ML20198S698

Confirmatory Survey of Specialty Fuels Bldg Exxon Nuclear Co Richland,Wa, Final Rept

ML20198S698
Person / Time
Site:	Framatome ANP Richland
Issue date:	04/30/1986
From:	Deming E OAK RIDGE ASSOCIATED UNIVERSITIES
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20198S689	List: ML20198S686 ML20198S691 ML20198S698
References
CON-FIN-A-9076-3 NUDOCS 8606100529
Download: ML20198S698 (48)

Text

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I Prepared by o'$ Rigge Associated CONFIRMATORY SURVEY Universities Prepared for OF THE U.S. Nuclear I

S**"Ess%ns SPECIALTY FUELS BUILDING m

Region V Office I

Ssfeguards and EXXON NUCLEAR COMPANY Supported ev M',t's".ls Programs RICHLAND, WASHINGTON n

Division of off$c"*

"*"9'**

E. J. DEMING Inspection and Enforcement

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I I

Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT APRIL 1986 I

g pa*1888 x 89eom7

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I I

CONFIRMATORY SURVEY OF THE SPECIALTY FUELS BUILDING EXXON NUCLEAR COMPANY RICHLAND, WASHINGTON I

Prepared by E. J. DEMING Radiological Site Assessment Program I

Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 I

Project Staff I

J.D. Berger F.T. Lange R.D. Condra M.J. Laudeman D.A. Gibson G.L. Murphy C.F. Weaver Prepared for I

I Safeguards and Materials Programs Branch Division of Inspection Programs Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission I

Region V Office FINAL REPORT April 1986 I

I based on work performed under Interagency Agreement DOE This report is No. 40-816-83 NRC Fin. No. A-9076-3 between the U.S.

Nuclear Regulatory Commission and the U.S.

Department of Energy.

Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the U.S. Department of Energy.

+

I lI I

i TABLE OF CONTENTS l

l l

\\

l Page l

l 11 List of Figures iii List of Tables Introduction and Site Hie" v 1

i 1

Site Description 2

Survey Procedures 4

Results Comparison of Results with Gaidelines 5

I e

S _a r, 33 References Appendices Appendix A: Major Sampling and Analytical Equipment 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

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- I I

i

l lI LIST OF FIGURES j

I Page Figure 1:

Plan View of Exxon Nuclear Co., Inc., Richland, I

Washington, Indicating Survey Locations in the 8

Retention Tank Drain Figure 2:

Plan View of the Specialty Fuels Building 9

t l

Figure 3:

Plan View of Mixed Oxide Room (Room 173) Indicating Grid System Established for Survey Reference and Grid 10 I

Blocks Selected for Survey 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 I

Figure 6:

Location of Measurements for Total and Removable Contamination on Floor, Walls, and Ceiling of 13

(

Room 155 Figure 7:

Location of Measurements for Total and Removable

)

Contamination on Floor, Walls, and Ceiling of l

Room 156 14 Figure 8:

Location of Measurements for Total and Removable l

Contamination on Floor, Walls, and Ceiling of 15 Room 158 g

l Figure 9:

Location of Measurements for Total and Removable l

Contamination on Floor, Walls, and Ceiling of Room 158A 16 Figure 10: Location of Measurements for Total and Removable Contamination-HPT Shower of Room 166A.

17 Figure 11: Locations of Paint and Caulking Material Samples 18 Figure 12: Locations of Residual Contamination Identified 19 by Surface Alpha Scans...

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I 11

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LIST OF TABLES Page I

Table 1:

Summary of Surface Contamination Measurements Room 173 (Floor) 20 Table 2:

Summary of Surface Contamination Measurements Room 173 (Lower Walls) 21 I

Table 3:

Summary of Surface Contamination Measurements Room 173 (Upper Walls) 22 Table 4:

Summary of Surface Contamination Measurements I

23 Room 173 (Ceiling)

Table 5:

Summary of Surface Contamination Measurements Room 155 24 Table 6:

Summary of Surface Contamination Measurements Room 156 25 Table 7:

Summary of Surface Contamination Measurements Room 158 (Airlock) 26 i

Table 8:

Summary of Surface Contamination Measurements Room 1584 (Airlock) 27 Table 9:

Summary of Surf ace 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 30 Systems Table 12:

Measurements of Plutonium in Paint and Caulking I

Material From Room 173 31 Table 13:

Results of Plutonium Analysis on Smear Samples 32 I

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111

[

l CONFIRMATORY SURVEY 0F THE SPECIALTY FUELS BUILDING EXXON NUCLEAR COMPANY RICHLAND, WASHINGTON I

j INTRODUCTION AND SITE HISTORY 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 storaga.

In 1985 the l

equipment was cleaned of gross contamination and removed for disposal.

Materials from the equipment decontamination process are contained in 55-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 l

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 I

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 the Region V Office of Inspection and Enforcement, the Radiological Site j

Assessment Program of Oak Ridge Associated Universities (ORAU), Oak Ridge, Tennessee, conducted a

confirmatory radiological survey during February 6-12, 1986. This report descriks the findings of that survey.

I SITE DE!CRIPTION 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 ca the western edge of the property, within the Specialty Fuels Bu!.idl.ig (refer to Figure 1).

Fuel element production was performed in room 173 of this building (Figure 2).

Plutonium packages were I

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

I I

these areas, a decontamination shower in the health physics room 166A also had a potential for plutonium contamination.

Room 173 has a floor area of about 175 m2

.~.3 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 adj acent 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.

SURVEY PROCEDURES I

Objactive I

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 I

lower walls in room 173 (Figure 3).

The grid origin was in the southwest corner with the west wall forming the

'0' 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.

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2

L I

Measurement of Total and Removable Contamination L

r 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.

L 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 p

of alpha and beta-gamma contamination levels were systematically performed at L

the center and four equidistant points, midway between the center and block corners.

Smears for removable alpha and beta contamination were performed at 7

L 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 ceilings of room 173 (refer to Figures 4 and 5).

Fourteen locations (floors, walls, and ceilings) were selected for L

measurement of total and removable contamination within room 155 (Figure 6),

r and an additional fourteen locations were selected in room 156 (Figure 7).

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 L

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 from floor drains and access points in the retention tank drain system (Figure 1).

Additional Sampling 2

Faint samples were collected from 100 cm areas at six locations on the floor of room 173 using commercial paint stripper.

Two of these locations were in the grid blocks where scans had identified residual contamination.

A sample of caulking material was also obtained f rom a floor crack in room 173.

Locations of these samples are indicated on Figure 11.

E 3

I RESULTS Alpha Surface Sean Surface scans identified three small loca' ions of elevated alpha contamination on the floor of room 173.

These were in grid blocks Al and G15 (Figure 12).

The G15 block was in an area that had been used for waste I

handling and packaging during decontamination of the facility.

The licensee cleaned these spots and resurvey indicated that cleaning had removed the 2

contamination to less than 40 alpha and 590 beta-gamma dpm/100 cm.

Scanning also identified residual contamination on four of the eight filter holder f rames in the return air ventilation ducts in room 173. The licensee removed these frames from the facility.

No additional areas were identified by the surface scans.

I Contamination Measurements Building Surfaces Results of total and removable contamination measurements on building floors, walls, and ceilings are presented in Tables 1-9.

The maximum alpha 2

neasurement was 200 dpm/100 cm, on the grill work of the door between rooms 2

155 and 156.

The maximum beta-gamma measurement was 7120 dpm/100 cm on the I

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 levels were 21 dpm/100 cm and 9 dpm/100 cm, respectively. The maximum alpha contamination level was obtained on the ' ast wall of the shower (Room 166A);

e the maximum beta was on the floor of room 155.

I Ventilation System Measurements Results of contamination measurements on ventilation ductwork and associated items are presented in Table 10.

The maximum total alpha 2

measurement was 89 dpm/100 cm in the exhaust ductwork, located in room 174. The high volume of air passing through the " greenhouse" duct discouraged direct measurement inside chat system.

Direct measurements were I

4

I I

not performed inside the floor vents, because of the negative findings of the 2

surface scans.

Removable alpha contamination of 660 dpm/100 cm was found inside the " greenhouse" duct.

The maximum removable beta contamination level 2

was 9 dpm/100 cm.

(The smear from the " greenhouse" duct was not analyzed for I

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 level of I

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 I

2 Paint samples from 100 cm areas on the floor of room 173 contained up to 373 dpte of plutonium (see Table 12). The maximum level was in the sample from 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 I

isolated locations of contamination.

The licensee removed the paint from a 2

6 m area encompassing grid blocks G14 and G15.

Resurvey indicated that paint stripping had removed the contamination to less than 43 dpm fixed gross 3

alpha and less than 13 dpm removable gross alpha.

The caulking sample from grid block B21 contained 7.17 pCi/g of plutonium.

I COMPARISON OF RESULTJ WITH GUIDELINES I

NRC surface contamination guidelines, applicable to release of facilities from plutonium licensing restrictions are:

Total Contamination 2

300 dpm/100 cm2 (maximum in a 100 cm area) 2 100 dpm/100 cm2 (averaged over I m )

I

I I

Removable Contamination 2

20 dpm/10G cm Direct alpha measurements were within these guidelines; however, the

'I smear from the shower in room 166A, the smear from the " greenhouse" duct and 2

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 plutonium.

These samples were therefore analyzed by alphs spectrometry for plutonium content. The results, presented in ' Table 13, show that plutonium is contributing a very small fraction of the total alpha contamination, and the I

plutonium levels in the samples are within the NRC guidance levels for release

-f rom licensing.

I Two paint samples frora the floor of room 173 contained-plutonium 2

contamination above the 300 dpm/100 cm guideline level.

On the recommendation of the NRC the licensee removed the paint from the area of concern using a commercial paint stripper.

Further sampling following paint removal provided data indicating the plutonium levels are within the NRC release limits.

I SU}efARY I

A survey of rooms 173, 155, 156, 158, and 158A and a decontamination

"" "*' '" " ~"

'66^

E Facility was conducted during February 6-12, 1906.

The survey included alpha E

surface

scans, measurements of total and removable contamination, and determination of plutonium concentrations in paint and caulking saiples.

The results of this survey identified three isolated areas of floor contamination in room

173, and residual contamination on four ventilation duct filter holders in the floor in room 173.

The licensee removed or reduced the contamination, and resurvey indicated that cleanup was effective in satisfying the NRC guidelines at these locations.

I 6

I Removable contamination measured in the retention tank drain system and the " greenhouse" duct work was shown not to be plutonium.

Samples of paint from two room 173 floor locations (blocks G14 and G15) contained plutonium 2

levels above the 300 dpm/100 cm guideline for release from licensing I

restrictions. The licensee removed the paint from this area, thereby reducing the contamination and satisfying the NRC guidance levels for release from licensing. Total and removable contaminaton levels measured in other surveyed areas were within guidelines.

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RETENTION TA*S i

FIGURE 1: Plan View of Exxon Nuclear Co., Inc., Richland, Vashington, Indicating Survey Locations in the Retention Tank Drain

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l METERS 9 DRAINS AIR RETURN VENTS VENTILATIDN X BAFFLE CUNTROL E GRID BLOCKS SURVEYED FIGURE 3: Plan View of Mixed Dxide Room (Room 173) l Indicating Grid Systen Established for Survey Reference and Grid Blocks Selected for Survey I

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I FIGURE 4: Location of Measurements for Total and ll Renovable Contaminations on Upper Valls i

of Roon 173 I

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l FIGURE 5: Location of Measurements for Total and Renovable Contamination on Celling of Room 173 i

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• 12 +11 7*

CEILING I

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• 10

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FIGURE 6: Location of Measurements for Total and l

Removable Contamination on Floor, Valls, and Ceiling of Room 15.5 I

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I FIGURE 7: Location of Measurements for Total and I

Renovable Contamination on Floor, Valls, and Celling of Roon 156 I

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Jk METERS II lI FIGURE 8: Location of Measurements for Total and Rec.ovable Contamination on Floor, Valls, and Celling of Room 158 15

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I FIGURE 9: Location of Measurements for Total and Removable Contamination on Floor, Valls, and Celling l

of Room 158A I

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FIGURE 10: Location of Measurements for Total and Renovable Contanination--HPT Shower l

of Roon 166A I

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METERS e PAINT SAMPLES A CAULKING SAMPLE AIR RETURN VENTS-1 FIGURE 11: Locations of Paint and Caulking Material Samples

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FIGURE 12: Locations of Residual Contamination Identified by l

Surf ace Alpha Scans I

19

E TABLE 1

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS E

ROOM 173 (FLOOR)

L EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamingtion RemovableContam{ nation Grid Blocka (dpm/100 cm )

(dpm/100 cm )

Alpha Alpha Beta-Gamma Beta-Gamma Alpha Beta (Max)

(Ave)

(Max)

(Ave)

H0b

<27

<27

<590

<590

<2

<6 A1 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 E

A5 72 45

<590

<590

<2

<6 L

CL 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 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 H15 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

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A21 66 49 1400 1180

<2

<6 L

H21

<27

<27

<590

<590 12

<6 B4-16

-- c (2_gd

<6-18d J

(Anchor Bolt Roles) r b

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aRefer to Figure 3.

bCoordinate listed is in the southwest corner of the grid block surveyed.

cDash indicates measurement not performed.

dRange of measurements in 7 dif ferent holes.

20

L EL TABLE 2

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS ROOM 173 (LOWER WALLS)

EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON i

Total Contamin tion Removable Contam nation Grid Blocka (dpm/100 cm )

(dpm/100 cm )

Alpha Alpha Beta-Gamma Beta-Gamma Alpha Beta (Max)

(Ave)

(Max)

(Ave) l 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 L

A21-1 30

<27 640

<590

<2

<6 113-0 42

<27

<590

<590

<2

<6 I7-1 66

<27

<590

<590 3

<6 B0-0 48

<27

<590

<590

<2

<6 C0-0 36

<27

<590

<590 7

<6 H0-0 72

<27

<590

<590

<2

<6 aRefer to Figure 3.

bLetter refers to East-Went coordinate. First set of numbers refer to North-South coordinate and dashed number indicates distance in meters from the floor.

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m W

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21

L TABLE 3

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS ROOM 173 (UPPER WALLS)

EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON F

Total Contamination Removable Conta ination 2

Locationa (dpm/100 cm )

(dpm/100 cm )

p Alpha Beta-Gamma Alpha Beta (Max)

(Max) 1

<27

<590 3

<6 2

<27

<590

<2

<6 3-Pipe

<27

<590 3

<6 4-Pipe

<27

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<6 L

5-Pipe

<27

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<6 6

<27

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<6 4

7

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<6 8

<27

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<590

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<6 10

<27 7120

<2

<6 11

<27 4620

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<6 L

12

<27 2400

<2

<6 13

<27

<590

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<6 r

14

<27

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15

<27

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<6 16

<27

<590

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<6 17

<27

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<2

<6

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<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 Refer to Figure 4.

[

E

[

[

22

l lI TABLE 4

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS ROOM 173 (CEILING) r L

EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON N

TotalContamingtion Removable Contagination a

(dpm/100 cm )

(dpm/100 cm )

Location F

Alpha Beta-Gamma Alpha Beta (Max)

(Max) 1-Air Duct

<27

<590

<2

<6 h

2

<27

<590 3

<6 3

3-Light Fixture

<27 930

<2

<6 1

4-Air Duct 38

<590

<2

<6 b

5-Light Fixture 28

<590

<2

<6 6-Air Duct 57

<590

<2

<6 7

<27

<590

<2

<6 p

L 8

<27

<590

<2

<6 9

28

<590

<2

<6 10-Light Fixture (27 1040

<2

<6 f

11-Light Fixture

<27

<590

<2

<6 12-Air Duct

<27

<590

<2

<6 a Refer to Figure 5.

1l 1l ll ll 23

l -

'I I

TABLE 5 I

SUMMARY

OF SUEFACE CONTAMINATION MEASUREMENTS ROOM 155 EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON I

Total Contamingtion Removable Contagination I

Locationa (dpm/100 cm )

(dpm/100 cm )

Alpha Beta-Gamma Alpha Beta (Max)

(Max)

I 1

<27

<590

<2

<6 2

47

<590

<2

<6 I

3

<27

<590 3

<6 4

<27

<590

<2

<6 5

<27

<590

<2 (6

8 6

57

<590

<2 9

7 66

<590

<2

<6 8

200

<590

<2 8

9 38

<590

<2

<6 I

' 6-10 28

<590

<2 11-Light 38

<590

<2

<6 12-Duct

<27

<590

<2

<6 I

13 28

<590

<2

<6 14

<27

<590 7

<6 a Refer to Figure 6.

I I

I I

I I

I I

24

'L TABLE 6 L

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS ROOM 156 5

EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Total Contamination Removable Contagination 2

Locationa (dpm/100 cm )

(dpm/100 cm )

i F

Alpha Beta-Gamma Alpha Beta (Max)

(Max) l 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 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.

E (I

i 25

E I

TABLE 7

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS ROOM 158 (AIRLOCK) l EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON I

l Total Contamin tion Removable Conta ination a

(dpm/100 cm )

(dpm/100 cm )

Location l

Alpha Beta-Gamma Alpha Beta I

(Max)

(Max)

I

(

1 47

<590

<2 7

2 66

<590

<2

<6 I

3 75

<590

<2

<6 1

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 I

9 38

<590

<2

<6 10 28

<590 3

<6 l

11

<27

<590

<2

<6 12 94

<590

<2

<6 I

13

<27

<590

<2

<6 14

<27

<590

<2

<6 i

I 15

<27

<590

<2

<6 I

16

<27

<590

<2

<6 17 66

<590 3

<6 l

18

<27

<590

<2

<6 I

a Refer to Figure 8.

I tI

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I 26

L TABLE 8

SUMMARY

OF SURFACE CONTAMINATION MEASUREMEMTS H

ROOM 158A (AIRLOCK)

L Exx0n suCtEAR COMeinT - R1CatAno, wASarscT0n

~

L Total Contamingtion Removable Contagination Locationa (dpm/100 cm )

(dpm/100 cm )

F Alpha Beta-Gamma Alpha Beta (Max)

(Max) 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 I

10

<27

<590 3

<6 11 38

<590

<2

<6 12 47

<590 3

<6 1

13 47

<590

<2

<6 14

<27

<590

<2

<6 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.

l I

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I I

I 27

[

~

TABLE 9

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS r

Room 166A (SHOWER)

L EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON

[

Total Contamin tion Removable Contagination a

(dpm/100 cm )

(dpm/100 cm )

14 cation

{

Alpha Beta-Gamma Alpha Beta (Max)

(Max)

A 110 5

<6 B

110

<2

<6 C

75 9

7 D

<27 5

<6 H

E 28 11

<6 F

<27 21

<6 G

<27

<2

<6 a Refer to Figure 10.

E E

[

[

D 28

b r

L i

~~

TABLE 10

SUMMARY

OF SURFACE CONTAMINATION MEASUREMENTS ON VENTILATION SYSTEMS IN MISCELLANEOUS SAMPLES EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON u

Locationa Area Total Alpha Removable Contamination 2

~

Contaminatign (dpm/100 cm )

(dpm/100 cm )

Alpha Beta (Max) l

-- b

<2

<6 Room 173 - D4 Floor Vent Bottom B

<2

<6 Room 173 - D4 Floor Vent Top

<2 9

j Room 173 - E9 Floor Vent Bottom

<2

<6 Room 173 - E9 Floor Vent Top

<2 (6

Room 173 - E14 Floor Vent Bottom

<2

<6 Room 173 - E14 Floor Vent Top

<2

<6 Room 173 - E20 Floor Vent Bottom 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

<6 660 Room 173 - West Wall

" Greenhouse" Duct Room 174 Exhaust Duct 45 5

<6 Room 174 Exhaust Duct 89

<2

<6.

aRefer to Figures 2 and 3.

b ash indicates measurement not made.

D EI I

5 29

E TABLE 11

SUMMARY

OF CONTAMINATION MEASUREMENTS IN DRAIN SYSTEMS EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON Location TotalAlphaContam{ nation Removable Contamigation (dpm/100 cm )

(dpm/100 cm )

(Max)

Alpha Beta ROOM 173a Drain - C2

<27

<2

<6 Drain - CIS 47

<2

<6 Drain - G20

<27 3

<6 b

RETENTION TANK ACCESS 1

-- c 140 750 2

3 3

aRefer to Figure 3.

bRefer to Figure 1.

cDash indicates measurement not performed.

1 I

I I

I I

I 30

l TABLE 12 u

MEASUREMENTS OF PLUTONIUM IN PAINT AND CAULKING MATERIAL 7L FROM ROOM 173 EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON L

Sample Locationa Total Plutonium 2

p (dpm/100 cm )

L b

Paint GIS 373 1 15

~

Paint G14 309 1 17 Paint B7 146

+ 8 Paint C8 35.0 7 2.4 l

Paint Al 19.4 I 1.7 Paint B21 61.2 _T 4.3 I

Caulking B21 7.17 1 1.38c l

aRefer to Figure 11.

bErrors are 2a based on counting statistics.

L cUnits for this sample are pCi/g.

I L

E F

B 1

I b

31 0

E I

TABLE 13 I

RESULTS OF PLUTONIUM ANALYSIS ON SMEAR SAMPLES EXXON NUCLEAR COMPANY - RICHLAND, WASHINGTON I

Sample Total Alphg Plutonium I

2 (dpm/100 cm )

(dpm/100 cm )

I Shower - Room 166A 21 5

"Greenhuse" Duct 660 0.89 + 0.36 Retention Tank Drain #1 140 3.15 + 0.80 Retention Tank Drain #2 750 1.86 I 0.66 I

I ll I

I I

I

.I I

I I

I 32

I l

1 REFERENCES I

1.

Plutonium Release Survg, transmitted by letter from C.W. Malody, Exxon Nuclear Company, Inc., to W.T. Crow, Nuclear Regulatory Commission Division I

of Fuel Cycle and Material Safety, November 25, 1985.

2.

Minitab Statistica! Project, Statistics Department, The Pennsylvania I

State University, University Park, PA 16802 l

3.

Plutonium Release Survey Addendum, transmitted by letter from C.W. Malody, Exxon Nuclear Company, Inc., to R. Thomas, Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety, April 18, 1986.

l I

l l

,I I

I l

1 1I lI

>I I

i I

I 33

E l

E l

^

l E

~

l L

E EI 1

E 1

APPENDIX A L

MAJOR SAMPLING AND ASALYTICAL EQUIPMENT E

L

[

EI 1I l

s APPENDIX A Major Sampling and Analytical Equipment The display or description of a specific product is not to be construed y

as an endorsement of that product or its manufacturer by the authors or their employer.

A.

Direct Radiation Measurements Eberline RASCAL Portable Scaler /Ratemeter Model PRS-1 (Eberline, Sante Fe, NM) y Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe, NM)

Ludlum Floor Monitor Model 239-1 (Ludlum, Sweetwater, TX)

Eberline Alpha Scintillation Probe Model AC-3-7 (Eberline, Sante Fe, NM)

F Eberline GM Pancake Probe L

Model HP-260 (EN line, Sante Fe, NM)

Eberline Scintillation Alpha Counter Model SAC-4 (Eberline, Sante Fe, NM)

B.

Laboratory Analysis Automatic low-background Alpha-Beta Counter Mode 1 LB5110-2080 (Tennelec, Inc., Oak Ridge, TN)

Alpha Spectrometry System Tennelec Electronics, EG6G ORTEC Surface barrier detectors (Tennelec, Inc., EG6G, Oak Ridge, TN)

A-1 l

[

E E

~

APPENDIX B MEASUREMENT AND ANALYTICAL PROCEDURES E

E

~

[

[

E

[

]

[

APPENDIX B Measurement and Analytical Procedures Alpha and Beta-Gamma Measurements l

l

{

Floors were scanned for elevated levels by passing slowly over the surface with a Ludlum Model 239-1 Gas Alpha Proportional Floor Monitors 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 Model 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 4n efficiency and correcting for active area of the detector. The effective 2

2 window area was 59 cm for the alpha detectors and 15 cm for the GM detectors. The average background count rate was approximately 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 evalt: ate individual smears at the site; smears were the'n returned to Oak Ridge and recounted using a low-background alpha-beta proportional system.

Analysis of Paint, Floor Caulking, and Other Samples for Plutonium 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 cerf um fluoride carrier and counted using surface barrier B-1 s

L

[

{

detectors (ORTEC), alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).

[

Errors and Detection Limits The uncertainties associated with the analytical data, presented in the tables of this report, represent the 95% (2a) 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 developed 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.

[

[

[

[

[

[

C

[

B-2

r 1

E E

E E

E 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 rL b

E FI

I I

GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT i

PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL I

I I

I U.S. Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety Washington, D.C.

20555 I

l July 1982 I

I I

I 1I 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 e,quipment prior to abandonment or release for unrestricted use.

The limits in Table 1 do I

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 case-by-case basis.

1.

The licensee shall make a reasonable effort to eliminate residual contamination.

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.

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 or premisee, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface I

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 p

continuing work with radioactive materials, or conversion of L

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, I

extent, and degree of residual _ surface contamination.

b.

Provide a detailed health and safety analysis which reflects that I

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 C-1

E 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 p

report should be filed at least 30 days prior to the planned date of L

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.

E E

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E

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C-2

MW M

M M

M M

M M

M M

M M

M M

TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclidesa Averageb,c,f Maximum,d f Removableb,e,f b

2 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 Th-230, Th-228, Pa-231, Ac-227, I-125, I-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, I-126, 1-131, I-133 2

2 2

Beta gamma emitters (nuclides 5000 dpm Sy/100 cm 15,000 dpm BY/100 cm 1000 dpm By/100 cm with decay modes other than alpha emission or spontaneous a

d, fission) except Sr-90 and 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 factors 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 d The maximum contamination level applies to an area of not more than 100 cm,

2 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 the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be 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 not more than 7 milligrams per square centimeter of total absorber.

I I

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l 3

NMSS/FuelCycle Matv}

l FCUF FC?/

l rp.

-l Dbbel #

Proj:ct # __ __ __.___ !

-l!

O!!nr f

roa LPDR m

Return to _G%c~pa-E SS 395 c

I1 I'

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