ML19309H375
| ML19309H375 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 04/21/1980 |
| From: | Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309H370 | List: |
| References | |
| 70-1113-80-05, 70-1113-80-5, NUDOCS 8005130114 | |
| Download: ML19309H375 (5) | |
Text
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4 UNITED STATES 5005130n4 '
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NUCLEAR REGULATORY COMMISSION REGION 11 0
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101 MARIETTA ST., N.W., SUITE 3100
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4 ATLANTA, GEORGIA 30303 APR 211980 Report No. 70-1113/80-05 Licensee: General Electric Company Wilmington, North Carolina 28401 Facility Name: Wilmington Manufacturing Department Inspector:
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J. B. Kah'e ~
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Approved by:
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J. B. Ka e',~ Acting Section Chief, Date Signed Safegua ~ s Branch Date of Inspection: March 31 - April 4, 1980 Areas Inspected:
This routine, unannounced inspection involved 33 inspector-hours onsite in the areas of facility changes and modifications, safety committees, internal audits and reviews, operations review, followup on ii. ems of noncompliance, followup on unresolved items, followup on an IE information notice and independent effort.
Results:
Of the 8 areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- W. W. McMahon, Acting Department General Manager
- J. E. Bergman, Fuel Manufacturing Manager
- E. A. Lees, Quality Assurance Manager
- C. E. Cliche, Fuel Fabrication Operation Manager
- B. F. Bentley, Fuel Chemical Operation Manager
- W. J. Hendry, Regulatory Compliance Manager
- A. L. Kaplan, Licensing and Compliance Audits Manager 3
- J. A. Mohrbacher, Nuclear Safety Engineering Manager
- P. J. von Herrmann, Fuel Process Technology Manager
- C. H. Risley, Acting Materials Manager
- G. E. Green, Finance Manager G. Finders, Compliance Auditor W. Haverty, Compliance Auditor J. Taylor, Nuclear Safety Engineer W. Peters, Senior Nuclear Safety Engineer D. Whaley, Ra'diation Safety Technician R. Patterson, Pellet Production Manager G. Palmer, Fuel Support Manager A. Cameron, Fuel Support Foreman B. Beane, HVAC Engineer D. Brown, Powder Production Manager F. Sweet, Assembly Area Foreman Other licensee employees contacted included eight operators.
- Attended exit interview.
2.
Exit Interview j
The inspection scope and findings were summarized on April 4, 1980, with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance 80-1-1: Failure to chock UF6 cylinders and to place valve protecters on cylinders when cylinders were temporarily stored in the truck aisleway next to the cylinder dock. The inspector verified that operators have been reinstructed concerning proper chocking of cylinders and the use of valve protectors. During an inspection of the area, it was observed that cylinders were chocked and valve protectors were properly ~
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(Closed) Noncompliance 80-1-2: Failure to conduct a criticality safety analysis for storing cylinders of uranium hexafluoride in the trunk aisleway
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by the cylinder dock. The inspector verified that a nuclear safety analysis has been completed detailing the criticality safety and other requirements for storing cylinders of uranium hexafluoride in the truck aisleway.
(Closed) Unresolved Item 79-19-02: Certificate of Compliance 17-9019 specified that the H/U-235 ratio of the contents shall not exceed 0.45.
The Certificate of Compliance has been revised (Revision 4, dated March 18, 3
1980) to correctly state that the H/U ratio shall not exceed 0.45.
(Closed) Unresolved Item 79-19-04.
Certificate of Compliance 71-9019 specified that a 17H specification container be used for the outside con-
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tainer. The Certificate of Compliance was revised (Revision 4, dated March 18, 1980) to authorize an alternative container with two rolling hoopes instead of the 17H specification container.
5.
Operations Review l
a.
Procedures During a tour of the FM0 process areas, the inspector examined several operating procedures. The procedures were current and in the licensee's established format for process requirements and operating documents (PROD's). Operators were cognizant of the location of the procedures and the procedure safety requirements.
It was observed that the general procedures for the process area nuclear safety requirements were posted in the change rooms.
b.
Storage Arrays of SNM It was observed that SNM was stored in approved arrays and in accor-dance with nuclear safety requirements. Containers of SNM were not stacked and were placed in designated locations. Separation of con-tainers was maintained where moisture content was unknown. Pellets were stored on approved trays and carts. Fuel rods were stored in approved cabinets and/or safe slab arrays.
c.
Handling and Transfer of SNM i
It was observed that SNM was placed in approved containers and moved within the area on approved transfer carts and in accordance with the nuclear safety requirements.
d.
Postings The licensee does not post the mass (weight) limit for storage of cans of UO2 powder in limit squares on the floor in the conversion area.
They stated that the 35 kgs limit is better maintained and controlled by procedural control (PROD's), personnel training and the 35 kgs
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container gross weight go-no go scale limit at the container lift i
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station. The scale limit is part of the material control and accounta-bility MICS system for not accepting transactions for containers weighing more than 35 kgs gross weight.
e.
Housekeeping Housekeeping conditions appears to be adequate. There were no apparent industrial safety or fire hazards.
6.
Safety Committees The inspector examined procedure, P/P 40-1, Rev. 4, Wilmington Techno-a.
logical Safety Council. The procedure provides for the charter of the Wilmington Technological Safety Council (VISC).
It outlines the Council responsibilities and the responsibilities of the members of the Council.
It sets forth the procedural requirements for conducting business and documenting minutes of meetings.
b.
The inspector examined the minutes for meetings of March 16, May 14, September 10, September 25 and October 8, 1979, January 31, February 15 and February 26, 1980. The minutes showed that the required members l
were in attendance and that the frequency of meetings met the license condition requirement. Meeting topics pertained to the health and safety considerations for major changes in procedures, processes, facilities and equipment.
7.
Internal Audits The inspector examined procedure P/P 40-6, Rev. 4, Regulatory Compliance Audits. The procedure establishes the system for conducting audits, reporting results, performing corrective actions and maintaining the associated documentation. The inspector examined the audit schedule and the results of audits performed by the Compliance Auditors and the Nuclear Safety Engineers. The timeliness for corrective actions was discussed with licensee representatives. They stated that the assignment of priorities for corrective actions was based upon items and issues which had the major safety significance.
8.
Facility Changes and Modifications The inspector examined several change requests and associated documentation.
Verification was made that the change requests, reviews and analyses, approvals and preoperational inspections were performed in accordance with the licensee's procedural requirements. Verification was also made that change request releases were made by the nuclear safety engineering function and that management had acknowledged that the request had been completed and accepted the project.
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The inspector verified that the licensee received IE Information Notice 80-11, Generic Problems with ASCO Valves in Nuclear Applications including Fire Protection Systems. They stated that responsibilities have been assigned to determine if the equipment identified in the Notice is in the licensee's facilities.
10.
Previous Unresolved Items Two previously identified unresolved items, 79-19-01 and 79-19-05, remain unresolved. Licensee representatives discussed procedural changes to resolve these items, however, the procedures were in the process of being revised and the final approvals had not been obtained. They were informed that the revised procedures would be examined during a subsequent inspection.
f 11.
Sludge Buildup in Large Tanks i
The inspector examined documentation showing that a visual inspection had been made of the ammonium recovery storage tanks on December 5 and 7, 1979.
Only trace quantities of solids were detected with much less than 0.03 percent uranium by lab analysis.
12.
Criticality Alarms The licensee has had two plant evacuations due to unexplainable false alarms of the new criticality warning system.
It is apparent that the problem is in the data acquisition modules. The vendor plans to be on site from April 7 to April 18, 1980, to check out equipment components and make study to determine if there may be a systems problem or damage to components d
due to installation or possibly lightning. Licensee representatives were informed that Region II inspectors would continue to follow the status of the criticality warning system.
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