents and their damper controls and three floor drains are located in the floor of room 173.
2 Rooms 155, 156, 158, and 158A are much smaller (5-15 m floor area) than room 173. These rooms have no exhaust ductwork or drains.
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SURVEY PROCEDURES O
Objective The survey objective was to verify the licensee's survey findings by measuring surface contamination levels and comparing the results with the appropriate NRC guidelines.
Procedures Gridding An alphanumeric one meter grid system was established on the floor and lower walls in room 173 (Figure 3).
The grid origin was in the southwest corner with the west wall forming the 'O' line and the south wall forming the
'A' line. Measurements on the upper walls and ceiling were referenced to the floor grid.
Because of their small area, rooms 155, 156, 158, 158A and 166A were not gridded.
O 2
DRAFT Measurement of Total and Removable Contamination i O Alpha Scans were performed on floors and lower walls using ZnS alpha detectors and ratemeters with audible indicators.
Locations of elevated direct radiation were noted for further investigation.
2 Using a random number selection program (Minitab ),
10% (35) of the grid blocks on the floor and lower wall of room 173 were selected for surface contamination measurements.
In each grid block surveyed, direct measurements of alpha and beta-gamma contamination levels were systematically performed at the center and four equidistant points, midway between the center and block corners.
Smears for removable algha and beta contamination were performed at that location in each grid block, where the highest direct level was obtained.
Total and removable contamination levels were also measured at 35 locations on the upper walls and re111ngs of room 173 (refer to Figures 4 and 5).
i Fourteen locations (floors, walls, and ceilings) were selected for measurement of total and removable contamination within room 155 (Figure 6),
1 i
and an additional fourteen locations were selected in room 156 (Figure 7).
I Measurements and smears were performed at eighteen locations in rooms 158 and
- 158A, (Figures 8
and 9) and at seven locations in the room 166A decontamination shower (Figure 10).
Direct measurements and/or smears were
}
also obtained from locations identified by the surface scans, inside ductwork, f rom ventilation controls and anchor bolt holes in the floor of room 173, and 1
from floor drains and access points in the retention tank drain system (Figure 1).
Additional Sampling 2
Paint samples were collected from 100 cm areas at six locations on the i
floor of room 173 using commercial paint stripper.
Two of these locetions were in the grid blocks where scans had, identified residual contamination.
A sample of caulking material was also obtained from a floor crack in room 173.
Locations of these samples are indicated on Figure !!.
l 3
DRAFT RESULTS O
Alpha Surface Scan 1
Surface scans identified three small locations of elevated alpha-contamination on the floor of room 173.
These were in grid blocks Al and GIS (Figure 12).
This GIS block was in an area that had been used for waste handling and packaging during decontamination of the facility.
The licensee i
cleaned these spots and resurvey indicated that cleaning had removed the 2
contamination to less than 40 alpha and 590 beta-gamma dps/100 cm.
Scanning also identified residual contamination on four of the eight filter holder i
frames in the return air ventilation ducts in room 173.
The licensee removed these frames from the facility.
No additional areas were identified by the l
surface scans.
1 Contamination Measurements Building Surfaces i O Results of total and removable contamination measurements on building
)'
floors, walls, and ceilings are presented in Tables 1-9.
The maximum alpha i
measurement was 200 dpm/100 cm, on the grill work of the door between rooms 2
2 155 and 156.
The highest beta-gamma measurement was 7120 dpm/100 cm on the upper west wall of room 173.
It should be noted that beta-gamma levels were generally elevated throughout the facility, due to uranium handling operations in an adjacent room.
The maximum removable alpha and beta contamination 2
2 j
levels were 21 dpm/100 cm and 9 dpm/100 cm, respectively.
The highest alpha 1
contamination level was obtainad on the east wall of the shower (Room 166A);
the highest beta was on the floor of room 155.
l Ventilation System Measurements
}
}
Results of contamination measurements on ventilation ductwork and j
associated items are presented in Table 10.
The highest total alpha measurement was 89 dpm/100 cm2 in the exhaust ductwork, located in room
}
174.
The high volume of air passing through the " greenhouse" duct, discouraged direct measurement inside that system.
Direct measurements were i
4 l
DRAFT not performed inside the floor vents, because of the negative findings of the
)
surface scans.
Removable alpha contamination of 660 dpm/100 cm was found 2
inside the " greenhouse" duct.
The highest removable beta contamination level 2
was 9 dpm/100 cm.
(The smear from the " greenhouse" duct was not analyzed for beta contamination).
Drain System Contamination Measurements Table 11 summarizes the measurements performed in room 173 floor drains and the retention tank access points.
The floor drains had a maximum total 2
contamination level of 47 dpm/100 cm and maximum removable icvel of 2
3 dpm/100 cm.
Removable alpha contamination in the three retention tank 2
drain access ports were 3,140, and 750 dpm/100 cm,
Other Measurement Results 2
Paint samples from 100 cm areas on the floor of room 173 contained up to 373 dpm of plutonium (see Table 12). The highest level was in the sample from V
grid block G15.
Grid block G14 had a level of 309 dpm of plutonium.
These two grid blocks are in the area where the alpha scan had earlier identified isolated locations of contamination. The caulking sample contained 7.17 pCi/g of plutonium.
COMPARISON OF RESULTS WITH GUIDELINES NRC surface contamination guidelines, applicable to release of facilities from plutonium licensing restrictions are Total Contamination 300 dpm/100 cm2 (maximum in a 100 cm2 area) 100 dpm/100 cm2 (averaged over 1 m )
2 p
Removable Contamination 2
20 dpm/100 cm 5
DRAFT o
Direct alpha measurements were 6aithih these guidelines; however, the smear f rom the shower in room 166A, the smear f rom the " greenhouse" duct and 2
i two smears from retention tank drain lines exceeded 20 dpm/100 cm.
Because this was a mixed oxide
- facility, it was possible that part of the contamination might be due to uranium, which has higher guideline levels than I
These samples were therefore analyzed by alpha spectrometry for plutonium content.
The results, presented in Table 13, show that plutonium is contributing a very small f raction of the total alpha contamination, and the plutonium levels in the samples are within the NRC guidance levels for release from licensing.
Two paint samples from the floor of room 173 contained plutonium 2
contamination above the 300 dpm/100 cm guideline level. This information was provided to Region V for consideration of further remedial action.
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SUMMARY
O A survey of rooms 173, 155, 156, 158, and 158A and a decontamination shower in room 166A of the Specialty Fuels duilding at the Exxon Nuclear Facility was conducted during February 6-12, 1980.
The survey included alpha surface
- scans, measurements of total and renovable contamination, and determination of plutonium concentrations in paint and caulking samples.
1 l
The results of this survey identified three isolated areas of floor contamination in room 173, and residual contamination on four ventilation duct I
filter holders in the floor in to
)The licensee removed or reduced the contamination, and resurvey indicated that cleanup was effective in satisfying the NRC guidelines at these locations.
I Removable contamination measured in the retention tank drain system and i
the " greenhouse" duct work was shown not to be plutonium.
Samples of paint j
from two room 173 floor locations blocks G14 and G15 contained plutonium O
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DRAFT l
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levels above the 300 dps/100 cm guideline for release from licensing restrictions.
Total and removable contaminston levels measured in other 1
f surveyed areas were-within guidelines.
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Survey Reference and Grid Blocks Selected for Survey 10
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OG (OUTSIDE) l l
l HETERS c
FIGURE 10: Location of Measurements for Total and Renovable Contamination--HPT Shower of Roon 166A O
17
DRAFT Em O
j 22 c.e GREENHOUSE 20 O DUCT 18
/l i I 16
'l l l r
e 14 12 10 8
I A
- l v
1 1 6 i i i i I
i ! I I
!I, i i i
i 4-
!I i ;
i i
I
- i 2
a i i 1 ! I i
.l l
i ! '
0 I ' ! I I I I I I A
C E
G 6 i ie i i l Ii1 i i I '
?
?
A METERS S PAINT SAMPLES A CAULKING SAMPLE
~
AIR RETURN VENTS j
1 O
FIGURE 11: Locations of Paint and Caulking Material Samples 18
DRAFT Exx.
Q,.,'
22 5
GREENHOUSE 20 O DUCT 18 I I i 16 l l l
,,e-EL----
14 12
,sU 10
- 2 8
-u d
6: { !
l
- i n:
4 di
,i,
j I
2! i '
I' I
I !
ei i
!. l I
! I cl I I ! I I I t.
E G
i I i ! li il i i i ! i l.
N 9
2 A
- HETERS S AREAS OF CONTAMINATION AIR RETURN VENTS
,m
,d FIGURE 12: Locations of Residual Contamination Identified by Surface Alpha Scans 19 i
l
DRAFT TABLE 1
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 173 (FLOOR)
EXXON NUC'. EAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion RemovableContamgnation Grid Blocka (dpm/100 cm )
(dpa/100 cm )
Alpha Alpha Beta-Gamma Beta-Gamma Alpha Beta (Max)
(Ave)
(Max)
(Ave) 2cv (to gua (tc9
,a lu C H0b
<27
<27
<590
<590
<2
<6 Al 48
<27
<590
<590
<2
<6 C2 30
<27
<590
<590
<2
<6 D2 48
<27
<590
<590
<2
<6 E2 48
<27
<590
<590
<2
<6 E3 36
<27
<590
<590
<2
<6 A5 72 45
<590
<590
<2
<6 C5 110
<27
<590
<590 3
<6 HS 30
<27
<590
<590
<2
<6 A6 30
<27
<590
<590
<2
<6 G6 30
<27
<590
<590 3
<6 C7 130
<27 1290
<590
<2
<6 O'
D8
<27
<27
<590
<590
<2
<6 H9
<27
<27
<590
<590
<2
<6 H11 54
<27
<590
<590
<2 (6
E12 66
<27
<590
<590
<2
<6 F12 42
<27
<590
<590
<2
<6 F13 36
<27
<590
<590
<2
<6 HIS 36
<27
<590
<590 5
<6 E16 42
<27 790 700
<2
<6 E17 36
<27 1430 1220
<2
<6 G17
<27
<27
<590
<590
<2
<6 F18 60
<27 1000
<590 5
<6 A21 66 49 1400 1180
<2
<6 H21
<27
<27
<590
<590 12
<6
<2-8d
<6-18d B4-16
-e (Anchor Bolt Holes) aRefer to Figure 3.
bCoordinate listed is in the southwest corner of the grid block surveyed.
cDash indicates measurement performed.
dRange of measurements in 7 different holes.
20
DRAFT TABLE 2 O
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 173 (LOWER WALLS)
EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion RemovableContam{ nation Grid Blocka (dpm/100 cm )
(dpa/100 cm )
Alpha Alpha Beta-Gamma Bet a-Gam:na Alpha Beta (Max)
(Ave)
(Max)
(Ave)
D23-lb 48
<27
<590
<590
<2
<6 E23-1 60
<27
<590
<590
<2
<6 A3-0 60
<27
<590
<590
<2
<6 A12-0 78 30
<590
<590
<2
<6 A21-1 30
<27 640
<590
<2
<6 113-0 42
<27
<590
'590
<2
<6 17-1 66
<27
<590
.90 3
<6 B0-0 48
<27
<590
<590
<2
<6 C04) 35
<27
<590
<590 7
<6 H0-0 72
<27
<590
<590
<2
<6 r
aRefer to Figure 3.
bLetter refers to East-West coordinate.
First set of numbers refer to North-South coordinate and dashed number indicates distance in meters from the floor.
O 21
DRAFT TABLE 3 O
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 173 (UPPER WALLS)
EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion Removable Contagination Locationa (dpm/100 cm )
(dpm/100 cm )
Alpha Beta-Gamma Alpha Beta P lco. ps dov - (st o P y
m 1
<27
<590 3
<6 2
<27
<590
<2
<6 3-Pipe
<27
<590 3
<6 4-Pipe
<27
<590
<2
<6 5-Pipe
<27
<590
<2
<6 6
<27
<590
<2
<6 7
<27
<590
<2
<6 8
<27
<590
<2
<6 9-Pipe 28
< 59 0_,s
<2
<6
~
10
<27 (7120
<2
<6 s
11
<27
'4620 1
<2
<6 12
<27 24~00
<2
<6 13
<27
<590
<2
<6 O
14
<27
<590
<2
<6 15
<27
<590
<2
<6 16
<27
<590
<2
<6 17
<27
<590
<2
<6 18 38
<590
<2
<6 19-Pipe
<27
<590
<2
<6 20
<27
<590
<2
<6 21
<27
<590
<2
<6 22
<27
<590
<2
<6 23 47 640
<2
<6 a Ref er to Figure 4.
O 22
I DRAFT l
TABLE 4
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 173 (CEILING)
EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON i
Total Contamingtion Removable Contagination Locationa (dpm/100 cm )
(dpa/100 cm )
Alpha Beta-Gamma Alpha Beta 1-Air Duct
<27
<590
<2
<6 j
2
<27
<590 3
<6 3-Light Fixture (27 930
<2
<6 4-Air Duct 38
<590
<2
<6 5-Light Fixture 28
<590
<2
<6 6-Air Duct 57
<590
<2
<6 7
<27
<590
<2
<6 l
8
<27
<590
<2
,< 6 9
28
<590
<2
<6 i
10-Light Fixture
<27 1940
<2
<6 i
11-Light Fixture
<27
<590
<2 (6
12-Air Duct
<27
<590
<2
<6 a Refer to Figure 5.
j t
i i
4 1
O 23
- b-
,_..~. - _.----,
,.-.. - ~., -.-----,-.---.- --,.. - -
.--c
DRAFT TABLE 5 O
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 155 EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion Removable Contagjination Locationa (dpm/100 cm )
(dpm/100 cm )
Alpha Beta-Gamma Alpha Beta 1
<27
<590
<2
<6 2
47
<590
<2
<6 3
<27
<590 3
<6 4
<27
<590
<2
<6 5
<27
<590
<2
<6 6
57
<590
<2 9
7 66
<590
<2
<6
('$00f 8
<590
<2 8
9
' 38
<590
<2
<6 10 28
<590
<2
<6 11-Light 38
<590
<2
<6 12-Duct
<27
<590
<2
<6 13 28
<590
<2
<6 14
<27
<590 7
<6 a Refer to Figure 6.
1 0
24
DRAFT TABLE 6 O
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 156 EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion Removable Contagination Locationa (dpm/100 cm )
(dpa/100 cm )
Alpha Beta-Gamma Alpha Beta 1
<27
<590 3
8 2
<27
<590
<2
<6 3
<27
<590
<2
<6 4
<27
<590 3
<6 5
<27
<590
<2
<6 6
<27
<590
<2
<6 7
<27
<590 3
<6 8
<27
<590
<2
<6 9
47
<590 3
<6 i
10 47
<590
<2
<6 11
<27
<590
<2
<6 12
<27
<590
<2
<6 13 38
<590
<2
<6
(~'}
14
<27
<590
<2
<6 a Refer to Figure 7.
' O i
l 25
- -----,- _-.~.
- - - -. - - - - - - - - - - - - - - -l
DRAFT TABLE 7 0
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 158 ( AIRLOCK)
EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion Removable Contagination Locationa (dpm/100 cm )
(dpa/100 cm )
Alpha Beta-Gamma Alpha Beta 1
47
<590
<2 7
2 66
<590
<2
<6 3
75
<590
<2
<6 4
<27
<590 5
<6 5
<27
<590
<2
<6 6
38
<590
<2
<6 7
<27
<590
<2
<6 8
<27
<590
<2
<6 9
38
<590
<2
<6 10 28
<590 3
<6 11
<27
<590
<2
<6 12 94
<590
<2
<6 13
<27
<590
<2
<6 14
<27
<590
<2
<6 O
15
<27
<590
<2
<6 16
<27
<590
<2
<6 17 66
<590 3
<6 18
<27
<590
<2
<6 a Ref er to Figure 8.
O 26 l
.. =.
DRAFT l
t TABLE 8 O
l'
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ROOM 158A (AIRLOCK)
EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion Removable Contagination Locationa (dpa/100 cm )
(dpa/100 cm )
Alpha Beta-Gamma Alpha Beta 1
<27
<590
<2
<6 2
<27
<590 3
<6 3
28
<590
<2
<6 4
<27
<590.
<2
<6 5
38
<590
<2 (6
6
<27
<590
<2
<6 7
28
<590
<2
<6 8
<27
<590
<2
<6 9
47
<590
<2
<6 10
<27
<590 3
<6 11 38
<590
<2
<6 12 47
<590 3
<6 13 47
<590
<2
<6 j
O 14
<27
<590
<2
<6 d
15
<27
<590 3
<6 16
<27
<590
<2
<6
)
17
<27 3080 5
<6 18
<27
<590
<2
<6 i
a Refer to Figure 9.
f i
i i
i O
J 27
DRAFT I
TABLE 9 O
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS Room 166A (SHOWER)
EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion Removable Contagination Locations (dpa/100 cm )
(dp /100 cm )
Alpha Beta-Gamma Alpha Beta ~~
l I
5
<6 A
110
<2
<6 B
110 C
75 9
7 5
<6 D
<27 E
28 1
<6 3
)l)
F
<27
<6 G
<27 2
<6 i
l a Refer to Figure 10.
l i
i O i,
i l
l i
l!O 1
28 L.-..
DRAFT TABLE 10 0
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS ON VENTILATION SYSTEMS IN MISCELLANEOUS SAMPLES EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON 1
Locationa Area Total Alpha Removable Contamination 2
l Contaminatign (dpm/100 cm )
(dpm/100 cm )
Alpha Beta i
Room 173 - D4 Floor Vent Bottom b
<2
<6 Room 173 - D4 Floor Vent Top
<2
<6 Room 173 - E9 Floor Vent Bottom
<2 9
Room 173 - E9 Floor Vent Top
<2
<6 4
Room 173 - E14 Floor Vent Bottom
<2
<6 Room 173 - E14 Floor Vent Top
<2
<6 Room 173 - E20 Floor Vent Bottom
<2
<6 j
Room 173 - B22 Ventilation Control
<27
<2
<6 Room 173 - C22 Ventilation Control 38
<2
<6 Room 173 - D22 Ventilation Control 38
<2
<6 Room 173 - F22 Ventilation Control
<27
<2
<6 Room 173 - West Wall
" Greenhouse" Duct 660 i
Room 174 Exhaust Duct 45 5
<6 Room 174 Exhaust Duct 89
<2
<6 aRefer to Figures 2 and 3.
bDash indicates measurement not made.
I i
4 i
- O t
I 1
29
..... -. ~ -.
DRAFT TABLE 11
SUMMARY
OF CONTAMINATION MEASUREMENTS IN DRAIN SYSTEMS EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON 1
Location TotalAlphaContamgnation Removable Contamigation i
(dpa/100 cm )
(dpa/100 cm )
Alpha Beta l
a ROOM 173a Drain - C2
<27
<2
<6 Drain - CIS 47
<2
<6 Drain - G20
<27 3
<6 RETENTION TANK ACCESSb 1
-- c 140 2
750 3
3 aRefer to Figure 3.
bRefer to Figure 1.
i CDash indicates measurement not performed.
J 1
i I
t t
I i o l
30 i
DRAFT 4
TABLE 12 MEASUREMENTS OF PLUTONIUM IN PAINT AND CAULKING MATERIAL FROM ROOM 173 EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON f
Sample Locationa Total Plutonium 2
(dpm/100 cm )
Paint GIS 373
+ 15b I
~
Paint G14 309 17 Paint (B7) 146
+ 8
~
Paint (C8, 35.0 + 2.4 g
19.4 + 1.7 Paint Al Paint B21 61.2 + 4.3 i
Caulking B21 7.17 + 1.38C l
J aRefer to Figure 11.
b rrors are 2a based on counting statistics.
E cUnits for this sample are pCi/g.
O 5
i i
i
- l i
i 4
k 1
i O
i 31 I
. ~
- ~. _
DRAFT l
TABLE 13
- O RESULTS OF PLUTONIUM ANALYSIS ON
~
SMEAR SAMPLES EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON I
i Sample Total Alphg Plutonium 2
(dpm/100 cm )
(dpa/100 cm )
Shower - Room 166A 21 5
)
"Greenhuse" Duct 660 0.89 + 0.36 i
Retention Tank Drain #1 130 3.15 + 0.80 j
Retention Tank Drain #2 750 1.86 + 0.66 l
{
1
!O i
1 i
1 l
i 1
4 l
- O a
i 4
32 i
.-----=7,,-c,.,,m,.,,,-.
-r-,
en
_.~,,--n.--_.,
m-w-,w-.,---..m--4
,,-.,.,r-=-
v-,.----,,,r--
DRAFT REFERENCES O
l l.
Plutonium Release Survey, transmitted by letter from C.W.
Malody, Exxbn Nuclear Company, Inc., to W.T. Crow, Nuclear Regulatory Commission Division
~
of Fuel Cycle and Material Safety, November 25, 1985.
i i
i 2.
Minitab Statistical Project, Statistics Department, The Pennsylvania i*
State University, University Park, PA 16802 l
4 L
l
)
!+
O I
1 f
J l
i f
j i
I i
1
]
- O i
{
33
DRAFT O
1 1
l APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT O
"-~^--w
DRAFT APPENDIX A O
Major Sampling and Analytical Equipment The display or description of a specific product is not to be construed as an endorsement of that product or its manuf acturer by the authors or their employer.
j A.
Direct Radiation Measut ements Eberline RASCAL Portable Scaler /Ratemeter Model PRS-1 (Eberline, Sante Fe, NM)
Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe, NM)
)
Ludlum Floor Monitor 1
Model 239-1 (Ludlum, Sweetwater, TX)
()
Eberline Alpha Scintillation Probe Mm'.11 AC-3-7 (Eberline, Sante Fe, NM)
Eberline GM Pancake Probe Model HP-260 (Eberline, Sante Fe, NM)
Eberline Scintillation Alpha Counter Model SAC-4 (Eberline, Sante Fe, NM)
B.
Laboratory Analysis Automatic low-background Alpha-Beta Counter Model LB5110-2080 (Tennelec, Inc., Oak Ridge, TN) 4 Alpha Spectrouetry System Tennelec Electronics, EG6G ORTEC Surface barrier detectors (Tennelec. Inc., EG&G, Oak Ridge, TN)
I O
A-1
DRAFT O
APPENDIX B M SUREMENT AND ANALYTICAL PROCEDURES O
O l
DRAFT APPENDIX B i
)
Measurement and Analytical Procedures 1
Alpha and Beta-Gamma Measurements 1
Floors were scanned for elevated levels by passing slowly over the surface with a Ludlum Model 239-1 Gas Alpha Proportional Floor Monitor.
Other surfaces were scanned using Eberline Model AC3-7 alpha scintillation probes with Eberline Model PRS-1 portable scaler /ratemeters.
Measurements of total alpha radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model AC3-7 alpha scintillation probes.
Measurement of direct beta-gamma radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Mcdel HP-260 thin-window pancake GM probes.
Count rates (cpm) were converted to 2
disintegration rates (dpm/100 cm ) by dividing the net rate by the 4x efficiency and correcting for active area of the detector.
The effective 2
2 window area was 59 cm far the alpha detectors and 15 cm for the GM O
detecters. The averase bac*steeed coent rate was aPPreaimate17 2 cpm for the alpha probes and 68 cpm for the GM probes.
Removable Contamination Measurements Smear measurements were performed on numbered filter paper disks, 47 mm in diameter. Smears were sealed in labeled envelopes with the location and other pertinent information recorded.
A ZnS alpha scintillation counting system was used to initially evaluate individual smears at the site; smears were then returned to Oak Ridge and recounted using a low-background alpha-beta proportional system.
Analysis of Paint, Floor Caulking, and Other Samples for Plutonium l
Samples were dissolved by pyrosulfate fusion and precipitated with barium sulfate.
The barium sulfate precipitate was redissolved and the plutonium separated by liquid - liquid extraction.
The plutonium and uranium was then precipitated with a cerium fluoride carrier and counted using surface barrier B-1
-~ -
DRAFT detectors (ORTEC), alpha spectrometers (Tennelec), and an ND-66 Multichannel O
ina1 zer cuecieat Data).
7 Errors and Detection Limits The uncertainties associated with the analytical data, presented in the tables of this report, represent the 95% (2o) confidence levels based only on counting statistics.
Other sources of error associated with the sampling and analyses introduce an additional uncertainity of + 6 to 10% in the results.
Calibration and Quality Assurance Laboratory and field survey procedures are documented in manuals de.veloped specifically for the Oak Ridge Associated Universities Radiological Site Assessment Program.
Instruments were calibrated with NBS-traceable standards.
Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations.
The ORAU laboratory participates in the EPA and EML Quality Assurance Program.
l O
B-2 l
i DRAFT LO 4
i k
i I
1 i
1 j
5 j
APPENDIX C j
CUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSF,S FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL lO 1
)
i l
3 i
i l
l 4
1 1
i b
4 i
i!O 1-1 t
1 i
DRAFT O
t GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL i
d.
i i
i
!O U.S. Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety 3
Washington, D.C.
20555 i
i l
i 3
)
July 1982 i
i
.!O 1
i
(
C-1
.i
-,-m--,ewmww-n--n.,e-+---
g
,,7
.g,
,-ww-
-r,-,ne-w-,m
--wam,,
,.m.
n,
.,,,_,mes-. pow-.-
.--,.-m--,,.~
- - -,- -, -na
DRAFT
(
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 f acilities or items from regulatory control is considered on case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or surf aces 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.
3.
The radioactivity on the interior surf aces 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 or premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface O
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 wo'uld 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 surf ace 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.
5.
Prior to release of premises for unrestricted use, the licensee shall make a
comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of I
I C-2
DRAFT the survey report shall be filed with the Division of Fuel Cycle and.
Material Safety, USNRC, Washington, D.C.
- 20555, and - also the Administrator of the NRC Regional Office having jurisdiction.
The report should be filed at least 30 days prior to the planned date of abandonment.
They survey report shall:
a.
Identify the premises.
b.
Show that reasonable effort has been made to eliminate residual contamination.
c.
Describe the scope of the survey and general procedures followed, d.
State the findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
1 O
1
)
O C-3
O O
O TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclides Averageb,c,f Maximum,d,f Removableb,e.f b
a 2
2 U-nat, U-235, U-238, and 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm associated decay products 2
2 2
Transuranics, Ra-226, Ra-228,
'100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm t
Th-230, Th-228, Pa-231, Ac-227, 1-125, 1-129 2
2 2
Th-nat, Th-232, Sr-90, Ra-223 1000 dpm/100 cm 3000 dpm/100 cm 200 dpm/100 cm Ra-224, U-232, 1-126, I-131, I-133 2
2 2
Beta gamma emitters (nuclides 5000 dpm By/100 cm 15,000 dpm By/100 cm
'1000 dpm By/100 cm nj.
with decay modes other than alpha emission or spontaneous fission) except Sr-90 and i
others noted above.
a Where surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta gamma-emitting nuclides should apply independently.
b As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric f actors associated with the instrumentation.
c Measurements of average contaminant should not be averaged over more than I square meter.
For objects of less surface area, the average should be derived for each such object.
2 l
d Ihe maximum contamination level applies to an area of ngt more than 100 cm,
e The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing g
4 the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When w
removable contamination on objects of less surface area is determined, the pertinent levels should be 5
reduced proportionally and the entire surface should be wiped, f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad /h at I cm and 1.0 mrad /h at I cm, respectively, measured through M
not more.han 7 milligrams per square centimeter of total absorber.
q 5
...