ML20133E618

Insp Rept 70-1201/85-05 on 850611-14.Violation Noted: Individual Allowed to Wear Respirator More than 12 Months After Last Physical & SNM Shipped to Another Licensee W/O Ensuring Type of SNM Authorized to Receive

ML20133E618
Person / Time
Site:	07001201
Issue date:	07/12/1985
From:	Albright R, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133E575	List: ML20133E571 ML20133E586 ML20133E618
References
70-1201-85-05, 70-1201-85-5, NUDOCS 8508070762
Download: ML20133E618 (5)

Text

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n REGION 11 g j 101 MARIETTA STREET,N.W.

• I e ATLANTA, GEORGI A 30323

\ *"** / JUL 1719g5 Report No.: 70-1201/85-05 Licensee: Babcock and Wilcox Company Commercial Nuclear Fuel Plant Lynchburg, VA 24505 Docket No.: 70-1201 (CNFP) License No.: SNM-1168 Facility Name: Commercial Nuclear Fuel Plant Inspection Conducted: June 11-14, 198a Inspector: 7-/2-if R. H. Albright Date Signed Approved by: h3h '7[/L)p5 C. M. Hosey,'Section 1:hief Date Sfgned Division of Radiation, Safety and Safeguards

SUMMARY

Scope: This routine, unannounced inspection involved 12 inspector-hours on site in the areas of radiation protection, solid radioactive waste management, and transportation of radioactive material.

Results: Two violations were identified - An individual was allowed to wear a respirator for more than 12 months after his last physical and the licensee shipped special nuclear material (SNM) to another licensee without ensuring that the receiver was authorized to receive the type, form, and quantity of SNM in the shipment.

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a REPORT DETAILS

1. Persons Contacted Licensee Employees .

R. A. Alto, Plant Manager C. W. Speight, Manager, Facilities and Services K. E. Shy, Health Physicist B. W. Pugh, Production and Material Control J. P. Watters, License and Control Administrator

2. Exit Interview .

The inspection scope and findings were summarized on June 14, 1985, with those persons indicated in paragraph 1 above. The violation of 10 CFR 20.103 for allowing an individual to wear a respirator for more than 12 months after his last medical evaluation for respirator use was discussed in detail. The plant manager acknowledged the violation.

The inspector notified the facility Health Physicist by telephone on June 19, 1985, of a violation of 10 CFR 70.42 for not having determined prior to shipment of SNM that the receiver was authorized to receive the type, form and quantity of SNM to be shipped.

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.

3. Licensee Action on Previous Enforcement Matters (Closed) VIO (70-1201/84-09-01) This violation concerned the failure to have management approved instrument calibration procedures. The inspector reviewed and verified the corrective actions as stated in B&W Commercial Nuclear Fuel Plant letter of November 8, 1984.

(Closed) VIO (70-1201/84-10-01,02,03,04) This violation concerned an -

improper shipment of SNM. The inspector reviewed and verified the l corrective actions as stated in B&W Commercial Nuclear Fuel Plant letter of February 8, 1985.

4. Radiation Protection (83822)

a. Instruments and Equipment License Application Section 8.3.4 identifies radiation protection instrumentation and the frequency of cali'sration. The inspector observed the instrumar.tatior, and found it operable aad within tFe calibration frequency.

No violations or deviations were identified.

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b. External Exposure Controls 10 CFR 20.101 specifies the applicable radiation dose standards. The inspector reviewed the computer printouts (NRC Form 5 equivalent) for the period July 1984 through March 1985.

No violations or deviations were identified.

c. Posting, Labeling, and Control 10 CFR 20.203 and the license specify posting and labeling requirements for containers and areas. Observations by the inspector revealed that labeling and posting were in accordance with the requirements of 10 CFR 20.203 and the license.

No violations or deviations were identified.

'd. Contamination Control License Application Section 8.4.5 specifies controls to be exercised over contamination throughout the plant. Review of r.ecords and observations by the inspector revealed that the program complies with the contamination control requirements.

No violations or deviations were identified.

e. Radiological Surveys 10 CFR 20.201(b) and 10 CFR 20.401(b) require that appropriate radia-tion surveys be made and records maintained of the survey results. The inspector reviewed selected radiation survey records for the period January through June.1985.

No violati'ons or deviations were identified.

f. Notifications and Reports 10 CFR 20 states certain reports and notification requirements as follows:

10 CFR 20.402 - Loss or theft of material 10 CFR 20.403 - Incidents 10 CFR 20.405 - Overexposure .

10 CFR 20.408 - Termination of work report 10 CFR 19.13 - To individuals Review of records and discussions with licensee representatives

resesled that the licensee has complied with the above requirements.

No violations or deviations were identified.

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g. Bioassay 10 CFR 20.103 and License Application Section 8.4 3 specify action levels for the internal exposu*e and bioassay programs. The inspector reviewed bioassay data for selected individuals for the period January through April 1985. None of the data reviewed indicated that individuals had exceeded any action levels.

No violations or deviations were identified.

h. Air Sampling 10 CFR 20.103 and License Application Section 8.2.3 specify air sampling requirements. The inspector observed air sampling equipment and reviewed records of air sampling results for the period January through June 1985.

No violations or deviations were identified.

1. Engineering Controls 10 CFR 20.103 and License Application Section 8.2 specify the use of engineering controls in order to limit the use of respirators.

Engineering controls were observed in the controlled area where there was a potential for airborne radioactive materials.

No violations or deviations were identified.

j. Use of Respirators 10 CFR 20.103 specifies the requirements for the respiratory protection program when the licensee makes use of respiratory protective devices in estimating exposure to airborne radioactive material. One require-ment is that prior to first use of a respirator and every 12 months thereafter, a physician must determine that the respirator user is physically able to use the respirator. The inspector reviewed records that indicated one individual had worn a respirator and it had been more than 12 months since the individual had been evaluated by a physician for use of a respirator. The individual was last evaluated by a physician on October 6,1983. The individual wore a respirator l and allowance was made for the use of the respirator on February 13, l 1985, and March 6, 7, and 9, 1985. The individual was re-examined by a l

physician for his ability to wear a respirator during the week of the inspection and passed the physical. The use of the respirator after more than 12 months had passed since the last physical was identified

, as an apparent violation of 10 CFR 20.103. (70-1201/85-05-01)

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5. Solid Padioactive Waste Management (84850 and 88035)

! 10 CFR 20.103, 20.311, and 20.401 and 10 CFR 61.55 and 61.56 contain

!- requirements for disposal of solid radioactive waste and records that must

4 be kept. The inspector reviewed selected records of radioactive waste shipments for the period July to December 1984. The licensee made shipments of contaminated waste to another B&W facility located in Apollo, Pennsylvania, on September 24 and December 12, 1984. The licensee stated that B&W Apollo was not considered a waste collector or reprocessor. The receiver's only function was to receive the material, crush the drums for radwaste volume reduction, and put it in a new outside package for shipment to a land disposal facility. The B&W Apollo facility makes independent measurements of the material in the shipment prior to sending it to the burial grourd. It was determined that the B&W facility at Apollo, Pennsylvania, was not considered.a waste collector and that the requirements of 10 CFR 20.311 and 10 CFR 61 were not applicable to these shipments.

No violations or deviations were identified.

6. Transportation of Radioactive Material (86740) 10 CFR 71.5 requires that licensees who transport licensed material outside the confines of its place of use or delivers such material to a carrier for transport shall comply with the requirements of 49 CFR Parts 170 through 189.

The inspector determined through discussions that the licensee has clearly delineated individuals, organizational entities, authorities and responsibi-lities for transportation activities. The inspector reviewed procedure AS-1111, Shipment and Receipt of Radioactive Materials, which defines individual responsibilities and requirements for shipping radioactive material s .

10 CFR 70.42 requires that prior to transferring SNM to another licensee the licensee verify that the receiver's license authorizes receipt of the type, form, and quantity of SNM to be transferred. The licensee used a 1977 B&W Apollo license to determine the type, form, and quantity of SNM that B&W Apollo could receive in transferring SNM to them on September 24, 1984, and December 12, 1984. The 1977 license was not current. The inspector discussed the conditions in the B&W Apollo license with NRC Region I. It was determined that B&W Apollo was authorized to receive the SNM transferred on these dates. The failure to verify prior to shipment that the receiver's license authorized receipt of the type, form, and quantities of SNM transferred was identified as an apparent violation of 10 CFR 70.42.

(70-1201/85-05-02)