ML20134Q001

Insp Rept 99990001/97-01 on 970114.No Noncompliance Noted. Major Areas Inspected:Organization,Activities & Review of Facility Contamination Incident

ML20134Q001
Person / Time
Issue date:	02/18/1997
From:	Johansen J, Duane White NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20134P964	List: ML20134P961 ML20134Q001
References
REF-QA-99990001-970218 99990001-97-01, 99990001-97-1, NUDOCS 9702260198
Download: ML20134Q001 (36)

Text

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U.S. NUCLEAR REGULATORY COMMISSION l

REGION I i

1 INSPECTION REPORT Report No.

99990001/97-001 l

)

Docket No.

99990001 l

License No.

Om. O License Licensee:

GE Weldina and Machinina Services 302 Hansen Access Road Kina of Prussia, PA 19406 Facility Name:

GE Technical Service Center inspection At:

302 Hansen Access Road Kina of Prussia PA l

Inspection Conducted:

January 14,1997 N3wd Af/T[77 Inspector:

cut c%

Duncan White date Senior Health Physicist i

Approved By:

11/kk Leh4u-

//3

)

J4nny M//Joh/np6n, Chief

/ dats fMaclear Materials Safety Branch 3 Division of Nuclear Materials Safety i

inspection Summarv: Special announced safety inspection conducted on January 14, 1997 (Inspection Report No. 99990001/97-001).

j Areas inspected: Organization and scope of activities; review of Peach Bottom contamination incident; independent measurements; and actions taken by licensee.

Results: No violations were identified. One drum containing welding cables was identified with elevated radiation levels. The licensee shipped this drum to their licensed facility in Memphis, Tennessee to identify the cause of the elevated radiation levels.

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L RETURN ORIGINAL TO REGION I 9702260198 970218 REG 1 GA999 ENVGENE 99990001 PDR

DETAILS i

1.

Persons Contacted i

• Eric Tschantre - GE Facilities Manager for King of Prussia facility Joseph Plantz - GE Mission Manager for King of Prussia facility Joseph Livingstone - GE representative for Peach Bottom and Limerick (by telephone)

Hal Trimble - Radiation Protection Manager, Peach Bottom Atomic Power Station (by telephone) i

• present at exit interview 2.

Oraanization and Scope of Activities The General Electric (GE) Technical Services facility in King of Prussia is the field i

services center for GE's welding and machining group. The facility dispatches approximately 30 welding systems and plus 20 to 30 other machining tools to client facilities around the world. The welding systems are primarily used in i

nuclear power plants due to the system's ability to be remotely operated and controlled with the aid of video cameras. The welding systems consist of three primary components: the power supply, cables and welding head.

The King of Prussia facility does not hold a license for radioactive materials.

Equipment used at nuclear facilities are surveyed at the client's plant for release for unrestricted use. GE's facility in Memphis, Tennessee has an Agreement State licensee which permits radioactive contaminated equipment on-site. Welding units used outside the United States and units from domestic facilities that are not surveyed are first sent through the Memphis facility prior to shipment to King of Prussia.

The King of Prussia facility has utilized the health physics staff from GE's Nuclear j

Energy Production facility in Wilmington, North Carolina to perform two radiation surveys. These surveys of the King of Prussia facility were performed on March 29,1996 and September 23,1996. The results of these surveys are found in and 2 of this report.

The surveys performed by GE's Wilmington staff and the diversion of equipment through their Memphis, Tennessee facility was in response to GE's concern that welding equipment with radiological contamination was found on their equipment from an overseas location and the GE's clients requiring that equipment bought into their facilities have no radiological contamination.

No safety concerns were identified.

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Inspection Report No. 99990001/97-001 l

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3. Haview of Peach Bottom Contamination Incident

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i On November 22,1996, a GE technician was cleaning out the drawer of power supply unit in the King of Prussia facility that was previously used at PECO's l

Peach Bottom Nuclear Generating Station during September 1996. ~One of the items inside the drawer was a plastic bag marked as radioactive. The bag contained two gaskets for the welding head. GE contacted PECO and a health l

physics supervisor was dispatched to the King of Prussia facility. In addition to the contaminated gaskets, the PECO survey identified several tools in the drawer l

to be contaminated. Survey of personnel and other areas of the GE facility did not identify the presence of radiological contamination. The contaminated gaskets and tools were returned to Peach Bottom. A summary of the PECO survey is i

found as Attachment 3 to this report.

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The GE representative stated that the power supply unit was located inside a contaminated zone while at Peach Bottom due to the limited floor space. The power supply for the welding head is normally maintained outside the contaminated zone with only the cables and the welding head located inside contaminated zone'. According to PECO the power supply were taken to the refueling floor but not used at Peach Bettc.m. The power supply was released from Peach Bottom on September 27,1996.

i The release of the power supply for the welding system from the contaminated

. area at Peach Bottom is still under review by PECO and Region l's Division of Reactor Safety. The inspector noted that the contaminated tools and bag were located in a drawer that according to the GE representative, is used as a work surface. The drawer, when opened, has a cover that hides the contents in the drawer from view and facilitates it use as a work surface it is only when the cover is lifted, that the contents of the drawer can be seen.

No safety concerns were identified.

4.

Independent Measurements i

The inspector surveyed the work and storage areas of the Technical Center with a i

Ludlum Model 44-10 5 centimeter (cm) by 5 cm Nal(TI) detector coupled to a Luditm Model 2221 ratemeter/ scaler (NRC Serial No. 054828) last calibrated on March 14,1996. The detector used by the inspector is capable of detecting gamma photons with energies with energies greater than 100 kev at or near environmental levels. The average background for this detector is 7,000 to 10,000 counts per minute (cpm).

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I Inspection Report No. 99990001/97-001 1

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.. -. - -. - - _. - - - _ -. -.... -. -.. - -. -... ~

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Wipes of removable contamination wipes were also taken at various locations y

around the facility.. Each wipe covered an area of approximately 100 square centimeters. Each wipe was counted for 10 minutes on a Tennelec Model LB5100 low background alpha / beta counter at the Region I offices. The counter's l

l efficiency for gross alpha and gross beta was 21.1% and 26.5%, respectively.

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f The radiation survey of the facility identified one drum with elevated gammri l

radiation levels. All other equipment, work and storage areas had background radiation levels. The drum with elevated radiation levels (marked as "CS-40-13")

contained cables used to connect the power supply to the welding head. The l

inspector identified one spot on the drum with a maximum reading of 27,000 l

l cpm. The elevated radiation levels were isolated to the one area of the derm 1

l All wipes taken at the facility did not indicate the presence of removable j

contamination. The results of the wipes are listed in the table below. Results are reported in units of disintegration per minute per 100 square centimeters (dpm/100 cm') at an unceit.',ty of one sigma.

Location Gross Alpha Gross Beta

.i Drum No. CS-40-13; hotspot

' 1.4 i 1.1 Oi3 l

Drum No. CS-40-13 180 degrees from hotspot 0 i 1.7 0.4

• 3 l

Drum No. CS-40-13; lid 1i1

-0.4 i 3 l

i Drum No. CS-40-22 1.411.1

-2 i 3 j

Shipping Container No. 2 1.4 1.0

-0.4

• 3

')

l Shipping Container No. 3 2.8 1.3 0.4 i 3 t

Welding Power Supply I

Serial No.1179 111 4t5

}

Welding Power Supply Serial No. 839 1.4 i.1

-3 i 3 i

Welding Power Supply Serial No.1022 111 1i3 Loading dock ramp 1i1

-1 i 3 i

i Shipping area floor

-5 5

0 3

Floor near CSi40-13 4

1

-0.4

• 3 I

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i Inspection Report No. 99990001/97-001 l

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Actions Taken by Licensee

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i As a result of the findings of this inspection and previous incidents, the general l-licensee has taken the following steps in response to the increase occurrences of i

i radiological contamination on the welding and machining equipment.

j a.

Welding units used outside the United States and units from domestic facilities that are not surveyed are first sent through the Memphis facility prior to j

}

shipment to King of Prussia.

l b.

Bar codes affixed to the exterior of shipping containers to track the movement i

i of equipment between client facilities.

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l c.

Two radiation and contamination surveys in 1996 of the King of Prussia i

facility by GE's health physics group from the Wilmington, North Carolina facility.

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d.

Purchase of radiation survey equipment for use at the King of Prussia facility.

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{

e.

Development of procedures and training of King of Prussia personnel to use survey equipment by GE's Wilmington health physics group.

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The drum identified during this inspection with elevated radiation levels was j

shipped by' commercial carrier as a limited quantity package to GE's Memphis i

facility for evaluation. The evaluation identified fixed Cobalt 60 contamination on two of the cables in the drum. The results of the licensee's survey are i

found in Attachment 4 of this report.

The inspector reviewed the actions taken by the general licensee and determined that they would minimize the potential for the spread of radioactive materials and inadvertent exposure of personnel at the King of Prussia facility.

No safety concerns were identified.

6.

Exit Interview The inspection findings were discussed with the individual identified in Section 1 of this report.

Inspection Report No. 99990001/97-001

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ATTACHMENT 1 i

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l RADIOLOGICAL SURVEY PERFORMED BY GENERAL ELECTRIC ON MARCH 29,1996 t

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Inspection Report No. 99990001/97-001 l

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OfMacdoarEnery Generaf BeeMe Company, MC N00 P. O. Bou 180, nenheten NC 2N02 010 676-6631 Apdl2,1996 l

l S. P. Morrey, Manager Nuclear Safety i.

l

Subject:

Elam af Prussia TSC Health Physics Suw Per your instrusions, a survey of the KOP TSC was perfonned on 3/29/96 by R. G. IAwis. Using two GM survey instr==*aan, a series of dose rate and contan=l==alam checks were perfonned in accordance with accepted GENE practicas and action levels. All iteens surveyed displayed backgreemd activity levels.

These was no hint of any radiation / contamination on any items checked. I've tecluded neanchmiaans which speciAcally describe the serveys perienmed. Please note that 37 " product" ra=*a3==es waso surveyed Additionally, people, agolpement, tools and a variety of other items were also cheded. At the conclusion of my survey, I notiSed E. Tschantre that his Pacility and iteens within were " clean" and teleased Additlemally, I would like to thank Eric and his stafYfor the help and courtesy I received while at TSC.

Post-it* Far Note 7671 c.=ggg jg> y

'* bis SeAAnfr4-

$4 lia// C W

Co.

R. G. IAwis Nuclear Safety Fe ve I

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I SERVICES FACILrrY

" SRM2004fP210 BKO-115 C/M - BFF = 13%

CAL DATB: 12/5/95 l

ASP 1/HP260 BKG =.02 awh/h CALDATB 11/7/95 l

B 520/HP270 BKG =.04 aw/hr CAL DATB: ll/7/95

(= 2 300 cpnt) 4 CONTAIMER #

MB/HR St CONTACT CPM Sv CONTACT GMBy SWIPE I

BKG BKG BKG l

2 BKG BKG BKG 3

BKG BKG BKG i

4 BKG BKG BKG 5

BKG BKG BKG 6

BKG BKG BKG 7

BKG BKG BKG 8

BKG BKG BKG 9

BKG BKG BKG 10 BKG BKG BKG 11 BKG BKG BKG 12 BKG BKG BKG 13 BKG BKG BKG l

14 BKG BKG BKG 15 BKG BKG BKG 16 BKG BKG BKG 17 BKG BKG BKG i

18 BKG BKG BKG l

19 BKG BKG BKG 1

20 BKG BKG BKG 21 BKG BKG BKG 4

l 22 BKG BKG BKG 4

23 BKG BKG BKG j

24 BKG BKG BKG 25 BKG BKG BKG 26 BKG BKG BKG 27 BKG BKG BKG 24 BKG BKG BKG l

29 BKG BKG BKG 30 BKG BKG BKG 31 BKG BKG BKG 32 BKG BKG BKG 33 BKG BKG BKG 34 BKG BKG BKG 35 BKG BKG BKG 36 BKG BKG BKG 37 BKG BKG BKG PIISCELLANEOUS TTEMS SURVEYED 36" Guide Rings Wold Head 2 Fork LiAs Tool Bones Heliarc Wonder Main Floor Areas MezzanineFloor Areas Gang Bones / containers

" Blue" plastic d ums Storags Racks - Upstairs & Downstairs Shipping Bay Elecaronic Shop (1)Bmployes; Handling containers

• All Swipes and Direct Randings = BKG

" Swipes rechecked at GB Wilmington R.o.lma 4ns

SERVICES FACILITY 1

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Arc Wehlers 1

i Rads Electronic Shop Tool Bones j

Park LiA Gang Boxes Ploor Areas (25) Boxes j

/

Box Queue Mezzanine j

Bay storay Racks i

Fork LIA Bones Blue Mastic 4

(12)

Dmans i

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n.o. w sn m

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ATTACHMENT 2 l

RADIOLOGICAL SURVEY PERFORMED BY GENERAL ELECTRIC ON SEPTEMBER 23,1996 l

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inspection Report No. 99990001/97-001

GE NuclearEnergy NUCLEAR ENERGY PRODUCTION RADIATIONPROTECTION MCH96 P. O. Box 780, Wilmington, NC 28402 i

cc: B. Robinson A. Mabry J. Sependa D. Barbour E. Tschantre-KOP E. Rouse 24 September 1996 L. Paulson Acting Manager Nuclear Safety Subject King of Prussia TSC Health Physic Survey A survey of the KOP TSC was performed on 9/23/96 by R. G. Lewis and E. L. Rouse.

Using GM survey instruments, dose rate measurements were perfomied Contamination swipes were also taken.

Items and areas surveyed included equipment, shipping containers, equipment in the containers, shop areas and personnel All items surveyed were within GENE criteria for " Unconditional Release". Attachments are included describing the specific surveys performed.

At the conclusion of the surveys, E. Tschantre was notified that his facility and items were

• Clean and Released". All actions were reviewed with the Wilmington H. P. Staff.

R. G. Lewis Nuclear Safety

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KING OF PRUSSIA SERVICES FACTI ITY Scalar SRM200/RD14 BKG=4.0 C/M - EFF = 29%

CAL DATE: 9/21/96 i

E-520/HP270 # 967 BKG = 0.05 to 0.06 mr/hr CAL DATE: 6/6/96 E-520/HP270 #1196 BKG =.04 mr/hr CAL DATE: 6/6/96 RM14/HP210 #1303 BKG = 60 cpm CAL DATE: 8/7/96 ITEMS SURVEYED RTEULTS h

h Cantact Swipe a Swine

• 3 Boxes and contents to Peachbottom BKG BKG BKG Fork Lift BKG BKG BKG Plastic Drums to Oyster Creek and Nine Mile Point BKG BKG BKG Penonnel BKG BKG BKG i

4 Welders BKG BKG BKG Facility Floors BEG BKG BKG Mezzanine Areas BKG BKG BKG 32 Drums / Rows of boxes on memnine BKG BKG BKG l

Shipping Bay BKG BKG BKG Forsmark Containers BKG BKG BKG Gang Boxes BKG BKG BKG Job Box from Hake BKG BKG BKG Electronics Shop BKG BKG BKG Miscellaneous Equipment BKG BKG BKG

• Box #33 to Peachbottom had one reading of 0.12 mr/hr e contact. Still within GENE guidelines for free release.

" The above surveys consist of hundreds of contact readings and swipes taken.

R. G. Lewis E. L. Rouse Nuclear Safety Radiation Protection

AREA SURVEY l

(Continued) 4 i

Gang Boxes Job Box Frtem Hake 1

Arc Storage Parts Area 3 Plastic Forsmark Welders m

g 2

BKG

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Weld Test Storage

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Area Contact 3

BKG Floor Areas 4

4 Menanine Level Fork Lift Omce ares Upper and Lower Bay Storage Area Storage Racks l

MAIN SHOP AREA ARC Weld Repair Ana Box Blue Drians Boi Fork Lift 13 _BKG i

Storage Parts Area Misc BKG Boxes Gear Box Misc to PeachBottom

)

KG 0.05 mr/hr Weld Tes' Storage Area Arc Welder

- 0.05 mir/br BKG Inside Arc Weider #2 4.1 anr/hr -

i Mezzanine Levei Fork Lift Omce area Upper and lower

~

Bay l

l Storage Area Storage Racks i

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ATTACHMENT 3 t

RADIOLOGICAL SURVEY PERFORMED BY PECO ON NOVEMBER 22,1996 i

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@ 007 REPORIS ruk GPECTRUN 2496.

22-NOV-199G 19:58 AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA A

A A

GAMMA SPECTRUM ANALYS IS A

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AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CANBrkkA APUUliE V3.2 Canberra Industries, Inc.

22-NOV-96 19:59: 09 ANALYS 1S PARAMEIERS Spectrum file number

2496.0 Sample no.

2496.0 MCA unit number 1

ADC unit number 1.0 Detector number 1./

Geometry number 1/

Search threshold 1 3.0 Search threshold 2 3.0 Search FROM channel 100 Search TO channel

4090 Id energy tolerance 1.0 Order of background

linear Smoothing factor 0

Esodom sum corr

disabled GRA parameter 1

Baseline channels

disablod Confidence levels LLD :

1.64b (95.0%)

MDA :

1.64b (95.0%)

Analysis library

SPF$ LIBRARY:SPFANL.110 /

Background subtract

disabled

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Sample description

GMEAR Analyzed by: BDM SCREWDRIVER G.E.

T E Cil. ILR.

f-Sample sine 1.000000E+00 EACH

'Conv. factor 1.000 Standaru sine 1.000000E+00 EAC

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Sample taken on

22-NOV-96 at 19:47:35 Collect started on

22-NOV-96 at 19:47:35 Decay time 0.0 minutes f

live time 600.0 seconds real time 600.0 seconds dead time 0.00 %

Energy calibration used done on 12 / 15 / 1995 Efficiency calibration used done on 12 / 21 / 1996 d# of coSE Ieo C

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01/03/97 FRI 13:06 FAI 1 717 456 3574 HEALTH PH1* SICS

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AAA PEAK F IT R E P O P. T AAA 22-NOV-96 19:58:09 pesh nuclide(s) centroid energy FWHH net area error s a nim a s arro no.

channel kev kev counts per second

+

l 1 GA 72 KR-88 1669.40 034.64 1.50 93.3 10.74 27.6 11.1 MN-S4 2 CD-60 2346.90 1173.34 1.60 57.6 13.81 23.8 14.0 3 CO-60 2665.25 1302.49 1.97 47.0 15.26 21.8 15.5

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,.01/03/97 FRI 13:56 FAI 1 717 456 3574 HEALTH PHYSICS

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SHEAR Analynod by

BDM number nuclide conf.value ---------- Activity (

uCi/SACH )

measured decay corrected a

+

i

1. Fission gases total 0.0000E+00 total 0.0000E+00 2.

Iodines total 0.0000E+00 total 0.0000E+00 3.

Particulates 1

MN-54 0.9943 7.4667E-04 +-1.83E+01% 7.4667E-04 +-1.83E+01%

2 CD-60 0.9975 6.1667E-04 +-1.72E+01% 6.1667E-04 +-1.72E+01%

total 1.3633E-03 total 1.3633E-03

/

Errors quoted at 1.650 sic 3ma ( 90.17. )

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,01/03/97 FRI 13:57 FAI 1 717 458 3574 HEALTH PHYSICS

@ 010 REPORTS FOR SPECTRUM 2497.

22 -N O V-l 'J 9 6 20: 03 AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA A

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GAMMA SPECTRUM ANALY0 1S A

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AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CANBERRA APOGEE V2.2 Canberrt Industries, Inc.

22-NOV-96 20:02:53 A HALYS IS PARAM EIER5 Spectrum file number

2497.0 Sample no.

2497.0 MCA unit number 1

ADC unit number 2.0 2/

Geometry number 1s Detector number Search threshold 1 2.0 Search threshold 2 3.0 Search FROM channel 100 Search Tu channel

4095 Id energy tolerance 1.0 Order of background

linear Smoothing factor 0

Random sum corr

disabled GRA parameter 1

Baseline channels

disabled Confidence levels LLD :

1.64b (95.0%)

MDA :

1.645 (95.0%)

Analysis library

SPFiLIBRARY:SPEANL.110 #

Background subtract

disabled r Samplo description

SHEAR /

Analy::ed by: BDM SCREWDRIVER CASE G.E.

TLR.,

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Conv. factor 1.000 Standard sine 1.000000E+00 EAC Sample taken on

22-NOV-96 at 19:52:18 '

Collect started on

22-NOV-96 at 19:52:10 Decay time 0.0 minutes f

live time 600.0 seconds real time 600.0 socond=

dead time 0.00 %

Energy calibration used done on 1 /

2/ 1996 Efficiency calibration used done on 1 / 11 / 1996 A

. 01/03/97 FRI 13:08 FAI 1 717 456 3574 HEALTH PITYSICS

@ 011 AAA PEAK F IT REPORT AAA 2 2 --flu V-96 20:02:03 peak nuclide(s) centroid energy FWHH not area error gammas erro no.

channel kev kev counts per second

+

1 HR-08 HN-54 1670.02 035.08 1.67 237.3 6. 6 'J 44.0 7.2 2 CD-60 2347.25 1173.71 1.94 88.6 11.16 22.8 11.4 3 CD-60 2665.40 13"2.78 3.05 82.4 11.49 24.0 11.0 i

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01/03/07 FRI 13:58 FAX 1 717 456 3574 HEALTH PHYSICS

@ 012 1

AAA RAD IONUCL IDE EEPORI AAA 32-HOV-96 20:02:53 Sample description

SMEAR Analyned by

BIJM nuta b er nuclide conf.value ---------- Activity (

uCi/CACH )

measured decay corrected

+

1.

Eission gases total 0.0000E+00 total 0.0000E+00 2.

Iodirius total 0.0000E+00 total 0.0000E+00

3. Particulates 1

MN-54 0.9899 1.1901E-03 +-1.19E+01% 1.1901E-03 +-1.19E+01%

2 CD-60 0.9491 6.3121E-04 +-1.36E+01% 6.3121E-04 +-1.36E+01%

total 1.8313E-03 total 1.0213E-03

/

Errors quoted at 1.650 sigma ( 90.1% )

1

i

'01/03/97 FRI 13:58 FAI 1 717 456 3574 HEALTH PHYSICS

@ 013 REPORTS FOR SPECTRUM 2506.

22-NOV-1996 21:49 AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA l

A A

A GAMMA SPECTRUM ANALYS IS A

A A

AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CANBERRA APOUEE U2.2 Canberra Industries, Inc.

22-NOV-96 21:49:21 I

A NALYS IS PARAMETERS Spectrum file number

2b06.0 Sample no.

2506.0 MCA unit number 1

ADC unit number 2.0 Detector number 2/

Geometry number l'

/

s Search threshold 1 2.0 Search threshold 2 3.0 Search FROM channel 100 Search 70 channel

4095 Id energy tolerance 1.0 Order of bacle.9round

linear Smoothing factor O

Randoni sum corr

disabled GRA parameter 1

Basoline channels

disabled i

Confidence levels LLD :

1.G45 (95.0%)

MDA :

1.64b (95.0%)

Analysis library

SPF$ LIBRARY:SPFANL.110 '

Background subtract

disabled

/

Sample description

SMEAR /

Analyr.ed by: B Dt1 20000 CPM gg Sample size 1.000000E+00 LACH

'Cenv. factor 1.000 59,andard size 1.000000E+00 EAC Sample taken on

22-NOV-96 at 21:15:00

Collect started on

22-NOV-96 at 21:28:35 Decay time 23.6 minutes

~

live time 600.0 seconds real time 607.0 seconds dead time 1.15 %

F.nergy calibration used done on 1 /

2/ 1996 Efficiency calibration used done on 1 / 11 / 1996 k

V J

01/03/97 FRI 13:59 FAI 1 717 456 3574 HEALTH PHYSICS

@ 014 AAA PEAK F IT REP 0RT AAA 22-NOV-96 21 49:21 peak nuclide(s) centroid energy l'W H H net area error g ainin a s erra no.

channel kev heV counts per second

+

1 BA-140 847.97 424.00 0.01 61.3 47.51 5.9 47.6 2 W-187 960.78 480.42 0.91 71.8 42.05 7.7 42.2 3 I-132 1013.08 506.57 0.76 9.4330.67 1.1330.6 4

1145.63 572.85 1.29 134.0 26.87 17.2 27.1 5 AG110M RB-89 1316.37 658.23 1.28 170.0 18.24 26.2 18.5 6

1503.96 752.04 1.17 16.5132.18 2.8132.2 7 CO-58 1621.84 310.99 1.46 193.1 13.15 34.8 13.4 0 GA-72 KR-88 1669.96 835.05 1.56 4b069.4 0.48 8361.0 2.8 MN-54 9 I-134 AG110M 1769.48 084.01 1.67 151.6 15.60 29.7 15.0 10 1810.04 905.09 1.39 42.7 51.09 8.6 51.1 11 2060.97 1030.b6 1.39 45.1 41.77 10.3 41.8 12 EE-S9 2199.22 1099.69 1.79 99.5 20.70 24.1 20.9 13 ZN-65 2231.44 1115.80 1.72 916.2 3.92 22b.0 4.6 14 CD-60 2346.78 1173.47 1.79 961G.9 1.04 2478.3 2.8 15 FE-59 2b33.43 1291.80 2.06 71.0 14.31 20.0 14.5 16 CO-60 2665.47 1332 01 1.93 8704.8 1.08 2630.3 3.0 s

1 l

l i

i W

,01/03/97 FRI 13:59 FAI 1 717 456 3574 HEALTH PHYSICS

@ 015 1

AAA RAD 10NUCL IDE REPORT AAA 22-NOV-96 21:49:21 Sample description

SMEAR Analyzed by

BDH number nuclide conf.value ---------- Activity (

UCi/EACH )

measured decay corrected

+

1.

Eission gases total 0.0000E+00 total 0.0000E+00 2.

Iodines total 0.0000E+00 total 0.0000E+00 3.

Particulates 1

MN-54 0.9923 2.2599E-01 +-4.75E+00% 2.3600E-01 +-4.75E+00%

2 CO-58 0.9917 9.4540E-04 +-2.22E+01% 9.4555E-04 +-2.22E+01%

3 EE-59 0.8933 1.2169E-03 +-1.98E+01% 1.2172B-03 +-1.98E+01%

4 CO-60 0.9725 6.7620E-02 +-3.41E+00% 6.7628E-02 +-3.41E+00%

5 ZN-65 0.9872 1.1993E-02 +-7.73E+00% 1.1993E-03 +-7.73E+00%

6 AG-110M 0.1999 8.8915E-04 +-2.03E+01% 8.8919E-04 +-2.03E+01%

total 3.0867E-01 total 3.0868E-01

/

These peaks were not identified number channel energy peak intensity (9ps)

+

1 848.0 424.00 5.856bH+00 +-

78.56% BA-140 2

960.0 400.42 7.73?6E+00 +-

69.62% W-187 3

1013.1 506.57 1.0629E+00 +- 545.64% I-132 4

1145.6 572.85 1.7160E+01 4-44.76%

6 luo4.0 762.04 2.7bl4E+00 +- 218.15%

10 1810.0 905.09 8.5590E+00 +-

84.40%

11 2061.0 1030.b6 1.0264E+01 +-

69.05%

V Errors quoted at 1.G50 sigma ( 90.1% )

l

01/03/97 FRI 14:00 FAI 1 717 456 3574 HEALTH PHISICS

@ 016

~

1 REPORTO TUR SPECTRUM 2007.

22-NOV-1995 21:50 A AAAAAAAA AAAAAAAAAAAAAAAAAAAA A AAAAA AAAAA AAAA AAAAAAAA A AAAAAAAAAAAAAA AAAAAAAAAAAA A

A A

GAMMA SPECTRUM ANA LYS IS A

A A

AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CANBEkRA APOGEE V2.2 Canberra Industries, Inc.

22-NOV-96 21:bo:16 ANALY S IS PARAMETERS Spectrum file number

2bO7.0 Sample no.

2507.0 MCA unit number 1

ADC unit nunber 1.0 Detector number 1s' Geometry number 1,-

/

Search threshold 1 2.0 Search threshold 2 3. 0,/

Search FROM channel 100 Search 10 channel

4095 Id energy tolerance 1.0 Order of background

linear Gmoothing factor 0

Random sum corr

disabled GRA parameter 1

Baseline channels

disabled i

Confidence levels LLD :

1.64b (96.0%)

MDA :

1.645 (95.0%)

Analysis library

SPE$ LIBRARY:SPEANL.110

Dschground subtract

disabled l

Sample description

SMEAR Analyzed by: BDM 4000 CPM

/

but

~.

Sample si=e 1.000000E+00 EACH Conv. factor 1.000 Standard size 1.000000E+00 EAC Sample taken on

22-NOV-96 at 21:15:00 [1 Collect started on

22-NOV-96 at 21:39:26 Decay time 24.4 minutes

f live tima 600.0 seconds real time 607.0 seconde dead time 1.15 %

Energy calibration used done on 12 / 15 / 1995 Efficioney calibration used done on 12 / 21 / 1995 4

01/03/97 FRI 14:00 FAI 1 717 496 3574 HEALTH PHYSICS

@017 AAA PEAK

?IT REPQRI AAA 22-NOV-95 21:50:16 peak nuclide(s) centroid energy fWHM net area error g a mia a s erro i,

no.

channel kev kev counts per second

+

t 1 1!6-139 CE-139 331.00 165.49 0.64 36.7 80.75 2.3 80.6 2

900.82 450.38 0.84 75.5 40.63 12.1 40.6 3 CD-DS 1622.00 810.93 1.63 141.6 lb.78 40.7 16.0 4 GA-72 KR-88 1669.73 834.80 1.44 42743.6 0.49 12646.9 2.8 MH-54 5

2016.15 1008.00 1.28 32.5 54.45 11.6 54.S G FE-59 2198.93 1099.08 1.86 102.2 18.94 39.6 19.1 7 ZN-65 2231.16 1115.48 1.70 315.9 7.90 124.0 8.3 0 CO-60 234G.47 1173.13 1.67 8029.8 1.14 3008.9 2.8 9 EE-59 2b83.59 1291.67 1.70 53.5 16.63 24.1 16.8 10 CD-60 2665.14 1332.44 1.74 7224.5 1.18 3358.0 3.0

>/

i l

l I

l l

l

01/03/97 FRI 14:00 FAI 1 717 456 3574 HEALTH PHYSICS 0018 1

AAA RAD I O N U C I, IDE REPQRI AAA 22-NOV-96 21:50:16 Gample description

SMEAR Analyued by

BDH nuinber nuclide conf.value ---------- Activity (

uCi/EACH ) ----------

measured decay corrected o

1.

Fission gases total 0,0000E+00 total 0.0000E+00 3.

Iodines Lotal 0.0000E+00 total 0.0000E+00

/

g f g Nk O

g b

,7 3.

Particulates 1

MN-54 0.9999 3.422bE-01 +-4.7GE+00% 3.422GE-01 +. 761+00%

1.1071E-03 +-2.65E+01% 1.1073E-03

+-2 65E+01%

2 CD-$8 0.9919 1.6377B-03 +-2.10E+01% 1.6381E-03 +ys,.10E+01%

3 FE-09 0.9303 4

00-60 0.9984 9.0044E-02 +-3.47E400% 9.0044E-02/+-3.47E+00%

5 ZN-65 0.9990 G.6111E-03 +-1.37E+01% 6.6114E-03 +-1.37E+01%

total 4.4165E-01 total 4.4166E-01 V

i These peaks were not identified number channel energy peak intensity (sps)

+

1 331.0 165.49 2.310SE+00 +- 133.39% BA-139 CE-139 3

900.9 450.38 1.2114E+01 +-

67.10%

5 2016.2 1000.00 1.1565E+01 +-

89.93%

4 Errore quoted at 1.650 sigma ( 90.1% )

_ _ _ _. _ _ _. _. __. _. -_._.. _.. _...._j.__._.._._.._._.

_ _ _.. _ _. ~. _

01/03/97 FRI 14:01 FAI 1 717 456 3574 HEALTH PHYSICS Q1019 Contaminated items Found at General Electric 4

October 1,1996 l

IIEMS DIRECT FRlSKED ltem Descriotion

. Contamination Level (dom)

Conversion Factor Activity (uCl)

Channel Lock Vise Grips 2800 4.51E-07 1.26E-03 Needle Nose Pliers 6000 4.51E 07 2.70E 03 j

Flashlight (Ma0enta) 1400 4.51 E-07 6.31E-04 Snips with Tape 14000 4.51E-07

,8.31E-03 Brass Components 0200 4.51 E-07 9.91 E-04 i

RTV Sealant 2000 4.51E-07 9.01E Crescent Wrench 2800 4.51E 07 1.26E-03 j

Hex Head

4000, 4.51E-07 1.80E-03 Wood File 3000 4.51E-07 1.35E-03 TOTAL 1.72E-02 I

l SMEARQ Smear Number Lem Smeared Activity (uCi) l 1

Screwdriver 1.36E 03 2

Screwdriver Case ~

1.82E-03 3-Gasket 3.09E-01 4

Gasket 4.42E-01 TOTAL 7.54E-01 i

Total Activity. Tools and Smears 7.71E-01 i

d If 4

1 i

4 i

W

01/03/97 FRI 14:01 FAX 1 717 456 3574 HEALTH PHYSICS

@ 020 4

a ISOTOPIC ANALYSIS OF SMEARS AT GENERAL ELECTRIC October 1,1996 SMEAR 1 - SCREWDRIVER ISOTOPE Activity (uCi) 10 CFR 20 LIMIT

% OF LIMIT LtLCD MN-54 7.47E-04 1.00E+02 7.47E 04 CO-60 6.17E-04 1.00E+00 6.17E-02 TOTAL 1.36E-03 6.24E-02 4

SMEAR 2 - SCREWDRIVER CASE ISOTOPE Activity (uCI) 10 CFR 20 LIMIT

% OF LIMIT

[u,C.D MN-54 1.19E-03 1.00Et02 1.19E-03 CO-80 6.31 E-04 1.00E+00 <

6.31E-02 TOTAL 1.62E-03 6.43E-02 SMEAR 3 - GASKET ISOTOPE Activity (uCl) 10 CFR 20 LIMIT

% OF l lMIT i

Lu!.CQ MN-54 2.26E-01 1.00E+02 2.26E-01 CO-58 9.46E-04 1.00E+02 9.46E-04 FE-59 1.22E-03 1.00E+01 1.22E-02 CO-60 6.76E-02 1.00E+00 6.76E+00 ZN-65 1.2CE-02 1.00E+01 1.20E-01 AG-110 8.69E-04 1.00E+01 8.89E-03 TOTAL 3.09E-01 7.13E+ 00 SMEAR 4 __ GASKET ISOTOPE Activity (uCl) 10 CFR 20 LIMIT

% OF LIMIT E

MN-54 3.42E-01 1.00E+02 3.42E-01 CO-58 1.11E-03 1.00E+02 1.11 E-03 FE-59 1.64E-03 1.00E+01 1.64E-02 CO-60 9.00E-02 1.00Et00 9.00E+ 00 ZN-65 6.61 E-03 1.00E+01 6.61 E-02 TOTAL 4.42E-01 9.43E+00

-. - ~..

i i

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ATTACHMENT 4

[

RADIOLOGICAL EVALUATION OF DRUM PERFORMED BY GENERAL ELECTRIC f

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Inspection Report No. 99990001/97-001 i

'~'

i tu a m a mt cc g,

7 GE-NUCLEARENERGY

'9 1790 DOCK STREET MEMPHIS, TN 38113 Rich Jones -

901)774-1922 Dial Comm: 8*964-4003 Joe Davidson -

901)774-1415 Dial Comm: 8*964-4005 l

Larry Hawkins -

901)774-1238 Dial Comm: 8*964-4004 l

l.

Bobby Newell-901)774 9322 DialComm: 8*964-4001 Cassandra Forby - 901)774-9328 Dial Comm: 8*964-4002 j

Bob Langford-901)774-9370 Diel Comm: 8*964-4000 i

Fax #: 901)774-9517 DialComm: 8*964-4200 I

FAX COVER SHEET l

Date:

3 I t a l 91 Number of Pages (including cover sheet) d TO:

fii c_ %h-ene.e G K..o.7.

PROM:

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w. hotr s COMMENTS: H w - is_

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Aptoe POCA/ WIN Spectrum e

Feb/10/1997 11:23:50AM i

WsLDZWe M rm1ALs (48)

ManDan 11TrommTZ0ff La M1658.80 Anguisities a Feb/10/1997 10:34s40AM i

2dentificetion Started f

User

Whu a Feb/10/1997 10:41:24AM Stapped 1000.002 pec I

MChrd 1

True Detector i NF Ge 1000.000 peo Live l

Osenetry 0.5 L Foly Jar 0.000 t 4

Deed l

Senple

N1658, Gross Count : 17135 counts Channelo : 8192 17.125 cps Gross mete :

l d

i semple Sampled Feb/10/ID9710:34:40AM l

Semple Quantity 1 6 0 24:OSAM 9605030.50 Baeruy Calibration Feb/10/1997 10:

Effistency Calibution Dee/4/1ppe 3:14:55AM RD96131.50 1setepe Library isotope. lib l

Frror Mm i

seror 4%WR pens maessy Aetivity dpm hey Flag 4%us f

+ 30,31 509.9 o.......

1.963e+004

• 1889

• 25.81 337.3 j

Co.60 1173,23 1.704e+004 e 1704 Co.60 1833.51 1.78Se+004 4 1643 Weighted Averegs 1,7e30,004 6 3242 Gesad 'rntet Activity (I%us) Pt Feb/10/1pp710:34:48AM Divided by Oswepte Quantity 1 A 0 3rrors Quoted et 3 Signe Wat s Quoted at 1.645 figen 74eming...............................................

Flags nachgeNNnd tubtracted b

Fitted staplet s

Pitted W itiplet Forced PDA from identification a

M a vs19e Activity shown is less than Ma valveAetivity overflow (too many

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UNITED STATES

[

g NUCLEAR REGULATORY COMMISSION j

REGloN i o,

475 ALLENDALE ROAD d'4 KING oF PRUSSIA, PENNSYLVANIA 19406-1415

. u: I8 Docket No. 99990001 General License Eric Tschantre i-Facilities Manager 1

GE Welding & Machining Services a

302 Hansen Access Road King of Prussia, Pennsylvania 19406

SUBJECT:

INSPECTION NO. 99990001/97-001

Dear Mr. Tschantre:

On January 14,1997, Duncan White of this office conducted a safety inspection at

. the above address of activities authorized by the NRC license listed above. The inspection was limited to the November 1996 incident involving the discovery of contaminated equipment at your facility. The findings of the inspection were a

discussed with you at the conclusion of the inspection. This also refers to the r

telephone conversations on February 5 and 12,1997 between you and Duncan White l

of this office. A copy of the NRC inspection report is enclosed Within the scope of this inspection, no violations were identified.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be placed in the Public Document Room. No reply to this letter is required.

Your cooperation with us is appreciated.

1 Sincerely, r

m enny M Jopapsen, ChieI" Nuclear Ma$ rials Safety Branch 3 Division of Nuclear Materials Safety

Enclosure:

I Inspection Report No. 99990001/97-001 4

cc:

Commonwcalth of Pennsylvania J

+

~

E. Tschantre GE Welding & Machining Services Attachments:

1.

Radiological Survey Performed by General Electric on March 29,1996 2.

Radiological Survey Performed by General Electric on September 23,1996 3.

Radiological Survey Performed by PECO on November 22,1996 4.

Radiological Evaluation'of Drum Performed by General Electric

U.S. NUCLEAR REGULATORY COMMISSION REGION I INSPECTION REPORT Report No.

99990001/97-001 Docket No.

99990001 License No.

General License Licensee:

GE Weldina and Machinina Services 302 Hansen Access Road Kina of Prussia, PA 19406 Facility Name:

GE Technical Service Center inspection At:

302 Hansen Access Road Kina of Prussia. PA Inspection Conducted:

January 14,1997 Inspector:

ch u r % [t ud_

M//T/T7 Duncan White date Senior Health Physicist Approved By:

4 M

I-t' % -

//3/

J4nny M/Joh/ny6n, Chief

/ dats Nuclear Materials Safety Branch 3 Division of Nuclear Materials Safety inspection Summarv: Special announced safety inspection conducted on January 14, 1997 (Inspection Report No. 99990001/97-001).

Areas inspected: Organization and scope of activities; review of Peach Bottom contamination incident; independent measurements; and actions taken by licensee.

Results: No violations were identified. One drum containing welding cables was identified with elevated radiation levels. The licensee shipped this drum to their licensed facility in Memphis, Tennessee to identify the cause of the elevated radiation levels.

DETAILS 1.

Persons Contacted-

• Eric Tschantre - GE Facilities Manager for King of Prussia facility Joseph Plantz - GE Mission Manager for King of Prussia facility Joseph Livingstone - GE representative for Peach Bottom and Limerick (by telephone)

Hal Trimble - Radiation Protection Manager, Peach Bottom Atomic Power Station (by telephone)

' present at exit interview 2.

Oraanization and Scooe of Activities The General Electric (GE) Technical Services facility in King of Prussia is the field services center for GE's welding and machining group. The facility dispatches approximately 30 welding systems and plus 20 to 30 other machining tools to client facilities around the world. The welding systems are primarily used in nuclear power plants due to the system's ability to be remotely operated and controlled with the aid of video cameras. The welding systems conc!st of three primary components: the power supply, cables and welding head.

The King of Prussia facility does not hold a license for radioactive materials.

Equipment used at nuclear facilities are surveyed at the client's plant for release for unrestricted use. GE's facility in Memphis, Tennessee has an Agreement State licensee which permits radioactive contaminated equipment on-site. Welding units used outside the United States and units from domestic facilities that are not surveyed are first sent through the Memphis facility prior to shipment to King of -

Prussia.

The King of Prussia facility has utilized the health physics staff from GE's Nuclear Energy Production facility in Wilmington, North Carolina to perform two radiation surveys. These surveys of the King of Prussia facility were performed on March 29,1996 and September 23,1996. The results of these surveys are found in and 2 of this report.

The surveys performed by GE's Wilmington staff and the diversion of equipment through their Memphis, Tennessee facility was in response to GE's concern that welding equipment with radiological contamination was found on their equipment from an overseas location and the GE's clients requiring that equipment bought into their facilities have no radiological contamination.

No safety concerns were identified.

1 Inspection Report No. 99990001/97-001

. 3.

Review of Peach Bottom Contamination incident On November 22,1996, a GE technician was cleaning out the drawer of power supply unit in the King of Prussia facility that was previously used at PECO's Peach Bottom Nuclear Generating Station during September 1996. One of the items inside the drawer was a plastic bag marked as radioactive. The bag contained two gaskets for the welding head. GE contacted PECO and a health physics supervisor was dispatched to the King of Prussia facility. In addition to the contaminated gaskets, the PECO survey identified several tools in the drawer to be contaminated. Survey of personnel and other areas of the GE facility did not identify the presence of radiological contamination. The contaminated gaskets and tools were returned to Peach Bottom. A summary of the PECO survey is found as Attachment 3 to this report.

The GE representative stated that the power supply unit was located inside a contaminated zone while at Peach Bottom due to the limited floor space. The power supply for the welding head is normally maintained outside the contaminated zone with only the cables and the welding head located inside contaminated zone'. According to PECO, the power supply were taken to the refueling floor but not used at Peach Bottom. The power supply was released from Peach Bottam on September 27,1996.

The release of the power supply for the welding system from the contaminated area at Peach Bottom is still under review by PECO and Region l's Division of Reactor Safety. The inspector noted that the contaminated tools and bag were located in a drawer that according to the GE representative, is used as a work surface. The drawer, when opened, ht.s a cover that hides the contents in the drawer from view and facilitates it use as a work surface. It is only when the cover is lifted, that the contents of the drawer can be seen.

No safety concerns were identified.

4.

Independent Measurements The inspector surveyed the work and storage areas of the Technical Center with a Ludlum Model 44-10 5 centimeter (cm) by 5 cm Nal(TI) detector coupled to a Ludlum Model 2221 ratemeter/ scaler (NRC Serial No. 054828) last calibrated on March 14,1996. The detector used by the inspector is capable of detecting gamma photons with energies with energies greater than 100 kev at or near environmental levels. The average background for this detector is 7,000 to 10,000 counts per minute (cpm).

i inspection Report No. 99990001/97-001

E

, Wipes of removable contamination wipes were also taken at various locations i

around the facility. Each wipe covered an area of approximately 100 square centimeters. Each wipe was counted for 10 minutes on a Tennelec Model LB5100 low background alpha / beta counter at the Region 1 offices. The counter's

)

efficiency for gross alpha and gross beta was 21.1 % and 26.5%, respectively.

l i

The radiation survey of the facility identified one drum with elevated gamma radiation levels. All other equipment, work and storage areas had background radiation levels. The drum with elevated radiation levels (marked as "CS-40-13")

contained cables used to connect the power supply to the welding head. The inspector identified one spot on the drum with a maximum reading of 27,000 cpm. The elevated radiation levels were isolated to the one area of the drum.

i All wipes taken at the facility did not indicate the presence of removable contamination. The results o' the wipes are listed in the table below. Results are reported in units of disintegration per minute per 100 square centimeters (dpm/100 cm ) at an uncertainty of one sigma.

2 Location Gross Alpha Gross Beta Drum No. CS-40-13; hotspot 1.4 i 1.1 Oi3 Drum No. CS-40-13 1

180 degrees from hotspot 0

1.7 0.4

• 3 Drum No. CS-40-13; lid 1*1

-0.4 i 3 i

Drum No. CS-40-22 1.4 1.1

-2 3

Shipping Container No. 2 1.4 i 1.0 0.4 i 3 Shipping Container No. 3 2.8 i 1.3 0.4 3

J Welding Power Supply Serial No.1179 1i1 4i5 Welding Power Supply Serial No. 839 1.4 1

-3 3

Welding Power Supply Serial No.1022 1i1 1i3 Loading dock ramp 1i1

-1 i 3 Shipping area floor

-5 i 5 0i3 Floor near CS-40-s 3 4i1

-0.4 i 3 Inspection Report No. 99990001/97-001 l

l j

5.

Actions Taken by Licensee As a result of the findings of this inspection and previous incidents, the general licensee has taken the following steps in response to the increase occurrences of radiological contamination on the welding and machining equipment.

Welding units used outside the United States and units from domestic facilities a.

that are r:ot surveyed are first sent through the Memphis facility prior to shipment to King of Prussia.

b.

Bar codes affixed to the exterior of shipping containers to track the movement of equipment between client facilities.

Two radiation and contamination surveys in 1936 of the King of Prussia c.

facility by GE's health physics group from the Wilmington, North Carolina facility.

d.

Purchase of radiation survey equipment for use at the King of Prussia facility.

Development of procedures and training of King of Prussia personnel to use e.

survey equipment by GE's Wilmington health physics group.

f.

The drum identified during this inspection with elevated radiation levels was shipped by commercial carrier as a limited quantity package to GE's Memphis facility for evaluation. The evaluation identified fixed Cobalt 60 contamination on two of the cables in the drum. The results of the licensee's survey are found in Attachment 4 of this report.

1 The inspector reviewed the actions taken by the general licensee and determined that they would minimize the potential for the spread of radioactive materials and inadvertent exposure of personnel at the King of Prussia facility.

Ne safety concerns were identified.

6.

Exit Interview The inspection findings were discussed with the individual identified in Section 1 of this report.

1 l

1 inspection Report No. 99990001/97-001

i ATTACHMENT 1 l

RADIOLOGICAL SURVEY PERFORMED BY GENERAL ELECTRIC ON MARCH 29,1996 l

l l

I l

f Inspection Report No. 99990001/97-001 l

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GENuclear Energy NUCLEAR ENERGY PRODUCTK>N GeneralBedric Company, MC M96 P. O. Box 180. %6nhoton. NC 26402 910 675-5531 April 2,19%

S. P. Murray, Manager l

Nuclear Safety

Subject:

Klar of Prinssia TSC Health Physics Survey l

Per your instructions, a survey of the KOP TSC was performed on 3/29/96 by R. G. Lewis. Using two GM survey instrunnents, a series of dose rate and contarnination checks were performed in acx:ordance with weepted GENE practices and action levels. All items surveyed displayed background activity levels.

'Ihere was no hint of any radiation / contamination on any llem checked. I've included attachments widch specifically describe the surveys performed. Please note that 37 " product" containers were surveyed Additionally, people, equipment, tools and a variety of other items were also checked. At the conclusion of my survey, I notified E. Tschantre that his Facility and items within were " clean" and released-i Additionally, I would like to thank Eric and his stafTfor the help and courtesy I moelved while at TSC.

l Post-it* Fax Note 7671 N#,y/g/efg l$> 3

• bis Se A on fe e- ~ 24)GutC coJDept.

ca.

R. G. Lewis Nuclear Safety en e tor l

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SERVICES FACit.ITY

" SRM200/HP210 BKG-115 C/M - EFF = 13%

CAL DATE: 12/5/95 ASP 1/HP260 BKG.02 mth/h CAL DATE: 11n/95 E 520/HP270 BKG.04 mr/hr CAL DATE: 11/7/95

(= 2-300 cpm)

CONTAINER #

MR/HR Dr CONTACT CPMDyCONTACT CPM St SWTPE I

BKG BKG BKG 2

BKG BKG BKG 4

3 BKG BKG BKG 4

BKG BKG BKG 5

BKG BKG BKG 6

BKG BKG BKG 7

BKG BKG BKG 8

BKG BKG BKG j

9 BKG BKG BKG j

10 BKG BKG BKG 11 BKG BKG BKG 12 BKG BKG BKG 13 BKG BKG BKG 14 BKG BKG BKG 15 BKG BKG BKG 16 BKG BKG BKG 17 BKG BKG BKG 18 BKG BKG BKG 19 BKG BKG BKG 20 BKG BKG BKG 21 BKG BKG BKG 22 BKG BKG BKG 23 BKG BKG BKG 24 BKG BKG BKG 25 BKG BKG BKG 26 BKG BKG BKG 27 BKG BKG BKG 28 BKG BKG BKG 29 BKG BKG BKG 30 BKG BKG BKG 31 BKG BKG BKG 32 BKG BKG BKG 33 BKG BKG BKG 34 BKG BKG BKG 35 BKG BKG BKG 36 BKG BKG BKG 37 BKG BKG BKG MISCELLANEOUS TTEMS SURVEYED 36" Guide Rings Weld Head 2 Fork Lins Tool Boxes Heliarc Welder Main Floor Areas Mezzanine Floor Areas Gang Boxes / containers

Blue" plastic drums Storage Racks - Upstairs & Downstairs Shipping Bay Electronic Shop (1) Employee; Handling conttiners

• All Swipes and Direct Readings = BKG

" Swipes rechecked at GE Wilmington R.O.I n 4AM6

SERVICES FACILITY Arc Welders Racks Electronic Shop ToolIkmes Pork LiA Gang Boxes Floor Areas (25) Boxes Box Queue Mezzanine Bay Storage Racks i

Pork Lin Boxes Blue Plastic (12)

Drums R. O. lewis 4h M

1 1

ATTACHMENT 2 RADIOLOGICAL SURVEY PERFORMED BY GENERAL ELECTRIC ON SEPTEMBER 23,1996 Inspection Report No. 99990001/97-001

D e

GE NuclearEnergy NUCLEAR ENERGYPRODUCTION RADIATIONPROTECTION WCH96 P. O. Box 780, Wilmington, NC 28402 cc: B. RotAnson A. Mabry J. Sependa D. Barbour E. Tschantre-KOP E. Rouse 24 September 1996 i

i l

L. Paulson l

Acting Manager i

Nuclear Safety

Subject:

King of Prussia TSC Health Physic Survey A survey of the KOP TSC was performed on 9/23/96 by R. G. Lewis and E. L. Rouse.

Using GM survey instruments, dose rate measurements were performed. Contamination swipes were also taken.

j items and areas surveyed included equipment, shipping containers, equipment in the containers, shop areas and personnel.

All items surveyed were within GENE criteria for

• Unconditional Release *, Attachments are included describing the specific surveys performed.

l At the conclusion of the surveys, E. Tschantre was notif.ed that his facilrty and items were

" Clean and Released

• All actions were reviewed with the Wilmington H. P. Staff.

R. G. Lewis Nuclear Safety

l KING OF PRUSSIA SERVICES FACII ITY Scalar SRM200/RD14 BKG=4.0 C/M - EFF = 29%

CAL DATE: 9/21/96 E-520/HP270 # %7 BKG = 0.05 to 0.06 mr/hr CAL DATE: 6/6/%

E-520/HP270 #11%

BKG =.04 mr/hr CAL DATE: 6/6/96 i

RM14/HP210 #1303 BKG = 60 cpm CAL DATE: 8/7/%

i a

s 1

ITEMS SURVEYED RESULTS D

h Contact Smige a Swipe

• 3 Boxes and contents to Peachbottom BKG BKG BKG Fork Lift BKG BKG BKG Plastic Drums to Oyster Creek and Nine Mile Point BKG BKG BKG Personnel BKG BKG BKG 4 Welders BKG BKG BKG Facilit> Floors BKG BKG BKG Mezzanine Areas BKG BKG BKG 32 Drums / Rows of boxes on mezzanine BKG BKG BKG Shipping Bay BKG BKG BKG Forsmark Containers BKG BKG BKG Gang Boxes BKG BKG BKG Job Box from Hake BKG BKG BKG Electronics Shop BKG BKG BKG Miscellaneous Equipment BKG BKG BKG

• Box #33 to Peachbottom had one reading of 0.12 mr/hr @ contact. Still within GENE guidelines for free release.

i

" The above surveys consist of hundreds of contact readings and swipes taken.

R. G. Lewis E. L. Rouse Nuclear Safety Radiation Protection

___.______m-.___

AREA SURVEY (Continued) i i

Gang Boxes

{

Job Box From Hake 1

Arc i

Storage Parts Area 3 Plastic

- Forsmark Welders Drums (BKG 2

O Weld Test Storage Area Contact 3

BKG Floor Areas 4

j

' Mezzanine Levei Fork Lift j

Omce area Upper and Lower Bay Storage Area Storage Racks

t g

i MAIN SHOP AREA ARC Weld Repair Area Box pue Blue Drums go, nWe Fork Lift 13 _BKG s

Storage Parts Area Misc BKG Boxes PeachBottorn.

Gear Box Misc ing to BKG 0.05 mr/hr W eld m st w Area Arc Welder 0.05 mr/hr

{

BKG

_ Inside 2

4 Arc Welder #2 4.l m r/hr -

3 d

j Menanine Levei Fork Lift Office area Upper and Lower Bay Storage Area Storage Racks.

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ATTACHMENT 3 RADIOLOGICAL SURVEY PERFORMED BY PECO ON NOVEMBER 22,1996

)

I l

Inspection Report No. 99990001/97-001

l 01/03/97 FRI 13:54 FAI 1 717 456 3574 HEALTH PHYSICS

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01/03/97 FRI'13:55 FAI 1'717 456 3574 HEALTH PHYSICS 2007 t

j REPORTS ruk SPECTRUM 2496.

22-NOV-1996 19:58

{

i A'AAAAAAAAAAAAAAAAAAAAAAAAAAAA*AAAAA***AAAAAAAAAAAAAAAAAAA*AAAAAAAAAA l

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A GAMMA SPECTRUM ANALYS IS i

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l AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA 4

CANMpHA APubliB V2. 2_

l Canberra ~ Industries, Inc.

22-NOV-96 19:58:09 t

'ANALYS 1S PARANZTERS Spectrum file number'

2496.0 Sample no.

.2496.0 MCA unit number 1,

ADC unit number 1.0 l

Detector nurnber 1./

Geometry number 1/

l l

l

/

./

l Search threshold 1 2.0 Search threshold 2 2.0 i

Search FROM channel 100 Search TO channel

4095 Id enersy tolerance 1.0 Order of backsround

linear Smoothing. factor O.

Random sum corr

disabled GRA parameter 1

Baseline channels

. disabled Confidence levels LLD :

1.64b (95.0%)

MDA :

1.645 (95.0%)

Analysis library

SPF$ LIBRARY:SPEANL.110 /

Dackground subtract

disabled

/

/

l Sample description

3MEAR-Analyced by: BDM l

SCREWDRIVER G.E. TECH. TLR. y Sample size 1.000000E+00 EACH Inv. factor 1.000 l

Standard size 1.000000E+00 EAC Sample taken on

22-NOV-96 at 19:47:35 Collect started on

22-NOV-96 at 19:47:35 1

Decay time 0.0 minutes f

live time 600.0 seconds real time 600.0 seconds l

dead time 0.00 %

j Energy calibration used done on 12 / 15 / 1991 Efficiency calibration used done on 12 / 21 / 1995 l

(c52 d' '# o f' dea j I" S y

/

posc 1

1 i

l l

01/03/97 FRI 13:56 FAI 1 717 456 3574 HEALTH PHYSICS

@008 AAA P E' A K F I T R E P O P. T AAA 22-NOV-96 19:58:09 pesh nuclide(s) centroid energy FWHH not area error g ain m a s erro no.

channel kev kev counts per second

+

1 GA-72 KR-88 1669.40 034.64 1.50 93.3 10.74 27.6 11.1 MH-54 2 CD-60 2346.90 1173.34 1.60 57.6 13.81 23.8 14.0 3 CD-60 2665.25 1302.49 1.97 47.0 15.26 21.0 15.5

/

l i

01/03/97 FRT 13:56 FAI 1 717 456 3574 HEALTH PilYSICS

@ 009 1

^

AAA RAD IONUCL IDL REP 0RT AAA 22-HOV-96 19:58:09 j

Sataple description

SMEAR Analynod by

BDH i

n uin b e r nuclido conf.value ---------- Activity (

uCi/EACH >

measured decay corrected

+

j 1.

Fission gases total 0.0000E+00 total 0.0000E+00

)

3.

Iodines total 0.0000E+00 total 0.0000E+00 3.

Particulates 1

HN-54 0.9943

7. 4 667E-0 4 +-1. 03E +01 % 7.4667E -04

+-1. 83E + 01%

2 CD-60 0.9975 6.1667B-04 +-1.72E+01% 6.1667E-04 +-1.72E+01%

total 1.3633E-03 total 1.3633E-03

/

l Errors quoted at 1.650 sigma ( 90.1% )

i l

01/03/97 FRI 13:57 FAI 1 717 456 3574 HEALTH PHYSICS

@010 1

REPORTS FOR SPECTRUM 2497.

22-NOV-1996 20: 03 AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA

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A GAMHA S P E C T R 11 M A NALYC I S A

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AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CANDERRA APOGEE V2.2 Canberra Industries, Inc.

22-WUV-96 20:02:",3 2

A NALY S 1S PA RAMETER5 Spectrum file number

2497.0 Sample no.

2497.0 l

HCA unit number 1

ADC unit number 2.0 2/

Geometry number 1s Detector number s/

/

Search threshold 1 2.0 Search threshold 2 3.0 Search FROM channel 100 Search TO channel

4095 j

Id energy tolerance 1.0 Order of background

linear Sacothing factor 0

Random sum corr

dieabled i

QRA parameter 1

Baseline channels

disabled 1

Confidence levels LLD :

1.645 (95.0%)

MDA :

1.645 (95.0%)

Analysis library

SPE$ LIBRARY:SPEANL.110 '

Background subtract

disabind f Sample description

SHEAR /

Analy::ed by: DDM SCREWDRIVER CASE G.E. TLR.,

Scmple si=e 1.000000E+00 EAC /

Conv. factor 1.000 Standard sine 1.000000E+00 EAC Sampic takeri on

22-NOV-96 at 19:52:10 #

l Collect started on

22-HOV-96 at 19:52:18 Decay time 0.0 minutes

/

live tirne 600.0 seconds real time 600.0 seconde dead time 0.00 %

Unergy calibration used done on 1 /

2/ 1996 Efficiency calibration used done on 1 / 11 / 1996 l

d 9

p6 i

01/03/97 FRI 13:58 FAI 1 717 456 3574 HEALTH PHYSICS

@ 011 AAA PEAK F IT HEP 0RT AAA 22-HuV-96 20:02:53 peak nuclide(s) centroid energy FWHH net carca error S a non a s erru no.

channel heV heV counts per second o

i KR-GG HN-54 1670.02 835.08 1.67 23'/.3 6.62 44.0 7.2 l

2 CO-60 2347.25 1173.71 1.94 83.6 11.16 22.8 11.4 3 CD-66 2G65.40 13'2.78 2.05 02.4 11.49 24.0 11.0 i

l l

l 2

01/03/97 FRI 13:58 FAI 1 717 456 3574 HEALTH PHYSICS

@ 012 1

AAA RAD I O f4 U C L IDE f: EPOEI AAA 22-HOV-96 20:02:53 Sample description

SMEAR Analyzed by

BDM number nuclide conf.value ---------- Activity (

uCi/CACH )

measured decay corrected

+

1.

Eission gases total 0.0000E+00 total 0.0000E+00 2.

lodines total 0.0000E+00 t o t.a 1 0.0000E+00 3.

Particulates 1

MN-54 0.9899 1.1901E-03 +-1.19E+01% 1.1901E-03 +-1.19E+01%

2 CO-60 0.9491 6.3131E-04 +-1.36E+01% 6.3121E-04 +-1.36E+01%

total 1.8213E-03 total 1.8313E-03

/

Errors quoted at 1.650 sigma ( 90.1% )

4

01/03/07 FRI 13:58 FAI 1 717 456 3574 HEALTH PHYSICS

@ 013 REPORTS EUR SPECTkUM 2 BOO.

22-NOV-1995 21:49 AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA A

A A

GA HMA SPECTkUM ANALY G I S A

A AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CANHERRA APOUEB V2.2 Canberra Industries, Inc.

22-HOV-96 21:49:21 A NALYS IS PA RAMdTERS Spectrum file number

2b06.0 Sample no.

2506.0 MCA unit number 1

ADC unit number 2.0 Detector number 2 g/

Geometry number l'

3

/

/

Search t,h r e c h o l d 1 2.0 Search threshold 2 3.0 Saarch FROM channel 100 Search 70 channel

4095 Id energy tolerance 1.0 Order of background

linear Emoothing factor 0

Random sum corr

disabled GRA parameter 1

Baseline channels

disabled Confidence levels LLD :

1.645 (95.0%)

MDA :

1.64b (9b.0%)

Analysis library

SPf$ LIBRARY:SPFANL.110 '

Background subtract

disabled

./*

Sample description

SMEAR /

Analyr.ed by: BDH 20000 CPM ggt--

p Sampic si::e 1.000000E+00 EACH

'Conv. factor 1.000 Standard size 1.000000E+00 EAC Sample taken on

22-NOV-96 at 21:15:00 '#

Collect started on

22-NOV-96 at 21:20:35 Decay time 23.6 minutes live time 600.0 seconds real tiene 607.0 seconds doad time 1.15 %

Energy calibration used done on 1/

2/ 1996 Efficiency calibration used done on 1 / 11 / 1996 N

. (i f

V y

,01/03/97 FRI 13:59 FAI 1 717 456 3574 HEALTH PHYSICS Q1014 6

AAA PEAK E IT REPOPT A A.h 22-t10V-96 21:49:21 peak nuclide(s) centroid energy fWilM net area error g r.a:ain ca s erro no.

channel kev kev counts per second

+

1 UA-140 847.97 424.00 0.01 61.3 47.51 5.9 47.6 2 W-187 960.78 480.42 0.91 71.8 42.00 7.7 42.2 3 1-132 1013.00 506.57 0.76 9.4330.67 1.1330.6 4

1145.63 572.05 1.29 134.0 26.87 17.2 27.1 5 AG110M RB-89 1316.37 658.22 1.28 170.0 18.24 26.2 18.5 6

1503.96 752.04 1.17 16.5132.18 2.8132.2 7 CO-58 1621.84 310.99 1.46 193.1 13.15 34.8 13.4 0 OA-72 K R --8 8 1669.96 B35.05 1.56 45069.4 0.48 8351.0 2.8 till-54 9 I-134 AG110M 1769.48 884.81 1.67 151.6 lb.60 29.7 15.0 10 1810.04 905.09 1.39 42.7 51.09 8.6 51.1 11 2060.97 1030.b6 1,39 45.1 41.77 10.3 41.8 12 PE-59 2199.22 1099.69 1.79 99.5 20.70 24.1 20.9 13 Zil-65 2231.44 1115.80 1.72 916.2 3.92 22b.0 4.6 14 CD-60 2346.78 1173.47 1.79 9616.9 1.04 2478.3 2.8 1S UE-59 2bS3.43 1291.80 2 06 71.0 14.31 20.0 14.5 16 CU-60 2665.47 1332 81 1.93 8704.8 1.08 2530.3 3.0 m

01/03/97 FRI 13:59 FAI 1 717 456 3574 HEALTH PHYSICS

@ 015 1

AAA I: AD 1 0 ft U C L IDE REPORT AAA 22-NOV-96 21:49:2)

Sample description

GMEAR Analyzed tiy

BbH number nuclide conf.value ---------- Activity (

uCi/EACH )

measured decay corrected

+

1.

Eission gases total 0.0000E+00 total O.0000E+00 2.

Iodines total 0.0000E+00 total 0.0000E+00 3

Particulates 1

HN-54 0.9923 2.2b99E-01 +-4.7bE+00% 2.2600B-01 +-4.75E+00%

2 CD-58 0.9917 9.4540E-04 +-2.22E+01% 9.455bE-04 +-2.22E+01%

3 EE-59 0.8933 1.2169E-03 +-1.98E+01% 1.2172B-03 +-1.98E+01%

4 CO-60 0.9725 6.7628E-02 +-3.41E+00% 6.7628E-02 +-3.41E+00%

5 ZN-65 0.9872 1.1993E-02 +-7.73E+00% 1.1993E-03 +-7.73E+00%

6 AG-110M 0.1999 8.8915E-04 +-2.03E+01% 0.8919E-04 +-2.03E+01%

total 3.0867E-01 total 3.0858E-01

/

These peaks were not identified number channel energy peak intensity (sps)

+

1 848.0 424.00 5.856bH+00 +-

70.56% BA-140 2

960.0 400.42 7.7376E+00 +-

69.62% W-187 3

1013.1 506.57 1.0629E+00 +- 545.64% I-132 4

1145.6 572.85 1.7150E+01 4-44.76%

6 1504.0 7b2.04 2.7bl4E+00 +- 218.15%

10 1810.0 905.09 8.5590E+00 +-

84.40%

11 2061.0 1030.b6 1.0264E+01 +-

69.05%

Errors quoted at 1.650 sigma ( 90.1% )

l I

01/03/97 FRI 14:00 FAI 1 717 458 3574 HEALTH PHYSICS

@ 016 REPORTC TOD GP::CTRUti 2507.

22-NOV-1993 21:50 AAAAAA AAAAAAAAAAAAAAAAAAAAAAA AAAAAAAAAAAAAAAAAA AAAAAAAAAAAAAAAAAAAA AA AAAAAAAAAA A

A A

GAMM A SPECTRUM ANA LYS IS A

A A

AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CANDEkRA APOGEE V2.2 Canberra Industries, Inc.

2 2-i10 V-96 21:bo:16 ANALYS IS P A R A M E T E R 's S pe c tr urn file number

2507.0 Sample no.

2b07.0 tiCA unit nuinber 1

ADC unit nunber 1.0 Detector number 1/

Geometry number 1 /

l

/

Search threshold 1 2.0 Search threshold 2 3.0 Scarch FROM channel 100 Search 10 channel

4095 Id energy tolerance 1.0 Order of background

linear Smoothing factor 0

Random sum corr

disabled GR A par aineter 1

Baseline channels

disabled Confidence levels LLD

1.64b (96.0%)

HDA :

1.645 (95.0%)

Analysis library

SPE$ LIBRARY:8PFANL.110 '

Boeltground subtract

disabled Sample description

SHEAR Analyzed by: BDH 4000 CPM

/

(.cg g Saaple size 1.000000E+00 EACH Conv. factor 1.000 Standard si=e 1.000000E+00 EAC Scmple taken on 22-NOV-96 at 21:15:00 $

Collect started on

22-NOV-96 at 21:39:26 Decay time 24.4 niinutes #

~_

f live time 600.0 seconds real time 607.0 seconde dead time 1.15 %

Energy calibration used done on 12 / 15 / 1995 Efficiency calibration used done on 12 / 21 / 1995

01/03/97 FRI 14:00 FAI 1 717 456 3574 HEALTH PHYSICS

@ 017 a

4AA PCAK F1T REF0EI AAA 22-NOV-96 21:50 16 peak nuclide(s) centroid energy TWHH net ir ea eri or gain Aas erro

]

no.

channel kev i.eV counts per second 1 DA-139 CB-139 331.00 165.49 0.64 36.7 30.70 2.3 80.8 2

900.82 450.30 0.84 75.5 40.33 12.1 40.6 3 CO-58 1622.00 Ulv.93 1.63 141.6 15.78 40.7 16.0 4 GA-72 KR-80 1669./3 834.30 1.44 42743.6 0.49 12646.9 2.0 MH-S4 5

2016.15 1009.00 1.28 32.5 54.46 11.6 54."J G EE-59 2198.95 1999.30 1.86 102.2 18.94 39.6 19.1 7 ZN-65 2231.16 1115.48 1.70 315.9 7.90 124.0 8.3 U CD-60 2346.47 1173.13 1.67 8029.8 1.14 3308.9 2.0 9 UE-59 2b83.59 1291.67 1.70 53.5 16.63 24.1 16.8 10 CD-60 2665.14 1332.44 1.74 7224.5 1.18 3358.0 3.0

/

i i

01/03/97 FRI 14:00 FAI 1 717 456 3574 HEALTH PHYSICS

@ 018

' 1 AAA RAD IONUCL IDE REPQRI AAA 22-NOV-96 21:50:16 l

Gemple description

SHEAR Analyued by

BDM number nuclide conf.value ---------- Activity (

uCi/EACH ) -~~-------

measured decay corrected i

+

1. Eission 9ases total 0.0000E+00 total 0.0000E+00 3.

Iodines gg total 0.0000E+00 total 0.0000E+00

/

)

f

)

7

+-4.76E+00% 3.4326E,g ?3 k 3.

Particulates

,e 01 +

.762+00%

1 MN-54 0.9999 3.422bE-01 2

CD-58 0.9919 1.1071E-03 +-2.65E+01% 1.1073E-03

+-2 65E+01%

1 7

3 EE-59 0.9303 1.6377E-03 +-2.10E+01% 1.6381E-03 +nd.10E+01%

4 CO-60 0.9984 9.0044E-02 +-3.47E400% 9.0044E-02ei-3.47E+00%

5 ZN-GS 0.9990 6.6111E-03 +-1.37E+01% 6.6114E-03 +-1.37E+01%

total 4.4165E-01 total 4.4166E-01 V

These peaks were not identified number channel energy peak intensity (sps)

+

1 331.0 165.49 2.310SE+00 +- 133.39% BA-139 CE-139 9

900.8 450.08 1.2114E+01 +-

67.10%

5 2016.2 1000.00 1.1565E+01 +-

69.93%

Errort quoted at 1.650 sigma ( 90.1% )

01/03/97 FRI 14*01 FAI 1 717 458 3574 HEALTH PHYSICS

@ 019 s

Contaminated items Found at General Electric October 1,1996 IIEMS DIRECT FRISKED ltem Descriotion Contamination Level (dom)

Conversion Factor Activity (uCl)

Channel Lock Vise Grips 2800 4.51E-07 1.26E-03 Needle Nose Pliers 6000 4.51 E-07 2.70E-03 Flashlight (Mogenta) 1400 4.51 E-07 6.31E-04 Snips with Tape 14000 4.51 E-07 6.31 E-03 Brass Components 2200 4.51 E-07 9.91 E-04 RTV Sealant 2000 4.51FJ7 9.01 E-04 Crescent Wrench 2800 4.51E-07 1.20E-03 Hex Head 4000 4.51E-07 1.80E-03 Wood File 3000 4.51E 07 1.35E-03 TOTAL 1.72E-02 SMEARS Smear Number item Smeared Activity (uCi) i 1

Screwdriver 1.36E-03 2

Screwdriver Case '

1.82E-03 3-Gasket 3.09E-01 4

Gasket 4.42E-01 TOTAL 7.54E-01 Total Activity. Tools and Smears 7.71E-01

,01/C3/97 FRI 14:01 FAI 1 717 456 3574 HEALTH PHYSICS

@ 020 r

a LSOTOPIC ANALYSIS OF SMEARS AT GENERAL ELECTRIC October 1,1996 i

SMEAR 1 - SCREWDRIVER ISOTOPE Activity (uCi) 10 CFR 20 LIMIT

% OF LIMIT LuCD MN.54 7.47E-04 1.00E+02 7.47E-04 CO-60 6.17E-04 1.00E+00 6.17E-02 TOTAL 1.36E-03 6.24 E-02 SMEAR 2 - SCREWDRIVER CASE ISOTOPE Activity (uCl) 10 CFR 20 LIMIT

% OF LIMIT GLC.D MN-54 1.19E-03 1.00Et02 1.19E-03 CO-60 6.31E-04 1.00E+00 4 6.31E-02 TOTAL 1.62E-03 6.43E-02 l

SMEAR 3 - GASKET ISOTOPE Activity (uCl) 10 CFR 20 LIMIT

% OF l.lMIT (uCl) i i

MN-54 2.26E-01 1.00E+02 2.26E-01 CO-58 9.46E-04 1.00E+02 9.46E-04 FE 59 1.22E-03 1.00E+01 1.22E 02 CO-60 6.76E-02 1.00E+00 6.76E+00 ZN-65 1.20E-02 1.00E+01 1.20E-01 AG-110 8.89E-04 1.00E+01 8.69E-03 TOTAL 3.09E-01 7.13E+00

_S_MEAR A - GASKEl ISOTOPE Activity (uCl) 10 CFR 20 LIMIT

% OF LIMIT E

MN-54 3.42E-01 1.00E+02 3.42E-01 CO-58 1.11E-03 1.00E+ 02 1.11 E-03 FE-59 1.64E-03 1.00E+01 1.64 E-02 CO-60 9.00E-02 1.00E+00 9.00E+00 ZN-65 6.61 E-03 1.00E+01 6.61 E-02 TOTAL 4.42E-01 9.43E+00 j

ATTACHMENT 4 RADIOLOGICAL EVALUATION OF DRUM PERFORMED BY GENERAL ELECTRIC Inspection Report No. 99990001/97-001

~

i a te m umt oc es

~

GE-NUCLEAR ENERGY i

1790 DOCK STREET MEMPHIS, TN 38113 4

i llich Jones -

901)774-1922 Dial Comm: 8*964-4003 Joe Davidson -

901)774-1415 Dial Comm: 8*964-4005 l

Larry Hawkins -

901)774-1238 Dial Comm: 8+964-4004 Bobby Newell-901)774-9322 DialComm: 8*964-4001 Cassandra Ferby - 901)774-9328 Dial Comm: 8*964-4002 Bob Langford -

901)774-9370 Dial Comm: 8*964-4000 Fax #: 901)774-9517 Dial Comm: 8*964 4200 FAX COVER SHEET Date:

altoI9 l Number of Pages (including cover sheet) d TO:

E 6 c_ % h a n re.e 9 K..o.7.

FROM:

bu

c. w o c.c COMMENTS: the e. is we c,n m m a sog. htrs er fuer mmod at %%

aiu.

p o w w e.. e. w e u m o c.

im W ei. "ar o e. Ou s-iu e t.4 n n. Tu fr oTnMJl __.

le.hms A __,_h m b MNke te n t m e tw e ae n,Ch oo r.st L AE - T V 3)pue

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M 3. blL - 34

_N at.s ub4eso magt i n-On te e sec r ti, Q s V D Mb d }w t - t-

.g

(% d WF.-1566 a m. N\\acTV hocauM (D

I, N.9 13 '97 P2:gTlj p "- -

F.SS 4 tee PCMCA/ WIN Spectrum Feb/10/1997 11:22:59AN WELDIIW3 MNTERIALE (42) i NEADER 18:*?AMATI0t* in M1654.80 Acquisition Feb/10/1997 10:24:48AM 2

Zeeltific* tion started troer shu Feb/10/1997 10:41:2&AM stopped True

1000.802 pec HCArd

1 i

Detect <"

HP C+

Live

1000.000 pec Geometr 0.5 t Poly Jar Deed s 0.000 t Sample

H16Ft Gross Count : 17125 counts ChanneIt : 8192 Orcas Rate : 17.125 opa sample Samp1M Feb/10/lpS7 10:24:48AM sample Quantity 1

• 0 24:05AM 9605030,50 Ener q' Calibration Feb/10/199710:

Efficierry Calib" tion Dee/4/1994 7:14:55AK DD96121.80 d

1sotope Library taotope, lib l

rrror Mon arror dem pene unorgy Activity dama dpm heV Flag

...............................................................* 20.31 l

509.9 1.562e+004

• 1589

• 25,81 i

337,2 1

Co.60 1173,21 1,108e+004 2 1704 Co.50 1332,51 1.78$e+004 4 1643 W;ighten Averags i

1,7eset004 6 3282 f

Gaand 'r,tal

)

• t Feb/10/1997 10:24:40AM (dpm) l Activit.y Diuded by 0wepte Quantity 1 & 0 i

2rrora Quoted rt 2 Sigma l

Quoted ct 1.d45 81gma i

NDA's 4

Maning Flags Mokgreamd Subtracted b

Pitted stoglet s

i 71tted 151tiplet Forced P'OA free identification a

i tea val"*

Activitw shown is less than MDA valveActivity overflor (too many h

.c j

9 i

l, i

1 1

4