ML20033H267
| ML20033H267 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 03/27/1990 |
| From: | Dan Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20033H265 | List: |
| References | |
| 70-1113-90-03, 70-1113-90-3, NUDOCS 9004190058 | |
| Download: ML20033H267 (3) | |
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ENCLOSURE 1 NOTICE OF VIOLATION i
9 General Electric Company Docket No. 70-1113 l
Wilmington, N.C.
License No. SNM-1097 During the-Nuclear Regulatory Comission (NRC) inspection : conducted on
. February 5-9, 1990, violations ' of NRC requirements were identified.. In i
accordance with the " General-Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1990), the violations are i
listed below:
A.
License Condition Number (No.) 9 of SNM-License'No.1097 requires that licensed material be used in accordance with statements, representations, and conditions of Part I of the License-Application dated October 23, 1987.
Part 1. Section 2.7.1 of the licensee's Application for License 1
No. SNM-1097 requires that radiation protection function activities be conducted in accordance with written procedures.
Process Requirements and 0perator Document (PROD)'No. 80.12. Rev. 9 dated November 18, 1989. requires in the FM0 Method Sheet, Step 15, that the can storage pad be kept locked whenever unattended.
Contrary to the above, the licensee failed to follow procedures for maintaining can storage pads locked in that..on February 7,1990, from approximately 5:00 p.m. until 6:15 p.m., Can Storage Pad 2 was noted to be unlocked with no personnel in attendance.
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This is Severity Level IV violation (Supplement IV).
3 B.
Licente Condition Number (No.) 9 of SNM-License No.1097-requires that licensed material be used in accordance with ' statements representations, and conditions of Part I of-the. License Application dated October 23 1987.-
Part 1, Section 2.7.1 of the licensee's Application for License No. SNM-1097 requires that radiation protection function activities be conducted in accordance with written procedures.
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Nuclear. Safety Instruction (NSI) No. E-3.0 Nuclear Safety Review Request, Revision.-(Rev.) 14 dated December 14, 1989, requires for. Facility Change i
Requests'(FCRs) requiring a radiological safety review that the Nuclear
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Safety Engineer compile and generate an. index of..all necessary documentation including, air flow verification data and drawings, i
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Genera 1' Electric Company Docket No. 70-1113 Wilmington, N.C.
2 License No. SNM-1097 1
NSI No. E-1.0, Nuclear Safety Review Records, Rev.13, dated December 19, 1990, details required air flow verification letter / memo. records, pertinent drawings and sketches, as. applicable, to be included as part of the Nuclear Safety Review records.
NSI No. E-7.0, Radiological Safety Review for Process and Equipment Change.
Request, Rev. 11, dated October 12, 1989, requires.the assigned NSE j
engineer' to ensure. that the required documents per NSI E-1.0, as appropriate, be included in the request file. folder.
1 Contrary to the above,.the licensee failed to follow procedures in-that on i
February 8,1990, the file folder for FCR No. _89.263, dated December 4 f
1989,; did not contain documentation of air flow evaluations conducted for the immediate areas-surrounding the Uranium Purification System'(UPS) q containment structure.
This is a Severity Level V' violation (Supp'lement IV).
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C.
License Condition ' Number (No.) 9 of SNM-License No.1097 requires that j
licensed material be used in accordance with statements, representations, and conditions-of Part I of the License Application dated 0ctober ~23, 1987.
r Part 1, Section 2.7.1 of the ' licensee's Application.for License No. SNM-1097 requires that radiation protection function activities be conducted in accordance with written procedures.
Nuclear Safety Release / Requirements- (NSR/R) Control No. 4.8.16. Rev. 8, _
dated November 7,1989, requires in Step 3. of the radiological safety section that the Queuing Pad in the Shop Support area _ near the_ Incinerator-t Building be clearly identified and posted " Caution - Radioactive Materials" and "Every Container In.This Area May Contain' Radioactive Materials."
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Contrary to above, the licensee failed to follow procedures for posting areas in that, on February 7,1990, the Queuing Pad -.in the Shop Support area was not posted with a: sign indicating ~ " Caution - Radioactive Materials" and "Every Container In This Area May: Contain Radioactive Materials."
L This is a Severity Level V violation (Supplement IV).
l Pursuant to the provisions of 10 CFR 2.201, General' Electric Company is hereby-required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:_ Document Control Desk, Washington, DC l20555, with a copy to the Regional Administrator, Region II, within 30 days'of_ the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation:- (1) admission or denial of.the violation, (2) the reason for the violation if admitted, (3) the-
. corrective steps which have been taken and the results achieved. (4) the i
corrective steps which will be taken' to avoid further_ violations, and (5) the
General Electric Company Docket No. 70-1113 Wilmington, N.C.
3
-License No. SNM-1097.
date when full. compliance will be achieved.
Where good-cause is shown, consideration will' be given to extending;the. response time.
If an adequate b
reply is not received within the time specified in this Notice, an order may be issued to show cause.why the ' license should not.be modified, suspended, or revoked or why such other action as may be proper should_ not be taken.-
FOR THE NUCLEAR REGULATORY COMMISSION:-
JRf4 hw -
Douglas M. Collins, Chief Emergency Prepa' redness and Radiological Protection Branch
. Division of. Radiation Safety and Safeguards Dated at Atlanta Geor a this 17frday of Afer 1990 l-L C -.
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NUCLEA3 CE ULATZY COMMISSION UNITED STATES
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IAAR 2 71990 keport No.: 70-1113/90-03 Licensee: General Electric Company Wilmington, NC 28401 Docket No.: 70-1113 t.icense No.: SNM-1097 Facility Name: General Electric Company Inspection Conducted:
February 5-9, 1990 Inspectors:
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) ate Signed Approved by:
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J. f, Potter, Chtef-Date Signed Facilities Radiation Protection Section Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards
SUMMARY
Scope:
This routine, unannounced inspection involved-review of licensee radiation protection (RP)activitiesincludingprogramstaffingandorganization, training, 4
radioactive contamination control, audits, internal and external exposure controls and evaluations; radioactive waste characterization, classification, and management; and transportation activities.
Results:
1 Demonstrated program improvements included -increased facility cleanliness and housekeeping, and upgraded breathing air monitoring and bioassay evaluations for; personnel working.on nontoutine tasks.
Training and verification of medical-qualifications for personnel potentially. exposed to radioactive materials were conducted in accordance with established RP program schedules.
Radioactive wasteL management issues and transportation activities were managed effectively and the associated procedures appeared to be technically adequate.
A recently vacated senior Nuclear Safety Engineering (NSE). technical position was noted as having a potential negative impact on RP-program activities.
Program weaknesses were-identified for the failure to follow procedures, for inadequacies in procedures, and for the lack of timeliness and effectiveness of licensee actions in