IR 05000285/1980011
| ML19347B020 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/13/1980 |
| From: | Hunnicutt D, Kelley D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19347B019 | List: |
| References | |
| 50-285-80-11, NUDOCS 8010010180 | |
| Download: ML19347B020 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-285/80-11 Docket No. 50-285 License No. DPR-40 Licensee: Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Facility Name:
Fort Calhoun Station - Unit 1 Inspection at:
Fort Calhoun Station, Blair, Nebraska Inspection Conducted: June 30 thru July 29, 1980 Inspector, h[
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,7/3/80 n/ D. L. Kelley, Senior Resident Inspector hate /
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Approved By:
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D.
M'. Hunnicutt, Chief, Reactor ProjectsSection II Cate'
Inspection Summary Inspection on June 30 thru July 29, 1980 (Report No. 50-285/80-11)
Areas Inspected:
Routine resident inspection of (1) Operational Safety Verification; (2) Fost-refueling Tests; and (3) Observation of Annual Emergency Drill.
The inspection of on-site activities by the resident inspector included 176 inspector hours.
Results:
In the three (3) areas examined, no deviations or items of non-compliance were identified.
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DETAILS 1.
Persons Contacted
- S. C. Stevens, Manager, Fort Calhoun Station
- R. L. Andrews, Section Manager - Operations W. C. Jones, Division Manager - Production Operations i
W. G. Gates, Supervisor, Operations G. Paterson, Supervisor, Maintenance L. Dugger, Reactor Engineer
- Denotes those attending exit interview.
The inspector also interviewed other licensee employees, including licensed reactor operators and office staff.
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2.
Operational Safety Verification a.
Daily i
On a daily basis, the inspector made the following control room observations to verify licensee compliance with operating license conditions and technical specifications:
-Proper control room and shift manning.
-Abnormality in instrument and recorder traces were identified and corrected.
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-ESF electrical panels were lined up consistent with requirements-for operating mode.
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-Operationr were being conducted in accordance with approved procedures.
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In addition, the inspector reviewed operating logs and records to obtain information on plant operations, trends, compliance with NRC requirements and assess the communications effectiveness provided by the logs and records.
b.
Weekly On a weekly basis the inspector toured accessible areas of the plant to ascertain the following:
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-The general plant cleanliness was such that plant operation personnel safety was not jeopardized and ignition sources and combustible materials were at a reasonably attainable minimum.
-There were no leakages from valves, pumps or flanges.
-Switchgear circuit breakers were in proper position for the operational mode.
-Randomly select valves on various ESF systems were verified to be in their proper positions.
-There were no excessive pipe vibrations.
-Randomly selected snubbers and pipe restraints were operable.
-Plant security force positions were properly manned.
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In addition to the above daily and weekly observations the inspector observed control room and security force shift changes.
Also observed during the security force shift change were personnel and package checks of the oncoming operating shift.
Several times during this inspection high ambient temperatures necessitated blocking open several security doors.
During the time these doors were open, the inspector verified that guards were stationed by the doors as required by the security plan.
The plant status during this inspection period was operation at 100% power.
One reactor trip occurred due to an instrument bus inverter trip.
The trip, recovery and return to full power operation were accomplished in accordance with approved procedures and no abnormal plant responses or behavior was observed.
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No deviations or items of noncompliance were identified.
3.
Post Refueling Testing The data for the following parameters are being reviewed:
-Core power distribution limits.
-Core thermal power distribution.
-Determination of shutdown margin.
-Isothermal temperature coefficient of reactivity
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-Power coefficient of reactivity.
-Control rod worth measurements.
The inspector has started review of the available data.
Some of the parameters require sampling data over a period of time.
As these data become available, they will be reviewed.
To date no problem areas have been encountered.
This review will continue during the next inspection period.
No deviations or items of noncompliance were identified.
4.
Annual Emergency Drill On July 29, 1980, the licensee conducted their annual emergency drill.
The inspector and four additional NRC inspectors observed the drill from various points throughout the plant.
The evaluation of the drill will
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be documented in a separate NRC report.
5.
Exit Interview During the period of this inspection, the inspector held several mini-exit reviews with licensee personnel. A final exit review was held with licensee personnel (denoted in paragraph 1) on August 1, 1980 to summarize the scope and findings of the inspection.
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