ML20037C987
| ML20037C987 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 03/17/1981 |
| From: | Kaplan A GENERAL ELECTRIC CO. |
| To: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8103300058 | |
| Download: ML20037C987 (1) | |
Text
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YKL GENERAL (njELECTRIC f~
NUCLEAR ENERGY PRODUCTS DIVISION
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WILMINGTON MANUF ACTURING DEPARWEW CASTLE HAYNE ROAD. P.O. BOX 780. WILMINGTON. N. C. 28402. (919) 343-5000 March 17, 1981 Mr. R.
C. Lewis, Acting Director Division of Resident & Reactor Proj ect Inspection U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, NW - Suite 3100 Atlanta, Georgia 30303
Dear Mr. Lewis:
(1) NRC Inspection Repor M 3/81-(L-,? ated 3/11/81 d
References:
(2) NRC License SNM-1097, Docket #70-1113 Thank you very much for your letter reporting the results of the inspection conducted at our licensed fuel 11brication plant by Mr. G. P. Coryell of your office on February 24-27, 1981.
This inspection report' does not contain any information which we believe to be proprietary.
Very truly yours, GENERAL ELECTRIC COMPANY Arthur L. Kaplan, Manager Licensing & Compliance, Audits M/C J26 ALK:bmw l
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NUCLEAR REGULATORY COMMISSION
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,o MAR 1 11981 General Electric Company ATTN:
J. A. Long, General Manager Wilmington Manufacturing Dept.
P. O. Box 780 Wilmington, NC 28402 Gentlemen:
Subject:
Report No. 70-1113/81-02 This refers t'o the 'rotitine safety 'inspec' tion conducted by G. P. Coryell of this office on February 24-27, 1981, of activities authorized by NRC License No.
SNM-1097 for the Wilmington Manufacturing facility and tc the discussi 1 of our findings held with J. E. Bergman at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of-this inspection, no violations or deviations were disclosed.
In accordance with Section 2.790 of the NRC's " Rules of Practice", Part 2, Title 10, Code of Federal Regulations, a. copy of this letter and the enclosed inspec-tion report will be placed in the NRC's Public Document Room.
If this report contains any' information that you (or your contractor) believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such application must include a full statement of the reasons on the basis of which it is claimed that the information is proprietary, and should be prepared so that proprietary information ider.tified in the application is contained in a separate part of the I
document.
If we do not hear from you within the specified period, the report will be placed in the Public Document Room.
Should you have any questions concerning this letter, we will be glad to discuss them with you.
Sinc 1
e AC,
. C. Lew s[ Acting director Division of Resident and Reactor Project Inspection
Enclosure:
(See Page 2)
c' General Electric Company 2
MAR 1 11981
Enclosure:
Inspection Report No.
70-1113/81-02 E
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101 MARIETTA ST., N.W., SulTE 3100 ATLANTA, GEORGIA 30303 Report No. 70-1113/81-02 Licensee: General Electric Company l
P. O. Box 780 Wilmington, NC 28401 Facility Name: Wilmington Manufacturing Department License No. SNM-1097 Inspector:
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G. P. Coryell Date Signed Approved by-P. Kellogg, Section Chief, pRPI Branch Date Signed
SUMMARY
Inspection on February 24-27,1981 Areas Inspected This routine. unannounced inspection involved 29 inspector-bours on site in. the.
areas of organization, operations, nuclear criticality safety, facility changes and modifications, safety committees, and 10 CFR 21 implementation.
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.Results-Of the areas inspec'ted,'no violations or deviations were identified in tr.e areas inspected.
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DETAILS 1.
Persons Contacted Licensee Employees "J. Bergman, Manager Fuel Manufacturing
- D. Brown, Manager Powder Production
- R. Patterson, Acting Manager, Fuel Fabrication
- W. Hendry, Regulatory Compliance 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, Buyer, Fuel Cycle Procurement W. Pommitz, Manager, Direct Material Purcha. sing Other licensee employees. contacted included three technicians, six operators, and two office personnel
- A'ttended exit intekv~iew
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2.
Exit' Interview The inspection scope.and findings'were' summarized on February 27, 1981 with those persons indicated in Paragraph I above.
The new NRC enforcement criteria was discussed with licensee management.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
IJnresolved Items Unresolved items were not identified during this inspection.
5.
Organization-
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.a.
. P. J. vonHerrman, Manager of the Fuel Process Technology Department has
- transferred to the General Electric Lamps Division. The department has (since,been e.eorgan.ized ir.to two dep'artments; Manufacturing Technology.
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i and Engineering Operations, J. L. Harmon, Manager and Microelectronics Apolications and Service Operation, L. N. Grossman, Manager.
b.
The Regulatory Compliance Section organization has not been changed except for some 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: NEBG Procedure 70-42, Reporting of c.
' ~~ ' Defects and-No'n' compliance '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 reportable item was performed in 1980.
The information flow and technical evaluation was accomplished in conformance with procedural requirements. A determination was made that the item was not reportable pursuant to 10 CFR 21.
c.
The inspector verified that posting requirements were met and that purchase orders contain 10 CFR 21 specifications where applicable.
It was noted that it is a procedural requirement that each material requisition contain necessary information to inform Purchasing of applicability of 10 CFR 21..
The 1.icensee's purchase. requisition _ forms-
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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, s
Minutes of Wilmington Technological 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 accordance'with the licensee's procedures. ' Changes that could involve radi~ tion'or criticality sa'fety considerations have written evaluations
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a and approvals by the safety function as required by section 4.6 Appendix-A of the license application.
Facility-and. process. changes :are now being. evaluated ag inst _ the
- c.,' criticality safety ~ criteria specified in the licensee's document,' NEDE y
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3 24697, Criticality Safety Criteria for Fuel Manufacturing Operations with Low Enriched Uranium, published in September 1979. The criteria and documentation requirements meet or exceed criteria contained in Appendix A of the license application 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 methods were used and that the analysis was rechecked and approud by a second qualified I
'eng'ineeF.lRecords' confirm. thit 'a preoperational ins'pection' had 'been i
- performed prior to issuance of a nuclear safety release. Each instal-lation m also inspected and accepted by area management.
b.
Criticality safety limits were posted with PROD documents in the processing and storage areas.
During tours of the facility the inspector observed that containers were placed in designated locations and that fuel pellets and rods are handled within safe slab require-i' ments. No deviations from posted limits were noted.
c.
Verification was made that waste and scrap SNM material is in approved containers and storage locations.
The inspector was informed that i
tight procedural-controls on scrap segregation has 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. license conditions-and the licenseets: procedure P/P 40-6,
. Regulatory Comp 1.iance.. Internal Audits.
Verification was made that audit findings are. reviewed by the Wilmington Technological Safety Council and that follow up audits are performed to confirm corrective actions.
I e.
The~new criticality alarm system was tested and calibrated during the December, 1980 shutdown. Approved testing and calibration procedures for_ this system have.been issued by the licensee.
10.
Operations a.
During tours of the operating areas, the inspector examined several operating ~ procedures.
Procedures were found to be current _and-with required approval signatures. Operators questioned were aware of the location and content of the_ procedures and posted control limits.
-Handli'ng' ~ nd ' transfer of SNM JW'as' observed 'to' be' in approved containers b.
a and transport equipment'and in accordance with procedural requirments'.
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- c.
-General housekeeping cond.itions.' appeared L te ~ be_ adequate and. no i
-industrial safety.or fire hazards were identified.
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