ML19209C096
| ML19209C096 | |
| Person / Time | |
|---|---|
| Site: | 07000033 |
| Issue date: | 08/02/1979 |
| From: | Clemons P, Crocker H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19209C089 | List: |
| References | |
| 70-0033-79-08, 70-33-79-8, NUDOCS 7910110518 | |
| Download: ML19209C096 (8) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 79-08 Docket No. <0-33 License No. SNM-23 Priority:
1 Category: UR Licensee:
Texas Instruments, Inc.
34 Forest Street Attleboro, MA 02703 Facility Name:
Texas Instruments, Inc.
Inspection at:
Attleboro, MA Inspection conducted:
June 19-21, 1979 M
f Inspectors:
i t,
' /P. E. Clemons, Radiatipn Specialist date signeo Approved by:
0 O s cov e/>/><
~
H. f/ Croi:ker, Adting Chief dafte /,igrfed Radfation Support Sect.on FF&MS Branch Inspection Summuy:
Insportion on June 19-21, 1979 (Report No. 70-33/79-08)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of the Radiation Protection Program includirig:
outstanding items, audits, 10 CFR 71.51, dosimetry, bioassay, training, instrument calibration, ventilation, annual report, termination reports, contami-nation control, breathing zone samples, stack samples, beta gamma surveys, smears, posting, fixed alpha survey, receipt of radioactive material and respiratory protection.
The inspection involved 18 inspectr. -hours on site by one regional based NRC inspector.
Results.
Of the 19 areas inspected, no items of noncompliance were identified in 18 areas.
One apparent item of noncompliance was identi-fied in one area (Infraction - Failure to make removable beta gamma survey; Failure to make fixed alpha survey-Paragraph 4).
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DETAILS 1.
Persons Contacted
- Mr. F. Sherman, Manager, HFIR Project
- Mr. C. Hopper, Manager, Nuclear Safety
- Mr. D. Talan, Health Physics Officer
- Denotes those present at the exit interview.
2.
Licensee Act.s v. revious Inspection Findings (Closed) Noncompliance (33/78-17-01) Failure to issue a film badge to the inspector upon entry into the Fuel Manufacturing Area (FMA).
The inspector was informed that the film badge requirement had been discussed with appro-priate personnel, and the inspector observed that the sign spacifying the film badge requirement had been relocated to a more prominent location.
(Closed) Noncompliance (33/78-17-02) Procedures not available at each work location.
The inspector observed that operating procedures had been placed at the Compactor and the Boil D',wn Unit located in the Furnace Room of the Fuel Manufacturing Area (FMA'.
(Closed) Noncompliance (33/78-17-03) Presence of radioactive material not evaluated as Compactor was operated.
The inspector reviewed survey data which indicated that several air samples had been taken during compacting operations, and during Boil Down operations to evaluate for the presence of radioactive material.
(Closed) Noncompliance (33/78-17-04) External radiation surveys were not adequate.
The inspector reviewed survey data which indicated that the surveys were more comprehensive.
3.
Audits Condition 13 of Soecial Nuclear Material License No. SNM-23 states, " Audits of the radiological... safety aspect: conducted pursuant to this license shall be conducted at least quarterly...."
The inspector verified that the required quarterly audits had been performed by reviewing reports, sub..litted to the licensee, dated December 14, 1978 and March 2, 1979.
The audits had been performed by an individual who is not an employee of the licensee.
The reports did not identify or indicate any rroblem areas.
No items of noncompliance were identified.
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3 4.
Surveys Condition No. 8 of Special Nuclear Material License No. SNM-23 incorporates the licensee's Health and Safety Manual.
Section 8.4.1 of the Health and Safety Manual states " Fixed alpha activity shall be determined by direct measurement with survey meters."
Section 8.2 of the Health and Safety Manual specifies control levels for fixed alpha contamination levels for Smidgen Clean Areas ana clean Protective Clothing.
Section 8.4.4 of the Health and Safety Manual states, " Removable beta-gamma activity shall be determined by the swipe technique...."
Section 8.2 of the Health and Safety Manual specifies control levels for removable beta-gamma contamination for the general area and equipment work surfaces within the Fuel Manufacturing 1rea.
Section 8.3.1 of the Health and Safety Manual states that, "All areu shall be measured and recorded at least monthly.
The licensee does not make fixed alpha contamination surveys in Saidgen Clean Areas and on Clean Protective Clothing, and the licensee does not make removable beta-gamma contamination surveys for general areis and equipment work surfaces within the Fuel Manufacturing Area.
The inspector made this determination as he reviewed survey records.
As he reviewed the fixed alpha survey records he noted that the araas cited above were not included in the data.
He asked a licensee representative to explain why these areas were not included. The licensee representative stated that survey data for these areas were not included because the cited areas were not included in the survey program.
As the inspector reviewed the smear survey data for the Fuel Manufacturing Area he noted there was only one column containing survey results.
He asked a licen:ee representative to explain.
The inspector was informed that the data represented the results of smear surveys for alpha contamination. The inspector asked if surveys were made to determine the removable contaminaton levels for beta-gammas as required by the Health and Safety Manual. A licensee representative informed the inspector that surveys were not made to determine the removable beta-gamma contamination levels.
The inspector stated that failure to perform fixed alpha surveys and removable beta-gamma surveys represents noncompliance with the license conditions.
(79-08-01) 5.
Quality Assurance Program for Shipping Containers 10 CFF 71.51 states:
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4
"(a) The licer.se M 11 establish, maintain, and execute a quality assurance progran.
tisfying each of the applicable criteria specified in Appenoix E, " Quality Assurance Criteria for Shipping Packages for Radioactive Material," and satisfying any specific provisions which are applicable to the licensee's activities including procurement of packaging. The description of the quality assurance program shall include a discussion of which requirements of Appendix E are applicable and how they will be satisfied. A description of that program shall be filed, in accordance with this section, by January 1, 1979, with i.he Director, Office of Nuclear Material Safety and Safeguards, Nuclear Regulatory Coninission, Washington, D. C. 20555.
If a person has filed such a description, the continued use of his existing quality assurance program is authorized until the acceptability of the program has been finally determined by the Commission".
A licensee representative stated that they are not required to comply with 10 CFR 71.51 because the containers used at the facility are the property of the Department of Energy. As a result, the licensee withdrew the quality assurance program which had been submitted to NRC-NMSS in a timely manner. Applicability of the regulation to this facility is currently undergoing review by NRC:IE and NMSS headquarters.
The licensee does ship waste, but the representative stated that the amount of radioactive material shipped out as waste in any single container is always an exempt quantity.
No items of noncompliance were ider.tified.
6s Dosimetry The inspector reviewed dosimetry data for the period October 1978 through March 1979, for the purpose of determining whether the licensee was in compliance with the requirements of 10 CFR 20.101.
Approximately 50 employees were monitored by use of film badges.
The badges are analyzed quarterly.
No items of noncompliance were identified.
7.
Bioassay Section 5.5.1.1.1 of the Health and Safety Manual, incorporated by Condition No. 8 of Special Nuclear Material License No. SNM-23, requires urinalyses for enriched uranium quarterly for people employed more than 50 percent of the time in the Fuel Manufacturing Area, and scrap and salvage personnel. The inspector reviewed data for the period September 1978 to April 1979.
The data did not indicate any problems with exposure control.
No items of noncompliance were identified.
8.
Ventilation 1128 296
5 The Fuel Manufacturing Area (FMA) in which unclad enriched uranium is handled is normally maintained at a negative pressure so that the air flow is always towards the manufacturing area.
The glove boxes, press, and compactor are normally operated at a negative pressure also.
A licensee representative, at the inspector's request, made measurements, using a velometer at the respective locations to determine that the FMA and equipment therein were operated at a negative pressure.
No items of noncompliance were identifie6.
9.
Training Section 10.2 of the Health and Safety Manual requires that all employees involved in the handling of fissionable material shall be given a reorienta-tion lecture by the Health / Physics Officer on an annual basis.
The inspector reviewed records which indicated that 31 employees received the required lecture, prer 1ted by the Health / Physics Officer on August 25, 1978.
No items of noncomoliance were identified.
10.
Instrument Calibration Section 11 of the Health and Safety Manual requires that instruments be calibrated.
The licensee calibrates instruments quarterly.
The inspector reviewed calibration records for the period September 1978 through March 1979 to determine if the instruments were being calibrated at the required frequency.
No items of noncompliance were identified.
11.
Annual Report 10 CFR 20.407 requires that a personnel monitoring report, covering the preceding calendar year, must be submitted to the Director of Management and Program Analysis, U.S. Nuclear Regulatory Commission, within the first quarter of each calendar year.
The inspector reviewed the licensee's personnel monitoring report that had been submitted to the Director of Management and Program Analysis on February 9, 1979.
The report indicated that 54 individuals were monitored during 1978, and the maximum dose recorded was 340 millirem for the year.
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6 No items of noncompliance were identified.
12.
Termination Report 10 CFR 20.408 requires a licensee to submit a report of an individual's exposure to radiation and radioactive material incured during the period of employment to the Director of Management and Program Anlaysis when the individual terminates employment with the licensee.
Such report shall be furnished within 30 days after the exposure cf the individual has been determined by the licensee or 90 days after the dato of termination of employment or work assignment, whichever is earlier.
10 CFR 20.409 requires the licensee to notify the individual also if the licensee is complying with 10 CFR 20.408.
The inspector reviewed termination reports for seven individuals who termi-nated employment with the licensee during the period October 1978 through March 1979.
The reports had been submitted as required.
No items of noncompliance were identified.
13.
Contamination Control On June 20, 1979, the inspector performed two surveys in the HFIR area.
An alpha smear survey was conducted in the FMA, the Anti Room, and a Smigden Clean Area.
The smear survey revealed very low levels of removable contami-nation.
No removable contamination above the limits specified in the licensee's Health and Safety Manual were found.
A survey for fixed alpha contamination was performed in the Anti Room using the licensee's Ludlum alpha monitor.
All areas monitored were within the background count rate of the equipment used.
No items of noncompliance were identified.
14.
Breathing Zone Samoles Section 5.2.2.3 of the Health and Safety Manual states, "All personnel who spend more than 50% of their time within the FMA shall have their activities monitored by a breathing zone sample for at least one working day per week."
The inspector reviewed breathing zone data for two employees who spend more than 50 percent of their time in the FMA for the period January to June 1979, to determine that the samples were being taken as required, and to determine if regulatory limits were exceeded.
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7 No items of noncompliance were identified.
15.
Stack Samples The inspector reviewed stack sample data for the period January through May 1979 to determine that sampling was being performed, and to determine if the sample results were within regulatory limits.
No items of noncompliance were identified.
16.
Posting The inspector reviewed the posting of the facility to determine if it was posted in accord with the requirements of 10 CFR 19 and 10 CFR 20.
No items of noncompliance were identified.
17.
Receipt of Radioactive Material 10 CFR 20.205(b)(1) requires each licensee upon receipt of a package of radioactive material to monitor the external surfaces of the package for radioactive contamination.
The inspector reviewed documentation of two shipments being received.
A shipment, composed of seven packages was received in December 1978, and a second shipment, composed of eignt packages, was received in March 1979.
The documentation indicates that each package had been monitored as required by the regulation.
No items of noncompliance were identified.
18.
Ressirators The licensee is not required to adhere to the requirement of 10 CFR 20.103(c) because the licensee does not make allowances for the use of respiratory protective equipment, however, Section 5.2.3.5 of the Health and Safety Manual states that records will be kept on all assignments, inspections, repairs, and leak tests of respirators.
The inspector reviewed respirator records for the period December 1978 through May 1979, to determine if the license condition was being complied with.
No items of noncompliance were identified.
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8 19.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on June 21, 1979.
The inspector summarized the purpose and scope of the inspection, and the findings as presented in this report.
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