ML20205R299
| ML20205R299 | |
| Person / Time | |
|---|---|
| Issue date: | 04/21/1999 |
| From: | Quay T NRC (Affiliation Not Assigned) |
| To: | Kipp C GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20205R304 | List: |
| References | |
| REF-QA-99900003 99900003-99-201, NUDOCS 9904220281 | |
| Download: ML20205R299 (2) | |
Text
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UNITED STATES y_
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.c. 2055 % 001
- ,o April 21, 1999 Mr. Craig P. Kipp General Manager Nuclear Fuel GE Nuclear Energy Nuclear Energy Production P.O. Box 780 Wilmington, NC 28402-0780
SUBJECT:
NRC INSPECTION REPORT NO. 99900003/1999201
Dear Mr. Kipp:
This refers to the inspection conducted by Robert Pettis, Jr. and Dr. Shih-Liang Wu of this office on March 22-25,1999. The purpose of the inspection was to review the implementation of selected portions of the General Electric Nuclear Energy (GE-NE) QL ality Assurance Program Description (NEDO-11209), including 10 CFR Part 21, as it relates to the activities performed in the Chemet laboratory. The team reviewed technical documentation, procedures, representative records, and also interviewed GE-NE personnel. At the conclusion of the inspection, the findings were discussed with members of your staff.
On the basis of this inspection, the team determined that certain of your activities appeared to be in violation of NRC requirements, as specified in the enclosed Notice of Violation (Notice).
Specifically, the NRC inspection team identified a potential deviation in which a laboratory analyst failed to perform over 20 required weekly calibrations of the LECO hydrogen analyzer over the past three years. The analyzer is used to perform hydrogen tests for both zirconium fuel cladding and ceramic fuel pellets. Preliminary evaluation results performed by GE-NE during the inspection identified several fuel pellets which appear to exceed the GE-NE specification limit for hydrogen of 1 part per million.
A similar issue regarding a different analyst was raised intemally to GE-NE by an employee in late 1998. That review, evaluated only as an employes integrity issue, concluded that no integrity problem existed since only one calibration had been performed by the analyst in the six months preceding the date of the concern. However, the review did not trigger a parallel review for applicability under 10 CFR 50, Appendix B, and 10 CFR Part 21 which was required to evaluate the possibility that other laboratory analysts may have performed inadequate calibrations over the years possibly resulting in the shipment of nonconforming material to operating nuclear plants. At the conclusion of the inspection on March 25,1999, GE-NE initiated Potential Safety Concern 9907 and Corrective Action Request 2170 to evaluate the condition under the reportability requirements of 10 CFR Part 21. The violation is of specific concern to the NRC since it has the potential to affect fuel performance for the affected plants.
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The report also includes an unresolved item for which the team needs additional information to reach its conclusions. GE-NE is requested to submit a written response to this item, which is e q discussed in Section 3.4 of the enclosed report, within 30 days from the date of this letter.
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You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. In your response, you should document the specific actions taken and any additional actions you plan to prevent recurrence. Your respoe may reference or include previous docketed correspondence, if the correspondence adequately p
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Mr. Craig P. Kipp specific actions taken and any additional actions you plan to prevent recurrence. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response. After reviewing your response to this Notice, including your proposed corrective actions, the NRC will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with 10 CFR Part 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosures, and your response will be placed in the NRC's Public Document Room (PDR). To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary informatien is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information tnat should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specitically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withhelding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
The responses requested by this letter and the enclosed Notice are not subject to the clearance procedures of the Office of Management and Bud et as required by the Paperwork Reduction 0
Act of 1980, Pub. L. No.96-511. Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely,
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Theodore R. Quay, Chief Quality Assurance, Vendor inspection, Maintenance and Allegations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation
Enclosures:
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- 2. Inspection Report No. 99900003/1999201
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