IR 05000313/1984036

Insp Rept 50-313/84-36 on 841213-15 & 850328-30.Violation Noted:Failure to Follow Procedures Re Containment Integrated Leakage Rate Test

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: IR 05000313/1984036 ML20137X742 ML20137X764
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 * $$ YAs/ // ////V5 h

J. I. Tapia, Reactor Inspsetor, Engineering and Operations-Section Dath

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Approved: -

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R. E.cIreland, Chief, Engineering and Date '

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Operations Sections 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

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leakage rate test. The. inspection involved 26 inspector-hours onsite and 25

.in-office inspector-hours by one NRC inspecto Results: Within the areas inspected, one violation (failure to follow procedures) and no deviations.were identifie f$f DY Y G

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DETAILS-

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. ' Persons Contacted Arkansas Power and Light Company (AP&L)

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~D.IN. Bennett, ILRT Director

.c N..Shively, Plant Engineer

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4 - _L.;J. Dugger, Instrumentation and Control Superintendent

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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 -

c l]f r J. M. Levine, General Manager:

7t- ~ . , 10. B. Lomax, Licensing Supervisor

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iBechtelEngineeringCorporation

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M. Burgess,.ILRT' Engineer

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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 ,

Reactors," and in the Plant Technical Specification 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:

Containment interior and exterior inspection requirements specifie ~

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L Instrument locations justified by area surveys.

4 ' Instrument calibiation requirements specifie _ Instrument : loss / test abort criteria delineate ,

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f ~ Instrument error analysis : performe ~

f.- ' Type B and-C test. result's correction to' Type A test results

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specified, ' Venting of internal isolated volumes require ~ Isdlation valve closing mode specified to be the normal mod . Proper postaccident system alignment.to prevent creation of

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artificial leakage barriers specifie .- Quality control hold points specifie l Test log entries required for repairs needed to complete tes ' ' Acceptance criteria specifie _

. Data acquisition. requirements specifie '

' . Data analysis technique specifie Met' hod of depressurization specifie The-inspector observed portions of the test preparations including

. alignment of valves, instrumentation distribution and the general inspection of the containment' interio Based on observations of

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instrumentation locations-during the containment tour, the N,RC inspector 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

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.above the refueling floor within 180 degrees of. arc was s'ubsequently

provided. . Temperature area surveys prior to pressurization and ta yn at

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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 atmospher <

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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 calculation, the. temperature survey and air' communication paths associated l 3 with the failed' detector and surrounding area '

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The-instrument calibration ~ certification traceable to the U. S. Bureau of

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Standards for the resistance temperature detectors, humidity measuring devices, pressure gauges,'and the flowmeter used in the verification. test i .were reviewe , The guideline's of ANSI /ANS-56.8-1981,' were used'to select

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the instruments for the ILRT. The formula from'th'e Instrumentation

7 ' Selection Guide (ISG) was used during the ILRT to ensure that the data- ,

acquisition system accuracy was sufficient to provide reliable test

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results. . This formula utilizes'the systematic error of each sensor to

determine'an'overall value for the data acquisition system. The instrumentation system for the ILRT was based on a computer controlled

.. data acquisition system capable of reading all sensors _ rapidly, storin the'information and then outputting to the. computer for conversions and-

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calculation of the dat An add'itional component of test methodology inspected involved th

verification.of valve' position During the pressurization phase, three valves (Nos; IA-15, SA-45, and N 2-1021) were-found tagged and. positioned

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in opposition ~ to the signed. procedural valve lineup control room test lo 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 prerequisit , ' 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,. ,

'. 4 Cri terion ~ V - (50-313/8436-01). Due to the' valve lineup discrepancies identified during the first hour.of pressurization, all test activitie ~ were halted and a reverification of valve positions was initiated. No 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 sheet After correct valve lineups were achieved, the ILRT pressurization was

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-restarted. The NRC re'sident inspector monitored subsequent ILRT '

,n 4 \-y Jactivitie *

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. Subsequent .to the performance of: the test, the NRC inspector obt'ained the 1 ~ *

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raw'. data and computed the leakage rate'in accordance with the Mass Point .

p- c Data! Analysis technique. The computations performed were compared with

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Lthe license'e's 'results for the purpose of verifying the calculational:

?. " , procedure-and confirming the.result This analytical technique confirmed

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the' acceptability of the results obtained by the licensee. The data -

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.providing the.as-found and as-left values.for the type B and C tests were-also reviewe ~

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5 Exit Interview

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TheNRC[inspectormetwithlicenseerepresentativesattheconclusionof the inspection. :The NRC inspector summarized the. scope and findings of*

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the inspectio l

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