ML17223A479
| ML17223A479 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/23/1990 |
| From: | Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17223A477 | List: |
| References | |
| 50-335-89-24, 50-389-89-24, NUDOCS 9001310083 | |
| Download: ML17223A479 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Florida Power and Light Company St
~ Lucie Docket Nos.
50-335, 50-389 License Nos.
DPR-67, NPF-16 During the Nuclear Regulatory Commission (NRC) inspection conducted on October 2
November 29, 1989, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
( 1989),
the violations are listed below:
A.
Title Ten Code of Federal Regulation
( 10 CFR),
Part 50, Appendix B,
Criterion V, requires activities affecting quality be accomplished in accordance with procedures.
10 CFR, Part 50, Appendix B, Criterion >(VII, requires sufficient records be maintained to furnish evidence of activi-ties affecting quality.
American National Standards Institute (ANSI)
N45.2.9 - 1974, paragraph 3.2. 1 specifies that Quality records are to be legible, completely filled out and adequately identifiable.
The preceding requirements are implemented by Florida Power 'nd Light Procedure QI 17-PR/PSL-1, Revision 14, "Quality Assurance Records",
Paragraphs
- 5. 1.C, 5.2.2 and 5.2.7 which require that records, both hard copies and microfilm, be reviewed for completeness and legibility, and readability.
Contrary to the
- above, on November 3, 1989, activities affecting quality had not been accomplished in accordance with procedures, which resulted in incomplete and illegible records of activities affecting quality in that the final quality records (microfilm) for seven Plant Work Order packages out of ten 'examined contained mi ssing dates, missing signatures, illegible
- data, and illegible signatures.
This is a Severity Level IV Violation (Supplement I) ~
B.
10 CFR 50, Appendix B, Criterion V requires, in part, that activities affecting quality shall be prescribed by documented drawings of a type appropriate to the circumstance and shall be accomplished in accordance with these drawings.
Contrary to the
- above, on October 3, 1989, activities affecting quality were not in accordance with drawings in that:
l.
Unit 1
Excore Neutron Flux Panel RY2680B printed circuit board protective enclosure was not installed (missing) as required by Gamma Metrics drawing 200646.
Florida Power and Light Company St.
Lucie Docket Nos.
50-335, 50-389 License Nos
~
Power supply assembly bottom protective covers for Unit 1 Reactor Protection System Panels MB, MC and MD were not installed as required by EE Controls Drawings D-10089.
3.
Two 120 VAC Instrument Bus 2MC Distribution Panel
- fuses, FU-3, required by control wiring diagram CWA-2998-B-327, sheets 1009 and
- 1636, were missing.
The fuses are part of the power monitoring logic circuit for the Auxiliary Feedwater Actuation System.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Florida Power and 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 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 corrective steps which will be ia.en 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 Albert F
~ Gibson, Director Division of Reactor Safety Dated at Atlanta, Georgia thi s 23rd day of January 1990