ML17223A817
| ML17223A817 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/11/1990 |
| From: | Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17223A816 | List: |
| References | |
| 50-335-90-13, 50-389-90-13, NUDOCS 9006200290 | |
| Download: ML17223A817 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Florida Power In Light Company St. Lucie 1 and 2
Docket Nos.
50-335 and 50-389 License Nos.
DPR-67 and NPF-16 During the Nuclear Regulatory Coomission (NRC) inspection conducted on April 17 to May 14,
- 1990, a violation of NRC requirements was identified.
The violation involved three aspects of configuration control:
material control, design control, and containment configuration control.
In accordance with the "Genera1 Statement of Policy and Procedures for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1990), the violation is listed below:
10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, as implemented by approved FPL Topical guality Assurance Report TAHAR 1-76A, Rev.
15, TgR 5.0, Instructions, Procedures, and
- Drawings, and further implemented by TAHAR Appendix C commitment to ANSI N18-7,
- 1976, paragraph 5.2.7, Maintenance and Modifications, require that maintenance'r modifications which may effect functioning of safety-related structures,
- systems, or components shall be performed in a manner to ensure quality at least equivalent to that specified in original design bases and requirements, materials specifications, and inspection'equirements.
Contrary to the above, in the three examples cited below, the licensee failed to maintain the quality specified in the original design requirements or materials specifications.-
1.
Seismic drawing 8770-G-796, sheet 3,
shows the seismic support for the Unit 1 maintenance hatch drawbridge inside containment to be a pair of 3 x 3 inch angle supports about 7 feet long and bolted to the drawbridge and adjacent deck.
During a containment tour in preparation for Unit 1
- startup, the raised drawbridge at the equipment hatch was not supported by the specified supports. It was supported by a chainfall.
2.
The maintenance organization removed the existing seismic mounting fasteners for the hydrogen sampling system containment isolation valves FSE-27-1 through 7 and, when unable to determine the existance of approved
- drawings, informally designed and installed significantly different mounting fasteners without design engineering involvement.
The approved but unissued drawings when located supported the original fastener installation.
3.
Carbon steel nuts were installed on the joint between the 1A ICW pump casing to pump stuffing box in lieu of 316 stainless steel nuts required by Ebasco Specification 53-47.
In addition, a single rubber gasket was installed on the safety-related lubricating water flanged joint in lieu of
-an insulation kit required by drawing 8770-B-124, CW 53, Rev 1, Circ.
Water System.
This is a Severity Level IV violation (Supplement I).
9006200290 900l~ll PDR ADOCK 0-000335 9
Florida Power 8 Light Company St. Lucie 1 and 2
Docket Nos.
50-335 and 50-389 License Nos.
- Pursuant to the provisions of 10 CFR 2.201, the Florida Power 5 Light Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, St. Lucie, 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 the violation:
( 1) admission or denial of the alleged violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results
- achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is
- shown, consideration will be given to extending the response time.
If an adequate 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 Dated at Atlanta Georgia this 11th day of June 1990 v'arvin V. Sinkule, Chief Reactor Projects Branch 3
Division of Reactor Projects
1