IR 05000313/1981031
| ML20039A023 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/27/1981 |
| From: | Randy Hall, Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039A020 | List: |
| References | |
| 50-313-81-31, 50-368-81-30, NUDOCS 8112160150 | |
| Download: ML20039A023 (6) | |
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-APPENDIX
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U.5i NUCLEAR REGULATORY COMMISSION
' REGION IV
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Report:
50-313/81-31
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. Licenses:
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Dockets:
50-313-50-368
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Licensee: Arkansas Power and Light Company Post Office Box 551.-
Little Rock, Arkansas 72203-Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection at:.ANO Site, Russellville, Arkansas Inspection Conducted:
November 2-6, 1981
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Inspector:
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P d6n, Re&ctor Inspector, Systems and Technical Date Approved:
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R. E. Ha'11, CKief, Systems and Technical Section D&te/
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Inspection Summary:
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Inspection Conducted on November 2-6, 1981 (Report 50-313/81-31; 50-368/81-34)
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Areas Inspected:
Routine, unannounced inspection of design change and cali-
bration programs.
The inspection involved 34 inspector-hours by one NRC
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inspector.
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Results:
Within the two areas inspected, no violations'or deviations were -
identified.
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DETAILS-
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1.
Persons Contacted
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. B. Austin, Assistant. Of fice ' Services Supervisor
- B. Baker, Operations Manager J. Benham, I&C Sepervisor C. Cole, Planning and Scheduling Supervisor
- L.:Duggar, Special Projects Manager
'*E. Ewing, Plant Engineering Superintenden'.
L. W. Humphrey, Plant Administrative-Manager P. Jones,.I&C Superintendent
- J. Levine, Engineering and Technical Services Manager
- R. Roderick, Human Resources Supervisor
- E. Saunders, Maintenance Manager
- L. Schempp, Manager Nuclear Quality Control M. Stroud, Engineer R. West, I&C Supervisor The NRC inspector also contacted other plant personne1~ including adminis-trative, clerical, engineering, and maintenance personnel.
- Denotes presence at the exit interview conducted November 6, 1981.
2.
Design Changes The purpose of this area of the inspection ~was to assure that the-licensee met Technical Specifications (Section 6) and 10 CFR 50.59 regarding design changes and modifications.
The~NRC inspector reviewed the licensee's design change records for the past year and procedural controls.
Signifi-cant findings and observations are in.the following paragraphs.
a.
Safety Evaluations The licensee had completed a safety evaluation for each design change.
The NRC inspector noted that the basis recorded for some of these evaluations appeared to be weak.
The NRC inspector noted that the licensee has also recently identified this as a problem.
A licensee memorandum, serial ANO-81-8666, dated October 10, 1981, specifically stated the need for a more complete written basis in design change safety evaluations.
Memorandum, serial SRC-81-62 of October 26, 1981, provided guidance on safety evaluations to Safety Review Committee members, Plant Review Committee members, and alternates for both committees. This is considered to be an unresolved item pending implementation of licensee action to improve the recording of basis of design change safety evaluations. (50-313/8131-01; 50-368/8130-01)
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b.
Design Change Backlog and Tracking The NRC inspector found that the licensee's tracking of design change packages was by three partially overlapping systems and seemed to have little management visibility.
The NRC inspector noted that at the site there were three different systems for tracking design changes, not counting the tracking of requests for engineering assistance, many of which would become design changes.
There was a computer printout that tracked design changes from the point which they were released to Planning and Scheduling for accomplishment until the implementing job order was complete.
The NRC inspector also found that Plant Engineering maintained a handwritten log to track design changes through the closecut phase.
There was also a handwritten log maintained by Document Control.
This latter log tracked design changes from the Plant Engineer's initial review through final close out.
The Document Control log provided the most complete record, but it appeared to have the least management visibility.
The backlog of open design changes was approximately 300 based on review of the Document Control logs.
This backlog was divided approximately evenly between the two units.
At the time of the inspection, there was a team of four contract personnel on site to assist in expediting the closecut of design changes.
From a sample of eight design changes, all of which the licensee had reported as (installation) completed in 1980, four were still not closed out (i.e., drawings updated, proce-dures updated, etc.).
In one case, design change 80-1042, the NRC inspector found that all installation work had been completed in May 1980, but that all of the affected drawings had yet to be marked up and forwarded to drafting.
The problem with drawing update has previously been identified in Inspection Report 50-313/8110 and 50-368/8110.
Licensee representatives stated that they had or were taking the following actions to resolve the problems with design change backlog and drawing update in addition to the four contract personnel now working on design change closecut:
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All draftsmen had been transferred organizationally to Plant Engineering and would be moved to the site as soon as suitable work areas are prepared.
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Document Control personnel had been transferred organizationally to Plant Engineering.
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Two new on-site engineering positions and one new document control billet have been added to Plant Engineering, though not yet filled.
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A new facility for plant engineering, drafting and document controlisbeingmadebyconversionofawarehguseonsite.
This facility,.which has approximately 7000 ft of floor space, was expected to be ready for use about December 1, 1981, according to licensee representatives.
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c.
Identification of Test Requirements The NRC inspector noted that licensee identification of test requirements for accomplishment in conjunction with the completion of a design change was not identified in a uniform manner.
There was no specific case found in which the NRC inspector believed that the licensee had not conducted post-installation testing appropriate to the change made.
These tests, however, were often only found in the records in the form of test results.
The NRC inspector expressed concern that the licensee was not more specific in the records main-tained of identifying retest requirements as a part of the design change package.
d.
Identification of Procedure Changes Records of design changes indicated that various departments had, as the result of a design change, updated affected procedures.
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"affected procedures" were often not identifiea.
The NRC inspector expressed concern that the licensee was not identifying required procedural changes as a part of design change development and approval.
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e.
Licensee Procedures The NRC inspector reviewed licensee Procedure 1000.13, Rev. 5 (10/15/81), " Control of Station Modifications." The NRC inspector found that this procedure did not provide for a uniform system of tracking design changes that provided management visibility as discussed in paragraph 2.b.
Procedure 1000.13 assigns the responsi-bility for " details of post-installation checkout" of design changes to plant engineering. However, as discussed in paragraph 2.c, it did not require a specific format for these test requirements.
The NRC inspector also noted that Procedure 1000.13 assigned the Operations Superintendent _ responsibility to " revise operations procedures to incorporate design changes" but did not, for example, assign a similar responsibility to the maintenance department for procedures unt'er their cognizance.
The NRC inspector concluded that the licensee's procedure was weak in these areas.
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Summary The NRC inspector found that the-licensee had problems with the control and closeout of design changes, but that the licensee had identified the most pressing problems and initiated corrective action.
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No violations or deviations were identified.
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3.
Calibration
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-The purpose of the inspection was to assure that the. calibration of components and equipment ' associated with-safety-related functions:was-accomplished as required (by Technical. Specifications.
The scope of-this inspection was limited to'the licensee programmatic controls for calibration and to Unit 2 calibrations.
Unit 1 calibrations will be covered during a subsequent inspection.
The NRC inspector reviewed the following licensee procedures concerned
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'with the control measuring and test equipment:
1000.14, Rev. 3 (11/4/81), " Control of M&TE and Standards"~
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1033.09, Rev. 0 (10/28/81), " Storage, Issue, and Return of Measuring ~
and Test Equipment (M&TE)"
1035.06, Rev. 0 (11/4/81),'"AN0 Master M&TE List" Licensee representatives stated that the revision and issue of instructions to control measuring and' test equipment would be complete-when procedure 1035.05 was issued.
The procedure was under preparation at the time of
'the inspection.
The NRC inspector found that the licensee listed all measuring and test equipment by computer printout.
This printout provided information to identify each piece of equipment (e.g., 'model, type, 'and.identificat_ ion and serial number), storage location, range, tolerance, and calibration interval.
The:NRC inspector traced five instruments, ' identified as having been used in completed calibration through certification of instrument calibration to National Standards.
No discrepancies were noted.
The NRC inspector checked 20 randomly selected calibration procedures for frequency of calibration in-accordance with Technical' Specification i
requirements.
For the sample checked, all had been done at the designated frequency.
The completed records of nine_ specific cslibrations were also examined.
All of these nine calibrations were found to have been completed and _ reviewed.' Test equipment used was identified as were the individual or individuals who performed the calibration.
Review of completed'cali-brations was found to have been done by the first line supervisor in each case.
Technical adequacy of each of these calibration procedures was-considered satisfactory by the'NRC inspector.
The NRC inspector verified through training records that two_ individuals, who between them had per-formed six of the calibrations reviewed in detail, were qualified by-licensee-_on-the-job training records to perform these calibrations.
The NRC inspector found'that the licensee had identified some process.
instrumentation which supported technical specification requirements; but for which;no' calibration procedure existed.
The NRC inspector was
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shown " action tasking" sheets assigning preparation of appropriate
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procedures.
Pending preparation of these calibration procedures,' the requirement to calibrate this supporting " process" instrumentation had-been identified to Planning;and Scheduling so that job orders could be
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issued at the appropriateifrequency to calibrate these instruments.
The.NRC inspector had no other' questions concerning Unit-2 calibration.
No violations or deviations were identified.
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4.
Unresolved Item
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An unresolved' item is a matter about which more informition is required in order to ascertain whether it is an acceptable item, a violation, or a deviation.~ One unresolved item is discussed in paragraph 2 of this report.
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-Item No.
Description 50-313/8131-01; 50-368/8130-01 Basis 'iri Safety Evaluations 5.
Exit Interview An exit interview was conducted November 6, 1981, with those personnel denoted in paragraph 1 of this report.
At this exit interview, the:
NRC inspector summarized the scope and. findings of his inspection.
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