ML19350C030
| ML19350C030 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 03/11/1981 |
| From: | Coryell G, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19350C026 | List: |
| References | |
| 70-1113-81-02, 70-1113-81-2, NUDOCS 8103240724 | |
| Download: ML19350C030 (4) | |
Text
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b, UNITED STATES
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ATLANTA, G EoRGIA 30303 Report No. 70-1113/81-02 Licensee: General Electric Company P. O. Box 750 Wilmington, NC 23401 Facility Name: Wilmington Manufacturing Department License No. SNM-1097
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' inspector:
.Y F
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G. D. Ccryei{
' ate Signed Approved by:
Date Signed P. Kellogg, Section Cnief, RRPI Brancn
SUMMARY
Inspection on February 24-27, 1981 Areas Inspected This routine unannounced inspection involved 29 inspector-hours on site in the areas of organization, operations, nuclear criticality safety, facility changes and modifications, safety committees, and 10 CFR 21 implementation.
.Results Of the areas inspected, no violations or deviations were identified in the areas inspected.
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s-CETAILS 1.
Persons Contacted Licensee Employees "J. Bergman, Manager Fuel Manufacturing "D. Brown, Manager Powder Production "R. Patterson, Acting Manager, Fuel Fabrication "W. Hendry, Regulatory Comoliance Manager
' *B.' Kubeck,' Acting Manager' MA&S"
- G. Green, Manager Financial Operation "S. Dale, Manager Chemical Manufacturing Engineering
- W. Peters, Acting Manager, Nuclear Safety Engineering
- R. Foleck, Licensing Engineer A. Kaplan, Manager, Licensing and Compliance Audits W. Smalley, Sr., Engineer, Environmental Protection J. Taylor, Sr., Nuclear Safety Engineer W. Haverty, Compliance Auditor -
J. Bradberry, Emergency Preparedness Coordinator S. Murray, Nuclear Safety Engineer D. Whaley, Nuclear Safety Technician E. Dengler, Euyer, Fuel Cycle Procurement W. Pommitz, Manager, Direct Material Purchasing Other licensee employees contacted included three technicians, six operators, and two office personnel
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- Attended exit interv' ew i
2.
Exit Interview The inspection scope and fin' dings were summarized on' February 27, 1981 with those persons indicated in Paragraph 1 above. The new NRC enforcement criteria was discussed with licensee management.
l 3.
Licensee Action on Previous Inspection Findings Not inspected.
4 Unresolved Items l
. Unresolved items were not identified during this inspection.
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- 5. -
Organi:atiorr a.
P. J. vonHerrman, Manager of the Fuel Process Technology Department has transferred to the General Electric Lamps Division. The deoartment has since been reorganf red into two. departments;. Manufacturing Technology
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2 and Engineering Operaticns, J. L. Harmon, Manager and Microelectronics Acolications and Service Oceration, L. N. Grossman, Manager.
b.
The Regulatory Compliance Section organi:ation has not been changed except for scme personnel reassignments.
R. H. D. Foleck is now Licensing Engineer and W. C. Peters, Senior Criticality Engineer.
6.
10 CFR 21 Implementation a.
Procedures and records relating to 10 CFR 21 were examined.
Implementing procedures. include:
NEEG Procedure 70-42, Reporting of Defects and Noncompliance under 10 CFR part 21 or 50.55(e); P/P 30.7, Reporting Defects and Noncompliance and P/P 60.6 Preparation of Material Requests.
b.
One evaluation of a potential reportacle item was performed in 1980.
The information flow and technical evaluation was accomplished in conformance with procedural requirements. A cetermination was made that the item was not reportable pursuant to 10 CFR 21.
c.
The inspector verified that oosting requirements were met and that purchase orders contain 10 CFR 21 specificatiens where applicable. It was noted that it is a procedural ;equirement that each material requisition contain necessary information to inform Purchasing of applicability of 10 CFR 21. The licensee's purchase requisition forms and blueprints have printed boxes requiring a yes or no check for 10 CFR 21 applicability. No violations or-deficiencies were identified.
7.
Safety Committee Minutes of Wilmington Technologic'al Safety Council meeting conducted on October 7, 1980, February 5, 1981 and February 17, 1981, were examined.
Records verify that. membership, quorum and meeting requirements of the licensees procedure 40-1 and SNM license conditions were met. The inspector had no further comments.
8.
Facility Changes and Modifications a.
The inspector examined drawings, nuclear safety evaluations and safety committee reviews for major units of conversion process equipment and toured the installations.
b.
Review of the change requests verify that both facility equipment and process change requests were reviewed, approved and inspected in
'accordan'ce with the-licensee's procedures. Changes thct could involve radiation or criticality' safety ' onsiderations have written evaluations
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c and -acprovals by the safety function as required by section d.6 Acpendix A of the license application.
c.
Facility. and, process - changes are now being evalutted against. the criticality safety criteria specified in the licensee's document, NECE
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3 24697, Criticality Safety Criteria for' Fuel Manufacturing Ocerations with Low Enriched Uranium, oublished in Sectem er 1979. The criteria and documentation requirements meet or exceed criteria contained in Apcendix A of the license acplication that are current license conditions.
9.
Nuclear Criticality Safety a.
The inspector examined four nuclear safety analysis for equipment installations and verified that authorized analytical methocs were used
. and that.,the analysis was. rechecked and a: proved by a second qualified
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engineer.
Records co'nfirm that a. preoperational inscection had been performed prior to'i~ssuance of a nuclear safety release. Each instal-la. ion was also inspected and accacted by area management.
b.
Criticality safety limits were costec with PRCO docu=ents in the processing and storage areas.
During tours of the facility tne inscector observed that containers were placed in designated locations anc that fuel pellets anc rods are handled within safe slab require-ments. No deviations from posted limits were notec.
c.
Verification was made that waste and scrap SNM material is in acproved containers and storage locations.
The inspector was informec that tignt procedural controls on scrap segregation nas reduced the rate of waste box buildup by more than fifty percent.
d.
Regulatory Compliance audits for the period July 1980 through January 1981 were reviewed. Audit scope, frequency and distribution meet or exceed 41 cense-conditions and the licensee's procedure P/P 40-6, Regulatory Compliance Internal Audits.
Verification - was made that audit findings are reviewed by the Wilmington Technological Safety Council and that folicw up audits are performed to confirm corrective actions.
l e.
The new criticality alarm system was tested and calibrated during the l
Decemoer, 1980 shutdown. Approved testing and calibration procedures i
for tnis system have oeen issued by tne licensee.
- 10. Operations-a.
During tours of the coeratins areas, the inspector examined several operating nrocedures. - Procedures were found to be current and with required approval signatures. Operators questioned were aware of the locatior, and content of the procedures and posted control limits.
'b.
'Han"difhgand'thansf'er' of SNM was observ5d tio be in' approved contiainers and transport equipment and in accordance with procedural requirments.
c.
General housekeecing conditions acceared to be adeouate and no l'
incustrial: safety se fire ha:ards were identified.
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