IR 05000335/1980002
| ML17208A530 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/07/1980 |
| From: | Dyer J, Elrod S, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17208A529 | List: |
| References | |
| 50-335-80-02, 50-335-80-2, NUDOCS 8004280241 | |
| Download: ML17208A530 (7) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST.< N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report No. 50-335/80-02 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, Florida 33101 Facility Name:
St. Lucie Unit No.
Docket No. 50-302 License No. DPR-67 Inspection at St. Lucie site near Fort Pierce, Florida Inspectors:
J.
A. Dye Da e
S gned S. A. Elrod Date Signed Za ZO Date Signed Approved by:
R.
. Martin, Section Chief, RONS Branch Da e igned SUMMARY Inspection on February 19-22, 1980 Areas Inspected This routine, unannounced inspection involved 45 inspector-hours on site in the areas of operations review, facility tours Licensee Event Report review and IE Bulletin review.
Results Of the four areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted License Employees
- C. M. Methy, Plant Manager-J.
H. Barrow, Operations Superintendent J.
E. Bowers, Maintenance Superintendent M. B. Vincent, Assistant Plant Supervisor Electrical N.
G. Roos, Quality Control Supervisor D. A. Culpepper, Shift Technical Advisor R. R. Jennings, Technical Supervisor H. S. Ruff, Quality Control Engineer
+Attended exit interview on February 20 and February 22.
2.
Exit Interview The inspection scope and findings were summarized on February 20 and February 22, 1980 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Licensee Event Reports Review The following LER's were reviewed to verify that reporting requirements had been met, causes had been identified, corrective actions appeared appropriate, generic applicability had been considered, and the LER forms were complete.
Additionally, for those reports identified by asterisk, a more detailed review was performed to verify that the licensee had reviewed the events, corrective action had been taken, no unreviewed safety questions were involved, and violations of regulations or Technical Specification con-ditions had been identified.
a.
HLER No. 79/32 - 'ailure of Emergency Diesel Generator 1-A" b.
HLER No. 79/33 - "Fire Barrier Degradation" c.
LER No. 79/34 - "Containment Isolation Channel MB inoperable on High Radiation Signal".
d.
HLER No. 79/35 - "Channel "C" Refueling Water Tank Ievel Out of Calibration".
e.
- LER No. 79/36 - "I,ine'ar Power Range Channel MB failed due to loss of Power Supply".
ga LER No. 80-01 - "Diesel Fuel Pump failed t'o start on Surveillance Test" LER No. 80-02
"Control Element Assembly No.
22 dropped to Full Insertion".
h.
LER No. 80-03 - "Control Element Assembly No.
30 Reed Switch Position Indication Channel Failed" No items of noncompliance or deviations were identified.
6.
IE Bulletins The following IE Bulletins were reviewed to determine whether they had been received and reviewed by appropriate management responses, where necessary, were accurate and complete, and that action taken, if required, was complete.
a.
(Closed)
IEB 79"23, "Potential Failure of Emergency Diesel Generator Field Exciter Transformer".
b.
(Closed)
IEB 79-25, "Failure of Westinghouse BFD Relays in Safety-Related Systems".
c.
(Closed)
IEB 79-28, "Possible Malfunction of Namco Model EA 180 Limit Switches at Elevated Temperatures".
No items of noncompliances or deviations were identified.
7.
Reactor Operations a.
Plant Tour A tour was made of selected portions of the plant.
Housekeeping in the areas toured was adequate.
b.
Control Room and Iog Book Review The Control room log book for January 10 thru February 20, 1980 was reviewed by the inspector.
The reactor was in stable operation for the period.
The log book entries met procedural requirements.
The control room was toured with the shift technical advisor.
Questions relative to annuciators and instrument readings were answered satisfac" torily by the license.P
At the exit interview, the inspector stated there were no further questions on reactor operations at this time.
No items of noncompliance or deviations were identifie /
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