IR 05000298/1979001
| ML19289D691 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/26/1979 |
| From: | Constable G, Johnson E, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19289D688 | List: |
| References | |
| 50-298-79-01, 50-298-79-1, NUDOCS 7903140131 | |
| Download: ML19289D691 (6) | |
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U. S. fiUCLEAR REGULATORY COMMISSION OFFICE OF IflSPECTION AND EtlFORCEMENT
REGION IV
Report flo. 50-298/79-01 Docket No. 50-298 License flo. DPR-46 Licensee:
Nebraska Public Power D* strict P. O. Box 499 Columbus,liebraska 68601 Facility Name: Cooper Nuclear Station Inspection At: Cooper fluclear Station, flemaha County, Nebraska Inspection Conducted: January 8-11, 1979 N
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E. H. Johnson, Reactor Inspector Date
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G. L. Constable, Reactor Inspector Date Approved By:
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'G. L. Madsen, Chief, Reactor Operations and Date Nuclear Support Branch Inspection Summary Inspection on January 8-11,1979 (Report No. 50-298/79-01)
Areas Inspected:
Routine, unannounced inspection of calibration of safety-related components, procedures, surveillance activities, new fuel inspection ar.1 follow up on LER's and unresolved items. The inspection involved fifty-four (54)
inspector-hours on-site by two (2) f1RC inspectors.
Resul ts : Of the six (6) areas inspected, no items of noncompliance or deviations were noted.
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-2-DETAILS Persons Contacted C. S. Ba.rus, Mechanical Engineer L. F. Bednar, Electrical Engineer P. J. Borer, Technical Assistant to the Station Superintendent B. Brungardt, Shift Supervisor R. D. Flannigan, Nuclear Engineer W. F. Gilbert, Training Coordinator M. Krcll, Instrument Supervisor
- L. C. Lessor, Station Superintendent E. R. Noyes, Engineering Supervisor J. L. Peaslee, Shift Supervisor R. O. Peterson, Reactor Engineer P. V. Thomason, Assistant to the Station Superinter. dent M. G. Williams, Operations Supervisor
- Present at the exit interview.
In addition to the above, the inspector held discussions with various maintenance, operations, technical support and administrative members of the licensee's staff.
1.
Plant Status During the period of this inspection, the plant was in routine full power operation. The inspectors conducted a walk-through of accessible areas of the plant. No significant discrepancies were noted.
2.
Procedures The objective of this inspection effort was to ascertain whether changes made to approved procedures are in conformance with license and procedural requirements. The inspector reviewed approxim_ately 60 of the 700+ procedure changes made during the past calendar year. An in-depth review was made of randomly selected procedures (listed below)
to verify that they were in conformance with 10 CFR 50.59(a); and to verify that the procedures were adeouate to control safety-related operation,.
-3-Procedure Title Revision 1.2 Station Organization and Responsibility
1.13 Station Design Changes
1.15 Document Control
2.2.65 Reactor Equipment Cooling Water System
2.3.2.2.2 Panel 9-3 Annunciator 9-3-2
5.4.2.6 Drywell Fire
5.4.2.20 Turbine Basement Oil Fire
6.3.17.1 Control Room Ventilation
No items of nonccmpliance or deviations were noted in this area.
3.
Calibration The objective of this inspection effort was to ascertain whether the calibration of components and equipment associated with safety-related systems or functions is in conformance with Technical Specification requirements.
Records and procedures associated with the following calibrations were reviewed to verify that the surveillance was accomplished at the required intervals, that procedures were adhered to, and that the technical content of the procedures appeared adequate.
Procedures Title 6.1.9 Reactor Vessel Low-High Water Level Calibration and Functional Test 6.1.19 Local Power Range Monitor Calibration Test 6.2.2.1.6 CSCS - Discharge Piping Full Low Pressure Alarm Calibration and Functional Test 6.2.2.8.10 PC - Drywell - Torus 0 % Analyzer Calibration and
Functional Test 6.2.3.1 Drywell Floor Drain Sump 1F Flow Loop Calibration and Functional Test 6.2.3.2 Drywell Equipment Drain Sump 1G Flow Loop Calibration and Functional Test 6.2.3.3 Drywell Air Sampling System Calibration and Functional Test No items of noncompliar.ce or deviations were noted in this area.
4.
Surveillance The following surveillance activities were observed during the course of the inspection.
Procedure Title 6.2.2.2.3 ADS Timer Calibration and Actuation Functional Test 6.2.2.4.4 CS - Core Spray Initiation Functional Test 6.3.15.3 Station Battery Weekly Check 6.3.3.1 HPCI Test Mode Surveillance Operation
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-4-The inspector noted that the observed activities were accomplished in accordance with approved procedures and that all test equipment appeared to be appropriate and properly calibrated.
No items of noncompliance or deviations were identified.
5.
Follow Up on Unresolved Items and Inspector Identified Open Items The following unresolved items and inspector identified open items were reviewed during this inspection. Their status is as indicated.
Resolved.
Unresolved Item 7813-1, Requirements for Review of Revised D_esign Changes - Revision 3, dated September 29, 1978 has been issued to 6EP-ll.
This revision corrects the previously noted discrepancy.
Closed.
Reference IE Report 77-07, Details, paragraph 2.
The licensee is currently revising the ASME Section 11 required inservice inspection program to include spring hanger hot and cold settings.
Closed.
Reference IE Report 77-09, Details, paragraph 15. The licensee is currently developing a listing of essential components.
This item will continue to be carried as an open item from Inspection Report 77-04, Details, paragraph 3.
Closed.
Reference IE Report 78-17, Details, paragraph 4.
The inspector reviewed the requalification training records to determine
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that the appropriate training had been provided to the individuals in question.
Closed.
Reference IE Report 78-20, Details, paragraph 2.
The torus access hatch plug has been removed from on top of the round pipes.
Open. Reference IE Report 77-04, Details, paragraph 6.
The inspector noted that on two occasions during 1978, the licensee had tested the emergency diesel generators at equal to or greater than their anticipated ECCS load. The licensee has not yet completed his evaluation as to whether this will be a nonnal practice.
No items of noncompliance or deviations were noted in this area.
6.
Follow Up on Licensee Event Reports The inspector reviewed the events reported on the below listed licensee event reports.
Based on a review of facility internal reports and log books, the inspector made the determination that the events occurred as
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Each event was discussed with the licensee's staff. The corrective actions indicated in each report were verified to have been completed by review of surveillance test data sheets, completed work request forms and discussions with licensee personnel.
The status of each licensee event report is given below:
LER No.
Description Status 78-18 Failure of condenser air removal valves Closed to close during surveillance test 78-19 Failure to maintain the reactor pressure Closed vessel in te vented condition during refueling operations 78-24 Main steam line monitor radiation set Closed points not reset following source calibration 78-31 Failure of crank shaft bearing on No. 2 Closed diesel generator 78-32 Building of SMB-3 Type limitorque operator Closed due to loose set screw on valve stem retaining yoke 78-35 Reactor Recirculation MG set speed Closed increase 78-22 Nonconservative set point on MSIV limit Open - The licensee switches is awaiting receipt of new switch types 78-33 Violation of cable separation criteria Open - This item is scheduled for com-pletion during the April refueling shutdown 78-34 Rod 30-31 uncoupled during operation Open - This rod will be removed during the April 1979 refueling outage.
In addition to the above, the following licensee event report was reviewed by the inspector in the Regional Office. Based on the 100%
review by the inspector of all licensee internal nonconformance reports, discussions with licensee personnel during the course of inspections, and periodic review of station logs, this report was closed with no further on-site follow u *
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LER 78-37, Failure of Servo Amplifier in Pressure Recorder PC PR-512A No items of noncompliance or deviations were noted in this area.
7.
Receipt of New Fuel During the course of this inspection, the licensee was in the process of performing receipt inspections on new fuel for use during the next core cycle. The inspectors observed portions of the receipt inspections.
The inspectors observed that fuel handling activities were conducted in
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accordance with approved procedures and the inspections were conducted in accordance with approved checklists.
No items of noncompliance or deviations were noted in this area.
8.
Exit Interview The inspectors met with the Station Superintendent at the conclusion of the inspection. The scope of the inspection and the findings were discussed.