ML20134G575

Advises That EIS & Environ Assessment Unwarranted for 820414 Request for Termination of License SNM-54.Bldgs H & J Decontaminated,Per Insp Repts 70-1007/83-01 & 70-1007/84-01 & Released for Unrestricted Use

ML20134G575
Person / Time
Site:	07001007
Issue date:	05/01/1985
From:	Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20134G565	List: ML20134G562 ML20134G570 ML20134G575
References
NUDOCS 8508260306
Download: ML20134G575 (1)

Text

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5 MAY I 1985 FCUP:PLH COCKET NO.:

70-1007 APPLICANT:

General Electric Company (GE)

San Jose, California SUPJECT:

CATEGORICAL EXCLUSION FOR RE00EST 0ATED APRIL 14, 1982 TO TERMINATE LICENSE Py letter dated April 14,198?, GE requested termination of Faterials License No. SNF-54 Buildings H and J at the San Jose site have since been decontaminated and, based on findings in Inspection Report Hos. 07001007/83-1 a nd 07001007/84-1, the NRC has relessed these buildings for unrestricted use.

The residual naterial possessed under this licensa will be transferred to Cali fornia License No. 0418-59. This action is administrative in nature and will have ro envircreental inpacts. Therefore, in accordance with 10 CFR 51.72(c)(11), an Environmantal Assessment or an Environnental Inpact Statement is not warranted for this proposed action.

FOR THE ffUCLEAR REGULATORY C0Ff4ISSION Original Signed Byj

17. I. Cr.qu y -

W. T. Crow, Acting Chief Uranium Fuel Licensing Rranch Division of Fuel Cycle and Material Safety. fMSS B508260306 850820 PDR ADOCK 07001007 C

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION V Report No. 70-1007/83-01 Docket No. 70-1007 License No. SNM-54 Licensee:

General Electric Company 175 Curtner' Avenue San. Jose, California. 95125' Facility Name:

General. Electric Company Inspection at:

San Jose, Cali.fornia 95125 Inspection conducted: May 12-13, 16-18, 1983 f

[ / ?3 Inspectors:

B. L. Brock, Fuel Facilities Inspector Date Signed f-AAAAY I Sl'1 $ 3 P. R. Zur,skowski, Radiation Specialist Date Signed

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'I - t - t N J. F. Pank) Radiation Specialist Date Signed w.

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Approved By:

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[d R. D. Thomas, Chief, Materials Radiation Date' Signed Prote ion Ins ection and Licensing Section I/[/k 3 Approved By:

H. E. Book, Chief, Radiological Safety Branch Date Signed Summary:

Inspection of May 12-13, 16-18, 1983 (Report No. 70-1007/83-01)

On April 19, 1983, the licensee requested NRC Region V to conduct a confirmatory survey of the facility to establish that the buildings can be released for-unrestricted use prior to the transfer of the operations to the state license and the termination of NRC License SNM-54.

On May 12, 1983, three Region V inspectors began the confirmatory survey in Building J of the facility. The survey was, completed on May 18, 1983.

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...e Results: This survey, conducted with Micro-R portable gamma scintillation survey instruments, air proportional alpha survey instruments, contamination wipes, and soil samples found the contamination levels were within !re NRC guidelines as shown in attached tables.

Based on the results of tna survey, it was determined that the facility can be released for unrestricted use and that no additional decontamination will be required.

A total of 72 man-hours were expended on site utilizing three inspectors in conducting this' survey.

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a DETAILS 1.

Persons Contacted

_B. L.,.Epste,in, Program Manager, Support. Programs G. E. Cunningham, Senior' Licensing Engineer C. Berry, Manager, Facilities Engineering & Planning M. Hensley, Construction Engineer, Facilities A. H. Lane, Radiation Protection Technician

===2.

Background===

The licensee discontinued activities involving SNM (specifically enriched uranium).in the Building J facility during the 2nd quarter of 1969. At that time, all contaminated equipment was removed and either sent to a licensed burial; site or to another facility authorized to accept the raterial. All ventilation ducting was removed (including that on the roof) and also sent to a burial f acility. The building was then decontaminated. The decontamination efforts included the jack hammering and removal of contaminated concrete. Following decontamination, the floors in the contaminated areas were retiled and the facility was internally released for unrestricted use by the licensee and used for over twelve years for activities not involving radioactive materials.

I In late July of 1982 the licensee requested NRC to conduct a survey of Building J to confirm that the facility meets the NRC limits for

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.. unconditional release;with.respe.ct. to: uranium. contamination.4. ; -

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'd N On August 5, 1982, three inspectors from NRC Region V conducted a preliminary survey of the old UF -UO c nyersion area where a known spill of approximately 300 lbs. 6of uranium hexafluoride occurred on 2

4 December 30, 1967. After the discovery of some contamination under floor tile that did not meet NRC release criteria, it was determined j

that additional decontamination would be required in this area of i

Building J.

Inresponsetoghesefindings,thelicenseetookthefollowingactions in this 6450 ft section of the building:

j 1.

All interior walls surrounding this area were removed.

i 2.

All f.loor tile was removed.

3.

The entire concrete floor surface was removed (scabbled) to a depth of approximately 1/4 inch.

4.

Approximately 500 linear feet of floor containing expansion joints wege removed. The area of these trenches added up to about 1400

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All contaminated drain lines were removed.

6.

An extensive survey of the building was made and the results sent I

to NRC Region V on April 19, 1983.

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In addition. to the survey results, the licensee also forwarded a leti_r -

requesting NRC Region V to conduct a 2nd survey to confirm that the On May 12-18, facility meets the NRC limits for unconditional release.

1983, three inspectors expended a total of 72 in _ ector hours conducting confirmatory surveys on floor, wall, supporting girder and roof areas of The survey criteria were based on NRC requirements established by the. " Guidelines for Decontamination of Facilities and Building J.

Equipment Prior to Release for Unrestricted Use or Term

" Standard' Review Plan for and on Policy and Guidance Directive FC-3:

Termination of Special Nuclear Material Licenses of Fuel Cycle Facilities", April 1, 1983.

3.

Discussion The survey results compared favorably with the licensee's measurements with the exception of several dozen isolated " hot spots" associated with Most of the spots on the ground floor i

the old UF - 0 e nyersio,n area.

were in areas not accessible to the scabbling machine used by the 6

2 The contamination on the roof (most probably associated with the spill of 1967) was in the area where filter banks and ventilation licensee.

Most of the contamination found in the ducting was removed in 1969,.

girders was associated with an inside wall (removed p The licensee was allowed of early 1968 (high pressure water was used).

to decontaminate these isolated spots while the inspectors wereAfter the decontam surveying other parts of the building.

were completed by the licensee, a resurvey indicated that NRC guidelines A review of all survey results had been met for the isolated spots.

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, yg. indicatesythat. Building: ','J"f meets..NRC: guidelines ~,for: unrestricte -us

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4.

Procedure A.

General The procedure used during this survey for the floor and roof areas was to locate poten,tial areas of contamination using gamma scintillation survey meters held at a distance of approximately one Contaminated areas located r

inch from the surfaces being surveyed.

were subsequently surveyed with an air proportional alpha meter to determine the alpha contamination level. The gamma scintillation Wipes survey meters were sufficiently sensitive for this survey.

Both the controlled and were collected wher,e appropriote.

uncontrolled areas of Building J were included in,this survey.

The licensee's decontamination efforts included removal of portions e aversion area and some of the concrete floor in the old UF -UO 6

2 of the soil thus exposed.

m Soil samples were collected from randomly selected locations as e.

l well as those locations where the presence of potential l

contamination was indicated by a gamma survey.

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3 B.

Instruments Used The instruments used in this survey are the Eberline Model PRM-7 gamma scintillation survey meters, LRL alpha survey meters, and a A Tennelec Gas Flow Proportional Ludlum alpha survey meter.

The specific instruments used counter was used to count the wipes.

are as follows:

Serial No.

' Calibration due date Instrument LRL Alpha Survey Meter NRC 374 10-21-83 9-14-83 LRL Alpha Survey, Meter,,

NRC 375,

'Ludium Alpha Survey Meter' NRC 3565 10-20-83 Eberline PRM-7 Survey Meter: -NRC 6383 3-28 Eberline PRM-7 Survey Meter NRC 8596 3-11-84 Eberline PRM-7 Survey Meter NRC 10839 8-16-83 Tennelec Gas Flow 57514 N.A.

Proportional Counte_r C.

Areas Covered The areas surveyed were the floors, walls, ceiling girders and roof of Building J and are described in' detail as follows':

(1) Floor Floor areas were surveyed where possible i.e., where the floor was not covered-by equipment or furniture (Figure 1).

An estima*e of the percent of the floor area surveyed is given v.r:. ;-y; ::v..n;. '. y:.i.e. ibelowy:Lg.- -. d.v. !, Y:.. t.A: c.: :::&..s'." : m.6 & ~.:. ; r&c M ? A W -

Location Total Est.

% of Total Area Area (Ft')

Surveyed 6000 100 UF -UO, Conversion Area South Controlled Area 4700 75 6

North Controlled Area 4800 60 Furnace Room 4100 90 850 80 Change Rooms 75 Offices & Machine Shop 2800 Area 90 Uncontrolled Area 28,000 (2)" Roof As with the floor area, all of the tar and gravel roof areas were surveyed where possible with gamma scintillation survey meters (Figure 2).

It is. estimated that approximately 80% of,,

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'An' alpha' survey'

" "the ' roof area was' ' surveyed ~ for gamma' radiation'.'

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was also made of the equipment on the roof such as vents, ducts, and machinery.

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4 (3) Walls a.

UF -UO Conversion Area 6

2 The existing wall surface of the UF -UO conversion area 6

2 was surveyed for alpha and gamma radiation from the floor to an approximate height of.7 feet.

In addi. tion, two..

' randomly selected areas 'of wall having the dimensions 28 feet by 10 feet were also surveyed for alpha radiation.

It is estimated that 3% of the actual call area of these two. randomly selected areas were surveyed for alpha radiation.

b.

North and South Controlled Area.

The, east wall of the south controlled area was surveyed for alpha radiation from the floor to the height of approximately 7 feet because of suspected potential

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contamination based on information provided by a licensee representative.

It is estimated that 1% of the perimeter wall area of the north and south controlled area was surveyed.

(4) Girders Several roof girders in both controlled and uncontrolled areas were selected for survey. The estimated height of these girders above the floor is approximately 35 feet.

The approximate location of these girders are indicated in Figure

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D.

Soil Survey Six samples had been collected from the soil underneath the concrete floor which had been exposed as a result of decontamination efforts by the licensee (Figure 4, Table 1).

One sample was also collected from the soil which had been underneath the liquid waste treatment facility which was ' utside and adjacent to the south wall of o

Building J.

This facility including equipment had been completely demolished and disposed. A soil sample from near Building L was collected as a representative background sample.

5.

Results of Surveys A.

Floors Survey A total of 10 areas of contamination were found on the floor area (Figure 1, T.able 2).

Of these 10 areas, 9 were located in the

,, Uyg.UO 'conversio'n -area and the-remaining' area was' located in the' s.

closet of the former men's change room. All of the contgminated areas found were below the NRC limit of 15000 dgm/100 cm for digerete sources.

The areas ranged from 300 cm to less than 100 in sizg. The a}pha contamigation levels found ranged from 2300 em i

dpm/100 cm to 11400 dpe/100 cm. However, the licensee's policy

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5 was to decontaminate to as low a level as possible.

Consequently, all of the contaminated spots found were subseguently decontaminated by the licensee to a maximum of 450 dpm/100 cm or less by chiseling out the contaminated concrete from the floor.

B.

Roof Survey

'A ' tio ta'l'of'11 areas of contaminatio'n were'found on the roof area and associated equipment (Figure 2, Table 3) such as vent covers. Six of the 11 contaminated areas were on the roof itself and were clustered around the vent duct exhausting the UF -UO, conversion 6

Because the roof covering is of tar and graveI compositi.on area.

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~ which is inherent 1'y sneven,' alpha surveys could not be'used as an accurate. indicator.of contamination. The licensee decontaminated -

the contaminated areas found during this survey, using the micro R meters, by removing the tar and gravel roofing down to,the bare wood. The 1eVel f alpha contamination remaining ranged frori 6800 2

2 on the bare wood to about dpm/100 cm fog about an area of 200 cm 110 dpm/100 cm.

i The remaining five contaminated areas were found while using alpha survey meters on the equipment on the roof. The rangg of alpha contaminat a levels found ranged from 110'dpm/100 cm to 570 dpm/100 cm C.

Girders Survey A preliminary survey was conducted at several girder locations in the northern and southern sections of the UF,-UO, conversion area.

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Twosgi.rde,reareas,ingtheenorthers. seation. conEainEdasigniffcante ' 3.-

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contaminatio'n levels. The first area was associated with a girder enclosing wall which had been removed by the licensee during the decontamination operation. The second girder area was associated with the ventilation duct work to the roof of the building. These isolated areas of contamination collectively comprised only a very small fraction of the total girder area surveyed. The survey results of the southern girder area indicated no significant contamination levels.

Based upon the results of the preliminary survey, nineteen girder locations were selected for further survey (Figure 3). Ten of these 0 e nversion area. The remaining girder locations were in the UF6 2

nine locations were selected at random in the uncontrgiled area.

Small areas of contaminatign of about 6800 dpm/100 cm ranging in 2

size from less than 100 cm to 200 cm were found at eight locations in UF -UO conversion area. 2These areas were decontaminated to 6

approxima ely 340 dpm/100 cm One l'catign'in'the uncontrolled" area'measuged 'approximately 3400'

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o dpm/100 cm for an estimated area of 100 cm. 2Thi8 decontaminated to approximately 350 dpm/100 cm 2

The remaining ten areas measured approximately 340 dps/100 cm,

These areas were alao decontaminated although they were well below

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6 the NRC limits. The measured alpha contamination levels after decontaminati,on were background.

D.

Soil Survey Eight soil samples including one background sample were collected for analyses on March 17, 1983. Two of.the,eight samples collected indicated soil contamination concentrations greater than the NRC release limit of 30 pCi/g for enriched uranium. Two decontamination efforts were subsequently made b? the licensee to reduce *.he soil concentrations of enriched uranium to acceptable levels. As a result, five additional soil samples were collected

'for a total'13' samples.

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Oftheeightlocationssa[npled,twolocationshadconcentrationsof

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20 and 22 pCi/g of enriched uranium respectively. The remaining locations had concentrations of less than 1 pCi/g of enriched uranium.

e E.

Wipe Survey The NRC limit fgr removable alpha (U-238, U-235) contamination is 1000 dpm/100 cm. A total of 29 wipes were collected. Twenty-two wipe's were collected from areas where contamination had been indicated by the gamma and alpha surveys (Table 4). The highest wipe level was 293 dpm/100 cm. The remaining wipes were well below this level.

6.

Conclusion

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.The concentrations of uranium in the' soil from under the concrete floor

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in the UF -UO, conversion area has been decontaminated to below the NRC g

limit of 30 pCi/g for enriched uranium. The survey of Building J indicate that all areas of contamination found have been decontaminated and are well within the NRC limits.

As a result of this survey, it is concluded that Building J may be released for unrestricted use.

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, 1-j Table 1 Results of Analyses of Soil Samples Collected from the UF -UO Conversion Area in Building J 6

2 Sample No.

Location (see Fig. 4).

Concentration of Uranium in pCi/g

,3-17-83 5-12-83

. 5-18-83.

1.

Northern end of the eastern 20 + 1.0 north-south trench in the southern half of the area.

8 2;

Southern end 'of the ke' stern

'22 +'1.0 north-south trench.

3.

West end. of southernmost

• 43 + 2.0

• 203 + 7

<1 east-west trench.

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Northern end of north-south 0.4 + 0.9 trench in southeastern corner of the building.

5.

Girder foundation in south- *2300 1 100

7. + 1 eastern area cf the building.

6.

Northern end of the north-0.4 + 0.9 south trench in the northern half of the area.

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• Background. sample. (collected,0.2 0 0 9,

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47 *..a O ~ & d. 'r M -

i by Building L).

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Liquid waste treatment 0.4 + 0.9 facility.

• Exceeds the NRC limit of 30 pCi/g for enriched uranium.

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8-4 Table 2 Alpha and Gamma Survey Results of Floor Area in Building J Before Decontamination After Decontamination alpha gamma alpha gamma 2

2 Location No.

dps/100 cm ur/hr dpa/100;cm ur/hr 1

3400 8-10 350 3-5(background) 2 4500 10-13 350 3

6800 12-15 4

3400 8-10 350

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~5 11400 30-35'-

50 6.

6800 12-15 350 7

5700 12-15 250 8

2700 5-8 450 9

2300 5-8 150 10 9100 20-25 350 (1)

Efficiency = 0.44 ua ;.. ; ^.. n. a. <:.. :.; M.. ' ; e...

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s Table 3 Survey of Building J Roof Area Before Decontamination After Decontamination alpha (1) gamma alpha-(1) 2 Location No.

..dpm/100 cm7

, ur/hr

.dpefl00 cm x.

8-10 350 I

15

'6800(2) 2 8-10 300 3

8-10 570 4

~8-10 570 5'

8-10 900-6 160 Bkgnd 160 7

230 230 8

110 110 9

370 10 80 80 11 (1) Efficigacy = 0.44 (2) 100 cm total area

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Table 4 Results of Wipe Survey i

Sample No.

Date Collected Location Dpm/100 cm

~5 16-83 N.E. side of Bldg. J (Drip.

1 1

marks from wall).

2 East side of Bldg. J, center 3

of wall, drip marks on

• wall.

3 Intersecting girders - 2nd 5

intersection near F.W. wall

~ of UF -UO e aversi~on room.

6 2

4 5-17-83 UF -UO e aversion area.

54 6

"2 5

13 6

4 7

17 8

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5 10 8

11 43 12 21 13 Old furnace room girder 20'

.212 west of pit.

14 Inside of large roof vent 8

by Col. C-9.

15

' Vent south of Col. C-9.

293 16 Girder by vent south of 245 Column C-9.

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Fluorescent'. light.. by..la rge,;.n :r....e29 e.Qo. ; < '

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i exhaust roof vent near column C-9.

18 Girder by large exhaust 69 vent near column C-9.

19 Intersection of cross beam 14 in uncontrolled area in middle of building.

t 20 5-18-83 Ist girder crosspiece North wall 6

by corner UF -UO c aversion 6

2 area.

21 22 22 ist girder crosspiece on east 32 wall for UF - 0 e aversion 6

2 area, south sample.

23 ist girder crosspiece on east 20 wall for UF - 0 e nyersion 6

2 area, north sample.

24 i

Wall junction-east wall on 9

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north 'erid"UF 0

6 2

area.

25 Wall junction - east wall on 52 north end UF - 02 * ""***i "

6 area.

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ag op.fino c,2 Sample No.

Date Collected Location 26 East wall - 2nd junction 26 from north end to wall.

East wall - 2nd junction 61 27 from north end to wall.

East wall - 4th. junction.

11'3 28.

from north wall-underside.

East wall - 4th junction 67 29 from north wall.

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j U. S. NUCLEAR REGULATORY COMMISSION s

REGION V Report No.'

70-1007/84-01

)

Docket No.

70-1007 License No.

SNM-54 Licensee:

General Electric Company i

175 Curtner Avenue San Jose, California 95125 1

l Facility Name:

General Electric Company

-Inspection at:

San Jose, California 95125 l

Inspection conducted:

February 22-24, July 2, 5 and September 18, 1984

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Inspectors:

/ /

1. f B. L. Brock, Fuel Facilities Inspector Date Signed

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P. R. Zurakowski, Radiation Specialist Datt Signed Approved By:

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R. D. Thomas, Chief Date fighed Nuclear Materials Safety.Section,

)

Summary:

Inspectione of February 22-24, July 2, 5 and September 18, 1984 (Report No. 70-1007/84-01)

On April 19, 1983, the licensee requested NRC Region V to conduct a confirmatory survey of the facility to establish. that Buildings (J and H) can be released for unrestricted use prior to the transfer of the operations to i

the state license and the termination of NRC License SNM-54. The Building J

]

survey was completed May 18, 1983 (see Inspection Report 70-1007/83-01). On l

February 22, 1984, two Region V inspectors began the confirmatory surveys in j

Building H of the facility. A State of California inspector participated 1

during the first two days of the inspection. The surveys were completed on September 18, 1984.

j l

Results: These confirmatory surveys,' conducted with Micro-R portable gamma j

scintillation survey instruments, air proportional alpha survey instruments, I

and contamination wipes, found the contamination levels were within the NRC J

i.

guidelines as shown in attached tables. Based on the results of these

{

surveys, it was determined that Building H can be released for unrestricted i.

use and no. additional decontamination will be required. A total of 50 man-hours was expended onsite utilizing two inspectors in conducting these i

surveys.

i This completes the confirmatory surveys inspection of the facilities processing SNM under NRC license SNM-54 at the General Electric Company, site in San Jose, California.

i 1

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._.__.__.__,__.--.-_.-,-m

DETAILS 4

f 1.

Persons Contacted A. H. Lane, Radiatio.n Protection Technician i

M. J. Hensley, Construction Engineer, Facilities j

J. Kass, Manager, Plant Materials and Experimental Mechanics W. W. Lew, Health Physicist, State of California

]

Department of Industrial Relations 4

j

===2.

Background===

As part of the licensee's efforts to terminate NRC Licen Building J was completed first and the NRC confirmatory surveys were 4

Building H previously reported (70-1007/82-02 and 70-1007/83-01). act I

direct conversion and vibratory R and D level work in UF to UO2 compaction were also undertaken. The operations stopped about 1977.

g Decontamination began in October, 1980 and continued j

status of Building H from March 23 through April 1, 1981 and in it's l

report indicated there were no corrective actions April 16,1981 identified with regard to meeting California or NRC release limits.

l This report presents the results of the'NRC confirmatory surveys of l

18, 1984. A State Building H on February 22-24, July 2, 5 and September of California Radiation Health Unit inspector was of invaluable assistance during the two days (February 22 and 23) he was available to l

The survey criteria were assist with the initial Building H inspection.

based on NRC requirements established by the " Guidelines for Decontamination of Facilities and Equipment Prior to Release for l

Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material, July 1982," and on Policy and Guidance" l

Directive FC-3:

Material Licenses of Fuel Cycle Facilities," April 1,1983.

Confirmatory Survey of February 22-24, 1984, 3.

4 A.

Instruments i

The field radiat, ion detection instruments selected for this survey f

were Eberline Model PRM-7 gamma scintillation survey meters, Lawrence Radiation Laboratory (LRL) alpha survey meters, and aThe l

Ludlum.Model,12 alpha survey meter.

The specific on a Tennelec Gas Flow Proportional counter.

~

instruments used and their calibration status were:

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• 1 I

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_.__-4_,

_., _ _., _ _.~._____ _._ _ _ -. ____.

[nstrumint

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Idzntificatica Ns.

Calibratica Due

.Eberline.PRM-7 Miro-R Heter NRC 006383 3/23/84 Eberline PRM-7 Micro-R Meter NRC 008596 3/27/84 Eberline PRM-7 Micro-R Meter NRC 10839 6/15/84 LRL Alpha Survey Meter NRC 000374 4/18/84 LRL Alpha Survey Meter JUIC 000375 3/16/84 Ludlum Alpha Survey Meter NRC 003565 4/20/84 Tenelec Gas Flow Proportional 57514 N.A.

Counter B.

Areas Surveyed (1) General Building H included about 35,000 sq. ft. of floor and roof space (15,000 sq. ft. on the first floor, 5000 sq. f t. on the second floor and 15,000 sq. ft. of roof).

The initial survey

.was made of all floor and roof areas using the Eberline Micro-R meters. These instruments indicated background gamma levels of 3 to 7 ur/hr.

It is estimated that 90 percent of both the floor area (See Figures 1 and 2) and the roof area (See Figure 3) were surveyed through inclusion of accessible areas under and around equipment. This effort to confirm the licensee's surveys resulted in identification of some areas exceeding the 3-7 ur/hr. background. Elevated alpha counts'were generally associated with elevated gamma counts. The gamma surveys were faster and readily identified areas for tile, carpet or wall footing removal.

On the first floor, an area in the Metallurgy Laboratory (beneath the hood and work bench) read about 200 ur/hr. Also, a first floor storage room doorway threshold read about 20 ur/hr.

In the old powder preparation area a reading of 30 ur/hr was obtained for the floor area adjacent.to a pillar supporting a platform previously used to store containers of UO2 Powder.

In the computer room, formerly a part of the pellet pressing and grinding operation, a reading

. of 10 ur/hr was obtained at the base of one of the pillars.

The hallway near the fuel, rod storage area read 25 ur/hr at one location. On the second floor an area in the room previously used for the preparation of UO2 powder, containing a neutron absorber, readings of 30 ur/hr were obtained.

The licensee organized a crew to undertake cleanup of the identified areas exceeding background.

Prior to the completion.

of the confirmatory surveys, the' identified areas of elevated readings were cleaned. NRC resurvey of these areas found contamination levels less than NRC release limits of 5000 dpm/100 cet average alpha contamination and 15,000 dpm/100 a maximum alpha.. Smear samples.were taken to determine if ce the NRC alpha limit for removable contamination (1000 dpe/100 ca ) was also met.'

Subsequent NRC measurement of r

the smear samples gave results less than the NRC limit for removable alpha contamination (See Table 1).

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(2) Enviranatntal Qualificatica 1aboratory (EQL)

(a) Powder Storate Platform An alpha survey of the elevated platform storage area yielded alpha contamination ranging from 1100 to 2

2400,dpm/100 cm. The licensee committed to damp mop the area before our return.the next day. The inspectors resurveyed and found the area much cleaner but were able toidentifythreehotspotsofalghacontaminationat 2

2 1200 dpm/100 cm, 5600 dpm/100 cm and 10,000 dpm/100 cm,

J The licensee recleaned the hot spots reducing them to less 2

than 130 dpm alpha /100 cm.

It was noted that some spaces between adjacent floor plates appeared to be contaminated and needed to be opened. The licensee stated that a welder would cut open the identified platform floor plate junction areas for our measurement during the next inspection.

(b)

Ceiling and Walls The survey of the ceiling and walls in the fuel processing area yielded only background readings of gamma and alpha radiation except on a pillar next to the south wall roll

~up door. An unpainted. surface of the pillar yielded 2

4400 dpa alpha /100 cm. A smear of this area yielded 482 dpm' alpha /100 cm2 as removable contamination which was

~

the highest of the 41 smear samples; hosever, it was still 2

less than the NRC release limit of 1000 dpm/100 cm. The licensee agreed to clean this hot spot prior to our next inspection.

(a) Ventilation Ducting, Pipes and Girders The ducting surveys yielded alpha contamination 2

levels ranging up to 5300 dpm/100 cm on top of the ducting with an average of about 1000 dpm/100 cm2 for

' forty-nine measurement points.

It was apparent, however, that the ducting in the southwest corner of the high bay exhibited higher contamination levels than other' portions of this area. The southwest corner high bay ducting yielded an average alpha t

contamination Ic7el of 2200 dps/100 ca (the range 2

was 900 - 5300 dpa/100 cm ).

The rest of the high bay area yielded an average alpha contamination level of 650 dpm/100 cat (the range was 20 -

2 2400 dpm/100 cm ).

The direct measurements yielded alpha contamination levels less than the NRC limits 2

except for one value of 5300 dpa alpha /100 cm. This level exceeds the NRC release limit of 5000 dpm z

alpha /100.ca. The licensee indicated they would decontaminate this specific location and the nearby acceptable hot spots. The smears taken of the

U ducting in all aracs c2asured less thin tha NRC release limits.

(3) Roof The Micro-R meter survey of the roof area yielded no areas contaminated above the 5 'ur/hr background. The subsequent alpha survey yielded an average alpha contamination level2 of 160 dpm/100 cm and ranged from 10 to 1700 dps/100 cm,

2 Both the direct measurements and the smear samples yielded results less than NRC release limits. The licensee indicated that the metal stand on which alpha contamination was found would be furthe~r cleaned before our next inspection.

Smears of the most contaminated remoyable alpha well 2

areas measured only 160 dpm/100 cm 2 removable.

below the NRC limit of 1000 dpm/100 cm 4.

Confirmation Survey of July 2, 5, 1984 A.

. Survey Instruments Identification No.

Calibration Due Instrument Eberline PRM-7 Micro-R Meter NRC-006383 9/13/84 Eberline PRM-7 Micro-R Meter NRC-008596 9/13/84 NRC-000374 10/25/84 LRL AlphaSurvey Meter LRL Alpha Survey Meter NRC-000375 9/15/84 B.

Areas Surveyed (1) General Resurvey of the reeleaned areas yielded measurements within NRC release limits. The area of the Metallurgical Laboratory that previously measured 200 ur/hr now ceasured background (5 ur/hr). Similarly, the Storage Room door threshold read background as did the base of the pillar in the computer room and the second floor Powder Preparation (neutron absorber addition) room. These areas did not previo'usly exceed NRC release limits for alpha contamination levels.

(2) Environmen3a1 Quality Laboratory (a) Powder Storage Platform The metal floor sections of the elevated platform for powder storage had been partially cut by a welding torch to provide access to the area beneath several plate junctions (plate junctions were on I beam supports).

The survey of the exposed I beam surface areas yielded alpha 2

These contamination levels of 2200 to 7800 dpm/100 cm.

results represented minimum values because the cuts made provided limited access to the surface of the I beams.

The licensee agreed to provide appropriate access for t

o prepar surysying. Thrre days 1cter,. the fifth of July, en i

NRC inspector measured the surface of the properly exposed' I beams in the identified locations and found alpha i

t contamination levels up to 11900 dpm/100 ca.

Cleaning with wet paper readily reduced the alpha contamination 2

i leve,1 to 3600 dpm/100 cm.

i

)

As a result of these measurements the licensee planned to remove the plates and decontaminate both the plates and i

the I beams. The results of the licensee's efforts would be checked during still another inspection.

1 (b) Ceiling and Walls The pillar at the rear roll up door in the EQL had previously met NRC release limits.

Remeasurement indicated no change as a result of the licensee's further cleanup effort.

l (c) Ventilation Ducting, Pipes and Girders The previously identified ' hot spots' were remeasured.

The appearance of the area indicated cleaning had been i

undertaken. Measurements however were largely unchanged.

i These measurements confirm previous. smear sample results which indicated the contamination (within NRC rele'ase limits) was fixed.

~

(3) Roof i

The licensee's effort to reduce the acceptable level of contamination was successful. The previously identified hot spots of 1700 dpm/100 cat were reduced to less than 2

250 dpm/100 cm (well beneath the NRC release limits).

4' 5.

Confirmatory Survey of September 18, 1984 A.

Survey Instruments Instrument Identification No.

Calibration Due l

Eberline PRM-7 Micro-R Meter-NRC-10839 12/28/84 LRL Alpha Survey Meter NRC-000375 2/23/85 B.

Areas Surveyed (1) Environmental Quality Laboratory (EQL)

(3se: Pordet Storage Platform The metal floor plates had been removed from the girder support structure. The plates had been sand blasted.,The W

1

- - +

l survsy of b th sides of tha nine estal plates yieldzd 2

background levels (5 dps/100 cm alpha and 3 ur/hr gamma).

The 1 beams of the supporting structure had been cleaned by grinding. The survey of the I bcams ranged from 2

background to 2400 dpm/100 cm alpha with gamma readings of 2 ur/hr. The contamination remaining from the licensee's clean up was less than NRC release limits and the wipe samples indicated the contamination was fixed.

6.

Conclusion

~

The surveys of Building H indicate that all areas of contamination found have been decontaminated and are well within the NRC release limits. As a' result of these surveys, it is concluded that Building H may be released for unrestricted use. This completes the confirmatory surveys of.the General Electric Company site in San Jose, California that had processed SNM under NRC License SNM-54. Since the areas in Building H, as well as those in Building J have been surveyed and found to meet the NRC guidelines for release as unrestricted use, the NRC License SNM-54 may be terminated.

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Table 1 Results of Wipe Survey (alpha)

Sample Number Location Jpm/100 cm2 A

Roof 1

B Roof 3

.C Roof 6

D Roof 18 E

Roof 35 F

Roof 160 G

Roof 66 H

Roof 3

I Pillar - Computer Room 47 J

Yellow duct port on top of. elevated powder storage ~

46 K

Yellow duct port on top of elevated powder storage 41 L

Top of yellow duct 30 M

Top of light fixture 16 N

Top of light fixture 34 0

Top of elevated powder storage (south wall) 6 P

Top of elevated powder storage (red square) 41 Q

Monorail crane (chain pull) 15 R

Inside yellow duct 10' from wall 144 S'

Cross support near ceiling 40-T.

Outlet. supply air duct (outside surface) 16 U

Large yellow duct (open end-inside) 27 V

Top of white duct at edge of conv. arca 14 W

Pillar supporting ceiling 4

X L beam near ceiling (edge of cony. area) 14 Y

Yellow duct north end (3rd side pipe) 158 Z

North end of white duct (top surface) 0 AA Storage room 1st floor 9

BB Hot spot that measured 8300 dpm and was cleaned to 830 dpm 13 CC Top of white duct.in instrument shop 18 DD I Beam near ceiling instrument shop 12 EE Top 6" pipe in instrument shop 26 FF Light fixture NW corner of instrument shop 54 4

GG White duct (top) NW corner of instrument shop 42 HH Top of 6" water pipe NW corner of instrument shop 91 II Pillar south wall of high bay area at roll up door 482 JJ Met. Lab hot spot 8

KK N. E. corner of Met Lab hot spot 3

Al Cleaned I beam platform floor support BG B1 Cleaned I beam platform floor support BG-C1 Cleaned I beam platform floor support BG DI Cleaned I beam platform floor support BG El Cleaned I beam platform ; floor support BG

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-u GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION.,0F LICENSES FOR BYPRODUCT, SOURCE, ORSPECIALNUCLEARMATERIA0

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U. S. Nuclear Regulatory Co=nission Division of Fuel Cycle and Material Safety Washington, D.C.

20555 i

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July 1982 4'

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o, 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. Tis licits in Table 1 do nct a'pply to premises, equipment, or scrap containing induced radio-l activity for which the radiological considerations pertinent to their use may be differ,ent.

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.

Radioactivity on equipment or surfaces shall not be covered by 2.

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.

The radioactivity on the interior surfaces of pipes, drain lines, 3.

or ductwork shall be determined by making measurements at all traps, and other appropriate' access points, provided that contam-ina' tion at these 1ocations is likely to.be representative of centamination 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 pu,rposes of measurement shall be presumed to be contaminated in excess of the limits.

Upon request, the Commission may authorize a licensee to relinquish 4.

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:

Provide detailed, specific information describing the premises, a.

equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.

Provide a detailed health and safety analysis which reflects.

b.

that the residual amounts of materials on surface areas, I

together with other considerations such as prospective use of-the premises, equipment or scrap, are unlikely to result in an

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unreasonable risk to the health and safety of the public.

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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 the survey report shall be filed with the Division of Fuel Cycle and Eaterial 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.

The survey report shall:

a.

Identify the premises.

b.

Show that reason'able effort has been made to eliminate res.idual contamination.

Describe the scope of the surfey and general procedures c.

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 eonfinm the survey.

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TA0i.5 1 -

ACCEPTABLE SURFACE CONTAMINATION LEVELS NUCLIDE5 AVERAGEbcf HAXIMUHbdf REH0VADLEbcI 8

2 1,000 dem'a/100 cm2 U-nat, U-235, U-238, and 2

15,000 dpm a/100 cm associated decay products 5,000 dpm a/100 cm 2

20 dpm/100 cm2 Transuranics, Ra-226 Ra-220 Th-230. Th-228, pa-231, 100 dpm/100 cm 300 dpm/100 cm 2

Ac-227, 1-125, I-129 2

2 3000_dpm/100 cm2 200 dpm/100 cm

, Th'-nat, Th-232, Sr-90, Ra-223. Ra-224, U-232, I-126, 1000.dpm/100 cm I-131, 1-133 Onta-ganea emitters (nuclides 2

1000 dpm Sy/100 cm2 with decay rodes other than alpha caissinn or spontaneous 5000 dpm sy/100 cm 15,000 dpm By/100 cm 2

fission) except Sr-90 and

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others noted above.

be ta-gama-emi tting

&Where surface contamination by both alpha-and beta-gamma-cmitting nuclides exists, the limits estabilshed for alpha-and nuclides should apply independently, b s used in this table, dpm (disintegrations per minute) means the rate of emissi A

For objects'of less surface area, the average cHeasurements of average contaminant should not be averaged over more than I square meter.

should be derived for cach such object.

The maximum contamination level applies to an area nf not more than 100 cm2 d

2 of surface area should 'be determined by wiping that area with dry filter or sof t ith an appropriate instrument _of CThe amount'of removable radioactive material pcr 100 cm absorbent paper, applying moderate pressure, and assessing the amount of radioactive mate known efficiency.

proportionally and the entire surface should be wiped.

tt h ld not exceed The average and maximum radiation levels associated with surface contaminat i

f I

total absorber.

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FR0 rt 2211

'85.08.12 18se3

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1 1

OU8-43 RADIOACTIVE MATERIAL LICENSE

" " * = '

Supplementary Sheet a...,,,, n g u,,..,,,, ?_1 General Electric Company Nuclear Energy Division 175 Curtner Avenue San Jose, CA 95125 Attention: Andrew H. Lane Radiation Safety Officer License Number 0418-43 is hereby amended in part as follows:

To add:

6.

Nuclide

7. Form 8

Possession limit J.

Plutonium-239:Deryllium J.

Sealed sources J. and K.

See Condition 17-or Plutonium-238 equivalent K.

Uranium 233/235 K.

Any 9.

Au_thorized use:

J.

To be used for research and development as defined in Section 30175(j) of California Radiation Control Regulation in materials testing.

K.

To be used for research and. development as defined in Section 30175(j) of California Radiation Control Regulation in the manuf acture of instrumenta-tion for distribution to authorized recipients.

13. (c) The letter dated May 17, 1982 as modified by the letter dated August 18, 1983 (with attached facility sketch) and the letter dated July 22, 1985 (reference to Building J.),

all signed by G.

E. Cunningham.

17.

The total mass of special nuclear material possessed under this license at any one time and at any one authorized location shall not exceed that stated in the following formulat The number of grams of Uranium-235 divided by 350, plus the nunber of grams of Uranium-233 divided by 200, plus the number of grams of plutonium (all isotopes) divided by 200, shall not exceed one (i.e. unity).

For the State Department of Health Services July 23, 1985 Date by

,,, Ra'diologic Health Branch RH 2SS R (2/92) 714 P Street, Sacramento. CA 95814 2

I