ML19260D866
| ML19260D866 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 12/12/1979 |
| From: | Coryell G, Gillespie F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260D858 | List: |
| References | |
| 70-1151-79-17, NUDOCS 8002120528 | |
| Download: ML19260D866 (5) | |
Text
[aasauq'o, UNITED STATES NUCLEAR REGULATORY COMMISSION o
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101 MARIETTA ST., N.W, SUITE 3100 k
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ATLANTA, GEORGIA 30303 DEC 121979 Report No. 70-1151/79-17 Docket No. 70-1151 License Fo. SNM-1107 Licensee: Westinghouse Electric Corporation Nuclear Fuel Division Columbia, South Carolina 29205 Facility Name:
Columbia Nuclear Fuel Inspection at:
Columbia Nuclear Fuel Plant Inspection conducted: November 27-30, 1979 7'
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Inspector:
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. G. P. Coryell
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Date Approved by:
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F.'P. Gillespie,/ Chief, MC&A Section, Safeguards Date Branch Inspection Summary Areas Inspected: This routine, unannounced inspection involved 29 inspector-hours onsite in the areas of Operations, Nuclear Criticality Safety, Maintenance, Procedure Control, Safety Committees and followup on IE Bulletin 79-19 " Packaging of Low Level Radioactive Waste for Transport and Burial".
Results: Of the six areas inspected, no apparent items of noncompliance or deviations are identified in five areas; one apparent item of noncompliance was found in one area (Deficiency posting incorrect criticality control limits for a work station in the scrap recovery area) (79-17-01).
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REPORT DETAILS 1.
Persons Contacted M. D'Amore, Plant Manager
- R. J. Wiggins. Acting Plant Manager
- W. H. Britton, Manager, Chemical Operations
- W. L. Goodwin, Manager, Regulatory Compliance
- C. F. Sanders, Manager, Radiological & Environmental Service E. K. Reitler, Jr., R&ES, Fellow Engineer H. T. King, Nuclear Criticality Engineer C. W. Herthum, Supervisor, Maintenance & Construction R. O. Noe, Chemical Development Engineer L. R. Turner, Supervisor, Chemical Manufacturing N. Stevenson, Supervisor, Chemical Manufacturing M. Jump, Manager, Analytical Services Other licensee employees contacted included 4 technicians, 6 operators and 2 mechanics, 2.
Exit Interview The inspection scope and findings were summarized on 11/30/79 with those persons indicated in Paragraph I above.
Licensee representatives discussed the status of the facility expansion.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Safety Committees The Regulatory Compliance Committee meeting minutes for September, a.
October and November monthly meetings were examined. Agenda topics include regulatory changes, NRC license amendment status, regulatory compliance inspection findings, ALARA Activity, Airborne Radiation Task Force activities and unusual incidents. Attendance requirements were met.
b No items of noncompliance or deviations were identified.
6.
Criticality Safety Several nuclear safety evaluations of new processes and equipment a.
changes were examined to verify that approved nuclear criticality P350 044
criteria were used and that review procedural requirements were accomplished. All evaluations had been checked by an independent reviewer for accuracy.
b.
Verification was made that a floor plan of the SNM process and fixed storage areas showed spacing requirements imposed to control neutron interaction as required by license condition No. 37.
The inspector reviewed the criticality alarm calibration and test c.
records and verified that the criticality detection and alarm system in the expansion area was calibrated and functioning.
d.
The inspector observed that SNM was placed in storage arrays in accor-dance with procedures and posted limits and that arrays of waste containers were in approved arrays and within established SNM limits.
7.
Operations Operations in progress were audited during tours of the plant.
a.
Operating procedures in the Chemical Conversion area were examined, these included temporary changes on Process Information Forms (PIF) and Supplemental Operating Instructions (SOI).
The procedures have been reviewed and approved in accordance with the licensee's Procedure Control System.
b.
Plant expansion and ventilation system construction work was in progress during the inspection period.
General housekeeping conditions were good and no significant industrial safety hazards were observed.
The inspector observed that criticality limit signs were posted at c.
work stations and storage areas. An incorrect criticality limit sign was posted at the washer work station in the scrap recovery area.
Posted limits were inappropriate and in a nonconservative direction.
Station records verify that operat. ions were being conducted correctly in that batch limits have been within procedural requirements. The improper posting is contrary to procedural requirements and leads to employee disregard for posted signs.
Licensee representatives were informed that this was an item of noncompliance (79-17-01).
8.
Procedure Control Procedure development is established by line management with the a.
approval of cognizant staff components. Each functional group develops, distributes and controls procedures and is responsible for obtaining reviews and approvals defined by administrative procedures and requirements of License Conditio >No.~31.
b.
The inspector reviewed a selected group of Chemical Operations proce-dures for required approvals, applicable nuclear criticality safety, F)SO 045
radiation safety requirements and sign offs.
It was observed that R&E Engineering has provided, in many instances, an attachment to the procedure that covers safety requirements.
No items of noncompliance or deficiencies were identified.
9.
Maintenance Maintenance work is initiated by use of a work order system as defined a.
in plant procedure SY-509 " Maintenance Work Order and Permit". The work order will require a safety observer, tank entry permit or cutting /
welding permit as needed. A Radiation Work Permit is required for jobs where a potential for exposure from operations may exceed 25% of the Appendix B limit.
The radiation protection requirements are established by R&E Engineering.
b.
Maintenance work is conducted in conformance with Facilities Planning procedures.
Series 100 " Administrative", Series 200 " Instrument Calibration & Monitoring" or Series 300-800 " Maintenance and Opera-tions".
Several work order records were checked for conformance with proce-c.
dural requirements and instructions, ie: RWP Coverage, Cutting / Welding Permit. No items of nonconformance were identified.
d.
Instrument calibrations are performed as defined in procedure FP-200
" Industrial Instrument Calibration".
Calibration and Preventive Maintenance scheduling is controlled by a computer program.
Calibra-tion records for selected safety related instruments were checked and no items of noncompliance or deviations were identified.
10.
IE Bulletin No. 79-19 The licensee's response to IE Bulletin No. 79-19 was timely and a.
addressed each action item.
b.
The licensee has current copies of DOT and NRC regulations for the transfer, packaging and transport of low-level radioactive waste material.
Copies of these documents and the Chem-Nuclear, NRC and State of South Carolina license requirements are available to personnel responsible for low level radioactive waste handling and shipment.
A management appointed team audit of waste handling procedures and c.
practices was performed by October 10, 1979.
Corrective actions based on audit findings include:
(1) revising existing procedures foc_each of the six functional groups involved in waste handling and transport.
(2) developing new procedures for loading scrap boxes and control of low level radioactive material outside of the plant.
(3) preparation of instructions for utility operators regarding specific packaging requirement.
(4) coordinate among the functional groups involved.
Procedure modifications and personnel training will be implemented by March 31, 1980. Some retraining meetings have been conducted.
d.
Verification was made tnat a routine audit function of activities associated with low level radioactive waste handling was scheduled to be in effect by December 31, 1979. Audits are to be defined in scope and will require written reports to management.
The inspector observed the repackaging of some boxes of noncombustible e.
waste to waste drums being prepared for shipment. No liquid waste solidification was in progress during the inspection period. Five drums of low level radioactive waste awaiting shipment were opened and examined.
There was no liquid in any of the drums and contents were as labeled. Containers were not damaged.
f.
No items of noncompliance or deviations were identified within the scope of this inspection.
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