IR 05000313/1984036
| ML20137X769 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/18/1985 |
| From: | Ireland R, Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20137X748 | List: |
| References | |
| 50-313-84-36, NUDOCS 8512100625 | |
| Download: ML20137X769 (4) | |
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
'NRC Inspection Report:
50-313/84-36 License:
DPR-51 Docket:
50-313
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Licensee:
Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One, Unit 1 Inspection At: ANO No. 1 Site, Russellville, Arkansas and U. S. NRC Region IV Offices Inspection Conducted:
December 13-15, 1984 and March 28-30, 1985 Inspector *
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J. I. Tapia, Reactor Inspsetor, Engineering Dath
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and Operations-Section
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Approved:
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R. E.cIreland, Chief, Engineering and Date
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Operations Sections
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Inspection' Summary Inspection Conducted December 13-15, 1984 and March 28-30, 1985
'(Report 50-313/84-36)
Areas Inspected:
Special, announced inspection of the containment integrated leakage rate test. The. inspection involved 26 inspector-hours onsite and 25
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.in-office inspector-hours by one NRC inspector.
Results: Within the areas inspected, one violation (failure to follow procedures) and no deviations.were identified.
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DETAILS-
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' Persons Contacted
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l1 Arkansas Power and Light Company (AP&L)
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~D.IN. Bennett, ILRT Director
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~C. N..Shively, Plant Engineer
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_L.;J. Dugger, Instrumentation and Control Superintendent l.
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J. McWilliams, Outage Manager
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_T..H. Cogburn, Special Projects Manager
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. P.L Campbell, Licensing Engineer
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l]f J. M. Levine, General Manager:
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10. B. Lomax, Licensing Supervisor
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iBechtelEngineeringCorporation
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M. Burgess,.ILRT' Engineer r
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' Integrated Leak Rate Test (ILRT)
s-The, third _ periodic containment ILRT conducted using the Absolute Method'as described in' ANSI _N45.4-1972, " Leakage Rate Testing of Containment
Structures-for Nuclear Power Plants,".and ANSI /ANS-56.8-1981, " Containment System Leakage Testing Requirements," was addressed during this
' inspection.' The inspection involved procedure and records review, test
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s witnessing ;and independent' calculations by the' NRC inspettor. LThis
~ inspection effort was performed in, order to ascertain whether the testing was-conducted in accordance with approved p'rocedures"and satisfied-the
- specified acceptance criteria contained in 10 CFR Part_50,' Appendix J,
" Primary Reactor Containment Leakage-Testing 1.. Water Cooled Power
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Reactors," and in the Plant Technical Specifications.
Engineering Test Procedure No. 1309.09, " Integrated Leak Rate Test;"
' incorporates the referenced requirements and criteria.
This procedure was reviewed by_the NRC. inspector and no discrepancies from the specified requirements and criteria were noted. The review provided verification that.the following test attributes were correctly addressed:
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a.
Containment interior and exterior inspection requirements specified.
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Instrument locations justified by area surveys.
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' Instrument calibiation requirements specified.
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_ Instrument : loss / test abort criteria delineated.
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~ Instrument error analysis : performed.
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' Type B and-C test. result's correction to' Type A test results f.-
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specified,
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' Venting of internal isolated volumes required.
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Isdlation valve closing mode specified to be the normal mode.
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Proper postaccident system alignment.to prevent creation of
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artificial leakage barriers specified.
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Quality control hold points specified.
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Test log entries required for repairs needed to complete test.
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' Acceptance criteria specified.
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Data acquisition. requirements specified.
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. Data analysis technique specified.
Met' hod of depressurization specified.
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The-inspector observed portions of the test preparations including
. alignment of valves, instrumentation distribution and the general inspection of the containment' interior.
Based on observations of instrumentation locations-during the containment tour, the N,RC inspector
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requested the calculational basis for the volumetric distribution of the-Tresistaace temperature detectors located above the refueling floor.
The method for volume fraction redistribution in the event of a detector
~ failure was'also requested.. Justification for -locating all detectors
.above the refueling floor within 180 degrees of. arc was s'ubsequently
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- provided.. Temperature area surveys prior to pressurization and ta yn at each end 'and;at midpoint of the polar crane as well as at each detector
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location along the 180 degree arc indicated a homogeneous atmosphere.
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-Reevaluation of volume. fraction values'resulting from a potential detector
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failure was. found to be based on-information from the volume fraction
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calculation, the. temperature survey and air' communication paths associated l
with the failed' detector and surrounding areas.
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The-instrument calibration ~ certification traceable to the U. S. Bureau of Standards for the resistance temperature detectors, humidity measuring
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devices, pressure gauges,'and the flowmeter used in the verification. test i
.were reviewed.
The guideline's of ANSI /ANS-56.8-1981,' were used'to select
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The formula from'th'e Instrumentation
' Selection Guide (ISG) was used during the ILRT to ensure that the data-
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acquisition system accuracy was sufficient to provide reliable test
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results.. This formula utilizes'the systematic error of each sensor to
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determine'an'overall value for the data acquisition system.
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instrumentation system for the ILRT was based on a computer controlled data acquisition system capable of reading all sensors _ rapidly, storing.
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the'information and then outputting to the. computer for conversions and-
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calculation of the data.
An add'itional component of test methodology inspected involved the.
verification.of valve' positions.
During the pressurization phase, three
valves (Nos; IA-15, SA-45, and N -1021) were-found tagged and. positioned
in opposition ~ to the signed. procedural valve lineup control room test log.
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-The valve lineup discrepancies rcsulted from a failure to modify the test-
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log sign off after.requ' ired valve realignments resulting from prerequisite.
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' local leak rate retests.
The difficulty in. establishing a controlled priority for tagging represents a. failure to -follow-the test procedure and therefore constitutes a violation of 10 CFR Part 50, Appendix B,.
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Cri terion ~ V - (50-313/8436-01).
Due to the' valve lineup discrepancies identified during the first hour.of pressurization, all test activities.
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additional l discrepancies were identified. AP&L revised the ILRT procedure
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by adding a. hold card temporary lift form to ensure that any valve.
position and accompanying valve position tag' changes are documented in the'
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control room log sheets.
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- After correct valve lineups were achieved, the ILRT pressurization was
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-restarted.
The NRC re'sident inspector monitored subsequent ILRT
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Jactivities.
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raw'. data and computed the leakage rate'in accordance with the Mass Point
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Data! Analysis technique. The computations performed were compared with p-c
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Lthe license'e's 'results for the purpose of verifying the calculational:
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procedure-and confirming the.results.
This analytical technique confirmed
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.providing the.as-found and as-left values.for the type B and C tests were-the' acceptability of the results obtained by the licensee.
The data
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also reviewed.
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Exit Interview
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TheNRC[inspectormetwithlicenseerepresentativesattheconclusionof
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the inspection. :The NRC inspector summarized the. scope and findings of*
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