IR 05000335/1980014
| ML17208A824 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/16/1980 |
| From: | Messitt B, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17208A819 | List: |
| References | |
| 50-335-80-14, NUDOCS 8007160830 | |
| Download: ML17208A824 (7) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W.. SUITE 3100 ATLANTA,GEORGIA 30303 Report No. 50-335/80-14 Licensee:
Florida Power 6 Light 9250 West Flagler Street Miami, FL 33101 Facility Name:
St. Lucie
Docket No. 50-335 License No. DPR-67 Inspection at St. Lucie site near Ft. Pierce, Florida I
Inspector:
B. R. Messit ate Signed Approved by:
C.
M. Upright cti Section Chief, RONS Branch SUMMARY Inspection on April 30 - May 2, 1980 ate igned Areas Inspected This routine, unannounced inspection involved 17 inspector-hours on site in the areas of calibration of technical specification required plant instruments and measuring and test equipment, and followup of recent LER's.
Results Of the two areas inspected, no items of noncompliance or deviations were identified in one area; one item of noncompliance was found in one area (Infraction Failure to report emergency diesel generator load sequence timers that did not meet Technical Specification limits during routine surveillance testing paragraph 5.c).
DETAIIS 1.
Persons Contacted Licensee Employees
+A. Bailey, Quality Assurance Supervisor J. Barrow, Operations Superintendent
"-J. Bowers, Maintenance Superintendent A. Collier, Instrumentation 6 Controls Supervisor R.'ennings, Technical Supervisor N.'Roos, Quality Control Engineer-D. Sager, Senior Plant Engineer-C. wells, Operations Supervisor
>D. West, Plant Engineer
>"C. Wethy, Plant Manager Other licensee employees contacted included technicians, and office personnel.
"Attended exit interview 2.
Exit Interview The ins ection p
scope and findings were summarized on May 2, 1980 with those persons. indicated in Paragraph 1 above.
The Plant Manager acknowledged the noncompliance discussed in Paragraph 5.c and committed to the following:
submit a supplement to LER 50-335/80-15 discussing retests, replacements,
.possible engineering remedies, and any generic aspects associated with the emergency diesel generator test; retest the Shield Building Ventilation System valves; and submit a report on the diesel generator test conducted in 1979 which discusses measures to control reporting events which require reporting, and a discussion of the event.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Followup of Recent Licensee Event Reports (LERs)
a ~
(Closed) 50-335/80-13, Diesel Generator Field Gabled')eficiency.
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c "Cj-This LER reported that the wrong size cable had been initially installed for the diesel generator field supplies. 'he inspector reviewed the completed work package including retests and had no further question (Open) 50-335/80-16, Potential Effect of Pressure Transmitters on Vacuum Relief Lines.
This LER reported vendor notification of a design problem with pressure transmitters.
The inspector discussed the work and retest requirements with the Instrumentation and Control Supervisor.
Since the work is not complete, this item remains open.
(Open) 50-335/80-15 Engineered Safety Features.
This LER reported discrepancies on the recent Periodic Integrated Test of Engineered Safety Features.
The discrepancies included failure of two fans to start, failure of ten diesel generator loading timers to actuate within the setpoint tolerance, and failure of Shield Building Ventilation System (SBVS) valves to actuate.
The inspector reviewed subsequent tests and discussed with plant personnel the fan start failures.
The components start when tested individually and it appears that the failure during the test was a
random event.
Both components could have been operated from the control room and redundant equipment exists which did start.
The inspector discussed failure of the SBVS valves with licensee personnel.
These valves require a pressure differential signal as well as an emergency signal to open.
It appears that a door in the shield building may have been open such that the required pressure differential was not generated.
These valves had been tested satis-factorily prior to the integrated test during this outage and could have been operated from the control room.
The licensee committed to retest these valves prior to startup from this outage.
The inspector discussed failure of the ten diesel generator loading timers with the licensee.
Both trains of engineered safety features were affected.
Nine of the timers were within one second of the required tolerance band and have been reset and tested satisfactorily.
One was outside the band by five seconds; this one has been replaced and tested satisfactorily.
During the discussions the inspector noted that there was a similar timer problem during the previous integrated test in 1979 and that no LER was submitted.
Technical Specification (T/S) 4.8.1.1.2.c.6 requires that timers actuate within a tolerance band of +
1 second.
T/S 6.9.1.9.a requires that the licensee submit a written report within thirty days to the Director of the regional office if:
"a.
Reactor protection system or engineered safety feature instrument settings which are found to be less conservative then those established by the technical specifications but->gich do not prevent the fulfillment of the functional requirements of affected systems."
Failure to submit a written report as required by T/S 6.9.1.9.a is considered to be an item of noncompliance (335/80-14-01).
The inspector discussed this item with the licensee and received a commitment from the licensee to submit a report on the 1979 Event.
Included in the report will be a discussion of why no report was made and actions to prevent recurrence. of non-reporting as well as the discussion of the event.
Additionally the inspector acknowledged that the licensee will submit a supplement to LER 335/80-15 discussing retests and replacements, possible engineering remedies and any generic aspects of the reported failures.
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No other items of noncompliance or deviations were identified in this area.
6.
Calibration The inspector conducted a review of the following calibration procedures and associated test results:
OP-0540051 Periodic Calibration of Reactor Coolant System Pressure, Ievel, and Temperature Monitors on the Hot Shutdown Control panel (HSCP)
OP-1100051 CEA Position Indication and Alarm System Calibration OP-1220050 Iinear Power Range Safety Channel quarterly Calibration OP-1400062 Reactor Regulating System Calibration Procedure OP-1400152 Seismic Instrument Calibration OP-1400154 Reactor Coolant I,eakage Detection System Calibration OP-1400164 Reactor Protection System - Refueling calibration -Trip Bypass Logic Operation OP-2000054 Periodic Calibration of Hydrogen Recombiner Temperature Instruments The procedures and calibration results were reviewed to verify the following:
Reviews and approvals were being conducted and data was recorded and evaluated; Test instruments were listed and identified in test'~suits Li Technical Specifications and limiting conditions for operations were adhered to; Technical contents were correct and included verifications of the return of equipment to service and removal of test equipmen Acceptance criteria were given and met, documented and signed off; and A second person had reviewed test results.
The inspector conducted an inspection of the Instrument and Controls shop and reviewed other records including calibration records for twenty pieces of measuring and test equipment and ten in-plant installed instruments.
The facility and records were inspected to verify the following:
Standard test instruments were labeled and included in the calibration program; Instruments were calibrated on schedule and labeled with calibration status; Storage facilities were proper for protecting the equipment; Non-conforming equipment was being tagged and provided with separate storage; and pezificatfon.; and calibration records were available and being maintained for measuring and test equipment.
The inspector used portions of one or more of the following acceptance criteria for the above items:
ANSI N18.7 (1972)
ANSI N18.1 (1972)
ANSI N45.2 (1971)
CFR 50, Appendix B Technical specifications ZPI QAM Within the areas inspected no items of noncompliance or deviations were identified.