ML20133P270

Insp Rept 70-0824/85-06 on 850705-16.No Violations or Deviations Noted.Major Areas Inspected:Mgt Organization & Controls,Nuclear Criticality Safety,Procedures,Operations Reviews & Audits

ML20133P270
Person / Time
Site:	07000824
Issue date:	07/30/1985
From:	Mcalpine E, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133P268	List: ML20133P264 ML20133P270
References
70-0824-85-06, 70-824-85-6, NUDOCS 8508140243
Download: ML20133P270 (4)

Text

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u UNITED STATES

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• o NUCLEAR REGULATORY COMMISSION

[ g REGION ll g j 101 MARIETTA STREET, N.W.

• ATLANTA, GEORGIA 30323

%.....*# AUG 011985 Report Nos.: 70-824/85-06 Licensee: Babcock and Wilcox Company 1 Lynchburg Research Center Lynchburg, VA 24505 Docket No.: 70-824 License No.: SNM 778 Facility Name: Lynchburg Research Center Inspection Conducted: Jul 15- , 1985 Inspector: -

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G. L. Troup " '[ Date Signed Approved by: M bb E. J. McAlpfhe, Chief, Material Control and 7[3O[f5 Date Signed Accountability Section, Nuclear Materials Safety and Safeguards Branch, Division of Radiation Safety and Safeguards

SUMMARY

Scope: This routine, unannounced inspection entailed 11 inspector-hours on site in the areas of Management Organization and Controls, Nuclear Criticality Safety, Procedures, Operations Review and Audits.

Results: No violations or deviations were identified.

8508140243 s C ADOCK 07000824 PDR

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REPORT DETAILS

1. Persons Contacted Licensee Employees

• A. E. Wehrmeister, Manager, Systems Development Laboratory

• C. E. Bell, Manager, Facilities F. M. Alcorn, Supervisor, Nuclear Criticality Safety

• W. S. Pennington, Health Physicist R. L. Bennett, Manager, Building C Decontamination Project M. N. Baldwin, Research Specialist

• Attended exit interview

2. Exit Interview The inspection scope and findings were summarized on July 16, 1985, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the licensee. 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 This subject was not addressed in the inspection.

4. Management Organization and Controls (88005)

a. The inspector verified that the organization of management conforms to the organization described in the application and license. There have been no management or supervisory changes which relate to licensed activities. No violations or deviations were identified.

b. The inspector reviewed the minutes of the Safety Review Committee (SRC) meeting of May 13, 1985, and verified that the requisite members were present. The topics covered by the committee included a review of the Safety Audit Subcommittee audit report and the LRC responses to NRC Notices of Violation. No violations or deviations were identified.

5. Procedures Controls (88005, 88015)

Administrative procedures RDD-1706-09, " Procedure for the Preparation, Approval and Control of Area Operating Procedures," and RDD-1706-10,

" Procedures Required for Compliance with Federal Regulations" establish guidance for initiation, review, approval, distribution and revision of laboratory procedures. The inspector reviewed six area operating procedures which had been initiated or revised during the last four months. All had

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6. Audits (88005, 88015)

a. The inspector verified that the Safety Audit Subcommittee met during the requisite time frame for audits (every four months) by meeting April 15-16, 1985. Identified items were documented and corrective action on previous items were verified. These items were reviewed by the Safety Review Committee. No violations or deviations were identified.

b. The inspector reviewed the reports and verified that monthly audits were conducted by the nuclear safety officer and the health physicist and the quarterly reports had been submitted to the Laboratory Director, as required by the license. No violations or deviations were identified.

7. Nuclear Criticality Safety (88015, 88025)

a. The inspector discussed the methods used and computer models available for performing nuclear criticality calculations with the cognizant supervisor. While there have been no modifications or changes initiated since the last inspection, the licensee has several programs available for any required calculations, such as the KEN 0 IV, ANISN and SCALE programs.

b. The inspector reviewed the plant records for the testing of the criticality monitoring system and the building evacuation alarms for the period April - June 1985. No violations were identified. The inspector observed that the test schedule for the monitoring system includes detectors which have been removed from Buildings A and C.

This was discussed with licensee representatives, who acknowledged that the test sequence is out of date, and stated that the schedule would be updated to reflect only those detectors still in service. The inspector had no further questions.

8. Operations Review (88015, 88020, 88025)

a. Decommissioning work for Building C is continuing. All SNM previously used or stored has been removed from the building. Removal of residual contamination, including drain and sewer lines, dirt, and paint is essentially complete. Materials are being segregated in waste drums for survey and disposal . A new glove box structure has been erected for the survey of waste materials prior to final packing and disposal.

b. General housekeeping was acceptable in Buildings B and C. No accumulations of combustibles were observed, u

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c. The inspector discussed the methods and procedures used to control facility modifications and maintenance activities. Major facility changes or modifications are submitted to the SRC for review and approval prior to initiation. Modification and maintenance activities are covered by Radiation Work Permits (RWPs). The procedure requires that a planning meeting be held when the RWP is being prepared so that all participants are aware of the requirements. Additionally, the responsible foreman signs the RWP prior to starting that the workers have been briefed on the requirements. Requirements for cutting and welding permits are specified in the Industrial Safety Manual . The inspector reviewed two RWPs in effect and discussed the requirenents with licensee representatives. No violations were identified.

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