ML20155B881

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Insp Rept 9999003/88-01 on 880422.No Violations Noted.Major Areas Inspected:Depleted U Shielding Program,Including Organization,Training,Radiation Protection Procedures,Use of Matls,Storage Matls,Facilities & Receipt & Transfer of Matl
ML20155B881
Person / Time
Issue date: 06/02/1988
From: Mallett B, Silvious A, Wiedeman D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20155B879 List:
References
REF-QA-99990003-880603 99990003-88-01, 99990003-88-1, NUDOCS 8806140007
Download: ML20155B881 (9)


Text

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U. S. NUCLEAR REGULATORY COMMISSION

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REGION III 4

Report No. 9999003/88001(DRSS)

Docket No. None Assigned Category E Priority III License N(. None Assigned Program Code 11300 Licensee:

Department of the Army U.S. Army Materiel Command Alexandria, VA 22333/0001 Inspection Conducted On: April 22, 1988 Inspection Conducted At:

Lima Army Tank Plant

, 1155 ut eye Road k

/)o Oh 45804

/

a Inspectors:

D. G. Wi eman, Chief J

ddM Nuclear Materials Safety Date Section 1

_ f[N8 B.

1 t ef Nuclear Materials Safety Date Sa rd Bran A. Cynn Yief d' AM Information Security Branch Date Division of Security gg.q-[,.8/ h I [AT Approved By:

Date Inspection Summary Inspection on April 22, 1988 (Report No. 9999003/88001(DRSS))

Areas Inspected:

Routine announced initial inspection of a depleted uranium (DU) shielding program, including organization, training, radiation protection procedures, use of materials, storage of materials, facilities, receipt and transfer of material, external and internal dosimetry, transportation, and posting.

Results: Of the areas inspected, no violations or NRC requirements were identified.

8806140007 880603 REG 3 QA999 EUSDODA 99990003 nr.n L

.4 DETAILS 1.

Persons Contacted Lt. Colonel John Scarfo, Commander, Lima Army Tank Plant (LATP)

  • Captain John A. Merkwan, Production Officer, Quality Assurance Division (LATP)
  • Paul Garman, Security Officer (LATP)
  • William V. Crady, Safety Manager (LATP)
  • Dick Sutliff, Manufacturing Program Manager, General Dynamics Corporation at (LATP)
  • Yolanda Shuman, Senior Health and Safety Representative and Radiation Protection Officer (RPO), For General Dynamics Corporation at (LATP)
  • Denotes those in attendance at the exit interview on April 22, 1988.

2.

Licensed Program This source material license was issued on July 14, 1986 and authorizes unlimited quantities of

  • depleted uranium (OU) to be used in accordance with the statements, representations and conditions stated in the Department of Army, Materiel Command's license application, dated June 13, 1986.

The license does noc authorize extrusion, rolling, forging, machining, grinding or drilling the DU.

  • The word depleted uranium (OU) is frequently misinterpreted which could result either in excessive or lack of safety controls. Depleted uranium, a byproduct of the nuclear-industry, differs from natural uranium primarily in having an appreciably lower uranium-235 isotope content.

Depleted uranium has gone through the gaseous diffusion process for the removal of the fissionable isotope uranium-235. Natural uranium contains 0.7% uranium-235 with 0.3% remaining after the gaseous diffusion process.

The term "depleted" refers to the fact that most of the uranium-235 has been extracted and not that the radiation has been depleted. The only significant difference between depleted and natural uranium is that the depleted uranium no longer has current economic value with respect to recovery of the uranium-235.

Uranium-235 while contained in either depleted or natural uranium has no particular radiological significance because it is homogeneously dispersed. Other than a lower uranium-235 content, the radiation, chemical and metallurgical properties of depleted and natural uranium are essentially identical with the safety controls applicable to both. Depleted uranium is useful for non-nuclear applications by virtue of its high density and the structural properties that are attainable.

Depleted uranium is the least hazardous long life radioisotope,provided that sound industrial hygiene practices are followed.

In general, safety cont *ols required for DU are similar to those required for other heavy metals, such as lead.

2

3.

Organization The Lima Army Tank Plant (LATP) is a government owned / contractor operated facility.

The primary contractor at LATP is General Dynamics Corporation.

The day-to-day radiation protection procedures and employee training is performed by contractor personnel.

If any problems are found, this is reported to Mr. William Crady who is the Safety Manager for the Army who reports to Lt. Colonel John Scarfo, Commander of the LATP. The Army's function is to monitor the radiation protection practices performed by the contractor.

No violations of Commission rules, regulations or license conditions were identified.

4.

Training An interview with the RP0 indicated that all users and employees that may come in contact with DU have received training.

The workers in Building 351 were trained on March 22, 1988 through April 12, 1988, then make-up sessions were conducted on April 19, 1988 through April 21, 1988.

This training consisted of a four hour session of basic radiation protection, emergency procedures, rules and regulations and a question / answer period.

Orientatica training for workers in Building 149 was conducted on March 29, 1988 through April 8, 1988. This orientation training was attended by several hundred individuals.

Each individual must sign a form (See Attachment B) that attends this training.

Each contractor employee that works with DU must complete the following prior to being assigned work with OU:

a.

A complete work history - See Attachment A of this report; b.

Chest X-ray; c.

Pulmonary function test; d.

Urinalysis - base line bioassay for DU; and e.

Blood test.

This training and orientation program is incorporated by reference in the licensee's application dated June 13, 1986.

The license requires training prior to assignmer<t to working with DU and biannually No violations of Ccmmission rules, regulations or license conditions were r

identified.

i 5.

Radiation Protection Procedures Personnel monitoring is issued to all workers in Building 351.

The l

thermoluminescent dosimeters (TLDs) are incorporated into the individual's security badge.

The TLD is exchanged monthly and the results are reviewed l

by the RPO.

Visitors are issued self-reading pocket dosimeters and must l

sign a form "Visitor Radiation Indoctrination Form and Dosimeter Record" (see Attachment C). Area TLDs are posted in and around the production l

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areas to monitor ambient radiation levels. Direct radiation surveys and contamination wipe tests are performed on all incoming packages of DU and during unpacking of the DU shipping containers, All final assemblies are sur.]yed prior to leaving Building 351. The license requires visitors to be issued pocket dosimeters, workers in Building 351 to be issued TLDs and surveys and wipe tests to be performed on incoming packages.

Weekly contamination wipes are performed at all exits to controlled areas, DU work areas and waste areas. The DU storage area is wipe tested each time it is used.

All workers entering and exiting a controlled DU work area survey themselves for contamination.

Each survey instrument is calibrated every three months.

Airborne levels of use areas are being monitored by air sampling in according with procedures specified in the license.

The licensee stated that surveys are performed of the truck transporting the packages at the time of receipt after packages are removed prior to releasing the truck from the site.

The licensee maintained records of the shipments received to date.

No violations of Commission rules, regulations or license conditions were identified.

6.

Use of Material The licensee uses the DU for additional shielding in the Abrams M1-Al tank.

The DU is received as complete packages to be placed in the tanks.

The DU was not machined, ground or drilled on the date of inspection and the licensee appears to have no plans to do this in the future.

The licensee's analysis of potential accidents that might occur during use of DU at the site are adequate to address the operations and uses observed by the inspectors.

No violations of Commission rules, regulations or license conditions were identified.

7.

Storage of Material The licensee stores all unused DU in a locked, posted and restricted room i

l as specified in the license application.

Access is controlled to the room via procedures specified in the license application. Access is l

controlled by security staff.

No violations of Commission rules, regulations, or license conditions were identified.

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8.

Facilities The facilities agreed with those described as part of the license application dated June 13, 1936.

The DU is handled in Buildings 147 and 351.

No violations of Commission rules, regulations or license conditions were identified.

9.

Receipt and Transfer of Materials The inspectors reviewed records and procedures of receipt and transfer of DU. This review showed that all licensed material is being received and transferred in accordance with 10 CFR 20 and 40.

No violations of Commission rules, regulations, or license conditions were identified.

10. Transportation The inspectors reviewed the licensee's procedures for transporting DU and tne procedures appear to be in compliance with 10 CFR 71 and 49 CFR.

No violations of Commission rules, regulations, or license conditions were identified.

11. Confirmatory Measurements The NRC inspectors made independent measurements during the inspection using a Xetex 305B, NRC Serial No. 019401, calibrated on March 14, 1988.

The licensee had four shipping containers on site as of the date of the inspection.

The results of surveys for one container were as follows:

a.

Radiation levels on a shipping container with a "B" package of DU was 1.0 to 2.0 mR/ hour (maximum) on contact with the container.

b.

Radiation levels on a "B" package of DU was 1.0 to 5.6 mR/ hour on contact.

The radiation levelt indicated in the licensee's surveys of the incoming shipment of this container and package were in a;reement with these levels. The licensee's wipe tests of these incoming packages indicated no contamination on the package surfaces.

No violations of Commission rules, regulations, or license conditions were identified.

I t 5

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12.

Inventories The licensee has an inventory system mainteined by the Radiation Safety Officer for all OU packages received and used at the facility.

This inventory system was as specified in the license.

No violations of Commission rules, regulations, or license conditions were identified.

13. Exit Interview On April 10, 1988, an exit interview was held with those denoted in Section 1 of this report.

The NRC findings were discussed and t.e'

~

licensee was given the opportunity to review all written material for proprietary information (exempted from public disclosure in accordance with 10 CFR 2.790).

The licensee did not permit the NRC to remove from the facility, a diagram of the points on the package where radiation i

levels were made by the NRC.

Attachments:

1.

Attachment A - Occupational External Radiation Exposure History 2.

Attachment B - Training Sign-in Sheet 3.

Attachment C - Visitor Radiation Indoctrination Form and Dosimetry Record I

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M.UERNAL RADLA. TION EXPOSURE HISTORY c.

a NAME CLOCK NO.

SHIFT DATE (WORK)

ADDRESS TELE. NO.

AGE

- - D.O.B.

SEX S.S. NO.

OCCUPATIONAL EXPOSURE - PREVIOU!. HISTORY

5. FREVIOUS EMPLOYMENTS INVOLVING FREviOUS DOSE MtSTORY
10. REMARKS
6. DATES OF
7. PERIODS RADIATION EXPOSURE -

0 9.

INSERT EMPLOYMENT OF ONE: RE, CORD LIST NAME AND ADDRESS BODY OF EMPLOYER (FROM TO)

EXPOSURE (REM)

CALC ATED ACCUMULATED OCCUPATIONAL DOSE - TOTALS

12. CERTIFICATION:

I CERTIFY THAT THE EXPOSURE HISTORY USTED IN COiUMNS 5,6, AND 7 IS CORRECT AND COMPLETE TO THE BEst OF MY KNOWLEDGE AND BEL!EF.

. CALCULATIONS PERMISSIBLE DOSE

'13. WHOLE BODY (e) PERMIS$1BLE ACCUM. DOSE = 5(N.1P)

REM

=

(b) TOTAL EXPCSURE TO DATE (FROM fiEM 11) >

REM (c) PERMIS3IBLE DOSE --------

. =

REM EMPLOYEE'S SIGNATURE DATF _

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l NAME OF UCENSEE: GENERAL. DYNAMICS CORPORATION


.-----------------J

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LAND SYSIU1S DIVISION LIMA ARW TANK PIAhT 1RAINIhG SIGN-IN SHEET TRAINING

SUBJECT:

DATE:

TIME:

INSTRUCIOR(S):

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r ATTACIIMENT C

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VISITOR RADIATION INDOCTRINATION FORM AND DOSIMETRY RECORD Ncme (Last)

First Midd. I Age Social Security D&te of Birth Street Address City State Zip Code I have been given a copy of Lima Army Tank Plant Visitor's Radiation Indect.-inttion Training handout.

I have read and understood this indoctrination handout and sa satisfied that I have been given the opportunity to ask questions concerning radiation protection, risks and standard operating procedures.

Fu r t h'e r, I une.erstand tPat I niu s t remain with the escort assigned to me at all times, while in any radiological gontrol area. The escort will provide all instructions necessary to ensure good radiat:on protection practices and conformance to station procedures.

I recognize that I may receive radiation. exposure during this visit at LATP.

Visitor's Signature Date

((.

10R FEMALES ONLY:

I have had the Appendix to Regulatory Guide 8.13 presented to me both orally and in written form.

I have had the opportunity to ask questions concerning the information in the Appendix and elect the foll6 wing at this time:

((7 1.

Elect to receive occupational radiation exposure not to exceed 125 mrem / calender quarter.

[]7 2.

Elect not to receive occupational radiation exposure at this site.

Visitor's Signature Date ESCORT SECTION Escort's Name (Last)

First Midd. I

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Social Security Purpose of Visit LATP Radiological Areas Entered

\\_J have ensured that this Visitor Record is complete, the proper dosimeter readings are recorded and the visitor has been informed of the readings.

Sigr _ \\f t e r Expesu re is Received j

,9 s d m m / e Esc ort's Signature

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