ML20003G535
| ML20003G535 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/11/1981 |
| From: | Randy Hall, Hunnicutt D, Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20003G533 | List: |
| References | |
| 50-313-81-05, 50-313-81-5, NUDOCS 8104290767 | |
| Download: ML20003G535 (4) | |
See also: IR 05000313/1981005
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-313/81-05
Docket No. 50-313
License No. DPR-51
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Licensee: Arkansas Power and Light Company
Post Office Box 551
Little Rock, Arkansas
72203
Facility Name: Arkansas Nuclear One (AN0), Unit 1
Inspection at: AN0 Site, Russellville, Arkansas
Inspection Conducted:
February 23-25, 1981
Inspector:
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Pia, Rptor Inspector, Engineering & Materials
Da'te
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Reviewed:
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D. M. Hunnicutt, Chief, Reactor Projects Section No. 2
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Approved: .M
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R. E. Hall, Acting Chief, Engineering & Materials Section
Da'te /
Inspection Summary:
Inspection conducted durina February 23-25,1981 (Recort No. 50-313/81-05)
Areas Inspected: Special, announced inspection involving review and witnessing
of Containment Integrated Leakage Rate Test (CILRT).
The inspection involved
thirty-two inspector-hours on site by one NRC inspector.
Results:
In the area inspected, one violacion was found in the area of access
control (violation - failure to provide suitably controlled environmental
conditions - paragraph 2).
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DETAILS
1.
Persons Contacted
Principal Licensee Employees
- J. P. O'Hanlon, ANO General Manager
- G. H. Miller, Engineering & Technical Support Manager
- L. W. Humphrey, Plant Administration Manager
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- D. D. Snellings, Technical Analysis Superintendent
- L. W. Schempp, Manager of Nuclear QC
- D. Glenn, Health Physics Supervisor
- J. B. Lamb, Safety & Fire Protection Coordinator
- P. Jones, I&C Superintendent
- S. Petzel, Production Engineer
J. R. Robison, I&C Supervisor
J. G. Waxenfelter, I&C Supervisor
P. Kearny, Production Engineer
C. H. Halbert, Mechanical Supervisor (ILRT Test Director)
D. Hamblen, QC Inspector
R. D. Beckham, QC Inspector
Other Personnel
R. Redford, Resident Engineer, Bechtel
- W. Horn, Project Superintendent, Bechtel
L. R. Young, Senior Startup Engineer, Bechtel
M. Burgess, Engineering Specialist, Bechtel
L. A. Buliszak, Engineering Specialist, Bechtel
H. M. Wilkerson, Engineering Specialist, Bechtel
S. M. Christensen, Engineering Specialist, Bechtel
The IE inspector also interviewed other licensee and contractor personnel
including members of the Arkansas Power and Light Company and Bechtel
engineering, construction and QC staffs.
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- Denotes those attending the exit interview.
2.
Containment Integrated Leakage Rate Test
The second periodic Reactor Containment Integrated Leakage Rate Test (CILRT)
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at Arkansas Nuclear One, Unit 1 was addressed during this inspection.
The
inspection included observations, procedure and records review and independent
calculations by the IE inspector.
This inspection effort was performed in
order to ascertain whether the testing was conducted in accordance with
approved procedures and specified acceptance criteria.
Specific requirements
are contained in the following documents:
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10 CFR, Part 50, Appendix J, " Primary Reactor Containment Leakage
a.
Testing for Water-Cooled Power Reactors"
b.
ANSI N45.2, " Leakage-Rate Testing for Containment Structures for
Nuclear Reactors"
c.
Arkansas Nuclear One, Unit 1 Technical Specifications, Section 4.4.1.1,
" Integrated Leakage Rate Tests"
Engineering Test Procedure No. 1309.09, " Integrated Leak Rate Test,"
Revision 0 incorporates the requirements into the test procedure.
This
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procedure was reviewed by the IE inspector; and no discrepancies from
the specified requirements were noted.
The instrument calibration certifications traceable to the U.S. Bureau of
Standards for the resistance temperature detectors (RTDs), dewcells,
pressure gauges, and the flowmeter used in the verification test were
reviewed.
During the performance of the type "A" test, the IE inspector computed the
leakage rate in accordance with the Mass Point Data Analysis - Absolute
Method technique of ANSI /ANS 56.8-1980.
The computations perfomed by the
IE inspector were used to compare with the licensee's results for the
purpose of verifying the calculational procedure and confirming the results.
This analytical technique confirmed the acceptability of the test results
being obtained by the licensee's contractor, Bechtel.
Technical Specifications pennit 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 it
can be demonstrated that the leakage rate can be accurately determined
during a shorter test period.
Evidence of the accuracy of a shorter test
duration consisted of the Mass Point Data Analysis of the performed
type "A" test date.
The analysis, using the Absolute Method, was performed
in accordance with the American National Standards Institutue/American
Nuclear Society Standard 56.8-1980, " Containment System Leakage Testing
Requi rements. " This analytical method consists of determining the mass of
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air in the containment, utilizing the ideal gas law, at each time point
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during the test and subsequently performing a straight line least squares
analysis to estimate the leakage rate. The analysis results in a statisti-
cally detennined estimation of the projected 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leakage rate.
The
IE inspector found that the test data showed, with a 95 percent level of
confidence, that the measured leakage rate was less than the allowable
leakage rate when computed using twenty data points.
Although this number
of data points represents four hours and forty-five minutes, the licensee
performed the type "A" test for a period of nine hours and forty-five minutes.
A review of the plot of leakage rate versus time for the additional data will
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be performed during a subsequent inspection of the submittal of the summary
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technical report in accordance with 10 CFR Part 50, Appendix J.Section V.B.
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The dewcell weight factor programadjustment, required as a result of one
out of six dewcells failing, was reviewed by the IE inspector.
The weight
factor readjustment was verified by independent calculation.
The IE inspector independently monitored the key containment parameters
during the CILRT.
During this review, the access control to the data
acquisition and processing area was found to be such that construction
activities were permitted adjacent to the Data Acquisition System (DAS).
Ongoing installation of firestop material and floor sweeping resulted in
a heavy congestion of personnel, pneumatic lines, ladders and a cloud of
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dust next to the DAS.
These activities represent a failure to restrict
access to the data acquisition and processing area as required by Appendix H,
" Access Control," of Engineering Test Procedure No. 1309.09, " Integrated
Leak Rate Test," Revision 0.
These activities degraded the environment of the DAS and had the potential
to impact the CILRT. Although the CILRT was not affected, this represents
a violation having a minor safety significance and is, therefore, a
Severity VI violation.
3.
Exit Interview
The IE inspector met with the licensee representatives denoted in paragraph 1
at the conclusion of the inspection. The IE inspector summarized the scope
and findings of the inspection.
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