IR 05000285/1980002
| ML19309C516 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/13/1980 |
| From: | Randy Hall, Kelley D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19309C511 | List: |
| References | |
| 50-285-80-02, 50-285-80-2, NUDOCS 8004080696 | |
| Download: ML19309C516 (4) | |
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O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-285/80-02 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: January 28 - February 1, 1980 Inspectors:
k atb Z - l'S - bo J.I.[ tap'la,Re tor Inspector, Engineering Support Date Section s
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P 2 -/ 3 - fb R. E. Hall, Chief, Engi6eering Support Section Date k /3'f0 Reviewed:
D. L. Kelley, Reactor Inspector, Reactor Projects Date Section Approved:
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'A-/.? - F O T. F. Westerman, Chief, Reactor Projects Section Date Inspection Summarv:
Inspection on January 28 - February 1, 1980 (Report No. 50-285/80-02)
Areas Inspected:
Special, announced inspection of activities related to the second periodic containment integrated leak rate test.
The inspection con-sisted of one-hundred six inspector-hours on site by two NRC inspectors.
Results:
In the one area inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Employees
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C. Stevens, Manager, Fort Calhoun Station
- G. R. Peterson, Supervisor, Maintenance L. Kusek, Technical Supervisor
- R. F. Mehaffey, Supervisor, I6C and Electrical Technical Services D. Dale, QC Inspector G. R. Chatfield, Reactor Operator M. Hugo, Electrical Engineer Other Personnel G. J. Larsen, Senior Service Consultant, Nuclear Services Corporation (NSC)
L. J. Lehman, Senior Service Consultant, NSC C. W. Rowley, Staff Service Consultant, NSC W. Purdy, Senior Service Engineer, NSC G. Kruger, Senior Service Engineer, NSC W. Williams, Consulting Engineer, Target Technology Limited L. F. Kesselman, Nuclear Service Site Manager, Combustion Engineering, Inc.
V. Laakso, Nuclear Service Site Manager, Combustion Engineering, Inc.
2.
Containment Integrated Leakage Rate Test The second periodic Reactor Containment Building integrated leakage rate test at Fort Calhoun Station, Unit No. I was addressed during this inspection.
The inspection included observations, procedure and records review, and inde-pendent calculations by the IE inspectors.
This effort was to ascertain whether the testing was conducted in accordance with approved procedures and specified acceptance criteria.
Specific requirements are contained in the following documents:
10 CFR 50, Appendix J, " Primary Reactor Containment Leakage Testing a.
for Water-Cooled Power Reactors" b.
ANSI N45.4, " Leakage-Rate Testing of Containment Structures for Nuclear Reactors" c.
Fort Calhoun Station, Unit No. 1 Technical Specifications, Section
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3.5 (1), " Integrated Leakage Rate Tests '
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Surveillance Test Procedure No. STN-CONT-7, " Type ' A' Test (Containment),"
incorporates the requirements with the test procedure.
This procedure was reviewed by the lE inspectors and found to be in conformance with the specified requirements.
In addition to the current testing program, a review was performed of the two previously performed Type "A" tests for
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the purpose of verifying the rationalization used by the licensee in proposing a shortened duration Type "A" test.
Technical Specifications permit a test duration less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the experience from two earlier Type
"A" tests provides evidence of the accuracy of a shorter test duration.
The IE inspectors found that the previous test date showed, with a 95% level of confidence, that the measured leakage rate was less than the allowable leakage rate when computed at test intervals less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Notwithstanding this justification, the current test was run for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> due to a time lag between data acquisition and processing in the Nuclear Services Corporation (NSC) home office computer.
A review of the plot of leakage versus time for the current data will be reviewed during a subsequent inspection.
Prior to the initiation of the Type
"A" test, one IE inspector accompanied the Nuclear Service Site Manager for Combustion Engineering and the OPPD Quality Control Inspector during the Containment Closure walk-through.
In addition, the Type "B" test performed on the Equipment Access Hatch was witnessed and found to conform to Surveillance Test Procedure No. ST-CONT-2,
" Containment Local Leak Detection Tests."
The IE inspector randomly selected ten valves and verified that their alignment was in accordance with the procedure and that no artifical leakage barriers were created. Due to a high level of corrosion-inhibiting chromates in the seal and lubrication oil coolers for the reactor coolant pumps, the safety injection tank leakage coolers, and the nuclear detector well cooling units, these systems were not vented into the containment atmosphere as originally specified.
Since these are closed systems inside containment which are normally filled with water under post-accident conditions, nonventing of these systems was in accordance with 10 CFR 50, Appendix J and the Technical Specifications.
The IE inspector toured the containment prior to test initiation in order to observe the placement of the resistance temperature detectors (RTDs)
and the dewcells.
Subsequently, the calibration certifications traceable
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to the U. S. Bureau of Standards for the RTDs, dewcells, pressure gauges and the flowmeter used in the verification test were reviewed.
During the performance of the Type "A" test, the IE inspectors computed the leakage rate in accordance with the Mass Point Analysis of proposed American Nuclear Society Standard N274, " Containment System Leakage
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Testing Requirements," Draft 3.
The computations performed by the IE inspectors were for the first ten half-hour-data points. The NSC computations incorporated data taken at ten minute intervals.
The inspectors' results were, therefore, a less accurate but more readily available indication of leakage rate trend.
Because of the data analysis delays, only preliminary NGC test results were avialable at the conclusion of the inspection. The IE inspectors also independently calculated the leakage rate using the Total-Time procedure delineated in ASNI N45.4 - 1972.
Both~ techniques confirmed the acceptability of the test results being obtained by the licensee's contractor, NSC.
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-Since the data and results of analysis from the Integrated Leakage Rate Test and the superimposed leakage Verification Test were not available prior to the conclusion of the inspection, these data were. requested by the IE inspectors to permit completion of the test results analysis.
The review and comparison of the requested data with the final CILRT report is, therefore, considered an unresolved item (8002-01).
3.
Exit Interview
The IE inspectors met with the licensee representatives denoted in para-
graph 1 at the conclusion of the inspection.
The IE inspectors summarized the scope and findings of the inspection. The licensee representatives committed to transmitting copies of the raw test data for the Verification
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Test to the RIV office.
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